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| REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING REMOVAL OF CERTAIN TRAINING REQUIREMENTS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated October 17, 2016 (Agencywide Documents Access and Management System Accession No. ML16291A318), PSEG Nuclear LLC (PSEG or the licensee) submitted a license amendment request (LAA) to revise the Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, Technical Specifications (TSs) by removing certain training program requirements. Specifically, the amendments would remove TS requirements that are redundant to, or superseded by, the requirements contained in Title 10 of the Code of Federal Regulations (10 CFR) Part 55, "Operators' Licenses," and 1O CFR Section 50.120, "Training and qualification of nuclear power plan personnel." | | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING REMOVAL OF CERTAIN TRAINING REQUIREMENTS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated October 17, 2016 (Agencywide Documents Access and Management System Accession No. ML16291A318), PSEG Nuclear LLC (PSEG or the licensee) submitted a license amendment request (LAA) to revise the Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, Technical Specifications (TSs) by removing certain training program requirements. Specifically, the amendments would remove TS requirements that are redundant to, or superseded by, the requirements contained in Title 10 of the Code of Federal Regulations (10 CFR) Part 55, "Operators' Licenses," and 10 CFR Section 50.120, "Training and qualification of nuclear power plan personnel." |
| For Hope Creek, this request would remove the requirements for conducting retraining for individuals identified in Section 5.5 of ANSl/ANS-3.1-1981, "Selection, Qualification and Training of Personnel for Nuclear Power Plants." 1 Section 5.5 of ANSl/ANS-3.1-1981 states, in part, that, "Mechanisms shall be established to ensure that individuals in the operating organization performing safety related functions remain cognizant of changes to the facility, procedures, governmental regulations, and quality assurance requirements .... " Quality Assurance personnel are listed in Section 4.4.5 of ANSI/ANS-3.1-1981 as requiring training consistent with other professional technical personnel which are listed in 10 CFR Section 50.120. By deleting TS Section 6.4.1, it would appear that the requirement to maintain a retraining and replacement training program for quality assurance personnel would also be deleted. | | For Hope Creek, this request would remove the requirements for conducting retraining for individuals identified in Section 5.5 of ANSl/ANS-3.1-1981, "Selection, Qualification and Training of Personnel for Nuclear Power Plants." 1 Section 5.5 of ANSl/ANS-3.1-1981 states, in part, that, "Mechanisms shall be established to ensure that individuals in the operating organization performing safety related functions remain cognizant of changes to the facility, procedures, governmental regulations, and quality assurance requirements .... " Quality Assurance personnel are listed in Section 4.4.5 of ANSI/ANS-3.1-1981 as requiring training consistent with other professional technical personnel which are listed in 10 CFR Section 50.120. By deleting TS Section 6.4.1, it would appear that the requirement to maintain a retraining and replacement training program for quality assurance personnel would also be deleted. |
| The U.S. Nuclear Regulatory Commission staff has reviewed the application and, based upon this review, determined that the following additional information is needed to complete our review: | | The U.S. Nuclear Regulatory Commission staff has reviewed the application and, based upon this review, determined that the following additional information is needed to complete our review: |
| : 1. The LAR technical analysis states that the TS requirements are redundant to, or superseded by, 1O CFR Part 55 and 1O CFR Section 50.120. Discuss the method and guidance documents that would be used regarding training of quality assurance personnel at Hope Creek. | | : 1. The LAR technical analysis states that the TS requirements are redundant to, or superseded by, 10 CFR Part 55 and 10 CFR Section 50.120. Discuss the method and guidance documents that would be used regarding training of quality assurance personnel at Hope Creek. |
| 1 Salem's TSs reference ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel." | | 1 Salem's TSs reference ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel." |
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Category:Letter
MONTHYEARIR 05000272/20244032024-09-25025 September 2024 and Salem Nuclear Generating Station, Units 1 and 2, Cybersecurity Inspection Report 05000354/2024403, 05000272/2024403, and 05000311/2024403 (Cover Letter Only) IR 05000272/20244022024-09-23023 September 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24267A1082024-09-23023 September 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) IR 05000272/20240052024-08-29029 August 2024 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2024005 and 05000311/2024005) LR-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 IR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024 Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding 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 ML24197A0552024-07-15015 July 2024 Requalification Program Inspection 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 LR-N24-0048, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) 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 ML24099A1572024-05-29029 May 2024 Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies 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 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 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 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 LR-N24-0038, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger2024-05-0909 May 2024 Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger 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 IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024 Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) 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 IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20240112024-04-0101 April 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram ML24071A2132024-03-12012 March 2024 Senior Reactor and Reactor Operator Initial License Examinations LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024 Spent Fuel Cask Registration IR 05000272/20230062024-02-28028 February 2024 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023006 and 05000311/2023006 IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges IR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024 In-Service Inspection Activities 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24253A1942024-09-0909 September 2024 NRR E-mail Capture - Final Eeeb RAI - Hope Creek Amendment to Revise TS to Change Surveillance Interval to Accommodate 24-Month Fuel Cycle IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 ML24060A0492024-02-28028 February 2024 NRR E-mail Capture - Final Exhb RAI for Hope Creek, Salem 1 and 2 Amendment to Modify Exclusion Area Boundary ML22333A9022022-11-29029 November 2022 NRR E-mail Capture - Final Iolb RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG ML22318A1062022-11-14014 November 2022 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000272/2023011 and 05000311/2023011 ML22290A2202022-10-17017 October 2022 NRR E-mail Capture - Final RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG ML22055A0702022-02-22022 February 2022 NRR E-mail Capture - Final RAI - Salem 1-Relief Request Associated with Fourth Inservice Inspection (ISI) Interval Limited Examinations (L-2021-LLR-0085) 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 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21068A4142021-03-0909 March 2021 NRR E-mail Capture - Final RAI for Salem Unit 1 LAR to Revise and Relocate Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML21043A1442021-02-11011 February 2021 NRR E-mail Capture - Salem - Final RAI Alternative for Examination of ASME Section XI, Category B-B, Item Number B2.11and B2.12 (L-2020-LRR-0103) ML21021A2592021-01-21021 January 2021 NRR E-mail Capture - Final RAI - Salem 1 - Steam Generator Tube Inspection Report 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) ML20281A5172020-10-13013 October 2020 Notification of Conduct of a Fire Protection Team Inspection ML18267A1712018-09-21021 September 2018 NRR E-mail Capture - Final RAI from PRA Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18264A0122018-09-20020 September 2018 NRR E-mail Capture - Final RAI from I&C Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) 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) ML18250A3132018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18171A3212018-06-20020 June 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Adopt TSTF-411 and 418 (L-2017-LLA-0442) 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) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) 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) 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) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate 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) 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) ML17212B1152017-07-31031 July 2017 Request for Additional Information - Salem Units 1 and 2 - Containment Fan Coil Unit Allowed Outage Time Amendment Request (CACs MF9364 and MF9365) ML17199A1122017-07-18018 July 2017 Request for Additional Information - Salem Units 1 and 2 - Accident Monitoring Instrumentation License Amendment Request (CAC Nos. MF8859 & MF8860) ML17192A1672017-07-11011 July 2017 Request for Additional Information - Salem Unit 1 - Steam Generator Tube Inspection Report 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) ML17115A4032017-05-0909 May 2017 Request for Additional Information Regarding Relief Request SC-14R-171 - Use of Code Cases N-695-1 and N-696-1 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 ML16218A0052016-08-11011 August 2016 Request for Additional Information Concerning Request for an Extension to Enforcement Guidance Memorandum 12-001 ML16195A4492016-07-14014 July 2016 Request for Additional Information Regarding Chilled Water System Modifications 2024-09-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 21, 2016 Mr. Peter P. Sena, Ill President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REMOVE CERTAIN TRAINING REQUIREMENTS (CAC NOS. MF8477, MF8478, AND MF8479)
Dear Mr. Sena:
By letter dated October 17, 2016 (Agencywide Documents Access and Management System Accession No. ML16291A318), PSEG Nuclear LLC (PSEG or the licensee) submitted a license amendment request to revise the Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Technical Specifications (TSs) by removing certain training program requirements. Specifically, the amendments would remove TS requirements that are redundant to, or superseded by, the requirements contained in Title 10 of the Code of Federal Regulations (10 CFR) Part 55, "Operators' Licenses," and 10 CFR Section 50.120, "Training and qualification of nuclear power plan personnel."
The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed to complete our review. On November 16, 2016, a draft of the question was sent to Mr. Paul Duke of your staff to ensure that the question was understandable, the regulatory basis for the question was clear, and to determine if the information was previously docketed. On November 21, 2016, a teleconference was held to clarify the question. Mr. Duke indicated that PSEG will submit a response within 30 days of the date of the call.
P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.
Sincerely, Carl n J. Park r, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING REMOVAL OF CERTAIN TRAINING REQUIREMENTS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated October 17, 2016 (Agencywide Documents Access and Management System Accession No. ML16291A318), PSEG Nuclear LLC (PSEG or the licensee) submitted a license amendment request (LAA) to revise the Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, Technical Specifications (TSs) by removing certain training program requirements. Specifically, the amendments would remove TS requirements that are redundant to, or superseded by, the requirements contained in Title 10 of the Code of Federal Regulations (10 CFR) Part 55, "Operators' Licenses," and 10 CFR Section 50.120, "Training and qualification of nuclear power plan personnel."
For Hope Creek, this request would remove the requirements for conducting retraining for individuals identified in Section 5.5 of ANSl/ANS-3.1-1981, "Selection, Qualification and Training of Personnel for Nuclear Power Plants." 1 Section 5.5 of ANSl/ANS-3.1-1981 states, in part, that, "Mechanisms shall be established to ensure that individuals in the operating organization performing safety related functions remain cognizant of changes to the facility, procedures, governmental regulations, and quality assurance requirements .... " Quality Assurance personnel are listed in Section 4.4.5 of ANSI/ANS-3.1-1981 as requiring training consistent with other professional technical personnel which are listed in 10 CFR Section 50.120. By deleting TS Section 6.4.1, it would appear that the requirement to maintain a retraining and replacement training program for quality assurance personnel would also be deleted.
The U.S. Nuclear Regulatory Commission staff has reviewed the application and, based upon this review, determined that the following additional information is needed to complete our review:
- 1. The LAR technical analysis states that the TS requirements are redundant to, or superseded by, 10 CFR Part 55 and 10 CFR Section 50.120. Discuss the method and guidance documents that would be used regarding training of quality assurance personnel at Hope Creek.
1 Salem's TSs reference ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel."
P. Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.
Sincerely,
/RA/
Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL 1-2 R/F RidsNrrPMHopeCreek Resource RidsNrrLALRonewicz Resource RidsNrrDirslolb Resource RidsRgn1 MailCenter Resource RidsACRS_MailCTR Resource RidsNrrDorlLpl 1-2 Resource TKolb, NRR RidsNrrPMSalem Resource ADAMS A ccess1on No.: ML16321A464 *b memo 1
OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DIRS/IOLB/BC*
NAME CParker LRonewicz NSalgado DATE 11/21/16 11/19/16 11/15/16 OFFICE DORL/LPL 1-2/BC(A) DORL/LPL 1-2/PM NAME SKoenick CParker DATE 11/21/16 11/21/16 OFFICIAL RECORD COPY