ML20234A769

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Summary of ACRS Subcommittee Meeting on 620731 Re Util Reactor.List of Attendees & Overall Schedule for Plant Encl
ML20234A769
Person / Time
Site: 05000000, Bodega Bay
Issue date: 08/15/1962
From: Boyd R, Wilcox R
US ATOMIC ENERGY COMMISSION (AEC)
To:
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20234A767 List: ... further results
References
FOIA-85-665 NUDOCS 8709180127
Download: ML20234A769 (4)


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To  :' Files- DATE: August 15, 1962-FROM : R. S. Boyd/ R. H. Wilcox - -

Research & Power Reactor Safety Branch -j

SUBJECT:

BODEGA BAY AT NIC PARK, UNIT NO. 1' l

'1 An ACRS Subcommittee meeting was held at H Street on July.31, 1962,- j to discuss Pacific Gas & Electric Company's Bodega' Bay reactor. It. '

is anticipated that an application for a construction permit will be l filed in September.

l The following people were in attendance:

J ACRS AEC STAFF 'PG&E l H. Kouts (Ch.) J. Newell C. Whelchel -

l L. Silverman R. Boyd F. Mantz i

' K. Osborn R. Wilcox W. Nutting <

R. Stratton R. Waterfield R. Lemon (GE) j C. Williams J. VanderHoven (WB) D. McDaniel - (GE)

J. Graham G. Hadlock (OGC) 1 The overall schedule for the Bodega plant, as outlined by PG&E, is -

........,,.. the following: -

(1) August 15, 1962 - Issuance of Permit by State of California (2) September 1, 1962.- Site Preparation and Meteorology Program  !

(3) ' March 1,1963 - Excavation begins (4) June 1, 1963 - First. concrete pouring (5) November 1, 1965 - Initial criticality 1 (6) May 1,1966 - Full power operation As the schedule implies, PG&E will require a construction permit be-fore June 1, 1963. It is their plan to file an application:for a-construction permit,.with a Hazards Summary Report, on September 4, 1962. A schedule tendered by Mr. Whelchel contemplated an October ACES' meeting, a ' November hearing, and issuance of a~ Construction Permit by January 15,1963. ..During ~ discussion ~ of the proposed sched-.  ;

ule we indicated that it was somewhat unrealistic, and that indeed  :

more time was evailable before the construction permit was needed.

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It appears that a hearing as-late as March,-1963, would not incon-vience PG&E.

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Files August 15, 1962 The proposed Bodega reactor will be a 325 Mw(e),1060 psig, forced circulation boiling water reactor with internal steam separation and vapor suppression containment.

The details of the meeting, presented below, are intended to provide the Staff and the ACRS with a cursory description of the site and the plant.

1 i

(1) PG&E will provide its own architect-engineering services ]

l (this was not the case with Humboldt Bay) . GE-APED will l provide the nuclear steam supply system, turbine-generator,  !

and will act as nuclear consultants. .j l (2) The plant location, about 50 miles North of San Francisco,  ;

is at Campbell Cove on Bodega Head. The nearest community, i Bodega Bay, has a population of about 350. PG&E now owns all of the land, about 225 acres, that they think necessary for the site. The University of California is planning a marine biology station on 400 acres north of the site, and the State is considering a state park north of the station.

(3) The land use is mostly involved with sports and commercial fishing. There are no residences within 1.5 miles of the site. There is 2700 ft exclusion distance to the North and 1300 ft SE to Durand Beach. The town of Bodega Bay is es-sentia11y 2 ' miles due East of the site. There are 500 people within a 5 mile radius, 2100 people within a 10 mile radius, and 115,000 people within a 25 mile radius.

(4) Meteorology for the site is sketchy. However, PG&E is planning a program designed to obtain temperature and wind data starting in September. These plans call for a 252 ft l mast with transducers at 7, 50 and 252 feet.

(5) The geology of the site was explained with the remark that Bodega Head is an " island of granite".

(6) Seismology will probably be one of the major site problems.

.The San Andreas Fault runs through the area with the western boundary estimated to be about 1500 ft East of the site.

PG&E has utilized consultants on this matter and presumably considerable information on seismic effects will be included in the hazards report.

(7) Oceanographic tests involving dyes and current drifts have been conducted at the site and will be continued. . In gen-eral the pre-operational monitoring program for Bodega is proposed to be similar to that conducted at Humboldt Bay.

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  1. Files August 15, 1962' l

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8 l (8)' Plant layout will involve grading from 90 ft MSL down to -l 25 ft HSL. The pressur uppression system will be im -

bedded in 20-30 ft of ro . The stack height has not yet i been determined. There is.no rail spur on the head; trans- j

, portation of equipment is expected'to be by barge.

(9) Fuel handling for Bodega will be un'derwater at all times.

The fuel elements will be 10= ft long. -

' (10)

Comments on the nuclear steam supply system are'the l following: ._ i J

a. thermal power - 1008 Hw(t) i
b. vessel designer - Combustion Eng.

~1ength 51.5 ft; 15 ft-I.D. ,

material: 302 plate - Section VIII of code '

thickness: 6 1/2" at core; clad 7/32" - 30455 6,4.

ave (above 1 acy neutrons) - 2.5 x 1018

c. steam flow - 4 x 106 lb/hr -l
d. recirculation flow - 43.5 x 10e6 lb/hr
e. internals - centrifugal steam separattors, in-core monitors, core spray and poison' system

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f. fuel - 2.7% enrichment,127 inches active length, UO2 pellets, 11 mil SS clad, Zr channels, 7 x 7 l matrix, 147" diameter core with 592 assemblies- l
g. rod drives and blades - GE drives,'l blade per four R fuel assemblies, total 145; B 4C blades; poison cur-tains in initial core (1% Boron Steel); no peripheral  ;

rods. d

h. Exposure: 15,000 Mwd /T. No critical experiments planped.
1. Power density, 33 Kw/1; avg. flux 103,000 Btu /(hr)(f 2t );

heat transfer area, 33,000 sq. ft.; Burnout' ratio at overpower,1.5 (overpower level not set); total void fraction,. 30%) exit quality, 9.5; moderator to fuel '

ratio, 2.7

j. reactivity balance - 28%; blades, 18%; curtains, 13%;

shutdown margin, 3%

k. It is planned that. this may some day be a 4 reactor site.

PG&E hopes to get 350 Mw(e) out of the turbine on the .;

  1. 1 plant ultimately. Present considerations are, however, i that this be a one reactor site.
1. Maximum credible accident: . with 28" pipes, a 6.4 f t2

/ area rupture. - 35 psig in dry well, tentative design:

50 psig; 29 psig in suppression pool; design, 35 psig (11) The Suppression Pool design has been based on Moss Landing tests subsequent to the Humboldt Bay tests. Additional tests.

are proposed to prove feasibility, of the omaission of baffle  ;

plates in the pool by testing with and without baffles.

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'l Files 4. ' August 15, 1962  :

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.(12) The accident analyses, as compared to those for Humboldt.

, Bay are:

1 a.. Cask drop accident - none (no cask) i

b. fuel handling - none (no cask)- d

, c.- control rod drop out - the rods are worth less than

.. the Humboldt Bay rods

d. The fuel loading accident is considered to form the. j basis for containment refueling building desi n.

f There would be expected to be some (0.5%)-' nobe gas. .;

release. '

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e. The reactor is designed such that loss of all pumping )

' power would not result in fuel damage.

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