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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
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 JUN 07.2012 PSEG Nu~cleaT LLC 10 CFR 50.55a LR-N12-0157 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311
Subject:
Submittal of Relief Request Associated with the Fourth Ten-Year Inservice Inspection (lSI) Interval Code Edition In accordance with 10 CFR 50.55a (76FR36232), "codes and standards," paragraph (a)(3)(i), PSEG Nuclear LLC (PSEG) hereby requests NRC approval of the attached request for the fourth 10-year lSI interval for Salem Generating Station Unit 2, beginning on November 27,2013. PSEG is requesting that the Unit 2 lSI inspection plan be developed in accordance with the requirements of the 2004 Edition American Society of Mechanical Engineering (ASME) Boiler and Pressure Vessel Code,Section XI. This request would standardize the ASME Code edition with the current Salem Unit 1 fourth 10-year lSI interval and with the current Salem Unit 1 and Unit 2 second 10-year Containment Inservice Inspection (CISI) interval. In order to support the development of the Salem Unit 2 fourth 1O-year inspection plan, PSEG is requesting approval by June 30,2013.
There are no regulatory commitments contained within this letter. Should you have any questions concerning this matter, please contact Mr. Brian Thomas at 856-339-2022.
r-LJrel Y, Paul . Duke, Jr.
-g, Manager - Licensing PSEG Nuclear LLC
Attachment:
10 CFR 50.55a Relief Request S2-14R-123
LR-N12-0157 JUN 0720'2 Page 2 cc: W. Dean, Administrator, Region I, NRC NRC Senior Resident Inspector, Salem J. Hughey, Project Manager, Salem, USNRC P. Mulligan, Manager IV, NJBNE L. Marabella, Corporate Commitment Tracking Coordinator T. Cachaza, Salem Commitment Tracking Coordinator
ATTACHMENT Salem Nuclear Generating Station, Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 Relief Request - S2-14R-123 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i), the proposed alternatives would provide an acceptable level of quality and safety.
- 1. ASME Component(s) Affected Code Class: 1, 2, and 3 components and their supports Examination Category: All Item Number: All
Description:
All items within the ASME Section XI Boundaries except IWE and IWL.
Unit/I nspection Interval Applicability: Salem Unit 2 - Fourth (4th) lSI 1O-Year Interval
2. Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2007 Edition with the 2008 Addenda.
- 3. Applicable Regulatory Requirements 10 CFR 50.55a(g)(4)(ii) states in part: "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 before the start of the 120-month inspection interval (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section), subject to the conditions listed in paragraph (b) of this section" Paragraph (b )(2) states: "As used in this section, references to Section XI refer to Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code, and include the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2007 Edition with the 2008 Addenda, subject to the following conditions:"
1
Salem Unit 2 will begin the fourth 120-month Inservice Inspection (lSI) interval on 11/27/2013 and is required to update the fourth interval Inservice Inspection Program to the 2007 Edition with the 2008 Addenda with the conditions of 10 CFR 50.55a(b)(2) and the additional augmented requirements of 10 CFR 50.55a(g)(6)(ii).
4. Reason for Request
On May 20, 2011, Salem Unit 1 was updated to the 2004 Edition of Section XI in accordance with the requirements of 10 CFR 50.55a(g)(4)(ii).
Prior to the Unit 1 update, both units were meeting the requirements of ASME Section XI, 1998 Edition with the 2000 Addenda and the conditions of 10 CFR 50.55a(b). Additionally, on April 22, 2010, the Salem Unit 1 and 2 Containment Inservice Inspection (CISI) programs were updated to the 2004 Edition of Section XI in accordance with the requirements of 10 CFR 50.55a(g)(4)(ii).
PSEG Nuclear shares the same procedures and processes for management and implementation of the Salem Unit 1 and Unit 2 ASME Section XI programs. As a result of the recent Salem lSI and CISI interval updates, the program procedures have been expanded to address two sets of ASME Section XI requirements with the corresponding conditions of 10 CFR 50.55a(b); the 1998 with the 2000 Addenda (Salem Unit 2 current interval) and the 2004 Edition (Salem Unit 1 lSI and Salem Unit 1 and 2 CISI). If Salem Unit 2 is updated to the 2007 Edition with the 2008 Addenda in November 2013, then the requirements representing the 1998 Edition with the 2000 Addenda would be replaced with those of the 2007 Edition with the 2008 Addenda. This will continue to result in programs and common procedures implementing two different EditionlAddenda of ASME Section XI.
For licensees who operate multiple units, it has become common to standardize programs, procedures, and processes like those of ASME Section XI. This has been shown to improve performance by focusing the use to a common set of requirements that are enhanced over time through multiple unit use. Implementing the same ASME standard allows the exchange of personnel knowledge in problem resolution between units, and optimizes the performance of the activity because the same requirements and processes are used repeatedly during multiple outages by the same personnel. PSEG Nuclear, like other licensees, optimizes performance by the sharing. of personnel between units and using common refueling outage teams.
- 5. Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), PSEG Nuclear requests authorization for Salem Unit 2 to utilize the alternative requirements in the 2004 Edition of 2
Section XI in lieu of the requirements contained in the 2007 Edition with the 2008 Addenda. In implementing this proposal, PSEG will comply with all NRC conditions specified in 10 CFR 50.55a(b) applicable to the 2004 Edition for Section XI. Code cases will be adopted per Regulatory Guide 1.147 as required by 10 CFR 50.55a(b)(5), and selected code cases will be applicable to the 2004 Edition. This alternative does not affect implementation of the augmented requirements contained in 10 CFR 50.55a(g)(6)(ii).
Salem Unit 2 has one remaining outage in the third interval (2RF019, Fall 2012) and will continue to meet the 1998 Edition with the 2000 Addenda until November 27, 2013.
It is acceptable to update the Salem Unit 2 ASME Section XI Program to the 2004 Edition in lieu of the 2007 Edition with the 2008 Addenda because the changes made to Section XI subsequent to the 2004 Edition were not necessary to ensure an acceptable level of quality and safety. In the latest 10 CFR 50.55a the NRC does not mandate that other plants using earlier edition and addenda as their code of record follow any of the requirements of the 2007 Edition with the 2008 Addenda. Additionally, the NRC uses 10 CFR 50.55a(g)(6)(ii) to identify augmented requirements that are believed by the NRC necessary to provide added assurance of structural reliability. This request does not affect Salem Unit 2's compliance with 10 CFR 50.55a(g)(6)(ii).
PSEG Nuclear believes that updating the Salem Unit 2 Section XI lSI program plan to the 2004 Edition to align with the Salem Unit 1 lSI program plan and the Salem Unit 1 and Unit 2 CISI program plans will improve the level of quality and safety. This improvement is achieved by creating one common set of technical and administrative requirements for personnel who develop, manage, plan, implement, report, and assess the ASME Section XI programs at Salem Unit 1 and 2.
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f),
(g), and (h) of this section, or portions thereof, may be used when authorized by the Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate. Any proposed alternatives must be submitted and authorized prior to implementation.
The applicant or licensee shall demonstrate that:
(i) The proposed alternatives would provide an acceptable level of quality and safety, or 3
(ii) Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
As discussed in Section 5 above, the proposed alternative to update the Salem Unit 2 ASME Section XI lSI Program to the 2004 Edition in lieu of the 2007 Edition with the 2008 Addenda as required by 10 CFR 50.55a(g)( 4 )(ii) provides an acceptable level of quality and safety.
Therefore, PSEG Nuclear requests authorization to perform the requested alternative to the Code requirement pursuant to the provisions of 10 CFR 50.55a(a)(3)(i).
- 6. Duration of Proposed Alternative The proposed alternative will be used for the fourth ten-year interval of the Inservice Inspection Program for Salem Unit 2 that begins November 27, 2013 and is currently scheduled to end on November 27,2023.
- 7. Precedents Request for alternatives to 10 CFR 50.55a(g)(4)(ii) to use Edition/Addenda that are earlier than the Edition/Addenda referenced in 10 CFR 50.55a(b) for successive 120 month intervals have been requested and approved for Arkansas Nuclear One (ANO) Unit 2 (References 1 and 2).
- 8. References
- 1. Request for Alternative to Use 2001 Edition Through 2003 Addenda in Lieu of the 2004 Edition, Arkansas Nuclear One, Unit 2 (ADAMS Accession Number - ML091600248)
- 2. Arkansas Nuclear One, Unit 2 - Request for Alternative AN02-ISI-003 to use 2001 Edition Through 2003 Addenda in Lieu of the 2004 Edition for the Fourth 10-Year Inspection Interval (TAC No. ME1452) (ADAMS Accession Number - ML100970659) ,
4