ML20066L465

Provides Substantiation of Adequacy of Leak Test Angle During Postulated Design Basis Events,Per . Containment Liner Serves as Pressure Boundary & Leak Tight Membrane During Postulated Accident

ML20066L465
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/26/1982
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-798, NUDOCS 8212010082
Download: ML20066L465 (2)

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wawww < SHOREHAM NUCLEAR POWER STATION P.O. WOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 November 26, 1982 SNRC-798 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Ref. 1 Letter SNRC-747 dated 8/9/82 LILCO (J. L. Smith) to NRC, Region I (R. C. Haynes)

Dear Mr. Denton:

The Ref. 1 letter responded to an unresolved I & E inspection item (Number 322/82-17-02) concerning containment leak test channels welded to the containment liner and the fact that the vents on these channels would be plugged during the performarice of the containment integrated leak rate test (ILRT). As stated in that letter, LILCO's intention not to remove these plugs was considered warranted for several reasons, including the follow-ing:

1) A detailed evaluation of the leak test channel system showed that the channel integrity is retained when subjected to all appropriate load combinations as defined in the DAR and FSAR.

2) Since the plugs are to be in place during operating conditions and NRC policy and industry practico is to perform tests in the operating configuration, the plugs should be in place during testing.

3) Construction (welder qualification material certification, etc.) of the leak test channels was equivalent to the construction of the remainder of C the primary containment liner. oD )}). f

4) The existing configuration provides a double barrier against potential leak paths from the primary con-tainment to the secondary containment in the area of the containment liner welds.

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Mr. Denton November 26, 1982 Page 2 In a 10/26/82 meeting with members of your staff, the NRC essentially. concurred with LILCO's approach. LILCO was re-quested, however, to provide a more detailed substantiation of the adequacy of the leak test angle during the oostulated design basis events, which is the purpose of this latter.

The Shoreham nuclear power station containment liner serves as a pressure boundary and leak tight membrane during a postulated accident. The liner was designed using the rules of ASME III 1968 edition as a guide as discussed in Shoreham FSAR Section 3.8.1.2.2 " Steel Liner and Penetrations". The leak test angles were installed to provide a means for testing the liner welds during construction to assure leak tightness of the liner connection welds. The leak test angles were not designed as strength elements or as a pressure boundary. However, the strength of the test angles and the weld connections were evaluated using the loading combinations for steel structures as shown in Shoreham FSAR Section 3.8.4.3.4 " Loading Combinations for Steel Structures" and the Shoreham DAR (Revision 5) Table 2-3A

" Load Combinations and Stress Limits for Structural Steel". Using the above loading combinations, the calculation shows that the angles and the weld connections remain intact during the postulated design basis events.

We trust the above is responsive to your request. Your approval is requested as soon as possible so that the present ILRT Test Schedule can be maintained.

Should you have any questions, please contact this office.

Very truly yours,

.c . L,

. L. Smith Manager, Special Projects Shoreham Nuclear Power Station JLS/jm c.c.: J. Higgins All parties

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