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Category:Memoranda
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Text
April 18, 2011 MEMORANDUM TO: Docket File FROM: N. Kalyanam, Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - VERBAL AUTHORIZATION OF REQUEST FOR ALTERNATIVE, W3-ISI-018 (TAC NO. ME5702)
By letter dated February 16, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110480484), Entergy Operations, Inc. (Entergy, the licensee),
requested U.S. Nuclear Regulatory Commission (NRC) approval of a proposed Request for Alternative W3-ISI-018, Inspection of Reactor Pressure Vessel Head Control Element Drive Mechanism Nozzles during the Third Ten-Year Inservice Inspection Interval, for Waterford Steam Electric Station, Unit 3 (Waterford 3).
The licensee requested relief from the inspection requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-729-1, Alternative Examination Requirements for Pressurized Water Reactor (PWR) Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial Penetration Welds,Section XI, Division 1, as required and conditioned by Title 10 of the Code of Federal Regulations (10 CFR) Part 50.
For W3-ISI-018, relief was requested due to the inability to qualify the ultrasonic examination techniques and personnel for examination of control element drive nozzles (CEDM) nozzles in accordance with the requirements.
The NRC authorized the same proposed alternative for Waterford 3 during the 16th refueling outage. The licensee had planned to replace the reactor vessel head (RVH) during refueling outage RF17. The licensee was scheduled to replace its RVH concurrently with replacement of the original steam generators. Replacement of both components would necessitate a temporary opening in containment.
The licensee discovered a manufacturing condition with the replacement steam generators which would prevent their installation during RF17. Replacing the upper head alone in RF17 would present a significant hardship to perform temporary openings in containment during sequential refueling outages. Further, due to the planned replacement of the Waterford 3 RVH, and industrys decision to discontinue generic efforts to establish a volumetric qualification program for Combustion Engineering plant CEDM nozzles, it would be a hardship for the licensee to develop and complete a qualification program between the fall of 2010 and RF17 at Waterford 3.
Based on the previous NRC authorizations of the licensees proposed alternatives and similar hardships existing now for RF17, the staff concludes that the licensees proposed alternatives provide reasonable assurance of structural integrity and leak-tightness of the subject CEDM nozzles, and that complying with the requirements of ASME Code Case N-729-1, as required and conditioned by 10 CFR 50.55a(g)(6)(ii)(D), would result in hardship without a compensating increase in the level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii). Therefore, the NRC staff provides verbal authorization for the proposed alternatives, W3-ISI-018, for the Waterford 3 for the 17th refueling outage, in the spring of 2011, up to the commencement of the 18th refueling outage in the fall of 2012 when the RVH is scheduled to be replaced.
All other ASME Code requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The participants in the telephone call were:
NRR REGION IV ENTERGY M. Markley J. Melfi W. Steelman T. Lupold J. Pollock J. Collins R. Williams N. Kalyanam W. Sims S. Bennett Docket No. 50-382
ML111010371 *via email OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB/BC NRR/LPL4/BC NRR/LPL4/PM MMarkley (BSingal NAME NKalyanam JBurkhardt TLupold* for) NKalyanam DATE 4/12/11 4/12/11 4/6/11 4/18/11 4/18/11
