ML19308B968
| ML19308B968 | |
| Person / Time | |
|---|---|
| Site: | Crane, Davis Besse  |
| Issue date: | 08/20/1970 |
| From: | Hendrie J Advisory Committee on Reactor Safeguards |
| To: | Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19308B954 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001170707 | |
| Download: ML19308B968 (4) | |
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ADVIL:Y COMMITTEE ON REACTOR E /EGUARDS UNITED GTATES ATOMIC EtERGY COMMISSION *.
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WAG!nNGTON. D.C. 20545 August 20, 1970 i
Honorable Clenn T. Seaborg Chairman U. S., Atomic Energy Commission.
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Washington, D. C.
20545 REPORT ON DAVIS-BESSE NUCLEAR POWER STATION
Subject:
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Dear Dr. Seaborg:
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I theAdvisoryCoNitteeon At its 124th meeting, August 13-15, 1970, Reactor Saf'eguards completed its review of the application by the l
Toledo Edison Company and The Cleveland Electric Illuminating Company A
for a permit to consttuct the Davis-Besse Nuclear Power Station.
26, 1970, at the site Subcommittee met to review the project on May and in Toledo, Ohio, and on August 4,1970, in Washington, D. C.
During its review, the Committee had the benefit of discussions with representatives and consultants of the applicants, the Babcock and.
Wilcox Company, the Ecchtel Corporation, and the AEC Regulatory Staf f, The Cowaittee also had the benefit of the documents listed.
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Q The plant will be located on the southwestern shore of Lake Erie ap-The nearest population proximately 21 miles cast of Toledo, Ohio.
centers are Toledo and Sandusky, Ohio, each about 20 miles from the j
site, with populations in 1960 of 379,000 and 32,000, respectively.
18,000, is The city of Fremor, Ohio, with a 1960 population of about located 17 miles from the site. The minimum exclusion distance is 2400 feet and the low population zone distance is two miles. Approx-i imately 3200 people live within five miles of the site.
Camp Perry, an Ohio National Guard facility, is located on Lake Eric
.2 bout five miles cast of the site. This installation is used during a short period each year for target practice with small arms and with i
e 40-mm. anti-aircraft s. hells armed only with a small destruct charge.
At the Eric Industrial Park, about three to four miles cast of the site, Cadillac Cage Company is engaged in testing ordnance equipment firing
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l All 120-un. mortar shells with a maximum range of ab^ ut two miles.
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firing from both locations is directed into restricted areas in Lake The applicants have proyided studies which demonstrate that none i
Eric.
of tbc projectiles now being fired from these installations could i
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penetrate the heavy reinforced concrete structures provided to protect Ol The Committee recor.nends, how-the-essential portions of the plant.
ever, that the applicants and the Regulatory Staf f make suitabic arrange-ments to be informed of any changes in these activities so that their r,ossible ef fect on the safety of the plant may be evaluated.
An area in Lake Eric about ten miles north of the site is used by air-craf t f rom the Self ridge Air Force Base in Michigan as an Anti-Submarine Warf are practice area and by the Lockbourne Air Force Base at Columbus, The Ohio, as an impact area for autonatic weapon firing from aircraft.
f applicants have been given assurance by of ficials of the Dep The Committee believes that routed closer than ten miles from the site.
this arrangement reduces, to acceptably low levels, the krobability of but recom.nends that formal arrangements an aircraf t striking the plant, be made to enable the applicants and the Regulatory Staf f to maintain continuing awareness of the operational patterns of military aircraft in this area.
The Davis-Besse plant will include a two-loop pressurized water reactor similar to those for the Midland units except tb-t the internal vent valves have been climinated by changes in the elevations of the steam Since the proposed arrangement elim-generators to obviate their need.
inates tbc possibility of coolant flow bypass through an open vent valve, the Davis-Besse reactor is designed for an initial core pov r level of y,'
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as compared to 2452 Kit for the Midland units.
2633 h.Jt l.
The applicants stated that it will be possible to anucal the pressure vessel if this should become necessa'ry at some time af ter operation is begun.
' A suitable preoperational vibration testing program should be employed Also, attention should be given to the devel-for the primary system.
opment and utilization of instrumentation for in-service monitoring for excessive vibration or loose parts in the primary system.
The containment consists of a steel vessel surrounded by a reinforced concrete shield building, with the annular space maintained at a slightly negative pressure and the air fro.m this space exhausted thr'ough filters.
i This design is similar to that for the Prairie Island, Kewaunce, and Hutchinson Island plants, except that the free volume of the steel con-tainment is much greater, nearly thre.e million cubic feet..The Regula-i l
tory Staf f should review the containment design pressure to assure that
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an adequate margin of conservatism exists.
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licants for the de-G Detailed criteria remain to be formulated by the.apps which traverse the i
s-ign of the penetrations for the hot process p peIn view of the importance annulus between the two containment barriers. i wed by the Regulatory ita' W ~
of these penetrations, criteria 'should be rev e licants should arrange Staif to assure adequate conservatism, and the app for an independent review of the actual design.
h development of The CtAnittee has cocaented in previous reports on t ein the containment w systems to control the bui.ldup of hydrogenf a loss-of-coolant accident.
The f coping with this problem, might follow in the unlikely event o applicants are studying various methods oincluding purgi The Counittee d should utilize a recc= ends that the primary protection in this regar tion within hydrogen control method which keeps the hydrogen concentraThe ca saic limits by means other than purging.The hydrogen control system and prov li.ng should have redundancy should also be provided.
for containment atmosphere mixing and samp d safety feature.
The Cou-and instru.acntation suitable for an engineereinformed of the resolution of this aittee wishes to be kept l evidence ob-The applicants have stated that they will provide additiona re that the tained by inproved culti-node analytical techniques to assulimiting core tempe caergency core cooling systcm is capable ofThey will also cake appropriate plant i
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to acceptably conservative values.if further analysis demonstrates that m
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r satisfac-This natter should be resolved during construction in a manneThe Co=
change s informed.
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tory to the Regulatory Staff.
h tudy of means The Comittee reco=nends that the applicants accelerate t e stion, and of desi to prevent comon f ailure modes from negating scram ac i
features to cuke tolerable the consequences of failure to anticipated transients.
ity of the prisaary would maintain flexibility with regard to relief capac This aatter should i
system and to a diverse means of reducing reacti.v ty.
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be resolved in a manner satisfactory to the Regulatory Staff dur ng co The Cocaittee wishes to be kept informed.
struction.
iliza-Ibe' Cocnittee believes that consideration should be given to the ut.
failure of a fuel tion of instrumentation for prompt detection of gressConsid dditional cethod thercoccuples as an aid to reliable operation and as an a clement.
of detecting behavior anomalics.
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treat-of liquid wastes followingwill be kept i harge in the discharge rovided from
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applicants propose batch d scConcentrations of radionuclides with positive dilution being pPlans for operation of waste i
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20 limits ter streams.such as to minimize the quan achieve rapid
'ell below 10 CFR everal equipment cooling wareatraent equipment should be made to should be gadioactivity discharged, and provisions have been identified by lispe.rsion in the lake.
RS re. ports.
related to large water reactorsACRS and cited in previous ACshould Other problems of these items the Regulatory Staff and theThe Cou:nittee believes that reso i
l t resolved during con-equally to the Davis-Besse p an.
h can be is given to these items, t e b
items The Coinnittee believes that the a oveif due considerat on l
constructed with reasonab erisk to i
i can be struction and that, Davis-Besse Nuclear Power Stat ond without undue assurance that it can be operate cafety of the public.
y Joseph M. Hendrie 9
Chairman i
e dated August 1,1969; LicensePrelimina
References:
Letter from Toledo Edison Company, Application, Vol h
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Report (PSAR) l 16, 1970 dolume 4 of the PSAR, l dated '.pril lication j.
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Amendments 1 through 9 to License App 3.
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