|
---|
Category:Letter
MONTHYEARLR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 ML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary ML24197A0552024-07-15015 July 2024 Requalification Program Inspection LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves IR 05000272/20245012024-06-12012 June 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 2024-08-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARIR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 ML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21300A0222021-10-27027 October 2021 Notification of Conduct of a Fire Protection Team Inspection ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18120A2482018-04-27027 April 2018 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403 ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb ML17222A1652017-08-10010 August 2017 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502) ML17181A1352017-06-29029 June 2017 NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70) ML17164A4062017-06-13013 June 2017 NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462) ML17027A3282017-02-27027 February 2017 Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies ML16321A4642016-11-21021 November 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements ML16277A5142016-11-0303 November 2016 Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16271A2052016-11-0202 November 2016 Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML16231A4272016-08-24024 August 2016 Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16217A4302016-08-17017 August 2016 Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade ML16007A1742016-05-31031 May 2016 Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error ML16089A0792016-05-0505 May 2016 Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16124A5802016-05-0303 May 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes ML15055A3772015-03-10010 March 2015 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57 ML14197A6192014-07-24024 July 2014 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386) ML14168A2352014-07-0202 July 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML13309B5922013-11-22022 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13168A2762013-08-12012 August 2013 Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228) ML13193A2912013-07-22022 July 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031 ML13204A2532013-07-19019 July 2013 Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom ML13190A2212013-07-0202 July 2013 RAIs for Hope Creek Regarding Response to Order EA-12-051 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML12334A3102012-12-0505 December 2012 Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items ML12310A1672012-11-0101 November 2012 Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5 ML1227901012012-10-0505 October 2012 Clarifying Information for Question No. 4 (with Attachment) ML12212A1032012-08-0808 August 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information ML12216A1792012-08-0303 August 2012 Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML12213A6162012-07-30030 July 2012 Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic 2024-05-07
[Table view] |
Text
OFFICIAL USE ONLY PROPRIETARY INFORMATION February 18, 2021 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE LOW PRESSURE SAFETY LIMIT TO ADDRESS GENERAL ELECTRIC PART 21 SAFETY COMMUNICATIONS (EPID L-2020-LLA-0210)
Dear Mr. Carr:
By letter dated September 24, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20272A063), PSEG Nuclear, LLC (the licensee) submitted a license amendment request to revise the Hope Creek Generating Station Technical Specification (TS) Safety Limit 2.1.1, THERMAL POWER, Low Pressure or Low Flow, and 2.1.2, THERMAL POWER, High Pressure and High Flow. The proposed change, which reduces the reactor steam dome low pressure safety limit specified in TS 2.1.1 and TS 2.1.2.
will resolve an issue identified in General Electric Nuclear Energy Safety Communication notification SC05-03 pursuant to Title 10 of the Code of Federal Regulations Part 21. The issue is concerning a potential to momentarily violate TS 2.1.1 during a Pressure Regulator Failure Maximum Demand - Open transient event.
The U.S. Nuclear Regulatory Commission staff determined that additional information is required as discussed in Enclosure 1. The licensee has agreed to provide the RAI responses by April 30, 2021.
The request for additional information (RAI) contains proprietary information as originally submitted in the September 24, 2020, license amendment request. Proprietary information is identified by text enclosed within double brackets as shown here (( )). A non-proprietary version of the RAI is provided in Enclosure 2.
Enclosure 1 transmitted herewith contains sensitive unclassified non-safeguards information.
When separated from Enclosure 1, this letter is DECONTROLLED.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION If you have any questions, please contact me at 301-415-4125 or via e-mail at James.Kim@nrc.gov.
Sincerely,
/RA/
James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. RAI (Proprietary)
- 2. RAI (Non-Proprietary) cc without Enclosure 1: Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION
ENCLOSURE 2 NON-PROPRIETARY VERSION REQUEST FOR ADDITIONAL INFORMATION PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION LICENSE AMENDMENT REQUEST TO REVISE LOW PRESSURE SAFETY LIMIT TO ADDRESS GENERAL ELECTRIC PART 21 SAFETY COMMUNICATIONS DOCKET NO. 50-354
OFFICIAL USE ONLY PROPRIETARY INFORMATION NON-PROPRIETARY VERSION REQUEST FOR ADDITIONAL INFORMATION PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION LICENSE AMENDMENT REQUEST TO REVISE LOW PRESSURE SAFETY LIMIT TO ADDRESS GENERAL ELECTRIC PART 21 SAFETY COMMUNICATIONS DOCKET NO. 50-354 By application dated September 24, 2020 (Reference 1), PSEG Nuclear, LLC (PSEG, the licensee) submitted a license amendment request (LAR) to revise the Hope Creek Generating Station (HCGS) Technical Specification (TS) Safety Limit (SL) 2.1.1, THERMAL POWER, Low Pressure or Low Flow, and 2.1.2, THERMAL POWER, High Pressure and High Flow. The proposed change, which reduces the reactor steam dome low pressure safety limit specified in TS 2.1.1 and TS 2.1.2, will resolve an issue identified in a notification pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 21. The issue is concerning a potential to momentarily violate TS 2.1.1 during a Pressure Regulator Failure Maximum Demand - Open (PRFO) transient event. The PRFO transient is analyzed in Chapter 15 of the HCGS Updated Final Safety Analysis Report.
After reviewing the LAR dated September 24, 2020, and Enclosure 6 (Reference 2) to the LAR, the U.S. Nuclear Regulatory Commissions (NRC) Nuclear Systems Performance Branch (SNSB) staff requests responses to the requests for additional information (RAIs) given below.
The proprietary information, pursuant to 10 CFR Section 2.390, in the RAIs is identified in red font text enclosed within double square brackets as shown here (( example proprietary text )).
SNSB-RAI 1 Regulatory Basis:
Criterion 10 - Reactor Design: The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
RAI:
Reference 2, Section 2.0, Table 2-1, design input item 9 states the thermal power scram time constant is 6.6 seconds. Table 2-2, Item 2 states:
The simulated thermal power (STP) is an acceptable model of the core power.
The thermal power time constant is provided in Design Input Item 9. The STP time constant used is (( )).
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Therefore, use of the STP time constant is conservative for the purpose of the PRFO analysis.
(a) The classical definition of time constant for a specified parameter that decreases with time is that it represents the time taken for the parameter to decrease by a factor of (1 - 1/e) = (approximately 0.632). Provide the definition of thermal power scram time constant used in the context of the above statement, the parameter for which the time constant is considered, and the fuel characteristics (or properties) on which it depends.
The NRC staff searched through References 3, 4, and 5 and the GNF2 and GNF3 generic compliance documents NEDC-33270P, Revision 3 (Reference 6), and NEDC-33879P Revision 0 (Reference 7), and could not find the definition and values of the time constants for the GE14, GNF2, and GNF3 fuels to verify that the key input value of 6.6 seconds used for the PRFO analysis is conservative.
(b) Describe the methods (test and/or codes) used to determine the thermal power scram time constant.
(c) Provide the reference documents in which the time constant is defined and the values of GE14, GNF2, and GNF3 fuels are given, or provide definition and the actual values for these fuels. Explain (( )) is conservative.
SNSB RAI 2 Regulatory Basis:
Criterion 10 - Reactor Design: The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
RAI:
For the analysis to evaluate the performance of the GEXL14 and GEXL17 correlations against the GNF3 test data, Reference 2, Section 3.0 states:
((
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
))
(a) Explain why the ((
))
(b) Explain what is meant by ((
))
(c) Confirm that the ((
)) respectively. If not, provide the source of the ((
))
(d) Based on the statement in Reference 5, Section 5.2.5, the additive constant applied to each fuel rod location ((
)). Explain how this ((
))
SNSB-RAI 3 Regulatory Basis:
Criterion 10 - Reactor Design: The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
RAI:
Reference 2, Section 3.1, states ((
)) Explain what is the significance and/or basis of (( ))
REFERENCES
- 1. PSEG Nuclear, LLC, letter to U.S. Nuclear Regulatory Commission, License Amendment Request: Revise Hope Creek Generating Station Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03, dated September 24, 2020 (ADAMS Accession No. ML20272A063).
- 2. GE-Hitachi Nuclear Energy, NEDC-33928P, Revision 0, SC05-03 Evaluation for Hope Creek Generating Station (Proprietary), September 2020 (ADAMS Accession No. ML20272A064).
- 3. Global Nuclear Fuel, NEDC-32851P-A, Revision 5, GEXL14 Correlation for GE14 Fuel, April 2011 (Proprietary) (ADAMS Accession No. ML111290535). Non-proprietary version designated as NEDO-32851-A, Revision 5, available at ADAMS Accession No. ML111290532.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION
- 4. Global Nuclear Fuel, NEDC-33292P, Revision 3, GEXL17 Correlation for GNF2 Fuel, June 2009 (Proprietary) (ADAMS Accession No. ML091830641). Non-proprietary version designated as NEDO-33292, Revision 3, available at ADAMS Accession No. ML091830624.
- 5. Global Nuclear Fuel, NEDC-33880P, Revision 1, GEXL21 Correlation for GNF3 Fuel, November 2017 (Proprietary) (ADAMS Accession No. ML17311A131). Non-proprietary version designated as NEDO-33880, Revision 1, available at ADAMS Accession No. ML17311A132.
- 6. Global Nuclear Fuel, NEDC-33270P, Revision 3, GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), March 2010 (Proprietary) (ADAMS Accession No. ML100700462). Non-proprietary version designated as NEDO-33270, Revision 3, available at ADAMS Accession No. ML100700443.
- 7. Global Nuclear Fuel, NEDC-33879P, Revision 0, GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II), March 2017 (Proprietary) (ADAMS Accession No. ML17096A516). Non-proprietary version designated as NEDO-33879, Revision 0, available at ADAMS Accession No. ML17096A517.
OFFICIAL USE ONLY PROPRIETARY INFORMATION