ML20239A665

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Summary of 620817 Meeting W/Util & ACRS to Discuss Bodega Bay Reactor Containment Pressure Suppression Test Program. List of Attendees Encl
ML20239A665
Person / Time
Site: 05000000, Bodega Bay
Issue date: 08/29/1962
From: Knuth D
US ATOMIC ENERGY COMMISSION (AEC)
To:
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20234A767 List: ... further results
References
FOIA-85-665 NUDOCS 8709180077
Download: ML20239A665 (2)


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.p vf1NITID STATES GOVERNMENT'. 1 Memorandum; -

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TO.  :' Files. _.

DATE: ' August 29, 1962 ,

THRU) Robert H V

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Research & Power, Reactor Safety Branch -

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SUBJECT:

HEETING 'TO' DISUCSS THE BODEGA BAY REACTOR CONTAINMENT PRESSURE -

SUPPRESSION TEST PROGRAM- -

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On August 17,-1962, a meeting was held with representatives of

.j Pacific Gas and . Electric Company, Advisory , Committee on Reactor ..

Safeguards, Division of Reactor Development-AEC and Division of ! ]

Licensing and Regulation-AEC. - The purpose of the meeting was. to :

discuss some of the results that were obtained from tests per- 'q formed in the pressure suppression test . facility and to comment-on the proposed test. program.' Those in attendance at'the meeting 1 included: ',

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.C. P. Ashworth

.PG&E- ~P. Sybulskis) - DRD-AEC 1 D.'B. Barton - PG&E' ;R. R.' Newton" . - DRD-AEC ' )

2 , C. C. Welchel - PG65 S. ' A. Szawlewicz - DRD-AEC . ,

R.'Fraley'. - ACRS 'A. B. Holt.. -. DIlnR-AEC j H. J. C. Kouts - ACRS- 'D. F. Knuth - DL&R-AEC l L. Silverman1 -~ACRS J. F. Newell' ' - DI&R-AEC 1

'R. H. Wilcox ' - DI/nR-AEC i The Bodega Bay plant design utilizes pressure suppression'on the-containment vessel;:the design is similar to that used for Humboldt Bay. The major differences between the'two designs are: ,

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1. The vent pipes are larger ~in the Bodega Bay' design (24" diameter vice 14" diameter)..
2. The energy input rate to the pool per unit water volume is about 2.4 times higher for the: Bodega Bay design (MCDA condition).

L 3. The geometry is different.

1 Because of the above differences,a pressure suppression test' faci- '

lity was constructed and' tests are being performed to confirm the ,

design' adequacy, 1 i

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, Files- - 2'- August 29,,1962 The' initial series of' tests were performed with one vent pipe.-

l The. design-of the containment vessel envisions the use of 112 vent pipes, so for purposes of thies test the reactor volume,: dry well volume and suppression chamber were sized'1/112 of.the con-

[ , templated Bodega Bay design volumes. :The tests were conducted by.

. rupturing two rupture discs which were placed in~ series. .The size'of the simulated failure was established with an orifice

, . located in the discharge flange. The orifice size (3.24", diameter) corresponding to the McQA break of a 28".' diameter.' pipe was used'

. most frequently in the tests.

The pressures' measured in the dry well and suppression chamber agreed well with the predicted _ calculated values. The maximum pressures! observed corresponding to the MCOA were 29 psig for the suppression chamber and 38 psig for the dry wcil. The~ pressures chosen for plant design purposes are 35 and 50 psig, respectively.

The tests indicate that vapor supprcasion with s' single vent pipe handling 1/112 of the steam' flow envisioned.for the' Bodega Bay.

plant can be handled within the' designed pressure ratings' of the equipment.

Further Tests The Pacific Gas and Electric. Company proposes'to modify the test-ing facility to test a more complete mock-up of the plant design'.;

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In thane tests the interaction between vent pipes, and hence the; need for baffles will be ascertained.

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, cc: J. F. Newell

A. B. Holt

! R. H. Wilcox a

.R. S. Boyd D. F. Knuth I

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