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4 AUGS 1963 R. Lowenscein, Director Division of Licensing & Regulation l
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Director of Regulation
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a M. 7 PREFABR ION FOR BODEGA HEAD HEAR N
[ T gv 6.V bg I have on my desk a draft hazards analysis on the d
N; _7 Bodega Head casa dated June 21, 1963.
It uses up i
56 pages, q\\
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Without prejudice to any changes that may need to V'; (b p
v be made in this draft, I want you to have prepared Shd i
a separate summary statement which deals with the 3dT [9 merits of this case in the manner described in the p
licensing board procedures discussed with the licensing f
board panel at the recent meeting.
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What the Comunission wants from the boards is very I
clear on this point, but there is no hope that the licensing boards can, as a practical matter, carry out the C = insion's wishes unless the staff work puts them in an easy position to do so.
Preparation of a safety analysis along the lines described above should be begun immediately so that i
it will be ready in ample tima for the hearing.
For your guidance, I enclose a rough outline prepared by Dr. Beck of the basic elements to be considered in t' is case, and at least some,. or most, of the judgment n
positions we must support.
What we eventually decide to say on earthquakes can very logically follow the i
treatment of the items contained herein, i
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Enclosure:
As aboy Dr. C. K. Beck 4
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ISAFETY/ ISSUES IN BODEGA BAY REACTOR _
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1.
The Bodega Bay reactor proposed by PG6E is similar in all important design concepts to several other successfully operating reactors.
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2.
There'are no innovations, new principles or concepts of any substance j
in this application. For example, most of the systems follow the I
design concepts and principles already in successful use in other plants, including such systems as:
j the pressure vessel the primary system the core design
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the control system j
th'e instrumentation system the poison injection system l
energency cooling systems the auxiliary power system i
radiation monitoring waste treatment, storage, disposal.
3.
Matters on which some thought will be given, as the detailed design is finalized include:
a.
The thickness of fuel element cladding, now tentatively proposed as 11 mils. The applicant may decide later to use thicker cladding.
If the cladding is used, the occurrence of hilures before intended end of life, which would release fission products into the primary coolant, might force uneconomical shutdowns. There would be no substantial hazards, and the eventual Mc:r*f CbNAj w:
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wid de-^ A-en
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A economic balances to the operator.
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f l' SAFETY / ISSUES IN BODECA BAY REACTOR j, 3"
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, 1.
The Bodega Bay reactor proposed by FG&E is similar in all impottant I
design concepts to several other successfully operating reactors.
2.
There are no innovations, new principles or concepts of any substance d
in this application. For example, most of the systems follow the
~2 design concepts and principles already in successful use in other plants, including such systems as:
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the pressure vessel
[4 the primary system
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the core design the control system the instnanentation system the gioison injection system emergency cooling systems Ej the auxiliary power system radiation monitoring N
waste treatment, storage, disposal.
Bgj 3.
Matters on which some thought will be given as the detailed design M
is finalised include:
I5 The thickness of fuel element cladding, now tentatively proposed y
a.
as 11 mils. The applicant may decide later to use thicker cladding.
If the cladding is used, the occurrence of failures before intended and
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of life, which would release fission products into the primary k
coolant, might force uneconomical shutdowns. There would be no Qf Y:.$"
substantial hasards, and the eventual _ o r y c id f q 4' M j.
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n economic balances to the operator.
4.
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e-Design of control blades,now under study, may result df"p
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/ increased assurance that inadvertent blade drop-out would not occur.
1 The design de' tails on the over-all containment volumes and on c.
d individual penetrations of containment must be developed-to accommodate initial and subsequent periodic pressure and leak test measurements to en extent which has not previously been required. Th does not arise from ext azards in this plant Y-s-1
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~ hat procedures -
in lants have not adequate.
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The ntsaber,and location of isolation values in the primary system
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pipes leaving the suppression pool contaianent have not been 3
1 finally settled.
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e.
The applicant proposes to operate with a higher percentage of y
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stesa voltane in the core than has been cuttomary. Further analytical W
work and some limited and controlled initial operations of the F
plant will eventually determine whether or not this is feasible, d
4.
There are no systems on which research and development must be done to settle concepts, principles and general arrangements.h On some matters, further work and collection of informa& Y, be W
5.
tion must
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done in finalising design details [ig./bM M[W
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Where and to what extent internal baffles are%C. e in the a.
suppression pool will be determined by experiments now e
in progress at Hoss Landing.
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b.
An environmental monitoring program, including surveys of ocean v
-- currents, marine life, etc. as well as radioactivity ' levels,is being conducted to provide a reference level for determination I
l whether any changes occur later as a result 6f plant operation'.
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c.
Detailed meteorological observations are being' made to provide d
information needed in determining operating procedures and-License limitations.
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Accident calculations and site characteristics lead to determination of containment pressure and leakage specifications and to containment j
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O2 voltanes, as follows:
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"y The plant dry well and suppression pool are designed to these values f
respectively, and,,we believe, are adequate.
7.
The site for this reactor is an excellent one in all respects but one,
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namely, the proximity to the well-known St. Andreas earthquake, which P4 m
runs feet to the northeast of the proposed reactor location. The t.=
h population distribution is favorable, the isolation distance factors.
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are well within acceptable ranges, the meteorciogy, though not good for
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certain portions of the time, is as good or better than that in California
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characteristics already described, and generally known and successfully proven plant characteristics, is considered accept )able e on y real f:
due yet to be settled, either in plant location or in the extra and additional design s'afeguards on otherwise adequate plant systems, f
r is the proximity of the plant to the St. Andreas fault and the.
implicationsthishasfortheplant,Y, 77*g Gfuc%spm% w W~%puA4Q u~~
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