ML19322C571
| ML19322C571 | |
| 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) |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001170897 | |
| Download: ML19322C571 (4) | |
Text
{{#Wiki_filter:' m ~ Aovsby COMMITTEE ON REACTOR t. EEGUARDS .... m:.;. UNITED STATES ' ATOMIC ENERGY COMr.MsioN W WAsHINGTori.D.C. 20545 August 20, 1970 s Honorable Glenn T. Seaborg Chairman U. S., Atomic Energy Cornission Washington, D. C. 20545 REPORT ON DAVIS-BESSE NUCIEAR FOUER STATION
Subject:
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Dear Dr. Seaborg:
\\ At its 124th meeting, August 13-15, 1970, the Advisory Committee on Reactor Saf*eguards completed its review of the application by the Toledo Edison Company and The Cleveland Electric Illuminating Company A for a permit to construct the Davis-B' ise Nucicar Power Station. 26, 1970, at the site Subcommittee met te review the proje.:t on May and in Toledo, Ohio, and on August 4, 1970, in Washington, D. C. During its review, the Corxnittee had the benefit of discussions with representatives and consultr.nr.s of the applicants, the Babcock and. Wilcox Company, the Bechtel Corporation, and the AEC Regulatory Staff. The Coraittee also had the benefit of the documents listed. The plant will be locatad on the southwestern shore of Lake Eric ap-The nearest population proximately 21 niles 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. 18,000, is The city of Frement, Ohio, with a 1960 population of about located 17 miles Jron the site. The minimum exclusion distance is 2400 feet and the low population 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 Eric about five miles cast of the site. This installation is used during i 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. l the site, At the Eric Industrial Park, about three to four miles cast ( Cadillac Gage Company is engaged in testing ordnance equipmen': firing j 120-mm. mortar shells with a maximum range of about two miles. All l firing from both locations is directed into restricted areas in Lake Eric. The applicants have proyided studies which demonstrate that none of the projectiles now being fired from these installations could 9 ))$ $$$$O = ? ! bq. ~ V I C I k 19'O n L6 1
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Y ~ I!onorable Glenn T. Seaborg ,2 - f.ucu ;t 20, 1970 penetrate the heavy reinforced concrete structures provided to protect The Coumittee reconmends, how-tJtc.cssential port ions of the plant. ever, that the applicants and the Regniatory Staff make suitable atrange-in t.hese activities so t. pat. their ment.s to be informed of any changes possibic ef fect on the safet.y of the plant may be evaluated. An area in f.ake Eric about ten miles north of the sit.c is used by air-in Michigan as an Anti-Submarine craf t f rom the Selfridge Ai.r Force Base Warf are practice area and by the Lockbourne Air Force Base at Colunbus, The Ohio, as an impact area for automatic weapon firing f rou aircraf t. applicants have been given assurance by officials of t.hc Department of Defense that military aircraf t enroute to or f rom t.his area will not he The Comatittee believ..s that routed closer than ten miles f rom the site. this arrangement reduces, t.o acceptably low levels, the prob aility of formal arrangements an aircraft striking the plant, but reconur. ends that be made to enabic the appilcants mid the Regulatory Staf f to maintain in continuing awareness of the operational patterns of military aircraft this area. The Davis-Besse plant wi.11 include a two-loop pressuri. zed water reactor similar to those for the 111dland units except that t.hc internal vent valves have been eliminated by changes in the elevations of the steam Since the proposed arrangement elim
- generators to obviate their need.
Inates the possibility of coolant flow bypass through an open vent valve, ,l the Davis-Besse reactor is designed for an initial core power 1cvel of g. l' 2633 w t as compared to 2452 P.Jt for the Midland units. l The applicants stated that it will be possible to anneal the pressure vessel if t.his should become necessa'ry at some time af ter operation is begun. ' A suitable preoperational vibration testing program should be caployed Also, attention should be given to the devel-for the primary system. opment and utilizat. ion of instruccentation for in-service raonitoring for excessive vibration or loose parts in the prinary system. ,I e The containment consists of a steci vessel surrounded by a reinforced i concrete shield buildiag, wi.th t.he annular space maintained at a slightly / I negative pressure and the att fro.m this space exhausted through filters. 3 -{ This design is similar to that for the Prairic Island, Kcwaunec, and !!utchinson Island plants, except that the free volume of the steci con-j is much greater, nearly thre.c million cubic fect., The Reguia-tainment 's tory Staf f should review the containment design pressure to assure that t ,) j an adequate margin of conservatism exirts. .-1 ~ '. -) y' G e h -p ~ ~ ~ ~ ~ ~ ' ~ 3 -. J. - -,.s _..... m 7 --._._....,.,,,.m. .-..y. m _.. g. --- ~. --,n 3 _.,,J
o o August 20,;1970 . h Hbnbrabic'Glenn T. Seaborg licants for the 3c-o f. Detailed criteria remain to be formulated by the:appwhich traverse the -: 4.- i sign of the penetrations for the hot process p pesIn view of the importance-M Ai ' annulus between the two containment barriers. LW "a' M i d by the Regulatory of these penetrat. ions, criteria 'should be rev eweStaif i t should arrange for an independent review of the actual design. development of 7 The CA::iittee has coamented in previous reports on the I tainment which l systems to control the buildup of hydrogen in the con l nt accident. The cright follow in the unlikely event of a loss-of-coo awith this problem, i applicants are studying various methods of cop nginclu The Connittee i recommends that the primary protection in this reg i within safe limits by means other than purging.The hydrogen control system and pro ~ should also be provided. h ld have redundancy for containment atmosphere mixing and sampling s ou ft feature. The Com-and instru;acntation suitabic for an engineered sa e y i f this matter. mittee wishes to be kept informed of the resolut on o i l evidence ob-The applicants have stated that they will provide addit onato assure that i tained by improved multi-node analytical techn ques temperatures cmergency core cooling system is capabic of limiting coreThey will also m / h s are required, to acceptably conservative values. p changes if further analysis demonstrates that such ; ange l. b', tisfac-This cutter should be resolved during construction in a manner sa j' tory to the Regulatory Staff. d f means Tbc Cormittee recommends that the applicants accelerate the stu y o i and of design to prevent common failure modes from negating scram act on, features to cuke tolerabic the consequences of f ailure ,~ 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 be resolved in a manner satisfactory to the Regulatory Staff during The Cocaittee wishes to be kept informed. struction. iliaa-The' Coccitece believes that consideration should be given to the ut failure of a fuel tion of instru.entation for prompt detection of grossConside m thermocouples as an aid to reliable operation and as an a eleocnt. i t 'of detecting behavior anomalics. N Y 4 s ? E s r 1 ~ V A I 4 l 9 7 7 7; ;;r;l;**
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G 3.. 20, 1970' C) August .-4a f.. aorabic Clenn T. Seaborg ) i treat-of liquid wastes follow ngwill be l ept h rge discharge r vidcel from applicants propose batch disc a of radionuclides in the with positive dilution being p oPlans for operation of waste <c Concentrations of 11 below 10 CFR 20 limitsveral equipment cooling water ::h as to nt. treams. made to reatment equipment should be sucd provisions should be adioactivity discharged, ar identified by ispersion in the lake. water reactors have been S reports. ACRS and cited in previous ACEof these items s l 9ther probicas related to large h the Regulatory Staff and t eThe Co=nittee believes that reso lution
- lant, resolved during con-equally to the Davis-itesse p above items can be h se items, the consideration is given to t e Tbc Cocnittee believes that the l
constructed with reasonab erisk to if due and that, i can be Davis-Lease Nuc1 car Power Stat onoperated without undue utruction assurance that it can be safety of the public. Sincerely yours, f ~ 4 3 Joseph M. IIendric a Chairman dated August 1,1969; License Letter froca Toledo Edison Coapany,f the Preliminary Safet Re ference s: Application, Volumes 1, 2 and 3 o 1. Report (PSAR) 16, 1970 Nolume4ofthePSAR,ldatedAprillication 2. Amendments 1 throug,h 9 to License App 3. D 4 4
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