ML20234B281: Difference between revisions

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C ADVISORY COMMITTEE ON REAC'IOR SA UNITED     STATES Washington     25, D. C. A'IDMIC ENERGY COMM April 18,1963 Honorable Glenn T. Seaborg Chairman U. S. Atomic Energy Commission Washington 25, D. C.
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:==
==Subject:==
 
REPORT ON BODEGA BAY ATOMIC PARK -  
REPORT ON BODEGA BAY ATOMIC PARK - U
~
                                                                                                            ~


==Dear Dr. Seaborg:==
==Dear Dr. Seaborg:==
A At its forty-seventh meeting, April 11-13 Electric Company for approval                       c          on by theof      constru Pacific   Gas and tion' R Bodega Bay Atomic Park, on Bodega Head Comittee                                      , Sonoma County, California.on of Pacific    Gas had           the benefit and Electric     Company,of with discussions the     Gen representatives       of the The d                AEC Staff and their consultants.eral Electric Company, and the a preliminary form The                      at application a subcommittee     had a'lso been reviewed on March 20,1963, and in meetin on July 31, 1962 of  the tions,   theCommittee Committee made       viewed use of thetheerdo    site date. at an earli      Members cuments listed.In its dilibera-The site of the pmposed nuclear power u i are used for camping and fishing.
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
u ure n      picnicking, Francisco. Areas coast agric lta nea,rby of California s tudies.
, 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
The reactor site as a field stationu red               forbymarine the University   bi lAn ad the San tively  low.Andreas fault zone. proposed is about one thousand feet wo o est of
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.
'                                          The plant will incorporate engineered               eguards.
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.
safThe rela-         surrou boiling water type.The 1006 Mw(t) reactor plant proposed i the reactor sure,  and is conne  located   Pressure in a dry suppression well that i             confinement is to bs of the 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 at 35 psi i                  water All    piping pumps penetrations andthrouth the primary the  r mary system, dry watersuch ascleanup feed-mary             sy tth
of California as a field station for marine bi lAn ad u ure s tudies.
                  . isolation valves.                                         s em, are not to be confined.
The reactor site u red by the University the San Andreas fault zone. proposed is about one thousand feet wo o tively low.
trate the dry well wall and open into thTheesapplicant                              that pene-states tha e dry well or the nuclear steam 1
The plant will incorporate engineered safThe surro est of rela-boiling water type.The 1006 Mw(t) reactor plant proposed i eguards.
                                      $1217 3 PDR rwuw                                             1     l
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
$1217 1
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                                                            . Seaborg                                                             onora                                                  April 18,1963 supp CPe      nsideration should be given to the inclu inc tion valves in some of the primary system                     pipinonal P bac6 f a strainer before the main steam line i g and to-ei n matter from interfering with proper valve actionsola         .
. Seaborg onor April 18,1963 a
e      naideration should be given to providing the emergen rsystem f      pump.      with pump back-up beyond that provided                       ary-by the mmittee believes that the dry well and the suppression be designed and built to permit leak testing atpool                  d r theshould ction      installation     of all penetrations, andesign          that pressure design and con-
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
                              -    ign pressure.             permit periodic leak testing at the suppressio In the initial tests of the dry well, the leak I
P naideration should be given to providing the emergen system with pump back-up beyond that provided by the e
ould be determined as a function of theressure,                internal   so p rates
r pump.
                      -          can be extrapolated
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/
                                                'i with confidence..e results                       of subsequ essure p/       l }Ina the unlikely event of a r j
l }In the unlikely event of a r
ugtthis--u relied on to reduce       eactor  accident th the consequenc,es.e         emergency ventilation frequent testing of the ability of thsystemeshould                      to permit also be design units to meet their specified efficiency           evels.
' i essure eactor accident th a
le filtration and iodine remo The requirements that are imposed on pl an active seismic area have                     antbeen design conside because of location in referenced have      been connulted  documents           contain red by thethe on this question                     reconsnend applicant, a ions of seismologists who and the                  t that line.
ugtthis--u relied on to reduce the consequenc,es.e emergency ventilation j
fault  the reactor and turbine buildings     .
frequent testing of the ability of thsystem should also be design units to meet their specified efficiency le filtration and iodine remo e
Tentative exploration indicates the design criteria for the plant arThe Committee believes th hazards associated with earthquakes                           o nt is established, diorite  rock    below    shoul            . e adequate from the standpoint of this point.                                      Careful examination of the quartz Furthermre,d careful attention shouldthe be beComittee made given to suggests the duringthat,building durin          excavation g design, systems to operate properly during and s bability of emergency shocks, and to the stress effects                     that mito hviolent earth u sequent reactor ent          building geological            and the turbine buildin formatjlons.                    g t be introduced.because the isolation of th The need for earthquake-induced shutdow e primary system can be considered at a l nt and a er time.
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.
e                                                       J
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.
  .                                                                                                                      -__._______m
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                         1. "
Honorable Glenn T. Seaborg
j'         - 3 .- -
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April '18, ' 1963             '
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l observations will be. used'to establish.ents,                            .
April '18, ' 1963 l
e-atmos and as one of the bases for determinining the height'of the                                                     ack.'
observations will be. used'to establish. atmos e-and as one of the bases for determinining the height'of the off-ga ents, :
off-gai      '
i ack.'
The' applicant has submitted ' evidence to establishaethat the an   .
The' applicant has submitted ' evidence to establish that the an temperature changes in the ocean near the condenser coolant.
temperature changes in the ocean near the condenser coolant.
1.
point will not be great enough to..cause appreciable influenc. discharge 1.
ae point will not be great enough to..cause appreciable influenc. discharge
                                          . marine life. The expected release' of radioactive'                                           e on the'effluentlocal        by l coolant the          water applicant              haswill    made bearrangements.to at rates.well below       obtain the           10 CFR 20 environmental lim data.
. marine life. The expected release' of radioactive' effluent by e on the' local l
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coolant water will be at rates.well below the 10 CFR 20 li I
                  ~                      and'1and life in the neighborhood of the proposedorplant                                                  marineboth be n.
the applicant has made arrangements.to obtain environmental data and'1and life in the neighborhood of the proposed plant both be I
after reactor operation. . These measures seem adequate                                         .
or marine after reactor operation.. These measures seem adequate to i
a to i plant can be operated so as not to alter the local' ecology                                           e-or e caus j    .
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undesirable concentration of radioactivity in marine life.                                  .
plant can be operated so as not to alter the local' ecology or caus n.
i t                                                                                                                                                                                i The ACRS believes             s that, subject to the above conditions
a e
                                                                                                                                , the proposed Head with reasonable assurance that
undesirable concentration of radioactivity in marine life.
                                        ' hazard to the health and safety of the public.
e-i j
it can out undue a              be op          i
The ACRS believes that, subject to the above conditions i
            /
t Head with reasonable assurance that it can be op s
Sincerely yours,
, the proposed i
            .,                                                                                          /s/ D. B. Hall l
' hazard to the health and safety of the public.
D. B. Hall                                                               l' Chairman Referencea:                                                                                                                               >
a out undue Sincerely yours,
/
/s/ D. B. Hall l
D. B. Hall l
Chairman Referencea:
1.
1.
t!
Number 1, dated DecemberPreliminary Hazards Summary Report t!
Number 1, dated DecemberPreliminary           28, 1962.-                     Hazards c Park - Unit Summary Report                      :
28, 1962.-
: 2.                                                                                                                                     .;
c Park - Unit 2.
Licensing and Regulation Relative dated March h,.1963.                                                                           s to on ofConstruc pplication,                           1 l
Licensing and Regulation Relative to Construc s on of dated March h,.1963.
                                                                  ^
1 pplication, l
                                                                                                                                                                              .l se   o 1
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Latest revision as of 07:03, 3 December 2024

Submits Rept on Bodega Bay Atomic Park from ACRS 47th Meeting on 630411-13.Concludes That Proposed Reactor Can Be Designed & Built at Proposed Location on Bodega Head W/ Reasonable Assurance That Plant Can Be Operated Safely
ML20234B281
Person / Time
Site: 05000000, Bodega Bay
Issue date: 04/18/1963
From: Hall D
Advisory Committee on Reactor Safeguards
To: Seaborg G
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20234A767 List: ... further results
References
FOIA-85-665 NUDOCS 8709180344
Download: ML20234B281 (3)


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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 -

~

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

$1217 1

3 PDR rwuw l

1

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1r k,. t,

de ~

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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

1. "j'

- 3.- -

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.

1.

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

~

plant can be operated so as not to alter the local' ecology or caus n.

a e

undesirable concentration of radioactivity in marine life.

e-i j

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.

1 pplication, l

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