ML20214Q399

Informs That Interim Approval of ASME Code Relief from Hydrostatic Test Requirements for Auxiliary Feedwater Sys Granted,Per Util 870529 Request.Relief Contingent on Visual Exam of Sys Outside Containment at Least Once Per Wk

ML20214Q399
Person / Time
Site:	Calvert Cliffs
Issue date:	05/29/1987
From:	Capra R Office of Nuclear Reactor Regulation
To:	Tiernan J BALTIMORE GAS & ELECTRIC CO.
References
NUDOCS 8706050011
Download: ML20214Q399 (3)

Text

DISTRIBUTION Docket No. 50-318 _...s ..-

(Docket File'a OGC NRCPDR E. Jordan Local PDR J. Partlow Mr. J. A. Tiernan PDI-1 Rdg. ACRS(10)

Vice President - Nuclear Energy S. Varga L. Tripp Baltimore Gas & Electric Company B. Boger P. O. Box 1475 C. Vogan Baltimore, MD 21203 S. McNeil

SUBJECT:

INTERIM APPROVAL OF ASME CODE RELIEF FROM HYDROSTATIC TEST REQUIREMENTS FOR THE AUXILIARY FEEDWATER SYSTEM The Commission's staff has completed their preliminary review of your request for ASME Code relief as provided in your submittal dated May 29, 1987. This request for ASME Code relief was necessitated by your inability to successfully, hydrostatically pressure test an approximately 20 foot portion of the auxiliary feedwater (AFW) system feeding the No. 22 steam generator.

This inability was due to leakage developing from the mechanical flange gasket joint downstream of the check valve 2-AFW-200. This leak precluded the achievement of full test pressure. The leaking flange could not be repaired during the conduct of the test due to cutting of the flange seating surface.

In addition, you stated that immediate repair of the flange followed by a hydrostatic pressure retest of the AFW system would be impractical as this portion of the AFW system is currently unisolable from the No. 22 steam generator, thus the steam generator would experience an unnecessary pressure transient above its design pressure as a result of the hydrostatic pressure test. The operational lifetime of the steam generator is limited by the number of times it is permitted to be hydrostatically pressure tested above its design pressure.

If the AFW hydrostatic pressure test were deferred until the next Unit 2 refueling outage, the system could be tested without pressurizing the No. 22 steam generator as a new, flanged check valve will be installed to isolate the steam generator.

You are currently required by 10 CFR 50.55a(g)(4)(1) to meet the requirements of Section XI of the 1974 Edition and Addenda through the summer of 1975 of the ASME Boiler and Pressure Vessel Code.Section XI, Article IWC-2510, requires the AFW system to be tested in accordance with Articles IWA-5000 and IWC-5000. Article IWC-5000 provides the requirements to hydrostatically pressure test the AFW system.

In your May 29, 1987 submittal, you requested relief until the next Unit 2 refueling outage (scheduled for spring 1989) from the requirements of Article IWC-2510 that you hydrostatically pressure test a portion of the AFW system.

8706050011 870529 0 PDR ADOCK 0500 P

a This portion encompasses the piping and components from the flange connection downstream of check valve 2-AFW-200 extending to, but excluding, control valve 2-AFW-4512-CV, manual bypass valve 2-AFW-165, and check valve 2-AFW-130.

The Commission's staff understands that you shall repair the leaking AFW flange and leak test the portion of the AFW system for which relief was requested prior to entering Mode 4 from this refueling outage.

The staff has made an initial determination in accordance with the provisions of 10 CFR 50.55a(g)(6)(1) that your ASME Code relief request is acceptable on an interim basis until our completion of a more detailed review of this request.

This letter shall serve as interim approval of your request for relief from the requirements of Section XI Article IWC-2510 of the 1974 Edition with Addenda through the Summer of 1975 of the ASME Boiler and Pressure Code that the portion of AFW piping described herein be satisfactorily, hydrostatically pressure tested.

The granting of this interim ASME Code relief shall be contingent upon your performance of an auamented VT-2 visual examination on the section of the AFW system outside of containment for which relief was requested. This visual examination shall be performed at least once per week.

This interim approval for relief from the Section XI, Article IWC-2510 ASME Code requirements shall expire either upon the issuance of a final approval '

for relief along with the issuance of the appropriate Safety Euluation or upon determination that this ASME Code relief is not acceptable.

The Commission hereby grants this interim relief from the hydrostatic pressure test requirements for this portion of AFW piping pursuant to 10 CFR 50.55a(g)(6)(1) and finds that this interim relief is authorized by law and will not endanger life or property or the common defense and security and is )

otherwise in the public interest, giving due consideration to the burden upon j the licensee that could result if the requirments were imposed on the  ;

facility. i l

Sincerely, Robert A. Capra, Acting Director Project Directorate I-1 l Division of Reactor Projects I/II cc: See next nage DRPR:PD11 DRPR:PD11 DRPR:PD11 CVogan

• SMcNeilgam RCapra 05/ /87 05/.29/87 05/2*I/87

1. C voy - ^#'" 3

.l Mr. J. A. Tiernan Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant CC:

Mr. John M. Gott, Sr., President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Commission Commissioners Office of Executive Director Prince Frederick, Maryland 20768 for Operations 631 Park Avenue D. A. Brune, Esq. King of Prussia, Pennsylvania 19406 General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg, Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. M. E. Bowman, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P. O. Box 1535 l Lusby, Maryland 20657-0073 Pesident Inspector c/e U.S. Nuclear Regulatory Commission P. O. Box 437 ' -

Lusby, Maryland 20657-0073 Eechtel Power Corporation ATTN: Mr. D. E. Stewart 7 ivert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 1

! Combustion Engineering, Inc. l ATTH: Mr. W. R. Forlacher, III l Project Manager .

P. O. Box 500 l 1000 Prospect Hill Road l Windsor, Connecticut 06095-0500 l l Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette

, Tawes State Office Building l Annapolis, Maryland 21204 i

.