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| | issue date = 12/30/2008 | | | issue date = 12/30/2008 |
| | title = Correction to Amendment No. 175 Regarding Technical Specification Requirements for Inoperable Inverters | | | title = Correction to Amendment No. 175 Regarding Technical Specification Requirements for Inoperable Inverters |
| | author name = Ennis R B | | | author name = Ennis R |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Joyce T | | | addressee name = Joyce T |
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| | docket = 05000354 | | | docket = 05000354 |
| | license number = | | | license number = |
| | contact person = Ennis R B, NRR/DORL, 415-1420 | | | contact person = Ennis R, NRR/DORL, 415-1420 |
| | case reference number = TAC MD9335 | | | case reference number = TAC MD9335 |
| | document type = Letter, Technical Specification, Amendment | | | document type = Letter, Technical Specification, Amendment |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 30, 2008 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 HOPE CREEK GENERATING STATION -CORRECTION TO AMENDMENT NO. 175 REGARDING TECHNICAL SPECIFICATION REQUIREMENTS FOR INOPERABLE INVERTERS (TAC NO. MD9335) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 30, 2008 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 SUB~IECT: HOPE CREEK GENERATING STATION - CORRECTION TO AMENDMENT NO. 175 REGARDING TECHNICAL SPECIFICATION REQUIREMENTS FOR INOPERABLE INVERTERS (TAC NO. MD9335) |
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| ==Dear Mr. Joyce:== | | ==Dear Mr. Joyce:== |
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| On December 18, 2008, the Nuclear Regulatory Commission (NRC) issued Amendment No. 175 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek). | | On December 18, 2008, the Nuclear Regulatory Commission (NRC) issued Amendment No. 175 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek). |
| This amendment consisted of changes to the Technical Specifications (TSs) in response to the application from PSEG Nuclear LLC (PSEG) dated July 30, 2008, as supplemented by letters dated September 29, and October 20, 2008. The amendment revised TS 3.8.3, "Onsite Power Distribution Systems," to establish a separate TS Action statement for inoperable inverters associated with the 120 volt alternating current distribution panels. On December 22, 2008, the PSEG staff notified the NRC staff that one of the license pages revised by Amendment No. 175 did not reflect a prior change made to that page by Amendment No. 174 which was issued by the NRC staff on May 14, 2008. | | This amendment consisted of changes to the Technical Specifications (TSs) in response to the application from PSEG Nuclear LLC (PSEG) dated July 30, 2008, as supplemented by letters dated September 29, and October 20, 2008. The amendment revised TS 3.8.3, "Onsite Power Distribution Systems," to establish a separate TS Action statement for inoperable inverters associated with the 120 volt alternating current distribution panels. |
| Specifically, license page 3 did not reflect the current approved maximum power level of 3840 megawatts thermal in license condition 2.C.(1). The corrected license page 3 is enclosed. The NRC staff regrets any inconvenience this may have caused. If you have any questions, please contact me at 301-415-1420. Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Hope Creek license page cc w/encl: | | On December 22, 2008, the PSEG staff notified the NRC staff that one of the license pages revised by Amendment No. 175 did not reflect a prior change made to that page by Amendment No. 174 which was issued by the NRC staff on May 14, 2008. Specifically, license page 3 did not reflect the current approved maximum power level of 3840 megawatts thermal in license condition 2.C.(1). The corrected license page 3 is enclosed. The NRC staff regrets any inconvenience this may have caused. |
| Distribution via | | If you have any questions, please contact me at 301-415-1420. |
| -3PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3840 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. Technical Specifications and Environmental Protection Plan Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No. 4)* This License Condition was satisfied as documented in the letter from W. R. Butler (NRC) to C. A. McNeill, Jr. (PSE&G) dated December 7, 1987. Accordingly, this condition has been deleted. parenthetical n otation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or supplements wherein the license condition is discussed. | | Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 |
| Amendment No. 175 December 30,2008 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 HOPE CREEK GENERATING STATION -CORRECTION TO AMENDMENT NO. 175 REGARDING TECHNICAL SPECIFICATION REQUIREMENTS FOR INOPERABLE INVERTERS (TAC NO. MD9335) | | |
| | ==Enclosure:== |
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| | Hope Creek license page 3 cc w/encl: Distribution via ListServ |
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| | - 3 (4) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| | C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: |
| | (1) Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3840 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. |
| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | (3) Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No. 4)* |
| | This License Condition was satisfied as documented in the letter from W. R. Butler (NRC) to C. A. McNeill, Jr. (PSE&G) dated December 7, 1987. Accordingly, this condition has been deleted. |
| | *The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed. |
| | Amendment No. 175 |
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| | December 30,2008 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 |
| | |
| | ==SUBJECT:== |
| | HOPE CREEK GENERATING STATION - CORRECTION TO AMENDMENT NO. 175 REGARDING TECHNICAL SPECIFICATION REQUIREMENTS FOR INOPERABLE INVERTERS (TAC NO. MD9335) |
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| ==Dear Mr. Joyce:== | | ==Dear Mr. Joyce:== |
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| On December 18, 2008, the Nuclear Regulatory Commission (NRC) issued Amendment No. 175 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek). | | On December 18, 2008, the Nuclear Regulatory Commission (NRC) issued Amendment No. 175 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek). |
| This amendment consisted of changes to the Technical Specifications (TSs) in response to the application from PSEG Nuclear LLC (PSEG) dated July 30, 2008, as supplemented by letters dated September 29, and October 20, 2008. The amendment revised TS 3.8.3, "Onsite Power Distribution Systems," to establish a separate TS Action statement for inoperable inverters associated with the 120 volt alternating current distribution panels. On December 22, 2008, the PSEG staff notified the NRC staff that one of the license pages revised by Amendment No. 175 did not reflect a prior change made to that page by Amendment No. 174 which was issued by the NRC staff on May 14, 2008. | | This amendment consisted of changes to the Technical Specifications (TSs) in response to the application from PSEG Nuclear LLC (PSEG) dated July 30, 2008, as supplemented by letters dated September 29, and October 20, 2008. The amendment revised TS 3.8.3, "Onsite Power Distribution Systems," to establish a separate TS Action statement for inoperable inverters associated with the 120 volt alternating current distribution panels. |
| Specifically, license page 3 did not reflect the current approved maximum power level of 3840 megawatts thermal in license condition 2.C.(1). The corrected license page 3 is enclosed. The NRC staff regrets any inconvenience this may have caused. If you have any questions, please contact me at 301-415-1420. | | On December 22, 2008, the PSEG staff notified the NRC staff that one of the license pages revised by Amendment No. 175 did not reflect a prior change made to that page by Amendment No. 174 which was issued by the NRC staff on May 14, 2008. Specifically, license page 3 did not reflect the current approved maximum power level of 3840 megawatts thermal in license condition 2.C.(1). The corrected license page 3 is enclosed. The NRC staff regrets any inconvenience this may have caused. |
| Sincerely, /raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Hope Creek license page cc w/encl: Distribution via ListServ DISTRIBUTION PUBLIC RidsOgcRp Resource LPL1-2 RIF RidsAcrsAcnw MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDirsltsb Resource RidsNrrLAABaxter Resource RidsRgn1 MailCenter Resource RidsNrrPMREnnis Resource GHili (2), OIS RidsNrrDorlDpr Resource SRay, NRRIEEEB ADAMS Accession No.: ML083650169 *via e-mail OFFICE LPL1-2/PM LPL 1-2/LA* LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 12/23/08 12/23/08 12/30108 OFFICIAL RECORD COpy}} | | If you have any questions, please contact me at 301-415-1420. |
| | Sincerely, |
| | /raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 |
| | |
| | ==Enclosure:== |
| | |
| | Hope Creek license page 3 cc w/encl: Distribution via ListServ DISTRIBUTION PUBLIC RidsOgcRp Resource LPL 1-2 RIF RidsAcrsAcnw MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDirsltsb Resource RidsNrrLAABaxter Resource RidsRgn1 MailCenter Resource RidsNrrPMREnnis Resource GHili (2), OIS RidsNrrDorlDpr Resource SRay, NRRIEEEB ADAMS Accession No.: ML083650169 *via e-mail OFFICE LPL1-2/PM LPL 1-2/LA* LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 12/23/08 12/23/08 12/30108 OFFICIAL RECORD COpy}} |
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MONTHYEARML0823400922008-08-21021 August 2008 E-mail - Acceptance Review for TAC MD9335 - Hope Creek Amendment Request - Inoperable Inverters Project stage: Acceptance Review ML0836501692008-12-30030 December 2008 Correction to Amendment No. 175 Regarding Technical Specification Requirements for Inoperable Inverters Project stage: Other 2008-12-30
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Category:Letter
MONTHYEARML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection 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) 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 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 - 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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 IR 05000272/20244032024-03-20020 March 2024 and Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 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-N24-0020, 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 - 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[Table view] Category:Technical Specification
MONTHYEARLR-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-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0060, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-29029 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20142A5412020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 16, Technical Specifications LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2020-05-15015 May 2020 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling2020-05-0707 May 2020 License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement.2019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. ML19058A2212019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0013, License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B2018-03-28028 March 2018 License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B LR-N18-0011, Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR2018-01-22022 January 2018 Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0124, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-09-21021 September 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re2017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Repor ML17157B2652017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor LR-N16-0066, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-06-17017 June 2016 License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade2015-09-21021 September 2015 Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade ML15265A2242015-09-21021 September 2015 License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)2010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100503982010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance2010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance ML1100504152010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)2010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)2010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) ML1100503992010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix2010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix ML1100503752010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100504022010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1025802422010-09-0808 September 2010 License Amendment Request H10-01:, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction2010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505182010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505002010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment2010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling2010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling ML1100505162010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling LR-N10-0355, Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment2010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment ML1100504772010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer2010-04-21021 April 2010 Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations2010-04-21021 April 2010 Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations ML1100505062010-04-21021 April 2010 Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations ML1100505052010-04-21021 April 2010 Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 252010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504172010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504742010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup2010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature2010-03-0505 March 2010 Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature 2023-03-29
[Table view] Category:Amendment
MONTHYEARLR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling2020-05-0707 May 2020 License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling LR-N17-0124, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-09-21021 September 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N09-0290, Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)2009-12-21021 December 2009 Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) ML0936401982009-12-21021 December 2009 Hope Creek Generating Station - License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project) LR-N09-0237, License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components2009-11-0404 November 2009 License Amendment Request H09-05 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components ML0836501692008-12-30030 December 2008 Correction to Amendment No. 175 Regarding Technical Specification Requirements for Inoperable Inverters ML0834601362008-12-0303 December 2008 New Jersey Department of Environmental Protection'S Bureau of Nuclear Engineering Comment on PSEG Nuclear Llc'S License Amendment Request to Remove Restrictions on Operation of the Hydrogen Water Chemistry System at Low Power. ML0834504962008-11-18018 November 2008 License Amendment Request (LAR) H08-04 ML0812306232008-05-14014 May 2008 Tec Spec Pages for Amendment No 174 ML0812306002008-05-14014 May 2008 Operating License Pages LR-N07-0163, License Amendment Request to Remove Turbine First Stage Pressure Values from Technical Specifications2007-07-26026 July 2007 License Amendment Request to Remove Turbine First Stage Pressure Values from Technical Specifications LR-N06-0437, License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications2006-11-15015 November 2006 License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications LR-N06-0286, Request for License Amendment Extended Power Uprate2006-09-18018 September 2006 Request for License Amendment Extended Power Uprate LR-N05-0432, Request for Change to Technical Specifications on Standby Liquid Control System2005-10-11011 October 2005 Request for Change to Technical Specifications on Standby Liquid Control System LR-N05-0030, Request for Change to Technical Specifications Relocation of Overcurrent Protective Devices2005-10-11011 October 2005 Request for Change to Technical Specifications Relocation of Overcurrent Protective Devices LR-N05-0266, Request for Change to Technical Specifications Correction of Containment Requirements During Handling of Irradiated Fuel and Core Alterations2005-10-0707 October 2005 Request for Change to Technical Specifications Correction of Containment Requirements During Handling of Irradiated Fuel and Core Alterations LR-N04-0454, Request for Change to Technical Specifications to Revise Scram Discharge Volume Vent and Drain Line Requirements Using the Consolidated Line Item Improvement Process2005-02-25025 February 2005 Request for Change to Technical Specifications to Revise Scram Discharge Volume Vent and Drain Line Requirements Using the Consolidated Line Item Improvement Process LR-N04-0350, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Primary Containment Hydrogen/Oxygen Concentration Analyzer and Monitor Channels Using the Consolidated Line Item.2004-10-0101 October 2004 Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Primary Containment Hydrogen/Oxygen Concentration Analyzer and Monitor Channels Using the Consolidated Line Item. LR-N04-0062, Request for License Amendment Arts/Mellla Implementation2004-06-0707 June 2004 Request for License Amendment Arts/Mellla Implementation LR-N04-0183, Request for Change to Technical Specifications Safety Limit Minimum Critical Power Ratio2004-04-27027 April 2004 Request for Change to Technical Specifications Safety Limit Minimum Critical Power Ratio LR-N03-0405, Request for Change to Technical Specifications Regarding Reactor Protection System Instrumentation, Control Rod Block Instrumentation, Source Range Monitors, and Power Distribution Limits Surveillance Requirements2003-10-24024 October 2003 Request for Change to Technical Specifications Regarding Reactor Protection System Instrumentation, Control Rod Block Instrumentation, Source Range Monitors, and Power Distribution Limits Surveillance Requirements ML0320904342003-07-0303 July 2003 License Change Request to Eliminate Post Accident Sampling System Technical Specifications Requirements ML0310700882003-04-16016 April 2003 Technical Specification Page 6-16b, Amendment 147 LR-N02-0417, Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters - Revision to Request for Change to TS Dated 06/28/20022003-01-18018 January 2003 Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters - Revision to Request for Change to TS Dated 06/28/2002 LR-N02-0343, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.2002-10-23023 October 2002 Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area. LR-N02-0069, Request for License Amendment A.C. Sources - Operating2002-08-20020 August 2002 Request for License Amendment A.C. Sources - Operating ML0222606802002-08-13013 August 2002 Technical Specifications for Amendment 139 Use of Existing Pressure-Temperature Curves Through Cycle 12 (Tac No. MB4685) ML0210504542002-04-0303 April 2002 Request for Change to Technical Specifications Reactor Coolant Chemistry 2021-05-07
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 30, 2008 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 SUB~IECT: HOPE CREEK GENERATING STATION - CORRECTION TO AMENDMENT NO. 175 REGARDING TECHNICAL SPECIFICATION REQUIREMENTS FOR INOPERABLE INVERTERS (TAC NO. MD9335)
Dear Mr. Joyce:
On December 18, 2008, the Nuclear Regulatory Commission (NRC) issued Amendment No. 175 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek).
This amendment consisted of changes to the Technical Specifications (TSs) in response to the application from PSEG Nuclear LLC (PSEG) dated July 30, 2008, as supplemented by letters dated September 29, and October 20, 2008. The amendment revised TS 3.8.3, "Onsite Power Distribution Systems," to establish a separate TS Action statement for inoperable inverters associated with the 120 volt alternating current distribution panels.
On December 22, 2008, the PSEG staff notified the NRC staff that one of the license pages revised by Amendment No. 175 did not reflect a prior change made to that page by Amendment No. 174 which was issued by the NRC staff on May 14, 2008. Specifically, license page 3 did not reflect the current approved maximum power level of 3840 megawatts thermal in license condition 2.C.(1). The corrected license page 3 is enclosed. The NRC staff regrets any inconvenience this may have caused.
If you have any questions, please contact me at 301-415-1420.
Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Hope Creek license page 3 cc w/encl: Distribution via ListServ
- 3 (4) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3840 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No. 4)*
This License Condition was satisfied as documented in the letter from W. R. Butler (NRC) to C. A. McNeill, Jr. (PSE&G) dated December 7, 1987. Accordingly, this condition has been deleted.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 175
December 30,2008 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - CORRECTION TO AMENDMENT NO. 175 REGARDING TECHNICAL SPECIFICATION REQUIREMENTS FOR INOPERABLE INVERTERS (TAC NO. MD9335)
Dear Mr. Joyce:
On December 18, 2008, the Nuclear Regulatory Commission (NRC) issued Amendment No. 175 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek).
This amendment consisted of changes to the Technical Specifications (TSs) in response to the application from PSEG Nuclear LLC (PSEG) dated July 30, 2008, as supplemented by letters dated September 29, and October 20, 2008. The amendment revised TS 3.8.3, "Onsite Power Distribution Systems," to establish a separate TS Action statement for inoperable inverters associated with the 120 volt alternating current distribution panels.
On December 22, 2008, the PSEG staff notified the NRC staff that one of the license pages revised by Amendment No. 175 did not reflect a prior change made to that page by Amendment No. 174 which was issued by the NRC staff on May 14, 2008. Specifically, license page 3 did not reflect the current approved maximum power level of 3840 megawatts thermal in license condition 2.C.(1). The corrected license page 3 is enclosed. The NRC staff regrets any inconvenience this may have caused.
If you have any questions, please contact me at 301-415-1420.
Sincerely,
/raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Hope Creek license page 3 cc w/encl: Distribution via ListServ DISTRIBUTION PUBLIC RidsOgcRp Resource LPL 1-2 RIF RidsAcrsAcnw MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDirsltsb Resource RidsNrrLAABaxter Resource RidsRgn1 MailCenter Resource RidsNrrPMREnnis Resource GHili (2), OIS RidsNrrDorlDpr Resource SRay, NRRIEEEB ADAMS Accession No.: ML083650169 *via e-mail OFFICE LPL1-2/PM LPL 1-2/LA* LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 12/23/08 12/23/08 12/30108 OFFICIAL RECORD COpy