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Category:Code Relief or Alternative
MONTHYEARML12249A2362012-10-11011 October 2012 Nuclear Generating Plant - Relief Request #11-001-MX Related to Suspension of Concrete Containment Examination for the Fourth-10-Year Interval of the Inservice Inspection Program 3F0912-08, Relief Request 11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i)2012-09-19019 September 2012 Relief Request #11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i) 3F0412-08, Relief Request (RR) 12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair2012-04-30030 April 2012 Relief Request (RR) #12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair ML1006400842010-03-19019 March 2010 Relief Requests 09 001 II, 09 002 II, and 09 003 II, Third 10-year Interval Inservice Inspection Program Plan. 3F0309-06, Submittal of Relief Request 09-001-IT, Revision 02009-03-30030 March 2009 Submittal of Relief Request #09-001-IT, Revision 0 ML0908204922009-03-20020 March 2009 Submittal of Third Ten-Year Inservice Inspection Interval Relief Requests #09-001-11, #09-002-11 and #09-003-11 ML0822103922008-09-0909 September 2008 Request for Relief No. 07-001-SS Regarding the Fourth 10-Year Interval Inservice Inspection Visual Examination of the Reactor Vessel Support Skirt ML0812604712008-05-22022 May 2008 Relief Request #08-001-RR, Revision 1, to Install a Weld Overlay on the Dissimilar Metal Weld in the Decay Heat Drop Line 3F0907-05, Relief Request 07-003-RR, Revision 1, and Response to Request for Additional Information2007-09-13013 September 2007 Relief Request #07-003-RR, Revision 1, and Response to Request for Additional Information ML0601302032006-02-0101 February 2006 Relief Request Subsequent Edition Letter and Addenda to Section XI of the ASME Code for Repair/Replacement Activities ML0400604752004-01-0606 January 2004 Ltr Safety Evaluation of Relief Request 03-001-RR and 03-0002-RR Concerning Alternative Repair Method and Flaw Characterization for Pressurizer Instrument Nozzle Penetrations 2012-09-19
[Table view] Category:Letter
MONTHYEARML23342A0942024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information ML23345A1882023-12-0606 December 2023 Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML23320A2592023-11-17017 November 2023 STC-23 077 Notification of the Crystal River Unit 3 Generating Plant License Termination Plan Public Meeting and Federal Register Notice ML23313A1322023-11-15015 November 2023 Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant ML23310A0712023-11-0707 November 2023 Audit Plan Cover Letter - Crystal River Unit 3 Nuclear Generating Plant LTP ML23187A1112023-07-25025 July 2023 Acceptance of Requested Licensing Action License Request to Add License Condition to Include License Termination Plan Requirements ML23107A2722023-06-13013 June 2023 Letter Transmitting NRC Survey Results for East Settling Pond ML23160A2962023-06-0909 June 2023 Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan ML23107A2732023-06-0707 June 2023 Orise Independent Survey Report Dcn 5366-SR-01-0 IR 05000302/20220032023-05-25025 May 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2022003 ML23103A1902023-04-19019 April 2023 Request for Supplemental Information Cover Letter ML23058A2532023-03-22022 March 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River, Unit 3 - NRC Inspection Report No. 05000302/2022003 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 ML22265A0192022-09-26026 September 2022 Nuclear Generating Plant - U.S. Nuclear Regulatory Commission'S Analysis of ADP CR3, Llc'S Decommissioning Funding Status Report (License No. DPR-72, Docket Nos. 50-302 and 72-1035) IR 05000302/20220022022-08-0909 August 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022002 IR 05000302/20220012022-05-0303 May 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022001 ML22116A1752022-04-27027 April 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3- Independent Spent Fuel Storage Installation Security Inspection Report 07201035/2022401 ML22105A3992022-04-18018 April 2022 Nuclear Generating Plant - Change in NRC Project Manager ML22011A1362022-01-31031 January 2022 Independent Spent Fuel Storage Installation Security Inspection Plan IR 05000302/20210042022-01-24024 January 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2021004 ML22024A2142022-01-24024 January 2022 Nuclear Generating Plant - NMFS NRC Letter - Crystal River Energy Complex Biological Opinion Status (License No. DPR-72, Docket Nos. 50-302 and 72-1035) ML21351A0052021-12-20020 December 2021 NRC Analysis of ADP CR3, LLC Decommissioning Funding Status Report for the Crystal River Unit 3 Nuclear Generating Plant (License No. DPR-72, Docket Nos. 50-302 and 72-1035) ML21322A2702021-11-24024 November 2021 Nuclear Generating Plant - Issuance of Amendment No. 260 Approving the Independent Spent Fuel Storage Installation Only Security Plan, Rev 3 IR 05000302/20210032021-11-0909 November 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021003 and 07201035/2021001 ML21288A4292021-10-18018 October 2021 Letter - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan ML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a IR 05000302/20210012021-08-12012 August 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021001 and 05000302/2021002 ML21182A1032021-07-0606 July 2021 Request for Additional Information (RAI) Related to the ISFSI-Only Emergency Plan ML21159A0422021-06-28028 June 2021 VY and CR Indirect License Transfer Package ML21060B4142021-04-12012 April 2021 U.S. Nuclear Regulatory Commission Analysis of Duke Energy Florida, Llc'S Initial Decommissioning Funding Plan for the Crystal River Independent Spent Fuel Storage Installation ML21028A5912021-03-0202 March 2021 Letter to Reid Forwarding Exemption from 10 CFR Part 20, Appendix G, Section Iii.E ML21055A7832021-02-25025 February 2021 Letter to Reid, Change in NRC Staff Project Management for Crystal River Unit 3 Nuclear Generating Plant ML21012A3142021-01-13013 January 2021 Independent Spent Fuel Storage Installation Security Inspection Plan IR 05000302/20200012020-11-19019 November 2020 NRC Inspection Report No. 05000302/2020001, Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3, Crystal River, Florida ML20269A2922020-10-0707 October 2020 NRC Form 311 QA Program Approval Revision 10 Related to Crystal River 3 ML20101G5822020-04-10010 April 2020 CR-3 License Transfer SE Corrected Cover Letter ML20069A0232020-04-0101 April 2020 Order Approving Transfer of Licensed Authority from Duke Energy Florida, LLC, to ADP CR3, LLC, and Draft Conforming Administrative License Amendment ML20050D0142020-02-19019 February 2020 NRC Independent Spent Fuel Storage Installation Inspection Report No. 07201035/2020001, Duke Energy Florida, LLC, Crystal River Unit 3, Crystal River, Florida ML20050F7702020-02-14014 February 2020 30-Day Notice of Payment from the City of Tallahassee Trust Fund Non-Qualified Nuclear Decommissioning Trust Fund for Crystal River Unit 3 ML20015A5672020-01-15015 January 2020 Independent Spent Fuel Storage Installation Security Inspection Plan ML20009D0432020-01-10010 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility Operating License No. DPR-72 ML19339G5092020-01-0202 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Approval of Partial Site Release for Facility Operating License No. DPR-72 ML19343A8252019-12-0606 December 2019 Letter from Erika Bailey, Oak Ridge Institute for Science and Education, to John Hickman, NRC, Forwarding Independent Confirmatory Survey Summary and Results for the 3,854-Acre Area Partial Site Release at the Crystal River Energy Complex IR 05000302/20190022019-11-20020 November 2019 NRC Inspection Report No. 05000302/2019002 and Independent Spent Fuel Storage Installation Inspection Report No. 07201035/2019002, Duke Energy Florida, LLC, Crystal River Unit 3, Crystal River, Florida ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19261A0702019-09-19019 September 2019 VEGP U3 Proficiency Watches Prior to Fuel Load ML19177A0802019-06-26026 June 2019 Nuclear Generating Plant (CR-3) - Notification of Revised Post-Shutdown Decommissioning Activities Report (Revised PSDAR) ML19170A1942019-06-14014 June 2019 Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment ML19129A1402019-05-15015 May 2019 Letter to Hobbs, Correction to Amendment No. 257 Approving Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Revision 1 2024-01-09
[Table view] Category:Safety Evaluation
MONTHYEARML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a ML21159A0422021-06-28028 June 2021 VY and CR Indirect License Transfer Package ML20101G5832020-04-10010 April 2020 CR-3 License Transfer SE Corrected ML20101G5822020-04-10010 April 2020 CR-3 License Transfer SE Corrected Cover Letter ML20069A0272020-04-0101 April 2020 CR-3 License Transfer Enc 3 SE ML20009D0432020-01-10010 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility Operating License No. DPR-72 ML20009D2502020-01-10010 January 2020 SER Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility ML19339G5092020-01-0202 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Approval of Partial Site Release for Facility Operating License No. DPR-72 ML19080A1892019-05-0303 May 2019 Rev 1 Safety Evaluation ML17027A1672017-06-27027 June 2017 Safety Evaluation ML17096A2832017-06-22022 June 2017 Non-Sensitive Safety Evaluation by the Office of Nuclear Material Safety and Safeguards for Crystal River Unit 3 ML17048A4832017-03-22022 March 2017 Safety Evaluation for CR-3 ISFSI Emergency Plan and EAL Bases Manual ML16244A1032016-12-0505 December 2016 Safety Evaluation for Crystal River Unit 3 ISFSI Emergency Plan ML16201A1352016-08-12012 August 2016 Safety Evaluation Input for Independent Spent Fuel Storage Installation Only Emergency Plan ML16173A0222016-08-10010 August 2016 Safety Evaluation for License Transfer, Crystal River Unit 3, from Seminole Electric Corp., Inc. to Duke Energy Florida, Inc ML15261A4522015-11-27027 November 2015 Nuclear Generating Plant - Issuance of Amendment No. 249 Regarding Technical Specification Change of Management Titles to General Manager Decommissioning ML15224B2862015-09-0404 September 2015 Nuclear Generating Plant - Issuance of Amendment for Operating License and Technical Specification Based on Permanently Shutdown and Defueled Status ML15121A5702015-05-29029 May 2015 Letter, Safety Evaluation for Order Approving Transfer of Licenses and Conforming Amendments ML15110A1292015-04-22022 April 2015 Correction to the Emergency Planning Exemptions Safety Evaluation ML15027A2092015-03-31031 March 2015 Issuance of Amendment Regarding Changes to the Emergency Plan and Emergency Action Levels ML15058A9062015-03-30030 March 2015 Letter, Exemptions from Certain Emergency Planning Requirements and Related Safety Evaluation ML14344A4082014-12-19019 December 2014 Nuclear Generating Plant - Review of Spent Fuel Management Program and the Preliminary Decommissioning Cost Estimate ML14318A9292014-12-19019 December 2014 H. B. Robinson; Shearon Harris Nuclear Power Plant; and Crystal River, Unit 3 - Issuance of License Amendments Regarding Revision to Cyber Security Plan Implementation Schedule Completion Date (TAC Nos. MF3263 - MF3267) ML14097A1452014-07-11011 July 2014 Nuclear Generating Plant - Issuance of Amendment No. 244, Revise Technical Specifications to Remove Certain Requirements from Section 5, Administrative Controls ML14155A1812014-06-26026 June 2014 Review of Certified Fuel Handler Training and Retraining Program ML13158A2772013-10-18018 October 2013 Issuance of Amendment Regarding the Request to Change the Licensee'S Name ML13121A1092013-05-0909 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security ML12249A2362012-10-11011 October 2012 Nuclear Generating Plant - Relief Request #11-001-MX Related to Suspension of Concrete Containment Examination for the Fourth-10-Year Interval of the Inservice Inspection Program ML12136A3922012-06-26026 June 2012 Issuance of Amendment Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments ML11292A0412012-02-24024 February 2012 Nuclear Generating Plant - Issuance of Amendment 240 Regarding Improved Technical Specifications 3.7.19 Diesel Drive Emergency Feedwater Pump Fuel Oil, Lube Oil, and Starting Air ML11321A1652011-12-27027 December 2011 Nuclear Generating Plant - Issuance of Amendment 239 Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments ML11255A0552011-12-0202 December 2011 Transmittal Letter - Order Approving Indirect License Transfer ML11193A0282011-07-29029 July 2011 Issuance of Amendments Approval of Cyber Security Plan ML1006400842010-03-19019 March 2010 Relief Requests 09 001 II, 09 002 II, and 09 003 II, Third 10-year Interval Inservice Inspection Program Plan. ML0911000562009-05-29029 May 2009 License Amendment, Issuance of Amendment Regarding the Revision of the Steam Generator Portion of the Technical Specifications to Replacement of the Steam Generators ML0834704912009-01-0909 January 2009 Issuance of Amendment Regarding Revisions to Improved Technical Specification Surveillance Requirement 3.7.5.2, Emergency Feedwater System ML0822103922008-09-0909 September 2008 Request for Relief No. 07-001-SS Regarding the Fourth 10-Year Interval Inservice Inspection Visual Examination of the Reactor Vessel Support Skirt ML0817502522008-07-31031 July 2008 Relief Request No. 07-00-001- Pt Fourth Ten-Year Interval Inservice Inspection on System Pressure Test Boundary Tac MD7738) ML0820200062008-07-30030 July 2008 Issuance of Amendment 230 Regarding Control Room Envelope Habitability in Accordance with TSTF-448 ML0812604712008-05-22022 May 2008 Relief Request #08-001-RR, Revision 1, to Install a Weld Overlay on the Dissimilar Metal Weld in the Decay Heat Drop Line ML0730301322007-11-15015 November 2007 Relief Request #07-003-RR Regarding Structural Weld Overlays ML0729103172007-10-25025 October 2007 License Amendment 227 Fuel Storage Patterns in the Spent Fuel Pool ML0725501372007-10-24024 October 2007 Issuance of Amendment Regarding Spent Fuel Pool Missile Shields ML0728508942007-10-23023 October 2007 License Amendment 225 Regarding Nuclear Services Closed Cycle Cooling Water System ML0722600082007-08-23023 August 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (Tac No. MD4524) ML0715004662007-06-15015 June 2007 License Amendment, Issuance of Amendment to Adopt TSTF-372 ML0713401122007-05-16016 May 2007 Issuance of License Amendment 223 Regarding Steam Generator Tube Inspection Program ML0709505032007-04-27027 April 2007 Evaluation of 2005 Steam Generator Tube Inspections at Crystal River Unit 3 ML0622005742006-10-19019 October 2006 Authorization for Use of Delta Protection Mururoa Single-Use, Supplied-Air Suits, Models V4 F1 and V4 Mth 2 2021-06-28
[Table view] |
Text
February 1, 2006Mr. Dale E. Young, Vice PresidentCrystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 West Power Line Street Crystal River, FL 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - RE: REQUEST FOR RELIEF FROM THEREQUIREMENTS OF THE ASME CODE (TAC NO. MC8993)
Dear Mr. Young:
By letter dated November 23, 2005, Florida Power Corporation submitted a request to use the1998 Edition, 2000 Addenda to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (hereafter referred to as the ASME Code)Section XI, for repair/replacement activities. Additional clarifying information was discussed in a phone call on December 1, 2005, between Florida Power Corporation and the Nuclear RegulatoryCommission (NRC) staff. The current inservice inspection Code of record for Crystal River,Unit 3, is the 1989 Edition, no Addenda. The authorization of the subsequent edition andaddenda of the ASME Code will allow the use of welder qualifications of the vendor performingwelding of an Inconel 690 plug in the Once-Through Steam Generator to repair a previously plugged tube. Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g)(4)(iv) states thatinservice examination of components and system pressure tests may meet the requirementsset forth in subsequent editions and addenda of the ASME Code provided that they are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed in 10 CFR 50.55a(b) and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.
D. Young-2-Due to the licensee's need for approval prior to restart, the NRC staff granted verbal approvalon December 1, 2005. The enclosed safety evaluation documents the verbal approval of the request.Sincerely,/RA/Michael L. Marshall, Jr., ChiefPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-302
Enclosure:
Safety Evaluation cc w/encl: See next page
ML060130203*No Legal ObjectionNRR-028OFFICELPL2-2/PMLPL2-2/LACFEB/BCOGCLPL2-2/BC NAMEBMozafariBClaytonJTsao by memo*MBuppMMarshall DATE 01 /31/200601/31/200612/20/200501/30/200602/01/2006 EnclosureSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELIEF REQUEST REGARDING THE USE OF A SUBSEQUENT EDITION AND ADDENDATO AMERICAN SOCIETY FOR MECHANICAL ENGINEERSBOILER AND PRESSURE VESSEL CODE SECTION XI FORREPAIR/REPLACEMENT ACTIVITIESFLORIDA POWER CORPORATIONCRYSTAL RIVER NUCLEAR PLANT, UNIT 3DOCKET NO. 50-30
21.0INTRODUCTION
By letter dated November 23, 2005, Florida Power Corporation (the licensee) submitted arequest to use the 1998 Edition, 2000 Addenda to the American Society of Mechanical Engineers (ASME) Boiler And Pressure Vessel Code (hereafter referred to as the ASME Code)
Section XI, Paragraph IWA-4712, "Fusion Welding" for repair/replacement activities. Additional clarifying information was discussed in a phone call on December 1, 2005, between Florida Power Corporation and the Nuclear Regulatory Commission (NRC) staff. The current inserviceinspection (ISI) Code of record is the 1989 Edition, no Addenda for Crystal River, Unit 3. The authorization of the subsequent edition and addenda of the ASME Code will allow the use ofwelder qualifications of the vendor performing welding of an Inconel 690 plug in the Once-Through Steam Generator to repair a previously plugged tube. The licensee submitted this request in accordance with the guidance provided in NRCRegulatory Issue Summary (RIS) 2004-16, dated October 19, 2004. In this RIS, the NRC staffstated that licensees who wish to use provisions of those editions and addenda of Section XI to the ASME Code subsequent to the Code of record for activities, including repair/replacement activities, must receive prior NRC review and approval as required by section 50.55a(g)(4)(iv) ofTitle 10 of the Code of Federal Regulations (10 CFR). 2.0REGULATORY REQUIREMENTSPursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (includingsupports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. Section50.55a(g)(4)(ii) of 10 CFR requires that ISI examination of com ponents and system pressuretests conducted during the first 10-year ISI interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The repair, replacement, and modification of plant components are not explicitly mentioned in10 CFR 50.55a(g)(4) and associated subparagraphs. However, these activities are specifically mentioned in ASME Code Section XI. The NRC staff considers that these activities are notseparate and distinct from, but are included under, inservice examinations. Therefore, the requirements of 10 CFR 50.55a(g)(4)(iv) are applicable to repair/replacement activities. Section 50.55a(g)(4)(iv) states that inservice examination of com ponents and system pressuretests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided that they are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed in 10 CFR 50.55a(b), and subject to Commission approval.
Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met. Currently, Section 50.55a(b)(2) incorporates by reference the ASME Code Section XI from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1).3.0REQUEST TO USE A SUBSEQUENT EDITION AND ADDENDA TO ASME CODESECTION XI FOR REPAIR/REPLACEMENT ACTIVITIES3.1Current Code RequirementsThe current ASME Section XI Code of record for Crystal River, Unit 3, is the 1989 Edition, withno Addenda. Paragraph IWB-4230 of the ASME Code, 1989 Edition with no Addenda provides requirements (specified in IWB-4231 through IWB-4235) that shall be met when manual or machine welding is used to weld plugs into heat exchanger tubes or tubesheet holes. The requirements include those for the welding procedure and performance qualifications. In particular, IWB-4232.4(e) provides requirements for performance qualification for welders and welding operators as follows:Renewal of qualification is required when the welder or welding operatorhas not performed tube plugging using the process for which he is qualified for 3 months or longer, or when there is a specific reason to question his ability to make quality weld per the Welding Procedure Specification. Renewal of qualification shall be identical to the initial qualification, except that only one tube weld need be made.In addition, IWB-4232.4 provides specific essential variables for performing the welderqualifications, such as welding process, filler metal, welding positions and preplaced metalinserts. 3.2Proposed Alternative Code Edition and RequirementsThe licensee proposes to use the 1998 Edition, 2000 Addenda of the ASME Section XI Codefor repair/replacement activities. Paragraph IWA-4712 of the ASME Code, 1998 Edition, 2000 Addenda provides requirements (specified in IWA-4712.1 through IWA-4712.5) that shall be met when manual, machine, or automatic welding is used to join plugs to Class 1 heat exchanger tubes or tubesheet holes. The requirements include those for the welding procedureand performance qualifications. In particular, IWB-4712.2(b)(6) provides requirements for performance qualifications for welders and welding operators as follows: Renewal of qualification is required when the welder or welding operatorhas not performed plugging using the process for which he is qualified for 6 months or longer, or when there is a specific reason to question his abilityto make quality welds in accordance with the WPS [Welding Procedure Specification]. Renewal of qualification shall be identical to the initial qualification, except that only one weld need be made.In addition, IWA-4712.2(b) provides specific essential variables for performing thequalifications, such as welding process, filler metal, base material, welding positions, preplaced metal inserts, and additional variables for welding operators in accordance with Section QW-360 to Section XI of the ASME Code.
4.0TECHNICAL EVALUATION
The NRC staff evaluated the licensee's request using the criteria contained in 10 CFR 50.55a(g)(4)(iv), which states that inservice examination of com ponents and systempressure tests may meet the requirements set forth in editions and addenda of the ASME Code subsequent to the Code of record provided certain conditions are satisfied.The first condition is that the proposed edition and addenda is incorporated by reference in10 CFR 50.55a(b). Currently, Section 50.55a(b)(2) incorporates by reference the ASME Code Section XI from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1), which includes the 1998 Edition, with 2000 Addenda of the ASME Section XI Code proposed by the licensee.The second condition is that the limitations and modifications listed in 10 CFR 50.55a(b) aresatisfied for the specific use of the proposed subsequent Code edition and addenda. There are no restrictions specified in 10 CFR 50.55a(b) for the portion of the 1998 Edition, with 2000 Addenda of the ASME Section XI Code that the licensee proposes to use.The third condition is that if portions of subsequent Code editions or addenda are used, allrelated requirements of the respective editions or addenda must be met. During a phone call with the licensee on December 1, 2005, the NRC staff requested a clarification of the followingstatement in the licensee's November 23, 2005, submittal to ensure that all of the relatedrequirements in Paragraph IWA-4712 of Section XI to the ASME Code, including that of the welding procedure, are met:The welding process and welder qualifications of the vendor performing theplug welding meets all of the requirements set forth in the ASME Code Section XI, 1998 Edition, 2000 Addenda. The licensee clarified the above statement by including the welding procedure in the abovestatement as shown in the November 23, 2005, submittal. Based on the licensee's submittal and the above clarification, the NRC staff is satisfied that the licensee has followed all relatedrequirements in the 1998 Edition, with 2000 Addenda of the ASME Code,Section XI that arerelevant to the stated repair/replacement activities.Based on the above, the NRC staff finds that the conditions of 10 CFR 50.55a(g)(4)(iv) aresatisfied and that the licensee
<s request to use the 1998 Edition, with 2000 Addenda of theASME Code,Section XI for repair/replacement activities is acceptable.
5.0CONCLUSION
The NRC staff concludes that the proposed request is acceptable and authorizes the use of theParagraph IWA-4712 to Section XI of the ASME Code, 1998 Edition, with 2000 Addenda, for the specified repair/replacement activities for the remainder of the current 10-year ISI intervals for Crystal River, Unit 3. All other requirements of the ASME Code,Section III and XI for whichrelief has not been specifically requested and approved remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.Principal Contributor: J. Honcharik Date: February 1, 2006 Mr. Dale E. YoungCrystal River Nuclear Plant, Unit 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, Florida 33733-4042Mr. Jon A. FrankePlant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Mr. Jim MallayFramatome ANP 1911 North Ft. Myer Drive, Suite 705 Rosslyn, Virginia 22209Mr. William A. Passetti, ChiefDepartment of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Attorney GeneralDepartment of Legal Affairs The Capitol Tallahassee, Florida 32304Mr. Craig Fugate, DirectorDivision of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100ChairmanBoard of County Commissioners Citrus County 110 North Apopka Avenue Inverness, Florida 34450-4245Mr. Michael J. AnnaconeEngineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Mr. Daniel L. RoderickDirector Site Operations Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708Senior Resident InspectorCrystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, Florida 34428Mr. Richard L. WardenManager Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708David T. ConleyAssociate General Counsel II - Legal Dept.
Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551