ML19308C805
| ML19308C805 | |
| Person / Time | |
|---|---|
| Site: | Crane, Saint Lucie  |
| Issue date: | 03/12/1970 |
| From: | Hendrie J Advisory Committee on Reactor Safeguards |
| To: | Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19308C802 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8002070539 | |
| Download: ML19308C805 (4) | |
Text
{{#Wiki_filter:- -/. . '.. :, w..u. . w,im$s "jfl se. ADVISORY COMMITTFE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION 8 WASHINGTON. D.C. 20545 k March 12, 1970 ~ 1-Honorable Glenn T. Seaborg Chairman ' -] U. S. Atomic Energy Commission
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Subject:
REPORT ON HUTCHINSON ISIAND P.IANT UNIT NO.1 L:
Dear Dr. Seaborg:
At its 119th meeting, March 5-7, 1970, the Advisory Committee on Reactor [), Safeguards completed its review of the application of the Florida Power and Light. Company for authorization to construct a" nuclear power plant ~.' - ! at its Hutchinson Island site in St. Lucie County, Florida. A Subcommittec y .. Q visited the site on January 5, 1970; a-second Subcommittee meeting was held in Chicago on February 21, 1970. During its review, the Committee had the benefit of discussions with the applicant, Combustion Engineering, f". M. (6-The Committee also had the benefit of the documents listed. Inc., Ebasco Services, Inc., the AEC Regulatory Staf f, and their consult- ..f ants. 1.\\! The Hutchinson Island Plant Unit No. I will be located on a tract of land g.," of approximately 1100 acres, about half way between Fort Pierce and'Stuart b' on the east coast of Florida. About 1000 people live within a five mile ra'dius of the site. 'The nearest population center is Fort Pierce (popula-t,. tion about 34,000), which is eight miles away. cr f,j The plant site on Hutchinson Island is underlain by sand to a depth of several hundre'd feet, To provide satisfactory bearing and settlement ,g M characteristics and resistance to liquefaction, the first sixt'y feet of loose send is being removed and the excavation refilled to foundation depth wi.th granular material compacted to a relative density of 85 per-b,. cent. .Qj9' Tl[eproposedpressurizedwaterreactorhasadesignpowerlevelof 4-%. 2440 nJ(t) and is similar to the previously reviewed Maine Yankee and j% Calvert Cliffs reactors (ACRS reports dated July 19, 1968'and March 13,
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1969). The containment system consists of a steel' containment vessel enclosed within a reinforced concrete building, with the annular space f maintained at a slight negative pressure and exhausted through filters. J.f,$ ,,y 'Ihe applicant has stated that the containment and. other structures and ig systems important to safety will be' designed to meet the same tornado rs
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' s. :.,h h.) t W':. Mar 12, 1970 2-P Honorable Gleni T. Seaborg ~ 3 ...t design criteria as have been used for other recently reviewed plants, and that p,rotection of vital components will be provided against the probable j maximum hurricanc-induced flood and runup level as estimated by th,e Coastal l' 7 93'. Engineering Research Center. f.h/ The applicant stated that a dynamic seismic analysis will be performed on Several other matters related t'o seismic design, 4.f. the primary system. . used in the design of piping and equipment, including the spectra to 'g and the design procedura, to.be used for various types of Class 1 piping, ,y should be r'esolved in' a manner satisfactory to-the Regulatory Staf f. j s. The applicant stated that the primary system will.be designed so that v.: U$ annealing of the pressure vessel will be practical at a temperature of a at Icast 650 F.
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Pump sec1 and other leakage from emergency core cooling (ECCS) ' equipment 3 '3 of .s.?i and lines outside the containment may ' lead to undesirable reicases The i.} radioactivity in the unlikely event of a loss-of-coolant accident. Committee recommends that the atmosphere around the ECCS lines and pumps j outside the containment be vented through a charcoal filter system.
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.a / Further study iu required with regard to potential releases of radio-activity in the unlikely event of gross damage to an irradiated subassembly J '.. during fuct handling and the,possible need for a charcoal filtration sys-tem in the fuel handling building. This matter should be resolved in a manner satisfactory,to the Regulatory Staff. n All hot process lines penetrating the containment annulus will be designed ( in with a guard pipe to direct steam flow back to the primary containment Y; the unlikely event of a rupture of the process pipe in the annulps region. In view of the importance of the guard. pipes, the applicant will arrange ,s )$
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9A The applicant stated that he will install a concrete wall in the contain- , q. ment penetrat' ion room to separate the~ cables and penetrations for redun- , 33 ..U dant devices essential to safety. The Conunittee believes that the separation "?? of redundant elements in the penetration room and elsewhere requires further -4 study, as to both criteria and design details. -T; D A suitable preoperational vibration testing program should be employed for A the primary system. Also, attention should be given to the development jf.f and utilization of instrumentation for in-service monitoring for excessive y ck vibration or loose parts in the primary system. w:. 1% o, ** .;5 /.M (5,3 G.li. 5' h y. 'h,, I d T '[Wl y \\li(U h; l
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~ '} j~ . c&%,n .~ Mar 12, 1970 o f -( - lionorable Glenn T. Seaborg as When details of the planned loads and ratings of the emergency diesel generators become available, the Regulatory Staff should assure itself 4 ') i i that adequacy of design conservatism.is realized and that suf fic ent (S testing and experience will be available prior to plant startup to prove 'l the reliability of the emergency power system. in active participation by app 11 The Committee reiterates its interest cants,in overall quality assurance programs to better assure the con-
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In the quality assurance program of the V; participation by the applicant 3 W Hutchinson Island Plant would be. desirable. 2.; Informat(on on a number of items, identified in previous reports of the .9 Committee, is.to be provided by the applicant to the Regulatory Staff 'y during construction. These include:
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A study of'rcans of preventing common failure modes from ,= l a) negating scram action and of design features to make toler-7 able the consequences of failure to scram during anticipated k'.Y t transients. 7y Review of development of systems to contro,1 the buildup of 7).;i tj' b) including an appropriately hydrogen in the containment,conservativ'e estimate of possible hydrogen -j instrumentation to monitor the course - of events in the un-7 j. likely event of a loss-of-coolant' accident. {* Other problems.related to large water reactors have been identified by the Regulatory Staff and the ACRS and cited in previous ACRS reports. i The Committee feels that resolution of these items should apply equally ,: Y to the llutchinson Island Plant. b..' The Consnittee b'elieves that the above itiems can be resolved during con-cr. if due consideration is given to these items, the U.YG struction and that, nuclear plant proposed for the llutchinson Island site can be constructed. (N; it can be operated without undue risk to
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{~3? with reasonable assurance that .1 M the health and safety of the public. f,. op Sincerely yours, }Ak c aW /s/ 4 m.. '.!;,Y;. A] :~.Y. Joseph M. llendrie g. Chairaan M'M' q 9l; ~ References attached. y {f $ w'. Q.;u'l
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}g -References - Hutchinson Island.: Plant UnitrNo.'1' y._ u , d.. 'l. ' Hutchinson. Island - Plant -Unit No.1,. Preliminary Sa fety Analysis Report ', Volumes:1 - 3.-
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4.-- M. 2. Florida Power &' Light Company letter, dated April 1,1969._ IM, + Dis"; ~ 3 1 Amendments 1 - 8 to License Application. i,..- .h. :st. p... a
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