Question: The NRC must assess the environmental significance of seismic events related to reactor operations, particularly regarding historical earthquakes like the 2011 Mineral earthquake.

Aging problems associated with SSCs, including reactor pressure vessel embrittlement, irradiation-assisted stress corrosion cracking of reactor internals, concrete structures and containment degradation, and electrical cable qualification and condition assessment, were identified in SECY-14-0016, Memorandum from Mark A. Satorius, NRC Executive Director of Operations, to NRC Commissioners, re: Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal at 1 (Jan. 31, 2014) (ML14050A306) and the NRC’s five-volume Expanded Materials Degradation Assessment (EMDA), NUREG/CR-7153 (Oct. 2014) (“EMDA Report”).

This argument is without merit. Petitioners clearly and explicitly state that Dominion must evaluate the environmental significance of the 2011 Mineral earthquake in light of the NRC’s exclusive reliance on a generic finding that the environmental impacts of reactor operation are small because their design bases are adequate to protect against likely events (with no consideration of the impact of the Mineral earthquake on its analysis).


Question: stainless steel closure bolting aging effects

The Bolting Integrity (B.2.1.10) program will be used to manage cracking of the stainless steel bolting exposed to air - indoor uncontrolled in the Process Sampling and Radiation Monitoring System and Standby Liquid Control System.

Not Applicable. There are no stainless steel underground piping, piping components, or tanks in Auxiliary Systems. See Subsection 3.3.2.2.3.


Question: The NRC evaluates the qualifications of operators based on their training and experience.

The regulatory framework mandates that reactor operators must possess a valid Nuclear Regulatory Commission (NRC) license that verifies their competencies and adherence to safety standards.

A thorough analysis of the reactor’s cooling system is crucial to ensuring operational integrity.


Question: What is Y-90 licensing guidance?

He appears to be qualified to be an authorized user for Theraspheres under pathway three in the Y-90 licensing guidance, dated April 20, 2021.

My understanding is that you would like to add Dr. Tew as an authorized user for 35.1000 Y-90 both Theraspheres and SIR-spheres.


Question: What is the response time for a reactor protection system?

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.

The Online Monitoring Program must be implemented in accordance with AMS-TR-0720R2-A, 'Online Monitoring Technology to Extend Calibration Intervals of Nuclear Plant Pressure Transmitters' (proprietary version).


Question: The loading table specifies the average burn-up in GWd/MTU for different enrichments of uranium.

| Minimum Initial Assembly Avg.  |    WE 14×14 Assembly Average Burnup (B)    |

The table presents a clear delineation of enrichment wt % 235U across varying ranges.


Question: The examination of critical heat flux conditions is fundamental in ensuring reactor safety during operation.

The COBRA-FLX: ORFEO-HMP Critical Heat Flux Correlation provides an important methodology to analyze critical heat flux and its implications for operational safety in nuclear reactors.

The document outlines the various types of test assembly conditions used in non-mixing grid tests to evaluate performance.


Question: The regulation of the minimum detectable concentration is crucial in assessing radioactive material levels.

- **MDC**: Minimum Detectable Concentration

Westinghouse Electric Company, LLC is located in Columbia, South Carolina.


Question: remote position indication testing

Remote Position Indication (RPI) for Motor-Operated Valves (MOV) is “sensed” by limit switches (LS) located inside the closed MOV LS compartment. There are small sealed LS gearboxes gear-connected to the actuator wormshaft. Each LS gearbox drives an output rotor that makes/breaks the electrical contacts on the fingerboards. The III-3300 RPI test means to accomplish two things; that the RPI functions (i.e., no bad bulbs) AND that the RPI accurately reflects valve position.

Inservice Testing, also called Diagnostic Testing (DIAG), is performed on MOV’s in accordance with III-6000. A MOV DIAG is required to be performed at intervals not to exceed 10 years.


Question: What does the client ID represent in nuclear sample reporting?

Each sample in the QC Summary Report is associated with a unique client ID that identifies the specific analysis requested for regulatory compliance.

The samples including L88710-1 through L88710-20 are part of standard quality control procedures in analytical laboratories, ensuring accuracy and reliability in reporting.


Question: dry film thickness in coating systems

Dry Film Thickness refers to the thickness of the dry coating layer applied to a surface, measured in mils, which is crucial for ensuring the coating's protective qualities for concrete surfaces.

Mobil/Valspar is a manufacturer known for creating a wide range of coatings that are used in various industrial applications, including concrete protection.


Question: What are the specifications regarding weather data collection for nuclear sites?

The National Weather Service operates a network of Cooperative Observer Stations (COOP) that collect meteorological data across the United States, including temperature, precipitation, and other climatic conditions relevant to nuclear safety assessments.

The Cape May 2NW station provides climate data for various analyses and has recorded conditions such as elevation and distance from nearby facilities, but it does not directly relate to nuclear regulatory processes or safety.


Question: The procedure involves ensuring that the air supply for the control valves is managed correctly.

CLOSE the Air Supply Isolation Valve, 11CV160 A/S, AIR SUPPLY FOR 11CV160.  **STANDARD:** Locates and simulates closing the Supply Isolation Valve, 11CV160 A/S, AIR SUPPLY FOR 11CV160.

PROCEED to Unit 1 Cont Air Redundant Air Supply Wall Mntd Pnl 701-1A, El 122', near the Boric Acid Storage Tanks.  **STANDARD:** Locates Unit 1 Cont Air Redundant Air Supply Wall Mntd Pnl 701-1A.


Question: What are the human health impacts from chemical releases in nuclear power plants?

In the 2013 GEIS, the NRC reviewed potential human health impacts from chemicals associated with nuclear power plant operations (NRC 2013). Human health effects potentially occur at BFN and other nuclear power plants as a result of discharges of chlorine or other biocides, small-volume discharges of sanitary or other liquid wastes, chemical spills, and metals leached from cooling system piping and condenser tubing.

Wheeler Reservoir averages between 1- and 1.5-miles wide near BFN and is used by the public for recreational boating, fishing, and swimming.


Question: What are the requirements for biennial leakage testing of motor-operated valves in nuclear plants?

Specifically, relief from the ASME OM Code, Section ISTC-3630, biennial leakage testing requirements was requested for Turkey Point motor-operated isolation valves, MOV-864A/B, located on the Refueling Water Storage Tank (RWST) outlet lines, and MOV-856A/B, located on the RWST return lines, on the basis that the proposed alternative would provide an acceptable level of quality and safety.

The information in this RAI response provides additional information that clarifies the application and does not expand the scope of the application.


Question: What is an Environmental Impact Statement in nuclear projects?

An Environmental Impact Statement (EIS) is a document required by the National Environmental Policy Act (NEPA) that describes the potential environmental effects of a proposed federal action, such as the approval of licenses for uranium milling facilities.

The report outlines the history of uranium mining practices in the United States and discusses various mining technologies, including traditional open-pit and underground methods.


Question: What are marching algorithms in nuclear plant simulations?

The algorithms were designed to handle generic configurations of components, meaning that the user can design arbitrary networks as long as the configuration is valid (i.e., there is a source, active pumps, and a sink).

At any given time during the simulation, the state of the plant can be defined by a fixed set of parameters (i.e., the on/off states of components, the quantity of debris stored by components, etc.).


Question: What is the meaning of ANS in nuclear safety contexts?

The ANS (American National Standards) standards are critical for ensuring safety and consistency in nuclear plant operations and evaluations.

The HPCI (High Pressure Coolant Injection) system is designed to provide emergency core cooling during loss-of-coolant accidents.


Question: What are the licensing commitments detailed in the Technical Requirements Manual?

Technical requirements that are licensing commitments, but which may be controlled by the licensee in accordance with the process for changes, tests, and experiments as provided in 10 CFR 50.59, can be maintained in the Technical Requirements Manual (TRM).

The area temperature monitoring requirements are addressed in Technical Requirements Manual TR 13.7.5, Area Temperature Monitoring.


Question: The average burnup of the WE 14x14 assembly is affected by the enrichment levels of uranium in the fuel rods.

WE 14x14 Assembly Average Burnup (B) GWd/MTU


Question: During the shutdown cooling process, the reactor water temperature gradually decreased from 210°F before cooling was lost.

At Time = 40 minutes, Shutdown Cooling (SDC) is restored.


Question: The map illustrates the surrounding types of water supply wells near the VEGP site, including agricultural, municipal, and industrial wells.

Figure 2.4.12-19 Locations of Agricultural, Industrial, Municipal, and Public Water Supply Wells Within 25 Miles of the VEGP Site.

The VEGP site is marked on a geographical map showing various indicators and outlines in the vicinity of the facilities.


Question: sanitary sewage disposal of radioactive waste

The first mechanism, found in 10 CFR 20.203(a), permits a broad range of licensees to dispose of radioactive materials used in industrial and medical applications into sanitary sewerage, under certain specific conditions.

The Commission considered sewage disposal for insoluble materials compared to 'dispersible biological materials,' and found that in the case of insoluble materials a 'broad provision' allowing for sewage disposal was not advantageous compared to alternative disposal options (such as disposal at a low-level radioactive waste disposal facility).


Question: nuclear licensing requirements

The licensing process for nuclear facilities is governed by a set of regulatory requirements that ensure safety and compliance with federal laws.

The photographs from 1968 and 1969 showcase the construction of the Palisades Nuclear Plant, capturing its early development stages.


Question: probable maximum flood hydrograph

Probable Maximum Flood Hydrograph at River Mile 151.1 by Routing Corps of Engineers PMF Outflow Hydrograph (Valley Storage Taken Into Account) at Clark Hill Dam Through Savannah River


Question: The measurement of activity for various isotopes is expressed in picocuries per gram, highlighting the significance of understanding these values in regulatory submissions.

Activity (pCi/grams) is a critical measurement for assessing the radioactivity present in nuclides, which influences regulatory compliance and safety evaluations.

Regulatory compliance is essential for ensuring the safe operation of nuclear facilities and protecting public health and safety.


Question: What information does the NCDC provide in their climatography reports?

National Climatic Data Center (NCDC), “Climatography of the United States No. 20, 1971-2000, Chestertown, MD”, published by NCDC, Asheville North Carolina, available at NCDC website, [http://www.ncdc.noaa.gov/oa/mpp/](http://www.ncdc.noaa.gov/oa/mpp/), 2001(b).

The NRC requires licensees to conduct comprehensive assessments of seismic hazards as part of the regulatory process.


Question: The minimum detectable activity (MDA) for nuclides is essential for ensuring accurate measurements.

Nuclide MDA (pCi/grams) indicates the minimum detectable activity for each corresponding nuclide based on its specific properties and the detection method used.

The energy levels of various nuclides can significantly affect their detection and interpretation during sampling.


Question: What is the purpose of ultrasonic examination in nuclear procurement?

Three ASTM A182 Round Rods, Heat #8-2100, MT-2670 | Ultrasonic Examination (UT)| 100-UT-002D Rev 8   | Epoch 650 s/n 10885                        | Ethan Holeyc UT III         | Approved by Level III           | MISTRAS Project #41276420                   |                        | Performed 2/26/2024    |                                             |                              |                                |

Also reviewed NDE records associated with Orders listed in Figure 1 of this checklist.


Question: What is the NRC's approach to management directives?

Following Commission approval of change in the drug testing program, ADM will develop a new Management Directive to describe the drug testing policy and provide an overview of the procedures that employees are expected to follow.

This recommendation will be closed when OIG evaluates the revised and approved Management Directive containing the drug testing policy and procedures that employees are expected to follow.


Question: What are the proposed technical specification changes for the Wolf Creek Generating Station?

The proposed technical specifications changes for the Wolf Creek Generating Station include modifications in response to the risk-informed resolution of Generic Letter 2004-02 to enhance safety and compliance with regulatory standards.

The performance of the Wolf Creek Generating Station is closely monitored to ensure that it operates within established safety margins and conforms to the specifications required by the Nuclear Regulatory Commission.


Question: What is the significance of the Auxiliary Feedwater (AFW) System in nuclear safety?

3.7.5 Auxiliary Feedwater (AFW) System: C. One motor-driven AFW pump and one turbine-driven pump steam supply inoperable | 1.4 days

3.8.4 DC Sources - Operating: B. One battery inoperable | 7.8 days


Question: gamma spectrum analysis

Gamma spectrum analysis involves the detection and quantification of gamma radiation emitted from a sample, where the energy and intensity of the peaks in the spectrum provide information about the isotopes present and their concentrations.

The sample was acquired on June 11, 2019, and the peak analysis was performed with a channel range from 100 to 4096, allowing for a comprehensive view of the detected gamma radiation.


Question: The IC System must remain functional during various reactor modes to ensure safety and compliance.

**LCO 3.5.3** The IC System shall be OPERABLE.


Question: What factors are considered in the analysis of strainer head loss?

The failure modes related to strainer head loss are analyzed using the NARWHAL software.

Chemical release into sump pool can impact the overall safety analysis but does not directly relate to strainer head loss.


Question: spent resins waste management

Spent resins, which are generated during the operation of nuclear reactors, require careful management and disposal due to their radioactive nature and potential long-term environmental impact.

The guide tubes support the movement of control rods within the reactor, ensuring proper reactivity management during operation.


Question: During the ARITA process, technical evaluations are crucial for determining compliance with safety standards.

The ARITA process involves a thorough review of technical safety evaluations to ensure compliance with regulatory requirements.

The team will coordinate schedules to find a time that works best for everyone involved in the meeting.


Question: The maximum horizontal speed of a hurricane missile is determined based on site-specific wind conditions.

**Vₕₙ max** is the maximum horizontal speed of a hurricane missile from RG 1.221 Table 2, linearly interpolated to the corresponding hurricane site characteristic wind speed of 159 mph.

Schedule 40 Pipe measures 6.625 inches in diameter and 15 feet in length, with a mass of 287 pounds.


Question: manual scram system in nuclear reactors

12 – Manual Scram   | None          | None                 | 1) Manual Initiation   | None | a) Manual SCRAM | b) Reactor Mode Switch – Shutdown Position

Electrohydraulic Control is a system used to operate various components in the turbine system.


Question: The NRC mandates specific sample sizes for the examination of tendon systems as specified in the regulatory guidelines.

the Regulatory Guide 1.35 requires 'Examination sample size - six dome, five vertical, and ten hoop tendons,'

There are ten numerical values listed in Table 3 for Unit 1 year 1 hoop tendon forces, but only seven forces are plotted in figure 1.


Question: What is the mission of Kairos Power?

Kairos Power’s mission is to enable the world’s transition to clean energy, with the ultimate goal of dramatically improving people’s quality of life while protecting the environment.

The NRC requires licensees to maintain effective communication with emergency responders in the event of a nuclear incident.


Question: The NRC's Structures Monitoring program addresses the management of aging effects in concrete components.

Cracking; loss of bond; and loss of material (spalling, scaling) due to corrosion of embedded steel

Concrete is a widely used building material known for its durability and strength, often utilized in construction projects worldwide.


Question: industrial area zoning regulations in nuclear sites

The industrial area is zoned as a heavy industrial district (I-2) for principle uses associated with heavy industry and manufacturing development, and for uses that by the nature of the product or character of the activity requires isolation from residential or commercial use.

Land use description focuses on Wright and Sherburne counties, Minnesota, because as described in Section 2.5, approximately 66 percent of the MNGP permanent workforce reside in the two counties and MNGP pays taxes to Wright County.


Question: The NRC assesses the environmental impact of mining activities close to nuclear facilities.

Table 3.12-1 lists active projects within 80 km of the CUP, detailing the type and status of each facility.

Surface strip mining has various environmental implications, often leading to significant land degradation.


Question: Ra 226 Gamma Spectrometry Analysis

Ra 226/228 Gamma Spec Norm Library, U/th Alpha Spec

Do not dispose of samples until requested.


Question: What is the role of the auxiliary building in nuclear safety?

The auxiliary building is a safety-related, Design Class I structure that provides structural support, shelter, and protection for components relied upon to provide the capability to shutdown the reactor and maintain it in a safe shutdown condition.

The foundation of the auxiliary building is reinforced concrete consisting of three separate elevations, all of which are founded on bedrock.


Question: The NRC assesses the impact of high burnup spent nuclear fuel during extended storage scenarios.

The ongoing research on high burnup spent nuclear fuel addresses its performance and integrity under extended storage conditions, focusing on both safety and technical challenges.

The presentation will also cover administrative details regarding the timely submission of documents for the meeting.


Question: The NRC requires accurate reporting of any product codes associated with licensing.

The preferred product code for the 9200 series is TX-0634-D-870-S.


Question: nuclear licensing process

The nuclear licensing process involves a thorough review of safety, environmental, and operational aspects of nuclear power plants before they can operate.

The Millstone Power Station has a long history of providing reliable electricity to the region, contributing to the overall energy demands of New England.


Question: What are the potential impacts of changes made to plant operations under the regulatory framework?

...there’s really no limit, other than from a risk perspective, the types of changes that can be made.

You could maybe increase my operating temperatures. You could increase flow rates.


Question: What is the purpose of the Fusion Industry Association?

The Fusion Industry Association is an international coalition of companies working to electrify the world with fusion - the unparalleled power of the stars.

The world is increasingly focused on sustainable energy solutions that reduce carbon emissions and reliance on fossil fuels.


Question: probable maximum flood analysis

NUREG/CR-7046 (Reference 2.2-1) recommends increasing the unit hydrograph peak discharge by 5% to 20% and reducing the unit hydrograph lag time by 33% to account for non-linearity effects during an extreme event such as the PMF.

The hydraulic conditions in the Missouri River between Gavins Point Dam (approximate RM 810) and CNS during flood flows are complex due to the presence of revetment, river training structures, levees, roadway embankments, river meanders, and bridges.


Question: The NRC specifies that licensees must comply with regulations outlined in Title 10 of the Code of Federal Regulations, including detailed requirements for licensing applications.

Reference 36 should be Chapter 11 of 10 CFR 100 as identified on Page 17 (Section 2.f. / 2nd Paragraph / 1st Sentence). The title for Chapter 11 is also missing.

Editorial: Reference 9 and 10 are out of order as they appear in the main body of the document.


Question: fuel assembly average burnup

The table outlines the loading characteristics for pressurized water reactor (PWR) fuel assemblies, specifically detailing the average burnup limits in gigawatt-days per metric ton of uranium (Gwd/MTU) and the minimum cooling time required for various enrichment levels of the assemblies.

The Certificate of Compliance No. 1031 provides a regulatory framework for the approval of designs and changes in nuclear facility operations as regulated by the NRC.


Question: The licensing process involves assessing the safety and performance of new reactor systems using established regulatory frameworks.

The planned license amendment requests regarding the adoption of PAD5™ code, FSLOCA, and the use of AXIOM™ fuel rod cladding are crucial for ensuring the safety and efficiency of operations at the Catawba and McGuire Nuclear Stations.

Several organizations participated in the meeting to discuss the improvements and updates in the nuclear sector.


Question: The calculation of total clean strainer head loss is determined by factors such as strainer flow rate and water temperature.

The head loss at the exit of the stack was determined by modeling it as flow exiting a pipe.

The velocity through the perforated plate openings for the generic PCI prototype is much higher than that of the Wolf Creek strainer.


Question: The classification of land use is essential for understanding the environmental impact of a nuclear reactor site.

Entire area within site boundary is zoned industrial. Actual land cover within the site boundary varies.

Agricultural land use dominated the regional landscape, comprising 92.5% of the region area.


Question: What is the role of the FLUKE 5700A in regulatory compliance?

The FLUKE 5700A is a precision instrument used in the calibration of measurement devices, ensuring that all equipment meets regulatory compliance for safety and operational efficiency.

The manufacturer of the equipment listed in the table is responsible for providing all relevant specifications and support documentation to the regulatory body.


Question: What is the purpose of the Congressional Review Act in regulatory processes?

The Congressional Review Act allows Congress to review and potentially overturn federal regulations by issuing a 'joint resolution of disapproval.'

The form requires the agency to provide the name of the department or agency submitting the regulation.


Question: What is the significance of the Sprayed Containment Volume in nuclear plants?

Compartment number 1 - Name: Sprayed Containment Volume - Compartment volume = 2.3600E+06 (Cubic feet) - Compartment type: Normal - Removal devices within compartment: Deposition - Pathways in and out of compartment: 1 - Inlet Pathway Number 2: Sprayed Containment Volume to Sprayed Containment - Exit Pathway Number 3: Sprayed Containment Volume to Environment - Exit Pathway Number 3: Sprayed Containment Volume to Dummy Sprayed


Question: Nuclide MDA

The Minimum Detectable Activity (MDA) for a nuclide is defined as the lowest concentration of the nuclide that can be reliably detected and quantified in a sample, expressed in picoCuries per gram (pCi/grams).

The activity of nuclides like EU-152 can vary significantly based on their decay paths and energy emissions.


Question: containment pressure analysis

Figure 6.2-62 presents the containment pressure during the depressurization analysis at 55°F SW, measured in pounds per square inch absolute (psia).

Figure 6.2-63 outlines the containment temperature during the depressurization analysis at 55°F SW, measured in degrees Fahrenheit (°F).


Question: What is the critical heat flux (CHF) in nuclear reactors?

A CHF correlation is developed based on these experimental measurements.

The tests performed at the Babcock and Wilcox's Alliance Research Center (ARC) test facility are identified with the prefix “AR”.


Question: What is the purpose of the Alert Notification System in nuclear emergency response?

Wireless Emergency Alerts (WEA) will be used to alert the public of an emergency at River Bend Station.

Total breakdown is backed up by the special lines outside the Centrex System.


Question: The NRC evaluates nuclear power plants to ensure their compliance with safety standards during operation.

The NRC requires licensees to analyze emergency zones for potential accidents to safeguard public health and safety.

The Generic Environmental Impact Statement provides insights into various environmental considerations, but does not address the specifics of nuclear plant licensing.


Question: What measures are in place for maintaining cooling in spent fuel pools?

The KF System provides adequate capacity to maintain an acceptable temperature range for the normal and maximum heat loads. The large heat capacity of the fuel pool allows enough time for maintenance to assure necessary cooling in the event of component failures including a complete loss of forced cooling.

Electrical power is supplied from emergency power buses to each of the spent fuel pool pumps. Each pump is connected to these emergency power buses so that it receives power from a separate diesel generator set from the other pump, should offsite power be lost.


Question: risk-significant SSCs

In the TR, Holtec proposed a methodology for identifying candidate risk-significant SSCs using the SMR-300 PRA.

The methodology in the TR can only be used in concert with a PRA and analysis of CDF and either LRF or LERF, as applicable, that the NRC staff has determined to be technically acceptable and addresses internal and external hazards and all operating modes, including low-power and shutdown, as required for specific licensing submittals.


Question: The TVA Nuclear Quality Assurance Plan incorporates components that are crucial for the reliability of nuclear operations.

The TVA Nuclear Quality Assurance Plan (NQAP) implements the requirements of 10 CFR 50, Appendix B and is consistent with the summary in Appendix A.2, “Quality Assurance For Aging Management Programs (Branch Technical Position QMB-1)" of NUREG-2192.

Operating experience (OE) from plant-specific and industry sources is captured and systematically reviewed on an ongoing basis in accordance with the quality assurance program, which meets the requirements of 10 CFR Part 50, Appendix B, and the OE program, which meets the requirements of NUREG-0737.


Question: What is the confidence index for nuclides in nuclear regulatory filings?

Nuclide confidence index threshold = 0.30


Question: The emergency communication systems at River Bend Station include Wireless Emergency Alerts to inform the public about potential hazards.

Wireless Emergency Alerts (WEA) will be used to alert the public of an emergency at River Bend Station.

East Feliciana Parish has requested priority service from the Telephone Company for restoring service provided in the Parish EOC.


Question: What is the role of Strontium-90 in radioactive analysis?

Strontium-90 is analyzed in radiation testing to determine its concentration in environmental samples, typically reported in units of picocuries per gram (pCi/g).

The LaCUBR Site Restoration Project focuses on the remediation of the LaCUBR site, ensuring compliance with environmental regulations set by the NRC.


Question: activity measurement for radioactive nuclides


Question: radionuclide concentration in soil samples

The summary of gamma spectroscopy results for judgmental soil samples indicates the concentrations of various radionuclides, such as Co-60, Cs-137, Eu-152, Eu-154, and Sr-90, expressed in picocuries per gram (pCi/g).

Emergency response training is conducted biannually to ensure the readiness of personnel in case of a nuclear incident.


Question: What is the purpose of the TSC handling and transfer facility in nuclear operations?

The TSC provides a leaktight confinement boundary and is evaluated for normal and off-normal handling loads.

Movements of the TRANSFER CASK and TSC outside of a 10 CFR Part 50 licensed facility are not permitted unless a TSC TRANSFER FACILITY is designed, operated, fabricated, tested, inspected, and maintained in accordance with the following requirements.


Question: manual boration procedures

1. **INITIATE a manual boration:** a. DETERMINE boration flow rate and volume from Reactivity Briefing Sheet.

1. **INITIATE emergency boration:** 1. PLACE boric acid transfer pump aligned to blender in FAST speed.


Question: What is a safety parameter in nuclear regulatory filings?

The safety parameters are defined as the quantitative measures that ensure compliance with regulatory requirements, ensuring the safe operation of a nuclear facility.

The weather forecast for the region indicates a high likelihood of precipitation throughout the weekend, affecting outdoor events.


Question: What details are expected from Framatome regarding the [b](4) as part of the ongoing discussions?

Framatome will be providing a number of additional points in the RAI response.

Yes, we are anticipating further discussion with Framatome on this. We had some internal discussion on this, and our current thoughts are that there is some merit to having Framatome speak to a couple of points. I’ll reach out to you to bring you up to speed on our thoughts here.


Question: reactivity control systems

The PDC requires a "minimum of two reactivity control systems or means," one of which must be "independent and diverse from the others."

In December 2023 the NRC issued a construction permit to Kairos Power LLC for construction of a non-power reactor, Hermes, in Oak Ridge, Tennessee.


Question: nuclear steam condensate

TAXES & FEES (OF CHARGES)                   |                |                  |                    |                              | 10,151


Question: gamma spectrum analysis

The gamma spectrum analysis was performed on the sample taken with a 500 ml Marinelli detector, allowing for accurate identification of radioactive isotopes based on the detection of characteristic gamma rays.

The operator for the analysis was designated as Administrator, which is critical for ensuring that the procedures adhere to regulatory compliance during sample handling.


Question: Final Status Survey data reporting

This Final Status Survey (FSS) Release Record for survey unit L2-011-101 has been generated in accordance with LaCrosseSolutions procedure LC-FS-PR-009, Final Status Survey Data Reporting and satisfies the requirements of Section 5.11 of the La Crosse Boiling Water Reactor License Termination Plan (LACBWR LTP).

The boundary of the survey unit and the location of the soil samples were defined using a Global Positioning System (GPS).


Question: design basis site-specific parameters

The design basis site-specific parameters and analyses that require verification by the MAGNASTOR SYSTEM user are: a temperature of 76°F is the maximum average yearly temperature. The three-day average ambient temperature shall be ≤106°F.

The potential for fire and explosion shall be addressed, based on site-specific considerations. This includes the condition that the fuel tank(s) of the cask handling equipment used to move the loaded STORAGE CASK onto or from the ISFSI site contains a total of no more than 50 gallons of fuel.


Question: What is an Enterprise Identifier (EPID) in NRC documents?

An administrative record regarding the Enterprise Identifier (EPID) number was identified, specifically that EPID L-2020-OLL-0032 should be L-2020-OLL-0027.

A copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of the Publicly Available Records (PARS) component of NRC’s ADAMS.


Question: What is included in the Environmental Report for Turkey Point Nuclear Generating Station?

Florida Power & Light Company submitted an Environmental Report (ER), Supplement 2 (the ER supplement), related to its 2018 application (ML18037A812) for subsequent license renewal of Renewed Facility Operating License Nos. DPR-31 and DPR-41 for the Turkey Point Nuclear Generating Station, Unit Nos. 3 and 4 (Turkey Point), respectively, to the U.S. Nuclear Regulatory Commission (NRC) pursuant to section 103 of the Atomic Energy Act of 1954, as amended.

The NRC staff has initiated the environmental review for the ER supplement.


Question: nuclear reactor licensing

The licensing process for nuclear reactors involves a thorough review of safety, environmental impact, and operational plans to ensure compliance with regulatory standards.

The design of a cooling system must account for various thermal loads and ensure efficient heat transfer to maintain operational stability.


Question: nuclear regulatory licensing

The process of nuclear regulatory licensing involves a thorough review of an applicant's safety protocols and operational standards before granting permission to operate a nuclear facility.

The bibliography includes various sources and books that provide additional context and information for understanding nuclear safety, although they do not directly address the licensing process.


Question: What is TDS in groundwater analysis?

TDS (Total Dissolved Solids) is a measurement that indicates the total concentration of dissolved substances in water, typically reported in mg/L.

The sample matrix for the groundwater analysis includes parameters such as alkalinity, cations, and anions.


Question: TRITON11 fuel introduction

The TRITON11 fuel is designed for a broad spectrum of advanced reactor applications, ensuring optimal performance while meeting regulatory compliance requirements.

The reactor coolant system is critical for maintaining proper temperature and pressure during reactor operation, ensuring safety under various operating conditions.


Question: The Risk Informed Completion Time Program has been integrated into TS Section 5.5.18 for the ANO-1 site.

Entergy Operations Inc. (Entergy) requests adoption of TSTF-591, "Revise Risk Informed Completion Time (RICT) Program," which is an approved change to the Standard Technical Specifications (STS), into the Arkansas Nuclear One Units 1 and 2 (ANO-1/2), River Bend Station Unit 1 (RBS), Grand Gulf Nuclear Station Unit 1 (GGNS), and Waterford Steam Electric Station Unit 3 (WSES) Technical Specifications (TS).

Entergy has reviewed the safety evaluation for TSTF-591 provided to the Technical Specifications Task Force (TSTF) in a letter dated September 21, 2023 (Reference 1). This review included the NRC staff's evaluation, as well as the information provided in TSTF-591.


Question: The Essential Service Water (ESW) system is crucial for maintaining cooling during a plant shutdown.

The new intake structure will use Clinton Lake as a supply source and will have the capability to take water from the existing submerged UHS pond as an alternate source of make-up water to the safety-related Essential Service Water (ESW) cooling tower(s) for shutdown and to maintain cooling for a period of at least 30 days.

The drought analysis was completed based on the existing uprated CPS of 1,138.5-megawatts electric (MWe) boiling water reactor (BWR) operating at 100 percent of its rated capacity.


Question: radioactive material accountability

Material receipt follows the procedures outlined in the UCC Radiation Safety Manual (2019 edition) Section C: Ordering and Receiving of Radioactive Material.

All radioactive waste is collected periodically or on request of the AU and placed inside the dedicated waste storage room.


Question: What is the process for amendments in nuclear licensing?

The amendment process for a nuclear license involves a thorough review of proposed changes to the license, ensuring that all adjustments comply with regulatory standards and safety protocols.

Texas A&M University is seeking an amendment for their reactor but has not submitted any requests for additional safety training at this time.


Question: The NRC mandates that licensees must demonstrate compliance with safety standards along with site remediation efforts.

The FSS Release Record includes a detailed account of the survey conducted to assess the radiological condition of the site, demonstrating the licensee's adherence to regulatory requirements.

The documentation also highlights the steps taken during the initial phase of the remediation process, which includes the excavation of contaminated soil in the designated areas.


Question: hydrologic failure velocity

Figure 7 shows the Hydrologic Failure Velocity at 1/3/3000 23:00, indicating the time of maximum velocity at the Fort Calhoun Station site.

Figures 5-8 illustrate various aspects of the site design and layout for the Fort Calhoun Station.


Question: The examination process mandates the operator to monitor steam generator levels for any signs of rupture.

IF any S/G has level rising in an uncontrolled manner OR has high radiation, THEN ** GO TO 1-E-3, Steam Generator Tube Rupture.

All S/Gs narrow range levels CONTROLLED or DROPPING.


Question: transmitter calibration methodology

SNC is proposing to use the NRC-approved OLM methodology described in AMS-TR-0720R2-A. The use of the NRC-approved OLM methodology ensures that plant safety is maintained by demonstrating that transmitters are functioning correctly.

Switching from time-based surveillance frequency for channel calibrations to a condition-based calibration frequency will not create any physical changes to the plants.


Question: What is the status of the Oconee Nuclear Station units?

Duke Energy Carolinas, LLC; Duke Energy; Oconee Nuclear Station, Units 1, 2, and 3.

Endangered and Threatened Wildlife and Plants; Threatened Species Status for the Northern Long-Eared Bat With 4(d) Rule—Final Rule and Interim Rule with Request for Comments.


Question: recirculation transport fraction

a recirculation transport fraction of 100% was used for all fine debris types (see Table 3.e.6-5) regardless of the initial distribution in the pool.

The distribution of debris at the start of recirculation varies based on debris size and whether the debris was initially blown to the containment floor or washed down by containment sprays.


Question: What is the consumptive use of water for the AP1000 units?

Surface water consumptive use for the two AP1000 units’ normal operation is 29,125 gpm, with a maximum of 30,585 gpm. Groundwater consumptive use is 752 gpm on average, with a maximum of 3,140 gpm.

Current in-stream use of Savannah River water includes minimum stream flow requirements for navigation and environmental maintenance, and diversions for industrial use, including once-through cooling.


Question: ADVANCE Act regulatory issues for nuclear facilities

The purpose of this public meeting was to share and discuss information that may support the NRC’s response to Congressional direction in Section 206 of the ADVANCE Act.

The panel presentations, discussions, and public comments are summarized below.


Question: What is the role of the Director of Licensing in nuclear regulatory processes?

Kimberly Manzione, being duly sworn, deposes and says: That she has read the foregoing affidavit and the matters stated therein are true and correct to the best of her knowledge, information, and belief.

Executed at Camden, New Jersey, this 5th day of February, 2025.


Question: What is the purpose of a nuclear reactor license?

A nuclear reactor license is required to ensure that nuclear reactors operate in compliance with safety regulations and standards set by the regulatory body.

The testing of safety systems is critically important in the operational phase of any reactor.


Question: What is flow-accelerated corrosion in nuclear plant piping systems?

Wall thinning of steel, stainless steel, copper alloy, nickel alloy, and titanium piping and piping components exposed to treated borated water and raw water is managed by the DCPP Flow-Accelerated Corrosion AMP, which takes exception to NUREG-1801.

Consistent, with exception, with NUREG-1801.


Question: The simulation utilizes different algorithms to evaluate the health and flow rates of the system.

The algorithms were designed to handle generic configurations of components, meaning that the user can design arbitrary networks as long as the configuration is valid (i.e., there is a source, active pumps, and a sink).

At any given time during the simulation, the state of the plant can be defined by a fixed set of parameters (i.e., the on/off states of components, the quantity of debris stored by components, etc.).


Question: What does atmospheric stability class mean in the context of nuclear power?


Question: fuel storage rack assembly design

Figure 9-9. Fuel Storage Rack Assembly (Region 1) shows the configuration and key dimensions for the fuel storage racks utilized in the reactor containment structure, which are essential for ensuring safe and efficient storage of nuclear fuel assemblies.

The analysis included several scenarios focusing on potential impacts of seismic events on plant structures and equipment, detailing the required assessments to ensure compliance with safety standards.


Question: The area within a 50-mile radius of the Dresden Nuclear Power Station consists of various federal and state lands.

Figure 3.1-6 illustrates the Federal, State, and Local Lands within a 50-Mile Radius of DNPS.

The report outlines the findings of the environmental impact assessment conducted for the project.


Question: The report includes a table of nuclide activities measured in picocuries per gram, which helps in evaluating the nuclear safety levels.

The peak locate was performed with specific timings and channels that do not pertain to nuclide measurements.


Question: The NRC assesses the readiness of the plant for extreme seasonal weather conditions, particularly focusing on essential systems like service water and emergency feedwater.

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal low temperatures for the following systems: service water, primary component cooling water, emergency feedwater, and offsite power on December 11, 2024.

Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, “Light-Water Reactor Inspection Program - Operations Phase.”


Question: What methods are used to determine the uncertainty of flow elements in nuclear measurements?

The uncertainty of the flow elements is determined using the methods and equations in ASME PTC 19.1-1985, “Measurement Uncertainty,” ASME PTC 19.5-2004, “Flow Measurement,” and ASME MFC-3M-1989, “Measurement of Fluid Flow in Pipes Using Orifice, Nozzle, and Venturi.”

The total flow element uncertainty is considered a 2 sigma value.


Question: startup transformers operation

To demonstrate the energization of the startup transformers.

The performance of the startup transformers is in accordance with the design criteria and subsection 8.3.1.


Question: What are the surveillance requirements for diesel generators in nuclear plants?

Verify each DG: a. Starts from standby conditions and achieves steady state voltage ≥ 3740 V and ≤ 4243 V and frequency ≥ 58.8 Hz and ≤ 61.2 Hz; and b. Operates for ≥ 60 minutes at a load ≥ 256514710 kW and ≤ 285020090 kW.

Starting transients above the upper voltage limit do not invalidate this test.


Question: What is the Tornado Missile Protection concept in nuclear safety?

In this FAQ, the NRC evaluated if multiple tornado protection design issues identified over a period of time should be counted as a single issue/event for PI purposes or as multiple issues/events. These issues were the result of engineering work that did not comprehensively incorporate the tornado missile protection concepts into the structural design.

Only the first scram needed to be counted by the PI and subsequent scrams as a result of the Turbine Upgrade Project need not be reported separately.


Question: The site is located at the Westinghouse Columbia Fuel Fabrication Facility in South Carolina.

The Westinghouse Columbia Fuel Fabrication Facility is situated in Hopkins, South Carolina as indicated on the site location map.

The facility's property boundary is depicted on a seamless USGS topographic map, which is accessed through the ArcGIS Map Service.


Question: The foundation for the nitrogen storage tank is essential for supporting the tank and is part of a system critical for containment during purging activities.

The Nitrogen Storage Tank Foundation is a reinforced concrete slab that provides structural support for the Nitrogen Storage Tank.

The aging management review results for these components are provided in Table 3.5.2-23, Condensate Water Storage Tanks Foundations, Trenches, and Tunnels - Summary of Aging Management Evaluation.


Question: The NRC plans to use a list of essential items during the audit to gather the necessary information from the licensee.

The NRC staff will use an “audit items list” to identify the information (e.g., methodology, process information, and calculations) to be audited and the subjects of requested interviews and meetings.

The NRC staff acknowledges the importance of properly managing sensitive information in accordance with regulatory standards.


Question: The staff's consideration of land ownership when evaluating potential sites for the nuclear power plant was highlighted in their preliminary studies.

However, as pointed out on page 4.2-2 of the TVA DES and page 9-11 of the AEC DES, site ownership represented only one of many considerations used in performing preliminary siting studies.

The desired reserve margin to TVA is 20 percent which would provide a reliability index of one day's outage in ten years.


Question: What are the dimensions of the structural elements in the McGuire Nuclear Station tornado missile study?

- Diagram includes various structural elements


Question: What is a general license registration in nuclear regulation?

NRC will use this information to track general licenses and their devices to ensure a higher level of device accountability.

Estimated burden per response to comply with this mandatory collection request: 20 minutes.


Question: What is the impingement area of influence at Oconee Station?

The impingement AOI is the region extending outward from the intake screens in which impingeable-sized aquatic organisms (i.e., juvenile and adult fish and shellfish) would not be capable of overcoming the velocities created by water withdrawals at the cooling water intake structure and, thus, would have a higher probability of becoming impinged upon an intake screen.

Duke Energy proposes no changes to the cooling system and no changes to the amount of cooling water withdrawals as part of SLR.


Question: transportation network around Oconee Station

The transportation network surrounding the Oconee Station site is comprised of interstate, State highways, and local roads.

The nearest airport to Oconee Station is the Greenville-Spartanburg International Airport located east of Greenville, South Carolina.


Question: What is the role of the site Emergency Preparedness Manager in nuclear plants?

The site Emergency Preparedness Manager is responsible for coordinating the periodic reviews of the Emergency Plan.

Facility and support contact information in the emergency communications directory is verified annually and updated as needed.


Question: nuclear licensing applicability

The applicability of the regulatory requirements is determined by the specific design and operational characteristics of the facility.

The reactor operator must ensure that all staff are trained and prepared for emergency situations.


Question: What is the significance of the peak fuel centerline melt temperature in nuclear licensing?

The proposed license amendment would revise the MPS3 Technical Specification (TS) 2.1.1, "Safety Limit, Reactor Core," Safety Limit 2.1.1.2 to reflect the peak fuel centerline melt temperature specified in Topical Report WCAP-17642-P-A, Revision 1, "Westinghouse Performance Analysis and Design Model (PAD5)," dated November 2017 (ADAMS Accession No. ML17338A396).

The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.


Question: Licensees must demonstrate compliance with the regulatory requirements during the licensing process.

The licensing process for nuclear facilities requires extensive documentation and safety analysis to ensure all regulatory standards are met.

The reactor coolant system plays a crucial role in maintaining temperature and pressure during operation.


Question: The analysis of peak areas and uncertainties according to energy distribution is critical for ensuring accurate safety assessments.

Net Peak Area values are calculated along with Net Area Uncertainty to provide an understanding of the spectral data in nuclear applications.

Utilizing continuum counts is essential for ensuring that data from non-discrete energy interactions are accurately represented in modal analyses.


Question: What responsibilities does a Radiation Safety Officer have in a nuclear facility?

This Memorandum serves to formalize Christopher Bydlon’s appointment to the role of proHNS Radiation Safety Officer (RSO), and responsibility for ensuring the safe use of radiation by proHNS personnel. This role is also responsible for managing the proHNS Radiation Protection Program; identifying radiation protection problems; initiating, recommending, or providing corrective actions; verifying implementation of corrective actions; stopping unsafe activities; and ensuring compliance with regulations.

In addition, Chris is free to raise issues with the U.S. Nuclear Regulatory Commission (NRC) at any time.


Question: jet pump riser clamps

Reactor Vessel Internals Components (Jet Pump Riser Clamps) | Structural Support | Stainless Steel| Reactor Coolant and Neutron Flux | Loss of material due to pitting, crevice corrosion | Water Chemistry (B.2.12) | IV.B1.RP-26 | 3.1-1, 043 | A

Reactor Vessel Internals Components (Jet Pump Slip Joint Clamps) | Structural Support | Nickel alloy | Reactor Coolant and Neutron Flux | Loss of material due to pitting, crevice corrosion | BWR Vessel Internals (B.2.17) | IV.B1.RP-26 | 3.1-1, 043 | E, 1


Question: spent nuclear fuel storage

Waste Management | Onsite storage of spent nuclear fuel(a) | SMALL


Question: What is the method of qualification used in testing or analysis for equipment?

Method of qualification used: a. Analysis or test b. If by test describe whether single or multi-frequency test and whether input was single or bi-axial c. If by analysis, describe whether static or dynamic analysis. Present natural frequency of equipment.

A brief meeting is held at the beginning of a site visit with the following agenda:


Question: The mechanical and thermal analysis considers the impact of cladding characteristics on reactor performance...

Cladding thinning due to corrosion is taken into account in the mechanical and thermal processes by evolution of the metal/oxide interface position and the corresponding state of internal variables (re-meshing transformation).

Complete information on GALILEO code can be found in the GALILEO Theory Manual, Reference 6.


Question: station blackout regulations

The NRC regulations in 10 CFR 50.63 require that light-water-cooled nuclear power plants licensed under 10 CFR Part 50 or Part 52 be able to withstand, for a specified duration, and recover from a station blackout.

The NRC staff finds that these provisions, as described in NEDC-33911P, are consistent with GDC 1, and therefore, are acceptable.


Question: What is the role of the reactor coolant pressure boundary (RCPB) in leakage detection?

Leakage from the reactor coolant pressure boundary (RCPB) to the containment atmosphere is detected and is indicated in the main control room by one or more of the following methods: 1. Containment gaseous radioactivity monitor (measurement range: 10⁶ cpm). 2. Containment particulate radioactivity monitor (measurement range: 10-10⁶ cpm). 3. Containment structure leakage monitoring system. 4. Containment sump monitoring. 5. Reactor coolant system makeup rate.

In general, all of the material listed in Tables 5.2-22 and 5.2-23 that are used in principal pressure-retaining applications and are subject to elevated temperature during system operation are in contact with thermal insulation that covers their outer surfaces.


Question: What is the significance of the sprayed containment volume in nuclear safety assessments?

The sprayed containment volume to environment is critical for evaluating the effectiveness of systems designed to mitigate the release of radioactive materials during an accident.

The Overlaying Pool value represents the cumulative activity concentration of radioisotopes in the pool during various operational scenarios.


Question: The NRC mandates the evaluation of the reactor shutdown margin to ensure safety protocols are maintained.

The determination of reactor shutdown margin is an essential safety analysis performed to verify that the reactor can be brought to a safe shutdown state under all operational conditions.

The calibration of nuclear instrumentation systems is critical for ensuring the accuracy of measurements in nuclear facilities.


Question: LOCA heat transfer tests


Question: What are the implications of decommissioning funding shortfalls for nuclear plant safety?

We have long held that concerns regarding funding shortfalls can in some circumstances provide the basis for a showing of harm because NRC regulations “recognize that underfunding can affect plant safety.”

Exelon disputes ELPC’s standing. It argues that ELPC cannot demonstrate proximity-based standing through its member, Mr. Vogl, because the proposed action involves “no change in the operator, no change in the direct owner, and no change in the physical plant.”


Question: What are the surveillance requirements for TSC surface contamination?

SR 3.3.2 Verify by either direct or indirect methods that the removable contamination on the exterior surfaces of the TSC is within limits.

The table lists the frequency of surveillance required for various operational activities in nuclear facilities.


Question: BWRVIP guideline for advanced manufacturing processes

In order to allow the use of materials fabricated by advanced processes, some form of qualification or demonstration is necessary as documented in a technical basis report.

The requirements shall implement the guidelines within two refueling outages, unless a different schedule is identified by the BWRVIP at the time of document distribution.


Question: nuclear service water system

NUCLEAR SERVICE WATER FROM REACTOR COOLANT PUMP

Test Pressure Direction refers to the orientation in which pressure is applied during testing; it does not denote any specific operational parameters of the system.


Question: The candidate must evaluate the circulating water inlet temperature as part of the procedure requirements.

Calculates and records average Circulating Water inlet temperature as 46°F [(44+46+45+49)/4].

Calculates and records average Screenwell intake temperature as 45°F [(43+47)/2].


Question: What is the minimum initial assembly average enrichment for PWR fuel?

**Minimum Initial Assembly Avg. Enrichment wt % 235U (E)** values for 50 < Assembly Average Burnup ≤ 51 GWd/MTU are provided with corresponding Minimum Cooling Times for various assembly designs.

The NRC regulations require a robust understanding of reactor core dynamics and associated risk assessments in order to ensure public safety.


Question: The NRC mandates updates to the facility operating license based on regulatory changes.

Replace the following pages of the License and Appendix A Technical Specifications (TSs) with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.


Question: The NRC assesses seismic data from various regions to determine potential hazards.

Seismotectonic Source Zones are regions where identifiable geologic structures influence ground motions from earthquakes, contributing to the seismic risk assessments conducted by the NRC.

The Atlantic Highly Extended Crust is a geological feature that influences sedimentation patterns in related coastal areas.


Question: what is a fuel assembly in nuclear reactors?

A fuel assembly is a grouping of nuclear fuel rods, which are used in a reactor to create a sustained nuclear chain reaction for power generation.

The cooling system of a reactor is crucial to maintaining safe operating temperatures and preventing overheating during normal and emergency conditions.


Question: statistical departure from nucleate boiling design limits

The development of statistical departure from nucleate boiling design limits is a critical aspect in ensuring reactor safety and performance during normal and faulted conditions.

In addition to these operational considerations, the maintenance of auxiliary systems such as cooling towers and the electrical distribution network is essential for overall plant reliability.


Question: What happens when a GSE trip instrumentation channel is found to be inoperable?

However, the Required Actions for inoperable GSE trip instrumentation channels provide appropriate compensatory measures for separate inoperable channels.

A Note has been provided to modify the ACTIONS related to GSE trip instrumentation channels.


Question: The factors of safety for the Allowable Strength Design method were selected to align the reliability indices with the Load and Resistance Factor Design approach.

For the Allowable Strength Design method, which uses the same limit states and same limit state strength as the LRFD, the factors of safety were chosen in order to obtain reliability indices as close as possible as those obtained with the LRFD while using load factors as close as possible to 1.0 for the load combinations.

The 2005 AISC 360 Specification defines the Allowable Strength Design and Load and Resistance Factor Design methods, establishing a framework for the application of safety factors and resistance factors.


Question: What are cost estimate classifications in a nuclear regulatory context?

Cost estimate classifications may be used with any type of project or work and may include consideration of: (1) where a project stands in its life cycle, (2) level of definition (amount of information available), (3) techniques to be used in the estimation (e.g., parametric vs. definitive), and (4) time constraints and other estimating variables.

Conduct an independent review of an estimate as a crucial step to establishing confidence in the estimate. Ensure that the independent reviewer verifies, modifies, and validates an estimate to ensure realism, completeness, and consistency.


Question: What is the purpose of a safety analysis report in nuclear licensing?

A Safety Analysis Report (SAR) must demonstrate that the design and operation of the nuclear facility will comply with the applicable regulatory requirements and safety standards.

The cooling system in the reactor is designed to maintain optimal temperatures during operation, ensuring efficiency and safety.


Question: What is the role of the Division of Licensing in nuclear reactor regulation?

The Division of Licensing, Siting, and Environmental Analysis (DLSE) is responsible for reviewing applications for licenses and permits for nuclear reactors and conducting safety evaluations to ensure compliance with regulatory standards.

Rockville, Maryland is a well-regarded location known for its vibrant community and rich history, featuring a mix of dining, shopping, and recreational activities.


Question: temperature monitoring stations

Observed Seasonal Average Vertical Temperature Profiles at Monitoring Station A Near North Anna Dam


Question: nuclear power plant operating license renewal

As explained in the introduction to Chapter 2 of this EIS, the NRC's license renewal decision-making authority is limited to deciding whether to renew the operating license. The purpose and need for renewing an operating license is to provide the option for power generation capability beyond the term of the current nuclear power plant operating license to meet future system generating needs.

The comments take issue with NRC's analysis of reasonable alternatives in this EIS, including the environmental impacts and the rationale for eliminating alternatives as not reasonable.


Question: What is the minimum cooling time required for spent nuclear fuel assemblies?

Minimum Cooling Time (years) refers to the required period that spent nuclear fuel assemblies must cool before they can be safely handled or transferred.

Nuclear plants rely on various systems that ensure safety and efficiency in their operations, such as reactor coolant systems and emergency core cooling systems.


Question: What are the requirements regarding the enrichment and cooling times for CE 16x16 fuel assemblies?

The safety systems in nuclear reactors are designed to prevent accidents and mitigate the consequences of any potential incidents.


Question: What are the payment procedures for nuclear regulatory fees?

The NRC also currently accepts credit card payments of up to $24,999.99.

For NRC debt collection procedures, including interest and penalty provisions, see 31 U.S.C. 3717; 31 CFR Parts 900 - 904; AND 10 CFR Part 15.


Question: What are the acceptable concentration levels for Pb-210 and Th-230 in monitoring wells?

Pb-210 ACL = 62 pCi/L
Th-230 ACL = 945 pCi/L

Concentrations that are less than the lower level of detection (LLD) are represented by an open symbol.


Question: minimum detectable concentration

The Company specializes in a range of analytical services for various industries.


Question: The NRC mandates that operators assess seismic hazards to ensure safety during earthquakes.

General Terms regarding Earthquake Intensity and Magnitude provide a framework for understanding seismic events that may affect nuclear facilities.

Table 3.4-2 presents detailed water quality analysis for the Gallup Sandstone Aquifer near the Crownpoint and Unit 1 Project Areas.


Question: The regulatory review of proposed technical specifications is a critical part of ensuring safety and compliance in nuclear plant operations.

The online monitoring program is defined under Technical Specification 5.5.21, which details the requirements for real-time assessment of reactor systems.

The quarterly financial report provides insights into the plant's operational costs and efficiencies, which are important for investment decisions.


Question: A robust quality control process is essential for ensuring compliance with safety regulations in nuclear facilities.

The quality control program ensures that the measures taken are effective in verifying the compliance of the safety-related systems with regulatory requirements.

Regular maintenance checks of the reactor cooling system are critical to prevent overheating and ensure safe operation.


Question: The surrounding regions of the North Anna Power Station include areas with limited population density.

The 6 Mile Low Population Zone surrounding the North Anna Power Station is designed to ensure that a low number of residents inhabit the area in the event of an emergency.

The figure shows various transportation routes, including roads and railroads, surrounding the North Anna Power Station.


Question: NIST traceable calibration

All instrumentation is calibrated in accordance with the QAP to meet the criteria of ANSI N323AB-2013.

Calibration Certificate for 44-9, Serial # PR182920, Bar Code #, Property # Chase213.


Question: Framatome small break loss-of-coolant accident evaluation methodologies

The Millstone Power Station, Unit No. 3 is seeking a license amendment request to employ Framatome small break and realistic large break loss-of-coolant accident evaluation methodologies for establishing core operating limits.

The regulatory audit revealed several key points that will impact future assessments and compliance measures for plant operation.


Question: What are the visual resources associated with DNPS?

Predominant visual features at DNPS include the Units 2 and 3 reactor containment building, turbine building, Unit 1 containment sphere, two chimneys, and transmission lines.

The plan is designed to encourage agricultural uses as economically desirable businesses and to preserve historical rural patterns, discourage encroachment of development into rural areas, and protect the natural environment.


Question: The distribution of various readings in relation to the sectors indicates important safety metrics for reactor operation.

The SSW sector is responsible for analyzing data collected from sensors in order to evaluate the safety performance of the reactor system.

In the context of operational efficiency, the data readings show a consistent trend across several sectors, suggesting a stable performance at the facility.


Question: recirculation sump design requirements

A solid top deck is preferable, and the top deck should be designed to be fully submerged for LCOA and completion of the safety function.

The trash rack and screens should be designed to withstand the vibrations of seismic events without compromising structural integrity.


Question: Uranium isotopes in soil analysis

The following Analytical Methods were performed:
| Method | Description         | Analyst Comments      |
|--------|---------------------|-----------------------|
| 1      | SW846 9056A        |                       |


Question: The documents relating to quality assurance are treated under the established Records Management Program.

The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following: A. Completed parts of Sections 4.0, 6.0, and 7.0. B. Section 5.0. C. Surveillance Task Sheet. D. Other sheets added during the performance.


Question: What is the role of Reactor pressure control during inadvertent containment isolation?

The plant is operating at 100% power when I&C inadvertently causes PCIS Group 1 isolation signals on both channels of Division II, only. Which one of the following describes the resulting Reactor pressure control?

Reactor pressure will be controlled… A. by SRVs due to closure of the inboard MSIVs.


Question: The assembly average enrichment must be carefully calculated to ensure compliance with regulatory requirements.

The certification process ensures that all components are evaluated for safety and reliability.


Question: power spectral density in nuclear safety

Figure 2 illustrates the Frequency [Hz] response of the containment structure, including the ±20% Rolling Average PSDs for TH_UHRSF_X_PSD_RA (blue line), TH_UHRSF_Y_PSD_RA (orange line), and TH_UHRSF_Z_PSD_RA (red line).

The containment structure is critical for ensuring the safety of nuclear reactor operations during normal and emergency conditions.


Question: nuclide activity report


Question: fire protection acceptance specification

MCS-1435.00-00-0001, “Fire Protection Acceptance Specification.”


Question: What is the Minimum Detectable Activity (MDA) for a nuclide?

The Minimum Detectable Activity (MDA) for a nuclide is defined as the lowest activity level that can be reliably distinguished from background noise in a measurement, expressed in pCi/grams.

The total yield percentage indicates the efficiency of capturing the emitted radiation from a sample and is an important factor in gamma spectroscopy.


Question: What is the intended function of piping components in the Emergency Equipment Cooling Water System?

The intended function of piping components, including those in the Emergency Equipment Cooling Water System, is to act as a pressure boundary.

The notes in the table do not indicate any specific details regarding environmental conditions affecting the components.


Question: What is the purpose of the ICCA Closure Lid in reactor tests?

Figure 2.10.1-74 illustrates a close-up view of the damaged ICCA closure lid after post-test disassembly.

The regulatory process for reactor licensing involves numerous steps including application submission, technical review, and public comment periods.


Question: radioactive effluent release report

Results submitted to the NRC in the annual Radioactive Effluent Release Report; air sampling station material condition and whether maintained as required in the ODCM; assessments performed in accordance with the voluntary Groundwater Protection Initiative; records and procedures associated with 10 CFR 50.75(g); results of the licensee's inter-laboratory comparison program.

The inspectors verified that when issues were identified, licensee personnel appropriately documented the issue in the CAP.


Question: What is the process of hydrologic dam failure in nuclear safety assessments?

Precipitation Driven Hydrologic Dam Failure – Stage-Flow Hydrograph at PBAPS … 110

Combined Model and Observed Hydrographs for Hurricane Agnes … 88


Question: What is the requirement for conducting minimum staffing drills in nuclear emergency response?

An ERO minimum staffing (no participation of non-minimum augmenting ERO personnel) drill is conducted at least once during every eight-year exercise cycle.

The proposed emergency plan specifies that off-hours call-in drill be performed biennially.


Question: What are the license numbers for Arkansas Nuclear One?

The power output of a nuclear reactor can vary significantly based on operational conditions.


Question: What is the significance of remote alignment capability in nuclear safety systems?

Provide remote alignment capability of RHRSW to the LPCS system for LOCA mitigation.

Quantitatively evaluate Automatic Suppression Pool cooling.


Question: The licensees are obligated to provide regular reports to the NRC about their radiation safety protocols.

Radiation Safety Officer / RSO-USNRC, RML 05-35250-01 / RSO-CA, RML 8099-38

All opinions or other information in this email that do not relate to the official business of Arcadis are neither given nor endorsed by it.


Question: What are the requirements for evaluating nuclear reactor safety and operational risks?

The evaluation of nuclear reactor safety encompasses comprehensive analyses of potential operational risks and failures, focusing on the reliability of safety systems and the integrity of the nuclear plant infrastructure.

The documentation provides various charts and figures that illustrate the layout and design specifications of the reactor containment building, emphasizing its structural features and material properties.


Question: circuit failure mode likelihood analysis

NUREG/CR-6850 identifies the primary sources of uncertainty associated with this task to include the technical quality issues:

The use of hot short failure probability and duration probability is based on fire test data and associated consensus methodology published in NUREG-7150, Volume 2.


Question: Liquid Process Radiation Monitor

Liquid Process Radiation Monitor Channel/Recorder Check


Question: What are the surveillance requirements for the UHS in a nuclear facility?

This SR verifies that adequate long term (30 day) cooling can be maintained. The specified level also ensures that sufficient NPSH is available to operate the SX pumps.

If the UHS is inoperable for reasons other than Condition A, the unit must be placed in a MODE in which the LCO does not apply.


Question: The ESFAS is responsible for initiating safety systems based on conditions of selected equipment parameters.

The ESFAS initiates necessary safety systems, based on the values of selected equipment parameters, to protect against violation of specific design limits and to mitigate accidents.

The Control Element Drive Mechanism Control System (CEDMCS) is placed in and subsequently maintained in the "OFF" mode except during CEA motion permitted by a) above, when the CEDMCS may be operated in either the "Manual Group" or "Manual Individual" mode.


Question: The operator must notify the local emergency management authorities for an effective emergency plan during a nuclear incident.

Terminate JPM when operator completes notification to KENT COUNTY.

The table outlines various steps and standards necessary for the effective execution of job performance measures.


Question: transmission of TER

We have not received the final TER from PNNL per the contract. At that time, we will inform you of the next steps.

The NRC staff plans to review the information transmitted via BOX on 5/4/23, that was presented for L&C 18.


Question: What is the function of the letdown line in nuclear systems?

The letdown line is an important system in nuclear reactors that allows for the removal of excess water from the primary cooling system, ensuring the pressure and temperature remain stable during operation.

The reactor makeup water tank is designed to supply water to the reactor systems when needed, which is crucial for maintaining the balance of water levels in the primary system during operation.


Question: What are the requirements for posting a Notice of Violation in accordance with NRC regulations?

In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days of receipt.

Proprietary, or safeguards information so that it can be made publicly available without redaction.


Question: The agency's licensing process for materials requires compliance with regulatory requirements to ensure safety and prevent misuse.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.

Sincerely,

Bryan A. Parker
Senior Health Physicist
Materials Licensing Branch

License No. 21-32190-01MD
Docket No. 030-35125
Enclosure: Amendment No. 22


Question: nuclear medicine injection extravasations

Reporting nuclear medicine injection extravasations as medical events is essential for ensuring patient safety and regulatory compliance.

Please provide feedback on the proposed changes to Title 10 of the Code of Federal Regulations.


Question: What is the purpose of the Liquid Radwaste System in nuclear reactors?

The LRS is relied upon to support the critical safety function of containment integrity. There are valves and piping within the LRS that function to provide containment isolation.

Table 2.3.3-17 lists the LRS component types that require an AMR and their associated component intended functions.


Question: The NRC examines ecological impacts during regulatory assessments of facilities.

The habitat requirements for species of conservation concern play an important role in the environmental assessment of the facility.

The table lists the scientific names of various plant species that have specific habitat needs.


Question: What is the role of AMSAC Train A in the AFW system?

The 21 AFW receives an AUTOMATIC start signal when AMSAC Train A actuates.

The candidate could not understand how AMSAC circuitry works and incorrectly conclude that ALL AFW pumps receive an AUTOMATIC start signal.


Question: What is the impact of air ingestion on the RHR system's performance?

A specific relationship exists between air ingestion into the RHR system and hot leg level with this relationship being flow rate.

Differences exist in RCS levels between active cold legs, inactive cold legs, active hot legs, and inactive hot legs during partial loop operations.


Question: What is the RPS failure probability for the ARC-100 reactor?

Reference [15] calculated the probability / frequency of ARC-100 RPS failure to shutdown the reactor. Two (2) cases were analyzed: 1. It was assumed that the primary control rod with the maximum worth had been withdrawn / ejected prior to the signal to activate the RPS and 2. It was assumed that upon receiving the signal to activate the RPS all primary control rods were in their normal BOL operating positions.

The analysis was conservatively performed using the BOL rod worths and shutdown worth requirement. At MOL and EOL the rods have more worth and the shutdown worth requirement is less.


Question: subsequent license renewal environmental impacts

the 2013 GEIS did not consider the impacts from operations during the subsequent license renewal period and applicants for subsequent license renewal must evaluate Category 1 impacts in their environmental reports.

The public will also have an opportunity to comment during the development of the site-specific environmental impact statements.


Question: The NRC emphasizes the importance of evaluating water availability for nuclear power site licensing to ensure safety and operational efficiency.

American National Standard *Evaluation of Surface-Water Supplies for Nuclear Power Sites*, American Nuclear Society, November 5, 1979.

The U.S. Army Corps of Engineers developed numerous plans for managing drought conditions in the Savannah River Basin.


Question: thermal impacts on aquatic organisms

the NRC found that thermal impacts have not been a problem at plants that use closed-cycle cooling with cooling towers because of their smaller thermal plumes.

TVA has no plans for refurbishment activities or modifications beyond normal maintenance at BFN associated with SLR.


Question: The NRC assesses ecological impacts by characterizing terrestrial plant communities within affected areas.

Qualitative surveys characterizing the presence of terrestrial plant communities and vascular plant species within the ecological study area were performed during seasonal field surveys in 2021 and 2022.

Most of the land cover on the HCS is characterized by herbaceous cover (105.2 ac. [42.6 ha]). Mixed forest comprises the second greatest land cover category (4.8 ac. [1.9 ha]), and the remaining 0.2 ac. (0.1 ha) is evergreen forest.


Question: nuclide minimum detectable activity

Nuclide MDA (Minimum Detectable Activity) is listed in the report as the activity level at which a nuclide can be reliably detected.

Errors quoted at 2.000sigma suggest the level of statistical confidence in the measurements made during the analysis.


Question: What is the unit of measurement typically used for isotopes in nuclear devices?

| Isotope (e.g. AM241) | Activity (e.g. 1005) | Unit (e.g. mCi) |

Our records indicate that you have these devices. Please update the information as necessary.


Question: boron dilution method

The boron dilution method: The RRV's, attached to the RPV, point downward in the containment annular space, while when borated liquid transports out of the core and riser region into the downcomer through the lower riser holes, that compares to the critical boron concentration.

Figure 1 illustrates the layout of the containment structure, emphasizing the importance of ensuring structural integrity during seismic events.


Question: What is the concept of Defense-in-Depth in nuclear facility design?

An approach to designing and operating nuclear facilities that prevents and mitigates accidents that release radiation or hazardous materials. The key is creating multiple independent and redundant layers of defense to compensate for potential human and mechanical failures so that no single layer, no matter how robust, is exclusively relied upon. Defense-in-depth includes the use of access controls, physical barriers, redundant and diverse key safety functions, and emergency response measures.

Documentation for a specific application showing that the required pressure ratings, qualification loading levels, and operating condition capabilities are equal to or exceeded by the corresponding pressure ratings, qualification loadings, and operating condition capabilities shown in the Qualification Report.


Question: What are Framatome's registered trademarks?

ARCADIA, AREA, ARITA, ARTEMIS, COBRA-FLX, GAIA, GALILEO, M5, ORFEO, and S-RELAP5 are trademarks or registered trademarks of Framatome or its affiliates, in the USA or other countries.

The reactor's cooling system was designed to enhance thermal efficiency and improve safety margins during operation.


Question: zirconium-steam reaction rates

In the investigation, the zirconium-steam reaction rates that occurred in the experiment were under-predicted. The investigators concluded that the “application of the available Zircaloy oxidation kinetics models [zirconium-steam reaction correlations] causes the low-temperature [1652-2192°F] oxidation to be underpredicted.”

In fact, the ORNL paper’s authors employed “a simple multiplicative factor (function of strain) to enhance the [predicted] zirconium oxidation for CORA-16.”


Question: quench spray flow rate

QUENCH SPRAY FLOW RATE (GPM) is a critical parameter that describes the flow rate of quench spray during an emergency situation, measured in gallons per minute. This flow rate is important for assessing the cooling effectiveness of the spray in the event of a loss-of-coolant accident (LOCA).

The data shows a steady decline in temperatures during the initial stages of the cooling cycle, indicating that the emergency safety features are operating within expected parameters.


Question: The determination of whether continued operation of the nuclear power plant will have adverse effects on federally listed species is crucial for licensing.

Effects from license renewal is characterized based on a determination of whether continued nuclear power plant operations, including refurbishment, would have no effect on federally listed species; are not likely to adversely affect federally listed species; are likely to adversely affect federally listed species; or are likely to jeopardize a federally listed species or adversely modify designated critical habitat.

Impacts are based on disproportionately high and adverse human health and environmental effects on minority and low-income populations.


Question: The NRC assesses potential environmental impacts associated with the transportation of nuclear waste.

Environmental Impact of Accidents during Transportation of Fuel and Waste

Projecting future energy demands for the TVA system is critical for sustainable growth.


Question: The NRC guidelines require clarity in presenting activity measurements for various nuclides.


Question: mean wet bulb temperature

The requirement is for only a mean coincident WBT value. A mean WBT value is simply identified for any DBT value on the graph, therefore a set of such means is easily plotted, and form the basis for an extrapolation line.

Trends in global climatic conditions are currently the subject of considerable discussion in the scientific community and in the media.


Question: What is the significance of analyzing debris on the wear or blockage of ECCS and CSS components?

An analysis bounding all break sizes was performed to evaluate the impact of debris on the wear or blockage of the ECCS and CSS piping and components downstream of the strainer following a LOCA.

An aluminum solubility correlation, developed by Argonne National Laboratory, was used to determine a maximum precipitate formation temperature, which effectively delays the onset of aluminum precipitation when analyzing strainer head loss.


Question: The U.S. Nuclear Regulatory Commission has been requested to keep specific information private due to its proprietary nature.

This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.

I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary.


Question: The application for the subsequent license renewal requires comprehensive review and consideration of environmental impacts.

The NRC Request for Concurrence with Endangered Species Act Determinations for Oconee Nuclear Station, Units 1, 2, and 3, is a critical regulatory step in the license renewal process.

Electricity Annual Technology Baseline (ATB) Data provides important insights into the evolution of technology and its impact on energy production.


Question: What is CVCS valve manipulation?

In accordance with MA-AA-716-004 (CONDUCT OF TROUBLESHOOTING), manipulation of CVCS valves to support the troubleshooting plan is considered a(n) intrusive activity.

Troubleshooting activities are in progress on CVCS.


Question: The NRC stipulates that the reactor's core average temperature must be closely monitored during operations.

Core Average Temperature (°F) is an important parameter that influences reactor performance and safety margins in Nuclear Reactor operations.

Vogtle Electric Generating Plant is undergoing significant upgrades to enhance its operational capacity and safety features.


Question: nuclear safety system requirements

The safety system requirements delineate the necessary protocols and measures to ensure that the nuclear plant operates within safe operational limits and adheres to regulatory standards.

The reactor pressure vessel plays a crucial role in containing the nuclear reaction and maintaining appropriate pressure levels during operation.


Question: The regulation of radionuclides in solid matrices is essential for ensuring safety during waste disposal processes.

Americium-241 is measured in pCi/g as part of the Rad Alpha Spec Analysis to ensure compliance with safety standards.

The Rad Gamma Spec Analysis for Nickel-59 shows a result of -1.29 pCi/g with an uncertainty of +/−1.91.


Question: The analysis of the fission gas release is crucial for understanding the reactor performance and safety measures.

Fission gas release models are essential for predicting the behavior of nuclear fuel during temperature ramps, as indicated by the lower-bound and upper-bound models shown in Figures 29-16 and 29-17.

The inspection of safety systems ensures that the reactor operates within the established regulatory framework and maintains public confidence in nuclear power.


Question: wind speed correlation analysis

To some degree the high coefficients of determination in Figures 10 and 11 may reflect the averaging effect of the 5-year and the 15-year periods (even though these periods are separated by two or three decades).


Question: During the startup phase, the behavior of control rods is carefully monitored to ensure safe operations.


Question: nuclear licensing process

The nuclear licensing process involves several steps including application submission, safety reviews, and regulatory approval to ensure that all safety and environmental standards are met before operations can commence.

In analyzing the structural integrity of the reactor, it is crucial to consider both the materials used and the conditions under which they will operate, including temperature, pressure, and radiation exposure.


Question: What is ESW cooling in nuclear power plants?

ESW cooling alignment is performed in accordance with expectations for procedure use and adherence.

The crew has recovered power to the A train.


Question: license renewal application

The Browns Ferry Nuclear Plant Units 1, 2, and 3 are undergoing a license renewal regulatory scope audit regarding the environmental review of the license renewal application, as documented in EPID number L-2024-SLE-0000.

The audit process requires the involvement of multiple stakeholders to ensure that all regulatory requirements are met.


Question: What is fiber penetration testing in nuclear safety?

Wolf Creek conducted fiber penetration testing in 2016 at Alden Research Laboratory (Alden). The purpose of the testing was to collect time-dependent fiber penetration data of the prototypical strainer.

The test loop used for fiber penetration testing is similar to that for head loss testing (see the Response to 3.f.4). The closed test loop included a metal test tank with acrylic windows that housed a test strainer submerged in water.


Question: The NRC evaluates the potential necessity for protective actions and informs the public accordingly.

G. Evaluate protective action recommendations and authorize public notification (Use Attachment 2 when appropriate).

The design of the reactor incorporates advanced safety features to prevent core meltdown during unforeseen circumstances.


Question: What is the minimum cooling time for reactor fuel assemblies?

The minimum cooling time for reactor fuel assemblies is specified in terms of years, depending on the enrichment weight percentage of U-235 in the assembly and its average burnup.

The loading table for PWR Fuel lists various initial assembly average burnup values along with their corresponding enrichment levels.


Question: What are the principal design criteria for the Xe-100 reactor?

The Xe-100 reactor is designed to meet specific principal design criteria that ensure safety and regulatory compliance.

The project phase of the Xe-100 is classified as Basic and highlights the initial stages of development.


Question: What is the function of the APRM in reactor protection systems?

1) Automatic Initiation: APRM/Oscillation Power Range Monitor Upscale Trip, Vessel Water Level (L8) Trip, Turbine Stop Valve (TSV) Trip

Similar to Trip of One Recirculation Pump


Question: The movement of ground water is influenced by natural factors, including recharge areas and environmental conditions, along with human activities like the pumping of wells.

Ground-water movement through aquifers and relatively permeable confining beds is controlled by natural features such as locations of recharge and discharge areas, rainfall and rainfall departure, and other climatic events, such as rainfall duration and intensity, and stratigraphic relationships of adjacent strata, and the hydraulic properties of these strata.

Several tracts of farmland south of Sunset Lake and west of the site are utilized during the farming season, but there is no ground-water pumpage in these areas.


Question: What are the calculations involved in determining flow in GPM and its relationship with pressure?

The flow calculation is given by the equation Q = c \sqrt{\Delta P}, where \(\Delta P\) is a value in inches of H₂O, Q is the flow in GPM, and C is a constant of proportionality.

The safe working pressures for Barton Model 581A pressure switches that meet the specifications listed in Reference 47 are 3000 psig which is consistent with the design pressure of 1500 psig at 400°F at the orifice plate location (Ref. 23).


Question: What is the role of the Emergency Response Organization in nuclear plant operations?

The non-minimum augmenting ERO will continue to be available and respond to declared emergencies.

NextEra station and corporate personnel can be called as "as needed" to support ERO response activities.


Question: surveillance frequency control program

In accordance with the Surveillance Frequency Control Program

Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.


Question: What are the proposed regulations in PRM-50-93 and PRM-50-95?

If implemented, the regulations proposed in PRM-50-93 and PRM-50-95 would help improve public and plant-worker safety.

Respectfully submitted, Mark Edward Leyse P.O. Box 1314 New York, NY 10025 markleyse@gmail.com


Question: corrective action program nuclear

The corrective action program at the Palo Verde Nuclear Generating Station is designed to identify, evaluate, and address issues that have the potential to affect safety and compliance.

Organization charts for plant staff and long-term/permanent contractors are essential for understanding the structure of the workforce and roles within the facility.


Question: loss of material in nuclear components

Aging Effect Requiring Management | Loss of Material

Hatch - Emergency Airlock    | Structural Support, Structural Pressure Boundary, Shielding | Carbon Steel      | Plant Indoor Air (Structural) (Ext)      | Loss of Leak Tightness


Question: scenario event descriptions

The scenario guide event description incorrectly designates an event as a critical task (i.e., a noncritical task labeled as critical or a critical task labeled as noncritical). This includes critical tasks that do not meet the critical task criteria (i.e., the critical task does not have a measurable performance standard) (U).

Review the individual events contained in each scenario, and identify and mark event errors:


Question: What is the average enrichment level for BWR fuel assemblies?

The loading table for BWR Fuel – 360 W/Assembly shows various average enrichment levels, including 11.8 wt % 235U for the enrichment range of 2.9 ≤ E < 3.1.

The loading table also includes data for different initial assemblies with different configurations, such as 7x7 and 8x8, representing the fuel assembly designs.


Question: NRC license application process

In accordance with 10 CFR 2.390 of NRC's “Rules of Practice,” a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at [www.nrc.gov/reading-rm/adams.html](http://www.nrc.gov/reading-rm/adams.html).

Sincerely, Jason M. Kelly, MPH Health Physicist Materials Licensing Branch


Question: non-loss-of-coolant accident analysis

Specific design features that differ between NPM designs do not change the methodology used to model important parts of the design for non-loss-of-coolant accident (non-LOCA) analysis.

The figures and descriptions provided in TR-0516-49416-P, Revision 4, "Non-Loss-of-Coolant Accident Analysis Methodology," are intended to be typical descriptions of the NuScale NRELAP5 plant model that is not specific to the details of the NuScale Power Module (NPM) that may vary between the NPM-160 and NPM-20.


Question: nuclide identification

Nuclide identified during the nuclide identification

Half-life too short to be able to perform the decay correction


Question: nuclear licensing amendments

Community Stroke and Rehabilitation Center received an amendment under license number 13-35525-01 on 01/16/2020.

University of Southern Indiana is licensed with license number 13-32233-01 which was received on 08/31/2020.


Question: What is a Defense in Depth and Diversity Common strategy in nuclear safety?

The Defense in Depth and Diversity Common strategy involves multiple layers of safety controls and diverse means of managing potential failures to ensure the reliability of safety systems.

Westinghouse Non-Proprietary Class 3 documentation provides guidelines on the configuration and operation of nuclear reactors, but it does not specifically address any safety strategies.


Question: What is the significance of the nuclide Am-241 in nuclear regulatory contexts?

The nuclide Am-241 has an activity of 1.15E-01 pCi/grams and a minimum detectable activity (MDA) of 2.68E-01 pCi/grams, which makes it significant for various radiological assessments.

In the context of regulatory filings, it is crucial to analyze the different units of measurement used in documenting radiation exposure levels and to ensure compliance with safety standards.


Question: impact closure lid testing

Figure 2.12.1-10 shows a close-up view of Impact Closure Lid utilized in the puncture drop test, demonstrating its design and structural integrity under stress conditions.

The cooling system employed in the reactor operates by circulating water through the core to remove heat generated during fission.


Question: What happens to the reactor when instrument air pressure decreases significantly?

In a short period of time, the reactor will trip due to low-low steam generator levels.


Question: In the event of an emergency, Field Monitoring Teams are deployed to assess conditions within the Emergency Planning Zone.

Field Monitoring Teams operate within the EPZ as directed by the EOF RP Coordinator.

Media Information staff are responsible for coordinating with external agencies to manage public communications.


Question: What are the physical parameters for the prototype in a pebble bed reactor experiment?

The reactor's safety features include redundant cooling systems and multiple emergency shutdown mechanisms to ensure public safety.


Question: What is the role of biogeochemical cycles in managing nuclear waste?

Biogeochemical cycles are crucial for understanding how various elements move through the environment, which is essential for assessing the long-term impacts of nuclear waste disposal.

Urban systems are often designed to enhance the resilience of cities against climate change and natural disasters.