ML19199A373
| ML19199A373 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/15/1977 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19199A372 | List: |
| References | |
| NUDOCS 7905010656 | |
| Download: ML19199A373 (3) | |
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c' Distribution Docket File VAMoore m 151977 NRC PDR RHVollmer Local PCR "LErnst Ccchet No. 50-327 LWR #4 File WPGar.-i l l DBVassallo IE (3)
SAVarga ACRS (16)
FJWilliams RCeYoung
,,etrocolitan Ciisan Connanv Vic M
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'tr. 1. C. Arnold n0*h"' resident RHeineman p,.,
Dross JRBuchanan Readina, Pennsylvania
- 1960, JKnight T3Abernathy RTEdesco Gentlemen:
HDenton Si13 JECT:
Cnt'IP77 TO "ITInATE C1NSEQUE* ICES OF A SECnNDARY SYSTE't LI"E "U K In various recent meetings and telcohone conversations between renbers of your staff and ours, the design of ecuioment needed to miticate the consecuancas of a steae line break accidert on Three vile Island, Unit 2 has been discussed.
Durino the meetino of Fahruary 13, 1977, our position on this mattar was cla-ified, and is su rarized below.
For a snontanecus break anywhere in a nain steam or main feedwater (secondary syster) lina, accident consequences mst be mitigated only by sa fety grade ecuipment. However, for the assumed single failure in safety grade ecuiment, credit may be taken for non-safety grade enuinrcnt as a backup.
For those portions of the secondary systen where a break riqht be caused bv a seisnic event, accident consequences must be mitigated only by seisnic Categcry I comnonents, in accor:iance with General Design Criterion 2, after assuming single failure in any seisnic Category I conoonent.
Your present analyses of the secondary system line break accidents are not based on citigating the consecuences of those accidents by equierent as stated above.
In addition, they do not address breaks initiated by a seismic event.
For these reasons, the analyses are not acceptable.
If it can be shown that the unmiticated consecuences of any secondary systen line break accident on this plant are acceotable, consiriering the above positions and assumino a stuck rod and the availability or unavailability of of fsite power, whichever is worse, then the present system design would be considr: red acceptable.
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Failing this, miticatina ecuinment w st be upgraded, or new equipner.:
added, to confom with the above nosition and assunctions, and appropriate analyses nerformed to show acceptable consecuences.
In order to assure that licensinq actions croceed in a tirely manner, you should submit as soon as possible a procram outlining and schedulinq your planned actions on this matter.
If it accears that these actions cannot be coroleted before the expected fuel loadino date, we would give consideration to arguments justif ine short term clant oceration
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prior to comoletion of that procran.
Sincerely, Crip 7.It @.d by C 3. 'l: :-' :
O. B. Vassallo, Assistant Director of Licnt Water Reactors Division of Preje ct Manaaement
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Metropolitan Edison Comcany George F. Trowbric;e, Esc.
Shaw, Pittman, Pctts & Trowbridge 18C0 M Street, N. W.
Washington, D. C.
20035 Chauncey R. Keeford, Esc.
Chairman York Committee for a Safe Environner.
2535 Broac Street York, Pennsylvania 174C4 Mr. Richard W. Heward Project Manager GPU Service Corporation 250 Cherry Hill Road Parsicpany, New Jersey 0705 Mr. Thomas M. Crimmins, Jr.
Safety anc Licensing Manager GPU Service Corporation 250 Cherry Hill Road Parsippany, New Jersey 07054 fsU 4
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