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C ADVISORY COMMITTEE ON REAC'IOR SA UNITED STATES A'IDMIC ENERGY COMM Washington 25, D. C.
April 18,1963 Honorable Glenn T. Seaborg Chairman U. S. Atomic Energy Commission Washington 25, D. C.
Subject:
REPORT ON BODEGA BAY ATOMIC PARK -
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Dear Dr. Seaborg:
A At its forty-seventh meeting, April 11-13 Electric Company for approval of constru tion' R on by the Pacific Gas and Bodega Bay Atomic Park, on Bodega Head c
, Sonoma County, California.on of Comittee had the benefit of discussions Pacific Gas and Electric Company, the Gen with representatives of theThe AEC Staff and their consultants.eral Electric Company, and the a preliminary form at a subcommittee meetin The application had a'lso been reviewed d
on March of the Committee viewed the site at an earli 20,1963, and in on July 31, 1962 tions, the Committee made use of the do er date.
Members cuments listed.In its dilibera-The site of the pmposed nuclear power u i are used for camping and picnicking, agric lta coast n Francisco. Areas nea,rby fishing.
of California as a field station for marine bi lAn ad u ure s tudies.
The reactor site u red by the University the San Andreas fault zone. proposed is about one thousand feet wo o tively low.
The plant will incorporate engineered safThe surro est of rela-boiling water type.The 1006 Mw(t) reactor plant proposed i eguards.
Pressure suppression confinement is to bs of the the reactor located in a dry well that i sure, and is conne e used, with internal pressure.cted to a toroidal suppression chember rateds ra As proposed piping as well as soup other par,ts of the p i water pumps and the primary water cleanup sy tth at 35 psi r mary system, such as feed-mary All piping penetrations throuth the dry i
. isolation valves.
s em, are not to be confined.
trate the dry well wall and open into thThe applicant states tha es that pene-e dry well or the nuclear steam
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. Seaborg onor April 18,1963 a
nsideration should be given to the inclu supp CPe tion valves in some of the primary system pipin bac f a strainer before the main steam line i onal inc g and to-ei n matter from interfering with proper valve actionsola 6
P naideration should be given to providing the emergen system with pump back-up beyond that provided by the e
r pump.
f ary-mmittee believes that the dry well and the suppression be designed and built to permit leak testing at d pool r the installation of all penetrations, and that design ction should esign pressure ign pressure. permit periodic leak testing at the suppressio and con-I In the initial tests of the dry well, the leak ould be determined as a function of the internal p can be extrapolated with confidence..e results of subsequ rates ressure, so p/
l }In the unlikely event of a r
' i essure eactor accident th a
ugtthis--u relied on to reduce the consequenc,es.e emergency ventilation j
frequent testing of the ability of thsystem should also be design units to meet their specified efficiency le filtration and iodine remo e
to permit evels.
The requirements that are imposed on pl an active seismic area have been conside ant design because of location in referenced documents contain the reconsnend t red by the applicant, and the have been connulted on this question a ions of seismologists who that the reactor and turbine buildings Tentative exploration indicates fault line.
the design criteria for the plant arThe Committee believes t hazards associated with earthquakes o nt is established, e adequate from the standpoint of diorite rock below Careful examination of the quartz shoul this point.
Furthermre,d be made during building excavation the Comittee suggests that, durin careful attention should be given to the systems to operate properly during and s bability of emergency g design, shocks, and to the stress effects that mi h u sequent to violent earth reactor building and the turbine buildin g t be introduced.because the ent geological formatjlons.
The need for earthquake-induced shutdow isolation of th e primary system can be considered at a l tn and a er time.
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Honorable Glenn T. Seaborg
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April '18, ' 1963 l
observations will be. used'to establish. atmos e-and as one of the bases for determinining the height'of the off-ga ents, :
i ack.'
The' applicant has submitted ' evidence to establish that the an temperature changes in the ocean near the condenser coolant.
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ae point will not be great enough to..cause appreciable influenc. discharge
. marine life. The expected release' of radioactive' effluent by e on the' local l
coolant water will be at rates.well below the 10 CFR 20 li I
the applicant has made arrangements.to obtain environmental data and'1and life in the neighborhood of the proposed plant both be I
or marine after reactor operation.. These measures seem adequate to i
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plant can be operated so as not to alter the local' ecology or caus n.
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undesirable concentration of radioactivity in marine life.
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The ACRS believes that, subject to the above conditions i
t Head with reasonable assurance that it can be op s
, the proposed i
' hazard to the health and safety of the public.
a out undue Sincerely yours,
/
/s/ D. B. Hall l
D. B. Hall l
Chairman Referencea:
1.
Number 1, dated DecemberPreliminary Hazards Summary Report t!
28, 1962.-
c Park - Unit 2.
Licensing and Regulation Relative to Construc s on of dated March h,.1963.
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