ML063450407

Fort Calhoun Station, Unit 1 - Request for Relief Use of Later Edition and Addenda of ASME Code for Examination of Cast Austenitic Stainless Steel Piping (TAC MD3052)

ML063450407
Person / Time
Site:	Fort Calhoun
Issue date:	01/05/2007
From:	Terao D NRC/NRR/ADRO/DORL/LPLIV
To:	Ridenoure R T Omaha Public Power District
Wang A B, NRR/DORL/LPL4, 301-415-1445
References
TAC MD3052
Download: ML063450407 (6)

Text

January 5, 2007Mr. R. T. RidenoureVice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR RELIEF RE: USEOF LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE FOR EXAMINATION OF CAST AUSTENITIC STAINLESS STEEL PIPING (TAC NO. MD3052)

Dear Mr. Ridenoure:

By letter dated September 22, 2006, Omaha Public Power District submitted a request to usecertain paragraphs and related portions of the 2001 Edition with the 2002 and 2003 Addenda of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at the Fort Calhoun Station, Unit No. 1.The Nuclear Regulatory Commission (NRC) staff concludes that the licensee's request to useAppendix III of the later edition and addenda of ASME Code,Section XI, addresses all related requirements and associated modifications and limitations in paragraph 50.55a(b) of Title 10 of the Code of Federal Regulations (10 CFR). Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv),the NRC staff approves the use of Appendix III of the 2001 Edition through the 2003 Addendafor ultrasonic testing examination of cast austenitic stainless steel piping at the Fort CalhounStation, Unit No. 1, for the remainder of the fourth 10-year inservice inspection interval. The NRC staff's safety evaluation is enclosed. If you have any questions regarding the safety evaluation, please contact Alan B. Wang at(301) 415-1445.Sincerely,/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-285

Enclosure:

Safety Evaluation cc w/encl: See next page

ML063450407NRR-028OFFICENRR/LPL4/PMNRR/LPL4/LADCI/CNPB/BCOGCLPL4/BCNAMEAWangLFeizollahiTChanFYCDTerao DATE12/21/0612/21/0612/5/061/3/071/5/07 April 2006Ft. Calhoun Station, Unit 1 cc:Winston & Strawn ATTN: James R. Curtiss, Esq.

1700 K Street, N.W.

Washington, DC 20006-3817ChairmanWashington County Board of Supervisors P.O. Box 466 Blair, NE 68008Mr. John Hanna, Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007Mr. David J. Bannister, ManagerFort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Joe L. McManisManager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Daniel K. McGheeBureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONREQUEST FOR RELIEF TO USE LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERSBOILER AND PRESSURE VESSEL CODE FOR EXAMINATION OFCAST AUSTENITIC STAINLESS STEEL PIPINGOMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1DOCKET NO. 50-28

51.0 INTRODUCTION

By letter dated September 22, 2006 (Agencywide Documents Access and Management SystemAccession No. ML062680167), Omaha Public Power District (the licensee) submitted a request to use certain paragraphs and related portions of the 2001 Edition with the 2002 and the 2003 Addenda of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at Fort Calhoun Station, Unit No. 1 (FCS).

2.0REGULATORY EVALUATION

The regulations in paragraph 50.55a(g)(4) of Title 10 of the Code of Federal Regulations(10 CFR) establish the effective ASME Code edition and addenda to be used by licensees for performing inservice inspections (ISI) of components and supports. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year 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 ISI code of record at Fort Calhoun for the fourth 10-year ISI interval which began on November 3, 2003, is the 1998 Edition through the 2000 Addenda. As allowed by the Code, the licensee extended the third interval to coincide with a refueling outage, thus the fourth interval will end on September 26, 2013. Paragraph 50.55a(g)(4)(iv) of 10 CFR states that the inservice examination of components andsystem pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph 50.55a(b), subject to the limitations and modifications listed therein and U.S. Nuclear Regulatory Commission (NRC) approval.

Portions of the editions or addenda may be used provided that all related requirements of the respective editions and addenda are met, subject to any modifications and limitations, and NRCapproval. The NRC Regulatory Issue Summary 2004-16, "Use of Later Editions and Addenda to ASME [Operation and Maintenance] Code Section XI for Repair/Replacement Activities,"

provides additional guidance on the use of later additions and addenda of Section XI of the ASME Code.

3.0TECHNICAL EVALUATION

3.1.System/Component(s) for which Relief is RequestedCast Austenitic Stainless Steel Piping - The hot and cold-leg piping connecting the reactorcoolant system to the two steam generators is cast stainless steel. The welds to be examined are the hot and cold-leg tie-in welds of the two replacement steam generators. Each replacement steam generator has one hot-leg and two cold-leg welds. The nominal wall thickness of the hot leg is approximately 3.5 inches and the cold leg is approximately 2.5 inches.3.2Applicable Code RequirementsThe ASME Code of record for the fourth 10-year ISI interval is the 1998 Edition through the 2000 Addenda.3.3 Licensee's RequestPursuant to 10 CFR 50.55a(g)(4)(iv), the licensee requests approval to use selected portions ofthe ASME Code,Section XI, 2001 Edition through the 2003 Addenda, for ultrasonic testing (UT) of cast austenitic stainless steel (CASS) piping.3.4Proposed Subsequent Portions of the ASME Code and Related RequirementsThe licensee requests approval to use the ASME Code,Section XI, Appendix III, of the2001 Edition through the 2003 Addenda for examination of cast stainless steel piping at FCS. The licensee states that there are no related requirements. 4.0EVALUATIONThe licensee proposed to use portions of a subsequent edition and addenda to the ASMECode,Section XI, that has been incorporated by reference in 10 CFR 50.55a(b)(2). The NRC staff's review focused on whether the related requirements of the respective code and addenda are being met, and any modifications and limitations that may apply. The licensee proposes to use the ASME Code,Section XI, Appendix III, of the 2001 Edition through the 2003 Addenda inits entirety for the cast stainless steel piping at FCS for the fourth 10-year ISI interval. The licensee identified that there are no related requirements. UT inspections of piping requires the use of Appendix VIII for the performance demonstration ofultrasonic examination systems. The requirements for CASS piping are in the course of preparation. Appendix VIII states that for piping welds whose requirements are in the course ofpreparation, the requirements of Appendix III, as supplemented by Table I-2000-1, shall be met. The scope of Appendix III of the ASME Code, 1998 Edition through the 2000 Addenda (theCode of record for FCS) is limited to vessels having nominal wall thickness of 0.2 inches to 2.0 inches, and does not address requirements for the subject piping welds. Appendix III of thislater edition and addenda provides requirements for UT examination of vessel and piping welds and is not limited to less than 2.0 inches.The NRC staff finds the use of Appendix III of ASME Code,Section XI, of the later edition andaddenda acceptable because this version of Appendix III contains the inspection requirementsfor the subject welds.

5.0CONCLUSION

The NRC staff concludes that the licensee's request to use Appendix III of t he later editionand addenda of ASME Code,Section XI, addresses all related requirements, associated modifications, and limitations in 10 CFR 50.55a(b). Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the NRC staff approves the use of Appendix III of t he 2001 Editionthrough the 2003 Addenda for UT examination of CASS piping at FCS for the remainder of the fourth 10-year ISI interval. Principal Contributor: A. Keim Date: January 5, 2007