Question: groundwater withdrawals in regulatory filings

Groundwater withdrawals are expressed in million gallons per day (mgd).

Surface water withdrawals for Jefferson County amounted to 0.08 million gallons per day.


Question: NRC Commission Meeting Schedule

The schedule for Commission meetings is subject to change on short notice. The NRC Commission Meeting Schedule can be found on the Internet at: https://www.nrc.gov/public-involve/public-meetings/schedule.html.

The NRC provides reasonable accommodation to individuals with disabilities where appropriate.


Question: What is the intended function of supports for raceways and other components?

Supports for Raceways, Cable Trays, Conduit, HVAC Ducts, Tube Track, Instrument Tubing, Non-ASME Piping and Components (Support members; welded connections; support anchorage to building structure) are designated as Structural Support.

Loss of Material is an aging effect requiring management for structural support components in air environments.


Question: The critical heat flux correlation is vital for safety assessments regarding reactor operation.

The COBRA-FLX code employs the ORFEO-HMP critical heat flux correlation to enhance the predictability of thermal-hydraulic behavior in nuclear reactors.

The test assembly conditions for HTP grid tests are documented in Table B-2, detailing various parameters used during experimental setups.


Question: inorganic radiochemistry parameters

These samples were analyzed for inorganic, radiochemistry parameters. The individual methods are referenced on both the ACZ invoice and the analytical reports.

All analyses were performed within EPA recommended holding times.


Question: The integrity of the tubesheet is critical during various plant operations, including normal and upset conditions.

The Tubesheet to Stub Barrel Junction, which is a critical component of the steam generator, has a maximum fatigue usage of 0.06 under normal, upset, and test conditions.

The channels are designed to manage the flow of coolant and facilitate efficient heat exchange during reactor operation.


Question: What are the corrective actions in response to an incident in a nuclear facility?

A safety standdown was conducted with Fuel Manufacturing Operations (FMO) operation and maintenance teams.

The pallet jack was verified to be operating correctly.


Question: The NRC oversees the licensing processes for nuclear facilities to ensure safety and compliance.

The process of obtaining a nuclear license from the NRC involves multiple regulatory requirements that ensure the safety and functionality of nuclear operations.

The report highlights various groundwater sampling methodologies utilized in environmental assessments.


Question: What is DNBR in nuclear safety analysis?

The transient for the streamline break presented in subsection 15.1.5 bounds the return to power following reactor trip and steamline isolation. The DNBR is always greater than the limit value.

Additionally, no system overpressurization will occur; thus, all applicable safety criteria are met.


Question: The NRC mandates that licensees document the methods used for analyzing environmental samples, particularly for radioactive materials.

The following Analytical Methods were performed: EPA 905.0 Modified/DOE RP501 Rev. 1 Modified.

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).


Question: The NRC expects licensees to conduct routine inspections to ensure the integrity of safety systems.

The regulatory framework mandates that all nuclear facilities implement and maintain safety-related systems to ensure operational safety and compliance with established performance criteria.

The weather patterns in the region have shown an increase in temperature variations over the past decade, impacting local flora and fauna.


Question: The analysis of loss of cooling for Reactor Coolant Pump seals is essential for safety assessments in nuclear facilities.

Model for Failure of RCP Seals Given Loss of Seal Cooling in CE NSSS Plants, Revision 0, March 2007.

EPRI Knowledge Base Article 2021/001, "How to Retain HFE Combinations Numbers/Names Between HRA Dependency Updates"


Question: What are the additional qualification testing requirements for the Tricon platform?

In Section 3.7.1.1.1 of the LAR, it states, in part, that after approval by the NRC of the Tricon platform in the SER, additional qualification testing and analysis has been performed on the Tricon as documented in Invensys/Triconex Topical Report Document No. 7286-545-1 Revision 4.3 which was included as Attachment 7.9 to this LAR.

Table 2-2 of Attachment 7.9 shows summary of exceptions to EPRI TR-107330 Requirements. However, the NRC staff did not locate an explanation, clarification, or analysis in the LAR that determined whether those exceptions are acceptable for the specific on-site conditions.


Question: What is the importance of the Chemical and Volume Control System in aging management evaluations?

Chemical and Volume Control System – Summary of Aging Management Evaluation is critical as it outlines how the aging effects such as cracking and loss of material are managed in piping components, specifically for Class 1 Piping.

The NRC License Renewal Application also includes detailed evaluations of seismic risks and the necessary upgrades to infrastructure to ensure safety during extreme events.


Question: The NRC has scheduled a virtual meeting to discuss the potential impacts of construction on historical properties.

Based on the above consultation with 36 CFR 800.5, the NRC has made a finding of Adverse Effect for this undertaking.

Construction of Kemmerer Power Station Unit 1 will have an adverse effect on 48LN740 because this area will be graded, disturbed, and modified for the construction of a parking lot and other associated structures.


Question: What is the significance of wind direction and speed in nuclear reactor safety assessments?

PERCENTAGE FREQUENCY OF WIND DIRECTION AND SPEED (MPH) DURING NOVEMBER, GGNS SITE

Data from Site Meteorological Tower, 2001 – 2003 (Reference 2).


Question: The configuration of the test tank included features to ensure proper flow dynamics and prevent sedimentation.

The test tank had a rectangular geometry, as shown in Figure 3.n.1-2 below. Debris was introduced in the high-agitation region located at the upstream end of the test tank. This region was equipped with two hydraulic mixing lines to create adequate turbulence and prevent the debris from settling.

Licensees are required to submit a discussion of safety features to ensure compliance with regulatory standards.


Question: What is the role of the gaseous waste disposal system in nuclear plants?

The gaseous waste disposal system provides adequate radioactive decay storage time for the waste gases and long-term holdup of those gases when either high-flow letdown is required or adverse meteorological conditions make it desirable to discontinue release of waste gas to environment.

The process vent blowers maintain a slight vacuum in the charcoal filters to prevent leakage from the filter assembly.


Question: What is the purpose of the comparator defeat switch in nuclear reactor operations?

4.1 Placed the COMPARATOR CHANNEL DEFEAT switch in the N42 position.

**3.1** Placed the QUADRANT POWER TILT ALARM LOWER SECTION switch in the PR N42 position.


Question: environmental report for license renewal

As required by 10 CFR 51.41 and 10 CFR 51.60, applicants must prepare an environmental report that includes the information specified in 10 CFR 51.45.

To adequately characterize the proposed action and assess the potential environmental impacts, the NRC staff needs information on which activities at the MEA would occur at what time(s) during the 20-year renewal period, including the potential overlap of the CBP and MEA schedules.


Question: What does LCO 3.0.4.b require in nuclear regulatory filings?

LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering MODE 4, and establishment of risk management actions, if appropriate.

First part is correct. Second part is incorrect. Plausible that RHR may not be used because of the alignment necessary for decay heat removal.


Question: The evaluation of new seismic hazard information is crucial for assessing the licensing basis of nuclear power plants.

The NRC has long taken the position that its safety assessment of seismic hazards for existing nuclear power plants is a “separate and distinct” process from license renewal.

The NRC publishes a draft version of the SEIS for public comment.


Question: gamma spectrum analysis

Gamma spectrum analysis involves evaluating the energy levels and intensities of gamma rays emitted by radioactive substances to determine the composition and concentration of isotopes in a sample.

The sample taken on 5/19/2019 weighed 8.805E+02 grams and was analyzed using a 500 ml Marinelli geometry.


Question: The NRC has instituted guidelines to ensure that materials used in reactor vessels meet specified mechanical properties, such as impact energy requirements.

The use of severely sensitized stainless steel as a pressure boundary material has been prohibited and has been eliminated by either a select choice of material or by programming the method of assembly.

The threads of the control rod drive mechanism adaptor as well as the surfaces of the guide studs are chrome plated to prevent possible galling of the mated parts.


Question: What is the purpose of RAIs in the regulatory process?

If the NRC staff identifies information during the audit that is needed to support its regulatory decision, the staff will issue RAIs to the licensee.

The audit will be held on April 11, 2023. If requested, the audit team will conduct a telephone conference with the licensee for the purposes of introducing the team, discussing the scope of the audit, and describing the information to be made available on the online portal.


Question: renewal of exemption distribution license

The renewal of the Exempt Distribution License No. 05-35173-01E for Rocky Mountain Instrument Co. is hereby granted for a period of three years from the date of this submittal.

The document outlines various regulatory requirements that all nuclear facilities must comply with to ensure safety and operational efficiency.


Question: To ensure control rod sequences maintain safety during operations, the analyzed rod position sequence is essential during both normal operations and potential emergencies.

The analyzed rod position sequence is developed consistent with the NRC approved Framatome Topical Report ANP-10333P-A, “AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA),” methodology, approved for use in Susquehanna TS 5.6, Administrative Controls.

Accidents are initiated by the malfunction of plant equipment, or the failure of plant structures, systems, or components.


Question: nuclear analyte measurements

The report includes various nuclear analyte measurements such as RUTHENIUM-106 and STRONTIUM-90, along with their respective results and units measured in pCi/L.

Air temperature affects the performance of the systems in the reactor, ensuring optimal operation during varying environmental conditions.


Question: The NRC monitors seismic and flooding risks at all licensed nuclear power facilities indefinitely.

The NRC's assessment of seismic and flood hazards for existing nuclear power plants is a separate and distinct process from license renewal reviews.

The Commission stated that revisions to regulatory requirements would be applicable to nuclear power reactor operators regardless of their license renewal status.


Question: What is the purpose of a probabilistic risk assessment in nuclear regulation?

Probabilistic Risk Assessment (PRA) is a systematic and comprehensive methodology to evaluate risks associated with complex engineered systems including nuclear reactors, primarily in order to inform decision-making processes regarding safety and regulatory compliance.

The Electric Power chapter describes various types of generators and their operational efficiencies, focusing on the integration of renewable energy sources to ensure a stable power supply.


Question: What is the minimum detectable activity for nuclides in this context?

Nuclide MDA (pCi/grams) refers to the minimum detectable activity for a nuclide, indicating the lowest level of activity that can be accurately quantified.

The peak size in counts per second (CPS) is an important measurement that helps in determining the presence and concentration of nuclides.


Question: Reactor Protective System Instrumentation

Four channels of RPS instrumentation shall be operable

One or more EFW Initiation or MSLI Functions with two channels inoperable, place second channel in trip within 1 hour


Question: bias term calculation in nuclear safety

**Bias Terms** includes the bias portion of \(A_LT\), \(C_L\), \(D_L\), \(P_MA\), \(PEA\), \(IRA\), and any other unique terms known to exist.

The process variable decreases towards trip for HPCI-FIS-78 (Sw. 1). From Reference 6, for: - process variables which increase to trip, NTSP1 = Limiting Setpoint - SM


Question: What actions are required to control the reactor pressure vessel water level during operations?

Control RPV water level between 180 and 220” using any of the following methods:

Further actions in AOP-4 may be performed if time permits, but will likely be delayed beyond the end of the scenario due to other complications.


Question: The NRC emphasizes the management of aging effects in systems exposed to raw water...

Consistent with NUREG-2191. The Open-Cycle Cooling Water System (B.2.1.11) program will be used to manage flow blockage and loss of material due to pitting, crevice corrosion, and microbiologically influenced corrosion (MIC).

Consistent with NUREG-2191. The Open-Cycle Cooling Water System (B.2.1.11) program will be used to manage reduction of heat transfer due to cracking in titanium heat exchanger tubes.


Question: What is the purpose of an Exercise Evaluation for nuclear plants?

Exercise Evaluation - Biennial - Not Applicable - completion not required during this inspection cycle.

The NRC requires licensees to maintain safety protocols during regular operations to prevent accidents.


Question: adverse effect finding

Based on the above coordination with 36 CFR 800.5, the NRC has made a finding of Adverse Effect for this undertaking.

Construction of the transmission and water supply lines will have an adverse effect on 48LN8940 because this area will be graded, disturbed, and modified for the construction and installation of these utilities.


Question: nuclear regulatory compliance

The examination procedures are designed to ensure that the applicants comply with the regulatory rules and procedures required by the Nuclear Regulatory Commission (NRC).

Every facility has its unique competencies based on operational needs and conditions experienced during testing.


Question: What is a cation-anion balance in water quality analysis?

Cation-Anion Balance | Calculation | | | | | | | | | |


Question: water quality monitoring in nuclear plants

Table 3.4-6. Dakota Sandstone Aquifer Water Quality in the Unit 1 Project Area displays various constituents, their measured units, means, minimums, and maximums in the context of regulatory filings.

The unit of measurement for calcium in this context is mg/L, a standard measurement used for assessing water quality.


Question: What happens when there is a loss of signal to the scoop tube positioner?

A loss of signal (< 1 mA) to the scoop tube positioner causes a scoop tube lock up.

The NRC requires licensees to conduct regular safety inspections and maintenance on all safety-related systems.


Question: The NRC mandates that licensees develop programs to examine the integrity of various piping and ducting components.

AMP XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"

There are no fiberglass piping, piping components, or ducting, ducting components exposed to air in Auxiliary Systems.


Question: nuclear licensing process

The nuclear licensing process involves multiple steps, including the submission of safety analysis reports, environmental impact assessments, and compliance with federal and state regulations to ensure the safe operation of nuclear facilities.

The economic models used for energy forecasting provide insights into potential trends in electricity demand and generation, impacting market strategies for various energy sources.


Question: What are the requirements for supplemental inspections in nuclear facilities?

There were no significant events in CY 2020, and there were no supplemental inspections.

These metrics were related to significant events and timeliness of supplemental inspections.


Question: The NOAA tidal gage provides measurements that include Mean High Water and Mean Lower-Low Water levels.

MHHW       | 2.9   | Mean Higher-High Water

Values calculated from monthly MHHW and MLLW values from 1987-2008


Question: What is the definition of Probable Maximum Tsunami Flooding in nuclear safety assessments?

Probable Maximum Tsunami Flooding (PMTF) is defined as the maximum possible tsunami flood level that could occur based on historical records, meteorological conditions, and oceanographic data, specifically evaluated for the VEGP 3 & 4 regions within the UFSAR Section 2.4.6.

The section discusses various climate-related phenomena that can impact nuclear facility safety, including rainfall and temperature extremes which are crucial for the evaluation of structural integrity under expected operational conditions.


Question: The approval process for using advanced materials like lead test assemblies is crucial for ensuring reactor safety.

The use of lead test assemblies is a critical aspect of the evaluation process for integrating accident-tolerant fuel in nuclear reactors.

Efforts to enhance public safety include ongoing inspections and monitoring of operational protocols.


Question: BWR 89-Assembly Basket

Figure B2-4 Schematic of BWR 89-Assembly Basket illustrates the configuration and arrangement of the assemblies used in a Boiling Water Reactor (BWR).

The regulatory framework surrounding nuclear power plants requires that operators maintain a high level of safety and minimize the risk of accidents.


Question: What is the role of the Thermal Barrier Booster Pumps in nuclear safety?

Task Standard: Thermal Barrier Booster Pump 1B is started, Thermal Barrier Booster Pump 1A is stopped, and both hand switches are returned to P-AUTO IAW 0-SOI-70.01, Section 8.7

Evaluation Method: Simulator  X  In-Plant  __________  Classroom  __________


Question: nuclear licensing process

The nuclear licensing process involves a series of regulatory approvals that must be obtained before a nuclear facility can be constructed and operated, ensuring compliance with safety standards and public health protection.

The updates for hardcopy manuals will be distributed within 3 days in accordance with department procedures.


Question: What is the purpose of outdoor water storage tank foundations in nuclear plants?

The outdoor water storage tank foundations and encasements support and protect the RWST, the CST, and the FWST and transfer tank.

The nuclear facility utilizes various safety systems to ensure the protection and monitoring of reactor operations.


Question: Strontium-90 detection limit

RL: Reporting Limit for Sr90 is listed as 0.0913 pCi/g, which indicates the minimum concentration of Strontium-90 that can be reliably reported.

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).


Question: isotope activity measurement

**Manufacturer Name**: OHMART/VEGA CORPORATION
**Device Model (Not Source Model)**: SHLD-1
**Device Serial Number**: 59903G
**Transfer Date**: 04/10/2018


Question: The NRC is analyzing the licensing process for micro-reactors, focusing on their deployment and operational testing.

Micro-reactor licensing and deployment considerations include the assessment of fuel loading and operational testing at a factory.

The response sheet includes various voting options such as Approved, Disapproved, and Abstain, indicating the decision-making process.


Question: The NRC mandates that licensees perform evaluations on emergency core cooling systems to ensure their reliability.

Core Spray lines are a critical component of the emergency core cooling systems that provide essential cooling to the reactor during loss of coolant accidents.

The nominal pipe diameter specified for the core spray system is consistently 12 inches across all relevant evaluations.


Question: The aging management program for structural support includes evaluation of cumulative fatigue damage in carbon steel components.

PZR Support Skirt is evaluated for Cracking and Cumulative Fatigue Damage under the Time-Limited Aging Analysis Evaluated for the Period of Extended Operation.

The Unit 1 pressurizer locations are composed of stainless steel and the Unit 2 pressurizer locations are mitigated by installation of an Alloy 690 full structural overlay.


Question: Critical Heat Flux correlation

The COBRA-FLX code uses the ORFEO-HMP correlation for predicting critical heat flux in an upward flow through axial geometries.

Figure A-57 illustrates the axial geometry of the CHF test setups SP590, SP591, and SP592 without specific reference to the correlation used.


Question: nuclear safety regulations

The regulatory framework for nuclear safety requires comprehensive safety assessments and licensing procedures to ensure the plant operates within safety limits and adequately protects public health and the environment.

The demographic trends indicated that the population growth in the residential sectors shows a steady increase over the years, particularly higher in the 0-2 km radius.


Question: The construction of the SMR at Oconee Station would only require a small amount of land because it uses existing infrastructure.

Approximately 36 ac (15 ha) of land on the Oconee Station site would be required to construct the SMR on land already zoned for industrial use.

Temporary visual impacts may occur during construction because of the use of cranes and other construction equipment.


Question: nuclear licensing process

The NRC conducts a thorough review of applications for nuclear licenses, considering safety, environmental, and regulatory compliance before granting approval.

The attorney representing Crow Butte Resources, Inc. is Anne R. Leidich, who practices law in the District of Columbia and Maryland.


Question: nuclear fuel cost projections

Recent experiences have proven that the 1970 National Power Surveys' projection that fossil fuel prices would increase at a greater rate than nuclear fuel prices is basically sound.

The best geothermal site for use at this time as a power source for the area would have the characteristics of the only site known to be exploitable in this country as a power source; i.e., the characteristics of the dry field, granitic-stock type with a capacity comparable to that of The Geysers.


Question: nuclear licensing and regulatory processes

Nuclear licensing is a regulatory process that ensures the safe use of nuclear materials and facilities, involving thorough assessments and compliance with safety standards set by authorities.

The Chelonia mydas species observed during the survey was found in varying locations across different measurement tags, with a noted variation in size from 26.5 to 77.7 centimeters, indicating a range of sizes in the population.


Question: What is the significance of energy measurements in nuclear safety assessments?

Energy (keV) is a crucial measurement used in nuclear safety assessments, indicating the energy levels associated with radioactive emissions.

The original area of a detected peak is essential for understanding the overall counts associated with a specific energy level.


Question: What is the significance of the Illinois Basin in relation to the Dresden Nuclear Power Station?

DNPS is on the northeast flank of the Illinois Basin. The north-northwest striking LaSalle anticlinal belt, a major structural element within the Illinois Basin, lies a few miles west of DNPS.

Coal has been mined in 76 counties in Illinois. More than 7,400 coal mines have operated since commercial mining began in Illinois circa 1810.


Question: The goal is to ensure that the system valves and RHR pumps respond correctly to simulated safety signals during testing.

To demonstrate operation of the residual heat removal (RHR) pumps and system valves and their associated control and interlock circuitry, including response to simulated safety signals.

Test data are recorded for future alignment purposes only, and specific acceptance criteria are not provided.


Question: What is the importance of nuclide identification in nuclear regulatory processes?

Nuclide identification reports detail the elemental composition and specific isotopes present, which are crucial for understanding radiation safety and compliance with regulatory standards.

The energy tolerance for measurements in nuclear experiments is set at 1.000 keV to ensure accuracy and reliability of the collected data.


Question: Licensees must ensure that their licensing documents contain accurate and current information as per NRC guidelines.

The NRC published a Final Rule requiring all licensed reactors to periodically update their Final Safety Analysis Reports.

The Rule became effective July 22, 1980, and established the following basic requirements for VEPCO’s nuclear power stations:


Question: activity levels in nuclear measurement

The Activity (dpm/100 cm²) column indicates the measured activity levels of radioactive materials in disintegrations per minute per square centimeter, which is crucial for assessing contamination levels and compliance with regulatory standards.

The Gamma Result column shows the detected gamma radiation levels, which are essential for radiation safety assessments but do not provide information on the activity levels.


Question: The NRC assesses whether license amendment applications meet the relevant regulatory requirements before approval.

The amendment would revise Technical Specification 3.6.3, “Containment Isolation Valves,” and Surveillance Requirement 3.6.3.1 to allow use of a blind flange.

The NRC Project Manager for this application is Samson Lee, who can be contacted at 301-415-3168.


Question: plume exposure pathway EPZ

As a result of these comments on the proposed rule, the NRC revised the requirements by listing in § 50.33(g)(2)(i)(A) the major considerations for the radiological consequence analysis to be used in determining the plume exposure pathway EPZ size for the facility: accident likelihood and source term, timing of the accident sequence, and meteorology.

The NRC’s determination of the acceptability of the applicant’s assessment supports the agency’s separate review of the applicant’s emergency plan.


Question: What is the significance of peak analysis in gamma spectrum analysis?

Peak Analysis From Channel  | 100
Peak Analysis To Channel    | 4096

Sample Size                | 1.063E+03 grams
Facility                   | Dairyland_NPP
Sample Taken On            | 5/9/2019 12:45:00 PM
Acquisition Started         | 5/15/2019 8:48:24 AM


Question: What are the acceptance criteria for Alloy X-750 dowel welds in nuclear reactors?

40 – 60 Methods and Conditions: VT-3 visuals for separated or missing locking welds from the dowels or missing dowels. Note 4 in the Item B13 allowed the basis of the guide block welds of Davis Besse to be done by alternate unit-specific basis.

Limited audit only to confirm: (1) whether Davis Besse has the specified guide block weld type, or (2) whether Note 4 was covered and replaced in Rev. 2 by elevating the Alloy X-750 dowel-to-LGA support pad welds at Davis Besse from Expansion to Primary category welds.


Question: What are the effects of a DC Electrical System failure in nuclear power plants?

Given a DC Electrical System failure, predict the effect of the DC Electrical System failure on the following: Emergency Diesel Generators, Components using DC control power.

The NRC requires that all regulated activities are conducted in a manner that maintains the public health and safety.


Question: The NRC mandates that any adjustment to the facility's configuration, as outlined in NEI 06-09-A, should be evaluated for its impact on the Risk-Informed Completion Time (RICT).

For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.

The risk assessment approaches and methods shall be acceptable to the NRC.


Question: The NRC specifies that licensees must document peak analysis and related measurements accurately in their regulatory filings.

Peak Analysis Performed on: 3/27/2019 9:05:22 PM

| Peak No. | ROI start | ROI end | Peak centroid | Energy (keV) | FWHM (keV) | Net Peak Area | Net Area Uncert. | Continuum Counts |


Question: Pressurizer Power Operated Relief Valves

3.4.11 Pressurizer Power Operated Relief Valves (PORVs)


Question: The non-availability of NPSH for the RHR pumps can lead to insufficient net positive suction head during operation.

This head loss includes clean strainer head loss and conventional debris (fiber and particulate) head loss.

The data presented in Tables 3.g.16-1 and 3.g.16-2 illustrate the thermal dynamics and operational parameters for the RHR pumps under various sump temperatures.


Question: nuclide confidence index

Nuclide confidence index threshold = 0.30


Question: nuclear regulatory filings

The submission included comprehensive documentation that complies with NRC regulations, ensuring that all technical specifications, operational data, and safety assessments are thoroughly presented for review.

The meeting was conducted to discuss various administrative topics, including scheduling and resource allocation for future projects.


Question: What are the aging management evaluations for electrical components in nuclear facilities?

The report outlines various components and systems that support the overall safety and operation of a nuclear facility, including important processes for compliance.


Question: What are the vertical limits of excavation for a reactor building?

The PPE shows the bounding condition for reactor building embedment depths as 39 ft (shallowest) to 84.3 ft (deepest). These depths are for the reactor building/nuclear island base mat and are referenced to the external plant grade.

As discussed in Subsection 2.5.4.5.2, the excavation may be performed in two stages, with both stages requiring structural support.


Question: gamma spectrum analysis

The gamma spectrum analysis involves examining the energy levels of gamma radiation emitted from a sample to identify isotopes and quantify their concentrations, typically using a detection system calibrated for specific energy ranges.

The sample size for this analysis is noted as 9.093E+02 grams, which is important for ensuring accurate results in the peak identification process.


Question: NRC Docket No. 71-9294

The NPC Safety Analysis Report submitted under NRC Docket No. 71-9294 provides an evaluation of safety measures and compliance with regulatory requirements for the licensed transportation of nuclear fuel.

The Global Nuclear Fuel company has a range of financial strategies to ensure its market position remains strong and competitive in the energy sector.


Question: What is the significance of a Large Break LOCA in nuclear safety?

Large Break LOCA refers to a loss-of-coolant accident where a substantial rupture occurs in the primary system, leading to a rapid loss of coolant and potentially resulting in core damage.

Flow rates to the components and systems that are serviced by the CCWs; interactions among the components.


Question: defense-in-depth evaluation in nuclear safety

The defense-in-depth philosophy is a fundamental component of the safety approach for nuclear facilities, which includes multiple layers of protection against system failures and external events.

The operational history of Turkey Point includes several milestones and achievements, such as the successful installation of new turbines and upgrades to the cooling systems.


Question: flood inundation map

The FEMA 100-year flood inundation map, which represents flood inundation before construction of the VCS plant, is presented in Figure 2.4.1-7.

Monthly flow data from the Victoria and Goliad stream gages during the three major statewide droughts before September 2007 (1947 to 1948, 1950 to 1957, and 1960 to 1967) are highlighted in Tables 2.4.1-4 and 2.4.1-5.


Question: What are the new emergency preparedness requirements for small modular reactors?

Through this final rule, the NRC is amending its regulations to create an alternative emergency preparedness (EP) framework for small modular reactors (SMRs) and other new technologies (ONTs).

Certain existing requirements and guidance are focused on large light-water reactors (LWRs) and currently operating non-power reactors (also referred to as research and test reactors), as defined in part 50 of title 10 of the Code of Federal Regulations (10 CFR), 'Domestic Licensing of Production and Utilization Facilities.'


Question: differential settlement in seismic isolators

The SIS analysis shall address short-, and long-term effects of differential settlement of the soil and foundation flexibility.

Licensing Basis Events SIS Testing outlines the regulatory requirements for analyzing events that may impact the safety and operation of a nuclear facility.


Question: The proposed system enhancements aim to align with the standards set by Regulatory Guide 1.23, ensuring more accurate meteorological data collection.

The new system is being designed to be fully compliant with Regulatory Guide 1.23.

The existing rain gauge will be retained, but rewired to new electronics.


Question: The process of obtaining a license for nuclear facilities includes extensive safety evaluations by the NRC.

The Nuclear Regulatory Commission (NRC) conducts thorough safety reviews as part of its licensing process to ensure that nuclear facilities operate within acceptable risk limits.

The design of the reactor core is crucial for efficient energy production, and various materials are used to achieve optimal performance.


Question: fire protection program audit frequency

Fire Protection program audit frequency will be evaluated to ensure compliance with safe operating standards.

Remove the review of the internal audit program, conducted every 24 months, from the independent review function.


Question: The components of the Saltwater and Chlorination System are constructed from various materials to ensure durability and effectiveness.

The materials of construction for the Saltwater and Chlorination System components are: Carbon Steel, Carbon Steel (Coated/Lined), Cast Austenitic Stainless Steel, Cast Iron (Gray Cast Iron), Copper Alloy (≤15% Zinc and ≤8% Aluminum), Copper Alloy (>8% Aluminum), Ductile Iron, Elastomer, Fiberglass, Fiberglass Reinforced Plastic, Glass, Nickel Alloys, Polyvinyl Chloride (PVC), Stainless Steel, Titanium.

Aging management programs help monitor different aspects of reactor systems to ensure they remain operational over time.


Question: What factors are considered in nuclear licensing decisions?

The NRC evaluates various aspects such as safety analyses, environmental impacts, and compliance with regulatory requirements in the nuclear licensing process.

Many species of birds migrate south for the winter, seeking warmer climates and abundant food sources.


Question: The NRC reviews and approves the risk categorization process for nuclear power reactors, allowing for flexible treatment methods based on risk assessment.

The provisions of 10 CFR 50.69 allow adjustment of the scope of equipment subject to special treatment controls (e.g., quality assurance, testing, inspection, condition monitoring, assessment, evaluation and resolution of deviations). For equipment determined to be of low safety significance, alternative treatment requirements can be implemented in accordance with this regulation.

The proposed amendment would modify the licensing basis to implement a change to the approved voluntary implementation of the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.69, “Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.”


Question: reactor construction inspection reports

Audit 100% of reactor construction inspection reports issued during the calendar year in relation to the inspection report timeliness requirements in Inspection Manual Chapter (IMC) 0613, “Power Reactor Construction Inspection Reports.”

For inspections not conducted by a resident inspector, inspection completion is normally defined as the day of the final exit meeting.


Question: The aging management of components, such as insulated valve bodies, includes monitoring for cracks and other forms of material loss.

Insulated Valve Body            | Leakage Boundary (spatial) | Copper Alloy (>15% Zinc) | Plant Indoor Air (Ext) | Cracking                        | External Surfaces Monitoring of Mechanical Components (B.2.3.22) | VIII.A.S-402     | 3.4-1, 063  | A     |

Piping Elements                 | Leakage Boundary (spatial) | Glass             | Lubricating Oil (Int) | None                            | VIII.I.SP-10                                            | 3.4-1, 055  | A     |


Question: The highest temperature the cladding must withstand is recorded at the PCT level.

At 50 seconds, the temperature recorded was 2000 °F.


Question: plume exposure pathway emergency planning zone sizing methodology

The Plume Exposure Pathway Emergency Planning Zone Sizing Methodology provides a framework for determining the appropriate size and scope of emergency planning zones based on potential radiological releases from the nuclear facility.

The NRC document outlines the various methods for evaluating the safety of reactor components under normal and accident conditions, emphasizing the importance of maintaining structural integrity and compliance with safety standards.


Question: Risk Informed Completion Time

However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time.

The 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status.


Question: What are deterministic beyond design basis accidents in nuclear regulation?

We've had Chapter 19 where deterministic, beyond design basis accidents have been formed under the best estimate sense. They do contribute specifically in a defense-in-depth context.

No, they wouldn't go away they would be captured by the class of LBEs that are the very unlikely events.


Question: What is meant by atomic energy in the context of nuclear regulations?

"Atomic energy" [means all forms of energy released in the course of nuclear fission or nuclear transformation;] "Atomic energy" as defined by the Atomic Energy Act, as codified in 42 U.S.C. 2014, as may be amended from time to time;

The commissioner shall request the federal government to assume such contractual obligations to the extent provided for by federal law.


Question: What is the impact of xenon-135 on reactor startup?

The applicant is required to have knowledge of the xenon-135 production/decay vs. time after shutdown curve, and the effects of xenon-135 on a reactor startup.

The importance rating of nuclear safety systems is determined by their significance to reactor operation and overall safety performance.


Question: nuclear reactor licensing process

The Plant Licensing Branch III oversees the review of applications for the construction and operation of nuclear reactors, ensuring that all regulatory requirements are met before granting licenses.

If you have any questions, please contact me at (301) 415-2855 or by e-mail at Scott.Wall@nrc.gov.


Question: energy peak analysis in nuclear safety

This report analyzes the safety of reactor operations under various environmental conditions.


Question: cladding temperature at PCT and burst elevations

Cladding Temperature at PCT and Burst Elevations - \(C_D = 0.6\) - High \(T_{avg}\), Min SI, Cosine Power Shape, Non-IFBA

The graph shows the relationship between temperature in degrees Fahrenheit and time in seconds.


Question: temperature validation in nuclear safety evaluations

As described in Section 5.4 of topical report ANP-10323-P (GALILEO), the following is requested: a. Please re-run the temperature validation cases listed in Table 7-3 and 7-4 of the GALILEO Validation Manual using upper bound and lower bound values of ADIFF123.

This RAI was further clarified in May 2019. It was verbally conveyed from Nuclear Regulatory Commission personnel that the purpose of this RAI is to demonstrate bounding analyses for the temperature and strain databases when uncertainties are considered.


Question: What is the purpose of a regulatory audit in nuclear licensing?

The NRC staff determined that a regulatory audit is needed to facilitate the review.

By letter dated June 28, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23180A304), Westinghouse Electric Company (Westinghouse) submitted Topical Report (TR) WCAP-18773-P/NP, Revision 0, "Higher Enrichment for Westinghouse and Combustion Engineering Fuel Designs" (ADAMS Package Accession No. ML23180A303) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval.


Question: Sensitivity studies need to account for variations in initial parameters such as power levels and dilution flow rates.

It is important to note that each use of the phrase “Sensitivity studies are performed as needed…” in TR-0516-49416-P, Revision 4, also existed in the TR-0516-49416-P-A, Revision 3 that was previously reviewed and approved by the NRC.

The methodology described in the report undergoes extensive review processes to ensure compliance with safety standards.


Question: liquid scintillation analysis

Rad Liquid Scintillation Analysis           |           |          |              |       |      |         |

**Company:** LaCrosseSolutions  **Address:** S4601 State Hwy 35  **Contact:** Mr. Jason Q. Spaide  **Client Sample ID:** LI-SUB-CDR-FSGS-008-SB  **Sample ID:** 436341001  **Matrix:** Soil  **Collect Date:** 15-SEP-17 09:05  **Receive Date:** 30-OCT-17  **Collector:** Client


Question: What is the procedure for synchronizing diesel generators to the electrical bus?

The procedure for synchronizing diesel generators (DG) to the bus includes verifying the voltage, frequency, and phase alignment between the DG and the bus before connecting them to ensure safe and reliable operation.

The review and approval process for Job Performance Measures involves multiple steps and requires validation by subject matter experts to ensure compliance with training standards.


Question: The amount of Cerablanket insulation, which is located around the reactor vessel, is not considered to be a source of debris.

Cerablanket insulation is used inside the reactor cavity around the perimeter of the reactor vessel and near the neutron detector wells. As stated in the Response to 3.a.1, reactor cavity breaks are excluded, and Cerablanket is shielded from the breaks outside of the reactor cavity by the primary shield wall. Therefore, Cerablanket is not considered a debris source.

The total amount of concrete assumed to be exposed and submerged in the containment sump pool was 10,000 ft².


Question: What is the function of the Instrument Air System in nuclear plants?

078A3.03: Ability to monitor automatic features of the Instrument Air System, including: Air compressor loading/unloading.

103K3.04: Knowledge of the effect that a loss or malfunction of the Containment System will have on the following systems or system parameters: Shield building vent system.


Question: What is the role of structural bolting in aging management?

Structural bolting is a significant component type classified under structural support, which plays a vital role in maintaining the integrity of structures. It can experience aging effects such as loss of preload due to self-loosening when exposed to various environmental conditions.

Steel components used for shelter and protection also play a critical role in structural support, but they can face different issues such as loss of material due to corrosion.


Question: The steps for properly donning a respirator in a safe environment include adjusting the head straps and centering the face piece.

The following will be performed for full face respirators in a non-contaminated area.

The face piece will be centered on the face, and the wearer will pull both lower (neck) head straps at the same time towards the rear.


Question: What is the function of the TAP-A program in thermal analysis?

The TAP-A program is applicable to both “transient and steady-state heat transfer in multidimensional systems having arbitrary geometric configurations, boundary conditions, initial conditions, and physical properties.

The wall panel model for the crane wall is 48 ft long with 8 axial stations each 6 ft in length.


Question: What are the requirements for radiation protection programs in nuclear facilities?

Nuclear facilities must establish and maintain a radiation protection program that meets the requirements outlined in 10 CFR Part 20, which includes setting appropriate dose limits and ensuring the safety of employees and the public.

The increase in renewable energy sources has shifted the focus of some industries away from fossil fuels, leading to cleaner production methods and reduced emissions.


Question: The petitioner advocates for minimum core reflood rates based on findings from various thermal-hydraulic tests.

In PRM-50-93, Petitioner argues for a new regulation stipulating minimum allowable core reflood rates, in the event of a LOCA, primarily by citing experimental data from the NRU Thermal-Hydraulic Experiment 1 (a total of 28 thermal hydraulic tests conducted with full-length Zircaloy fuel rods, driven by low-level fission heat), NRU Thermal-Hydraulic Experiment 2 (a total of 14 thermal hydraulic tests conducted with full-length Zircaloy fuel rods, driven by low-level fission heat), and NRU Thermal-Hydraulic Experiment 3 (a total of three thermal hydraulic tests conducted with full-length Zircaloy fuel rods, driven by low-level fission heat).

First, in the cover letter of NEI's comments on PRM-50-93, NEI misleadingly states: Results from the second test were discounted by the original experimenters because of instrumentation problems.


Question: What are the safety protocols regarding nuclear reactor licensing?

The licensing of nuclear reactors involves a comprehensive review of safety protocols, which must meet stringent regulatory requirements set forth by the Nuclear Regulatory Commission (NRC) to ensure the protection of public health and the environment.

The history of energy policy in the United States has been shaped by various administrations, including significant addresses by past presidents highlighting national energy goals.


Question: What is gaseous swelling in nuclear fuel?

The gaseous swelling phenomenon is caused by the creation of new porosity consisting of intra- and inter-granular bubbles, created by condensation of irradiation-induced vacancies and filled with gaseous fission products.

The NRC requires licensees to maintain detailed records of all safety-related inspections and assessments conducted throughout the operational phase of the facility.


Question: Students must arrange for their travel and lodging for the NRC Technical Training Center training.

Individuals listed in Enclosure 1 have been accepted for participation in the Licensing Practices and Procedures (G-109) course.

The facility’s telephone number is (423) 855-6500.


Question: How do you calculate Corrected Venturi Reactor Thermal Power?

Calculate Corrected Venturi Reactor Thermal Power (RTPcorr): 98.74, 1.01, 99.73

The venturi meter is a device used for measuring fluid flow by converting the pressure difference into a flow measurement.


Question: What is the allowable flow rate for RHR pumps during Mid-Loop operation?

RHR flow is limited to 2300 gpm while in Mid-Loop operation.

The crew is required to throttle 2A RHR pump flow, because cavitation was caused by excessive RHR flow.


Question: gamma spectrum analysis

The gamma spectrum analysis involves the examination of gamma radiation emitted from a sample, using a detector to measure and analyze the energies of these emissions for identification and quantification of radioactive isotopes.

The peak analysis performed on 5/28/2019 9:29:22 AM involved examining the data from channel 100 to channel 4096 to assess the characteristics of detected peaks.


Question: What is Core Damage Frequency (CDF) in nuclear safety evaluations?

The proposed methodology for identifying candidate risk-significant SSCs for the SMR-300 design adjusts the thresholds for RAW based on the baseline CDF and LRF to ensure that measurable contributors to risk are identified regardless of the risk profile.

In the absence of specific review procedures for evaluating methods for assessing risk significance, the NRC staff identified the following three key areas of review for this TR:


Question: The NRC reviews the socioeconomic impacts related to the construction of power alternatives, including the natural gas option.

Socioeconomic impacts from construction of the natural gas alternative would include those discussed for all replacement power alternatives in Section 3.10.9.1.

Given the number of units (i.e., six) and land requirement for natural gas operations, property taxes could be noticeable given Oconee County’s small property tax base (see Section 3.10.5).


Question: The NRC mandates that air samplers undergo flow calibration at least once per year to ensure accuracy in monitoring airborne radioactive materials.

Portable air samplers are used to survey airborne radioactive material concentrations. Air samplers are calibrated for flow at least annually. Surveys may be performed for radioactive particulate and radioiodine airborne concentrations.

An adequate inventory of protective clothing will be maintained on hand at the access control area or other control points, as necessary to support plant operations and maintenance activities.


Question: The goal of the Deterministic Fracture Mechanics evaluation is to assess how long it may take for a presumed flaw to reach the allowable flaw size outlined in the ASME Code.

The objective of the DFM evaluation is to determine the time it takes for a postulated flaw to grow to the ASME Code allowable flaw size.

The NRC requires licensees to adhere to specific maintenance protocols to ensure operational efficiency.


Question: nitrate action level


Question: The report discusses simulations conducted using COBRA-FLX to assess critical heat flux.

The COBRA-FLX code provides methodologies for predicting the critical heat flux in nuclear reactor conditions.

The data in Table B-3 show the local conditions derived from various experimental setups not associated with heat flux calculations.


Question: The analysis shows the effect of temperature on the Prandtl number for different fluids used in thermal systems.

Figure 12 illustrates the Prandtl Number Matching and Distortions for Flibe at temperatures between 550°C and 750°C, and heat transfer oil at temperatures between 58°C and 118°C.

The table displays various temperatures for heat transfer oil, which play a significant role in thermal management of nuclear reactors.


Question: Each reactor building isolation valve must remain effective during various operational modes.

Each reactor building isolation valve shall be OPERABLE.

Separate Condition entry is allowed for each penetration flow path.


Question: What is K-40 in the context of nuclear safety measurements?

K-40 is a radionuclide with an activity concentration of 1.37E+01 pCi/g Dry and an uncertainty of 1.48E+00, measured in g dry.

The Flag Values indicate whether the measurement is secure, providing assurance of data integrity.


Question: The decay rate of the Isolite material is reported as 7.500.

The decay rate of Isolite is measured in units of Ci (Curies).

The manufacturing date for Isolite units is consistently listed as 5/1/08.


Question: The safety-related systems necessitate physical support, shelter, and protection according to the applicable regulations.

Provides physical support, shelter, and protection for safety-related systems, structures, and components. **10 CFR 54.4(a)(1)**

None of the license renewal boundary drawings included any significant findings or changes.


Question: The analysis of design basis accidents first considers the operational integrity of the systems designed to contain fission products.

A structure, system, or component (SSC) that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Only three US sites continue to operate B&W reactors: ANO-1, Davis Besse, and Oconee.


Question: What is a plume exposure pathway emergency planning zone?

...a scalable approach for determining the size of the plume exposure pathway emergency planning zone...

Those applicants and licensees have the option to develop a performance-based EP program as an alternative to using the existing, deterministic EP requirements in 10 CFR part 50.


Question: What is a nuclide in radiation measurement?

Nuclide MDA (Minimum Detectable Activity) is a critical measurement used in radiation detection to assess the lowest amount of a particular nuclide that can be reliably detected.

The table indicates various nuclides and their respective energy levels and yields, showcasing the complex interactions of radiation with matter.


Question: What is the Certificate of Compliance for nuclear cask systems?

U.S. Nuclear Regulatory Commission, 'Certificate of Compliance No. 9255, Revision 12 for the Model No. NUHOMS®-MP187 Multi-Purpose Cask (Docket 71-9255).'

Proposed SNM-1050, WCS Consolidated Interim Storage Facility Technical Specifications, Amendment 0.


Question: vibration acceptance criteria centrifugal charging pump

Vibration limits are not imposed on the Speed Increaser and Motor by the OM Code. These readings are evaluated for trending purposes only.

Outboard Axial (A-A) measurements are evaluated for trending purposes only to ensure efficient operation and safety.


Question: The license amendment will be reviewed and needs to comply with safety regulations, ensuring public safety is maintained.

In accordance with 10 CFR 50.91, “Notice for public comment; State consultation,” Section (b)(1), a copy of this amendment application, with Attachments, is being provided to the designated Kansas State official.

This letter contains no commitments. If you should have any questions regarding this submittal, please contact me at (620) 364-8831 x8687, or Dustin Hamman at (620) 364-4204.


Question: component cooling water system

The Component Cooling Water System (CCW) serves to remove heat from the components requiring cooling, thereby maintaining the temperature of the reactor and associated systems within safe operational limits.

The Reactor Operator must ensure that all alarms and indications are addressed promptly to maintain operational integrity.


Question: nuclear regulatory compliance

The results for Nickel-63 were reported as -0.478 pCi/g with an uncertainty of +/-1.42, which is important for determining compliance with regulatory standards.

The Analytical Methods carried out included DOE ENV. HALS-300, Am-05-RC Modified and ASTM C 1475-00 Modified, which followed rigorous scientific protocols.


Question: The NRC oversees licensees to ensure compliance with regulatory requirements regarding safety systems.

The submittal includes detailed information concerning the licensing process to ensure the safety of nuclear reactors.

The Municipal Electric Authority of Georgia has multiple enclosures related to operational performance and utility management.


Question: What are reactivity manipulations in nuclear operations?

Reactivity manipulations may be conducted under normal or controlled/abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.

For new reactor facility licenses that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.


Question: The NRC emphasizes the importance of having a comprehensive emergency plan for reactor operations.

The SBK Emergency Plan Annex outlines the procedures and measures required to address potential emergencies that may impact the safety of the nuclear facility.

The document specifies the administrative responsibilities that each department will undertake during the licensing process.


Question: The NRC mandates that licensees must evaluate the occurrence of abnormal events during operation.

1. Total malfunctions (5-8)                                       | 6                |             |


Question: The NRC governs the procedures for analyzing environmental samples to ensure compliance with safety regulations.

**Titration and Ion Analysis**| | | | | | | | | |


Question: effluent monitoring requirements

Table 3.6-2 in Duke Energy's Environmental Report (ER) summarizes applicable effluent (water quality) monitoring requirements under Oconee Station’s NPDES permit, including a description of the main processes that contribute flow to each outfall.

Oconee Station’s significant outfalls are further discussed below.


Question: What is the significance of measuring Radium 226 in groundwater?

The results for Polonium 210, dissolved were measured on 07/22/24 at 8:03 and yielded a value of 3.21 pCi/L.


Question: What are common regulatory questions related to nuclear safety?

The NRC's assessment of licensee performance is designed to ensure compliance with applicable regulations and to effectively address safety issues.

It is important to maintain equipment to ensure that operations run smoothly and that productivity goals are met.


Question: confidentiality provisions in nuclear regulatory filings

The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.

Other reasons identified in Enclosure 4 of SNC letter ND-20-1414 for Vogtle Electric Generating Plant Units 3 and 4, Westinghouse Affidavit CAW-20-5130 (VEGP 3&4- PSI/ISI-ALT-15).


Question: What is the purpose of Defense in Depth and Diversity in nuclear safety?

Defense in Depth and Diversity is a safety philosophy employed in nuclear engineering that involves establishing multiple layers of protection and differing strategies to prevent accidents and mitigate risks.

The Digital Modernization Project aims to improve the operational efficiency of nuclear plants by integrating advanced technologies into existing systems.


Question: What are the limitations for loading patterns in nuclear fuel storage?

Loading Pattern B with heat load in any storage location above 444W (uniform load) requires the following additional limits: a. Assemblies with highest loads must be stored in Zone C. b. Assemblies with lowest heat loads must be stored in Zone A and B, with the lowest overall heat load in the center of Zone A and progressively increasing heat loads in the surrounding rings.

The storage location can include maximum heat load limits of 33,000, 39,500, 42,000, and 42,000.


Question: location of nuclear fuel cell facilities

(1g) location of all nuclear fuel cell facilities located or proposed within 50-mile radius | Figure 2.2-1 | NA | - | -

(1f) nature and extent of projected land use with methodology/sources of information | Sec. 4.1 | NA | p. 4-92 to 4-96 | -


Question: What are the conditions for using Ge-68/Ga-68 generators under NRC regulations?

As requested, you have been authorized to possess and use Ge-68/Ga-68 generators.

Failure to conduct your program in accordance with NRC regulations, license conditions, and representations made in your license application and supplemental correspondence with NRC will result in enforcement action against you.


Question: The minimum detectable activity for nuclides can be critical in assessing safety and regulatory compliance.

Nuclide MDA (pCi/grams) indicates the minimum detectable activity for each nuclide, which is vital for understanding contamination levels and regulatory limits.

Unidentified peaks can sometimes indicate the presence of multiple isotopes within a sample that may complicate analysis.


Question: The licensee must adhere to the approved procedures and representations laid out in their submitted documents.

Licensed material shall only be used by, or under the supervision of: A. Individuals permitted to work as authorized users in accordance with 10 CFR 35.13 and 10 CFR 35.14.

The following individuals are authorized users for the material and medical uses as indicated: | Authorized User (M.D., D.O., etc.) | Material and Use          | |-------------------------------------|---------------------------| | Paul Anthony Lyle, M.D.            | 10 CFR 35.100, 10 CFR 35.200 | | Raymond P. Radanovich, D.O.        | 10 CFR 35.100, 10 CFR 35.200 |


Question: The NRC has specific requirements for visual inspections of the support pad items during the augmented ISI intervals.

40 – 60: VT-3 visual inspection of the support pad items during each 10-year augmented ISI interval – longer intervals allowed if approved by NRC.

Components stay Expansion for 40 – 60. For 60 – 80, no need to audit elevation of the lower grid rib sections to Primary.


Question: The proposed amendment aims to modify the existing technical specifications to incorporate more flexible completion times that are informed by risk assessment methodologies.

The Technical Specifications were revised to adopt TSTF-505, Revision 2, which provides risk-informed extended completion times for certain equipment outages.

The Regulatory Audit Agenda includes detailed administrative procedures for submitting amendments to the NRC.


Question: Lutathera patient protocols

David Theel described the findings regarding the admission of a patient who had been treated for Gastroenteropancreatic Neuroendocrine Disease at Teton Cancer Institute with Lutathera (Lu-177).

Idaho Falls Community Hospital will no longer provide the observation and routine Laska administration that created the waste storage and decay, staff training and education, patient safety, and public safety issues that you brought to our attention.


Question: tailpipe emissions vehicle construction

Worker transport vehicles are estimated to generate tailpipe emissions of 0.51 THC, 0.26 NOx, 0.84 CO, 0.08 PM10, 0.07 SO2, and 76.31 CO2 during an operational period of 3,030 hours.

The construction supplies and fuel are primarily delivered using semi-haul trucks, which operate for 1,460 hours with various emission levels.


Question: What is the commitment regarding overhead heavy load and light load handling systems in the context of nuclear refueling?

The existing program is credited and will be enhanced as follows: 1. Revise the implementing procedures to ensure surface conditions are monitored by visual inspection to provide reasonable assurance that loss of material is not occurring due to general corrosion or wear and the bridges, structural members, and structural components do not exhibit deformation or cracking.

Revise implementing procedures to ensure aging effects will be detected for bolted connections by visually inspecting for loss of material due to general corrosion; cracking; and loose or missing bolts or nuts, and other conditions indicative of loss of preload.


Question: What are the key responsibilities for emergency response coordination in nuclear facility accidents?

Supervising the development and maintenance of plans and procedures for Parish response to an accident at River Bend Station, including: - a quarterly verification and update of emergency implementing procedures telephone numbers, - an annual review and update of emergency implementing procedures, - an annual review of the plan and certified to be current, and, - an update of plans and agreements, as needed, taking into account issues identified in drills and exercises.

Ensuring notification and coordination of all local agencies supporting emergency operations, as required.


Question: What are the consequences of a single rod withdrawal in a nuclear reactor?

Withdrawal of a single RCCA results in both a positive reactivity insertion tending to increase core power and an increase in local power density in the core associated with the withdrawn RCCA, which could eventually result in DNB.

The maximum positive reactivity insertion rate at power is less than that observed at subcritical conditions.


Question: What is cumulative fatigue damage in nuclear reactor components?

Cumulative fatigue damage is an aging effect assessed by a fatigue TLAA in Section 4.3.

Consistent with NUREG-1801. Further evaluation is documented in Section 3.1.2.2.1.


Question: occupational radiation exposure at nuclear plants

Occupational radiation exposure at commercial nuclear power reactors and other facilities is monitored and regulated to ensure the safety of workers and the public.

Custom Soil Resource Report for Limestone County, Alabama provides detailed information about soil, land use, and conservation practices.


Question: What are land use restrictions in the context of nuclear site cleanup?

I mentioned notice of land use restrictions earlier. This is a document that is recorded on a piece of property that has completed its remedial or mitigative actions under a brownfield agreement.

I think it's important to note that we provide permit exemptions for any onsite cleanup activities related to those matters that are identified and addressed.


Question: What is an ECCS evaluation model in nuclear safety?

The ECCS evaluation model remains the licensing basis for demonstrating that the ECCS calculated cooling performance following postulated LOCAs meets the acceptance criteria.

Under 10 CFR 50.12, a licensee may request and the NRC may grant exemptions from the requirements of 10 CFR 50 that are authorized by law, will not present an undue risk...


Question: What are Agreement States in nuclear regulation?

Agreement States are States that enter into an agreement with the NRC to maintain a program that is adequate to protect public health and safety, and the environment, and is compatible with the NRC’s program.

The regulations included in this rulemaking are a matter of both adequacy and compatibility with the Agreement States.


Question: The licensing of nuclear reactors involves a thorough assessment by the NRC to ensure compliance with safety regulations.

The NRC reviews all applications for a nuclear power plant license to ensure the applicant can meet the regulatory requirements for safety and operational performance.

The emergency diesel generators provide backup power to crucial components during a blackout to maintain the safety of the reactor.


Question: What is a Marinelli beaker and its use in gamma spectrum analysis?


Question: What is the role of internal audits in nuclear facility regulation?

Internal audits are crucial for ensuring compliance with regulatory requirements and identifying areas for improvement within the operational framework of a nuclear facility.

The operational efficiency of turbines can greatly influence the overall performance of the power generation system under varying load conditions.


Question: The Nuclear Regulatory Commission evaluates the suitability of high-level waste disposal sites in accordance with legislative mandates.

The HLW Program for Pre-Licensing Positioned to Meet Nuclear Waste Policy Act Requirements provides a framework for assessing disposal facilities according to established safety and regulatory standards.

Several state officials have raised concerns about the economic impact of proposed energy initiatives, highlighting the need for careful consideration of community input.


Question: What is the Certificate of Compliance in nuclear licensing?

Certificate of Compliance No. 1031 is a regulatory approval that specifies the standards and conditions under which the MAGNASTOR system must operate for nuclear waste storage.

The administrative procedures for submitting license applications are crucial for maintaining compliance with federal regulations.


Question: What are the requirements for channel redundancy in signal processing for nuclear safety systems?

Generally, if a parameter is used only for input to the protection circuits, three channels with a two-out-of-three logic are sufficient to provide the required reliability and redundancy. If one channel fails in a direction that would not result in a partial Function trip, the Function is still OPERABLE with a two-out-of-two logic. If one channel fails such that a partial Function trip occurs, a trip will not occur and the Function is still OPERABLE with a one-out-of-two logic.

These requirements are described in IEEE-279-1971 (Ref. 4). The actual number of channels required for each unit parameter is specified in Reference 2.


Question: The NRC stipulates that licensees must utilize the appropriate methodologies for their assessments.

The methodology for evaluating the safety of nuclear reactors includes a systematic assessment of various operational parameters and potential risks.

The proposed changes to the guidelines will require a thorough review process to ensure compliance with existing regulations.


Question: The regulation of precipitation loss rates is critical for effective watershed management in nuclear safety assessments.

**ERA**N - Exponent of precipitation for loss rate function

The rainfall data collected over various time intervals shows significant variability in precipitation amounts.


Question: The NRC emphasizes the need for careful evaluation of system performance during lockout procedures.

The Operator Training Program includes metrics for job performance that focus on critical operations during emergency and abnormal scenarios, such as loss of power and system recirculation needs.

Are "well operator" dislocations accounted for in the latest performance assessments?


Question: PZR level regulations

PZR level may not be > 11% at this time. If so, THEN the crew should perform the action to stabilize RCS pressure using normal spray to allow the PZR to refill.

RO reports PZR level is > 11% (19% Adverse)


Question: What is the significance of bundle data in reactor safety evaluations?

This is Steve Bajorek. Actually there are two petitions in play right now.


Question: The NRC performed an evaluation of the environmental consequences associated with the license renewal process for nuclear facilities.

The FEIS includes the NRC staff’s site-specific evaluation of the environmental impacts of the subsequent license renewal (SLR) for Oconee Station and alternatives to the SLR.

In accordance with Title 36 of the Code of Federal Regulations Section 800.8(c), the NRC staff elected to use the National Environmental Policy Act of 1969, as amended, process to comply with its obligations under Section 106 of the National Historic Preservation Act of 1966, as amended.


Question: NRC submittal file download instructions

The following files have been uploaded to the MassTransit Web File Transfer Services. You can download them by going to: and selecting the file(s) and clicking Download (All/Selected).

This message was automatically generated from the PNNL FX Web File Transfer Service. If you have questions about its validity, please contact the sender listed above.


Question: What are the requirements for remote audits in nuclear licensing?

The NRC staff requests the licensee to have the information referenced in Section 4.0 of this audit plan available and accessible for the NRC staff’s review via an internet-based portal by November 1, 2022, so the NRC staff has sufficient time to review the documents before the audit starts on December 1, 2022.

A desktop audit will take place between December 1, 2022, and January 31, 2023.


Question: uranium recovery process

During the ISR process, an oxidant-charged solution, called a lixiviant, will be injected into the production zone aquifer (uranium orebody) through injection wells.

The proposed facility will encompass approximately 4,282 hectares (10,580 acres), which consists of two contiguous mining units, the Burdock Unit and the Dewey Unit.


Question: Define enthalpy in the context of nuclear safety

Enthalpy is a thermodynamic quantity that represents the total heat content of a system and is used in various processes, including those within nuclear reactor operations.

The use of high-performance materials in reactors is critical for maintaining structural integrity and longevity.


Question: The NRC reviews the proposed amendment to ensure it does not result in significant hazards considerations.

The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92 are satisfied. Therefore, the NRC staff proposes to determine that the license amendment request involves a no significant hazards consideration.

The use of the alternate POD values for the limited number of bobbin indications for WBN, Unit 2 for the BOC voltage distribution for the WBN, Unit 2 OA [operational assessment] does not involve a significant reduction in a margin of safety.


Question: maximum allowable rod internal over-pressure

Maximum allowable rod internal over-pressure limits are summarized in Table B-1.

A series of results are obtained for different cladding types, at beginning of life BOL and EOL.


Question: What are the major features of sump screen design modifications?

The currently installed sump strainers consist of two PCI Sure-Flow strainers with one strainer in each sump pit. Each sump strainer is made up of 72 modules. The modules are arranged in a square matrix of 16 modules on each level, except for the bottom level that has only eight modules. Eight modules are seven plates/disks high, and 64 modules are eleven plates/disks high. The interior of the disks contains wire stiffeners for support, made up of wires - 7 gauge and 8 gauge. The disks are completely covered with perforated plate having 0.045 inches diameter holes. The bottom disk of a module is separated 3 inches from the top disk of the adjacent module. The space between adjacent modules is encased in a sleeve connecting the central core tube of each module. Each module has cross-bracing on all four exterior vertical surfaces. The strainers are installed on a strainer substructure assembly, which is installed at the bottom of the containment recirculation sump pit. The strainers superstructure consists of four vertical supports on the 2000' elevation concrete pad. These supports are inside the sump's 6" concrete curb. A series of horizontal channels connect to the four vertical supports and provide lateral restraint for the module stacks. The strainers are robust so as to also serve as the trash racks, as described in a license amendment application and approved in the associated NRC safety evaluation. The material for the strainer supports, both the lower support platform and the superstructure, are also stainless steel.

Debris barriers have been installed in all openings through the secondary shield wall near the emergency recirculation sumps, specifically these were installed at the Loop A and Loop D passageway entrances.


Question: What is the response of the Automatic Depressurization System (ADS) relief valves during a Loss of Offsite Power and Loss of Coolant Accident?


Question: What does energy measurement in keV signify in nuclear regulatory filings?

Energy (keV) is used as a measurement unit for the peaks identified during the analysis of nuclear regulatory filings, representing the energy levels of emitted radiation.

The values shown in the table represent areas and uncertainties that are critical for understanding the statistical analysis of background measurements.


Question: To ensure structural integrity under tornado missile impacts, only critical members must withstand these scenarios.

The objective of the CHB analysis and design for tornado missile impacts is to ensure that structural integrity and stability of the primary framing system is maintained.

Administrative Controls will be used to mitigate impacts of design-basis tornado loading for the transportation casks (during overhead crane operations) and NAC transfer casks.


Question: thermal power verification

Verify **Fₒ(Z)** is within limit specified in the COLR.

Not required to be performed until 12 hours after declaring Power Distribution Monitoring System (PDMS) inoperable.


Question: The NRC's guidance for the design of safety-related structures addresses the impacts of various loads including dead, live, and impulsive forces.

N690-18 Section N9.1.6, Design for Impactive and Impulsive Loads, and its subsections identify the criteria for design of SC walls for impactive and impulsive loads.

Appendix N5 does not address seismic and other dynamic loads. Therefore, an exception to Appendix N5 should be taken.


Question: What is a specific license in the context of nuclear regulatory filings?

Definitions Specific license  <br> Connecticut states that the definitions are not included in the proposed legislation but will be adopted in regulation.

Connecticut needs to provide an explanation or justification as to the reason for the omissions; or supply the missing information.


Question: cracking in reactor coolant pressure boundary components

Nickel alloy and steel with nickel-alloy cladding reactor coolant pressure boundary components exposed to reactor coolant may experience cracking due to primary water stress corrosion cracking.

Consistent with NUREG-1801. Cracking of the nickel alloy RV bottom mounted instrument nozzle exposed to reactor coolant is managed by the DCPP ASME Section XI ISI, IWB, IWC & IWD AMP (B.2.3.1), the DCPP Water Chemistry AMP (B.2.3.2), and the DCPP Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-induced Corrosion in RCPB Components AMP (B.2.3.5).


Question: NRC license renewal process

We have received your application dated September 24, 2024, for renewal of NRC license number 06-05869-01 (MC643444).

I forgot to mention that you should have a member of senior management review and sign any response sent back to us.


Question: What is the purpose of a license amendment in nuclear regulation?

A license amendment allows for changes to be made to the existing conditions or requirements of a nuclear license as needed to reflect new information or changing circumstances that may affect the safety or operation of the facility.

The review process for a licensing application involves several stages, including initial review, technical assessment, and public comment.


Question: The examination was conducted to evaluate the knowledge and skills of the operators at the facility, as per regulatory standards.

In accordance with NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Indiana Michigan Power Company, the licensee for CNP is submitting the following materials:

If you have any comments or concerns, please contact Todd Valley or Steve Pettinger at (269) 465-5901, extension 3738, or myself at (269) 466-3407.


Question: visual inspection of auxiliary feedwater systems

Visual inspections of the interior surfaces of Auxiliary Feedwater System and Main Feedwater System components and piping will be performed when available.

For McGuire, Duke commits to implement the final version of the fuse holder interim staff guidance (initially provided to NEI by NRC letter dated May 16, 2002 and when finalized by the staff) by June 12, 2021 (the end of the initial license of McGuire Unit 1).


Question: What are the estimated vehicle and material shipments during decommissioning?

Table 7 provides the estimated passenger vehicles and material shipments to and from the project areas during decommissioning, including categories such as worker transport and material transport.

The duration of operation per trip for the semi-haul truck is estimated to be 0.5 hours, providing a key metric for assessing logistics.


Question: What is the significance of Americium-241 in nuclear safety evaluations?

Americium-241 is detected in environmental samples and is analyzed in the context of nuclear safety due to its radioactive properties and potential impact on health.

The Tritium sample was analyzed using liquid scintillation counting, demonstrating the characteristics of a liquid isotopic measurement that is crucial for environmental monitoring.


Question: Ge-68/Ga-68 generator regulations

In accordance with 10 CFR Section 30.35, 'Financial Assurance and Recordkeeping for Decommissioning,' applicants must have a Decommissioning Funding Plan (DFP) to obtain a license to possess Ge-68/Ga-68 generators.

Used generators may be returned to the manufacturer/distributor. This permission does not relieve licensees from the requirement to comply with 10 CFR Part 71 and Department of Transportation (DOT) regulations.


Question: license amendments in nuclear regulation

This proceeding does not concern any future license amendment or FSAR change that Holtec may seek in the future. Only the changes encompassed by these four LARs are at issue.

These premises undermine almost all of the petitioners' contentions. There are four LARs within the scope of this proceeding, nothing more.


Question: Federal Information Security Modernization Act

The Federal Information Security Modernization Act of 2014 (FISMA) requires federal agencies to develop, document, and implement an agency-wide information security program to protect their information and information systems, including those provided or managed by another agency, contractor, or other source.

The NRC has four regional offices that each operate under the direction of a Regional Administrator.


Question: definition of power defect in nuclear reactors

The Total Power Defect is defined as the difference in reactor power output from its expected value due to the dropped control rod, which has important implications over the life of the core.

The NRC requires a detailed assessment of potential seismic hazards in the vicinity of the plant to determine the design basis for structures.


Question: What is the Full Spectrum LOCA methodology?

The proposed amendment would add the Westinghouse Electric Company LLC (Westinghouse) Topical Report WCAP-16996-P-A, Rev. 1, Realistic LOCA [loss of coolant] Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology), to the list of approved analytical methods used to determine the core operating limits as listed in Technical Specification 5.6.3, “Core Operating Limits Report (COLR).”

A regulatory audit is a planned activity that includes the examination and evaluation of primarily non-docketed information.


Question: Main Control Room Emergency Habitability System

This ITAAC verified the functional arrangement of the as-built Main Control Room Emergency Habitability System (VES) as is described in the Design Description of Combined License (COL) Appendix C, Section 2.2.5.

Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.


Question: Water Chemistry aging management program

The Water Chemistry aging management program is consistent with the 10 elements of aging management program XI.M2, Water Chemistry, specified in NUREG-2191.

In 2022, a program effectiveness review was performed for Chemistry Control Program described in FSAR Section 0.1.5 in support of preparing the BFN Subsequent License Renewal Application.


Question: What is the purpose of a mass notification system in nuclear plant emergency planning?

As described in Revision 3 of the CNP ANS Design Report, the station selected a mass notification system (MNS) as the backup alerting and notification method for the 10-mile emergency planning zone (EPZ).

Per Section V, Parts A and B of the “Memorandum of Understanding (MOU) between the Department of Homeland Security (DHS/FEMA) and the NRC regarding radiological emergencies, planning, and preparedness,” dated July 1, 2024:


Question: What are the physical security requirements for Independent Spent Fuel Storage Installations?

The NRC requires licensees to comply with the physical security requirements for Independent Spent Fuel Storage Installations as outlined in the regulation IP 81311.

The inspection activity is scheduled from September 12, 2022 to September 16, 2022, involving two staff members.


Question: What are the requirements for the delivery of radioactive materials?

The inspectors examined the licensee’s procedures and shipment records and observed actual transport activities to determine that the licensee met package delivery requirements.

Certificates of Disposal for radioactive waste shipments 0857-01-0247, CPWU2986325-269, and ISEU100028-314.


Question: ATWS-ARI instrumentation requirements

The ATWS-ARI instrumentation for each Function in Table 3.1.1-1 shall be OPERABLE:

Separate Condition entry is allowed for each channel.


Question: The Environmental Protection Agency emphasizes the importance of evaluating essential fish habitat in proximity to nuclear facilities.

A review of the NOAA EFH showed no EFH within 6 miles of DNPS, nor were any EFH areas protected from fishing.

Cross regional boundaries. NOAA only provides EFH for federally managed fish and invertebrates.


Question: What are the requirements for emergency communications plans in nuclear facilities?

All communication plans shall have arrangements for emergencies, including titles and alternates for those in charge at both ends of the communication links and the primary and backup means of communication.

The program to provide for: (a) The training of employees and exercising, by periodic drills, of emergency plans to ensure that employees of the licensee are familiar with their specific emergency response duties, and (b) The participation in the training and drills by other persons whose assistance may be needed in the event of a radiological emergency shall be described.


Question: The evaluation of intangible benefits requires a systematic approach, which is reflected in the decision matrix framework.

Table A-1 Example of a Decision Matrix—Quantification of Intangible Benefits

Table A-2 Example of a Cost-Benefit Index


Question: How will airborne uranium particulate levels be monitored in a facility?

When non-routine work activities will be performed in an area or manner that could result in exposure to uranium particulates, area air samples or breathing zone samples will be utilized to determine airborne uranium particulate levels.

To ensure compliance with 10 CFR 20.1301, 20.1302, and 20.1501, NuFuels will maintain a continuous air monitoring program at three separate locations: upwind of the CCP or satellite facilities, downwind from the CCP or satellite facilities at the restricted area boundary, and downwind at the nearest residence.


Question: The modifications to the Equipment Access Door Seals ensure that the access doors remain securely sealed when deflated.

The Equipment Access Door Seals (EADS) have been modified so that the Equipment Access Doors are permanently in the closed position with the Equipment Access Door seals deflated.

Access doors must be kept clear to allow personnel to achieve safe and efficient movement within the facility.


Question: What safety-related systems are in place for potential liquid spills at nuclear facilities?

Appropriate independent safety-related systems would be in place to assure the safe shutdown of a new facility, in the event of a possible unavailability of raw water makeup from the river.

The closest such military flight route, as illustrated in Figure 2.2-5, is VR107 which is SE of the site but beyond V245 at its closest point of approach to the site.


Question: nuclide minimum detectable activity

The nuclide minimum detectable activity (MDA) is a critical measurement that indicates the lowest concentration of a nuclide that can be reliably detected in a sample.

The peak size in counts per second (CPS) is measured to understand the intensity of the signal at a specific energy level.


Question: nuclear fuel cycle

And I would just like to again drive home the importance of looking at the nuclear fuel cycle because nuclear energy is being touted as a green energy, a clean energy to meet these standards that are coming up. But the mining, the milling, and the processing of uranium fuel have very -- they do have a carbon footprint that is not in your figures for nuclear energy.

However, due to a lack of data and to protect employee privacy, we are unable to provide an analysis that discloses demographic information for employees of Oconee Station.


Question: nuclear reactor licensing requirements

The licensing process for a nuclear reactor involves a detailed evaluation of the applicant's safety and environmental assessments, followed by a series of public hearings and reviews by regulatory bodies.

The cooling system operates by circulating water through the reactor core, absorbing heat, and transferring it to the steam generators.


Question: environmental report in nuclear licensing

three of the four do cite this -- what we call the environmental report.

So I don't think they would have problems determining what's different between that document and this one.


Question: What is the role of hydrographs in regulatory assessments?

The hydrograph represents the rate at which water moves through a given area over time, which is crucial for understanding hydrological responses in regulatory assessments.

The table above outlines the different station weightings and their respective values for the units analyzed.


Question: nuclear reactor safety systems

Nuclear reactor safety systems are designed to ensure safe operation under normal and accident conditions, providing multiple layers of protection against potential hazards.

The assessment of environmental impacts from nuclear plants includes factors like land use, water quality, and air pollution, which are critical for sustainable energy development.


Question: The NRC stipulates that the ECCS must meet specific criteria related to core cooling and cladding integrity after an emergency shutdown.

The LCO helps to ensure that the following acceptance criteria for the ECCS, established by 10 CFR 50.46 (Ref. 2), will be met following a LOCA: a. Maximum fuel element cladding temperature is ≤ 2200°F; b. Maximum cladding oxidation is ≤ 0.17 times the total cladding thickness before oxidation; c. Maximum hydrogen generation from a zirconium water reaction is ≤ 0.01 times the hypothetical amount generated if all of the metal h in the cladding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react; d. Core is maintained in a coolable geometry; and e. Adequate long term core cooling capability is maintained.

The Engineered Safety Feature (ESF) buses shed normal operating loads and are connected to the emergency diesel generators (EDGs).


Question: The NRC stipulates that any exceedance of permissible limits must be reported with corrective actions documented as required by license and permit regulations.

If the data indicates that exceedences of applicable limits has taken place, appropriate reporting and documentation of corrective actions will be performed in accordance with NRC license and permit requirements.

Access to this area will be through the main gate.


Question: What is the significance of holding time in nuclear sample analysis?

Samples (See Below) were received and analyzed outside the hold time.

The following samples were analyzed using the above methods and analytical procedure(s).


Question: maximum water surface elevation

The maximum WSEL in Rock Run Creek (EL 118 ft-NAVD88) is well below the PBAPS CLB protection level of EL 134.87 ft-NAVD88 (EL 135 ft-C.D.).

Excluding the effects of wind-generated waves (Section 3.6), the maximum WSEL of NUREG/CR-7046, Appendix H-1 PMF flooding alternatives (126.04 ft-NAVD88) is below the PBAPS CLB protection level of EL 134.87 ft-NAVD88 (EL 135 ft-C.D.).


Question: What is the significance of background subtraction in nuclear measurements?

Background subtraction is crucial in the analysis of nuclear decay data, as it helps to isolate the signal from the noise associated with ambient radiation.

The identified nuclides are used in various applications, including medical imaging and cancer treatments.


Question: Understanding the implications of abnormal operations and how they affect the area radiation monitoring system is crucial for the operator.

K/A is matched because the applicant is required to have knowledge of the operational implications of a caution from an abnormal operating procedure.

The Common Radiation Detectors used in monitoring are essential for ensuring accurate readings during normal reactor operations.


Question: What is the role of the Nuclear Reactor Regulation office?

The Nuclear Reactor Regulation (NRR) office is responsible for the regulation of commercial nuclear power plants and non-power nuclear reactors, ensuring safety and compliance with regulatory requirements.

The NRC provides reasonable accommodation to individuals with disabilities where appropriate.


Question: Instrumentation must be available to monitor key variables and systems throughout all operational phases to ensure safety.

Appendix A to 10 CFR Part 50, General Design Criterion (GDC) 13, “Instrumentation and control,” states that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.

Components and modules shall be of a quality that is consistent with minimum maintenance requirements and low failure rates. Quality levels shall be achieved through the specification of requirements known to promote high quality, such as requirements for design, for the drafting of components, for manufacturing, quality control, inspection, calibration, and test.


Question: The NRC must ensure that licensees comply with NEPA standards for environmental reviews.

In Oglala Sioux Tribe, the D.C. Circuit reviewed the Commission's decision to leave Powertech’s license in place 'notwithstanding the Commission’s conclusion that there has been a significant deficiency in its NEPA compliance — unless an intervenor demonstrates irreparable harm.'

Constellation argues that the standards in Oglala Sioux Tribe v. NRC and Allied-Signal, Inc. v. NRC should have been applied.


Question: Understanding the importance of maintaining operational integrity in service water systems is crucial for reactor safety.

Knowledge of the relationship between a loss of service water and the following systems or components: (CFR: 41.8 / 41.10 / 45.3)

Safety drills and training exercises are conducted regularly to ensure preparedness for emergency situations.


Question: The NRC mandates measures to ensure adequate protection against random failure of the Jocassee Dam, citing public health and safety concerns.

Duke fails to address the environmental significance of a 2011 Safety Evaluation, in which the NRC Staff determined that the potential for a random (i.e., “sunny day”) Jocassee Dam failure constitutes an “adequate protection” issue requiring Duke to implement additional measures to protect against flooding of essential safety equipment and thereby prevent a reactor meltdown.

The [ER] fails to consider additional mitigative measures that may well be cost-effective.


Question: TID source term in nuclear regulation

TID source term is one that could be a show stopper for moving forward with uprates, so this is one that we highlight as being a really big topic for us to consider going forward.

I heard this morning about putting it into the guidance, but if it's in the rule we're not sure how you get out of that requirement and that's something that we need to think about in terms of discussions with the staff.


Question: The NRC mandates that licensees monitor parameters such as turbined pressure to comply with safety regulations.

HPCI Pump Discharge Pressure (HPDP) is monitored as part of the High Pressure Coolant Injection (HPCI) system, which is essential for maintaining reactor safety during an emergency.

HPCI Turbine Exhaust Pressure (HTEP) is carefully tracked to ensure the proper functioning of the turbine during normal operations.


Question: The application for extending the licenses of nuclear facilities must demonstrate that the systems will continue to operate effectively over time.

is reasonable assurance that the intended functions are maintained consistent with the current licensing basis during the subsequent period of extended operation.

Browns Ferry Nuclear Plant Subsequent License Renewal Application (Rev. 0) 3-556


Question: The NRC emphasizes that independent assessments of cooling systems are essential for accurate safety analyses, particularly for loss-of-coolant accident scenarios.

The BWR-FLECHT Program was carried out by the General Electric Company (GE) under a subcontract of the Idaho Nuclear Corporation, itself a contractor to the test program sponsor, the AEC.

The BWR-FLECHT Program has been heavily criticized for its narrow scope and significant methodological flaws in evaluating core cooling performance.