ML19308B952
| ML19308B952 | |
| Person / Time | |
|---|---|
| Site: | Crane, Davis Besse  |
| Issue date: | 01/14/1970 |
| From: | Hendrie J Advisory Committee on Reactor Safeguards |
| To: | Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001170658 | |
| Download: ML19308B952 (4) | |
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AovibN coMMnTEE ON REACH 0R E.
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UNITED STATES ATOMIC ENEftGY COMMISSION W
WASHINGTON. D.C. 20545
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August 20, 1970 b
Honorable Glenn T. Seaborg Chairman U. S., Atomic Energy Commission Washington, D. C.
20545
Subject:
REPORT 0 DAVIS-BESSE NUCLEAR POWER STATION 3
Dear Dr. Seaborg:
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the Advisory ConNittee on 13-15, 1970, At its 124th meeting, August Reactor Safeguards cocnpleted.its review of the application by the Toledo Edison Company and The Cleveland Electric, Illuminating Company A
for a permit to construct the Davis-Besse Nuclear Power Station.
Subcommittee met to review the project on May 26, 1970, at the site and in Toledo, Ohio, and on August 4, 1970, in Washington, D. C.
During its review, the Cor.tnittee had the benefit of discussions with 3
representatives and consultants of the applicants, the Babcock and, Wilcox Company, the Bechtel Corporation, and the AEC Regulatory Staff.
The Committee also had the benefit of the documents listed.
l The plant will be located on the southwestern shore of Lake Erie ap-The nearest population proximately 21 miles cast of Toledo, Ohio.
j centers are Toledo and Sandusky, Ohio, each about 20 miles from the site, with populations in 1960 of 379,000 and 32,000, respectively.
The city of Fremont, Ohio, with a 1960 population of about 18,000, is located 17 miles from the site. The minimum exclusion distance is 2400 feet and the low pcpulation zone distance is two miles. Approx-imately 3200 people live within five miles of the site.
Camp Perry, an Ohio National Guard facility, is located on Lake Erie about five miles cast of the site. This installation is used during a short period each year for target practice with small arms and with 40-mm. anti-aircraf t shells armed only with a small destruct charge.
At the Eric Industrial Park, about three to four miles cast of the site, j
Cadillac Gage Company is engaged in testing ordnance equipment firing All g
120-mm. mortar shells with a maximum range of about tuo miles.
l firing from both locations is directed into restricted areas in Lake i
The applicants have proyided studies which demonstrate that none Eric.
of the' projectiles now being fired from these installations could i.
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U v .Honorabic.G1cun T. Seaborg. .2 - August 20, 1970 (<El penetrate the heavy reinforced concrete structures provided to protect The *ommittee recor.= ands, how-t< Qic.cssential. portions of the plant. ev'er, that the applicants and the Regulatory Staf f make suitable arrange-nents to be informed of auf changes in these activities so that their possibic 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 from the Self ridge Air Force Base in Michigan as an Anti-Submarine Warfare practice area and by the Lockbourne Air Force Base at Columbus, The Ohio, as an impact area for automatic weapon firing from aircraf t. applicants have been given assurance by officials of the Departaent of Defense that military aircraft enroute to or from this area will not be Tne Co=a' ttee believes that routed closer than ten miles f rom the site. this arrangement reduces, to acceptably low levels, the probability of but recommends that formal arrangements an aircraft striking the plant, be made to enabic the applicants and the Regulatory Staff to maintain continuing awareness of the operational patterns of military aircraf t in this area. The Davi -Besse plant will include a two-loop pressurized water reactor similar to those for the Midland units except that the internal vent valves have been climinated by changes in the elevations of the steam Since the proposed arrangement clim
- generators to obviate their need.
inates the possibility of coolant flow bypass through an open vent valve, the Davis-Besse reactor is designed for an initial core power icvel of c3 2633 Eit as compared to 2452 Kit for the Midland units. j, j, I The applicants stated that it will be possible to anneal the pressure vessel if this should become necessa?ry at some time af ter operation is begun. ' A suitabic 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 steci vessel surrounded by a reinforced concrete shield buildiag, with the annular space mainteined at a slightly negative pressure and the air fro.m this space exhausted through filters. This design is similar to that for the Prairie Island, Kewaunce, and Hutchinson Island plants, except that the free volume of the steel con-l is much greater, nearly three million cubic feet..The Regu a-talnment tory Staff should review the contatnment design pressure to assure that i an adequate margin of conservatism exists. t 4 ? 1, i /*, y,.,,.,. ...... x.. 7._ _. 7-y.. - ...w ..~.-_...m._,_ '!Jyfj)i g .Q ! "}
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, A'.S1fon'brable'Glenn T. Seaborg licants for the de ..of..:j Datailed criteria remain to be formulated by the:appi es which traverse the- - : o. r > sign of the penetrations for the hot process p pannulus b I view of the importance-A' ad iW V I' i of these penetrations, criteria 'should be rev eStaff to as t should arrange for an independent review of the actual design. h development of The Cduittec has commanted in previous reports on t eontainment which h systems to control the buildup of hydrogen in t e c f lant accident. The might follow in the unlikely event of a loss-o -coowith this problem, i applicants are studying various methods of cop ng The Committee biners. including purging and the use of catalytic recomhis regard should utilize a recommends that the primary protection in t i ithin hydrogen control method which keeps the hydrogen concentra safe limii s by means other than purging.The hydrogen control system and prov should also be provided. h ld have reduudancy for containment atnosphere mixing and sampling s oua ft feature. The com-i f this matter. mittee wishes to be kept informed of the resolut on o l evidence ob-The applicants have stated that they will provide additiona to assure that the i tained by improved multi-node analytical techn queslimiting core temperatures emergency core cooling system is capabic ofThey will also make appropriate pla are required. to acceptably conservative values. h j changes if further analysis demonstrates that suc 3 '. r satisfac-l. l tory to the Regulatory Staff. d of means The Co::mictee recomends that the applicants accelerate the stu ytion to prevent common failure modes from negating scram ac i features to make tolerable the consequences of failure t anticipated transients. f the primary would maintain ficxibility with regard to relief capacity oThis matter should system and to a diverse means of reducing reactivity. I during con-be resolved in a manner satisfactory to the Regulatory Staff The Committee wishes to be kept informed. struction. the utiliza-The' Committee believes that consideration should be given tofailure of a f tion of instrumentation for prompt detection of grossConsid thermocouples as an aid to reliable operation and as an a eleoent. of detecting behavior anomalies. .{ e 9 -f k ~ 's f .m _ _ '. ^{ _..m c, .- ^ a ~
r, \\ \\ .. /,.., r.a O August 20, 1970'
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I 4' . c., i sorable Glenn T. Seaborg I i treat-b of liquid wastes follow ngwill be kept 7 h rge in the dischargeing provided from applicants propose batch disc aConcentrations of radionucl of waste { e f j veral equipment cooling water sh as to minimize the quantities o -11 below 10 CFR 20 limits ut. achieve rapid treams. made to visions should be reatment equipment should be sucadioactivity discharged, a identified by ispersion in the lake. water reactors have been RS reports. ACRS and cited in previous ACof these items sho l related to large e @ther problems the Regulatory Staff and tbcThe Committee believes that reso i i lant. resolved during con-equally to the Davis-Besse p above items n to these items, the can be i ble The Comittee believes that theif due consideration is g ve constructed with reasonarisk to the h and that, i can be Davis-Besse Nucicar Power Stat ont d without undue struction assurance that it can be opera e safety of the public. Sincerely yours,
- seph M. IIendrie Jo Chairman
\\ dated August 1,1969; License Letter from Toledo Edison Company,f the Preliminary Safe
References:
Application, Volumes 1, 2 and 3 o 1. Report (PSAR) 16, 1970 i Yolume4ofthePSAR,ldatedAprillication 2. Amendments 1 through 9 to License App 3. 1 l
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