ML19224A790

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Forwards Preliminary Review of Section 6.2 of Fsar. Section Not Adequately Complete to Allow Initiation of Detailed Technical Review
ML19224A790
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/25/1974
From: Hendrie J
US ATOMIC ENERGY COMMISSION (AEC)
To: Tedesco R
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7905300325
Download: ML19224A790 (2)


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Docket No. 50-320 Voss A. Moore, Assistant Director for Light Water Reactors. Group 2, L PRELIMINARY RIVIEW OF THREE MILE ISLA'iD NUCLEAR STATION, UNIT 2 Plant Name: Three Mile Island Nuclear Station, Unit 2 Docket No.:

50-320 Licensing Stage:

OL NSSS Supplier:

Babcock & Wilcox architect Engineer:

Burns & Roe Contain: ?nt Type:

Dry Responsibia Branch & Project Managcc LWR 2-2; B. Washburn Requested Completion Date: March 5, 1974 Applicant's Response Date:

N/A Review Status:

Prelf=inary Review Complete As requestod by your =enorandum dated February 15, 1974, the Contain=ent Syste=s Branch has perfor=ed a prelir.inary review of Section 6.2 of the FSAR for :he Three Mile Is12nd Nuclear Station, Unit 2.

Based on this review we have deter =ined that Section 6.2 is net adem, *al"

- - le*a to allow t% i iM *f on <-f a detailed technical review; however, ve reluctant?y indicate that.in a leneral and not overly incressi"a -'~~. &e noo ncan t -

1appare.itly nas responara to tha 4---

-'._r._.__..m -c f " a e * ' a d er_d for=- t guin.

Wa h t -a-P -a *ba need for a re"ision to the mide Thus a lack of res(ponse to these needs certainly =ust not 3

we dso note that our information reeds are not even if one were to agree that in a strict sense, the applicant responded to the guide contents.

Needless to say we will start so=e kind of a review effort; however, it can only be a =inimal effort until we get sufficient responses to the enclosed infor=ation request.

These specific deficiencies'have been identified and ite=ized in the en-closure, and are su m rized below:

s 1.

The analytical =odel, assu=ptions, and justification regarding the sources and a=ounts of energy that =ight be released into the contain=ent during reflood and post-reflood phases of the LOCA.

2.

The description of the =odel and computer ccdes use<' to predict contain=ent subco=part=ent pressure response analysis.

3.

The design pressures for contain=ent subco:part=ents.

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