ML20028E983

Informs That Issue on Implementation of NUREG-0737,Item II.F.2 Re Installation of Sys to Detect Inadequate Core Cooling Is No Longer Contested.Nrc 821210 Order Required Sys Installation.Certificate of Svc Encl

ML20028E983
Person / Time
Site:	Three Mile Island
Issue date:	01/25/1983
From:	Baxter T METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Buck J, Edles G, Gotchy R NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8301280318
Download: ML20028E983 (7)

Text

_.

00(METED SHAW, PITTMAN, POTTs & TROWBRIDGE "W A PARTNER $Mep OF PROFESSIONAL CORPOmATIONS 1800 M STRCCT. N. W.

• WASHINGTON, D. C. 20036 12O21 822-1000 cAMSay O POTTS. P C THOMAS A. SAATER PC JOMN M O'NCILL. JR. , cDAVLD LAW 4ENCE MILLER JAMES M SunOE R. P C JAY A. EPSTIEN ,FREDEltlCM L MLEIN STEUART L. PtTTM AN. P C.

TIMOTHY S. McSRIDC'QQ9 GEOmOE F TROWBRIDOE. P C. SMELDON J. WEISEL. P C TELECOPIER ANO L ALLEN 1.1 i - { l'.STEVElg P, PtTLER*

AND J. PAmatNO STEPMEN D. POTTS. P C JOHN A McCULLOWOM. PC ."

OCKALD CH ARNOFF. P C J PATRICM MICMEY. P C- 12O21822-1058 & S22 IISS ELISAGETH M PENDLETON 4.MANOFSMY PHILLsP O BOSTWICM. P C. GEORGE P MICHAELY. JR , P C. *AUL A. KAPLAN JEFFRE7 S. OlANCOLA A TIMOTMY MANLON. P C J THOMAS LENM Amt. P C. - MARRY M. OLASSPtEGEL MANNAM E. M LIESERMAN k QEOmOC M NOGERS. JR . P C STEVEN L. MELTZER. P C JEFFERYL.YASLON SANDRA E. FOLSOM FK ED A LITTLE, P C DEAN D. AULICM. P C. RAPiFAK 400 JACK McMAY JUDITH A SANDLER JOHN S RMINELANDER. P C. JOHN ENCEL. P C. g ggg, ggg.ggyg THOMASM McComM sCM EDWARD D YOUNO. ul GWCE W CMumCMeLL PC CMAmLES S TEMMIN. P C SUSAN M. FREUND ROSERT L. WILLMORE LEELIE A NtCMOLSON, JR , P C. STEPMEN 3 MUTTLER. P C - JOMN L. CARR. JR. ANDREW D ELLIS MAntisN D. MRALL P C WINTHROP N BROWN. P C PMILIP J MARVEY WENDELIN A WHITE NICHARD J M ENDALL. P C. JAMES S MAMLIN. P C TELEA ROSERT M. GOmDON STANLEY M. SAmo JAv E SsLSERO P C RANDAL 3 MELL. P C SS-2Siip2 (SMAWLAW WSMB J EANGARA M mOSSOTTI.PC. ROSERT E 3AMLER SONNat S O' OTTLtES LESLaE M. SMITH CEORGE V ALLEN. JR . P C RICHARD E GALEN CABLg + SMAWLAwa MOWMD M SMAFFERMAN ViROINIA S RUTLEDGE FKED DRASNER #C ROSERT S ROSSINS DESORAVB SAUSER MATHEnlNE P CMEEK R. M ENLY WE BSTER P C. STEVEN M LUCAS - SCOTT A. ANENGERO JANtCE LEMRER-STEIN NATM ANIEL P SREED. JR . P C DAVID M muSENSTEIN CAMPSELL MILLEFER TRAVIS T. SmOWN. JR MASM AUGENGLtCM PC LYNN WHITTLESEY WILSON SETHH MOOOASIAN GAIL E. CURREY EENEST L. SL AME. JR , P C MATIAS F. TRAvlESO-DIAZ JOMN F. DE ALY' SMEILA McC MARVEY RICHAmD M MRONTMAL CARLETON S JONES P C. VICTORIA J. PERMINS L' * ' " '

COU8sSEL SANDmA E. G' RUSCA*

MENNETH J. MAUTMAN

'leOT ADMaTTED IN D C.

WRITER'S DIRECT DIAL NUMSER January 25, 1983 822-1090 Gary J. Edles, Esquire Dr. John H. Buck Chairman Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Board i Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Reginald L. Gotchy Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of Metropolitan Edison Company (Three Mile IsL&nd Nuclear Station, Unit No. 1)

Docket No. 50-289 (Restart)

Administrative Judges Edles, Buck and Gotchy:

This is to inform you of new developments with respect to Licensee's Exception No. 1 to the Atomic Safety and Licensing Board's Initial Decision in this proceeding. Exception No. 1, which is directed at a recommended long-term condition, states that:

4 The decision by the Licensing Board to require i additional instrumentation to detect inadequate core cooling, in the form of reactor coolant level instrumentation or its equivalent, is ,

not based on the whole record and is not 8301200318 930125 PDR ADOCK 05000289 U Q PDR

l 4

SHAW, PITTMAN, PoTTs & TROWBRIDGE l

. ...r c .. o ..on...o 6 co..our.o .

Gary J. Edles, Esquire Dr. John H. Buck Dr. Reginald L. Gotchy ,

January 25, 1983 Page Two l

supported by reliable, substantial and probative evidence. See PID 11 630-705.

! See Licensee's Brief in Support of its Exceptions to the Atomic Safety and Licensing Board's Partial Initial Decision on Plant Design and Procedures, Separation, and Emergency Planning Issues, March 10, 1982.

In an order for Modification of License, dated December 10, 1982, the NRC Staff directed Licensee to install at TMI-l an instrumentation system to detect inadequate core cooling, including, inter alia, a reactor coolant inventory tracking system. See 47 Fed. Reg. 57163 (December 22, 1982) (attached). Similar orders were issued to other licensees with plants of B&W design. Licensee has decided not to request a hearing on the order, and the deadline i for filing such a request has passed. Thus, the Order has become effective, pursuant to section V of the Order, and Licensee will install a reactor coolant inventory tracking system of a design and on a schedule which results from the Staff review of the t

technical information to be filed by Licensee in response to l the Order.

l Consequently, there is no longer a contest between Licensee t

and the Staff in this proceeding on the implementation of NUREG-l 0737 Item II.F.2, the subject of Licensee Exception No. 1. In I view of the Order for Modification of License, Licensee proposes that an appropriate disposition of the exception now would be to vacate the Licensing Board's recommended long-term condition as unnecessary.

Respectfully submitted, Thomas A. Baxter Counsel for Licensee

! TAB:jah Attachment cc: Service List attached

i l ,

, UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

SERVICE LIST Gary J. Edles, Esquire James M. Cutchin, IV, Esquire Clairman Office of the Executive Imgal Director Atcmic Safety and Licensing Appeal U.S. Nuclear Regulatory h insion Board Washington, D.C. 20555 U.S. Nuclear Regulatory Cr=minsion Washington, D.C. 20555 Docketing and Service Section Office of the Secretary Dr. John H. Buck U.S. Nmlaar Regulatory Ocmnissicn Atcmic Safety and Licensing Appeal Washington, D.C. 20555 l Board

! U.S. Nuclear Regulatory Conmission John A. Ievin, Esquire Washington, D.C. 20555 Assistant Osunsel Pennsylvania Public Utility Cr==imaion Dr. Reginald L. Gotchy P.O. Box 3265 Atcnic Safety and Licensing Appeal Harrisburg, Pennsylvania 17120 Board U.S. Nuclear Regulatory Ommissicn lbbert Adler, Esquire Washington, D.C. 20555 Assistant Attorney General 505 Executive House Ivan W. Smith, Esquire P.O. Box 2357 O=i man Harrisburg, Pennsylvania .17120 Atenic Safety and Licensing Board U.S. Nuclear Regulatory Conmission Ms. Iouise Bradford Washington, D.C. 20555 'IMI ALERT 1011 Green Street Dr. Walter H. Jordan Harrinhurg, Pennsylvania 17102.

Atcnic Safety and Licensing Board Panel Ellyn R. Weiss, Esquire 881 West Outer Drive Harnon & Weiss Oak Ridge, Tennessee 37830 1725 Eye Street, N.W., Suite 506 Washington, D.C. 20006 Dr. Linda W. Little Atcnic Safety and Licensing Board Steven C. Sholly Panel Unicn of Concerned Scientists 5000 Hezmitage Drive 1346 Connecticut Avenue, N.W., Suite 1101 Raleigh, North Carolina 27612 Washington, D,.C. 20036 l

.. . - , - - , , . - - , . . - - . _ _ . - - , - - - - - . . . - - . - . - . ~ . , - . . - - - -

Jordan D. Cunningham, Esquire 2320 North Second Street Harrisburg, Pennsylvania 17110 ANGRY /IMI PIRC 1037 Maclay Street Harrisburg, Pennsylvania 17103 William S. Jordan, III, Esquire Hamon & Weiss 1725 Eye Street, N.W., Suite 506 Washington, D.C. 20006 c muncey Kepford Judith H. Johnsrud Envimmental Coalition on Nuclear Power 433 Orlando Avenue State Cbilege, Pennsylvania 16801 Marjorie M. Aamodt R. D. 5 Coatesville, Pennsylvania 19320 r

Federal Register / Vol. 47..Ns. 246 / Wedn:sday, December 22. 1982 / N tices

)i . 57183 Mansgement. Room 3:08. N:w n o s.n.e. grso see m e wei.enees i 1 Executive Office But! ding, Washington. "" ""* = sume cons ress ews 1 D.C. a o,., , ,,

Dated at Bethesda. Maryland this 10th day &". . T , "." l* .* Doet et pie. 80-339]

of December 19s2. =s to m.en.s unen ww nun.

For the Nuclear Regulatory Commission. a,',",',.'"",",,",ng.,,,,,,,

, General pubile UtlNtles Nuoleer Corp. I f

Darrell G. Elseehut. ***""** **'m . > We faland Nuclear Stedon, Unit 4

Dirsctor. Division ofLicensing. Office of No.1); Order for Modifleetion of e

j NucleorRractorRegulatwn.  ;. ~ '"J^"**"*'*"C"'E'***"****'"t m {

I Appendix A.-Checitlist for Ptant Specinc I Review of Inadequate com Cooling (ICC)

.E.2"."

• " " " " E I"ME ".*" "."7m*'s.".',M. wm Ji ,,,ta,,, Q"" *.*,P *8 **sm.un ee messe er Corporation Se GeneralPublic Utilities Nuclear lastrumentation system e (the licensee) and three co-

' " I For N.e"m""asm"iTi si#E E "e's*ess mams. owners hold Facility Operating IJcense Docket No. ,

No.DPR-60, which authorizes the Opersted by: . cm m,: es a licensee to operate the %ree Mile

[

- l@'*g @ g ".,.83

• g'_8""

m o.

=

• "8 = =0"*** '" ","".""Te('

Island Nuclear Station. Usit No.1 (the Th3 followmg items for review are taken e**. facility), at power levels not in excess of .

from NUREC-om. pp ILF.2-3, and 4.

R sponses should be made to full 2

Mg,se,, Te,,e$,$,'m,,.7.,*,,*".**

n an w wease, 2535 magawatts thermal ne facility is requirements la NUREG4m.not 7"ommE

4. m. 7E%. pen v se samme emessa locateda at y. the

_ _licensee's

_ M waarsite reactor (PWR) in Dauphin abbreviated forms below. Applicants should ,,,,,,,,,, . County, Pennsylvania.

provide toforence to either the applicant's sm.

us m ese a.semnmmeam o aii,** ""9 "" " ""'""* me e'** * *, " ""f.E '

submittal or the generic description under the ,",,,,s"'""""*""'""'"""'8""*"""""" II '

column labeled " Reference "'lliese items are Co**, p a se usges ass _s,.,s3

' Following the accident at Three Mile required to be reviewed on a plant speciac s== se e nunse.orer. ansa- Island Unit No. 2 (DG-2), the Nuclear besie by NUREG4m for allplants. 8 Differences from the generic descriptione """c',,2=

• . s rg, W,,," f,E"",,'.,",e,m,8,""' M Regulatory Commission (NRC)IdendSed '

l i

provided by Westinghouse. the Westinghouse 4, es,my, cm.e.ss,a,,g

, ,es.uss. . en=, emme,,,a,na,",,",

u. =a g's.n the need for additional instrener'tation Own:r's Group. Combustica Engineering or ,(**"** * '"h8'8 *

• 8* ""*" 8"" *e mn e AH to detect inadatuate core @ (ICC).

ucensees were requiralby Orders -

Combustion Engineering Owner's Group must 7. com. m. -

be indicated by "yes or no"in the column '""""** *eusssssen

• " " ' " " " e" e.

• *es.

• *as issued in December 1979, to review ami upgrade exisdaginstrumentation to l labeled deviations and must be justified. ass am e ese sassa.orsr.nsa assure that infonnation on the reactor j: j3 Under the Column labeled schedule. either c . e, . a m,ea.us coolant subcooung margin and the l'8 indicate that your documentation of the item e,,._.om.,m,n.,=,,

se y

,gssungsumm, U D mperatus imucatai by the core exit is complete or provide a proposed schedule summons. ans as emner aque""'

for y:ur submittal. les over an elevated I pig,rW were available a

. ,,,, operators in the control room. In'

==. a.== addition, the NRC proposed that I ** o sess- additionallastrumentation to provide an

[ ,T,,,,_ """"" unambiguous, easy to interpret

i. o e s. , a cm is s .

Indication ofICC be studied and such i

• • 'r=='**** * ^==a.ar * *

• instrumentation be provided if found

• • • • '"'"""""# [ 1 *" ".,,", ,,,

.,, .,. necessary. In NUREG-0737, en omse 1. n nons e me en men. .

Clarification of T.fiActiertMan

( k",,,'*"_**""**'"",",,",

,, , ~~' ~

• '8"**=a*""**** Jteg riremenir, the design requireinents ;

i and quali8 cation criteria for additional r c e====>a e o.a===s or

• P., s m as. c.emana en instrumentation were speci$ed. On I

a an

.",,","",7,,,,

.a e , e me.v.

"o"."."

8"'

Wes

'.,"m'.".

mese ==.

.."".s"sHamms".'.'"E e ** ****

=, October 31,1980, licensees were required. pursuant to 10 CFR 50.54(f), to ,

""a""a

,,,,,g"",,,,,, ""****** -

provide a report detailing their planned '!

ao ,i.on m

,.nn ,,,,,, , instrumentation system for monitoring

== une a mm. == as=s .=. ICC.

• ",.*,,",,"7.*.".".",."".'.O Following analysis of the information ,

==am a A.momenes e evanne provided by the licensees, meetings with

• • • • '. ac .wi nuaes.om

'N 7'slC a=a e mas industry groups and independent studies by the NRC Staff, the Commission has se & da=o=a t ** Acaa- "O T.,,',", O li determined that during a smallbreak

• '.'fi, '.,.

i====wr Loss of Coolant Accident (LOCA). there a o=cre= e-ima- a==. 8**"'***'""""**""* le a period of time before the core has

",',L*'",,,,,,,,,*,,,,'",,C, a ce Er "*'"' " " """

nne s,a='t boiled dry (Indicated by core exit .,

am . an e .ca thermocouples) when the operstors have 1l

• . '""ga' "'"* ** * ' ,"*"" insufficient information to clearly  !'

m. m ** ".",,e,*,,."M"m"='

.a, a in es e e. indicate void formation in the reactor a = 'a 1.'=c.4cre.'ar'*=a we a = e= . e "o.a"=" '"a='s*a="="a*e*s*."=. vessel *s*head or to track the inventory of

=sor ca a aiorv '= e =sm =ma.a s. coolant in the vessel and primary es svam =* ==r== ==s """'"'"*"""""** system. He Subcooling Margin Monitor

• • • • "8"'"" ~ * ' ' * '

gives early indication of a problem but e  :

l u--- _ - . _ - _ -- - ___. _ - - . . _ - _ . _- . _ - -

S7164 Federal Regist:r / Vol. 47. N2. 246 / W.in:sday. D;cember 22. 982 / Notices Babcock and Wilcox(B&W) re:ct:rsin e n pp. ILF.2-3 and 4 of that document is does not indic:te wb:ther the condition provided in the Appendix to this Order.

is g:tting worse or betur. which the steam or noncondensables can accumulate in the hot leg candy 4.The licensee shall develop a

& cddition of a reactor coolant schedule for installation and maldng inventory system willimprove the cane (h!gh point of the system) and interfere with natural circulation, a d/p operational ihe ICC instrumentation r:11rbility of plant operators to diagnose measurement extending from the top of system which ensures installation '

the approach ofICC and to assess the the hotleg candy cane to the low point during the earliest refueling shutdown cd:quacy of responses taken to restore consistent with the existing status of the c:re cooling. The benefit will be in the hot leg is also required. A d/p -l preventive in nature in that the measurement extending from the bottom plant and practicaldesign and '

instrum:r4tation will assist the operator of the reactor ve'ssel need not be pmcurement considerations.This in avoid:nce of a degraded or melted provided il equivalent instrumentation schedule shall be subject to approval by f I (e.g., pump power or pump curmnt the Director. Division of Licensing.

ccre wh:n voids in the reactor coolant monitor)is provided to trend the syst:m and saturation conditions result 5. Prior to using thelastalledICC from over cooling events, steam Reactor Coolant System void content instrumentation system as a basis for g:n: rat:r tube ruptures, and small break when pumps are r-int operator decisions or actions. final '

Consequently, the Commissica has ,u,.,, . ..,u., u,h calibration loss of coolant events.The addition of a r:setor coolant inventory system. determined that an instrumentation data and proposed emergency procedure coupled with upgraded incere system for detection of ICC consisting of revisions, shall be submitted for NRC thernoccuple instruments and a upgrade subcooling margin nanitora, review and approval, and the task subcooling margin monitor, provides an com. exit thermocouples, and an analysis portion of the controlroom ICC instrumentati-2 package which inventory tracking of PWR sysgacilities.To . licensee.Pr6er ' mis reqmred for design review must be com '

could reduce signincantly the likelihood the operation to NRC approval, the

• cfinc:rrect operator diagnosis and assure that an acceptable systemis system may be md fo& pmpm of tnatalled as soon as practicable the operator training and familiarization errors f:r events such as steam generator tube ruptures, loss of - information descibed below andin - and may be used with peudence as instrument bus or control system upsets. Appendix A must be submitted to the talinput to plant operating pump seal failures, or overcooling NRC for review and approval. 'g[u cvents o ting from disturbances in III 6.%e licsnsee may request from *he the secon ry coolant side of the plant.

For low probability events, involving Am 14y. pursuant to Sections 103. submittals ofan Commission the extension of time for requimd information.

coir.cidental multiple faults or more 181L and 182 of the atomic Energy Act of 1954, as amended, and the Commission's . Such a request must set forth the rapidly developing small break LOCA conditions, the ICC instrumentation regulations in to CFR Parts 2 and 50, it is proposed schedule and justification for the delay.Such request shallbe directed could also reduce the probability of hereby ordered that Facility Operating to the Secutary of the bunnussion.U.S. .'

incorrect operator diagnosis and License No.DPR-50 is modified as NRC. Washington, D.C.20555. Any such subsequent errors leading to a degraded follows: request must be submitted atleast 30 core. 1.De licensee shallinstallanICC days prior to the date the information is m NRC has completedits review of instrumentation system consisting of -

j mquired.

several generic reactor level or =Wm' margin monitors, core-exit inventory system instrumentation thermocouples and a reactor coolant gy syst:ms which have been proposed for inventory tracking system all of which %e licensee may request a hearing on the detection ofICC in pWRs.The conform to the design parameters this Order within 25 days of the date of Combustion Engineering Heated specified in N_UREG-0737. Item ILF.2.

its publication in the Federal Register. A junction Thermocouple (HITC) system Installation of theICCinstrumentation request for hearing shall be submitted to cnd the Westinghouse Reactor Vessel syste'm shall be completed and made the Director. Office of NRR. U.S. NRC, Level Instrumentation System (RVLIS) operationalin accordance with the timetables approved pursuant to the Washington.D.C.20555. Copies of the cre cccIptable for tracking reactor request shall also be sent to the .

coolint system inventory and provide terms of this Order. Secretary of the Commission and the

(

an enhacedICCinstrument package 2. Within 90 days of the date of this (

' Order, the licensee must complete a Executive Legal Director at the same when used in conjunction with core exit address.

I thermocouple systems and subcooling conceptual design review for a reactor 8 If a hearing is requested by the margin monitors designed in accordance coolant inventory tracking system. licensee, the Commianlon willissue an  !

with NUREG-0737 and operated within identify the design selected and submit '

to the Director. Division of Licensing order designating the time and place of (

rpproved Emergency Operating any such hearing. If a hearing is held.

detailed schedules for engineering, 8 Procedure Guidelines.The details of the the issue to be considered at such NRC Staff review of these generic procurement and installation of the 8 syst ms are reportedin NUREG/CR- inventory tracking system. References to hearing shall be: Whether, on the basis generic design descriptfons, where of the matters set forth in Section II of t 2827 and NUREG/CR- 628 for the this Order, this Order should be Combustion Fngineering and applicable, are acceptable. r Within 90 days of the date of this sustained.

Westinghouse systems respectively.

OthIr differential pressure (d/p) Order, the licensee shall review the y [

measurement techniques for reactor status of conformance of all components 7' cool nt system inventory tracking are of the ICC instrumentation system with his Order shall become effective '

NUREG-0737. Item ILF.2. and submit a upon expiration of the period within a acceptable provided that they meet which a heanng may be requested or.if NUREG-0737 design requirements and report on the status of such C conformance. For your convenience in a hearing is requested, on the date

• monitor the coolant inventory over the range from theaeessel upper head to the performing the status review, a checklist specified in an onist issued following of the nine items of documentation cited further proceedings on this Order. ,

bottom of the hot leg as a rmmmum. For

j I? '

,. Federal Register / Vcl. 47. N . 246 / Wednesday. December 22. 1982 / N:tices

. 57165 i

, This requIst for inf:rmiti:n w:s sm:ndments dated August 30,1982, as result in any significant environmental approved by the Office of Management supplemented by letters dated October impact and that pursuant to to CFR and Budget under Clearance No. 3150- 29,1982 and November 19.1962, (2) 51.5(d)(4) an environmentalimpact i 0065 which expires on June 30.1983. Amendment Nos. 66 and 47 to Ucense statement or negative declaration and  ;

i Comments on burden and duplication environmentalimpact appraisal need may be directed to the Office of Nos. DPR-58 and DPR-74. and (3) the i Commission's related Safety Evaluation. not be prepared in connection with the ,

Men:gement and Budget. Reports and 1

All of these items are available for issuance of the amendment.  !

Management. Room 3208. New public inspection at the Commission's Executive Office Building. Washington. For further details with respect :o this I

" Pub!!c Doctanent Room.1717 H Street. action. see:(11 %e application for .

D.C. .

N.W Washington, D.C. and at the l . amendment dated July 6.1981 as Dated at Bethesda, Maryland. this 10th day Maude Reston Palenske Memorial supplemented November 22 and of D:cember 1982. Ubrary 500 Market Street. St. Joseph.

December 3.1962 (2) Amendment No.14' For the Nuclest Regulatory Commission. Michigan 49065. A copy ofitems (2) and (3)may be obtained upon request to Ucense No.DPR-22. and (3) the Robert A.N! Commission's related Safety Evaluation.

'#'8 / addressed to the U.S. Nuclear All of theseitems are available for

/ $#It kul ff Regulatory Commission. Washington. public inspection at the Commission's

"" "3 D.C. 20555. Attention: Director. Division

' Public Det ument Room.1717 H Street.

, of Ucensing. N.W Washington,D.C.and at the Dated at Bethada. Maryland, this ath day Environmental Ccuervation Library.

of December 1982. MSeapolis Public Library. 300 Nicollet

',,(Docket Noa. 50-315 AND 50-316 For the Nuclear Regulatory Commisalon. Mall. Minneapolis. Minnesota. A copy of L . i So.,,, 4, y ,,,, items (2) and(3)may be obtained upon  !

issuance of Amendments to Facipty Chief. Opemting /teoctors Bianch No. 2* request addressed to the U.S. Nuclear

, Operating Ucensee Dinsion off.icensins. Regulatory Commission. Washington.  ;

l Th2 U.S. Nuclear Regulatory

. D.C. 20555.' Attention: Director. Division l 2,,eeaa - . of Ucensing. A i

Commission (the Commission) has I

issu d Amendment No. 66 to Facility Dated at Bethuda. Maryland this toth day E Operating Ucense No. DPR-58, and of December.1sez. I

[Decket No. 50-2631 For the Nuclear Regulatory Comminion.

"8 States Power Co.;leeuence e se No. D -74 issued t th ' " A B. Vaasano. -

Ind1*.na and Michigan Elactric Company of to FacHNy Opereung Gef. O

' (the licensee), which revised Technical U**"** -

1. "#""Wns AsarMmach "# " &2 ,

Specifications for operation of D.C. The U.S. Nuclear Regulatory ***"*'**"*""I l Cook Units 1and 2(the facilities) Commission (the Commission)has 1 located in Berrien County, Michigan. o Issued Amendment No.14 to Facility j Th2 cmendments are effective as of the Operating Ucense No. DPR-22. Issued to l dat2 cfissuance. Northern States Power Company. which OM8 Review of Informadon % l

); '

The amendments revise the Technical revised the !! cense and the Technical NRC F. ors.1212. "Quanficatione

) Specifications to allow containment Specifications for operstron of the u ";_y, (p,,g n ,,,7 L purging during operation and to allow Monticello Nuclear Generating Plant Aomeev:Neclear Regulatory '

purge and vent modifications reqsired (the facility) located in Wright County, Commission. ' '

as part of the TMI Action Plan. .

Minnesota. ne amendment is effective n i,

Th2 application for the amendments AcTiose Notice of the Office of i as ofits date ofissuance.

czmplies with the standards and The amendment:(1) Approves the Management and Budget review of

'l requirements of the Atomic Energy Act information collection.

repair to the recirculation system piping

, of 1954. as amended (the Act), and the and authorizes resumption of power. suesesany:The Nuclear Regulatory Commission's rules and regulations. The subject to certain conditions, and (2) Commisalon has recently submitted to Commission has made appropriate changes the Technical Specifications to Bndings as required by the Act and the the OfCce of Management and Budget revise the Umiting Conditions for  ;

Commission's rules and regulations in 10 Operation and Survedlance (OMB) for review the following proposal l

l CFR Chapter I, which are set forth in tne Requirements for the coolantleak for the collection ofinformation under ~

licinsa amendments. Prior public notice detection system.

the provisions of the Paperwork '

of th:s2 amendments was not required The application for amendment Reduction Act (44 U.S.C. Chapter 35).

1. Type of submission, new, revision l

since the amendments do not involve a complies with the standards and O significant hazards considersdon. requirements of the Atomic Energy Act or extension: Extension. j Th2 Commission nas determined that of1954. as amended (the Act), and the 2. 'l'h Utle d b infomadd 1 the issuance of these amendments will Commission's rules and regulations. De co on om m n:t result in any significant Commission has made appropriate e, d don 4 environmentalimpact and that pursuant findings as required by the Act and the (Professional)"*

to 10 CFR 51.5(d)(4) an environmental Commission's rules and regulations in 10 3.The NRC imprct statement or negative CFR Chapter I. which are set forth in the Fom 21Jos numberif applicable:

i dIci: ration and environmental impact license amendment. Prior public notfce 4. How often the collection is  !

sppraisal need not be prepared in of the amendment w:.. ' tot required required: when an applicant is connsction withissuance of these since the amendment does not involve a considered for employment.

amendments. significant hazards considera tion. 5. Who will be required or asked to For futher details with respect to this The Commission has determined that l report: Previous supervisors and action. see (1) The application for the issuance of this amendment will not personal acquaintances.

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