ML20154P482

Abstracts of Comments Submitted in Response to Petition for Rulemaking PRM 50-44

ML20154P482
Person / Time
Issue date:	09/16/1987
From:	NRC
To:
References
FRN-51FR31341, RULE-PRM-50-44 NUDOCS 8806030351
Download: ML20154P482 (36)

Text

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PRM 50-44 J l 1 1 UNIVERSmES MW W S, B, ABSTRACT COMMENTS o o Univerney of 2AUS7 No X U of F proposes to show tiat petitioned asser160n that Wigrier U of F commeras are wet stahd and provide =Maanalinput to consador us evalue-Florido energy in grapNie moderated Argonaut seactors represents a Sre ang tw Argonaut reactors. An explanation of te varianons at tw calculanons of (U of F) hazard is groundiens and should be dismissed. U of F addressee saored energy in tw UCLA Argonaut roecer is provuk.d. TNs and U of F's pows that tw BEp0 Equrvaient Flus and tw appropriate factor of 3.41 to to pettoner's chwvalue of stored energy (30 cal /g) d totapy rele===N= indicato she proper last neutron exposure as a luncion of fiermal =maheacacy wotAd not be a signacars temperatse rwe h tw grapNeo (-15(P C) notaron Buonce. U of F also analyzes tw NUREGm2079 should be connedored in tie Staffs evaluanon. calculation of stored energy for en Argonaut reecer Applyvig appropriate correction factors to the S ceFg stored energy value in NUREG/CR 2079(corrects for opereeing history and to BEPO equivalent Sun) to obtain a corrected value of 29.9 caug in good agreement wwi UCLA data at 33.5 caug mino explains maximtsn, trunimum and volume averaged stored energy values. Clase tie de aepancy beiween poemoners animum value for UCLA Argonaut of 30 caLgm witiIhe ent seured value of 19.2 caugrn. U of F analyew of tw diserhaan of stored energy in Argonaut modersior graphine needs tem to cor-* t tut even though tw original analyeas wee bened on asetsnpelons sist only asow orders of magnseLde accuracy, te values are appropriate for iaustratri0 4 that the Wigner Eftect is not a renovant inaue. The corrected cal-culatons and measured values show Wiet peak and average values of Wigner energy neorage are estemely low and are in-sulecient N re==aad to heat tw paphies by more tien an innig-s nincent amount. U of F doecnboo tie enemimum temperatres achievable by release of stored energy and Ends tiet a stored-energy release curveis umelutindetenruning ani9perboundaryof tie Annivalue lor paphite temperamnes adj=rt to anneeEng and report Wie 108-lowingr 150 caug 400 MWD /AT AT30*C - L OF36(fCg a n, <1000 MWD /AT AT30*C - L OF46(fCJ "*-* C Also report tint conenued heating does not teetAt in sponseneous terrporatne increases. U of F inspection of curve for 100 carg sucomean a semperanne rise ofless than 150* C for the petelone a c.an a. sad 39 cang lor UCLA graphite: comments lhet although CBG grossly Page 7 N

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,m 7 ;g .x PRM' z .5044 E !"o ag g INDUSTRY aM E So 2io ABSTRACT COMMENTS Gas Cooled 11/3/e6 Yes Requests extensson of ccmment period. None Reactor Assoc. 90d GCR OOW Crwnical 11/3/86 Yes Gequets extension of cerrment period. None s U.S A 90d GATectinologies 11/3!86 Yes Reque ses extension of comment period.' Norm i i Putsc Sonnce 11/3/86 Yes Recpssts eum of ent period.- h Company of 90d Colorado Page1 U

.PRM z =Q 50-44 = $ d ~~ ta &S 2 lNDUSTRY. n li' So ABSTRACT COMMENTS o Weslinghot:sa 110/S6 X Owr:s and operales a 10KW poottype training reacw. Reactor Wesbnghotme's assessment of tw problem and twir recommended approach = Electne rarely operates above 100W. Average power since core mori5ed certainly seasonable However,it probably resde from 1heer oorem that the Corporation to include yaptete toRector has been 19W.

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• proposed by CBG wodd not be warranted for tw ? n.g+==

Comments that penson is impulsive, emotionaNy based, and NTR. N BNLis able to pacvide a secommended standard c4,detonal trwehod for j founded on the Chemobyl arewlant which is signiAcantly dNerent spred onesgy, the *.systeme$c approecit

• twy recommend shodd be swintert from research reactors. Chernobyl arc = tant was the result of as a possible option. Unicatunately tw details of their stored energy calcdation interrelated human factors and doelgn weaknesses, are not provided.

Believes possibibly of graphite Ere in a US reactor shodd be assessed, however, wants assessment to be corrpleted in a : logical, systemanc manner Weslinghouse suggests the fotow-ing systematic approach- )

1. Each Econsee wodd perform a deta" -1 analyses is quan:i:a-alvely deterrrane to stored energy in ww 5censeek crophite.

2. From these calculailons the licensee would determino the probability of occurrence of a graphile fire.

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3. All Econeses would submit twee analyses 42 the NRC for rcview.

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4. If the ts:al abred energy h to graphite or to probability of a grapN:o Are oa:urring exceeds some predetermined value.

tw,Cw licensees should be required to verify his existing - g i g svacuston pians would be suitable for response to a t vuee ne.mergency o, iomwinic and aue-t oew s,e. QtLq end evacuation plans and FSAR revwiort Werdrs h.s providse proErranary assessment of their reactor corWh,; C,ct the reactor wi:hout water is subcnecal and also I j because ci bw powcr operation contains very smal quenetes of L j Ession produe:s. Analysis of graphies reRector,assummg Aunt at { reRector samc ss Eux !n to core, case.a.a== 0.0006 cal /gm of stored energy at teSectos casomblies. This saored energy,it released, would irmu3 Draphies temperan;re by 1*F. Maximum suoi plane anmperahao for rnarinum credible accident is no greater shar* 320*F. Co. elude that evenif resector graphite were { at ternperature of fuel plais that :he oxidation of graphits b negligbie at 321*F. i Paga 2 U.

PRM z z Q Q $0-44 W M8 '8 '8 INDUSTRY 5W QW So Bo ABSTRACT COMMENTS Gas-Cooled 2/Ml7 No X GCRA represents a number of US unh:ies interested in gas-cooled Similar in content to the commonas recewed from GA Technobgias comparing Reactor reactor devebpment and commerciatza6on. Comments apply to Chernobyl reactor to the commcacial HTGR. Associates tw pension only as it relates to corrsnercial gas-cooled reactor information is selevant to FSV and shotAf be imetored into tw NRC 69.11 raSpor:es (GCRA) designs. to petimon requests regarding Fort St Vraitt Bases sor pontion: The generic HTGR concerns should be considered in the ongoing safety eyalua-1 - Graphite 6res should be considered as credible events by the NRC as a result of the reported graphite fire which oa:urred at Chernobyl - Stored energy e::ects have been underestimated as shown by new data The credibility of graphite fires is addossed stanng that the CBG basis fails e recognize the requirements for a graphite Sre and Ihe signi6 candy different probabiitties of events, dependent on reactor desigrt hat could fait design rneasures taken to avoid such Eros. Commercial gas-cooled reactor designs operate at temperatures Ngh enough to permit rapid oxidation, but use helium coolant which is inert and excludes air / oxygen arom contact with me graphite. The inert coolant le contained by a high-integrity pres-i sure vessel Chernobyl reactor had high temperature graphile j protected by a He and N mixture cover gas contained only by a bpressure hermencaay sealed vault. Explains that sie Chernobyl accident was rW by one or more rapid power excursions due to the inherendy posinve foodback kom he void coef6cient of he water coolant Rapid heating of me water in the seactor coolant channels led to an explosive volumel-ric expansion of he water m steam resulting in gross failure of tw reactor vault osowing air access to bu grepNeo moderator. It is argued that Chemobyl accident has no impact on the assess-ment of me credbibty of a similar event occurring in lhe commer-ciel gaseoled graphite moderated seactors. Concludes that designs for msnmercial gas-cooled graphite mod-erated reactors operate at temperatures well above the tempera-ese at which any sigraficant stored energy occurs. Recommends petinon be denied to the extent it applies to com-rnercial gas-cooled grapiute rnoderated reactors. I j Page3 -E

PRM z z $2 9 $ g$ fp 50-44 p r WE 2 I"8 8 ag 2 INDUSTRY $W W So Bo ABSTRACT COMMENTS Putse Service U57 No X Summarizes petsuon requests and their bases. Addresses cred-PSC s identication of design dfierences between FSV and Chemobyl should be Company of tulity of graphne fires. Citos failtre of CBG b die the causatvo induded in sospense to pontion. Stsnmary of NRC's evaluanons and cweh==vis Colorado mechanism or the significant dflerences in reactor 1esien of PSC s autettal on the hypothe6 cal oxygen ingress event should also be stened. between the Chemobyl plant and Fort St Vrain (rSV) plant PSCs====== ment of stored energy should be reported. IdentEen causaive mechanisms at Chemobyl. . Power surge due to large reactivity insordon . Femek from positive void coeffident . Operadon of reactor outside its design basis limits PSC has ad*essed various reactor accidents resulung ki gregh-its oxidation in CP & OL proceedngs. Currendy, fils information may be found in updated FSV-FSAR None of tie postelated so. cidenas lead to significant graphite oxidadon. PSC coneh lad tint an accident inwohnng signaticant graphie oxidation at FSV is not credible. Also states NRC seached ahas same condusert PSC recendy determined that four simtJtaneous Independent struc-tural failures would have to occur to permit oxygen (air) llow into the FSV PCRV riscossary to initiate and b sustain signi6 cant oxk dation of the FSV graphite. Even though no credible mechensam was found b Introduce sufficient air for signi5 cant graphite oxida-tion, PSC has identified a method that could terminate such an event. Further describes information provided NRC on this rielhod and tie design dfferences between Chemobyl and FSV. FSV has an emergency plan which provides for action to protect the health and salsty of tio public based on oftniis doses. Deems a special graphite Are evacuation plan unnooessary and not cost effecdve since resources would have b be expended unneces-sarily for development and mair snance of unnecessasy pro-e cedures and documents. PSC ches tioir evaluation of stored energy- . Not signifcant operating concem at FSV because it be-comes neghgeble at temperatures >500*F (FSV graphite exceeds this temperature at powers >7% of full power) . II operated at 5% for 30 days, adiabatic rebase results in only 4*C calculated temperatsre rise, which is insignifcant retaave to design temperature of FSV core Page 4 N

i PRM z Q W4 g l tao 2 2 INDUSTRY na W So 80 ABSTRACT COMMENTS Public Service 1/97 No X Rooommends hat pettion for rulemalung, to me extent that it Company of apphes to FSV be dermed and concludes that requesas made ty Colorado the petition are withour merit when appiled to FSV. Implementa-(Conenued) Won would place a turden on PSC's roeources wim no resideng a beneAls to public healih and salsty. 4 GA Technologies. 2/3/87 No X Provides summary of CBG pontion and GNs aaneeement of the Comments are relevant to heliurr> cooled HTGRs including Fort St. V,airt These 4 Inc. Chernobylaccident Presents the dillerences betwoon he HTGR comments should be factosed into staffs response to pennoner% concems for and me RMBK reactors-Fort St Vrah. - HTGR has He coolant and will not react wish ceramic fuel 4 i partcle comangs or graphite . RM8K boding water coolant can react wien zircanoy fuel W very quicMy at temperatures reached under transient condemons i . HTGR has negative reactivity leW over its entire range of operation and loes of its single phase coolant is negative . RMBk's two-phase boilin0 water coolant in combinsson with 1 omer factors can result in a poedive reactivity inserton and W when coolantis lost or voided

• HTGR kaelis normeNy coupled with me graphite moderator, resulting in a core met heats up aloudy during power or Sow transients RMBK's kset is not hermasy coupled wim me moderator, and the thermal roeponse ame of he core la similar to that of LWRs These differences preclude an HTGR wrMant of the type that occurred at Chemobyl and make an HTGR accident met involvee 4

sagnsicant graphies oxidselon highly incredble. Seness met me Ere initiasy observed at Chernobyl was caused by cumrig fuel and claddng. not txaning graphies. GA4 ovaluelion of stored energy at Fort St. Vrain is operated at 5% power (below 250%) for 30 days shows Ihat if released adabeticap would increase core temperanas by less man 5'C. y Recornmends that NRC deny pettion. I Page 5 l su e

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PRM Ac es g ABSTRACT COMMENTS in Ww reactor pool underlarge quanihies of water. Conclude met the NRC has correcWy assessed me safety impEca'Jons of graph-iso as it b used h meearch mactors and innt the C8G pontion I r 'l e Page 2 t

PflM 50-44 INDIVIDUAL cmzENs nW W S B ABSTRACT COMMENTS 3 Harry Peartmari, 1113/86. No X Allegatons and claims are not supported by available tacts. References on measurernents of sto,ed energy in UCLA ArgonatA Reactor may PhD Graphite Stored Energy Measurements - Cites paper given at provide an important means of estabishng credbiley of any BNL recommended ANS Nevada Meeting, June 1986 by Ashbau0h, Ostrander, and cab dational methodology Peastnan. The paper reports restdan of measurements of the Excepmons to petimoners claims must be consadored. stored ens.gy in sampise of paphite from too locations (Lo',192 Peariman's motiod of cahdad'10 yaphite seosed energy needs ac be exarroned caugm near tie conter of the graphite island and 33.2 caugm at in detail km d- '--f.ii a secommended c=h dW model. j tio edge of tie center luol box of tie UCLA Argonaut Reactor). AI arguments presented are tec;tyy of conesderation in estabhahne NRC staff l The 332 was changed to 33.3 caFyn to be consistent whh recommendations. References 1,3,7, and 8-are worthy of further invesagston. l f rounduig procedures. 4 Comments on the resuhn as losows: I j Totalreactor operation of 21 Mwd . Thermal Auence - 3 x 10'*nta - Whaqtic conditionslargely a tieosoalcalconcept-dulScult to adiieve in practice - Stored energy doaoases witiincreasing distance tom care regiors, e g.,5.61 cal /gm @ 18*; 1.34 caugm @ 22* and unmeasurable O 26* - Whhin graphite leland, stored energy decreases from 33.3 to 192 calem in going a distance of only about 3*, from bei box ed e sonesd center of paphite leiend 0 i - A zone abota 3 VAdejustoutside tie fuel boxes is a Emhed voluras where adebetic release of stored energy condd reetdt in tenperature increases of 100* to 139" C - resuas Irom cooler paphite temperatres and a peak of $1e last i Suu l - Citas repost, *BEPO Wigner Ensegy Release,* Geneva 1958, I which gives data on energy release in ansel of reactor paphhe in place and in tio laboratory, e g.,80*C less i tempereture rise over 6 tv. period cornpared to 1 hr. in j laboratory - Graphne Stored Energy C=hdations -NRC sponsored calculations (NUREG/CR 2079) uses higNy approximate and empirical model applied to a hypotiotical Argonaut } reactor i 1 l Page 1 of 3 i U

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PRM 50-44 ' INDIVIDUAL cmZENS 5 E o ou ABSTRACT COMMENTS h V. 10/30/06 No X Cass locanon of graphhe reactors on univoresty campuses in No new information provided. Resistes pennons daims and concerns withous Wh ard, PhD urban assas make rnishaps similar to Chernobyl and Windscale providing any addisonal bas!s or sakstannation. events equaNy dangerous. Proes reports on Chemobyl tragedy do not note het rnany US cities host reactoss with simder designs j wahout containmut N% Local Are Sghting units urpopered to EgM papNeo Esos. NRC has iederassimated the danger of graphite Ares. I New data shows measurernerW of 33.2 cal /gm for UCLA as opposed to 5 cal /gm estimated by NRC. 4 Stored energy can help cause paphies are. Operators should be regdred to measure Wigner energy present in graphhe and develop an effecive plan for preventing deanter Ernery Nomeby 11/7/06 No X Cates the assertions of the C8f3 pettion b new arguments or information presented. Staff sosporme to pennon wie address

• Cherreobyl proved grapNeo Ares are not nor><redibio aN of he stated concerns 4
• There are dozone of graphile moderated research reactors.

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64 ?3 PRM 5044 CITIZEN'S GROUPS 5E E 3o ABSTRACT COMMENTS o Nuclear-Free 11/3/86 No X Ches Chernobyl drsaster and paphite Are at Windscale Reactor No new Ischrecal adormanon presented. Restates CBG irdormanon and poemort Berkeley as indcation that it is imprudent for NRC b maintain the posinon Conoems are: (1) role of paphies in the Chemobyl and Wirwhenta events (2) the 1 _r met a graphite fro is a heddde* event Urges NRC to order oedbbty of paphine txaning, and (3) me need for an evacuation plan for the the preparation of an evacuation plan at Berkeley Research Betheley reacbr and Urworsey of Catforrh campus at Berkeley. Response b Reactor. CBG petition should address mese concoms 4 l GE4tockholder's 11/3/86 No X Cates inadequate salsty regtdatoris at US renewch reactors No new techmcalinformaton preeensed. batales CBG information and poemon. Afhance Against using graphite. Support PRM 50-44. Also sentes met Chemobyl Concems are: (1) measurement of stored energy in reactor graptute (2) plars, Nuclear Power demonstrates the yeat danger of paphite Aree and the dl6cuhy equipment, and training in extinguishing a paphne nre,(3) preparation end peke in extinguishly them. Restates CBG petitions proposed rules. Ecation of evacuation plans for o&sies personnel and for nearby residents. Urges rules to saloguard pubEc heahh and reassure public. Response to CGB pension should address twee concoms ) Maryland Nuclear 11/3/86 No X Urges adophon of new ndes to improve salety of research No new technicalinformation presented, beates CBG pennon anformamon and safety Constion reactors using graphine. Cites Chemobyl sociders as demonetai-poshiort Concoms are: (1) danger trorn paphne Em, (2) dificuhy in exangtash-ing how dangescus graphies Em are and how difRcdt they are b bg paphne Sm,(3) GreAghters lack of Waining or exponence in extngtantung ) put out. Urges hat PRM 50-44 be adopted and implemented. graphite Gree, and (4) he need for evacuation of laboratory workers and odiers nearby. Response to CBG ponton shodd addreas these concerns. i I Ohio Chizens For 11/3/86 No X Supports PRM $0-44. Considers NRC's policy of regarding No new or technicalinformation presented. Restates CBG informanon and posi. Esponsable graphies fires as notararmia events as a norgredible and irrs-tiort Concems are for NRC b make a proper response to me Chemobyllessons Energy,Inc. timal proposem, consadoring paphhe Ero at Chemobyl NRC loamed Response to CBG peeson shodd address these concoms. should consider the reality of graphile Ero and evoke appro-priate response i i i W 1 '}}