|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:June 25, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038 | | {{#Wiki_filter:June 25, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836) | | REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836) |
|
| |
|
| ==Dear Mr. Joyce:== | | ==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 for renewal of Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station Units 1 and 2, respectively. 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 for renewal of Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station Units 1 and 2, respectively. The staff of the U.S. |
| 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, | | 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. |
| /RA/ Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-272 and 50-311 | | 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. 50-272 and 50-311 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| As stated
| |
|
| |
|
| cc w/encl: See next page | | As stated cc w/encl: See next page |
| | |
| | ML101620190 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa BPham BBrady DATE 6/22/10 6/15/10 6/23/10 6/25/10 |
|
| |
|
| ML101620190 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa BPham BBrady DATE 6/22/10 6/15/10 6/23/10 6/25/10 Letter to T. Joyce from B. Brady dated June 25, 2010
| | Letter to T. Joyce from B. Brady dated June 25, 2010 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836) | | REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836) |
| 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 Salem Nuclear Generating Station, Units 1 and 2 cc: Mr. Robert Braun Senior Vice President Nuclear 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 |
|
| |
|
| 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 | | Salem Nuclear Generating Station, Units 1 and 2 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 |
|
| |
|
| Mr. Larry Wagner Plant Manager - Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
| | Salem Nuclear Generating Station, Units 1 and 2 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 |
|
| |
|
| Mr. Michael Gallagher Vice President - License Renewal Projects Exelon Nuclear LLC 200 Exelon Way Kennett Square, PA 19348 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
| | REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836) |
| | | RAI 3.3.2.2.10.6-01 |
| 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
| |
| | |
| Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102
| |
| | |
| Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
| |
| | |
| Mr. Paul Davison Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038
| |
| | |
| Salem Nuclear Generating Station, Units 1 and 2 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 SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836)
| |
| RAI 3.3.2.2.10.6-01 | |
|
| |
|
| ==Background:== | | ==Background:== |
|
| |
|
| SRP-LR Section 3.3.2.2.10, item 6 refers to Table 3.3.1, item 28 and GALL Report Item VII.G-9 and recommends further evaluation of a plant-specific program to manage loss of material due to pitting and crevice corrosion for copper alloy piping, piping components, and piping elements exposed to internal condensation. LRA Section 3.3.2.2.10.6 states that copper alloy fire protection system piping, piping components, and piping elements exposed to internal condensation are managed for loss of material due to pitting and crevice corrosion by the Fire Protection and Fire Water System Programs. Specifically, the Fire Protection Program is credited to manage loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted in LRA Table 3.3.2-12, pages 3.3-236, 239, and 243. Issue: | | SRP-LR Section 3.3.2.2.10, item 6 refers to Table 3.3.1, item 28 and GALL Report Item VII.G-9 and recommends further evaluation of a plant-specific program to manage loss of material due to pitting and crevice corrosion for copper alloy piping, piping components, and piping elements exposed to internal condensation. LRA Section 3.3.2.2.10.6 states that copper alloy fire protection system piping, piping components, and piping elements exposed to internal condensation are managed for loss of material due to pitting and crevice corrosion by the Fire Protection and Fire Water System Programs. Specifically, the Fire Protection Program is credited to manage loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted in LRA Table 3.3.2-12, pages 3.3-236, 239, and 243. |
| The description of the Fire Protection Program in LRA Section B.2.1.15 states that the program performs visual inspections of fire barriers and the external surfaces of the Halon and CO 2 systems, and includes performance testing of the diesel driven fire pump fuel supply lines. The description of the Fire Protection Program does not include criteria for inspections of the internal surfaces of components which could detect loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted listed in LRA Table 3.3.2- | | Issue: |
| : 12. Request:
| | The description of the Fire Protection Program in LRA Section B.2.1.15 states that the program performs visual inspections of fire barriers and the external surfaces of the Halon and CO2 systems, and includes performance testing of the diesel driven fire pump fuel supply lines. The description of the Fire Protection Program does not include criteria for inspections of the internal surfaces of components which could detect loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted listed in LRA Table 3.3.2-12. |
| Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the copper alloy components exposed to air/gas - wetted in LRA Table 3.3.2-12. | | Request: |
| | | Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the copper alloy components exposed to air/gas |
| RAI 3.3.2.12-02 | | - wetted in LRA Table 3.3.2-12. |
| | RAI 3.3.2.12-02 |
|
| |
|
| ==Background:== | | ==Background:== |
|
| |
|
| SRP-LR Table 3.3.1, item 54 recommends the "Compressed Air Monitoring Program" to manage loss of material for stainless steel piping, piping components, and piping elements exposed to internal condensation within the compressed air system. LRA Table 3.3.1, item 3.3.1-54 states that the Fire Protection Program will be substituted to manage loss of material due to pitting and crevice corrosion of the stainless steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for stainless steel spray nozzles, piping and fittings, and valve bodies in LRA Table 3.3.2-12, pages 3.3-238, 239, 240 and 245, where it references Table 3.3.1, item 3.3.1-54. | | SRP-LR Table 3.3.1, item 54 recommends the Compressed Air Monitoring Program to manage loss of material for stainless steel piping, piping components, and piping elements exposed to internal condensation within the compressed air system. LRA Table 3.3.1, item 3.3.1-54 states that the Fire Protection Program will be substituted to manage loss of material due to pitting and crevice corrosion of the stainless steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for stainless steel spray nozzles, piping and fittings, and valve bodies in LRA Table 3.3.2-12, pages 3.3-238, 239, 240 and 245, where it references Table 3.3.1, item 3.3.1-54. |
| | |
| SRP-LR Table 3.3.1, item 71 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel piping, piping components, and piping elements exposed to moist air or condensation. LRA Table 3.3.1, item 3.3.1-71 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for steel piping and fittings in LRA Table 3.3.2-12, page 3.3-235, where it references Table 3.3.1 item 3.3.1-71. Furthermore, in the same table and same page, the LRA also credited the Fire Water System Program for the same material, environment, and aging effect/mechanism combination.
| |
|
| |
|
| SRP-LR Table 3.3.1, item 72 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel HVAC ducting and components internal surfaces exposed to condensation. LRA Table 3.3.1, item 3.3.1-72 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the galvanized steel damper housing exposed to air/gas - wetted for the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for galvanized steel damper housing in LRA Table 3.3.2-12, page 3.3-227, where it references Table 3.3.1, item 3.3.1-72. | | SRP-LR Table 3.3.1, item 71 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel piping, piping components, and piping elements exposed to moist air or condensation. LRA Table 3.3.1, item 3.3.1-71 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for steel piping and fittings in LRA Table 3.3.2-12, page 3.3-235, where it references Table 3.3.1 item 3.3.1-71. Furthermore, in the same table and same page, the LRA also credited the Fire Water System Program for the same material, environment, and aging effect/mechanism combination. |
| | SRP-LR Table 3.3.1, item 72 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel HVAC ducting and components internal surfaces exposed to condensation. LRA Table 3.3.1, item 3.3.1-72 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the galvanized steel damper housing exposed to air/gas |
| | - wetted for the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for galvanized steel damper housing in LRA Table 3.3.2-12, page 3.3-227, where it references Table 3.3.1, item 3.3.1-72. |
| Issue: | | Issue: |
| The Compressed Air Monitoring Program includes control of contaminants in order to limit loss of material due to corrosion, and leakage testing to detect loss of material. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program includes inspections of the internal surfaces of piping and components to detect loss of material. LRA Section B.2.1.15 states, "The program also provides for aging management of external surfaces of the Halon and carbon dioxide fire suppression system components through periodic functional tests and visual inspections for any loss of material." The description of the Fire Protection Program in LRA Section B.2.1.15 does not include criteria for inspections of the internal surfaces of components or leakage testing which could detect loss of material. It is not clear to the staff how the Fire Protection Program is adequate to manage loss of material for the steel and stainless steel components for which is it is credited in Table 3.3.2-12 under items 3.3.1-54, 3.3.1-71, and 3.3.1-72. | | The Compressed Air Monitoring Program includes control of contaminants in order to limit loss of material due to corrosion, and leakage testing to detect loss of material. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program includes inspections of the internal surfaces of piping and components to detect loss of material. LRA Section B.2.1.15 states, The program also provides for aging management of external surfaces of the Halon and carbon dioxide fire suppression system components through periodic functional tests and visual inspections for any loss of material. The description of the Fire Protection Program in LRA Section B.2.1.15 does not include criteria for inspections of the internal surfaces of components or leakage testing which could detect loss of material. It is not clear to the staff how the Fire Protection Program is adequate to manage loss of material for the steel and stainless steel components for which is it is credited in Table 3.3.2-12 under items 3.3.1-54, 3.3.1-71, and 3.3.1-72. |
| Request: Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the various steel and stainless steel components exposed to an internal environment of air/gas - wetted discussed above.}} | | Request: |
| | Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the various steel and stainless steel components exposed to an internal environment of air/gas - wetted discussed above.}} |
Letter Sequence RAI |
|---|
TAC:ME1834, Control Room Habitability (Approved, Closed) TAC:ME1836, Control Room Habitability (Approved, Closed) |
Results
Other: LR-N16-0144, Completion of Activities to Support Entry Into the Period of Extended Operation, ML092400531, ML092400532, ML092430231, ML092460442, ML092470039, ML092520185, ML092650382, ML092660174, ML092660447, ML100850459, ML102280211, ML102430586, ML11125A024
|
MONTHYEARLR-N09-0192, 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
LR-N09-0161, PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, Transmittal of License Renewal Application2009-08-18018 August 2009
PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, Transmittal of License Renewal Application
Project stage: Request
ML0924005312009-08-18018 August 2009
PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 2 of 3
Project stage: Other
ML0924302312009-08-18018 August 2009
PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 1 of 3
Project stage: Other
ML0924005322009-08-18018 August 2009
PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 3 of 3
Project stage: Other
ML0924604422009-09-0303 September 2009
Delaware Citizen Comment on Salem Hope Creek License Renewal Application
Project stage: Other
ML0924700392009-09-0404 September 2009
Comment on Salem - Hope Creek License Renewal Applications from Citizen
Project stage: Other
ML0926601742009-09-0707 September 2009
Comment on License Renewal for Salem and Hope Creek Power Plants - Goodman
Project stage: Other
ML0925201852009-09-0808 September 2009
Comments About Relicensing Salem and Hope Creek Reactors in Nj, Steven Hegedus
Project stage: Other
ML0926503822009-09-0808 September 2009
Citizen Comment on Salem Hope Creek License Renewal Application
Project stage: Other
ML0926604472009-09-23023 September 2009
Hope Creek, E-mail from Ruth Panella Comments on License Renewal
Project stage: Other
ML1008502062010-03-24024 March 2010
Task Order No. 004 Under Delivery Order No. NRC-DR-03-09-061
Project stage: Acceptance Review
ML1008504592010-04-0606 April 2010
Project Manager Change for the License Renewal of Salem Nuclear Generating Station, Units 1 and 2 (TAC No. ME1834 and ME1836)
Project stage: Other
ML1007606612010-04-14014 April 2010
RAI Regarding Balance of Plant Scoping and Screening Results for the Salem Nuclear Generating Station Units 1 & 2 (Tac Nos. ME1834 and ME1836)
Project stage: RAI
ML1013805112010-05-24024 May 2010
Request for Additional Information for the Salem Generating Station, Units 1 and 2, License Renewal Application, Section 3.3.2 (TAC Nos ME1836 and ME1834)
Project stage: RAI
LR-N10-0191, Response to NRC Request for Additional Information Dated April 30, 2010, Regarding Scoping and Screening Methodology for License Renewal Application2010-05-28028 May 2010
Response to NRC Request for Additional Information Dated April 30, 2010, Regarding Scoping and Screening Methodology for License Renewal Application
Project stage: Response to RAI
ML1014600612010-06-0707 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Section 3.5 (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1014400812010-06-10010 June 2010
Request for Additional Information for the Review of the Salem Generating Station, Unit 1 and Unit 2, License Renewal Application Identified During the Audit (TAC ME1836 and ME1834)
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
ML1014810092010-06-11011 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application
Project stage: RAI
ML1015504712010-06-11011 June 2010
RAI for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Sections 3.1.2 and 3.3.2 (TAC No ME1834/ME1836)
Project stage: RAI
ML1014801892010-06-14014 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Sections 4.3 and 4.4 (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1013905372010-06-17017 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application(Tac Nos ME1834, ME1836)
Project stage: RAI
ML1016201902010-06-25025 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2, License Renewal Application (Tac ME1834/ME1836)
Project stage: RAI
ML1016804022010-06-29029 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2, License Renewal Application Regarding Subsection 3.1.2.2.14 (TAC ME1834/ME1836)
Project stage: RAI
ML1014807262010-06-30030 June 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Section B.3.1.1 (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1017203642010-07-12012 July 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1&2 LRA Regarding ASME Section XI ISI, Subsections Iwb,Iwc, and Iwd (TAC Nos. ME1834/ME1836)
Project stage: RAI
LR-N10-0243, Response to NRC Request for Additional Information Dated June 14, 2010, Related to Sections 4.3 and 4.4 License Renewal Application2010-07-13013 July 2010
Response to NRC Request for Additional Information Dated June 14, 2010, Related to Sections 4.3 and 4.4 License Renewal Application
Project stage: Response to RAI
ML1019504872010-07-19019 July 2010
Request for Additional Information for the Salem Generating Station, Unit 1 and Unit 2, License Renewal Application, Section 4.6 (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1019606342010-07-23023 July 2010
Request for Additional Information for the Salem Generating Station, Unit 1 and Unit 2, License Renewal Application (TAC ME1834 and ME1836)
Project stage: RAI
ML1019304962010-07-30030 July 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC No. ME1834 and Me 1836)
Project stage: RAI
ML1019504792010-08-0303 August 2010
Request for Additional Information Regarding ASME Section XI, Subsection IWE for the Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1019704742010-08-0303 August 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Bolting Integrity (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1015402422010-08-0606 August 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application for Buried Piping Inspection Program (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1020004042010-08-0909 August 2010
Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC Nos. ME1834 and ME1836)
Project stage: RAI
LR-N10-0295, Responses to NRC Requests for Additional Information Dated July 12, 2010, July 19, 2010 and July 23, 2010 Related to Various Sections of License Renewal Application2010-08-10010 August 2010
Responses to NRC Requests for Additional Information Dated July 12, 2010, July 19, 2010 and July 23, 2010 Related to Various Sections of License Renewal Application
Project stage: Response to RAI
ML1020304172010-08-19019 August 2010
RAI Regarding the Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC ME1834 & ME1836)
Project stage: RAI
ML1022802112010-08-25025 August 2010
Scoping and Screening Audit Summary Regarding the Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application
Project stage: Other
LR-N10-0313, Responses to Request for Additional Information Dated 08/03/10, Related to Bolting Integrity and 07/30/10 to Steam Generators and Question Posed During Region 1 Inspection, Regarding License Renewal Application2010-08-26026 August 2010
Responses to Request for Additional Information Dated 08/03/10, Related to Bolting Integrity and 07/30/10 to Steam Generators and Question Posed During Region 1 Inspection, Regarding License Renewal Application
Project stage: Response to RAI
LR-N10-0322, Response to NRC Request for Additional Information, Dated August 6, 2010 Related to the Buried Piping Inspection Program Associated with License Renewal Application2010-09-0707 September 2010
Response to NRC Request for Additional Information, Dated August 6, 2010 Related to the Buried Piping Inspection Program Associated with License Renewal Application
Project stage: Response to RAI
ML1024600782010-09-29029 September 2010
RAI for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application (TAC Nos. ME1834 and ME1836)
Project stage: RAI
ML1026003402010-10-12012 October 2010
RAI for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application for Buried Piping Inspection Program (TAC No. ME1834 and ME1836)
Project stage: RAI
ML1029102492010-10-25025 October 2010
Request for Additional Information for Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application on Structures Monitoring (TAC No. ME1834 and ME1836)
Project stage: RAI
ML1029300492010-11-0404 November 2010
Request for Additional Information for Salem Nuclear Generating Station, Units 1 and 2, LRA on Primary Water Stress Corrosion Cracking in Steam Generator Tube-to-Tube Sheet Welds
Project stage: RAI
ML1030101002010-11-0404 November 2010
Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station, Units 1 and 2
Project stage: Approval
ML1031201722010-11-0404 November 2010
Safety Evaluation Report with Open Items Related to the License Renewal of Salem Nuclear Generating Station, Units 1 and 2
Project stage: Approval
ML1024305862010-11-0909 November 2010
Audit Report Regarding the Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application (TAC Nos. ME1834 and ME1836)
Project stage: Other
ML1028101942010-11-22022 November 2010
RAI for Salem Nuclear Generating Station Units 1 and 2 LRA for Use of Westems Program in Metal Fatigue Analysis
Project stage: RAI
ML1032700762010-12-10010 December 2010
RAI for Salem Nuclear Generating Station Units 1 and 2 LRA
Project stage: RAI
LR-N10-0414, Response to NRC Request for Additional Information, Dated October 25, 2010, Related to Structures Monitoring Associated with License Renewal Application2010-12-14014 December 2010
Response to NRC Request for Additional Information, Dated October 25, 2010, Related to Structures Monitoring Associated with License Renewal Application
Project stage: Response to RAI
2010-06-11
[Table View] |
Similar Documents at Salem |
|---|
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
LR-N24-0068, Core Operating Limits Report - Cycle 282024-10-21021 October 2024
Core Operating Limits Report - Cycle 28
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)
ML24267A1082024-09-23023 September 2024
Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report
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)
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)
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
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
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
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
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 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-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024
2023 Annual Radiological Environmental Operating Report (AREOR)
LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024
2023 Annual Radioactive Effluent Release Report (ARERR)
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
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
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
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
ML24071A2132024-03-12012 March 2024
Senior Reactor and Reactor Operator Initial License Examinations
LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024
Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report
LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024
Spent Fuel Cask Registration
IR 05000272/20230062024-02-28028 February 2024
Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023006 and 05000311/2023006
IR 05000272/20244012024-02-26026 February 2024
And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only)
LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024
In-Service Inspection Activities
IR 05000272/20230042024-02-0505 February 2024
Integrated Inspection Report 05000272/2023004 and 05000311/2023004
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 05000272/20234012024-01-22022 January 2024
Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401
ML24004A1542024-01-0808 January 2024
Notification of Conduct of a Fire Protection Team Inspection
LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023
Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days
LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023
Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion
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
ML24250A0582023-11-14014 November 2023
PSEG to Marine Mammal Stranding Center, Salem Sea Turtle Stranding Response Services
IR 05000272/20230032023-11-13013 November 2023
Integrated Inspection Report 05000272/2023003 and 05000311/2023003
LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023
Core Operating Limits Report Cycle 30
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)
IR 05000272/20230102023-10-12012 October 2023
Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010
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 05000272/20230052023-08-31031 August 2023
Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005)
ML23233A0762023-08-21021 August 2023
Requalification Program Inspection
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
2024-09-23
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARIR 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)
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
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
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)
ML18250A3132018-09-0606 September 2018
NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140)
ML18171A3212018-06-20020 June 2018
NRR E-mail Capture - Final RAI: Revise Technical Specifications to Adopt TSTF-411 and 418 (L-2017-LLA-0442)
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)
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
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
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
ML16218A0052016-08-11011 August 2016
Request for Additional Information Concerning Request for an Extension to Enforcement Guidance Memorandum 12-001
ML16195A4492016-07-14014 July 2016
Request for Additional Information Regarding Chilled Water System Modifications
ML16188A4152016-07-0707 July 2016
Request for Additional Information Aging Management Program Plan for Reactor Vessel Internals
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
ML16013A1592016-02-17017 February 2016
Request for Additional Information Regarding Chilled Water System Modifications
ML15287A1412015-11-0202 November 2015
Request for Additional Information License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems
ML15287A1052015-11-0202 November 2015
Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling) (CAC Nos. MF5831 & MF5832)
ML15299A3832015-10-29029 October 2015
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request Regarding Chilled Water System Modification
ML15069A1812015-03-31031 March 2015
Request for Additional Information Aging Management Program Plan for Reactor Vessel Internals (TAC Nos. MF5149 and MF5150)
ML15075A2602015-03-24024 March 2015
Request for Additional Information Spring 2014 Steam Generator Tube Inspections
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)
ML14168A2422014-06-28028 June 2014
Request for Additional Information Regarding Flooding Hazard Reevaluation
ML14135A2912014-06-0202 June 2014
RAI Regarding Request for Relief SC-I4R-140 from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection
ML14086A6362014-04-30030 April 2014
Request for Additional Information Regarding Core Operating Limits Report
ML14066A2952014-03-0606 March 2014
Licensed Operator Positive Fitness-For-Duty-Test (FY14)
ML13330A5672013-11-22022 November 2013
Request for Additional Information: Salem Units 1 and 2 - Relief Request SC-14R-133 Repair of Service Water Piping (TAC MF1375 & 1376)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13304B9362013-10-29029 October 2013
Request for Additional Information: Salem Units 1 and 2 - Relief Request SC-14R-133 Repair of Service Water Piping (TAC MF1375 & 1376)
ML13270A4142013-10-17017 October 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 (TAC Nos. MF0913 and Mf
ML13249A0112013-09-0505 September 2013
Weko Seal Relief Request RAI
ML13196A3382013-07-15015 July 2013
2013 Decommissioning Fund Report RAI
ML13192A2322013-07-11011 July 2013
Draft Request for Additional Information Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Pool Instrumentation.
ML13186A1672013-07-11011 July 2013
Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML13179A3032013-06-28028 June 2013
RAIs for Salem Regarding Response to Order EA-12-051 (SFP Instrumentation)
ML13137A4882013-06-0505 June 2013
Request for Additional Information Relief Request SC-l4R-133
ML13149A0862013-06-0505 June 2013
Request for Additional Information Decommissioning Funding Status Report
2024-03-20
[Table view] |
Text
June 25, 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 SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836)
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 for renewal of Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station Units 1 and 2, respectively. 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. 50-272 and 50-311
Enclosure:
As stated cc w/encl: See next page
ML101620190 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa BPham BBrady DATE 6/22/10 6/15/10 6/23/10 6/25/10
Letter to T. Joyce from B. Brady dated June 25, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836)
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
Salem Nuclear Generating Station, Units 1 and 2 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
Salem Nuclear Generating Station, Units 1 and 2 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 SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (TAC NO ME1834 / ME 1836)
RAI 3.3.2.2.10.6-01
Background:
SRP-LR Section 3.3.2.2.10, item 6 refers to Table 3.3.1, item 28 and GALL Report Item VII.G-9 and recommends further evaluation of a plant-specific program to manage loss of material due to pitting and crevice corrosion for copper alloy piping, piping components, and piping elements exposed to internal condensation. LRA Section 3.3.2.2.10.6 states that copper alloy fire protection system piping, piping components, and piping elements exposed to internal condensation are managed for loss of material due to pitting and crevice corrosion by the Fire Protection and Fire Water System Programs. Specifically, the Fire Protection Program is credited to manage loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted in LRA Table 3.3.2-12, pages 3.3-236, 239, and 243.
Issue:
The description of the Fire Protection Program in LRA Section B.2.1.15 states that the program performs visual inspections of fire barriers and the external surfaces of the Halon and CO2 systems, and includes performance testing of the diesel driven fire pump fuel supply lines. The description of the Fire Protection Program does not include criteria for inspections of the internal surfaces of components which could detect loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted listed in LRA Table 3.3.2-12.
Request:
Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the copper alloy components exposed to air/gas
- wetted in LRA Table 3.3.2-12.
RAI 3.3.2.12-02
Background:
SRP-LR Table 3.3.1, item 54 recommends the Compressed Air Monitoring Program to manage loss of material for stainless steel piping, piping components, and piping elements exposed to internal condensation within the compressed air system. LRA Table 3.3.1, item 3.3.1-54 states that the Fire Protection Program will be substituted to manage loss of material due to pitting and crevice corrosion of the stainless steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for stainless steel spray nozzles, piping and fittings, and valve bodies in LRA Table 3.3.2-12, pages 3.3-238, 239, 240 and 245, where it references Table 3.3.1, item 3.3.1-54.
SRP-LR Table 3.3.1, item 71 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel piping, piping components, and piping elements exposed to moist air or condensation. LRA Table 3.3.1, item 3.3.1-71 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for steel piping and fittings in LRA Table 3.3.2-12, page 3.3-235, where it references Table 3.3.1 item 3.3.1-71. Furthermore, in the same table and same page, the LRA also credited the Fire Water System Program for the same material, environment, and aging effect/mechanism combination.
SRP-LR Table 3.3.1, item 72 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel HVAC ducting and components internal surfaces exposed to condensation. LRA Table 3.3.1, item 3.3.1-72 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the galvanized steel damper housing exposed to air/gas
- wetted for the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for galvanized steel damper housing in LRA Table 3.3.2-12, page 3.3-227, where it references Table 3.3.1, item 3.3.1-72.
Issue:
The Compressed Air Monitoring Program includes control of contaminants in order to limit loss of material due to corrosion, and leakage testing to detect loss of material. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program includes inspections of the internal surfaces of piping and components to detect loss of material. LRA Section B.2.1.15 states, The program also provides for aging management of external surfaces of the Halon and carbon dioxide fire suppression system components through periodic functional tests and visual inspections for any loss of material. The description of the Fire Protection Program in LRA Section B.2.1.15 does not include criteria for inspections of the internal surfaces of components or leakage testing which could detect loss of material. It is not clear to the staff how the Fire Protection Program is adequate to manage loss of material for the steel and stainless steel components for which is it is credited in Table 3.3.2-12 under items 3.3.1-54, 3.3.1-71, and 3.3.1-72.
Request:
Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the various steel and stainless steel components exposed to an internal environment of air/gas - wetted discussed above.
