Similar Documents at Salem |
---|
Category:Code Relief or Alternative
MONTHYEARML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping ML21145A1892021-06-10010 June 2021 Authorization and Safety Evaluation for Alternative Request No. SC-I4R-200 ML20099E2332020-04-20020 April 2020 Issuance of Alternative Request S1-I4R-191 for the Fourth 10-Year Inservice Inspection Interval LR-N19-0084, Proposed Alternative for Examination of ASME Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections, Per Inservice Inspection Relief Request SC-I4R-1922019-09-10010 September 2019 Proposed Alternative for Examination of ASME Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections, Per Inservice Inspection Relief Request SC-I4R-192 LR-N19-0083, Request for Relief S1-I4R-191 from Alloy 690 PWR Reactor Vessel Head Inspection Interval, Fourth 10-year Interval2019-09-10010 September 2019 Request for Relief S1-I4R-191 from Alloy 690 PWR Reactor Vessel Head Inspection Interval, Fourth 10-year Interval ML17219A1862017-08-17017 August 2017 Safety Evaluation of Relief Request SC-I4R-171 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) ML15349A9562015-12-24024 December 2015 Relief from the Requirements of the ASME Code ML15195A4952015-07-28028 July 2015 Relief from the Requirements of the ASME Code ML14153A1462014-06-23023 June 2014 Safety Evaluation of Relief Request No. S2-14R-131 Regarding the Fourth Ten-Year Inservice Inspection Interval (Tac ME2442) ML13088A2192013-04-18018 April 2013 Safety Evaluation of Relief Request No. S2-14R-123 Regarding the Fourth Ten-Year Inservice Inspection Interval Code Edition LR-N12-0157, Submittal of Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval Code Edition2012-06-0707 June 2012 Submittal of Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval Code Edition ML1124201752011-09-19019 September 2011 Safety Evaluation of Relief Requests Regarding Pressure Testing of Service Water System Buried Piping - Salem Nuclear Generating Station, Unit Nos. 1 and 2 LR-N10-0380, Request for Authorization to Continue Using a Risk-Informed Inservice Inspection Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping2010-10-21021 October 2010 Request for Authorization to Continue Using a Risk-Informed Inservice Inspection Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping ML0936500862010-01-0707 January 2010 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Inspection Program for Salem Nuclear Generating Station, Unit Nos. 1 and 2 ML0920304642009-08-11011 August 2009 Safety Evaluation of Relief Requests for the Fourth 10-Year Interval of the Inservice Testing Program for Salem Nuclear Generating Station, Unit 1 & 2 (TAC ME0322, ME0323, ME0324, ME0325, ME0326, ME0327, ME0328, ME0329, ME0330, ME0331, ME03 LR-N09-0126, Relief Requests to Extend the Inservice Interval for Reactor Vessel Weld Examination2009-06-11011 June 2009 Relief Requests to Extend the Inservice Interval for Reactor Vessel Weld Examination ML0825502182008-10-10010 October 2008 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Testing Program for Salem Nuclear Generating Station, Unit Nos. 1 and 2 LR-N05-0446, ASME Code Relief Request Salem Units 1 and 22005-11-16016 November 2005 ASME Code Relief Request Salem Units 1 and 2 LR-N04-0473, Relief Request SC-13-RR-A14 Synchronization of Salem Units 1 and 2 ISI Programs Ten-Year Inservice Inspection Intervals2005-10-31031 October 2005 Relief Request SC-13-RR-A14 Synchronization of Salem Units 1 and 2 ISI Programs Ten-Year Inservice Inspection Intervals ML0525802662005-09-30030 September 2005 Evaluation of Relief Requests S1-RR-04-V01 and S1-RR-04-V02 Related to the Third 10-Year Interval Inservice Testing Program ML0511803442005-05-0404 May 2005 Evaluation of Relief Request S2-13-RR-F01 ML0511503792005-04-29029 April 2005 Evaluation of Relief Request S2-13-RR-A06 ML0428005542004-10-0606 October 2004 Request for Additional Information Relief Requests S1-RR-04-V01 and V02 ML0409203612004-04-23023 April 2004 Evaluation of Relaxation Request No. S1-RR-13-B22, First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0320902002003-07-28028 July 2003 Relief, Relief from ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request S1-RR-F01, MB6098 ML0305902162003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-A02 ML0305902072003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-A06 ML0224704092003-02-0303 February 2003 Relief, Use of ASME Code Case N-532-1, Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission, MB6089 ML0301607502003-01-16016 January 2003 Relief, ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request S1-RR-B01 and S1-RR-C01 ML0228105402002-11-27027 November 2002 Relief Request, Evaluation of Relief Request SC-RR-E01 and SC-RR-L01 ML0228307152002-11-27027 November 2002 Relief Request, Evaluation of Relief Request SC-RR-A01, TAC Nos. MB5569 & MB5570 ML0232302982002-11-12012 November 2002 Request for Additional Information Inservice Inspection Program Relief Request S1-RR-B01 ML0226004852002-10-30030 October 2002 Relief Request, Relief from ASME Code Requirements Related to the Salem Inservice Inspection Program, Relief Request SC-RR-F02, ML0225506812002-10-0707 October 2002 Code Relief, ASME Code Section XI, Inservice Inspection Program Requirements Related to Pressure Testing of Class 3 Components ML0225504352002-10-0404 October 2002 Relief, ASME Code Requirements Related to the Salem Inservice Inspection Programs, MB6086 & MB6087 ML0206100052002-03-21021 March 2002 Generation Station, Units 1 and 2, Code Relief, Inservice Inspection Requirements of Reactor Pressure Vessel Nozzle Inner Radius Sections, MB4071 and MB4072 ML0205304402002-03-21021 March 2002 Code Relief, Relief from ASME Code Requirements Related to the Inservice Inspection Program, Second 10-Year Interval, Relief Request S2-RR-B04 ML0205904012002-02-11011 February 2002 Inservice Inspection Program Relief Request S2-RR-B04, Inspection of Reactor Pressure Vessel (RPV) Flange-to-Shell Weld 2023-02-02
[Table view] Category:Letter type:LR
MONTHYEARLR-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 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0055, 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 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 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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-N23-0033, 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 LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0003, 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 LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022 Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08
[Table view] |
Text
Thomas P.Joyce PSEG Nuclear LLC Site Vice President - Salem PO. Box 236, Hancocks Bridge, NJ 08038-1236 tel: 856.339.2086 fax: 856.339.2956
- OCT 312005 LR-N04-0473 0 PSEG MOMlear LLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SALEM GENERATING STATION - UNIT I DOCKET NO. 50-272 FACILITY OPERATING LICENSE NO. DPR-70 RELIEF REQUEST SC-13-RR-A14 SYNCHRONIZATION OF SALEM UNITS 1 AND 2 ISI PROGRAMS TEN-YEAR INSERVICE INSPECTION INTERVALS In accordance with the provisions of 10 CFR 50.55a(a)(3), PSEG Nuclear LLC (PSEG) hereby transmits a request to use an alternative to the requirements of 10 CFR 50.55a(g)(4)(ii) and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section Xl, Subparagraph IWA-2430 (d). Licensees are required to revise and update their Inservice Inspection (ISI) Programs every 120 months to the latest edition and addenda of Section Xl of the ASME Code referenced in 10 CFR 50.55a as of twelve months prior to the start of a new inspection interval.
The attached proposed alternative for ISI proposes extending the third Ten-Year Interval for Salem Generating Station Unit 1 and aligning the date for commencing the fourth Ten-Year Interval with Salem Generating Station Unit 2. Altering the start date of the interval for Unit 1 will allow PSEG ISI processes and procedures for both units to meet the same requirements of the applicable edition and addenda of ASME Section Xi.
Should you have any questions regarding this request, please contact Mr. Paul Duke at (856) 339-1466.
Sincerely, Thomas P. Joyce Site Vice President Salem Generating Station
Enclosure:
4U4"7 Relief Request SC-13-RR-A14
Document Control Desk 2 LR-N04-0473 4CT 3 1 2005 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. S. Bailey, Project Manager - Salem Unit 1 and Unit 2 Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K.Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box415 Trenton, NJ 08625
Document Control Desk Attachment I LR-N04-0473 Relief Request SC-13-RR-A14 Proposed Alternative to Align Unit I and Unit 2 Ten-Year Inservice Inspection Intervals Relief Requested Pursuant to the requirements of 10CFR50.55a(a)(3)(i) and (ii), PSEG Nuclear LLC (PSEG) requests use of a proposed alternative to the requirements of 10 CFR 50.55a(g)(4)(ii) and American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code Section Xl, Subparagraph IWA-2430 (d) for updating the Salem Units 1 and 2 Inservice Inspection (ISI) Programs on a frequency required by ASME Section Xi and the Code of Federal Regulations.
PSEG requests that the start date for the Unit 1 fourth Ten-Year ISI Interval be aligned with that of Unit 2 so that both commence on November 23, 2012.
Paragraph IWA-2432 requires each inspection interval to consist of ten-year duration; except as modified by IWA-2430 (d)which permits the inspection interval to be extended or decreased by as much as one year, provided that successive intervals are not altered by more than one year from the original pattern of intervals.
Basis for Relief The Salem Generating Station Unit 1 first Ten-Year ISI Interval started July 11, 1977 with the issuance of the Operating License and ended February 27,1988.
This interval included 7 Months and 16 Days to coincide with end of refueling outage per the 1974 Edition with summer 1975 Addenda of IWA-2400. The second Ten-Year IS Interval commenced on February 27, 1988 and ended May 19, 2001. This interval excluded 36 Months and 10 Days (April 7, 1995-April 17,1998) for extended shutdown, and 2 Months and 13 days to coincide with end of the refueling outage per the 1983 Edition with summer 1983 Addenda of IWA-2412 (b).
The Salem Generating Station Unit 2 first Ten-Year ISI Interval started October 13, 1981 with the issuance of the Operating License and ended May 10,1992.
The second Ten-Year IS Interval commenced on May 10, 1992 and ended November 23, 2003. This interval excludes 26 Months and 21 Days (June 8, 1995-August 29, 1997) for an extended shutdown, and 7 Months and 16 days to coincide with the end of the refueling outage per the 1986 Edition of IWA-2430 (d)(3).
The illustration below depicts the current schedule of Salem Units 1 and 2 third Ten-Year ISI intervals.
l Z2 Salem Unit 1 Salem Unit2 -
I CO0 I I M
Document Control Desk Attachment I LR-N04-0473 Relief Request SC-13-RR-A14 On May 19, 2011, Salem Unit 1 is scheduled to conclude its third Ten-Year ISI interval. On November 23, 2013, Salem Unit 2 is scheduled to conclude its third Ten-Year ISI interval.
Salem U Ink I mu 255 D l34 2 5 35 2 21 s t ml 1 l Init2 Salem U If Salem Unit 1 and 2 take advantage of the combined benefits of ASME Section Xl paragraph IWA-2430 (d)(3) permitting the inspection interval to be extended or decreased by as much as one year, Salem Unit 1 would conclude its third Ten-Year ISI interval on May 19, 2012 and Salem Unit 2 would conclude its ISI interval November 23, 2012. This would still result in approximately 6.5 months separation. Alignment of end of the third Ten-Year ISI interval for both Salem units is not possible without exceeding ASME Section Xl paragraph IWA-2430 (d)(3) requirements. Unless relief is granted, Salem Units 1 and 2 successive ten-year inservice inspection intervals will not coincide because 10 CFR 50.55a(g)(4)(ii) states "Inservice examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-month inspection interval, subject to the limitations and modifications listed in paragraph (b) of this section."
Maintaining both Salem units to the same edition of the ASME Code and schedule has distinct advantages without any reduction in the level of quality or safety:
- 1. Site procedures will meet the requirements of one edition of the ASME Code instead of two different editions.
- 2. The ISI Programs can be written as one document covering both units.
- 3. The probability of applying a wrong inspection and/or test requirement is reduced.
- 4. Having one set of procedures and documents reduces the administrative burden of complying with the ISI requirements without a reduction in the level of quality of the ISI Programs.
With the proposed alternative schedule for Unit 1, the required third Ten-Year Interval (and following examinations and tests) will be completed. There will be no reduction in the number of ISI examinations as a result of the date change.
=
Document Control Desk Attachment I LR-N04-0473 Relief Request SC-13-RR-A14 Alternative Requirement PSEG Nuclear proposes to align the end of each unit's third Ten-Year ISI interval and perform subsequent successive 120-month program update requirements per 10CFR50.55a(g)(4)(iv) commencing on November 23, 2012.
Justification of Relief Altering the third ISI Ten-Year interval so that both Salem Unit 1 and Unit 2 end on the same date and begin the fourth ISI Ten-Year interval on the same date reduces the administrative costs and burden of complying with two different editions of the ASME ISI code. The possibility of working to the wrong procedures or documents (both NDE and administrative) is reduced because both units would be governed by the same edition of the ASME code.
The proposed action does not result in a reduction of examinations or tests and provides an acceptable level of safety and quality.
Implementation Schedule The ISI Programs for Salem Units 1 and 2 will be updated and become effective on November 23, 2012. The new interval schedule will remain in effect for the fourth and subsequent Ten-Year intervals.
Precedent The safety evaluation (TAC Nos. MB7564 and MB7565) issued to Prairie Island Nuclear Generating Plant, Docket Nos. 50-282 and 50-306, on October 2, 2003 approved a similar request.