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| | number = ML12334A310 | | | number = ML12334A310 |
| | issue date = 12/05/2012 | | | issue date = 12/05/2012 |
| | title = Hope Creek Generating Station - Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items (TAC ME8113) | | | title = Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items |
| | author name = Hughey J D | | | author name = Hughey J |
| | 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 = 05000272, 05000311, 05000354 | | | docket = 05000272, 05000311, 05000354 |
| | license number = NPF-057 | | | license number = NPF-057 |
| | contact person = Hughey J D | | | contact person = Hughey J |
| | case reference number = TAC ME8113 | | | case reference number = TAC ME8113 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = TAC:ME8113, TAC:ME8113 | | | project = TAC:ME8113 |
| | stage = RAI | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 December 5, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 HOPE CREEK GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS (TAC NO. ME8113) Dear Mr. Joyce: By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications and Facility Operating License for Hope Creek. The NRC staff has reviewed the request submitted by the licensee and has determined that additional information is required, as provided in the enclosure, in order to complete its review. The draft questions were sent to Mr. Paul Duke, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On November 30, 2012. Mr, Duke indicated that the licensee will submit a response by December 31,2012, If you have any questions, please contact me at (301) 415-3204 or via e-mail at John. Hughey@nrc.gov. po John D, Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. Request for Additional cc: Distribution via ListServ 1 Agencywide Documents Access and Management System Accession No. ML 12062A148 .J-I1r/lltcf'{}l-V'/ | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 5, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 |
| REQUEST FOR ADDITIONAL INFORMATION REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NUMBER 50-354 By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request (LAR) for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications (TS) and Facility Operating License (FOL) for Hope Creek. The proposed changes are administrative in nature and fall into one of four categories: (1) correct typographical errors, (2) delete historical requirements that have expired, (3) make editorial changes to correct errors and/or omissions from previous license amendment requests, or (4) update component lists to reflect current plant design. The NRC staff has determined that additional information is needed to complete the review, as described below. On page 4 of Attachment 1 to the amendment request, PSEG requested to remove the requirement for an annual report for main steamline safety/relief valve challenges from TS Administrative Controls Section 6.9.1.5. The licensee stated that the requirement should have been deleted during the implementation of Amendment 161, which was issued with letter dated January 11, 2006,2 but it was not removed due to an oversight. After review, the NRC staff found that this reporting requirement was not requested to be removed in the associated LAR dated January 11, 2005.3 No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR. On page 7 of Attachment 1 to the amendment request. PSEG requested to remove FOL License Condition 2.C.(13), "Safety Parameter Display System [SPDS] (Section 18.2, SSER No.5)," from the license for Hope Creek. Specifically, FOL License Condition 2.C.(13) requires PSEG to add certain parameters to the SPDS and have them operational prior to the earlier of 90 days after restart from the first refueling outage, or July 12,1988. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12062A148 2 ADAMS Accession No. ML060050496 3 ADAMS Accession No. ML050190207 Enclosure Per License Condition 2.C.(13), the listed parameters are required to be operational in SPDS. No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR. On page 8 of Attachment 1 to the amendment request, PSEG requested to remove FOL License Condition 2.C.(22), "Steam Dryer," from the license for Hope Creek. Most of the specific conditions listed in FOL License Condition 2.C.(22) were completed after, at the latest, the second refueling outage following the implementation of the Extended Power Uprate, and are now historical. However, the NRC staff believes that one condition is still applicable. FOL License Condition 2.C.(22).2.e states, PSEG Nuclear LLC shall revise plant procedures to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facility's steam dryer inspection program with BWRVIP-139 [Steam Dryer Inspection and Flaw Evaluation Guidelines];4 and to identify the NRC Project Manager for the facility as the point of contact for providing power ascension testing information during power ascension. Reflecting long-term monitoring of plant parameters potentially indicative of steam dryer failure in plant procedures is a legal requirement per license condition 2.C.(22).2.e. No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR. 4 ADAMS Accession No. ML 101270122 December 5,2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 HOPE CREEK GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS (TAC NO. ME8113) Dear Mr. Joyce: By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications and Facility Operating License for Hope Creek. The NRC staff has reviewed the request submitted by the licensee and has determined that additional information is required, as provided in the enclosure, in order to complete its review. The draft questions were sent to Mr. Paul Duke, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On November 30,2012, Mr. Duke indicated that the licensee will submit a response by December 31,2012. If you have any questions, please contact me at (301) 415-3204 or via e-mail at John. Hughey@nrc.gov. Sincerely, IRA! John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Request for Additional cc: Distribution via ListServ 1 Agencywide Documents Access and Management System Accession No. ML 12062A148 DISTRIBUTION: RidsNrrPMHopeCreek Resource RidsNrrLAABaxter Resource RidsNrrDorlDpr Resource RidsRgn 1 MailCenter Resource RidsNrrDorlLpl1-2 Resource LPlI-2 R/F RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource PUBLIC J. Whited, NRR ADAMS Accession No'.. ML12334A310 | | |
| * via e-mail OFFICE LPL 1-2/PM LPL 1-2/PM LPL 1-2/LA LPL1-2/BC LPL 1-2/PM NAME JWhited .IHughey ABaxter" MKhanna JHughey DATE 11/30/2012 12/412012 11/30/2012 12/512012 12/5/2012 OFFICIAL RECORD COPY 1 Agencywide Documents Access and Management System Accession No. ML 12062A148
| | ==SUBJECT:== |
| }} | | HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS (TAC NO. ME8113) |
| | |
| | ==Dear Mr. Joyce:== |
| | |
| | By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications and Facility Operating License for Hope Creek. The NRC staff has reviewed the request submitted by the licensee and has determined that additional information is required, as provided in the enclosure, in order to complete its review. |
| | The draft questions were sent to Mr. Paul Duke, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On November 30, 2012. Mr, Duke indicated that the licensee will submit a response by December 31,2012, If you have any questions, please contact me at (301) 415-3204 or via e-mail at John. Hughey@nrc.gov. |
| | po .J-I1r/lltcf'{}l-V'/ |
| | John D, Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-354 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc: Distribution via ListServ 1 Agencywide Documents Access and Management System Accession No. ML12062A148 |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NUMBER 50-354 By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request (LAR) for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications (TS) and Facility Operating License (FOL) for Hope Creek. The proposed changes are administrative in nature and fall into one of four categories: (1) correct typographical errors, (2) delete historical requirements that have expired, (3) make editorial changes to correct errors and/or omissions from previous license amendment requests, or (4) update component lists to reflect current plant design. The NRC staff has determined that additional information is needed to complete the review, as described below. |
| | RAI-01: On page 4 of Attachment 1 to the amendment request, PSEG requested to remove the requirement for an annual report for main steamline safety/relief valve challenges from TS Administrative Controls Section 6.9.1.5. The licensee stated that the requirement should have been deleted during the implementation of Amendment 161, which was issued with letter dated January 11, 2006,2 but it was not removed due to an oversight. |
| | After review, the NRC staff found that this reporting requirement was not requested to be removed in the associated LAR dated January 11, 2005. 3 No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR. |
| | RAI-02: On page 7 of Attachment 1 to the amendment request. PSEG requested to remove FOL License Condition 2.C.(13), "Safety Parameter Display System [SPDS] (Section 18.2, SSER No.5)," from the license for Hope Creek. Specifically, FOL License Condition 2.C.(13) requires PSEG to add certain parameters to the SPDS and have them operational prior to the earlier of 90 days after restart from the first refueling outage, or July 12,1988. |
| | 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML12062A148 2 ADAMS Accession No. ML060050496 3 ADAMS Accession No. ML050190207 Enclosure |
| | |
| | -2 Per License Condition 2.C.(13), the listed parameters are required to be operational in SPDS. No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR. |
| | RAI-03: On page 8 of Attachment 1 to the amendment request, PSEG requested to remove FOL License Condition 2.C.(22), "Steam Dryer," from the license for Hope Creek. |
| | Most of the specific conditions listed in FOL License Condition 2.C.(22) were completed after, at the latest, the second refueling outage following the implementation of the Extended Power Uprate, and are now historical. However, the NRC staff believes that one condition is still applicable. FOL License Condition 2.C.(22).2.e states, PSEG Nuclear LLC shall revise plant procedures to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facility's steam dryer inspection program with BWRVIP-139 [Steam Dryer Inspection and Flaw Evaluation Guidelines];4 and to identify the NRC Project Manager for the facility as the point of contact for providing power ascension testing information during power ascension. |
| | Reflecting long-term monitoring of plant parameters potentially indicative of steam dryer failure in plant procedures is a legal requirement per license condition 2.C.(22).2.e. No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR. |
| | 4 ADAMS Accession No. ML101270122 |
| | |
| | ' ML12334A310 |
| | * via e-mail OFFICE LPL 1-2/PM LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME JWhited .IHughey ABaxter" MKhanna JHughey DATE 11/30/2012 12/412012 11/30/2012 12/512012 12/5/2012}} |
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Category:Letter
MONTHYEARIR 05000272/20240032024-10-30030 October 2024
Integrated Inspection Report 05000272/2024003 and 05000311/2024003
ML24296B1932024-10-23023 October 2024
Project Manager Assignment
ML24295A3742024-10-23023 October 2024
Project Manager Assignment
IR 05000354/20240032024-10-23023 October 2024
Integrated Inspection Report 05000354/2024003
LR-N24-0068, Core Operating Limits Report - Cycle 282024-10-21021 October 2024
Core Operating Limits Report - Cycle 28
ML24291A0572024-10-17017 October 2024
License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1
LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024
Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)
LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024
2024 Annual 10 CFR 50.46 Report
LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024
Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
IR 05000272/20244022024-09-23023 September 2024
And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only)
ML24267A1082024-09-23023 September 2024
Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report
ML24255A8042024-09-11011 September 2024
Notification of Conduct of a Fire Protection Team Inspection
LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024
In-Service Inspection Activities
05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024
Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000354/20240052024-08-29029 August 2024
Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005)
IR 05000272/20240052024-08-29029 August 2024
Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2024005 and 05000311/2024005)
LR-N24-0044, Relief Request VR-042024-08-0606 August 2024
Relief Request VR-04
IR 05000354/20240022024-07-30030 July 2024
Integrated Inspection Report 05000354/2024002
IR 05000272/20240022024-07-30030 July 2024
Integrated Inspection Report 05000272/2024002 and 05000311/2024002
LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024
Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding
ML24200A0572024-07-18018 July 2024
Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves
NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024
– Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5
ML24197A0552024-07-15015 July 2024
Requalification Program Inspection
ML24145A1772024-07-15015 July 2024
And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary
05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024
Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)
LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024
License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves
IR 05000272/20245012024-06-12012 June 2024
And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501
ML24099A1572024-05-29029 May 2024
Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies
ML24150A0032024-05-28028 May 2024
Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement
ML24150A1002024-05-28028 May 2024
Core Operating Limits Report, Reload 25, Cycle 26, Revision 23
LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024
Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response
LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024
License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
ML24142A4072024-05-20020 May 2024
License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5
IR 05000272/20240102024-05-16016 May 2024
Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010
05000272/LER-2024-001, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger2024-05-0909 May 2024
Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger
IR 05000354/20240012024-05-0808 May 2024
Integrated Inspection Report 05000354/2024001
IR 05000354/20240102024-05-0707 May 2024
Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010
IR 05000272/20240012024-05-0707 May 2024
Integrated Inspection Report 05000272/2024001 and 05000311/2024001
LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024
Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage
LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024
2023 Annual Radioactive Effluent Release Report (ARERR)
LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024
2023 Annual Radiological Environmental Operating Report (AREOR)
LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024
Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000354/20243012024-04-10010 April 2024
Initial Operator Licensing Examination Report 05000354/2024301
LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024
Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000272/20240112024-04-0101 April 2024
And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011
LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024
And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal
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
05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024
Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram
2024-09-05
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24253A1942024-09-0909 September 2024
NRR E-mail Capture - Final Eeeb RAI - Hope Creek Amendment to Revise TS to Change Surveillance Interval to Accommodate 24-Month Fuel Cycle
IR 05000354/20240102024-05-0707 May 2024
Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010
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
ML24060A0492024-02-28028 February 2024
NRR E-mail Capture - Final Exhb RAI for Hope Creek, Salem 1 and 2 Amendment to Modify Exclusion Area Boundary
ML22333A9022022-11-29029 November 2022
NRR E-mail Capture - Final Iolb RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG
ML22318A1062022-11-14014 November 2022
Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000272/2023011 and 05000311/2023011
ML22290A2202022-10-17017 October 2022
NRR E-mail Capture - Final RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG
ML22055A0702022-02-22022 February 2022
NRR E-mail Capture - Final RAI - Salem 1-Relief Request Associated with Fourth Inservice Inspection (ISI) Interval Limited Examinations (L-2021-LLR-0085)
ML22006A3212022-01-0606 January 2022
NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink
ML21300A0222021-10-27027 October 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21068A4142021-03-0909 March 2021
NRR E-mail Capture - Final RAI for Salem Unit 1 LAR to Revise and Relocate Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report
ML21041A3972021-02-18018 February 2021
Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary)
ML21043A1442021-02-11011 February 2021
NRR E-mail Capture - Salem - Final RAI Alternative for Examination of ASME Section XI, Category B-B, Item Number B2.11and B2.12 (L-2020-LRR-0103)
ML21021A2592021-01-21021 January 2021
NRR E-mail Capture - Final RAI - Salem 1 - Steam Generator Tube Inspection Report
ML20295A4922020-10-21021 October 2020
NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131)
ML20281A5172020-10-13013 October 2020
Notification of Conduct of a Fire Protection Team Inspection
ML18267A1712018-09-21021 September 2018
NRR E-mail Capture - Final RAI from PRA Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140)
ML18264A0122018-09-20020 September 2018
NRR E-mail Capture - Final RAI from I&C Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140)
ML18263A1442018-09-12012 September 2018
NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101)
ML18250A3132018-09-0606 September 2018
NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140)
ML18250A3142018-09-0606 September 2018
NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101)
ML18171A3212018-06-20020 June 2018
NRR E-mail Capture - Final RAI: Revise Technical Specifications to Adopt TSTF-411 and 418 (L-2017-LLA-0442)
ML18150A6912018-05-30030 May 2018
NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542
ML18120A2482018-04-27027 April 2018
Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403
ML18094B0832018-04-0505 April 2018
Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29)
ML18067A1482018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation)
ML17348A6242017-12-14014 December 2017
NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002)
ML17348A9972017-12-14014 December 2017
NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002)
ML17349A0812017-12-14014 December 2017
NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur
ML17331A0072017-11-21021 November 2017
E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate
ML17348A6282017-11-21021 November 2017
NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002)
ML17324A2602017-11-17017 November 2017
NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls
ML17320A2152017-11-16016 November 2017
NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002)
ML17290B0132017-10-17017 October 2017
NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb
ML17222A1652017-08-10010 August 2017
NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502)
ML17212B1152017-07-31031 July 2017
Request for Additional Information - Salem Units 1 and 2 - Containment Fan Coil Unit Allowed Outage Time Amendment Request (CACs MF9364 and MF9365)
ML17199A1122017-07-18018 July 2017
Request for Additional Information - Salem Units 1 and 2 - Accident Monitoring Instrumentation License Amendment Request (CAC Nos. MF8859 & MF8860)
ML17192A1672017-07-11011 July 2017
Request for Additional Information - Salem Unit 1 - Steam Generator Tube Inspection Report
ML17181A1352017-06-29029 June 2017
NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70)
ML17164A4062017-06-13013 June 2017
NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462)
ML17115A4032017-05-0909 May 2017
Request for Additional Information Regarding Relief Request SC-14R-171 - Use of Code Cases N-695-1 and N-696-1
ML17027A3282017-02-27027 February 2017
Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies
ML16321A4642016-11-21021 November 2016
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements
ML16277A5142016-11-0303 November 2016
Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling
ML16271A2052016-11-0202 November 2016
Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves
ML16231A4272016-08-24024 August 2016
Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval
ML16217A4302016-08-17017 August 2016
Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade
ML16218A0052016-08-11011 August 2016
Request for Additional Information Concerning Request for an Extension to Enforcement Guidance Memorandum 12-001
2024-09-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 5, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS (TAC NO. ME8113)
Dear Mr. Joyce:
By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications and Facility Operating License for Hope Creek. The NRC staff has reviewed the request submitted by the licensee and has determined that additional information is required, as provided in the enclosure, in order to complete its review.
The draft questions were sent to Mr. Paul Duke, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On November 30, 2012. Mr, Duke indicated that the licensee will submit a response by December 31,2012, If you have any questions, please contact me at (301) 415-3204 or via e-mail at John. Hughey@nrc.gov.
po .J-I1r/lltcf'{}l-V'/
John D, Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Request for Additional Information cc: Distribution via ListServ 1 Agencywide Documents Access and Management System Accession No. ML12062A148
REQUEST FOR ADDITIONAL INFORMATION REQUEST TO CORRECT TECHNICAL SPECIFICATION AND FACILITY OPERATING LICENSE EDITORIAL ITEMS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NUMBER 50-354 By letter dated March 1, 2012,1 PSEG Nuclear LLC (PSEG, the licensee), submitted a license amendment request (LAR) for the Hope Creek Generating Station (Hope Creek). Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, PSEG requested a license amendment to correct editorial items in the Technical Specifications (TS) and Facility Operating License (FOL) for Hope Creek. The proposed changes are administrative in nature and fall into one of four categories: (1) correct typographical errors, (2) delete historical requirements that have expired, (3) make editorial changes to correct errors and/or omissions from previous license amendment requests, or (4) update component lists to reflect current plant design. The NRC staff has determined that additional information is needed to complete the review, as described below.
RAI-01: On page 4 of Attachment 1 to the amendment request, PSEG requested to remove the requirement for an annual report for main steamline safety/relief valve challenges from TS Administrative Controls Section 6.9.1.5. The licensee stated that the requirement should have been deleted during the implementation of Amendment 161, which was issued with letter dated January 11, 2006,2 but it was not removed due to an oversight.
After review, the NRC staff found that this reporting requirement was not requested to be removed in the associated LAR dated January 11, 2005. 3 No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR.
RAI-02: On page 7 of Attachment 1 to the amendment request. PSEG requested to remove FOL License Condition 2.C.(13), "Safety Parameter Display System [SPDS] (Section 18.2, SSER No.5)," from the license for Hope Creek. Specifically, FOL License Condition 2.C.(13) requires PSEG to add certain parameters to the SPDS and have them operational prior to the earlier of 90 days after restart from the first refueling outage, or July 12,1988.
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML12062A148 2 ADAMS Accession No. ML060050496 3 ADAMS Accession No. ML050190207 Enclosure
-2 Per License Condition 2.C.(13), the listed parameters are required to be operational in SPDS. No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR.
RAI-03: On page 8 of Attachment 1 to the amendment request, PSEG requested to remove FOL License Condition 2.C.(22), "Steam Dryer," from the license for Hope Creek.
Most of the specific conditions listed in FOL License Condition 2.C.(22) were completed after, at the latest, the second refueling outage following the implementation of the Extended Power Uprate, and are now historical. However, the NRC staff believes that one condition is still applicable. FOL License Condition 2.C.(22).2.e states, PSEG Nuclear LLC shall revise plant procedures to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facility's steam dryer inspection program with BWRVIP-139 [Steam Dryer Inspection and Flaw Evaluation Guidelines];4 and to identify the NRC Project Manager for the facility as the point of contact for providing power ascension testing information during power ascension.
Reflecting long-term monitoring of plant parameters potentially indicative of steam dryer failure in plant procedures is a legal requirement per license condition 2.C.(22).2.e. No justification for this change was provided in the LAR dated March 1, 2012, and a change of this type is not considered by the NRC staff to be editorial in nature as characterized in the LAR submittal. Please provide the rational for requesting this change in this LAR.
4 ADAMS Accession No. ML101270122
' ML12334A310
- via e-mail OFFICE LPL 1-2/PM LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME JWhited .IHughey ABaxter" MKhanna JHughey DATE 11/30/2012 12/412012 11/30/2012 12/512012 12/5/2012
