ML19220C032

Forwards Revised Accident Analysis Branch SER Suppl Input of Analysis of Steam Line Break Accident.Concludes Radiological Consequences Are Acceptable.W/O Encl

ML19220C032
Person / Time
Site:	Crane
Issue date:	01/18/1978
From:	Vollmer R Office of Nuclear Reactor Regulation
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML19220C033	List: ML19220C032
References
NUDOCS 7904280094
Download: ML19220C032 (2)

Text

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JAh i 8 578 Docket No. 50-320 PE 0RANDLM FOR: Domenic B. Vassallo. Assistant Director for Light Water Reactors, DPM FROM:

[*:hard H. Vollmer Assistant Director for Site Analysis. DSE

SUBJECT:

THREE MILE ISLAND Uf!IT NO. 2 SER SUPPLEMENT INPUT PLANT t4AME: Three Mile Island Unit No. 2 LICENSING STAGE: OL 00CKE1 NUMBER: 50-320 MILEf7NE fiUMBER: 27-3!

RESPCliSIBLE BRANCH: LWR No. 2 PP.0 JECT PANAGER:

H. Silver REQUESTED COMPLET'.0H DATE: January 16, 1978 REVIEW STATUS: AAB Review Corplete Attached is the revised Accident Analysis Branch SER Suppicment input of the analysis of a postulated steam line break accident for the Three Mile Island :tuclear Unit Mo. 2 facility.

We conclude that the radiological consequences of this accident are acceptable. It should be pointed out that our evaluation is based upon the assumption that the steam generator leak rate remains at I gpm even when the system bxcmes water-solid anout 20 minutes after the event and the differential pressure across the steam generator aporoaches 2500 psi.

The Mechanical Engineering Branch should be asked to c afirm this assucption.

8 OfKC6]EC Richaro H. Yolicer, Assistant Director fer Site Analysis Division of Site Safety and Euvinsrmental Analysis closu m SER Supplement Input Distribution:

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