ML19257A549
| ML19257A549 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/24/1979 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML19257A548 | List: |
| References | |
| NUDOCS 8001040608 | |
| Download: ML19257A549 (2) | |
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- - - - w-u LONG ISLAND LIGHTING COMPANY FLC'O SHOREHAM NUCLEAR POWER STATION m a w zge w P.O. DOX 618, NORTH COUNTRY ROAD e WADING RIVER. N.Y.11792
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October 24, 1979 SNRC-441 Mr. Boyce Grier, Director Office of Inspection & Enforcement Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 LONG ISLAND LIGHTI.'!G COMPANY Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322
Dear Mr. Grier:
On October 13, 1977, in accordance with 10CFR50.55 (e) we reported verbally to Region 1 a deficiency in the design of the Safety Relief Valve (SRV) system.
On November 18, 1977, we submitted an interim 30-day report, and on February 23, 1978 and November 27, 1978, we submitted follow-up reports.
This letter serves as our final report on this deficiency.
In our February 23, 1978, letter to the NRC we pointed out two alternative corrective actions that we could take depending upon data that was currently being generated as part of the Mark II containment test program; the first being to verify that the plant could withstand "second pop" loads and the second being a modification to the SRV control system to preclude all SRV's actuating in the "second pop" mode.
At that time we informed you that we anticipated making a decision on an SRV load miti-gating device in May of 1978 and hoped to resolve the second pop deficiency a short time after that decision.
FINAL RESOLUTION In June of 1978 the design for the SRV discharge devices was changed from a ramshead device to a "T" quencher device of KWU 1689 156 800104o $OY FC 8935
October 24, 1979 Mr. Boyce Grier Page 2 design.
In both generic and Shoreham specific discussions with the NRC, we have established a conservative SRV load definition based on a bounding ramshead load.
In the process of develop-ing and verifying the conservatism of this now-agreed-upon load specification, German test data f' rom the Brunsbuttle and Karl-stein test programs was utilized to demonstrate that the actual "T" quencher loads are conservatively bounded by the ramshead load specification which has been utilized for the production design work on Shoreham.
The Karlstein tests utilized the exact "T" quencher configuration being employed at Shoreham.
The German test data which has been utilized in the design cri-t~eria verification referenced above was based on second and subsequent " pops" of SRV valves and the test cases chosen were the highest pressure amplitude traces experienced during the test, whether the highest pressure for a given test was noted in the second, third, or other subsequent " pop".
Therefore, the original second pop concern is now moot since the increased loads associated with any subsequent " pop" phenomena have in fact been included in the design consideration for Shoreham.
CORRECTIVE ACTION No corrective action is required since the second pop phenomena is covered by the current Mark II containment load specifications which have been agreed upon by both the Mark II lead plants and the NRC.
Very ruly yours, l
['
J.
P.
No arro Project Manager Shoreham Nuclear Power Station WJM:jm cc:
Mr. Victor Stello, Director Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr.
J. Higgins, Site NRC i689 157