ML20128C238
| ML20128C238 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/20/1992 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Beckman W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TAC-M83757, NUDOCS 9212040302 | |
| Download: ML20128C238 (7) | |
Text
_
November 20, 1992 Docket No. 50-155 l
Mr. William L. Beckman, Plant Manager l
Big Rock Point Plant Consumers Power Company 10269 U.S. 31 North Charlevoix, Michigan 49201
Dear Mr. Beckman:
SUBJECT:
>LARiflCATION OF REPORTING REQVIREMENT FOR ACTUATION OF THE REACTOR PROTECTION SYSTEM (TAC N0. M83757)
This letter is in response to your June 3, 1992, submittal requesting clarification of the requirements contained in 10 CFR 50.73(a)(2)(iv), which concern the reportability of actuations of Engineered Safety features (ESFs),
including the Reactor Protection System (RPS).
In particular, your submittal requested guidance for reporting RPS actuations which occur during shutdown conditions and which do not involve control rod motion.
On October 13, 1992, an amendment to the reporting requirements contained in 10 CFR 50.73(a)(2)(iv) became effective, in the revised rule, the staff removed the requirements for reporting a number of various EST actuations, including RPS actuations which nccur when all control rods are already inserted into the core, in light of this revision, the " spurious" RPS actuations with no control rod motion described in your submittal would specifically be non-reportable, as long as no other reportable actuations occurred as a result of these actuations, or the signal that caused these actuations.
Additionally, ventilation system actuations and reactor water clean-up system isolations will no longer be reportable.
Enclosed please find the fedeal Regjllet notice describing the changes to 10 CfR 50.72 and 50.73, as published on September 10, 1992 (57 FR 41378).
I encourage you to review these changes for applicability to your procedures and to make changes as necessary.
If you have any questions concerning this issue, please contact me at (301) 504-3018.
Sincerely, (kininal signed by Leonard Olshan, Project Manager Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
- SEE PREVIOUS CONCURRENCE,
OFFICE LA:PDl!!-l*
(PM:PDIll-1 PD:PDill-lh NAME MShut+1eworth b01shan LMarsh DATE 11/5/92 11/W/92 11/P/92
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c I 4 9212040302 921120 PDR ADOCK 05000155 Mr P
PDR 4 u m4 L
Mr. William L. Beckman
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Big Rock Point Nuclear Plant cc:
Mr. Thomas A. McNish Consumers Power Compa,nySecretary 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon Esquire Consumers Powe,r Company 212 West Michigan Avenue Jackson, Michigan 49201 3
Jane E. Brannon, County Clerk County Building Charlevoix, HI 49720
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Office of the Governor Lansing, MichiganRoom 1 - Capitol Building 48913 U.S. Nuclear Regulatory CommissionRegional Administrato 799 Roosevelt Road Glen Ellyn, Illinois 60137 Nuclear Facilities and Environmental Monitoring Section Office Department of Public HealthDivision of Radiological Health 3423 N. Logan Street P. O. Box 30195 Lansing, Michigan 48909 Resident inspector OfficeU.S. Nuclear Regulatory Commission Big Rock Point Plant 10253 U.S. 31 North Charlevoix, Michigan 49720 Nuclear Operations-Hr. David P. Hoffisan, Vice President Big Rock Point Plant Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201
.,,,r---
Federal Restoler / Vol $7, No,176 / Thunday, September 10, 1992 / Rulee and Regulations i
m72 and 10 O'R so.73--Clartreation of NRC Systems and Guldehnes For Reporting." Fouowing ruolution of putdic commenta, h NUREG will be issued in h final form.W NUREG l
~ will contain improved guidance for
~ event reporting-10 CM Par 150 NRCs reviews of operating
)
experience and the pattems of hceMeas' Mts atto-Ag13 reporting c,f operating events sinr41964
~
Winor Modifications to Nuclear Power have,tndjcated that reports on some of these evente are not necenary for b Reactor tvont Reporting NRC to perform its safety mission and Requirements that continued reporting of these events Aomcy:Nucir1r Regulatory would not contribute usefulinfortrat4m Commission. -
to the operating reactor events Acupe Nel rule.
5
- databan. Addadonally, hse svuuAny:W Nucleer Reguletory -
unnecessary reports would have continued to consume both tbs Commlulon (NRC) has amended its beensees' and the NRCs ruourcae dat regulauona to make ndnor modifications to the cunent nuclear power reactor could be better applied elsewhere. W event reporting requinments. W final NRC has determined that certain types rule applies to all nuclear power reactor of events. primarily.those involving beensees and deletes reporting invalid engineered safety feature (EST) requirements for 60me events that have aduauona, am oGule M no safety 81 nffiC8aC8-8 been determined te t.e of little or no
. safety slgnificance. The final rule Vaud ESF actunuona are thou
' reduces the industry's reporting burden actuations that result from " valid and the NRCs rnponse burden in event signale" or from intentional manual initisuon, unless 11is part of a review and assessment.
o serscTivs DAts: October 13.1992.
preplanned test. Valid signals are thop 81 n8 8 8 M 8kd in M8ponse to 8
Pon rumman woawAnoes cotrTAct I I""I **"did" " E**'k" RaliTripathi. Office for Analysis and
u'"s'f 6e aquirments fw N as
' Evaluauon M Operational Deta. U.S.
Inluaum Nuclear Regulatory Commlulon.
Washington DC 20555. Telephone (301).
Invah actustions are by definitfoa those that do not meet the criteria for 492-H 35.
being valid. Ws invslid actuations m,ygg,y, m y,,,,
include actuations ht are not the rnult Backgroumi of valid signals and are not intentional manual actuations. Invalid actuations
- W Comm!ssionisinuing a finalrule include instances where instrument that airside the nuclear power reactor 8""
event reporting requirements contained ther invalid signale c'aused actuation of in to CFR 50.72. *1mmediate Notification 6e N(e g a csWet, an enw I Requirements for Operating Nuclear In u** Of lumPero o lifted leads, an error,
' Power Reactors." and 10 CFR 50.73.
in actuadon of swucho M controls,
- 't.fcensee Event Report System." W
- 9uipment failure, or radio frequency finalrule is loued as part of the I"
- b.
Commission's ongoing activities to
, improve ha regulations. Specifically. thla NRCs evaluation of both the reported
- final rule amends 10 CFR 50.72 (b)(2)(li). events since January 1964, when the existing rules first became effective, and
. and 10 CFR 60.73 (4)(2)(lv). On June 26, the comments received during the Event 1982 (57 FR 2a642b the Commiselon Wodshopt conducted in Fall
. lasued a proposed rule requesting pubhc '.Repo. ol1990i entitled needed impro
. comments on these as.endenants.
in the' rules. The NRC determined that ^
Over the past several years, the NRC has (naeased its attee%s 'o event =
-. invaUd actuation,leolation, or
~ reporting lseues to ens.te palformity,- i realignment of a limited set of ESFs',.
consistency, and completenen in including the systema, subsystems, or reporting. In September 1991, the NRCs' components [i.e., an invalid actuation.
I I
Omco for Analysis and Evaluation of isolauon, or rnlignment of only the l
Operational Data (AEOD)leaued for reactor'wstor clean-up (RWCU) system.f l
- comment a draft NUREG-1022. Revioloct l
1.5 " Event Reporting Systems to CFR
. IMar Raoulatory camminion,wuhueca De sosea A enpy is she evadat,le for faapecoas er j
copytn3 or 4 Ese se the NRC Pubus Deceae f
(
- Proe namele copp mer be requested by arrinns to Roman. stao L auen NW,(Lawer invel),
the Distrentice and Matt Servicae Seoksi, U.3,.
washmetoa, DC 30saa 1
red:ral Register / Vd. 57, N,176 / Thursday, Sept:mber 10, 1902 Rhl:a and Regdations 4LT73 the control room emersency venulation ventilation system, auxiliary buddire nla rule endudes thne categodes of ICREV) s) stem, the reactor buildmg ventilation system, or their equivalent events frorn reporting-ventilation systern, the fuel building ventilation s) stems). The actuation of (1)lhe first cat endudes events ventilation system. or the auxiliary the standby gas treatment system in which an invall orRpS buddmg ventilation system, or their following an invalid actuation of the actuation occurs when the systatn la eqmalent ventilation systems) a'e of reactor building ventilation e) stem is altvedy properly removed frwn service ht11e or no esfety significance. Ilowever, also exempted from reporting. In if all requirementa cf plant procedures these es ents are currently repo 1able addition, the final rule endudes invalid for amoving equipment from service under 10 C}R 5012 (b)(2)(b) and to CTR actuations of these f3Fs (or their have been met. This indudes required 50 73 (a)(2)Sv).
equivalent systetas) frvm signals that daarance documentauon, equipment The fmal rules for the current event onginated from non-13F circuitry.
and control board tagging. and properly reportmg regulations,10 CTR 50.72 and flowever, invalid actust6ns of other f"sidoned valves and power supply 10 CIR 50 73 (48 FR 3M09. August 29,
'I"5-1983, and 48 IV 3MM. july 2ti,1M3, 11Fs would continu to be reportable.
respectively), stated that ESF systems, F r etemplt emerpA'y con motmg (2) The second category endudes g
j,g gg,,.
events in whidi en invahd ESP or RPS mdsdmg the reactor protection system (EpSI, are prouded to mitigate the contat ment isolation valve closures actuation occurs after the safety that affect cooling systems, main steam function has already been completed (s.b ni p e a na e
n a
n 2'
r w h d not !4 tha'lenged frequently or residual heat removal e stem isolaUone v s are 1 edy do ed, or an inval d unnnessenly.The Statements of for systuns designated any other Consideration for 'hese final rules s!so names but designed to fu fill the full i8*"'dI-s'ated that operation of an ESF as part hmction sirnilar to these systems and (3) The tidtd cateFory exdudes events of a pre planned operational procedure their equivalents), are still reportable. If in which an invalid 15F actuation or test need not be reported. Ihe.
en invalid ESF actuation reveals a
, occurs that invo.es only a limited set of Commission noted that ESP sctuations defect in the system so that the systern No l1.e when an hwalid actuation, mdudmg reactor trips, are frequently '
failed or would fail to perform its isolauon, or nabgnment d only the associated with significant plant intended function, the es eat continues to RWCO system, or any of the following au b'd transients ar.d are indicatise of esents, be reportable under other requirements ve
,b sYs M
that are of safety significance. At that of 10 CTR 50.72 and 10 CTR 5013,If a.
time, the Comrnession also required all condition or defidency has (1) an building ventitetion system, auxiliary It F actuations, induding the RPS adverse impact on safety.related a d g ventila o ste r th actuations, w hether rnanual or equipm'nt and consequently on the automatic, sahd or ins alid-exte t as abihty to shut down the reactor and invalid actuations that involve other noted, to be reported to the NRC hy maintain it in a safe shutdown I'SFs not specificall enduded,(e.g.,
te'ephone within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of occurrence condition. (2) has a potential for Q'
{"gy' sjnment C
follow ed b) a wntten brensee Event significant radiological release or Isolation valve closures that affect Report (LER) withm 30 days of the potential exposure to plant personnel or.
Incident. This requirement on timehress the genersil public, or (3) would m Img systms, enab steam now, of trportmg ternams unchanged.
cornpromise control room habitabibty. -
[*'n'u" r act, tio residual The reported information is used by the event /oiscovery continues to be the NRC in conf,rrnation of the bcynsing reporuble, heat nmoval systm isoladons, or their bases,identihcation of precursors to Invalid 15F actuations that are
- 9 * " '# * * * "
ses cre core damage. identification of ilant specific deficiencies generte en luded by this final tuIe, but occur as IJcensees continue to be required "to essons, reslew of management control a pan a wp dable ennt, continue to submit LERa if a deficiency or condition systems, and hcensee performance be described as part of t.he reportable associated with any of the invalid ESF event.These amendments are not a ssessment' actuations of the RWCU or the CREV intend (d to preclude submittal of a systems (or other equivalent ventilation E,scussion complete, accurate, and thorough systems) satisfies any reportability The NRC has determined that sorne description of an event that,, otherwise criteria under i 50L72 and l SCJ3.
esents that invols e only invahd ESF np rtable under 10 CFR 50 72 or 10 CFR actuations are of httle or no safety 5013. The Commission relaxed only the im ct of the Amendments on the signmcenc e. tiowever, not all invalid selected event reporting requirements In ustry and Govemment Resources ESF actuations are being exempted from specified in this final rule.
Relaxing the requirement for reportirig reporting through this rule.The.
Licensees are still required under to of certain types of ESF actuations relax ations in event reporting CFR part 60, appendis B. " Quality reduces the industry's nporting burden requirements contained in the final rule Assurance Crtteria for Nuclear Power
- and the NRC's response burden.Tus apply only to a narrow, limited set of Plants and Fuel Reprocessing Plants," to reduction la consistent with the spec.lically defined invalid ESF address corrective actions for events or objectives and the requirements of be actuations. These events indude invalid conditions that are sdverse to quality Paperwork Reduction Act.1tese actuation. Isolation, or realignment of a whether the event is reportable or not.
amendments have no impact on the hmited set of ESFs including systems, in a ddition. minirnizing ESP actuttlons
- NRC's ability to fulfillits mission to subsystems, or componenta (l e., an (such as RWCU isolations) to reduce ensure public health and safety because Lavalid actuation, isolation. or -
operational radiation exposures,
the deleted reportability requirements reabgnment of only the RWCU syatem, associated witn the investigation and have little or no safety s!gnificance.
or the CREV systerr. reactor building recovery from the actuations, are..
' existing rules will result in about 150 (or It is estimated that the changes to the venti!ation s) stem, fuel building consistent with ALARA requiremerda.
[
- 41380 Federal Regleter / Vol. 67, No.17e / Tbursday Geptember 10, 1992 / Rules and Regul:tlons 5-10 percent) fewer Ucenses Event their concerns about' eliminating the average 50 boers per licenses response.
Reporta each yeer. Similar tv :luctions selected event reporting requirements.
including the time required revtewing tre expected in the ausr.ber of prompt hoe commenters believe that the Instruction.a. searching enfating data svent notificetona reportable under 10 elimination c4 these event reporting sources gothering and maintaining the CHL 50.72. Some respondents, in their requirments mey adversely affect the data needed, and reviewing the comments on b proposeid rule, dated NRC's informtion database and collection of infortnation. Send lune 26.1992, sebmitted an estirnate of ultimately affect the agency's ability to comments regarding the estimated approximately 15 percent reducdon in carey out its miselon to protect public burden reduction or any othee aspect of their reporting burden.
health and safety. For many yeera. th*
this collection of infortnation, including S
ry of Carmnh NRC staff has been systematically suggenths for reducing this burden, to reviewing information obteined froen the Infarrnation and Records The NRC received 19 commento-3 Licensee Event Reports.ne**
Mansgement Dranch (MNBD-771th UA from individuals. 3 from industry-easenments of teactor operational Nuclear Regulatory Commission, supported organitauona, and 14 from experience have tododed data on th*
We shington. DC 20555: and to the Dew utilities. F.xcept for two respondanta. all types of eventa induded in the three Offimr. Office of Information and commenters welcomed the rategories that the NRC le deleting from Regulatory Affalts NEOB-3019 Commission's efforts to reduca the reporting, The steffs reviews and 0011 and 3150-0104). Offica of '(2%
licensee burden and to save the assesements of nearly 1000 eact*
Management and Budget. Washington, ageney's resources la event review and years of operational emperience have DC m processing, The stilities and the identibd enentially no safety indnatry. supported organlaations signi!Vam associsted with h type of Regulatory Analysis exprened.h'ett desire for a broadee events included in the aforaneauoned relaution to indude alllavalid ESP three categories.%e Co ntnisalon has W Commlulon has repared e actuations from reporting, reviewed tha ux) of these regulatory analy:Is on is naal mle.
Other comments frora the respondents amendments, a on b basis of the h analysis eammines the costa and benefits of the alternatives considered concerned the following: darification of etaffs asaesament of the past reacta, the definition of " invalid
- actuations; operational eaperience, has by the Commisalon. He analysis !s examples of events being exempted subsequently conduded with a available for inspection in b NRC from reporting; considersuon of plant.
reasonable confidence that relaution Public Document Room. 2120 L Street, specific Mtuauons: 4mempuon from from reporting oi events in the three NW. tower Level. Wuhington, DC reporting of the actuation of the standby categories does not a!Iect the agency's 20555. Single copies of the analysis may gas treatment system follow 4g an abthty to protect public health and be obtained from: Raji Tripathl. Office for Analysis and Evaluation of invalid actuation of the reactor building safety,d on the loput from the stilities.
Operational Data. US Nudear ventilation systenc and ponibly Base exterding relauuon of invalid these amendrnents wiu reduca the Regulatory Commission. Washington, act e Jons/isolations of RWCU from industry's reporting burden by about 15 DC 20555. Telephone (301) 492-445.
rep to indude those of the percent.no esumated savings of the Regulat"I Flexibility Certifkation chemic and volume control systam in NRC's response burden in event review a pressurized water reactor. N and assessment is about 5-10 percent.
In accordance with the Regulatory Statement of Conalderations for this Flexibility Act of 1980 (5 USC,005 (DJ).
finalrule addresses most of these Envhtmlimpact: caw the Commission certifles that this rule coccarns. Other luues and clarifications E*'I" E ",
does not have a significant econorr.ic concerning event reportability wiu be
. De NRC has determined that this impact on a substantial number of small addressed in NUREG-1021 Revision 1.-
final rule le the of action described entities.N final rule affects only b l{owever, it is not practical to addreas a in categorical e unions to CHL 61.22 event reporting requirements for plant-specific situation unless it relates (cX3Xu) and (!i1). Nrefore, neithee an operstlocal nuclear power planta. %e environmental impact statement not en companies that own these plants do not to a generic concera.
& Commission attesees that only environrnectal auesament has been fall within the scope of the definition of certain spectfte invalid ESF actuations prepared for this final rule.
"small entities" set forth in the a the amerNent Paperwork Reduction Act Stalement a
e ibit ty Act or the Small NUREG-to:2. Revision t will contaln This fhsel rule amende information specific sumples and additional collection requirements that are subject regulations Inued by the Small Business guidance on eveats which are presently to the paperwork Reduction Ad of 1900 Administrelion Act in 13 CFR pa t 121.
reportable as well as those which are (44 U.S.C. 3501 et seql hoe Backllt Analyals beina exempted from reporting through amendments were approved b the these amendmenta. In h future, the Office of Management and Bufsd
. Commission has completed an As required by to CFR 50.109 the Commisalon wit! give due cona;deration approval numbers 3130-0011 and 3150 assessment of the need for Backf1t to other propoeed relaxations from 010L es ent reporting after the NRC staff has Because the ruta wiR relax axistlog Analysis for this final mle.W had an opportunity to reassess 6 data reporting requirements, puhtfo reporting ' proposed amendments include needs of the agency and performed burdan of information la expected to be relautions of cartsin existing safety assessments to justfy inluating a redumd. R is estimated that about 150 requinments on reporting of information
' separate general'rulemaking. Unt0 such fewer IJcensee Event Reporta [NRC to the NRC.Wss changes neithat time, all events not specificaDy Form 366) and a almnarly redi ced impose adottional reporting exempted in these amendments continue number of prompt event nMbmHm, requlrements nor requin rDodiflCatinne to be reportabla, made pursuant to to CFR 50J2. wUlhe to the fed!1tles or their licenses.
He two peependents who opposed required each year %e res According!y, the NRC has conduded the proposed amendments expressed
' reduction in burden is estimat to that this final rule does not constitute a
.---w
2 t
Federal Registee / Vol. 57. No',17e / %eriday. September 10,1sta / Rules'and Regulatione statt :
boca. fit end. thus, a bacMit analyste is *
- 2. la I 80.7L painsre (b)(3XH)to Fw Ibe 18eclear V 7 -
not regtdred.
revised to rood as lemas H. Yoyle.'
IJet of subjects is is CFR Port te Iears Mnoensenen -
' A
- "* D ##" "
Antitrus1. Cle esified informstion,.
mehomense for opemeng meteer pmr W MrW M &el am) '
Criminal penalty, Fire prevontion, l
Incorporstion by reference.
~-
4 Intergovernmentai relations, Nuclear (b) Non-emergency Eeenta. ' ' * -
power plants and reactors Radietion
(!) Four-bour reporte. * * '
protectiott. Reactor siting criteria.
"(11) Any event or condition that results Reporting and recordkeeping.
in a manual or automatic actuation of for the tessons set out in the any engineemd safety feature (ESF), - -
preamble and under the authority of & including b reactor Atomic Energy Act of1964. as amended, (RpS), except when: protection systein.
the Energy Reorganization Act of 1trf4, (A)'!he actuation roeults from and le ae amended, and 5 U.S.C. &&2 and 563, part of a pre planned sequence during the Commission is adopting the lesting or reactor operetion:
following amendments to 10 CFR part (B) The aetuation is invalid a' nd: -
50.
(J) Occurs whue the eyetemis properly removed from service; PART 60-DOMESTIC UCENSING OF has )t een already completed; or (J Occu.) after b tafety function -
PRODUCTION ANDUTtLtZADON FACIUTIES (3) Involves only the following specific 1.ne authort*y ejtstion for Part 50 le ESFs or their equivalent eyetems:
revised to read as follows:
(/) Reactor water clean up system:
O Au'Lbortry:Sece.102.103.104,106,141,182 183.186, te9 es Stat. 94 93r, SR 968. 953 '
D On Is 954,953,956 es amended, ecc. 234, as Stat.
(ill) Reactor building ventilation 1244, ee amended (42 U S C 2132. 2133, riu, oyatem:
2135, 2201, 2232, 2233, 2238. 2;;38, 2242): wee.
(lv) Fuel building ventilation system; 201, ee amended. 2o2,206, se Stat.1242. as or amended.1244.1240 (42 US C be41,5642, (e) AuAllfory budding ventilation Se tion Sar eleo leeued under Pub. L es '
7 "', ',
001, sec. m 92 Stot. 2961 (42 U.S C 5461)
,a*
Section M10 also leeued under acco.101. tes, L la l 50.71 paragraph (e)(2)[ly)la se Siet. 9% 955. es amended (42 U.S C 2131, revised io read as follows: -
2:35k sec.102, Pub. L t1-190,43 Stat. 453 (42 US C 4332). Sections 50.13,8044(dd) and l 64.73 f.loonese met toport system.
m103 eleo leeued under sec. los. se Stat. 838..
. (a) Reportable events. ' * '-
4 ee emended (42 US C 21W Sechone m23 50.35. 60 55, and 60 Se eleo issued under sec.
(2) Helicensee shah reportr * *
- 165, se Stat. 355 (42 U S C 2:38). Sectione (iv) AnI event or condition that m33e,la35a. and Appendta Q also inued resulted in a manual or automatic under sec.102. Puth L Irt-teo,43 Stat. 463 (42 actustion of any neered 6alety US C. 4332). Sectione 80.34 and WH also feature (ESF),inel the reactor-leeued under etc. 204, se Stat.1245142 US C protection system (RPS), except when:
Skt). Sectione 50.58, Erl, and Sa82 also (A) The actuation resulted from and -
Lesaed under Pub. L 97-418. 96 Stat. 3073 (42 U S C ?.239) Section 60Je eleo leaved under wee part of a pre planned sequence sec.122. 88 Stat. 93e 142 UAC 2162). Sectione during testing or reactor operetion; 50 00-fC 81 eleo leeued under sec. te4, se Stat.
(B) The actuation was invalid and: -
954. es unended (42 U S.C 22H). Appendte F 14 Occurred wW h sydem was eleo fund under sec. ter, as Stat. 968 (42 - properly removed from service;,
U.S C. 223r).
(2) Occurred after the safet For the purposes of sec. 223. se Stat. 86a, es bed been already completed;y functfon or, amended (42 USC 2273); 10 30A Base (s end (b). and Sa54(c) are Leeued under sec.)
(J)lavolved on}y the followf ag -
telb, sa SteL. 948. es amended (42 UAC,
specific ESFe or their equivalent '
2201(b)k i i SOA nr(el. nato (eMc). na34(e) oYMema-M CIO' -
(ii) Contra. ster clean.up system:
and (e). 60 44(eHet Saee(s) and (b). saar(b),
Saee(eL let (dL and (e), no te(et sess(ek (i),
t som emergency -
tiX1L (IHnk (pl (4L (ik (v). and tyk noss(r), - ventilation system:
2 6a55ela). (cHe), is), and (bk 80Jelck
(//J) Heactor building ventiletion.
I 6000(e), 50 82(b). 60.e4(b), 50 65, and 50.80(e) eystem:'
and (b) are leeued under sec. tell, se Stat.
949, se amended (42 U.S C 2201(ilk and
(/v) Fuel building ventilatlon 5ystem; l l 50.9(d). (hl and (jj. Sa54f w), (s), (1,b), (o:).-
and (dd). 5035(e). SO 3 A(b) 60.elfbt 80 e2(b)... M Ada#Ihk ventnah 80J0(el 50 r1(aHe) and tek 50.r2(ak 60.r3(el ' F *"-
and (bk sart. 60.re, and 60 no are nu.ed
?'
- "*r*
under sec.1e10. k' Stet. 9% es amended (42 Deled at Rocky!Be. letD, thle Irth day ed U.S C 22011o1).
Auguet tes2.
P 4
L
$ a DISTRIBU110N:
Docket file..
PDR PD31 Reading file JRoe JZwolinski LHarsh MShuttleworth L01shan 0GC ACRS(10)
BRP Plant file WShafer, Rlli cc: Plant Service List
. _ _.