ML20214G591

Discusses Summary of Second Question List Re PSAR Topics

ML20214G591
Person / Time
Site:	Columbia
Issue date:	04/14/1972
From:	Clark R US ATOMIC ENERGY COMMISSION (AEC)
To:	Boyd R US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-0129, CON-WNP-129 NUDOCS 8605220302
Download: ML20214G591 (3)

Text

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f E!O' :iC F ERGY COMMISSION

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t h ger.. :,:yd, Assi: tant Director for Boiling Water Reactors DRI r,:"fd ? "i EC "? 0'TSTIO:: 1,IST FCR !!ANFORD NO. 2, DOCUFT No. 50-397 )

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1;.e a e. r.: cues;ien lirt acdresses meet of the PSA!t tcpics not covered f i, : - :;re questir list and a few itcts from the first list whose an se. r

$,nc bee n reviewd. The only areas renainine te be reviewed ace cf.:1. an.aruace, conformance to ECCS interin criteria, and sone er:. i : n-3;.4 t ( m s like the fire water system and the instrunent air sy ne,

i The c,aostions in the second list are nainly routine in rature and are l

directed tow,rd obtaining information not provided in the PSAR except as not.d b.!10 :

1.

Questien 2.16 concerns the effect of the FFTF on !!anford ':o. 2 Plant Safety. The FFTF exclusion area includes the llanford No. 2 site.

e 2.

Question 4.35 requests that the P&lD's for the reactor coolant systen be improved (clarified).

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Question 4.40 request s preliminary drawine and design criteria for the recirculation systen control valve and pump discharge block valve interlocks.

4 Question 4.41 concerns itself with the inadequacy of the res;unses to question 4.1, 4.2, 4.3 and 4.4 in the first j

que uica list.

These cuestions requested information on I

frc.cture touchncsa. Rather than asking them to orovide additional ansvers to these four questions, we are now asking, WPPSS to conform to a recently revised /J'T Code Sectten III " Fracture Toughness Rules" (Code case 1514),

which at prescat is not nandatory.

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qucatden './.2

,cked WPPSS to provide us with a surveillance

.le,.t.dr;+:a1 schedule. Mone was given in answer to I

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Question 10.4 concerns itself with the adecuacy of the Standby Scrvice '?atcr Systen krerr.ency cooling water) to survive

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a. active ecmponent. The service water s este

.s a; it inta tro systenc, a standby scrvice water system (cr.crgency) and a service water system (non essential leads) in P S ??..'r e n:'.n a n t N o. 2.

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Question H-1 concerns the generic problem of the error band in the calculation of LOCA blowdown loads on the control rod guide i

tubes.

These : : pose the non-routinc areas of the second cuestion list.

No tanagement actica on any of these items is requested at this time.

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Robert A. Clark,' Chief N

BWR Branch No. 3 Division of Reactor Liccasing f

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. 52. lit el April 14, 1972 Distribution N c':ct F!1 DRL l'eadin LGRu3 Readinn; S.11. Hanaue r R. S. Ecyl R. C. DcYoung R. Tedesco Bht Branch Chiefs C. Lainas E. G. Case Compliance i

S. !!iner R. A. Clark N. D. ?!ason l

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