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| | number = ML063340284 | | | number = ML063340284 |
| | issue date = 12/20/2006 | | | issue date = 12/20/2006 |
| | title = RAI Inservice Inspection Program Relief Request (TAC Nos. MD1052 and MD1053) | | | title = RAI Inservice Inspection Program Relief Request |
| | author name = Bailey S N | | | author name = Bailey S |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLB | | | author affiliation = NRC/NRR/ADRO/DORL/LPLB |
| | addressee name = Levis W | | | addressee name = Levis W |
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| =Text= | | =Text= |
| {{#Wiki_filter:December 20, 2006Mr. William LevisSenior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X09 Post Office Box 236 Hancocks Bridge, NJ 08038 | | {{#Wiki_filter:December 20, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X09 Post Office Box 236 Hancocks Bridge, NJ 08038 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SALEM NUCLEAR GENERATING STATION, UNIT NO. 2, REQUEST FORADDITIONAL INFORMATION RE: INSERVICE INSPECTION PROGRAM RELIEF REQUESTS (TAC NOS. MD1052 AND MD1053) | | SALEM NUCLEAR GENERATING STATION, UNIT NO. 2, REQUEST FOR ADDITIONAL INFORMATION RE: INSERVICE INSPECTION PROGRAM RELIEF REQUESTS (TAC NOS. MD1052 AND MD1053) |
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| ==Dear Mr. Levis:== | | ==Dear Mr. Levis:== |
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| On March 21, 2006, PSEG Nuclear LLC (PSEG), the licensee for the Salem NuclearGenerating Station, Unit No. 2, requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, for the inservice inspection (ISI) of Class 1 and Class 2 components. PSEG stated that it had conducted examinations as part of the second ten-year interval ISI program to the extent practical; however, coverage for certain weld examinations was less than required by the ASME Code. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the questions in the enclosure to this letter are necessary in order for the staff to complete its review. The enclosure was sent via e-mail to PSEG on October 19, 2006, to see whether the questions were understandable, whether the regulatory bases were clear, and whether the information was already docketed. PSEG indicated that no clarifications were needed. Please provide a response to the enclosed questions within 30 days of the date of this letter in order to allow the NRC staff to complete a timely review of the relief requests. This request was discussed with Mr. James Mallon of your staff on December 12, 2006. If you have questions about this request, please contact me at (301) 415-1321.Sincerely,/RA/Stewart N. Bailey, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-311 | | On March 21, 2006, PSEG Nuclear LLC (PSEG), the licensee for the Salem Nuclear Generating Station, Unit No. 2, requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, for the inservice inspection (ISI) of Class 1 and Class 2 components. PSEG stated that it had conducted examinations as part of the second ten-year interval ISI program to the extent practical; however, coverage for certain weld examinations was less than required by the ASME Code. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the questions in the enclosure to this letter are necessary in order for the staff to complete its review. The enclosure was sent via e-mail to PSEG on October 19, 2006, to see whether the questions were understandable, whether the regulatory bases were clear, and whether the information was already docketed. PSEG indicated that no clarifications were needed. Please provide a response to the enclosed questions within 30 days of the date of this letter in order to allow the NRC staff to complete a timely review of the relief requests. This request was discussed with Mr. James Mallon of your staff on December 12, 2006. If you have questions about this request, please contact me at (301) 415-1321. |
| | Sincerely, |
| | /RA/ |
| | Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next page
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| ML063340284OFFICELPL1-2/PMLPL1-2/LADE/CPNB/BCLPL1-2/BCNAMESBaileyCRaynorTChan*HChernoff DATE12/15/0612/15/068/24/06, 9/25/0612/20/06* by memo Salem Nuclear Generating Station, Unit No. 2 cc:
| | Request for Additional Information cc w/encl: See next page |
| Mr. Dennis WinchesterVice President - Nuclear Assessment PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Thomas P. JoyceSite Vice President - Salem PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George H. GellrichPlant Support Manager PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Carl J. FrickerPlant Manager - Salem PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038Mr. James MallonManager - Licensing 200 Exelon Way, KSA 3-E Kennett Square, PA 19348Mr. Steven MannonManager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038Jeffrie J. Keenan, EsquirePSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038Township ClerkLower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038Mr. Paul Bauldauf, P.E., Asst. DirectorRadiation Protection Programs NJ Department of Environmental Protection and Energy
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| CN 415 Trenton, NJ 08625-0415Mr. Brian BeamBoard of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102Regional Administrator, Region IU.S. Nuclear Regulatory Commission | | ML063340284 OFFICE LPL1-2/PM LPL1-2/LA DE/CPNB/BC LPL1-2/BC NAME SBailey CRaynor TChan* HChernoff DATE 12/15/06 12/15/06 8/24/06, 9/25/06 12/20/06 |
| | * by memo Salem Nuclear Generating Station, Unit No. 2 cc: |
| | Mr. Dennis Winchester Township Clerk Vice President - Nuclear Assessment Lower Alloways Creek Township PSEG Nuclear Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Thomas P. Joyce Radiation Protection Programs Site Vice President - Salem NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. George H. Gellrich Mr. Brian Beam Plant Support Manager Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Carl J. Fricker U.S. Nuclear Regulatory Commission Plant Manager - Salem 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. James Mallon U.S. Nuclear Regulatory Commission Manager - Licensing Drawer 0509 200 Exelon Way, KSA 3-E Hancocks Bridge, NJ 08038 Kennett Square, PA 19348 Mr. Steven Mannon Manager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 |
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| 475 Allendale Road King of Prussia, PA 19406Senior Resident InspectorSalem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 REQUEST FOR ADDITIONAL INFORMATIONREQUESTS FOR RELIEF REGARDING EXAMINATION COVERAGESECOND TEN-YEAR INSERVICE INSPECTION INTERVAL SALEM NUCLEAR GENERATING STATION, UNIT NO. 2DOCKET NO. 50-311On March 21, 2006, PSEG Nuclear LLC (PSEG), the licensee for the Salem NuclearGenerating Station (Salem), Unit No. 2, requested relief from certain requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
| | REQUEST FOR ADDITIONAL INFORMATION REQUESTS FOR RELIEF REGARDING EXAMINATION COVERAGE SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 On March 21, 2006, PSEG Nuclear LLC (PSEG), the licensee for the Salem Nuclear Generating Station (Salem), Unit No. 2, requested relief from certain requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), |
| Section XI, for the inservice inspection (ISI) of Class 1 and Class 2 components. PSEG stated that it had conducted examinations as part of the Second Ten-Year Interval ISI Program to the extent practical; however, coverage for certain weld examinations was less than required by the Code. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the following questions are necessary in order for the staff to complete its review:Questions on Relief Request S2-I2-RR-B01: | | Section XI, for the inservice inspection (ISI) of Class 1 and Class 2 components. PSEG stated that it had conducted examinations as part of the Second Ten-Year Interval ISI Program to the extent practical; however, coverage for certain weld examinations was less than required by the Code. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the following questions are necessary in order for the staff to complete its review: |
| 1.1Request for Relief S2-I2-RR-B01, Part B, Examination Category B-B, PressureRetaining Welds in Vessels Other than Reactor Vessels1.1(a)For weld 2-PZR-CIRC DUH, the information submitted by the licensee is not sufficient todemonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support the determination that the inspection of this weld is limited and impractical.1.2Request for Relief S2-I2-RR-B01, Part C, Examination Category B-D, Full PenetrationWelds of Nozzles in Vessels1.2(a)For certain nozzle welds, information submitted by the licensee is not sufficient todemonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by licensee identification numbers shown below.31-STG-1220-IRS29-STG-1230-IRS29-STG-1240-IRS29-STG-1220-IRS31-STG-1240-IRS29-STG-12R10-IRS 31-STG-1230-IRS31-STG-12R10-IRS1.2(b)From the licensee's submittal, it appears that all welds considered in Category B-Dunderwent a pressure test, with the exception of 29-RCN-12R10 and 29-RCN-1230. | | Questions on Relief Request S2-I2-RR-B01: |
| Please clarify whether a pressure test was performed on these welds, and the results of the pressure test.Enclosure 1.3Request for Relief S2-I2-RR-B01, Part D, Examination Category B-J and B-F, PressureRetaining Welds in Piping and Pressure Retaining Dissimilar Metal Welds in VesselNozzles1.3(a)In the licensee's submittal, Table 1 of Relief Request S2-I2-RR-B01 contains a listing ofmultiple limited examinations for Class 1 piping and nozzle welds that have occurred during the second 10-year interval. The table lists ASME Code examination categories for each piping and nozzle weld prior to (B-F and B-J), and after (R-A), implementation of a risk-informed inservice inspection (RI-ISI) program. It is unclear whether the piping and nozzle weld examinations were performed under a conventional ASME Code program, or under the new RI-ISI program. It is important to understand which program was used to examine each piping weldbecause: a) under a conventional ASME Code Section XI program, which requires a substantial population of applicable Category B-F and B-J welds to be examined, requests for relief for limited examinations based on impracticality may be submitted per Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(5)(iii),whereas, b) under a RI-ISI program, which is an existing alternative to ASME Code requirements approved by the NRC for Salem Unit No. 2, there is no method for evaluating a request for relief under 10 CFR 50.55a(g)(5)(iii). 1.3(b)According to Table 1, Examination Category B-F and B-J, the post ISI ASME itemnumbers are listed as R1.19-2, R1.20-4, or R1.20-6. According to Code Case N-577 or N-578, as applicable, for implementation of RI-ISI programs at Salem Unit No. 2, these item numbers do not appear in Table 1, Examination Category R-A. Please provide the correct designations.1.3(c)For certain piping welds, information submitted by the licensee is not sufficient todemonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by licensee identification numbers listed below.Examination Category B-F6-PR-1205-129-RC-1210-531-RC-1220-16-PR-1203-131-RC-1240-131-RC-1210-1 4-PR-1200-131-RC-1230-1Examination Category B-J10-SJ-1221-2131-RC-1220-431-RC-1220-4LU-I2-CV-1275-44 8-SJ-1262-104-PS-1231-2031-RC-1220-4LU-O 8-SJ-1245-127.5-RC-1230-13-CV-1231-14 8-SJ-1241-186-RH-1231-162-CV-1275-43 1.4Request for Relief Part E, Examination Category B-G-1, Pressure Retaining Bolting,Greater than 2 Inches in Diameter.1.4(a)Relief is being requested for certain examination requirements for Examination CategoryB-G-1, "Pressure Retaining Bolting Greater than 2 Inches in Diameter." However, there are no B-G-1 items listed in Table 1. Please add the appropriate Category B-G-1 items to Table 1, and include sufficient information to demonstrate impracticality, or revise the request appropriately.Questions on Relief Request S2-I2-RR-C01: | | 1.1 Request for Relief S2-I2-RR-B01, Part B, Examination Category B-B, Pressure Retaining Welds in Vessels Other than Reactor Vessels 1.1(a) For weld 2-PZR-CIRC DUH, the information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support the determination that the inspection of this weld is limited and impractical. |
| 2.1Request of Relief S2-I2-RR-C01, Part C, Examination Category C-F-1 and C-F-2,Pressure Retaining Piping Wleds2.1(a)In the licensee's submittal, Table 1 of Relief Request S2-I2-RR-C01 contains a listing ofmultiple limited examinations for Class 2 piping welds that have occurred during the second 10-year interval. The table lists ASME Code examination categories for each piping weld prior to (C-F-1 and C-F-2), and after (R-A), implementation of an RI-ISI program. It is unclear whether the piping weld examinations were performed under a conventional ASME Code program, or under the new RI-ISI program.It is important to understand which type of program each piping weld examination wasperformed under, because: a) under a conventional ASME Code Section XI program, which requires a substantial population of applicable Category C-F-1 and C-F-2 welds to be examined, requests for relief for limited examinations based on impracticality may be submitted per 10 CFR 50.55a(g)(5)(iii), whereas, b) under a RI-ISI program, which is an existing alternative to ASME Code requirements approved by the NRC for Salem Unit No. 2, there is no method for evaluating a request for relief under 10 CFR 50.55a(g)(5)(iii). 2.1(b)For the component identified as 8-CS-2227-5, a valve-to-pipe weld, the licensee haslisted this as ASME Examination Category C-F-1, Item A-E<3/8. This item number does not correspond with Table IWC-2500-1 in the 1986 Edition of the ASME Code. Please confirm that this weld is required to be examined by requirements of ASME Code, Table IWC-2500-1, Examination Category C-F-1. If so, please list the correct item designation for this weld.2.1(c)For certain piping welds, information submitted by the licensee is not sufficient todemonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by the licensee identification numbers below.8-CS-2227-512-PR-2201-114-RH-2212-114-RH-2224-112-RH-2252-383-CV-2255-93-CV-2256-63-CV-2255-12 14-BF-2211-230-MS-2211-934-MS-2241-36-MS-2211-13 2.2Request for Relief Part D, Examination Category C-C, Integral Attachments for Vessels,Piping, Pumps and Valves2.2(a)For certain component attachment and support welds, information submitted by thelicensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by the licensee identification numbers below.14-BF-2211-Trunnions 11PL-11 & 11-PI-1214-BF-2231-17PS14-BF-2231-18PS34-MS-2241-242PL 12-RH-2252-38PS-1&212-RH-2252-38PS-3 32-MS-2231-1PS-232-MS-2221-1PS-2 32-MS-2211-1PS-232-MS-2211-2PL-1 thru 3 12-RH-2252-5PL-1 thru 614-BF-2221-3PL-1 thru 8}} | | 1.2 Request for Relief S2-I2-RR-B01, Part C, Examination Category B-D, Full Penetration Welds of Nozzles in Vessels 1.2(a) For certain nozzle welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by licensee identification numbers shown below. |
| | 31-STG-1220-IRS 29-STG-1230-IRS 29-STG-1240-IRS 29-STG-1220-IRS 31-STG-1240-IRS 29-STG-12R10-IRS 31-STG-1230-IRS 31-STG-12R10-IRS 1.2(b) From the licensees submittal, it appears that all welds considered in Category B-D underwent a pressure test, with the exception of 29-RCN-12R10 and 29-RCN-1230. |
| | Please clarify whether a pressure test was performed on these welds, and the results of the pressure test. |
| | Enclosure |
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| | 1.3 Request for Relief S2-I2-RR-B01, Part D, Examination Category B-J and B-F, Pressure Retaining Welds in Piping and Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles 1.3(a) In the licensees submittal, Table 1 of Relief Request S2-I2-RR-B01 contains a listing of multiple limited examinations for Class 1 piping and nozzle welds that have occurred during the second 10-year interval. The table lists ASME Code examination categories for each piping and nozzle weld prior to (B-F and B-J), and after (R-A), implementation of a risk-informed inservice inspection (RI-ISI) program. It is unclear whether the piping and nozzle weld examinations were performed under a conventional ASME Code program, or under the new RI-ISI program. |
| | It is important to understand which program was used to examine each piping weld because: a) under a conventional ASME Code Section XI program, which requires a substantial population of applicable Category B-F and B-J welds to be examined, requests for relief for limited examinations based on impracticality may be submitted per Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(5)(iii), |
| | whereas, b) under a RI-ISI program, which is an existing alternative to ASME Code requirements approved by the NRC for Salem Unit No. 2, there is no method for evaluating a request for relief under 10 CFR 50.55a(g)(5)(iii). |
| | 1.3(b) According to Table 1, Examination Category B-F and B-J, the post ISI ASME item numbers are listed as R1.19-2, R1.20-4, or R1.20-6. According to Code Case N-577 or N-578, as applicable, for implementation of RI-ISI programs at Salem Unit No. 2, these item numbers do not appear in Table 1, Examination Category R-A. Please provide the correct designations. |
| | 1.3(c) For certain piping welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by licensee identification numbers listed below. |
| | Examination Category B-F 6-PR-1205-1 29-RC-1210-5 31-RC-1220-1 6-PR-1203-1 31-RC-1240-1 31-RC-1210-1 4-PR-1200-1 31-RC-1230-1 Examination Category B-J 10-SJ-1221-21 31-RC-1220-4 31-RC-1220-4LU-I 2-CV-1275-44 8-SJ-1262-10 4-PS-1231-20 31-RC-1220-4LU-O 8-SJ-1245-1 27.5-RC-1230-1 3-CV-1231-14 8-SJ-1241-18 6-RH-1231-16 2-CV-1275-43 |
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| | 1.4 Request for Relief Part E, Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 Inches in Diameter. |
| | 1.4(a) Relief is being requested for certain examination requirements for Examination Category B-G-1, Pressure Retaining Bolting Greater than 2 Inches in Diameter. However, there are no B-G-1 items listed in Table 1. Please add the appropriate Category B-G-1 items to Table 1, and include sufficient information to demonstrate impracticality, or revise the request appropriately. |
| | Questions on Relief Request S2-I2-RR-C01: |
| | 2.1 Request of Relief S2-I2-RR-C01, Part C, Examination Category C-F-1 and C-F-2, Pressure Retaining Piping Wleds 2.1(a) In the licensees submittal, Table 1 of Relief Request S2-I2-RR-C01 contains a listing of multiple limited examinations for Class 2 piping welds that have occurred during the second 10-year interval. The table lists ASME Code examination categories for each piping weld prior to (C-F-1 and C-F-2), and after (R-A), implementation of an RI-ISI program. It is unclear whether the piping weld examinations were performed under a conventional ASME Code program, or under the new RI-ISI program. |
| | It is important to understand which type of program each piping weld examination was performed under, because: a) under a conventional ASME Code Section XI program, which requires a substantial population of applicable Category C-F-1 and C-F-2 welds to be examined, requests for relief for limited examinations based on impracticality may be submitted per 10 CFR 50.55a(g)(5)(iii), whereas, b) under a RI-ISI program, which is an existing alternative to ASME Code requirements approved by the NRC for Salem Unit No. 2, there is no method for evaluating a request for relief under 10 CFR 50.55a(g)(5)(iii). |
| | 2.1(b) For the component identified as 8-CS-2227-5, a valve-to-pipe weld, the licensee has listed this as ASME Examination Category C-F-1, Item A-E<3/8. This item number does not correspond with Table IWC-2500-1 in the 1986 Edition of the ASME Code. Please confirm that this weld is required to be examined by requirements of ASME Code, Table IWC-2500-1, Examination Category C-F-1. If so, please list the correct item designation for this weld. |
| | 2.1(c) For certain piping welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by the licensee identification numbers below. |
| | 8-CS-2227-5 12-PR-2201-1 14-RH-2212-1 14-RH-2224-1 12-RH-2252-38 3-CV-2255-9 3-CV-2256-6 3-CV-2255-12 14-BF-2211-2 30-MS-2211-9 34-MS-2241-3 6-MS-2211-13 |
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| | 2.2 Request for Relief Part D, Examination Category C-C, Integral Attachments for Vessels, Piping, Pumps and Valves 2.2(a) For certain component attachment and support welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by the licensee identification numbers below. |
| | 14-BF-2211-Trunnions 11PL-11 & 11-PI-12 14-BF-2231-17PS 14-BF-2231-18PS 34-MS-2241-242PL 12-RH-2252-38PS-1&2 12-RH-2252-38PS-3 32-MS-2231-1PS-2 32-MS-2221-1PS-2 32-MS-2211-1PS-2 32-MS-2211-2PL-1 thru 3 12-RH-2252-5PL-1 thru 6 14-BF-2221-3PL-1 thru 8}} |
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MONTHYEARIR 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 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement 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 ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 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-N23-0045, 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 IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 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 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 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 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-N23-0006, 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 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual 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 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) 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-N23-0012, 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 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22333A9022022-11-29029 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 ML13102A2752013-04-25025 April 2013 Request for Additional Information Change to PSEG Emergency Plan to Remove the Backup R45 Plant Vent Radiation Monitor Indications ML13063A7172013-03-11011 March 2013 Second Request for Additional Information Deletion of Condition for Inoperable Control Area Air Condition System/Control Room Emergency Air Conditioning System Isolation Dampers 2022-02-22
[Table view] |
Text
December 20, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2, REQUEST FOR ADDITIONAL INFORMATION RE: INSERVICE INSPECTION PROGRAM RELIEF REQUESTS (TAC NOS. MD1052 AND MD1053)
Dear Mr. Levis:
On March 21, 2006, PSEG Nuclear LLC (PSEG), the licensee for the Salem Nuclear Generating Station, Unit No. 2, requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for the inservice inspection (ISI) of Class 1 and Class 2 components. PSEG stated that it had conducted examinations as part of the second ten-year interval ISI program to the extent practical; however, coverage for certain weld examinations was less than required by the ASME Code. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the questions in the enclosure to this letter are necessary in order for the staff to complete its review. The enclosure was sent via e-mail to PSEG on October 19, 2006, to see whether the questions were understandable, whether the regulatory bases were clear, and whether the information was already docketed. PSEG indicated that no clarifications were needed. Please provide a response to the enclosed questions within 30 days of the date of this letter in order to allow the NRC staff to complete a timely review of the relief requests. This request was discussed with Mr. James Mallon of your staff on December 12, 2006. If you have questions about this request, please contact me at (301) 415-1321.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
Request for Additional Information cc w/encl: See next page
ML063340284 OFFICE LPL1-2/PM LPL1-2/LA DE/CPNB/BC LPL1-2/BC NAME SBailey CRaynor TChan* HChernoff DATE 12/15/06 12/15/06 8/24/06, 9/25/06 12/20/06
- by memo Salem Nuclear Generating Station, Unit No. 2 cc:
Mr. Dennis Winchester Township Clerk Vice President - Nuclear Assessment Lower Alloways Creek Township PSEG Nuclear Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Thomas P. Joyce Radiation Protection Programs Site Vice President - Salem NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. George H. Gellrich Mr. Brian Beam Plant Support Manager Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Carl J. Fricker U.S. Nuclear Regulatory Commission Plant Manager - Salem 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. James Mallon U.S. Nuclear Regulatory Commission Manager - Licensing Drawer 0509 200 Exelon Way, KSA 3-E Hancocks Bridge, NJ 08038 Kennett Square, PA 19348 Mr. Steven Mannon Manager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
REQUEST FOR ADDITIONAL INFORMATION REQUESTS FOR RELIEF REGARDING EXAMINATION COVERAGE SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 On March 21, 2006, PSEG Nuclear LLC (PSEG), the licensee for the Salem Nuclear Generating Station (Salem), Unit No. 2, requested relief from certain requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
Section XI, for the inservice inspection (ISI) of Class 1 and Class 2 components. PSEG stated that it had conducted examinations as part of the Second Ten-Year Interval ISI Program to the extent practical; however, coverage for certain weld examinations was less than required by the Code. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the following questions are necessary in order for the staff to complete its review:
Questions on Relief Request S2-I2-RR-B01:
1.1 Request for Relief S2-I2-RR-B01, Part B, Examination Category B-B, Pressure Retaining Welds in Vessels Other than Reactor Vessels 1.1(a) For weld 2-PZR-CIRC DUH, the information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support the determination that the inspection of this weld is limited and impractical.
1.2 Request for Relief S2-I2-RR-B01, Part C, Examination Category B-D, Full Penetration Welds of Nozzles in Vessels 1.2(a) For certain nozzle welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by licensee identification numbers shown below.
31-STG-1220-IRS 29-STG-1230-IRS 29-STG-1240-IRS 29-STG-1220-IRS 31-STG-1240-IRS 29-STG-12R10-IRS 31-STG-1230-IRS 31-STG-12R10-IRS 1.2(b) From the licensees submittal, it appears that all welds considered in Category B-D underwent a pressure test, with the exception of 29-RCN-12R10 and 29-RCN-1230.
Please clarify whether a pressure test was performed on these welds, and the results of the pressure test.
Enclosure
1.3 Request for Relief S2-I2-RR-B01, Part D, Examination Category B-J and B-F, Pressure Retaining Welds in Piping and Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles 1.3(a) In the licensees submittal, Table 1 of Relief Request S2-I2-RR-B01 contains a listing of multiple limited examinations for Class 1 piping and nozzle welds that have occurred during the second 10-year interval. The table lists ASME Code examination categories for each piping and nozzle weld prior to (B-F and B-J), and after (R-A), implementation of a risk-informed inservice inspection (RI-ISI) program. It is unclear whether the piping and nozzle weld examinations were performed under a conventional ASME Code program, or under the new RI-ISI program.
It is important to understand which program was used to examine each piping weld because: a) under a conventional ASME Code Section XI program, which requires a substantial population of applicable Category B-F and B-J welds to be examined, requests for relief for limited examinations based on impracticality may be submitted per Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.55a(g)(5)(iii),
whereas, b) under a RI-ISI program, which is an existing alternative to ASME Code requirements approved by the NRC for Salem Unit No. 2, there is no method for evaluating a request for relief under 10 CFR 50.55a(g)(5)(iii).
1.3(b) According to Table 1, Examination Category B-F and B-J, the post ISI ASME item numbers are listed as R1.19-2, R1.20-4, or R1.20-6. According to Code Case N-577 or N-578, as applicable, for implementation of RI-ISI programs at Salem Unit No. 2, these item numbers do not appear in Table 1, Examination Category R-A. Please provide the correct designations.
1.3(c) For certain piping welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by licensee identification numbers listed below.
Examination Category B-F 6-PR-1205-1 29-RC-1210-5 31-RC-1220-1 6-PR-1203-1 31-RC-1240-1 31-RC-1210-1 4-PR-1200-1 31-RC-1230-1 Examination Category B-J 10-SJ-1221-21 31-RC-1220-4 31-RC-1220-4LU-I 2-CV-1275-44 8-SJ-1262-10 4-PS-1231-20 31-RC-1220-4LU-O 8-SJ-1245-1 27.5-RC-1230-1 3-CV-1231-14 8-SJ-1241-18 6-RH-1231-16 2-CV-1275-43
1.4 Request for Relief Part E, Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 Inches in Diameter.
1.4(a) Relief is being requested for certain examination requirements for Examination Category B-G-1, Pressure Retaining Bolting Greater than 2 Inches in Diameter. However, there are no B-G-1 items listed in Table 1. Please add the appropriate Category B-G-1 items to Table 1, and include sufficient information to demonstrate impracticality, or revise the request appropriately.
Questions on Relief Request S2-I2-RR-C01:
2.1 Request of Relief S2-I2-RR-C01, Part C, Examination Category C-F-1 and C-F-2, Pressure Retaining Piping Wleds 2.1(a) In the licensees submittal, Table 1 of Relief Request S2-I2-RR-C01 contains a listing of multiple limited examinations for Class 2 piping welds that have occurred during the second 10-year interval. The table lists ASME Code examination categories for each piping weld prior to (C-F-1 and C-F-2), and after (R-A), implementation of an RI-ISI program. It is unclear whether the piping weld examinations were performed under a conventional ASME Code program, or under the new RI-ISI program.
It is important to understand which type of program each piping weld examination was performed under, because: a) under a conventional ASME Code Section XI program, which requires a substantial population of applicable Category C-F-1 and C-F-2 welds to be examined, requests for relief for limited examinations based on impracticality may be submitted per 10 CFR 50.55a(g)(5)(iii), whereas, b) under a RI-ISI program, which is an existing alternative to ASME Code requirements approved by the NRC for Salem Unit No. 2, there is no method for evaluating a request for relief under 10 CFR 50.55a(g)(5)(iii).
2.1(b) For the component identified as 8-CS-2227-5, a valve-to-pipe weld, the licensee has listed this as ASME Examination Category C-F-1, Item A-E<3/8. This item number does not correspond with Table IWC-2500-1 in the 1986 Edition of the ASME Code. Please confirm that this weld is required to be examined by requirements of ASME Code, Table IWC-2500-1, Examination Category C-F-1. If so, please list the correct item designation for this weld.
2.1(c) For certain piping welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by the licensee identification numbers below.
8-CS-2227-5 12-PR-2201-1 14-RH-2212-1 14-RH-2224-1 12-RH-2252-38 3-CV-2255-9 3-CV-2256-6 3-CV-2255-12 14-BF-2211-2 30-MS-2211-9 34-MS-2241-3 6-MS-2211-13
2.2 Request for Relief Part D, Examination Category C-C, Integral Attachments for Vessels, Piping, Pumps and Valves 2.2(a) For certain component attachment and support welds, information submitted by the licensee is not sufficient to demonstrate impracticality. Please submit further information in the form of drawings, sketches and/or descriptions to support this evaluation for the following components, as identified by the licensee identification numbers below.
14-BF-2211-Trunnions 11PL-11 & 11-PI-12 14-BF-2231-17PS 14-BF-2231-18PS 34-MS-2241-242PL 12-RH-2252-38PS-1&2 12-RH-2252-38PS-3 32-MS-2231-1PS-2 32-MS-2221-1PS-2 32-MS-2211-1PS-2 32-MS-2211-2PL-1 thru 3 12-RH-2252-5PL-1 thru 6 14-BF-2221-3PL-1 thru 8