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| | issue date = 08/19/2010 | | | issue date = 08/19/2010 |
| | title = Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times. | | | title = Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times. |
| | author name = Perry J F | | | author name = Perry J |
| | author affiliation = PSEG Nuclear, LLC | | | author affiliation = PSEG Nuclear, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC AUG 1 9 2010 10 CFR 50.90 LR-N10-0310 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 | | {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC AUG 1 9 2010 10 CFR 50.90 LR-N10-0310 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 |
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| ==Subject:== | | ==Subject:== |
| | Supplement to License Amendment Request H09-06 to Adopt TSTF-460, REVISION 0, "CONTROL ROD SCRAM TIMES" |
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| ==References:== | | ==References:== |
| | (1) Letter from PSEG to NRC, "License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated December 1, 2009 (2) Letter from PSEG to NRC, "Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated July 23, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The request would revise Technical Specification; (TS) testing frequency for the surveillance requirement (SR) in existing TS 3.1.3.2, "Control Rod Maximum Scram Insertion Times." These changes are based on TS Task Force (TSTF) change'traveler TSTF-460 (Revision 0) that has been approved generically for the boiling water reactor (BWR) |
| | Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6) by revising the frequency of STS SR 3.1.4.2, control rod scram time testing, from "at least once per 120 days of POWER OPERATION" to "at least once per 200 days of POWER OPERATION." A notice announcing the availability of this proposed TS change using the Consolidated Line Item Improvement Process was published in the Federal Register on August 23, 2004 (69 FR 51854). |
| | In Reference 2, PSEG corrected a typographical error in Section 6.0 "Commitments" of Attachment 1, page 12 of 14. Specifically, the section did not correctly reference the specific commitments made by PSEG in Attachment 4 of the submittal. |
| | At the NRC's request PSEG is submitting an additional supplement to this license amendment request, which will modify the technical specification mark ups submitted to the NRC in Reference |
| | : 1. The revised pages are editorial in nature and do not modify the intent of the license amendment request. To ensure there is consistency within the section and reduce confusion, the proposed change will insert the word "Deleted" to page v of the Index and page 3/4 1-8. The revised mark ups are Attachment 1 to this letter. A-0 95-2168 REV. 7/99 |
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| Supplement to License Amendment Request H09-06 to Adopt TSTF-460, REVISION 0, "CONTROL ROD SCRAM TIMES" (1) Letter from PSEG to NRC, "License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated December 1, 2009 (2) Letter from PSEG to NRC, "Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated July 23, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The request would revise Technical Specification; (TS) testing frequency for the surveillance requirement (SR) in existing TS 3.1.3.2, "Control Rod Maximum Scram Insertion Times." These changes are based on TS Task Force (TSTF) change'traveler TSTF-460 (Revision
| | Document Control Desk 2 LR-N10-0310 PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in References 1 and 2. The additional information provided in this letter does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration. |
| : 0) that has been approved generically for the boiling water reactor (BWR)Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6) by revising the frequency of STS SR 3.1.4.2, control rod scram time testing, from "at least once per 120 days of POWER OPERATION" to "at least once per 200 days of POWER OPERATION." A notice announcing the availability of this proposed TS change using the Consolidated Line Item Improvement Process was published in the Federal Register on August 23, 2004 (69 FR 51854).In Reference 2, PSEG corrected a typographical error in Section 6.0 "Commitments" of Attachment 1, page 12 of 14. Specifically, the section did not correctly reference the specific commitments made by PSEG in Attachment 4 of the submittal.
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| At the NRC's request PSEG is submitting an additional supplement to this license amendment request, which will modify the technical specification mark ups submitted to the NRC in Reference 1. The revised pages are editorial in nature and do not modify the intent of the license amendment request. To ensure there is consistency within the section and reduce confusion, the proposed change will insert the word "Deleted" to page v of the Index and page 3/4 1-8. The revised mark ups are Attachment 1 to this letter. A-0 95-2168 REV. 7/99 Document Control Desk 2 LR-N10-0310 PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in References 1 and 2. The additional information provided in this letter does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration.
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| There are no regulatory commitments contained in this submittal. | | There are no regulatory commitments contained in this submittal. |
| If you have any questions or require additional information, please do not hesitate to contact Mrs. Erin West at (856) 339-5411.I declare under penalty of perjury that the foregoing is true and correct.Executed on ? / //10 (Date)Sincerely, John F. Perry Site Vice President | | If you have any questions or require additional information, please do not hesitate to contact Mrs. Erin West at (856) 339-5411. |
| -Hope Creek Attachment Marc L, Dapas, Acting Regional Administrator | | I declare under penalty of perjury that the foregoing is true and correct. |
| -NRC Region I R. Ennis, Project Manager -USNRC NRC Senior Resident Inspector-Hope Creek P. Mulligan, Manager IV, NJBNE Commitment Coordinator | | Executed on ? / //10 (Date) |
| -Hope Creek PSEG Commitment Coordinator | | Sincerely, John F. Perry Site Vice President - Hope Creek Attachment Marc L, Dapas, Acting Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector- Hope Creek P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Hope Creek PSEG Commitment Coordinator - Corporate |
| -Corporate Document Control Desk LR-N10-0310 ATTACHMENT 1 TECHNICAL SPECIFICATION PAGES: REVISED: LICENSE AMENDMENT TO ADOPT TSTF 460, REV 0.The following Technical Specifications for HCGS (Facility Operating License NPF-57) are the revised pages affected by this change request: TS No. Title Page INDEX CONTROL RODS v 3.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES 3/41-8 4.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES- 3/4 1-8 SURVEILLANCE REQUIREMENTS S INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY | | |
| .......... | | Document Control Desk LR-N10-0310 ATTACHMENT 1 TECHNICAL SPECIFICATION PAGES: REVISED: |
| ........................................ | | LICENSE AMENDMENT TO ADOPT TSTF 460, REV 0. |
| 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN..! | | The following Technical Specifications for HCGS (Facility Operating License NPF-57) are the revised pages affected by this change request: |
| ...................................... | | TS No. Title Page INDEX CONTROL RODS v 3.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES 3/41-8 4.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES- 3/4 1-8 SURVEILLANCE REQUIREMENTS |
| 3/4 1-1 3/4.1.2- REACTIVITY ANOMALIES | | |
| ................................... | | S LIMITING CONDITIONS FOR OPERATION INDEX AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY .......... . ....................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN..! ...................................... 3/4 1-1 3/4.1.2- REACTIVITY ANOMALIES ................................... .1-2 1-2+/-( |
| .1-2 3/4.1.3 CONTROL RODS. 1-2+/-(Control Rod Operability | | 3/4.1.3 CONTROL RODS. |
| ................................... | | Control Rod Operability ................................... 3/4 1-3 Control Rod Maximum Scram Insertion Times ..... ......... 3/4 1-6 Control Rod-A~-vý Scram insertion Times ................. 3/4 1-7 Four Control Rod iGroup Scram Insertion Times ............ 3/4 1-8 Control Rod Scram Accumulators ............................ 3/4 1-9 Control Rod Drive Coupling ................................ 3/4 1-11 Control Rod Position Indication ........................... 3/4 1-13 Control Rod Drive Housing Support....................... 3/4 1-15 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer ...................................... 3/4 1-16 Rod Sequence Control System (Deleted) .................. 3/4 1-17 Rod Block Monitor ........... ............................ 3/4 1-18 3/4.1,5 STANDBY LIQUID CONTROL SYSTEM ........................... 3/4 1-19 Figure 3.1.5-1 Sodium Pentaborate Solution Volume/Concentration Requirements ..... 3/4 1-21 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ............. 3/4 2-1 S HOPE CREEK v Amendment No. 105 |
| 3/4 1-3 Control Rod Maximum Scram Insertion Times ..... ......... | | |
| 3/4 1-6 Control Rod-A~-vý Scram insertion Times ................. | | REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD GROUP' SCP)M INSERTION TIMES L |
| 3/4 1-7 Four Control Rod iGroup Scram Insertion Times .. .......... | | LIMITING CONDITION FOR OPERATION |
| 3/4 1-8 Control Rod Scram Accumulators | | : 3. 1.3..4 - - ýaý Nvo-awo awaga- -- -- -- 111-1 -1.1 -..- - "a4k% |
| ............................ | | I .... |
| 3/4 1-9 Control Rod Drive Coupling ................................ | | a ulv hdzt |
| 3/4 1-11 Control Rod Position Indication | | - iijigo@;60+ |
| ........................... | | AVI'LICADILITY.lv CONDTICUt1 znI 2 seCU'TIlTA |
| 3/4 1-13 Control Rod Drive Housing Support....................... | | ~~8sNh'itHh 66Eh~isi 4 P..t.~o z ~ |
| 3/4 1-15 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer | | *e-fg 1..e D.5 Seltl -ne~e feantVl..LJA. |
| ...................................... | | e5551..SL veel 4 .12. |
| Rod Sequence Control System (Deleted) | | dtfUTiSl: hl Mrt.I.IS tZMVEMJtfeir: i! feff-1s#i th e ooo 51stgo 4 . 1 .'L. |
| .................. | | 4 UC!eet-reg0 eds 2ICNTJS 1:1 1i -LSI1 L1- -- ySS. -li LI .L-VV1 j-ISISI HOPE CREEK 3/4 1-8 Amendment No. 180}} |
| Rod Block Monitor ........... | |
| ............................ | |
| 3/4.1,5 STANDBY LIQUID CONTROL SYSTEM ........................... | |
| Figure 3.1.5-1 Sodium Pentaborate Solution Volume/Concentration Requirements | |
| .....3/4.2 POWER DISTRIBUTION LIMITS 3/4 1-16 3/4 1-17 3/4 1-18 3/4 1-19 3/4 1-21 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ............. | |
| 3/4 2-1 S HOPE CREEK v Amendment No. 105 REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD GROUP' SCP)M INSERTION TIMES LIMITING CONDITION FOR OPERATION L 3. 1.3..4 -ýaý -- ---Nvo-awo awaga- --111-1 -1.1 -..- -"a4k%I ....a ulv -hdzt iijigo@;60+ | |
| AVI'LICADILITY.lv seCU'TIlTA CONDTICUt1 znI 2~~8sNh'itHh 66Eh~isi 4 P..t.~o z ~*e-fg Seltl -ne~e 1..e D.5 e5551..SL f eantVl..LJA. | |
| veel 4 .12.dtfUTiSl: | |
| hl Mrt.I.IS tZMVEMJ tfeir: i! feff-1s#i th e 51stgo ooo 4 .1 .'L. 4 UC!eet-reg0 eds 2ICNTJS 1:1 1i -LSI1 L1- --ySS. -li LI .L-VV1 j-ISISI HOPE CREEK 3/4 1-8 Amendment No. 180}} | |
Letter Sequence Supplement |
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TAC:ME2815, Control Rod SCRAM Time Testing Frequency (Approved, Closed) |
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MONTHYEARML0934302422009-12-0101 December 2009
License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times.
Project stage: Request
ML0936501192009-12-31031 December 2009
Acceptance Review for TAC ME2815 - Hope Creek - License Amendment Request Regarding Control Rod Scram Times - TSTF-460
Project stage: Acceptance Review
LR-N10-0257, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Revision 0, Control Rod Scram Times.2010-07-23023 July 2010
Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Revision 0, Control Rod Scram Times.
Project stage: Supplement
LR-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.2010-08-19019 August 2010
Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.
Project stage: Supplement
ML1022503952010-09-27027 September 2010
Issuance of Amendment Control Rod Scram Times
Project stage: Approval
2010-07-23
[Table View] |
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|---|
Category:Letter type:LR
MONTHYEARLR-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
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
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)
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
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
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
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
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
LR-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022
2022 Annual 10 CFR 50.46 Report
LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022
Emergency Plan Evacuation Time Estimate
LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022
License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report
LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022
Emergency Plan Document Revisions Implemented November, 2021
LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022
2021 Annual Radioactive Effluent Release Report (Rerr)
LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022
2021 Annual Radiological Environmental Operating Report
LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022
Emergency Plan Document Revisions Implemented March 24, 2022
LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022
Guarantees of Payment of Deferred Premiums
LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022
Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data
LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022
Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility
LR-N22-0019, Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges2022-02-24024 February 2022
Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges
LR-N22-0011, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2022-02-0101 February 2022
Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink
LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-01-0707 January 2022
Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs
LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022
Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs
LR-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports2021-12-0202 December 2021
Corrected Hope Creek 10 CFR 50.46 Reports
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-N21-0081, Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments2021-11-15015 November 2021
Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments
LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021
License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System
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-N21-0071, 2021 Annual 10 CFR 50.46 Report2021-09-30030 September 2021
2021 Annual 10 CFR 50.46 Report
LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021
License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS
LR-N21-0069, Emergency Plan Document Revisions Implemented August 10, 20212021-09-0909 September 2021
Emergency Plan Document Revisions Implemented August 10, 2021
LR-N21-0059, In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage2021-08-13013 August 2021
In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage
LR-N21-0054, Correction to Prior Spent Fuel Cask Registration Letter2021-07-15015 July 2021
Correction to Prior Spent Fuel Cask Registration Letter
LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2021-06-17017 June 2021
Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem
LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021
Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication
LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021
Core Operating Limits Report, Reload 23, Cycle 24, Revision 21
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-N21-0039, Deviation from EPRI Document 33002012244 Inspection Requirements2021-04-30030 April 2021
Deviation from EPRI Document 33002012244 Inspection Requirements
LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021
Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication
2023-09-08
[Table view]
Category:Technical Specifications
MONTHYEARML23341A1372024-01-16016 January 2024
Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning
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
ML21050A0022021-03-12012 March 2021
Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements
ML21047A3132021-03-10010 March 2021
Issuance of Amendment No. 226 Revise Emergency Core Cooling System Technical Specification for High Pressure Coolant Injection System Inoperability (Non-Proprietary)
ML20281A6132020-11-0909 November 2020
Issuance of Amendment No. 225 Revise Technical Specification Actions for Suppression Pool Cooling
ML20231A6322020-09-29029 September 2020
Issuance of Amendment No. 224 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors
ML20034E6172020-02-27027 February 2020
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer
ML19186A2052019-08-0606 August 2019
Issuance of Amendment No. 217 Remote Shutdown System
ML19065A1562019-03-27027 March 2019
Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension
ML17317A6052017-12-13013 December 2017
Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535
ML17047A0202017-03-21021 March 2017
Issuance of Amendment to Delete Technical Specification Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves
ML17053A1782017-03-15015 March 2017
Issuance of Amendment to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling
ML16270A0382016-10-13013 October 2016
Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change
ML15286A0912015-11-30030 November 2015
Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522
ML15141A2712015-06-17017 June 2015
and Salem Nuclear Generating Station, Unit Nos.1 and 2, Issuance of Amendments Update of Appendix B to the Renewed Facility Operating Licenses
ML14108A3992014-12-18018 December 2014
Issuance of Amendment Request to Relocate Flood Protection Technical Specification to the Technical Requirements Manual
LR-N14-0189, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process2014-11-25025 November 2014
License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process
ML14108A3122014-07-29029 July 2014
Issuance of Amendment Request to Relocate Safety Relief Valve Position Instrumentation to Technical Requirements Manual
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
LR-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual2013-07-30030 July 2013
License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual
LR-N12-0067, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items2012-03-0101 March 2012
License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items
LR-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process2012-01-26026 January 2012
Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process
ML0527202982011-07-20020 July 2011
Current Facility Operating License NPF-57, Tech Specs, Revised 12/18/2017
ML11116A1482011-07-20020 July 2011
Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station
LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011
Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal
ML1109801512011-04-19019 April 2011
Correction to Amendment No. 187 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425
LR-N11-0098, Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 1872011-04-0404 April 2011
Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187
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-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.2010-08-19019 August 2010
Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.
ML1015907132010-07-21021 July 2010
Issuance of Amendment Control Rod Notch Testing Frequency
LR-N10-0097, License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension2010-03-29029 March 2010
License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension
LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2010-03-19019 March 2010
Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML0932700232009-12-0808 December 2009
Issuance of Amendment Mode Change Limitations
ML0934302422009-12-0101 December 2009
License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times.
ML0916006832009-07-15015 July 2009
Issuance of Amendment Technical Specification Requirements Related to Snubbers
LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications2009-01-0505 January 2009
License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications
LR-N08-0150, Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request2008-07-30030 July 2008
Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request
LR-N08-0071, License Amendment Request - Hydrogen Water Chemistry Low Power Restriction2008-04-25025 April 2008
License Amendment Request - Hydrogen Water Chemistry Low Power Restriction
ML0734500402008-01-24024 January 2008
Tech Spec Pages for Amendment 173 Control Room Habitability
LR-N08-0003, Supplement to License Amendment Request for Extended Power Uprate2008-01-16016 January 2008
Supplement to License Amendment Request for Extended Power Uprate
ML0728500372007-10-16016 October 2007
Technical Specifications, Issuance of Amendment Removal of Turbine First Stage Pressure Values from Technical Specifications
ML0724003042007-08-27027 August 2007
Tech Spec Pages for Amendment 171 Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications
LR-N07-0215, Supplement to License Amendment Request for Extended Power Uprate2007-08-27027 August 2007
Supplement to License Amendment Request for Extended Power Uprate
ML0724805722007-06-15015 June 2007
Gnf S-0000-0068-2643, Gnf Additional Information Regarding the Requested Changes to the Technical Specification Slmcpr. Hope Creek (KT1) Cycle 15
LR-N07-0061, Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-17017 April 2007
Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
ML0630704822006-10-31031 October 2006
Tech Spec Pages for Amendment 170 Regarding Clarification of Requirements During Handling of Irradiated Fuel Core Alterations, and Operations with the Potential for Draining the Reactor Vessel
ML0624101882006-08-28028 August 2006
Technical Specifications - Fuel Storage and Handling
ML0621403972006-08-0101 August 2006
Technical Specifications, Issuance of Amendment Ultimate Heat Sink, MC8054
LR-N06-0259, Supplement to Request for License Amendment Ultimate Heat Sink2006-07-18018 July 2006
Supplement to Request for License Amendment Ultimate Heat Sink
ML0610105472006-04-10010 April 2006
Technical Specifications Pages Re Relocation of the Component Identification from the Overcurrent Protective Device Lists in TS 3/4.8.4.1, Primary Containment Penetration Conductor Overcurrent Protective Devices, and TS 3/4.8.4.5
2024-01-16
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC AUG 1 9 2010 10 CFR 50.90 LR-N10-0310 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Supplement to License Amendment Request H09-06 to Adopt TSTF-460, REVISION 0, "CONTROL ROD SCRAM TIMES"
References:
(1) Letter from PSEG to NRC, "License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated December 1, 2009 (2) Letter from PSEG to NRC, "Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Revision 0, Control Rod Scram Times," dated July 23, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The request would revise Technical Specification; (TS) testing frequency for the surveillance requirement (SR) in existing TS 3.1.3.2, "Control Rod Maximum Scram Insertion Times." These changes are based on TS Task Force (TSTF) change'traveler TSTF-460 (Revision 0) that has been approved generically for the boiling water reactor (BWR)
Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6) by revising the frequency of STS SR 3.1.4.2, control rod scram time testing, from "at least once per 120 days of POWER OPERATION" to "at least once per 200 days of POWER OPERATION." A notice announcing the availability of this proposed TS change using the Consolidated Line Item Improvement Process was published in the Federal Register on August 23, 2004 (69 FR 51854).
In Reference 2, PSEG corrected a typographical error in Section 6.0 "Commitments" of Attachment 1, page 12 of 14. Specifically, the section did not correctly reference the specific commitments made by PSEG in Attachment 4 of the submittal.
At the NRC's request PSEG is submitting an additional supplement to this license amendment request, which will modify the technical specification mark ups submitted to the NRC in Reference
- 1. The revised pages are editorial in nature and do not modify the intent of the license amendment request. To ensure there is consistency within the section and reduce confusion, the proposed change will insert the word "Deleted" to page v of the Index and page 3/4 1-8. The revised mark ups are Attachment 1 to this letter. A-0 95-2168 REV. 7/99
Document Control Desk 2 LR-N10-0310 PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in References 1 and 2. The additional information provided in this letter does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration.
There are no regulatory commitments contained in this submittal.
If you have any questions or require additional information, please do not hesitate to contact Mrs. Erin West at (856) 339-5411.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ? / //10 (Date)
Sincerely, John F. Perry Site Vice President - Hope Creek Attachment Marc L, Dapas, Acting Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector- Hope Creek P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Hope Creek PSEG Commitment Coordinator - Corporate
Document Control Desk LR-N10-0310 ATTACHMENT 1 TECHNICAL SPECIFICATION PAGES: REVISED:
LICENSE AMENDMENT TO ADOPT TSTF 460, REV 0.
The following Technical Specifications for HCGS (Facility Operating License NPF-57) are the revised pages affected by this change request:
TS No. Title Page INDEX CONTROL RODS v 3.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES 3/41-8 4.1.3.4 FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES- 3/4 1-8 SURVEILLANCE REQUIREMENTS
S LIMITING CONDITIONS FOR OPERATION INDEX AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY .......... . ....................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN..! ...................................... 3/4 1-1 3/4.1.2- REACTIVITY ANOMALIES ................................... .1-2 1-2+/-(
3/4.1.3 CONTROL RODS.
Control Rod Operability ................................... 3/4 1-3 Control Rod Maximum Scram Insertion Times ..... ......... 3/4 1-6 Control Rod-A~-vý Scram insertion Times ................. 3/4 1-7 Four Control Rod iGroup Scram Insertion Times ............ 3/4 1-8 Control Rod Scram Accumulators ............................ 3/4 1-9 Control Rod Drive Coupling ................................ 3/4 1-11 Control Rod Position Indication ........................... 3/4 1-13 Control Rod Drive Housing Support....................... 3/4 1-15 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer ...................................... 3/4 1-16 Rod Sequence Control System (Deleted) .................. 3/4 1-17 Rod Block Monitor ........... ............................ 3/4 1-18 3/4.1,5 STANDBY LIQUID CONTROL SYSTEM ........................... 3/4 1-19 Figure 3.1.5-1 Sodium Pentaborate Solution Volume/Concentration Requirements ..... 3/4 1-21 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ............. 3/4 2-1 S HOPE CREEK v Amendment No. 105
REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD GROUP' SCP)M INSERTION TIMES L
LIMITING CONDITION FOR OPERATION
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