ML19248D385

Summary of 790611 Meeting Re Open Items & Proposed Changes for TMI-1 Restart

ML19248D385
Person / Time
Site:	Crane
Issue date:	06/28/1979
From:	Diianni D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7908150717
Download: ML19248D385 (35)

Text

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[f$eq, UNITED STATES

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7 NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D. C. 20555 k

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June 28, 1979 Docket No. 50- N9 g_.,....-_...---

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>--, m LICENSEE: METROPOLITAN EDISON COMPAtlY (Met Ed/GPi'SC)

FACILITY-THREE MILE ISLAND UNIT NO. 1 (TMI-1)

SUBJECT:

MEETING

SUMMARY

ON THE JPEN ITEMS REGARDING TMI-l RESTART On June 11, 1979 the TMI-l licensee met with the NRC staff to discuss open items and proposed changes for restart of TMI-1.

A list of attendees is enclosed.

The subject matter presented by the licensee is as follcws:

(a)

Retraining Program (b)

Procedure Changes (c)

Plant Modifications (d)

Emergency Plan (e)

Safety Analysis & Studies A summary of tnese items is as follows and further details on the presentation concerning these topics are attached.

Retraining Procram The licensee committed to retraining aoproximately 40 reactor operators needed to cover the coerating shifts.

Furthermore, the licensee committed to have a degreed engineer present during plant operation to assist the shift supervisor.

As part of the retraininc programs, the operators will be taking college level technical courses in fluid flow, heat transfer and Thermodynamics.

The staff indicated :he qualification of the instructors for these courses should be addressed.

The licensee was also advised to contact the NRC Coerating Licensing 3 ranch regarding the content of the technical courses for ne coerators.

A criterion for retraining ocerators should De developed and be made cart of tne restart recort.

The crocosed schedule for retraining snows the NRC examination 7 90815vlO P

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period starts August 10, 1979 and to last for one week.

NRC will consider this reauest with resoect to other commitments for this period.

Procedure-A total of 80 to 100 procedures are scheduled for review and revision as necessary to meet the critieria presented in the encloadre (Procedure Changes).

The procedure review is being completed at an approximate rate of 3 per day and the licensee plans that the procedure reviews will be completed by the end of July 1979.

The staff indicated that some of the procedures will be reviewed by the NRC staff and that the training schedule should reflect possible changes to the procedures as a result of the NRC review.

Modifications The licensee proposed plant modifications some of which were committed to be completed prior to reactor restart and the remaining modifications to be completed as soon as practicable (See Enclos.ure 5 ).

The licensee committed to stucy the feasibility of install.ag reactor vessel level indication as well as remote (from outside containment) reactor vessel ventino.

The licensee also committed to resolving the problem of containment curce.

Presently the licensee has committed to a valve analysis instead of 1imiting purging to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year.

Emeraency Plan The licensee proposed to make changes to the emergency plan covering those items over which the licensee has direct control.

The existing emergency olan submitted to the staff appears to be inadequate as to the death of details existing in the plan.

The licensee was requested to review Reg. Guide 1.101 in this regard.

It was agreed that staff would discuss with the licensee the require-ments in this area.

However, reapproval of the emergency plan would be required prior to restart.

Safety Analysis & Studies The licensee plans to review certain of the existing safety analyses as outlined in Enclosure 8.

fhis review is expected to be completed prior to the restart of T'iI-l.

Staff Ccments & Future Plans It was agreed to have a meeting during the week of June 25th (actual date to be established) at the site to discuss the future efforts on the TMI-l restart.

Althougn an agenda was discussec it will be finalized before tne meeting.

It was indicated that it is likely that tnere will be a public meetinq near the site wnere tecnnical issues are discussed with the oublic.

The questien of 3 oublic nearing will be cetermined.

The cuestion of T'41-1/TMI-2 onysical separation during all ooer3 ting moces of the Ovo units.vould need to be addressed.

The cojective is that operatinc concitions of both units will not af fect eacn other due to croximity and/or commonality of service facilities.

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f A complete response to the bulletins may not be necessary. The staff will give the licensee guidance as to those specific items to be covered in the bulletins.-

i Conclusion

~

The licensee indicated that according to his schedule he o ld be ready for restart about August 15, 1979.

These discussions resulted in no agreements or cotr.aiteents by the staff ~

regarding any aspect of the 1NI-1 restart.. The basis upon which TMI-l would be allowed to restart, and the associated schedule, have not yet been established.

~

s Original signed by

~

D. C. Dilanni, Project Manager Operating Reactors Branch !4 Division of Operating Reactors

Enclosures:

1.

List of. Attendees 2.

Agenda

^

3.

Retraining Program 4.

Procedural Changes 5.

Control Modificctions 6.

Studies Required Prior to Restart 7.

Emergency Plan 8.

Safety Analysis cc w/ enclosures: See attached list

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Enclosura 1 TMI-1 Restart Meeting June 11, 1979 Attendees Name Orcanization D. C. Dilanni f4RC Harley Silver R. H. Vollmer H. R. Denton Darrell Eisenhut Brian Grimes Bob Capra Bob Reid T. M. Novak Lawrence Chandler G. R. Klinger H. B. Kister John R. Sears Peter Tam H. Dieckamp GPU R. C. Arnold R. W. Heward, Jr.

E. G. Wallace D. G. Slear R. F. Wilson J. G. Herbein MET ED J. L. Seelinger A. Tsaggaris George F. Trowbridge SHAW, PITTMAtl (Counsel)

W. P. Cornsife PA DER AG:TA It1TRCDUC~ICN At0 CVERVIEW R.C. ARNCL-)

TRAINING J. L.SEELINGS

RCCEEDURES J. L. SEELINGS PLANT l'CDIFICATICNS D.G.SLEAR EMERGENCY FLAN A.TSAC M IS SAFET/ ANALYSIS E.G.WALLACE e

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TPI-l It!STPL' met!Ti'T. ION FDDIFICATIOi!S PRIOR TO RESTART

___._.._.h0)iJECT DESCRIPTION l;ib i k uM EllT AT I ON If1 SIDE

• UPGRADE Tile RELIABILITY OF INSTRUMENTS AtJD VAI.Yl'.

, f'ff)ll)

Lulli Alt liEtif OPERATORS It4 SIDE CONTAINMEtJT BY Tile ADDIT 101: OF l

IIEAT SilRINK TUBillG TO it1 PROVE WATERTIGitTilESS.

f r

• RAISE OTSG' LEVEL TRANSMITTERS (LTL LT2, LUI) i o,.

liffd HEIGilT OF 72 INCllES ABOVE Tt!E CONTAINMEllT LA$i.f:i ifi FLOOR.

I l

I IflCORE IllERM0 COUPLES

• COMPLETE TERMitJATION OF CR-AL l tJCURE THEfm0COUPl.1 '

TO Tile CONTAINMENT PEtlETRAT10fl.

([2M'l)

• ll00K-UP A MINitAUM OF 16 :2E! FCTED 5 :- 00HES TO Tile I

COMPUTER PRIOR TO RESTART.

• PROVIDE WIDE rat 4GE (UP TO 2300* F) READOUT ON D/,l A LODGER.

I CollTAlf4 MENT ISOLATION

• MODIFY WIRING AND TERMillATIOrls TO i ttl TI AT L ISOLATlull l

OF ALL LINES WiiOSE ISOLATION DOES fl0T DECRADE Coki.

l (fE'lWS)

COOLING CAPABILITY UP0tl AUTOMATIC lillTI AT10tl Of l

lil G H PRES 50RE If1 JECT 10N.

i I

c.

c.

[

SUBJECT DESCRIPTION lisiflROL Ruoll VALVE POSITION f0R VALVE POSITION Ir1DICATION TilAT IS DEiGiln Vict IllDICATIOld ACTUAL, f1AKE A CONSCIOUS DECISION of; WillCI: iO e

bu' CilANGF; TO A,CTUAL POSITION OR PROVIDE I ND i C Ail isi:

'l J l

OPERATOR TilAT Tile POSITION IS liEMAND VICE ACTUAL.

l

[UMPilTER

- ELif11tJATE BACKLOGGI NG IN Tile Cof1PilTER OF AL ARM f

(j2M-7)

MESSAGES DUE TO OllTPUT LIMITS OF 855 SELECTRIC I

TYPERS.

j IMPPOVE RELI ABILITY OF COMPUTER OUTPilT ALARt1 TilRollGli REDUNDANT TYPERS.

l 1

i l

POWER OPERATED RELEIF VALVE

• RAISE Tile SETPoltiT To 2/ 50 PSIC SO THAT ANTIC 1PA fl 0 1

ld)

TRANSIENTS DO NOT OPEN POO\\'.

PO!!V POSITION INDICATION

• REPLACE CURRENT PORV POSITION I ND IC AT l atJ IN litt.

C0rlTROL ROOM WITil POSITIVE I t1D I C AT 10N.

liiE I Nii l C A -

0'Ih TION SilALL BE CAPAllLE OF UNAMBIGl10llSLY DETECTit.G r

WilEN VALVE IS STUCK OPEN.

s.

t '

h

TMI-1 SYSTEI1 MODIFICATIONS PRIOR TO RESTART SilBJECT DESCRIPT10N I

l11LCAYll EAT

• MODIFY Tile DECAY llEAT SYSTEM TO PROVIDE FOR (121M-7-)

MONITORING AtJD MAINTEtJANCE FROM A REMOTE LOCAT;urt, I

• MINIM 11E PERSONNEL EXPOSURE.

~

• ENHANCE RELIABILITY.

I i

l li'il-2 NEACTOR COOLANT SAMPLING

• PROVIDE A NEW tiUCLEAR SAMPLING FACILITY FOR I Ml

'l i

p,.

SO TilAT NORMAL OPERATIONS OF If.1 -l MILL Nu f it' DISRUPTED BY TMI-2 RECOVERY OPERATION SAMPLirin.

l llYDROGEN NECOMBif1ER PROVIDE PERMANENT ll2 R ECOMb l NER INSTALLA110N lt;CLUOlih.,

(Filt-i2)

PIPING AND MANUAL VALVES BETWEEll RECOMHitiER AllD C ONTA I NMEtlT.

l i

![MER6ENCYFEEDWATER (Pm 3)

F0tt0 Wing LOSS Or Il PCP'S OR LOSS OF aorti FEEN eutus.

• PROVIDE FOR AUTO.lNITI ATION OF MOTOR DRIVEft Efil I

! li Gil PRESSURE IllJECTION

• COMPLETE illE APPRGVED SMALL BREAl; LOCA MODIFICAT10:1 hAlpl/

TO T!IE llPI SYSTEM BY Tile ADDITION OF CROSS CONN!?CT:

2

. ci AND NEW VALVES.

,x;,

4

TI'.I-l INSTRUf1Ef! TAT 10i f 0DIFICATIONS AS S00il AS PRACTICAL SultlECT DESCRIPTION INSTRilMErlTATIOfi ItJSIDE

• RAISE PRESSURIZER LEVEL TRANSMITTERS (LT1, l.T'/

l.14) l u)fD AINMENT TO A liEIGilT OF 72 INCllES All0VE Tite C0f0 AlllMElll t

BASEMENT FLOOR.

i INCORE TilERM0 COUPLES

(,, }

• HOOK-UP ALL 52 INCORES TO THE COMPUTER.

I COMeuTER PROVIDE A MEANS FOR OPERATOR TO CALL UP AtiD DISPIAY l

!!SSS RELATED DATA IN GRAPillC TREND OR FIXED F.ORMAT.

i i

i RCS SATURATION Ik\\RGIN I'OrilTOR

• ALARM, II;DICAT10fl AND TREt!DII G OF Tile 11ARGI N lo s ei, LIMITING SATURATI0t C0tJDIT10tl Irl Tile REAtt0R CoolAct SYSTEM.

CONTitiUOUS DISPLAY OF Tile REACTOR C00Udi f i

l SYSTEM SATURATI0ti IIARG!tl ill TERMS OF PSI (OF) MAI.Gil:

TO Tile PLANT OPERATOR.

i l'

I

{

RCS II:MPERATURt

• lilCREASE Tile RANGE OF liOT LEG AND COLD LEG TEMPT:HAitiin f

IN Tile COMPUTER.

m e

i i

e, I

Tiil-1 SYSTEM F0111FICATICES AS S00fl AS PR/,CTICAL

___... 591M[_CT DESCRIPTION lu.'ST EWi rCuoveR AUTOMATE Tile SWITCil0VER FROM TiiE DWST 10 rnE l

C0flTAINMEf1T SUMP FOR LPl RECIRCULAT10tl POST-LOCA.

i.

l c

l WASTE CAS IAllK VENTit1G

• PROVIDE PIP!NG AND VALVES NECESSARY TO VEUT WAST.'

(Lan-s)

/

{

GAS TANKS llACK TO CONTAINMENT.

l I!L AC TOP l',U I LD I NG SPRAY

• MODIFY PIPING TO PROVIDE EQUAL DRAWDOWN OF SWEl A!;D SYsTut (b M ' 7) flA0ll TANK UNDEf< ALL SINGLE FAILURE CONDITIONS.

I l

• I)ELETE SODIUM TH10 SULFATE ADDITiori.

l l

l!lllLDING COOLING (/D-/2)

• RESOLVE PROBLEMS WITH WATER SEALS ON lIEACTUR fArtflOTORS i

I i

l UEL llAfil)L li.G llU I LD I f1G

$\\-lG)

• l!UILD AN AIRTIGitT BARRIER TO S EPARATI: TMI 1 FilP, I

FRot Ifll-2 IN ORDER TO PRECLilJE AIRBOUlf dLEASES I

AT TMl-2 FROM CONTAMINATING Ifil-1.

s

i. _ _ -. _ _ _

l

. I SuluECT DESCRIPTION l _ ___ _ __ _

CONCRETE COATING

• Tit 0ROUGitLY COAT CONCRETE Ill Tite CONTAlflf1Efl1 AND l

i Lui-Ib)

' ' +

AUXILIARY BUILDING LOWER LEVELS It! ORDER To l'Ra'Llili:

i PEtJETRAT10f1 EY CONTAMl HATION,

l i

l CofifAlf4MEfJT SUMP FATER

• PROVIDE WATER LEVEL MEASUREt1ENT CAPABILITY l

,n g; (0'-10' t 2") WITiiOUT OPENING CONTAlt4MEf1T ISOLATION i

j VALVES.

l i

l l

• PROVIDE A SAMPLING CAPABILITY F,0R C0tlTAlflMEi1T SufiP I

i WATER.

l 4

l i

l I

i l

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i y1 O_......_.____

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4

'lHI-l STUDIES e

ItEQillitED PRIOR TO RESTART i f, I;tillllEP.

SU11J ECT DESCRIPTIO!i RS-1 1.0CA Determine if safety analyses have adequately addressed specific locations of 1.0CA.

Review proposed THI-l small break fix.

l',,B c.

RS-2 Containment} Isolation Evaluate the need f or a iditional containment isolation signals. Evaluate the ui.aquacy of, existing signals.

.r RS-3 Post Accide'nt Hoaltoring a)Evaluateextendedrangereadoutsfoh'existingqualified equipment.

b) Evaluate addition of new instruments for post-accident monitoring.

c) Review and evaluate signale currently connected to transient monitor.

RS-4 Cc.id Shutdown Review ins'.rumentation and equipment.aquired to achieve cold ahutdown. Ensure the equipment is adequate for l.0CA/llSI.B environmental conditiens and if neccusary, watertight. Raise elevations if necessary.

It s-5 Preusurizer Relief Valve Position Evaluate how to provide indication of instrumentation for detecting Icaking/ stuck open valves. Consider existing temperature detertors, relocated RTD's, differential pressure fim ir.dication, thermal flow switches and

't acoustico.

'<"h.'

m u.

3 t,

'f' RS-6 Vulve Position Indication Evaluate the need for position indication in control room S

o on valves currently not indicated in the control room.

p 3

i

i. ; N;

fi'b@!-y.., by.; d.! o,,, J i,; a.,,: q. G,, 3.l...p..d! j ps., i o, n .i .p e,.,

,0 e I F--~~' - - - tattlutk Sull.I ECT DESCRIPTIO!! 5 -7 Itudiation ilonitoring Evaluate installed inplant radiation,sionitoring capability with regard to range, location, filter statua determina-ti 1 .i-Lion, etc. ,, j, q' (. '? 6,i, ... n. '1i It S -8 Contaliunent Normal Cooling Review upgrading the containment normal' coc?; 9 system and the leak tightness of systems in'contaipa.ent to .t improve operating environment with. Vent; and Purge Valves continuously closed.

7..

a, ., s I It S-9 Pol (V Iteliability Assess the reliability of the PORV. l<S-10 Pressurizer Vent Valve Evaluate the need for alternate power for the 12ressurizer Vent Valve operatora, liS-l l Pressurizer Code Safety Valves Evaluate the capability of Pressurizer Code Safety Valves to pass adequate water during solid plant operation. itS -12 lleactor Drain Tank Reassess the rupture disc set pressure on the reactor drain tank ami see if it should be replaced by a higher p: essure device. 1(S-13 Contaltunent lluilding Sump Water Evaluate the potential for boron dilution in containment building sump water during DilA's. Determine the need for mixing capability and/or the capability to provide higher boron concentrations in sump water. w sc e-l 8

• 1 a_

NJ s' 't ,p t ________7

-3 !;II.MiiER Sul!J ECT DESCRIPTION 1(S-14 Decay lleat System iteview the decay heat system with respect to the Design !! asis Accidents and other anticipated operating conditions. Consider the following: 1 1 ~ a) Added shielding to protect componenta_ or personnel. 8 o. b) Remote TV monitorlug. ,, [!n.., .d '., ~ l l' [ c) Hove trant>mitters out of Dit pump Soom. I. :1 d) have radiation anonitors away.from Dll pits. ' I;' e) Ventilation changes to minimize offsite exposure. l f) Ventilation changes to minimize the spread of con-tamination and airborne release. g) Collecting seal Icakage in a manner that minimizes noble radioactive gas releases. 1(S-I S Emergency Feedwater System Provide or review a single failure analysis of the installed syste:a, evaluate deviations and make recoimaenda-tions. RS-16 THi-1/THI-2 Shared Systems Evaluate the systems shared between THI-1 and THI-2 and ' the need to provide separation prior to restart and/or in the long term. RS-17 Spent Fuel Pool Cooling-Review stattes of spent fuel pool cooling line leakage. P What repairs should be made prior to restart? sC y I ,,'l,'..j' ' l 8 NO 4 ( i CO

s r'---- !:U::bl_R SuliJ ECT DESCRIPTION R S-I ts Containment Building Temperature Review location of contaisunent building atmosphere moattoring thermocouples and verify that the technical specification limit to a.hutdown at 130*F average containment temperature can be based on the installed thermocouples. f f. ' il s a g ItS-19 Cowlenser Off Gas Filter' Evaluate the need to add a condenser'off gas filter to THI-1. 3 RS-20 lustrument Air Evaluate the status of Instrument Air at THI-1. Are we providing clean / dry instrument air? HS-21 Heactor Coolant Pump Power Fvaluate the need to inove the surge suppression capacitors outside containme t to improve RCP reliability. RS-22 Llaute Gas System Evaluate the need for making more sensitive leak checks of the system. 9i I g g . i h N[ .Z: ,(;., ' N1 g g NO

/ / + ~ 1 EMERGENCY PLUT NRC Y.eeting: June 11, 1979 , : q .. i I '; s 8 J /

I. ORGANIZATION - Four Phase Approach A. Phase I - on shift comple=ent 3. Phase II - Emergency Organization as defined in the current Emergency Plan C. Phase III'- Met-Ed/GPU =anned organi:ation that would mobilize and staff an off-site e=ergency control station 1. HP Support a. TLD Control b. Environmental sa=pling, analysis and effluent assessment c. In-plant sample coordination d. Manpower corrdination 2. Cc==unication sackup 3. Maintenance - manpower coordinatica 4. Logistics Coordination - cocpany and non-company resources 5. Security - badging and plant access 6. Ad 194*trative 2upport D. Phase I7 - Comprehensive organization to coordinate all aspects of a long ters accident recovery 1. Plant Operation 2. Waste Manage =ent 3. Plant Modifications 4. Technical Support 5. Technical Working Group ~ ~ 6. Task Manage =ent/ Scheduling 7. Ad=inistration and Legistics 8. Public/ Government Affairs li '01

e 4 + II. .:CMMUNICATIONS EQUIPMENT UFCRADE A. Control Rooms ~ 1. Direct line to NRC 2. Hot line to off-site emergency control center 3. Additional outside lines 4. Multiple conference call capability 5. Independent lines to Met-Ed/GPL3C Manage =ent B. Off-site E=ergency Control Center - Primary and Backup 1. Radio capability 2. Hot lines to each control room 3. Multiple dial telephone capability C. Other 1. Spli ops. and Security frequencies 2. Improve =enitoring team equipment 3. Tape recording capability III. D'ERGENCY EOUI?ME.NT A. Radiation Monieoring Team Kits 3. Inverters C. Respirators D. TLD's - including off-site reading capability I. Portable GELI 7. SC3A's or plug in air system 17. C00RDI'!ATICN OF INDUSTRY RESOLTCH A. Identif7 specific resources (naterial and nannover) required for accident support h 4 ys 3. Obtain Letters of Agreement E' / k b

.- / 9 V. COMMI.NICATIONS A. CD, State Agencies, Local'Com= unities 3. Release of Information to Public .C. NRC 5 VI. 'ND !.. Develop EMERGENCY PREPAREDNESS PLAN 3. Train personnel 4-C. Conduct exercises w m-9 Ao

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f Enclosure 7 EMERGENCY PLCI ';2C ' ae:ing : June 11, 1979 f f) .. f,) 'n,_ o n ( t

a I. CRCANIZATION - Four Phase Approach A. Phase I - on shift co:ple=ent 3. Phase II - Emergency Organi stion as defined in the current E=ergency Plan C. Phase III - Met-Ed/GPU =anned organi:stion that would cobilize and staff an off-site e=ergency control station y NN 4 1. HP Support a. TLD Control b. Environ = ental sa pling, analysis and ef fluent assessment c. In-plant sample coordinatien d. Manpower coordination 2. Cc==unication backup 3. Maintenance - =anpower coordination 4 Logistics Coordination - cocpany and non-co pany resources 5. Security - badging and plant ac ces s 6. Ad=inistrative Support D. Phase !? - Cocprehensive organization to coordinate all aspects of a long ter accident recovery r. p p [3.' ' l. Plant Operation 2. '4aste Management 3. Plant Modifications 4 Technical Support J. Technical Jorking Group 6. Task Management /Schecuiing 7. Administration anc Logistics 3. PubIic/Gevernment Affairs r I - h.Je c..

o II. COMMUNICATIC;jS ECUIPME';T UFCRADE A. Control Roc =s 1. Direct line to NRC 2. Hot line to off-site emergency control center 3. Additional outside lines ~ !'7 8 b5

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4. Multiple conference call capability 5. Independent lines to Met-Ed/G?USC 'itnage ent 3. Off-si te Energency Centrol Center - ? inary and 3ackup -.r l. Radio capabill:7 's- _ - _3 2. Hot lines to each control rocs 3. Multiple dial telephone capability C. Other 1. Spli: 0?s. and Securi:y frequencies 2. I: prove Ocnitoring team equipment 3. Tape recording capability III. EMERGENCY ECUIPMENT A. Radiation Monitoring Tea: Kits 3. Inverters C. Respira: rs D. !!.D's - including off-site reading capability E. Fortable GELI F. SC2A's or plug in air system 7. COCED: NATION OF ::"DUSTRY RESCURCIS A. Identify specific resources (= :erial and sa pcwer) required for accident support 3. Obtain Le::ers of Agreenen f,i ,4 .1) G /

o V. _COMMLNICATIONS lAtpm#w2 A. CD, State Agencies, Local Cc= unities O by,j, 3. Release of Infor=ation to Public C. NRC VI. MErdOD A. Develop.W.ERGENCY PREPAREDNESS PIXi 3. Train personnel C. Conduct exercises I p

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Enclosure 8 SArrTY '"*LY1:S I. Reviewed :he 2:11-1 Safety Analysis to: A. Deternine where operator action was essential to the conple:1on of response; B. Dete::ine where plant c;;anics =ay ef fect the current bounding analyses, II. Concluded that the Eollowing Analysis chould be done: A. Loss of Feeduatar - to review changes to AFW systeca and operator actions. 3. Loss of Off Site Power - to review changes to AFW systens and transition :o Na: ural Circulation Ir. Safety Analysis Review of 35W Snall 3reak LOCA and Transient Analysis Reports 1. Revieu to insure it reflects the I:!I-l plant design 2. Review :o insure appropriate operator guidelines are reflected in procedu:es. IV. Modify the Snall 3reak LCCA Analysis :o Reflec: H?! Crocs Connect odifications. 1 It s

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MEETING

SUMMARY

, DISTRIBUTION OR884 Mr. J. G. Herbein Vice President Metropolitan Edison Company P. O. Box 542 coading, Pennsylvania 19640 William P. Dornsife Department of Environmental Resources Bureau of Radiological Health Division of Nuclear Reactor Review P. O. Box 2063 Harrisburg, Pennsylvania 17120 Docket File R. Reid NRC PDR V. Noonan L PDR P. Check ORBd4 Rdg G. Lainas NRR Rdg G. Knighton H. Denton E. G. Case Project Manager OELD V. Stello 01&E (3) D. Eisenhut R. Ingram R. Vollmer W. Russell R. Fraley, ACRS (16)

8. Grimes Program Support Branch TERA T. J. Carter J. R. Buchanan A. Schwencer D. Ziemann Meeting Summary File T. Ippolito NRC Participants Peter Tam W. Gammill L. Engle D. Ross I

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