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MONTHYEARML0235404462002-12-20020 December 2002 FRN: Individual Notice, Hope Creek Generating Station - Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing... Project stage: Other ML0301304142003-01-10010 January 2003 Biweekly Notice Memo, Notice of Issuance, Provides One-Time Change to TS 4.8.1.1.2.h.14 to Allow Testing of Emergency Diesel Generator Lockout Relays to Be Performed at Power Until Startup from Its Eleventh Refueling Outage Project stage: Other ML0301303262003-01-10010 January 2003 Technical Specification Page 3/4 8-8 to Amendment 141 of License NPF-57 Project stage: Other ML0301301572003-01-10010 January 2003 License Amendment, Exigent Change Regarding Emergency Diesel Generator Output Breaker Lockout Relays, TAC No. MB6965 Project stage: Other 2002-12-20
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Category:Federal Register Notice
MONTHYEARML22034A9832022-02-15015 February 2022 FRN - Notice of Issuance of COVID-19 Exemptions Issued in January 2022 ML21091A0662021-04-23023 April 2021 FRN - Notice of Issuance of Multiple COVID-19 Exemptions Regarding Various Parts of 10 CFR Issued in March 2021 ML20335A0902020-12-21021 December 2020 Federal Register Notice - November 2020 COVID-19 Exemptions ML20243A0002020-09-23023 September 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for August 2020 ML19312A4712020-01-15015 January 2020 FRN: Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station - Environmental Assessment and Finding of No Significant Impact Related to Changes to Emergency Plan Staffing Requirements ML19312A4352020-01-15015 January 2020 Environmental Assessment and Finding of No Significant Impact Related to Changes to Emergency Plan Staffing Requirements ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19140A4562019-05-28028 May 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 06/04/2019 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 NRC-2018-0096, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 20182018-05-14014 May 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018 ML18127B7232018-05-14014 May 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018 NRC-2018-0011, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: Februar2018-01-24024 January 2018 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: February 6, ML18002A3812018-01-24024 January 2018 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: February 6, NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 20182017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17353A1922017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17248A2262017-09-15015 September 2017 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: October 3, 2017 NRC-2016-0161, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 20162016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16215A2272016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 NRC-2016-0143, Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI2016-07-18018 July 2016 Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Au ML16187A2232016-07-18018 July 2016 Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Au ML15132A6682015-06-0404 June 2015 Hc and Salem, Unit 1 and 2 - Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment to Update Appendix B to the Renewed Facility Operating Licenses ML14335A6482015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units NRC-2015-0009, G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units2015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14335A6302015-01-15015 January 2015 G20110262 - Final Response to Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 NRC-2012-0264, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2 - Exemption from Certain Requirements of 10 CFR Part 26, Fitness for Duty Programs (TAC Nos. ME7651, ME7652 and ME7653)2012-10-26026 October 2012 Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2 - Exemption from Certain Requirements of 10 CFR Part 26, Fitness for Duty Programs (TAC Nos. ME7651, ME7652 and ME7653) ML12299A0712012-10-26026 October 2012 and Salem Nuclear Generating Station, Units 1 and 2 - Exemption from Certain Requirements of 10 CFR Part 26, Fitness for Duty Programs ML12299A0812012-10-26026 October 2012 and Salem Nuclear Generating Station, Units 1 and 2 - Exemption from Certain Requirements of 10 CFR Part 26, Fitness for Duty Programs NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments ML12056A0432012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations2011-09-22022 September 2011 FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations ML1126504892011-09-22022 September 2011 FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations ML1122302752011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML11116A1482011-07-20020 July 2011 Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station ML11117A2062011-07-20020 July 2011 Notice of Issuance of Renewed Facility Operating License No. NPF-57 for an Additional 20-Year Period ML1112200122011-04-20020 April 2011 05/12-14/2011 - Meeting (583rd) of the Advisory Committee on Reactor Safeguards - Federal Register Notice ML1027207232010-09-29029 September 2010 Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal (Hope Creek), November 3, 2010 ML1001203242010-02-25025 February 2010 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 Docket Nos. 50-272, 50-311 and 50-354 Exemption NRC-2010-0043, Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 Docket Nos. 50-272, 50-311 and 50-354 Exemption2010-02-25025 February 2010 Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 Docket Nos. 50-272, 50-311 and 50-354 Exemption ML1000500542010-01-29029 January 2010 FRN: General Notice. Hope Creek Generating Station & Salem Nuclear Generating Station, Unit Nos. 1 and 2 Environmental Assessment and Finding of No Significant Impact ML0928706352009-10-23023 October 2009 11/05/2009 Notice of Meeting to Discuss License Renewal Process and Environmental Scoping for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station, License Renewal Application Review ML0927801472009-10-15015 October 2009 Notice of Acceptability for Docketing of the Application and Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License No. NPF-57 for an Additional 20-Year Period, PSEG Nuclear, LLC, Hope Creek Nuclear Generating Sta ML0927404212009-10-15015 October 2009 Notice of Intent to Prepare an Environmental Impact Statement and Conduct the Scoping Process for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Nuclear Generating Station ML0922908012009-08-31031 August 2009 FRN: General Notice. Notice of Receipt and Availability of Application for Renewal of Hope Creek Generating Station ML0816205382008-06-12012 June 2008 Federal Register Notice Regarding the Meeting of the ACRS Subcommittee on Power Uprates (Hope Creek), July 8, 2008 ML0802205552008-03-0303 March 2008 Enclosure Hope Creek, Final Environmental Assessment and Findings of No Significant Impact Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level 2022-02-15
[Table view] Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval 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 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 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 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 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 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations 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 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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 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 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 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 LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
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Text
December 20, 2002 Mr. Harold W. Keiser Chief Nuclear Officer & President PSEG Nuclear LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING RE: REQUEST FOR CHANGE TO TECHNICAL SPECIFICATION 4.8.1.1.2.h.14, EMERGENCY DIESEL GENERATOR LOCKOUT RELAYS (TAC NO. MB6965)
Dear Mr. Keiser:
The enclosed notice was forwarded for publication in the Federal Register. The notice relates to your application for an amendment to Facility Operating License No. NPF-57 for the Hope Creek Generating Station dated December 17, 2002. The proposed amendment would provide a one-time change to Technical Specification (TS) 4.8.1.1.2.h.14 to allow the testing of Hope Creeks emergency diesel generator (EDG) lockout relays to be performed at power until startup from its eleventh refueling outage (spring 2003). The current TS surveillance requirement only allows the EDG lockout relays to be tested during shutdown conditions.
PSEG has requested that the proposed TS change be issued on an exigent basis in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.91(a)(6).
Sincerely,
/RA/
Robert J. Fretz, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Federal Register Notice cc w/encl: See next page
ML023540446
- Concurrence by telephone call OFFICE PDI-2/PM PDI-2/LA* PDI-2/SC NAME RFretz LCox/SLL for, MOBrien - changes only VNerses for JClifford DATE 12/19/02 12/19/02, 12/19/02 12/20/02 PSEG Nuclear LLC Hope Creek Generating Station cc:
Mr. David F. Garchow Lower Alloways Creek Township Vice President - Operations c/o Mary O. Henderson, Clerk PSEG Nuclear - X04 Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Mr. John T. Carlin Radiation Protection Programs Vice President - Nuclear Reliability and NJ Department of Environmental Technical Support Protection and Energy PSEG Nuclear - N10 CN 415 P.O. Box 236 Trenton, NJ 08625-0415 Hancocks Bridge, NJ 08038 Brian Beam Mr. Gabor Salamon Board of Public Utilities Manager - Nuclear Safety and Licensing 2 Gateway Center, Tenth Floor PSEG Nuclear - N21 Newark, NJ 07102 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Jeffrie J. Keenan, Esquire 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Ms. R. A. Kankus U.S. Nuclear Regulatory Commission Joint Owner Affairs Drawer 0509 PECO Energy Company Hancocks Bridge, NJ 08038 Nuclear Group Headquarters KSA1-E 200 Exelon Way Kennett Square, PA 19348
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION PSEG NUCLEAR LLC DOCKET NO. 50-354 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-57, issued to PSEG Nuclear LLC (PSEG or the licensee), for operation of the Hope Creek Generating Station (Hope Creek) located in Salem County, New Jersey.
The proposed amendment would provide a one-time change to Technical Specification (TS) 4.8.1.1.2.h.14 to allow the testing of Hope Creeks emergency diesel generator (EDG) lockout relays to be performed at power until startup from its eleventh refueling outage (spring 2003). The current TS surveillance requirement (SR) only allows the EDG lockout relays to be tested during shutdown conditions. Approval and implementation of the proposed TS change would allow the testing that has been completed to be used to comply with TS 4.8.1.1.2.h.14.
PSEG has requested that the proposed TS change be issued on an exigent basis in accordance with Title 10 of the CODE OF FEDERAL REGULATIONS (10 CFR) Section 50.91(a)(6). On December 12, 2002, all 4 Hope Creek EDGs were declared inoperable at 1:07 p.m. due to the licensees failure to fully comply with TS SR 4.8.1.1.2.h.14.a. PSEG invoked TS 4.0.3, thus permitting 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete the required surveillance activities. The SR that was not met required the licensee to demonstrate that the EDG differential current and low lube
oil pressure could independently provide trip and lockout inputs to the lockout relay 86R. TS 4.8.1.1.2.h requires this test to be performed during shutdown conditions. At 11:20 a.m. on December 13, 2002, PSEG invoked TS 4.0.3 when it determined that portions of SRs 4.8.1.1.2.h.14.b (backup relay 86B) and 4.8.1.1.2.h.14.c (breaker failure relay 86F) were missed for EDG A and EDG C. TS 4.0.3 allows the licensee to complete missed surveillance tests within a 24-hour period following discovery that a SR was not done. On December 13, 2002, PSEG requested that the NRC exercise discretion in accordance with Section VII.C of the General Statement of Policy and Procedures for NRC Enforcement Actions (Enforcement Policy), NUREG-1600, by granting a Notice of Enforcement Discretion (NOED). At the time of the NOED request, the licensee was conducting portions of testing to meet 4.8.1.1.2.h.14.b and 4.8.1.1.2.h.14.c. Because TS 4.8.1.1.2.h currently requires that these tests be performed during shutdown conditions and the time to Hope Creeks next scheduled outage would exceed the non-compliance period beyond 14 days, PSEG further requested a one-time change to TS 4.8.1.1.2.h under exigent circumstances. Approval of this one-time TS change would allow testing recently conducted during power operations to satisfy the SR on the EDG lockout relays.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under exigent circumstances, the NRC staff must determine that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously
evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
This request is only administrative in nature. Portions of the protective Emergency Diesel Generator (EDG) lockout function testing required by Technical Specification (TS) 4.8.1.1.2.h.14 were discovered to have been missed and have since been satisfactorily performed during power operation. The provision of TS 4.8.1.1.2.h that requires testing be performed during shutdown precludes PSEG from taking credit for the on-line testing to meet the surveillance requirement. The scope of this amendment request is to enable PSEG to take credit for the testing that has been performed at power to satisfy TS 4.8.1.1.2.h.14. The requested amendment applies on a one-time basis until the next refueling outage. The change is administrative and cannot affect the initiation of any accident, nor does it affect the capability of the EDGs to fulfill their design basis accident functions.
Therefore, the request does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The request is only administrative in nature in that surveillance requirement 4.8.1.1.2.h requires the surveillance to be performed during shutdown. The operability of the EDG lockout functions has been satisfactorily demonstrated; however the surveillance requirement as presently written cannot be administratively completed due to the shutdown conditions identified in the surveillance requirement. Since no physical changes are being made to the plant and there are no changes being made to the operation of Hope Creek, this request does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed amendment does not involve a significant reduction in a margin of safety.
The operability of the EDG lockout functions has been satisfactorily demonstrated, however the surveillance requirement as written cannot be administratively completed due to the shutdown conditions identified in the surveillance requirement. Since there is no impact to the ability of the EDGs to function during a design basis accident, this request does not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 14 days after the date of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment until the expiration of the 14-day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 14-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received.
Should the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance. The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By [insert date 30 days from date of publication], the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commissions "Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.714, 1 which is available at the Commissions Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, and available electronically on the Internet at the NRC Web site http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors: (1) the nature of the petitioners right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioners property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioners interest.
1 The most recent version of Title 10 of theCode of Federal Regulations, published January 1, 2002, inadvertently omitted the last sentence of 10 CFR 2.714(d) and subparagraphs (d)(1) and (2), regarding petitions to intervene and contentions. For the complete, corrected text of 10 CFR 2.714(d), please see 67 FR 20884; April 20, 2002.
The petition should also identify the specific aspect(s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
If the amendment is issued before the expiration of the 30-day hearing period, the
Commission will make a final determination on the issue of no significant hazards consideration.
If a hearing is requested, the final determination will serve to decide when the hearing is held.
If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, or may be delivered to the Commissions Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, by the above date. Because of continuing disruptions in delivery of mail to United States Government offices, it is requested that petitions for leave to intervene and requests for hearing be transmitted to the Secretary of the Commission either by means of facsimile transmission to 301-415-1101 or by e-mail to hearingdocket@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and because of continuing disruptions in delivery of mail to United States Government offices, it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by e-mail to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to Jeffrie J. Keenan, Esquire, Nuclear Business Unit - N21, P.O. Box 236, Hancocks Bridge, NJ 08038, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated December 17, 2002, which is available for public inspection at the Commissions Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management Systems (ADAMS) Public Electronic Reading Room on the Internet at the NRC web site http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this day of December 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert J. Fretz, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation