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| | number = ML101370559 | | | number = ML101370559 |
| | issue date = 06/09/2010 | | | issue date = 06/09/2010 |
| | title = Request for Additional Information for the Review of the Hope Creek Generating Station License Review Application (TAC No. ME1832) | | | title = Request for Additional Information for the Review of the Hope Creek Generating Station License Review Application |
| | author name = Brady B M | | | author name = Brady B |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| | addressee name = Joyce T | | | addressee name = Joyce T |
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| =Text= | | =Text= |
| {{#Wiki_filter:June 9, 2010 | | {{#Wiki_filter:June 9, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038 |
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| Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832) |
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| ==Dear Mr. Joyce:== | | ==Dear Mr. Joyce:== |
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| By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. NPF-57 for the Hope Creek Generating Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's request for additional information is included in the enclosure. Further requests for additional information may be issued in the future. | | By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. NPF-57 for the Hope Creek Generating Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs request for additional information is included in the enclosure. Further requests for additional information may be issued in the future. |
| | Items in the enclosure were provided to John Hufnagel and other members of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2981 or by e-mail at bennett.brady@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354 |
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| Items in the enclosure were provided to John Hufnagel and other members of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2981 or by e-mail at bennett.brady@nrc.gov. Sincerely, /RA/
| | ==Enclosure:== |
| Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354
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| ==Enclosure:==
| | As stated cc w/encl: See next page |
| As stated cc w/encl: See next page | |
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| ML101370559 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady S. Figueroa B. Pham B. Brady DATE 5/25/10 5/18/10 5/28/10 6/09/10 Letter to T. Joyce from B. Brady dated June 9, 2010 | | ML101370559 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady S. Figueroa B. Pham B. Brady DATE 5/25/10 5/18/10 5/28/10 6/09/10 Letter to T. Joyce from B. Brady dated June 9, 2010 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832) |
| DISTRIBUTION | | DISTRIBUTION: |
| : | | HARD COPY: |
| HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource ------------- BPham BBrady CEccleston REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI Hope Creek Generating Station cc: Mr. Robert Braun Senior Vice President Nuclear PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Plant Manager - Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 | | DLR RF E-MAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource BPham BBrady CEccleston REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI |
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| Mr. Michael Gallagher Vice President - License Renewal Projects Exelon Nuclear LLC 200 Exelon Way Kennett Square, PA 19348 | | Hope Creek Generating Station cc: |
| | Mr. Robert Braun Mr. Michael Gaffney Senior Vice President Nuclear Manager - Hope Creek Regulatory PSEG Nuclear LLC Assurance One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight Mr. Ali Fakhar PSEG Nuclear Manager, License Renewal P.O. Box 236 PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek Township Clerk PSEG Nuclear Lower Alloways Creek Township P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Mr. Paul Bauldauf, P.E., Asst. Director Plant Manager - Hope Creek Radiation Protection Programs PSEG Nuclear LLC NJ Department of Environmental One Alloway Creek Neck Road Protection and Energy, CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. Michael Gallagher Mr. Brian Beam Vice President - License Renewal Projects Board of Public Utilities Exelon Nuclear LLC 2 Gateway Center, Tenth Floor 200 Exelon Way Newark, NJ 07102 Kennett Square, PA 19348 Regional Administrator, Region I Mr. Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission Manager - Licensing 475 Allendale Road PSEG Nuclear LLC King of Prussia, PA 19406 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Paul Davison Vice President, Operations Support Mr. Gregory Sosson PSEG Nuclear LLC Director Corporate Engineering One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 |
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| Mr. Jeffrie J. Keenan, Esquire Manager - Licensing PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Gregory Sosson Director Corporate Engineering PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038Mr. Michael Gaffney Manager - Hope Creek Regulatory Assurance PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
| | Hope Creek Generating Station cc: |
| | Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079 |
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| Mr. Ali Fakhar Manager, License Renewal PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Township Clerk Lower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy, CN 415 Trenton, NJ 08625-0415
| | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832) |
| | RAI 3.1.2.2.4.1 |
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| Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102
| | ==Background:== |
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| Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
| | Hope Creek Generating Station (HCGS) License Renewal Application (LRA) Subsection 3.1.2.2.4, Paragraph 1 Standard Review Plan-License Renewal (SRP-LR) Subsection 3.1.2.2.4, Paragraph 1 SRP-LR Appendix A, Subsection A.1.2.3.4, Paragraph 1 LRA Subsection 3.1.2.2.4, Paragraph 1, addresses cracking due to stress corrosion cracking (SCC) or intergranular stress corrosion cracking (IGSCC) that could occur in the stainless steel or nickel alloy BWR top head enclosure vessel flange leak detection lines. The LRA states that Hope Creek Generating Station (HCGS) will use aging management program (AMP) B.2.1.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC and IWD (ISI) program, and AMP B.2.1.2, Water Chemistry, to manage the aging effects of cracking due to SCC or IGSCC in the stainless steel vessel flange leak detection line exposed to treated water. It also states that the HCGS ISI program uses a VT-2 visual examination of the line prior to reactor cavity drain down, as approved by a current relief request, prior to drain down during each refueling outage. |
| | SRP-LR Subsection 3.1.2.2.4, Paragraph 1, and GALL Report item IV.A1-10 (R-61) states that a plant-specific AMP is to be evaluated because existing programs may not be capable of mitigating or detecting crack initiation and growth due to SCC in the vessel flange leak detection line. |
| | SRP-LRA Appendix A, Subsection A.1.2.3.4, Paragraph 1, provides generic recommendations for the detection of aging effects program element of a plant-specific AMP. This paragraph states that detection of aging effects should occur before there is a loss of the structure and component intended function(s). |
| | Issue: |
| | The staff does not understand how a VT-2 visual examination of the vessel flange leak detection line, as described in the LRA, would be capable of detecting cracking in the line prior to a through-wall crack having occurred. Also, the relief request described in the LRA is approved only for the current ten-year ISI inspection interval, which does not extend into the period of extended operation; and there is no assurance that the relief request would either be made by HCGS or be approved by the staff during the period of extended operation. |
| | ENCLOSURE |
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| Mr. Paul Davison Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
| | Request: |
| | a) Explain how VT-2 examination will detect cracking in the vessel flange leak detection line prior to failure of the lines intended function of providing a reactor coolant pressure boundary. |
| | b) Explain how aging of the vessel flange leak detection line will be managed during the period of extended operation without referring to implementation of a relief request which has neither been requested nor approved for the period of extended operation. |
| | RAI 3.3.2.2.5.2 |
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| Hope Creek Generating Station cc: Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)
| | ==Background:== |
| RAI 3.1.2.2.4.1
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| ===Background===
| | HCGS LRA Subsection 3.3.2.2.5, Paragraph 2; Table 3.3.1, Item 3.3.1-12; Table 3.5.2-8, pages 3.5-176 SRP-LR Subsection 3.3.2.2.5, Paragraph 2 GALL Item VII.A4-1 HCGS LRA Subsection 3.3.2.2.5, Paragraph 2, states that HCGS will implement the Structures Monitoring Program to manage hardening and loss of strength due to elastomer degradation of the compressible joint seals (inflatable pool seals) in the reactor building exposed to treated water, and that the Structures Monitoring Program includes visual inspections of elastomer components to assure that existing environmental conditions are not causing material degradation that could result in loss of component intended function. Table 3.3.1, item 3.3.1-12 states that compressible joint seals in the reactor building have been aligned to the item based on material, environment, and aging effect. |
| : Hope Creek Generating Station (HCGS) License Renewal Application (LRA) Subsection 3.1.2.2.4, Paragraph 1 Standard Review Plan-License Renewal (SRP-LR) Subsection 3.1.2.2.4, Paragraph 1 SRP-LR Appendix A, Subsection A.1.2.3.4, Paragraph 1 LRA Subsection 3.1.2.2.4, Paragraph 1, addresses cracking due to stress corrosion cracking (SCC) or intergranular stress corrosion cracking (IGSCC) that could occur in the stainless steel or nickel alloy BWR top head enclosure vessel flange leak detection lines. The LRA states that Hope Creek Generating Station (HCGS) will use aging management program (AMP) B.2.1.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC and IWD (ISI) program, and AMP B.2.1.2, Water Chemistry, to manage the aging effects of cracking due to SCC or IGSCC in the stainless steel vessel flange leak detection line exposed to treated water. It also states that the HCGS ISI program uses a VT-2 visual examination of the line prior to reactor cavity drain down, as approved by a current relief request, prior to drain down during each refueling outage.
| | SRP-LR Subsection 3.3.2.2.5, Paragraph 2, applies for hardening and loss of strength due to elastomer degradation in elastomer linings of the filters, valves, and ion exchangers in spent fuel pool and cleanup systems (BWR and PWR) exposed to treated water or to treated borated water. GALL item VII.A4-1 associated with this SRP-LR paragraph recommends a plant-specific AMP that determines and assesses the qualified life of the linings in the environment is to be evaluated. |
| SRP-LR Subsection 3.1.2.2.4, Paragraph 1, and GALL Report item IV.A1-10 (R-61) states that a plant-specific AMP is to be evaluated because existing programs may not be capable of mitigating or detecting crack initiation and growth due to SCC in the vessel flange leak detection line. SRP-LRA Appendix A, Subsection A.1.2.3.4, Paragraph 1, provides generic recommendations for the "detection of aging effects" program element of a plant-specific AMP. This paragraph states that "detection of aging effects should occur before there is a loss of the structure and component intended function(s)." | | Issue: |
| Issue: The staff does not understand how a VT-2 visual examination of the vessel flange leak detection line, as described in the LRA, would be capable of detecting cracking in the line prior to a through-wall crack having occurred. Also, the relief request described in the LRA is approved only for the current ten-year ISI inspection interval, which does not extend into the period of extended operation; and there is no assurance that the relief request would either be made by HCGS or be approved by the staff during the period of extended operation.
| | Since the SRP recommends determination and assessment of a qualified life for the components associated with Subsection 3.3.2.2.5, Paragraph 2, it is not clear to the staff whether HCGS has determined a qualified life for the compressible joint seals (inflatable pool seals) that it has associated with this paragraph through the LRA Tables. It also is not clear whether visual inspection, alone, is capable of detecting hardening and loss of strength in the compressible joint seals that HCGS has associated with Subsection 3.3.2.2.5, Paragraph 2. |
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| Request: a) Explain how VT-2 examination will detect cracking in the vessel flange leak detection line prior to failure of the line's intended function of providing a reactor coolant pressure boundary. | | Request: |
| b) Explain how aging of the vessel flange leak detection line will be managed during the period of extended operation without referring to implementation of a relief request which has neither been requested nor approved for the period of extended operation.
| | Provide additional information to explain how the Structures Monitoring Program adequately manages the subject aging effects. Specifically, clarify whether HCGS has determined a qualified life for the compressible joint seals aligned with LRA Table 3.3.1, Item 3.3.1-12, and Subsection 3.3.2.2.5, Paragraph 2.}} |
| RAI 3.3.2.2.5.2
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| ===Background===
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| : HCGS LRA Subsection 3.3.2.2.5, Paragraph 2; Table 3.3.1, Item 3.3.1-12; Table 3.5.2-8, pages 3.5-176 SRP-LR Subsection 3.3.2.2.5, Paragraph 2 GALL Item VII.A4-1
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| HCGS LRA Subsection 3.3.2.2.5, Paragraph 2, states that HCGS will implement the Structures Monitoring Program to manage hardening and loss of strength due to elastomer degradation of the compressible joint seals (inflatable pool seals) in the reactor building exposed to treated water, and that the Structures Monitoring Program includes visual inspections of elastomer components to assure that existing environmental conditions are not causing material degradation that could result in loss of component intended function. Table 3.3.1, item 3.3.1-12 states that compressible joint seals in the reactor building have been aligned to the item based on material, environment, and aging effect.
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| | |
| SRP-LR Subsection 3.3.2.2.5, Paragraph 2, applies for hardening and loss of strength due to elastomer degradation in elastomer linings of the filters, valves, and ion exchangers in spent fuel pool and cleanup systems (BWR and PWR) exposed to treated water or to treated borated water. GALL item VII.A4-1 associated with this SRP-LR paragraph recommends a plant-specific AMP that determines and assesses the qualified life of the linings in the environment is to be evaluated.
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| Issue: Since the SRP recommends determination and assessment of a qualified life for the components associated with Subsection 3.3.2.2.5, Paragraph 2, it is not clear to the staff whether HCGS has determined a qualified life for the compressible joint seals (inflatable pool seals) that it has associated with this paragraph through the LRA Tables. It also is not clear whether visual inspection, alone, is capable of detecting hardening and loss of strength in the compressible joint seals that HCGS has associated with Subsection 3.3.2.2.5, Paragraph 2.
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| Request: Provide additional information to explain how the Structures Monitoring Program adequately manages the subject aging effects. Specifically, clarify whether HCGS has determined a qualified life for the compressible joint seals aligned with LRA Table 3.3.1, Item 3.3.1-12, and Subsection 3.3.2.2.5, Paragraph 2.}}
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Letter Sequence RAI |
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Results
Other: LR-N09-0162, PSEG Nuclear, Hope Creek Generating Station, Transmittal Letter, License Renewal Application, LR-N10-0234, 10 CFR 54.21(b) Review to Identify Any Current Licensing Basis (CLB) Changes Made Since Submittal of the License Renewal Application (LRA), ML092430373, ML092430374, ML092430384, ML092430386, ML092430387, ML092430388, ML092430389, ML092430390, ML092430484, ML092460442, ML092520185, ML092650382, ML092660174, ML092660447, ML100850462, ML101660452, ML102100544, ML111090416
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MONTHYEARLR-N09-0191, Information to Support NRC Staff Review of the Application for Renewed Operating License2009-08-18018 August 2009
Information to Support NRC Staff Review of the Application for Renewed Operating License
Project stage: Request
ML0924303742009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 2 of 3
Project stage: Other
ML0924303892009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix E
Project stage: Other
ML0924303842009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3 Through Appendix a
Project stage: Other
ML0924303862009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix B
Project stage: Other
ML0924303872009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix C
Project stage: Other
ML0924303902009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix F
Project stage: Other
ML0924304842009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3 of 3
Project stage: Other
ML0924303882009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 3, Appendix D
Project stage: Other
LR-N09-0162, PSEG Nuclear, Hope Creek Generating Station, Transmittal Letter, License Renewal Application2009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, Transmittal Letter, License Renewal Application
Project stage: Other
ML0924303732009-08-18018 August 2009
PSEG Nuclear, Hope Creek Generating Station, License Renewal Application, Volume 1 of 3
Project stage: Other
ML0924604422009-09-0303 September 2009
Delaware Citizen Comment on Salem Hope Creek License Renewal Application
Project stage: Other
ML0926601742009-09-0707 September 2009
Comment on License Renewal for Salem and Hope Creek Power Plants - Goodman
Project stage: Other
ML0926503822009-09-0808 September 2009
Citizen Comment on Salem Hope Creek License Renewal Application
Project stage: Other
ML0925201852009-09-0808 September 2009
Comments About Relicensing Salem and Hope Creek Reactors in Nj, Steven Hegedus
Project stage: Other
ML0926604472009-09-23023 September 2009
Hope Creek, E-mail from Ruth Panella Comments on License Renewal
Project stage: Other
ML1007704192010-03-17017 March 2010
Task Order No. 005 Under Delivery Order No. NRC-DR-03-09-061
Project stage: Acceptance Review
ML1008504622010-04-0606 April 2010
Project Manager Change for the License Renewal of Hope Creek Generating Station
Project stage: Other
ML1009703502010-04-14014 April 2010
License Renewal Application - Request for Additional Information for Section 2.2.5, Boral Monitoring Program
Project stage: RAI
ML1007503312010-04-15015 April 2010
Request for Additional Information Regarding Scoping and Screening Results for the Hope Creek Generating Station (Tac ME1832)
Project stage: RAI
ML1010205112010-04-27027 April 2010
License Renewal Application - Request for Additional Information for Section 2.1, Scoping and Screening Methodology
Project stage: RAI
ML1010601552010-05-14014 May 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application Identified During the Audit
Project stage: RAI
ML1013803162010-06-0101 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application Section 3.3.2
Project stage: RAI
ML1013806202010-06-0101 June 2010
Request for Additional Information Regarding Sections 4.6 and 4.7 of the Hope Creek Generating Station License Renewal Application
Project stage: RAI
ML1014501792010-06-0303 June 2010
Letter Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application
Project stage: RAI
ML1013801492010-06-0707 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Section 3.5
Project stage: RAI
ML1013705592010-06-0909 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Review Application
Project stage: RAI
ML1014600772010-06-10010 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC ME1832 and ME1836)
Project stage: RAI
ML1013707612010-06-14014 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application
Project stage: RAI
ML1016104482010-06-22022 June 2010
RAI for the Review of the Hope Creek Generating Station License Renewal Application for Fire Protection
Project stage: RAI
LR-N10-0234, 10 CFR 54.21(b) Review to Identify Any Current Licensing Basis (CLB) Changes Made Since Submittal of the License Renewal Application (LRA)2010-06-24024 June 2010
10 CFR 54.21(b) Review to Identify Any Current Licensing Basis (CLB) Changes Made Since Submittal of the License Renewal Application (LRA)
Project stage: Other
ML1016601502010-06-25025 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Open Cycle Cooling Water System Program and Structures
Project stage: RAI
ML1015906752010-06-25025 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Section 4.3
Project stage: RAI
ML1017500242010-06-29029 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Fiberglass Doors
Project stage: RAI
LR-N10-0211, Response to NRC Request for Additional Information, Dated June 3, 2010, Related to Sections 3.2.2, 3.3.2 and B.2.2.2 of License Renewal Application2010-06-30030 June 2010
Response to NRC Request for Additional Information, Dated June 3, 2010, Related to Sections 3.2.2, 3.3.2 and B.2.2.2 of License Renewal Application
Project stage: Response to RAI
ML1015804812010-06-30030 June 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Metal Fatigue of Reactor Coolant Pressure Boundary Program
Project stage: RAI
LR-N10-0242, Response to NRC Request for Additional Information, Dated June 9, 2010, Related to Sections 3.1.2 and 3.3.2 of License Renewal Application2010-07-0606 July 2010
Response to NRC Request for Additional Information, Dated June 9, 2010, Related to Sections 3.1.2 and 3.3.2 of License Renewal Application
Project stage: Response to RAI
LR-N10-0248, Response to NRC Request for Additional Information, Dated June 22, 2010, Related to Fire Protection License Renewal Application2010-07-19019 July 2010
Response to NRC Request for Additional Information, Dated June 22, 2010, Related to Fire Protection License Renewal Application
Project stage: Response to RAI
ML1020002932010-08-0303 August 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Bolting and Flow Element
Project stage: RAI
ML1015400542010-08-0606 August 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Buried Piping Inspection Program
Project stage: RAI
ML1020303982010-08-18018 August 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Primary Containment Valve Material
Project stage: RAI
ML1021005442010-08-19019 August 2010
Scoping and Screening Audit Summary Regarding Hope Creek Generating Station License Renewal Application
Project stage: Other
LR-N10-0317, Response to NRC Request for Additional Information Dated August 3, 2010, Related to Bolting and Flow Element, and Update to PSEG July 6, 2010, Response to NRC RAI Associated with RPV Leak Detection Line - License Renewal Application2010-08-26026 August 2010
Response to NRC Request for Additional Information Dated August 3, 2010, Related to Bolting and Flow Element, and Update to PSEG July 6, 2010, Response to NRC RAI Associated with RPV Leak Detection Line - License Renewal Application
Project stage: Response to RAI
ML1016604522010-09-0303 September 2010
Audit Report Regarding the Hope Creek Generating Station License Renewal Application
Project stage: Other
ML1027804222010-10-12012 October 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for Buried Piping
Project stage: RAI
ML1032805742010-12-13013 December 2010
Request for Additional Information for the Review of the Hope Creek Generating Station License Renewal Application for One Time Inspection and Selective Leaching
Project stage: RAI
ML1110904162011-05-0505 May 2011
Project Manager Change for the License Renewal of Hope Creek Generating Station
Project stage: Other
ML11144A2452011-06-10010 June 2011
Schedule Revision for the Review of the Hope Creek Generating Station License Renewal Application
Project stage: Approval
ML11117A2062011-07-20020 July 2011
Notice of Issuance of Renewed Facility Operating License No. NPF-57 for an Additional 20-Year Period
Project stage: Request
ML11116A1482011-07-20020 July 2011
Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station
Project stage: Approval
2010-06-24
[Table View] |
|
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Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024
Integrated Inspection Report 05000354/2023004
ML24030A8752024-02-0101 February 2024
Operator Licensing Examination Approval
ML24009A1022024-01-26026 January 2024
Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000354/20234012024-01-22022 January 2024
Material Control and Accounting Program Inspection Report 05000354/2023401
ML23341A1372024-01-16016 January 2024
Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning
ML23335A1122023-12-15015 December 2023
Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers
ML23307A1532023-12-15015 December 2023
NRC Investigation Report No. 1-2023-001
ML23270C0072023-11-29029 November 2023
Notice of Proposed Amendment to Decommissioning Trust Agreement
ML23324A3072023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000354/20230032023-11-0707 November 2023
Integrated Inspection Report 05000354/2023003
IR 05000272/20234022023-10-12012 October 2023
and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only)
LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023
Submittal of 2023 Annual 10 CFR 50.46 Report
LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023
and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement
ML23249A2612023-09-0606 September 2023
License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000354/20230052023-08-31031 August 2023
Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005)
ML23192A8212023-08-14014 August 2023
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location
IR 05000354/20230022023-08-0303 August 2023
Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001
IR 05000354/20230102023-08-0303 August 2023
Biennial Problem Identification and Resolution Inspection Report 05000354/2023010
LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023
Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1
LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023
Spent Fuel Cask Registration
LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023
Emergency Plan Document Revisions Implemented June 28, 2023
IR 05000354/20230112023-05-0101 May 2023
Commercial Grade Dedication Report 05000354/2023011
ML23121A1412023-05-0101 May 2023
Senior Reactor and Reactor Operator Initial License Examinations
LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023
2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station
LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023
2022 Annual Radioactive Effluent Release Report (ARERR)
IR 05000354/20230012023-04-26026 April 2023
Integrated Inspection Report 05000354/2023001
LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023
License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location
LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023
License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains
ML23087A1492023-04-17017 April 2023
NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek
ML23089A0942023-04-17017 April 2023
NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek
ML23103A3232023-04-13013 April 2023
Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89
ML23095A3682023-04-12012 April 2023
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023
Submittal of Hope Creek Generating Station Technical Specification Bases Changes
LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23086A0912023-03-24024 March 2023
NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations
LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023
and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums
ML23037A9712023-03-0909 March 2023
and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report
IR 05000354/20220062023-03-0101 March 2023
Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006)
LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023
and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments
LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023
Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges
LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023
Annual Property Insurance Status Report
LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023
Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717
IR 05000354/20220042023-01-24024 January 2023
Integrated Inspection Report 05000354/2022004
LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023
In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage
LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023
and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination
LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022
Emergency Plan Document Revisions Implemented November 21, 2022
LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022
Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments
ML22335A0412022-12-0101 December 2022
Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information
IR 05000354/20220032022-11-0303 November 2022
Integrated Inspection Report 05000354/2022003
2024-02-01
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML22006A3212022-01-0606 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
ML21041A3972021-02-18018 February 2021
Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary)
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)
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)
ML18250A3142018-09-0606 September 2018
NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101)
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)
ML17349A0812017-12-14014 December 2017
NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur
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)
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)
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)
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)
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
ML16007A1742016-05-31031 May 2016
Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error
ML16089A0792016-05-0505 May 2016
Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval
ML16124A5802016-05-0303 May 2016
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes
ML15055A3772015-03-10010 March 2015
and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57
ML14197A6192014-07-24024 July 2014
and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386)
ML14168A2352014-07-0202 July 2014
Request for Additional Information Regarding Flooding Hazard Reevaluation
ML13309B5922013-11-22022 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13168A2762013-08-12012 August 2013
Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228)
ML13193A2912013-07-22022 July 2013
Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031
ML13204A2532013-07-19019 July 2013
Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom
ML13190A2212013-07-0202 July 2013
RAIs for Hope Creek Regarding Response to Order EA-12-051
ML13154A4952013-06-0404 June 2013
Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station
ML12334A3102012-12-0505 December 2012
Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items
ML12310A1672012-11-0101 November 2012
Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5
ML1227901012012-10-0505 October 2012
Clarifying Information for Question No. 4 (with Attachment)
ML12212A1032012-08-0808 August 2012
and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information
ML12216A1792012-08-0303 August 2012
Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule
ML12213A6162012-07-30030 July 2012
Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule
ML1209002372012-03-29029 March 2012
and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information
ML12056A0512012-03-12012 March 2012
Enclosure 5 - Recommendation 9.3: Emergency Preparedness
ML12056A0482012-03-12012 March 2012
Enclosure 2 - Recommendation 2.1: Flooding
ML12056A0492012-03-12012 March 2012
Enclosure 3 - Recommendation 2.3: Seismic
ML12056A0472012-03-12012 March 2012
Enclosure 1 - Recommendation 2.1: Seismic
2022-01-06
[Table view] |
Text
June 9, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)
Dear Mr. Joyce:
By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. NPF-57 for the Hope Creek Generating Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs request for additional information is included in the enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were provided to John Hufnagel and other members of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2981 or by e-mail at bennett.brady@nrc.gov.
Sincerely,
/RA/
Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
As stated cc w/encl: See next page
ML101370559 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady S. Figueroa B. Pham B. Brady DATE 5/25/10 5/18/10 5/28/10 6/09/10 Letter to T. Joyce from B. Brady dated June 9, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)
DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource BPham BBrady CEccleston REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI
Hope Creek Generating Station cc:
Mr. Robert Braun Mr. Michael Gaffney Senior Vice President Nuclear Manager - Hope Creek Regulatory PSEG Nuclear LLC Assurance One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight Mr. Ali Fakhar PSEG Nuclear Manager, License Renewal P.O. Box 236 PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek Township Clerk PSEG Nuclear Lower Alloways Creek Township P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Mr. Paul Bauldauf, P.E., Asst. Director Plant Manager - Hope Creek Radiation Protection Programs PSEG Nuclear LLC NJ Department of Environmental One Alloway Creek Neck Road Protection and Energy, CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. Michael Gallagher Mr. Brian Beam Vice President - License Renewal Projects Board of Public Utilities Exelon Nuclear LLC 2 Gateway Center, Tenth Floor 200 Exelon Way Newark, NJ 07102 Kennett Square, PA 19348 Regional Administrator, Region I Mr. Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission Manager - Licensing 475 Allendale Road PSEG Nuclear LLC King of Prussia, PA 19406 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Paul Davison Vice President, Operations Support Mr. Gregory Sosson PSEG Nuclear LLC Director Corporate Engineering One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
Hope Creek Generating Station cc:
Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)
RAI 3.1.2.2.4.1
Background:
Hope Creek Generating Station (HCGS) License Renewal Application (LRA) Subsection 3.1.2.2.4, Paragraph 1 Standard Review Plan-License Renewal (SRP-LR) Subsection 3.1.2.2.4, Paragraph 1 SRP-LR Appendix A, Subsection A.1.2.3.4, Paragraph 1 LRA Subsection 3.1.2.2.4, Paragraph 1, addresses cracking due to stress corrosion cracking (SCC) or intergranular stress corrosion cracking (IGSCC) that could occur in the stainless steel or nickel alloy BWR top head enclosure vessel flange leak detection lines. The LRA states that Hope Creek Generating Station (HCGS) will use aging management program (AMP) B.2.1.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC and IWD (ISI) program, and AMP B.2.1.2, Water Chemistry, to manage the aging effects of cracking due to SCC or IGSCC in the stainless steel vessel flange leak detection line exposed to treated water. It also states that the HCGS ISI program uses a VT-2 visual examination of the line prior to reactor cavity drain down, as approved by a current relief request, prior to drain down during each refueling outage.
SRP-LR Subsection 3.1.2.2.4, Paragraph 1, and GALL Report item IV.A1-10 (R-61) states that a plant-specific AMP is to be evaluated because existing programs may not be capable of mitigating or detecting crack initiation and growth due to SCC in the vessel flange leak detection line.
SRP-LRA Appendix A, Subsection A.1.2.3.4, Paragraph 1, provides generic recommendations for the detection of aging effects program element of a plant-specific AMP. This paragraph states that detection of aging effects should occur before there is a loss of the structure and component intended function(s).
Issue:
The staff does not understand how a VT-2 visual examination of the vessel flange leak detection line, as described in the LRA, would be capable of detecting cracking in the line prior to a through-wall crack having occurred. Also, the relief request described in the LRA is approved only for the current ten-year ISI inspection interval, which does not extend into the period of extended operation; and there is no assurance that the relief request would either be made by HCGS or be approved by the staff during the period of extended operation.
ENCLOSURE
Request:
a) Explain how VT-2 examination will detect cracking in the vessel flange leak detection line prior to failure of the lines intended function of providing a reactor coolant pressure boundary.
b) Explain how aging of the vessel flange leak detection line will be managed during the period of extended operation without referring to implementation of a relief request which has neither been requested nor approved for the period of extended operation.
RAI 3.3.2.2.5.2
Background:
HCGS LRA Subsection 3.3.2.2.5, Paragraph 2; Table 3.3.1, Item 3.3.1-12; Table 3.5.2-8, pages 3.5-176 SRP-LR Subsection 3.3.2.2.5, Paragraph 2 GALL Item VII.A4-1 HCGS LRA Subsection 3.3.2.2.5, Paragraph 2, states that HCGS will implement the Structures Monitoring Program to manage hardening and loss of strength due to elastomer degradation of the compressible joint seals (inflatable pool seals) in the reactor building exposed to treated water, and that the Structures Monitoring Program includes visual inspections of elastomer components to assure that existing environmental conditions are not causing material degradation that could result in loss of component intended function. Table 3.3.1, item 3.3.1-12 states that compressible joint seals in the reactor building have been aligned to the item based on material, environment, and aging effect.
SRP-LR Subsection 3.3.2.2.5, Paragraph 2, applies for hardening and loss of strength due to elastomer degradation in elastomer linings of the filters, valves, and ion exchangers in spent fuel pool and cleanup systems (BWR and PWR) exposed to treated water or to treated borated water. GALL item VII.A4-1 associated with this SRP-LR paragraph recommends a plant-specific AMP that determines and assesses the qualified life of the linings in the environment is to be evaluated.
Issue:
Since the SRP recommends determination and assessment of a qualified life for the components associated with Subsection 3.3.2.2.5, Paragraph 2, it is not clear to the staff whether HCGS has determined a qualified life for the compressible joint seals (inflatable pool seals) that it has associated with this paragraph through the LRA Tables. It also is not clear whether visual inspection, alone, is capable of detecting hardening and loss of strength in the compressible joint seals that HCGS has associated with Subsection 3.3.2.2.5, Paragraph 2.
Request:
Provide additional information to explain how the Structures Monitoring Program adequately manages the subject aging effects. Specifically, clarify whether HCGS has determined a qualified life for the compressible joint seals aligned with LRA Table 3.3.1, Item 3.3.1-12, and Subsection 3.3.2.2.5, Paragraph 2.
