Letter Sequence Other |
---|
|
|
MONTHYEARML0610904822006-03-16016 March 2006 M-DSC-411, Rev. 0 - Pressurizer Lower Level Nozzle Welding and Transient Analysis Project stage: Other ML0613801192006-05-16016 May 2006 ISI-3-23 Request to Use ASME Code Case N-746 Project stage: Other ML0626204912006-10-0202 October 2006 Request for Relief (ISI-3-16) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (TAC Nos. MC9433/MC9433) Project stage: Other ML0634503472006-12-27027 December 2006 Relief, Relief Request ISI-3-23 for Third 10-Year ISI Interval to Allow Use of American Society of Mechanical Engineers Code Case N-746, MC9433 & MC9434 Project stage: Other 2006-12-27
[Table View] |
|
---|
Category:Code Relief or Alternative
MONTHYEARML13035A1882013-04-29029 April 2013 Relief Request ISI-3-36, Reactor Coolant Pressure Boundary Testing, Third 10-Year Inservice Inspection Interval ML12341A2782012-12-0404 December 2012 Relief Request: American Society of Mechanical Engineers (Asme), Code Case N-770-1 ML12250A6422012-10-15015 October 2012 Correction to Relief Request ISI-3-35, Use of Subsequent Edition of ASME OM Code for Snubbers Program, for 3rd and 4th 10-Year Inservice Inspection Intervals ML12179A4922012-07-20020 July 2012 Relief Request ISI-3-35, Use of Subsequent Edition of ASME OM Code for Snubbers Program, for 3rd and 4th 10-Year Inservice Inspection Intervals ML1127300742011-11-0404 November 2011 Relief Requests ISI-3-32, ISI-3-33, and ISI-3-34, Alternative to Requirements for Examinations of Welds and Core Support Structure Surfaces, Third 10-Year Inservice Inspection ML0927901532009-10-0202 October 2009 Revision 1 to Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-29, Inspection of Reactor Vessel Head Control Element Drive Mechanism Nozzles ML0927901552009-10-0202 October 2009 Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-30, Inspection of Reactor Vessel Head In-Core Instrument Nozzles ML0836403752009-01-23023 January 2009 Relief Requests ISI-3-27, Revision 1, and ISI-3-28, Revision 1, for the Application of Weld Overlay on Dissimilar and Similar Metal Welds ML0832201312008-11-12012 November 2008 Revision to Third Ten-Year Inservice Inspection (ISI) Interval Requests ISI-3-27 and ISI-3-28, Use of Structural Weld Overlay and Associated Alternative Repair Techniques ML0824609302008-09-0808 September 2008 Corrections to Safety Evaluations Issued for Approval to Use Alternative to the Requirements for Repair / Replacement Activities Related to the Performance of Structural Weld Overlays (TAC Nos. MD458.. ML0732404372007-12-13013 December 2007 Request for Relief ISI-3-28 - Approval to Use Alternatives to the Requirements of ASME Code for Repair/Replacement Activities Re Performance of Structural Weld Overlays (Tac Nos. MD6256 & MD6257) ML0732500042007-12-13013 December 2007 RR ISI-3-27 - Approval to Use Alternatives to the Requirements of ASME Code for Repair/Replacement Activities Related to Performance of Structural Weld Overlays (TACs MD4580 & MD4581) ML0713800132007-06-12012 June 2007 Relief Request ISI-3-25 - Third 10-Year Inservice Inspection Interval Re Use of Structural Weld Overlay and Associated Alternative Repair Techniques ML0713707402007-06-12012 June 2007 Relief Request ISI-3-24 Third 10-Year ISI Interval Regarding Four Reactor Coolant System Pressurizer, Dissimilar Metal, Nozzle-to-safe-end Welds Structural Overlay & Alternative Repair Techniques ML0703101542007-02-15015 February 2007 Relief Request for Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Reactor Vessel Head Penetration Repairs ML0701807372007-02-0707 February 2007 Third 10-year Inservice Inspection Interval, Requests for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML0634503472006-12-27027 December 2006 Relief, Relief Request ISI-3-23 for Third 10-Year ISI Interval to Allow Use of American Society of Mechanical Engineers Code Case N-746, MC9433 & MC9434 ML0628500962006-12-21021 December 2006 Request for Relief for the In-Service Inspection Program and Approval to Use the Alternative Requirements of ASME Code Case N-513-2 ML0631103222006-12-14014 December 2006 Request for Relief (RR ISI-3-18) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Third 10-Year ISI Interval ML0632405892006-12-14014 December 2006 Third 10-year Inservice Inspection Interval, Requests for Relief ISI-3-19 and ISI-3-20 from the Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code-TAC MD1128/1129 ML0626204912006-10-0202 October 2006 Request for Relief (ISI-3-16) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (TAC Nos. MC9433/MC9433) ML0626402822006-10-0202 October 2006 Request for Relief (ISI-3-17) from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (TAC Nos. MC9487/MC9488) ML0622902412006-08-15015 August 2006 Revision to the Duration of Relief Request ISI-3-22 Third 10-Year Inspection Interval, San Onofre Unit 3 ML0613503702006-05-11011 May 2006 Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-21 Requests for Alternative to ASME Code Rules for the Embedded Flaw Repair Process for Control Element Drive Mechanism (CEDM) # 56 ML0613600652006-05-11011 May 2006 Third Ten-Year Inservice Inspection (ISI) Interval Relief Request ISI-3-22 Request for Alternative to ASME Code Rules for the Inside Diameter Structural Weld Overlay Repair Process for Control Element Drive Mechanism (CEDM) # 56 ML0604103232006-02-0808 February 2006 Inservice Inspection Program Relief Request ISI-3-15 ML0602602212006-01-18018 January 2006 Withdrawal of Relief Request ISI-3-10, Revision 1 ML0505600352005-03-0909 March 2005 Evaluation of Relief for Use of Mechanical Nozzle Assemblies as an Alternate to the American Society of Mechanical Engineers Code Repairs ML0506800542005-03-0202 March 2005 Safety Evaluation of Relief for Repair of Pressurizer Sleeves During the Third 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4789 and MC4790) ML0436203412004-12-23023 December 2004 SONGS, Unit 3 - Request for Relief from Requirements of the ASME Code Concerning Reactor Vessel Head Penetration Repairs ML0613503742004-10-31031 October 2004 Attachment 1, Relief Request ISI-3-21 Evaluation of the Acceptability of Embedded Flaw Repair of the Indication in Reactor Vessel Head Penetration No. 56 at SONGS Unit 3 ML0426403392004-09-15015 September 2004 Revision to the Duration of Relief Request ISI-3-7 Third 10-Year Inspection Interval ML0420504262004-07-22022 July 2004 SONGS, Request Relief from Requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Concerning Inservice Inspection (ISI) Program Updates for the Third 10-Year ISI (TAC Nos. MC0334 & MC0335) ML0412604592004-05-0505 May 2004 SONGS, Units 2 & 3, Inservice Inspection Program Relief Request ISI-38, Embedded Flaw Repair Process ML0411401662004-04-21021 April 2004 SONGS, Units 2 and 3, Request for Relief from the Requirements of the ASME Code Concerning Updates to Inservice Testing Program ML0408401282004-03-19019 March 2004 Songs, Units 2 and 3 - Relief Request- Relaxation of the Requirements of Order EA-03-009 Regarding Reactor Pressure Vessel Head Inspections ML0408405762004-03-19019 March 2004 Relief, Requirements of the ASME Boiler and Pressure Vessel Code Concerning Mechanical Nozzle Seal Assemblies ML0302801692003-01-24024 January 2003 Mechanical Nozzle Seal Assembly Type 2 Code Replacement Request for Relief from 10 CFR 50.55a ML0232502022002-11-19019 November 2002 Second Ten-Year Interval Inservice Inspection Program Pressure Retaining Piping Welds Relief Requests B-2-06 & B-2-07 ML0223208152002-09-10010 September 2002 Songs Units 2 & 3, Relief, American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code Concerning Use of Electrical Discharge Machining, MB5251, MB5252 ML0208704592002-03-27027 March 2002 Relief, Mechanical Nozzle Assemblies as an Alternative to American Society of Mechanical Engineers (Amse) Code Repairs ML0133902732002-01-11011 January 2002 SONGS, Units 2 and 3, Request for Relief Regarding Reactor Pressure Vessel Nozzle Examinations (TAC Nos. MB2484 and MB2485) 2013-04-29
[Table view] Category:Letter
MONTHYEARIR 05000361/20240052024-10-0404 October 2024 NRC Inspection Report 05000361/2024005 and 05000362/2024005 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 07200041/20244012024-08-16016 August 2024 San Onofe Nuclear Generating Station, Security Baseline Inspection Report 07200041/2024401 IR 05000361/20240042024-08-0909 August 2024 NRC Inspection Report 05000361/2024004 and 05000362/2024004 ML24191A2472024-07-0202 July 2024 (Songs), Units 1, 2, and 3, and the Independent Spent Fuel Storage Installation - Revision to the ISFSI-Only Emergency Plan and Associated Changes to Emergency Plan Implementing Procedures ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24141A0802024-05-15015 May 2024 (Songs), Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Operating Report IR 05000361/20240022024-04-0101 April 2024 – NRC Inspection Report 050-00361/2024-002 and 050-00362/2024-002 ML24094A0642024-03-27027 March 2024 Independent Spent Fuel Storage Installation, Decommissioning Funding Status Report 2023 ML24065A0152024-02-28028 February 2024 Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation 2023 ML24044A0812024-02-14014 February 2024 LTR-24-0008: NRC Response to Paul Blanch Email Safety of Spent Nuclear Fuel at SONGS ISFSI IR 05000361/20240012024-02-13013 February 2024 NRC Inspection Report 050-00361/2024-001 and 050-00362/2024-001 (1) ML24037A0542024-01-30030 January 2024 (Songs), Units 2 and 3, Submittal of Annual Corporate Financial Reports ML24022A1492024-01-17017 January 2024 Independent Spent Fuel Storage Installation, Revision 4 to the Physical Security Plan ML24017A2432024-01-15015 January 2024 LTR-24-0008 Paul Blanch, E-mails Request for Formal Response to Requests for Meeting to Discuss Safety Issues with NRC Staff IR 05000361/20230062023-11-29029 November 2023 NRC Inspection Report 05000361/2023-006 and 05000362/2023-006 ML23333A0682023-11-22022 November 2023 (SONGS) Units 1, 2, 3 and Independent Spent Fuel Storage Installation - Notification of Change in Nuclear Officer IR 05000361/20230052023-10-11011 October 2023 NRC Inspection Report 05000361/2023005 and 05000362/2023005 ML23276A5942023-09-28028 September 2023 And Independent Spent Fuel Storage Installation - Supplement to Decommissioning Funding Status Reports ML23268A0922023-09-20020 September 2023 Generation Station, Units 1, 2 and 3, and the Independent Spent Fuel Storage Facility (ISFSI) - Re-Registration of Dry Fuel Storage Casks for Amended Certificate of Compliance No. 1040 IR 05000361/20230012023-09-13013 September 2023 NRC Inspection Report 05000361 2023-001 and 05000362 2023-004 ML23240A5372023-08-18018 August 2023 Confirmatory Survey Activities Summary and Results for the Unit 2 and 3 Intake Structures at the San Onofre Nuclear Generating Station San Clemente CA ML23129A1802023-06-14014 June 2023 Cover Letter to State of CA on Draft EA Regarding San Onofre ISFSI Updated DFPs IR 05000361/20230032023-05-31031 May 2023 NRC Inspection Report 05000361/2023003 and 05000362/2023003 IR 05000361/20230022023-05-23023 May 2023 NRC Inspection Report 05000361/2023-002 and 05000362/2023-002 ML23137A1032023-05-11011 May 2023 (Songs), Units 1, 2 and 3, and Independent Spent Fuel Storage Installation - 2022 Annual Radiological Environmental Operating Report ML23123A0932023-04-28028 April 2023 (Songs), Units 1, 2 and 3, Submittal of Annual Radioactive Effluent Release Report - 2022 ML23230A0882023-04-10010 April 2023 Independent Spent Fuel Storage Installation - Decommissioning Quality Assurance Plan ML23094A1272023-03-29029 March 2023 Independent Spent Fuel Storage Installation - 10 CFR 50.82(a)(8)(v and VII) and 10 CFR 72.30(c) Decommissioning Funding Status Report 2021 ML23094A1332023-03-29029 March 2023 Nuclear Property Insurance ML23062A1172023-02-28028 February 2023 Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation - 2022 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23059A2812023-02-22022 February 2023 (Songs), Units 1, 2 and 3, 2022 Annual Turtle Incidental Take Report ML23046A3792023-02-22022 February 2023 NRC Inspection Report 050-00361/2023-001 and 050-00362/2023-001 ML23045A2022023-02-0909 February 2023 Submittal of Annual Corporate Financial Reports for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 for Fy Ending June 30, 2022 ML22287A1352023-01-0505 January 2023 Issuance of Exemption from Title 10 of the Code of Federal Regulations Part 72.106(B), Independent Spent Fuel Storage Installation Controlled Area Boundary (L-2021-LLE-0056) ML22348A0622023-01-0404 January 2023 NRC to SCE, Transmittal of the National Marine Fisheries Service'S December 12, 2022, Letter of Concurrence for Decommissioning of San Onofre Nuclear Generating Statiion, Units 2 and 3 IR 05000206/20220062022-12-15015 December 2022 NRC Inspection Report 05000206/2022006, 05000361/2022-006, and 05000362/2022-006 ML22347A2122022-12-12012 December 2022 NMFS to NRC, Endangered Species Act Section 7(a)(2) Concurrence Letter for Decommissioning of the San Onofre Nuclear Generating Station ML22340A6652022-12-0505 December 2022 Letter from John Fassell, Chief; Re., State of California Department of Public Health Review and Comments on SONGS Draft Environmental Assessment ML22333A8192022-11-21021 November 2022 Submittal of San Onofre Nuclear Generating Station, Units 2 and 3, Defueled Safety Analysis Report, Revised November 2022 IR 05000361/20220052022-11-17017 November 2022 NRC Inspection Report 05000361/2022-005 and 05000362/2022-005 ML22301A1462022-10-20020 October 2022 Report of Violations of the National Pollutant Discharge Elimination System Permit San Onofre Nuclear Generating Station (Songs), Units 2 and 3 ML22277A0162022-09-29029 September 2022 Independent Spent Fuel Storage Installation Response to Request for Additional Information Regarding Request for Exemption from 10 CFR 72.106(b) IR 05000361/20220042022-09-26026 September 2022 NRC Inspection Report 05000361/2022-004 and 05000362/2022-004 ML22238A0552022-08-29029 August 2022 U.S. Nuclear Regulatory Commission'S Analysis of Southern California Edison'S Decommissioning Funding Status Report for San Onofre Nuclear Generating Station, Units 1, 2, and 3 ML22234A1602022-07-31031 July 2022 Final Report Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 18CLVS431 ML22207B8612022-07-26026 July 2022 NRC (Public) Inspection Report 05000361/2022003; 05000362/2022003 IR 05000361/20220032022-07-26026 July 2022 NRC Inspection Report (Public) 05000361-2022003 and 05000362-2022003 (002) IR 05000361/20220022022-05-12012 May 2022 NRC Inspection Report 05000361/2022-002 and 05000362/2022-002 2024-09-18
[Table view] Category:Safety Evaluation Report
MONTHYEARML0920203932010-02-24024 February 2010 Safety Evaluation for Amendment 165 to Release the Off-Shore Portions of the Circulating Water System from the License (TAC L605690) ML0634503472006-12-27027 December 2006 Relief, Relief Request ISI-3-23 for Third 10-Year ISI Interval to Allow Use of American Society of Mechanical Engineers Code Case N-746, MC9433 & MC9434 ML0525107022005-09-30030 September 2005 License Amendment, Issuance of Amendment to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports 2010-02-24
[Table view] |
Text
December 27, 2006 Mr. Richard M. Rosenblum Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 - RE:
REQUEST FOR RELIEF ISI-3-23 FOR THIRD 10-YEAR INSERVICE INSPECTION INTERVAL TO ALLOW THE USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE CASE N-746 (TAC NOS. MD1809 AND MD1810)
Dear Mr. Rosenblum:
By letter dated May 16, 2006, Southern California Edison (SCE, the licensee) submitted Relief Request ISI-3-23, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(i), to allow the use of American Society of Mechanical Engineers (ASME) Code Case N-746, Use of 46Fe-24Ni-21Cr-6Mo-Cu-N (UNS N08367) Bolting Material for Class 2 and 3 Components, for the third 10-year inservice inspection (ISI) interval, which began on August 18, 2003, and is scheduled to end on August 17, 2013.
The licensee proposes to use the Code Case for the replacement of bolting material associated with eight saltwater cooling pumps that supply cooling water from the ocean to the component cooling water-heat exchangers at San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS 2 and 3). Use of Code Case N-746 will allow SCE to use Unified Numbering System N08367 (UNS N08367) bolting material conforming to the requirements of SB-691 on replacement Salt Water Cooling Pumps.
The Nuclear Regulatory Commission (NRC) staff finds the licensees request for relief acceptable. Therefore, the NRC staff authorizes the alternative proposed by SCE, in accordance with 10 CFR 50.55a(a)(3)(i), which states that the proposed alternatives may be used when authorized by the Director of the Office of Nuclear Reactor Regulation if the applicant demonstrates that the proposed alternatives would provide an acceptable level of quality and safety.
Based on the information provided in the licensees submittal, the NRC staff concludes that the licensee has provided an acceptable alternative to the requirements of ASME Code,Section XI, 1998 Edition through 2000 Addenda. The staff concludes that the proposed alternative provides reasonable assurance of quality and safety. Therefore, the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for SONGS 2 and 3 for the current 10-year ISI interval, or until Code Case N-746 is approved for general use by inclusion in Regulatory Guide (RG) 1.84. After that time, if the licensee wishes to continue to use Code Case N-746, the licensee must follow the conditions, if any, specified in the RG.
R. Rosenblum The staff's safety evaluation is enclosed.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosure:
Safety Evaluation cc w/encl: See next page
ML063450347 *Minor editorial changes made in staff supplied SE OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CPNB* OGC-NLO NRR/LPL4/BC NAME NKalyanam LFeizollahi TChan TCampbell DTerao DATE 12/18/06 12/18/07 12/4/06 12/21/07 12/27/07 San Onofre Nuclear Generating Station Units 2 and 3 cc:
Mr. Daniel P. Breig Director, Radiologic Health Branch Southern California Edison Company State Department of Health Services San Onofre Nuclear Generating Station P.O. Box 997414, MS 7610 P.O. Box 128 Sacramento, CA 95899-7414 San Clemente, CA 92674-0128 Resident Inspector/San Onofre NPS Mr. Douglas K. Porter, Esquire c/o U.S. Nuclear Regulatory Commission Southern California Edison Company Post Office Box 4329 2244 Walnut Grove Avenue San Clemente, CA 92674 Rosemead, CA 91770 Mayor Mr. David Spath, Chief City of San Clemente Division of Drinking Water and 100 Avenida Presidio Environmental Management San Clemente, CA 92672 P.O. Box 942732 Sacramento, CA 94234-7320 Mr. James T. Reilly Southern California Edison Company Chairman, Board of Supervisors San Onofre Nuclear Generating Station County of San Diego P.O. Box 128 1600 Pacific Highway, Room 335 San Clemente, CA 92674-0128 San Diego, CA 92101 Mr. James D. Boyd, Commissioner Mark L. Parsons California Energy Commission Deputy City Attorney 1516 Ninth Street (MS 31)
City of Riverside Sacramento, CA 95814 3900 Main Street Riverside, CA 92522 Mr. Ray Waldo, Vice President Southern California Edison Company Mr. Gary L. Nolff San Onofre Nuclear Generating Station Assistant Director - Resources P.O. Box 128 City of Riverside San Clemente, CA 92764-0128 3900 Main Street Riverside, CA 92522 Mr. Brian Katz Southern California Edison Company Regional Administrator, Region IV San Onofre Nuclear Generating Station U.S. Nuclear Regulatory Commission P.O. Box 128 611 Ryan Plaza Drive, Suite 400 San Clemente, CA 92764-0128 Arlington, TX 76011-8064 Mr. Steve Hsu Mr. Michael R. Olson Department of Health Services San Diego Gas & Electric Company Radiologic Health Branch 8315 Century Park Ct. CP21G MS 7610, P.O. Box 997414 San Diego, CA 92123-1548 Sacramento, CA 95899 Mr. A. Edward Scherer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 March 2006
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF NUMBER ISI-3-23 SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
By letter dated May 16, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061380119), the Southern California Edison Company (SCE, the licensee) requested, pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
paragraph 50.55a(a)(3)(i), that the Nuclear Regulatory Commission (NRC) approve Relief Request ISI-3-23. The relief requested approval of American Society of Mechanical Engineers (ASME) Code Case N-746, Use of 46Fe-24Ni-21Cr-6Mo-Cu-N (Unified Numbering System (UNS) N08367) Bolting Material for Class 2 and 3 Components. Specifically, the licensee proposed to use the Code Case for the replacement of bolting material associated with eight saltwater cooling pumps that supply cooling water from the ocean to the component cooling water-heat exchangers at San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS 2 and 3). The ASME Code of record for replacement of components for SONGS 2 and 3 is the ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.
The ASME Code,Section XI, requires that the replacement pumps meet the construction code (or later) to which the original component was constructed. The existing pumps are ASME Code,Section III, Division 1, Class 3 pumps, constructed from 316L stainless steel material which require periodic overhauls to maintain reliability because of saltwater corrosion. The pumps will be replaced using UNS N08367 material, which is saltwater corrosion-resistant.
UNS N08367 material is included in the ASME Code,Section III, as an approved material for pressure boundary parts; however, the material is not listed in the ASME Code as an approved bolting material. To allow the use of UNS N08367 material, the ASME Code approved and published Code Case N-746 which approved UNS N08367 material for bolting applications.
Experience has shown the that use of UNS N08367 bolting material is superior to the existing 316L stainless steel bolting material that is currently used. The UNS N08367 bolting material provides superior corrosion resistance in saltwater service and provides galvanic compatibility with the pump pressure boundary parts.
The replacement of the saltwater pumps is scheduled to take place during the third 10-year inservice inspection (ISI) interval which began on August 18, 2003 and is scheduled to end on August 17, 2013. The ISI code of record for the SONGS 2 and 3, is ASME Code,Section XI, 1998 Edition through 2000 Addenda.
2.0 REGULATORY EVALUATION
Paragraph 50.55a(g) of 10 CFR specifies that ISI of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code,Section XI, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Paragraph 50.55a(a)(3) of 10 CFR states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Paragraph 50.55a(g)(5)(iii) of 10 CFR states that if the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit information, as specified in §50.4, to support the determinations.
3.0 EVALUATION OF THE RELIEF REQUEST The information provided by the licensee in support of the request has been evaluated by the NRC staff and the bases for disposition are documented below.
3.1 Licensees Evaluation 3.1.1 Component Identification SONGS Units: 2 and 3
==
Description:==
Salt Water Cooling Pumps, 4 per Unit.
Code Class: 3 3.1.2 Applicable Code Edition and Addenda The construction code for the SONGS 2 and 3 replacement saltwater cooling pumps is the ASME Boiler and Pressure Vessel Code,Section III, 1998 Edition through 2000 Addenda.
3.1.3 Applicable Code Requirements Sub-article ND-2128(a) ASME Code, Section Ill, 1998 Edition through 2000 Addenda states, "Material for bolts and studs shall conform to the requirements of one of the specifications listed in Table 3, ASME Section II, Part D, Subpart 1. Material for nuts shall conform to SA-194 or to the requirements of one of the specifications for nuts or bolting listed in Table 3 of ASME Section II, Part D, Subpart 1."
3.1.4 Reason for Request New saltwater cooling pumps are being fabricated from UNS N08367 material to replace the existing 316L stainless steel pumps. The pressure boundary parts will be UNS N08367 material as allowed by ASME Code,Section III. It is desired to use pressure boundary bolting
of the same chemical composition as the pressure parts, namely N08367. However, N08367 material is not listed in the bolting table (Table 3, ASME Code,Section II, Part D) specified in ASME Code, Section Ill, ND-2128.
For this application, the use of UNS N08367 bolting material is superior to the existing bolting materials in Table 3, ASME Code,Section II, Part D. The current bolting materials available in the Table 3 do not provide the superior corrosion resistance of UNS N08367 material in saltwater service and galvanic compatibility with the pressure boundary parts.
3.1.5 Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), SCE proposes to implement Code Case N-746 and use alternative pressure boundary bolting material (UNS N08367) for use on ASME Code, Section Ill, Division 1, Class 3 saltwater cooling pumps. The pumps fall under 10 CFR 50.55a(e), Quality Group C Components meeting the requirements for Class 3 components in the ASME Boiler and Pressure Vessel Code. Specifically, SCE is requesting approval to use Code Case N-746. This proposed alternative would provide an acceptable level of quality and safety and thus would meet the requirements of 10 CFR 50.55a(a)(3).
The pumps are being replaced with UNS N08367 material because of its superior corrosion resistance for saltwater service. The UNS N08367 material is already approved for use as pressure boundary components in various product forms such as plate (SB-688), forgings (SB-462 and SB-564), welded pipe and tube (SB-675, 804, and 676), seamless pipe and tube (SB-690); and rod, bar, and wire (SB-691).
There is a precedent for application of rod material for use as bolting. A review of Table 3, ASME Code,Section II, Part D, shows three nickel-alloy specifications that cover rods:
Ni-Cr-Fe-Mo, Fe-Ni-Cr-Co (SB-572), Ni-Mo-Cr, Ni-Cr-Mo (SB-574), and Ni-Cr-Fe rods (SB-581), listed as bolting. This precedent supports the approval of Code Case N-746.
3.1.6 Duration of Proposed Alternative SCE requests that the 10 CFR 50.55a(a)(3)(i) relief for the alternative bolting material for the saltwater cooling pumps be granted for SONGS 2 and 3 for the third 10-year interval which began on August 18, 2003, and is scheduled to end on August 17, 2013.
3.1.7 Staff Evaluation The licensee requested approval of ASME Code Case N-746, Use of 46Fe-24Ni-21Cr-6Mo-Cu-N (UNS N08367) Bolting Material for Class 2 and 3 Components. The relief is needed because of planned replacement of eight saltwater cooling pumps at SONGS 2 and 3. ASME Code,Section XI, 1998 Edition through the 2000 Addenda is the ISI Code of record for SONGS 2 and 3.
ASME Code,Section XI, requires that the new pumps meet the construction code to which the original item was constructed. The licensee stated that the existing pumps are ASME Code,Section III, Division 1, Class 3 pumps constructed from 316L stainless steel material, which require periodic overhauls to maintain reliability because of corrosion from saltwater. The existing pumps will be replaced with corrosion-resistant material UNS N08367, which is superior material for seawater service as compared to 316L material currently in service. UNS N08367 is a
nickel-molybdenum alloy with excellent resistance to chloride pitting and crevice corrosion.
UNS N08367 retains high ductility and impact strength and has been used for chemical process tanks and pipelines, offshore oil and gas production equipment, and seawater heat exchangers.
UNS N08367 material is included in the ASME Code,Section III, as an approved material for pressure boundary parts. However, the material is not listed in the ASME Code as an approved bolting material.
To approve the use of UNS N08367 as bolting material, the ASME Code,Section III, approved and published Code Case N-746. The NRC staff finds Code Case N-746 to be acceptable for use and has included it in the forthcoming revision of Regulatory Guide (RG) 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III. However, the forthcoming revision of RG 1.84 has not yet been published and, therefore, Code Case N-746 is not yet listed as an approved Code Case in RG 1.84.
Based on the pending approval of Code Case N-746, the staff finds the licensees reasoning in support of its request for relief acceptable and concludes that the use of Code Case N-746 is acceptable.
4.0 CONCLUSION
Based on the information provided in the licensees submittal, the NRC staff concludes that the licensee has provided an acceptable alternative to the requirements of ASME Code,Section XI, 1998 Edition through 2000 Addenda. The staff concludes that the proposed alternative provides reasonable assurance of quality and safety. Therefore, the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the SONGS 2 and 3 for the current 10-year ISI interval, or until Code Case N-746 is approved for general use by reference in RG 1.84.
After that time, if the licensee wishes to continue to use Code Case N-746, the licensee must follow the conditions, if any, specified in the RG. All other ASME Code, Sections III and XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: G. Georgiev Date: December 27, 2006