ML17334B398

Summary of 910124 Meeting W/Indiana Michigan Power Co at NRC Headquarters Re Licensee Implementation of Reg Guide 1.97 Recommendations & Detailed Presentation Re Steam Generator Wide Range Level Instrumentation Upgrade.Viewgraphs Encl

ML17334B398
Person / Time
Site:	Cook
Issue date:	03/07/1991
From:	Brian Holian Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9103140043
Download: ML17334B398 (41)

Text

March 7, 1991 Doc'ket No. 50-315 and 50-316 LICENSEE:

Indiana Michigan Power Company FACILITIES:

D.

C.

Cook Plant

SUMMARY

OF MEETING WITH INDIANA MICHIGAN POWER COMPANY January 24, 1991 - Regulatory Guide 1.97 Implementation Representatives from Indiana Michigan Power Company met with the staff at NRC headquarters on January 24.

A list of meeting attendees is provided as Enclosure 1.

Topics of discussion included the licensee's implementation of Regulatory Guide (RG) 1.97 recommendations (status and schedule),

followed by a

more detailed presentation concerning the steam generator wide range level (SGWRL) instrumentation upgrade.

The meeting handout is provided as Enclosure 2.

The SGWRL instrumentation upgrade was originally scheduled for D. C. Cook' 1992 outages.

Due to the scope of the modification, coupled with extensive containment walkdowns which are necessary early in the design process, D. C.

Cook requested that installation of the upgraded instrumentation be deferred to the refueling outages following the 1992 outages.

The staff expressed concern that a design and modification process of this scope (a relatively small scope modification) would need such an extended scheduled.

Much of the meeting was spent understanding Indiana Michigan's design engineering

process, and the complexities of the containment walkdowns which would warrant an extension of their schedule.

The containment walkdowns are critical to ensure that the modification is planned correctly, and that the requisite materials are properly ordered.

The staff accepted the licensee's position that the modification process would be best served by performing the containment walkdowns early in the design process.

However, the staff felt that the licensee should commit to perform the containment walkdowns at the earliest outage of sufficient duration; thereby, expediting the design process and allowing completion of the modification at the earliest date possible.

The SGWRL instrumentation upgrade is the final RG 1.97 modification necessary for the D. C.

Cook plant.

The staff, with the condition noted above, finds the schedule for the SGWRL modifications acceptable.

/s/

Brian E.,Holian, Project h1anager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1.

Meeting Att hdees 2.

Meeting H

dout DISTRIBUTION D

NRC 8

LOCAL PDRs BHOLIAN FMIRAGLIA JPARTLOW OGC RLOBEL BBOGER EJORDAN LA/PD31 DRP345 PM/PD31:DRP345 PSHUTTLEWORTH BHOLIAN 3/0/91 A/)

3/5 /91 4i0314 043 '710307 PDR ADOCK 050003i5 P

PDR RSTRANSKY BMARCUS LMARSH SICB BMARCUQg/f7 3/ T/91 JZWOLINSKI ACRS(10)

D/PD31: DRP345 LMARSH

/7/91 (pg CABBATE SHANNON

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March 7, 1991 Docket No. 50-315 and 50-316 LICENSEE:

Indiana Michigan Power Company FACILITIES:

D.

C.

Cook Plant

SUMMARY

OF MEETING WITH INDIANA MICHIGAN POWER COMPANY January 24, 1991 - Regulatory Guide 1.97 Implementation Representatives from Indiana Michigan Power Company met with the staff at NRC headquarters on -January 24.

A list of meeting attendees is provided as Enclosure 1.

Topics of discussion included the licensee's implementation of Regulatory Guide (RG) 1.97 recommendations (status and schedule),

followed by a more detailed presentation concerning the steam generator wide range level (SGWRL) instrumentation upgrade.

The meeting handout is provided as Enclosure 2.

The SGWRL instrumentation upgrade was originally scheduled for D. C. Cook' 1992 outages.

Due to the scope of the modification, coupled with extensive containment walkdowns which are necessary early in the design process, D. C.

Cook requested that installation of the upgraded instrumentation be deferred to the refueling outages following the 1992 outages.

The staff expressed concern that a design and modification process of this scope (a relatively small scope modification) would need such an extended scheduled.

Much of the meeting was spent understanding Indiana Michigan's design engineering

process, and the complexities of the containment walkdowns which would warrant an extension of their schedule.

The containment walkdowns are critical to ensure that the modification is planned correctly, and that the requisite materials are properly ordered.

The staff accepted the licensee's position that the modification process would be best served by performing the containment walkdowns early in the design process.

However, the staff felt that the licensee should commit to perform the containment walkdowns at the earliest outage of sufficient duration; thereby, expediting the design process and allowing completion of the modification at the earliest date possible.

The SGWRL instrumentation upgrade is the final RG 1.97 modification necessary for the D. C.

Cook plant.

The staff, with the condition noted above, finds the schedule for the SGWRL modifications acceptable.

/s/

Brian E. Holian, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1.

Meeting Attendees 2.

Meeting Handout DISTRIBUTION NRC

& LOCAL PDRs BHOLIAN FMIRAGLIA JPARTLOW OGC RLOBEL BBOGER EJORDAN LA/PD31:DRP345 PM/PD31: DRP345 PSHUTTLEWORTH BHOLIAN 3/f/91 3/5 /91 RSTRANSKY BMARCUS LMARSH SICB BMARCU~

3/ T/91 JZWOLINSKI CABBATE ACRS(10)

SHANNON D/PD31:DRP345 LMARSH g 3/7/91 ghr)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 7, 1991 Docket No. 50-315 and 50-316 LICENSEE:

Indiana Michigan Power Company FACILITIES:

D. C.

Cook Plant

SUMMARY

OF MEETING WITH INDIANA MICHIGAN POWER COMPANY January 24, 1991 - Regulatory Guide 1.97 Implementation Representatives from Indiana Michigan Power Company met with the staff at NRC headquarters on January 24.

A list of meeting attendees is provided as Enclosure 1.

Topics of discussion included the licensee's implementation of Regulatory Guide (RG) 1.97 recommendations (status and schedule),

followed by a more detailed presentation concerning the steam generator wide range level (SGWRL) instrumentation upgrade.

The meeting handout is provided as.

The SGWRL instrumentation upgrade was originally scheduled for D. C. Cook' 1992 outages.

Due to the scope of the modification, coupled with extensive containment walkdowns which are necessary early in the design process, D. C.

Cook requested that installation of the upgraded instrumentation be deferred to the refueling outages following the 1992 outages.

The staff expressed concern that a design and modification process of this scope (a relatively small scope modification) would need such an extended scheduled.

Much of the meeting was spent understanding Indiana Michigan's design engineering

process, and the complexities of the containment walkdowns which would warrant an extension of their schedule.

The containment walkdowns are critical to ensure that the modification is planned correctly, and that the requisite materials are properly ordered.

The staff accepted the licensee's position that the modification process would be best served by performing the containment walkdowns early in the design process.

However, the staff felt that the licensee should commit to perform the containment walkdowns at the earliest outage o'f sufficient duration; ther eby, expediting the design process and allowing completion of the modification at the earliest date possible.

The SGWRL instrumentation upgrade is the final RG'.97 modification necessary for the D.

C.

Cook plant.

The staff, with the condition noted above, finds the schedule for the SGWRL modifications acceptable.

Enclosures:

1.

Meeting Attendees 2.

Meeting Handout Brian E. Holian, Project Manager Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Mr. Gerald B.

S lade Consumers Power Company Palisades Plant CC:

M. I. Miller, Esquire Sidley

& Austin, 54th Floor One First National Plaza Chicago, Illinois 60603 Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue

Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Hichigan Avenue

Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Jerry Sarno Township Supervisor Covert Township 36197 H-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. David J.

Vandewalle Director, Safety and Licensing Palisades Plant 27780 Blue Star Memorial Hwy.

Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Commission Palisades Plant 27782 Blue Star Memorial Hwy.

Covert, Michigan 49043 Nuclear Facilities and Environmental Monitor ing Section Office Division of Radiological Health P.O.

Box 30035 Lansing, Michigan 48909 Gerald Charnoff, P.C.

Shaw, Pittman, Potts

'rowbridge 2300 N. Street, N.W.

Washington, D.C.

20037 Mr. David L. Brannen Vice President Palisades Generating Plant c/o Bechtel Power Corporation 15740 Shady Grove Road Gaithersburg, Maryland 20877

ENCLOSURE 1

MEETING ATTENDEES JANUARY 24, 1991 D.

C.

COOK NRC AFFILIATION PHONE

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" ENCLOSURE 2 DONALD C -" COOK NUCLEAR PLANT REG-GUIDE 1 - 97 SAFETY EVALUATION REPORT STEAM GENERATOR NIDE RANGE LEVEL UP GRADE DE S IGN CHANGE IMPLEMENTATION ACTIVITIES) SCHEDULE Washington January 24, 1991 XcldXNRCX0200.WP

Nl

1 ) STATUS OF CURRENT REG GUIDE 1 - 9 7 COMPLIANCE =

NUMBE R OF PARAMETERS MODIFIED ENGINEERXNG 6c DES XGN MANHOURS EZP ENDED FUNDS EXP ENDED 2 ) EZISTING CONF IGURATION OF WXDE RANGE S TEAM GENE RATOR LEVEL CONFIGURATION RATIONALE FOR ORI GINAL

• POS ITION 3 ) PROPOSED UPGRADE OF SGWRL CONTROL ROOM AUZ BUILDING ELECTRICAL IN CONTAINMENT ELECTRICAL IN CO'NTAINMENT MECHANICAL LEVEL OF DIFFICULTY REG -

GUIDE 1

97 COMPLIANCE AFTER SGWRL MODIFICATXON 4 ) IMPLEMENTATION ACTIVXTIE S ENGINEERING DES XGN CONSTRUCTION 5 ) IMPLEMENTATXON SCHEDULE 6 )

SUMMARY

Washington XcldXNRCX0200.WP

EZXSTING STEAM GENERATOR WIDE RANGE LEVEL INSTRUMENTATION CONFIGURATION

( One Unxt descry bed typ9 ca 1 for bot h )

ONE

( 1 )

CHANNEL PER S iG-TOTAL OF FOUR CHANNELS AVAXLABLE NON SE ISMICALLY QUALIFIED INDICATORS AND RECORDERS-TOTAL OF EIGHT

( 8 ) INDICATORS AND TWO

( 2 )

RECORDERS IN THE CONTROL ROOM

( FOUR INDICATORS ARE ON THE HOT SHUTDOWN PANEL )

REMOTE INDICATION AND POWER SUPPL IE S ARE PROVE DED IN LOCAL SHUTDOWN

( LSI )

PANELS FOR APPENDIZ R CONCERNS THESE ARE NONSAFETY RELATED AND ARE NORMALLY NOT SWITCHED INTO THE CIRCUIT -

ISOLATXON IS PROVIDED BY THE MANUAL SWITCH ON THE LSI PANELS NORMAL POWER SUPPLY IS PROVIDED FROM THE FOUR

( 4 )

CRID' EACH CHANNEL POWER SUPPLY X S INDEPENDENT FROM THE OTHERS THE POWER SOURCE S ARE OUR BATTERY BACKED SAFETY RELATED SOURCES

( 1 E )

'4

<<n II

CABLES TO THE PANEL-INDICATIONS AND COMPUTER INPUTS EZIT FROM CONTROL GROUP CABINET NO 23-CABLES FROM THE LSI PANELS

( AUZ BUILDING )

TO THE CONTROL ROOM TERMINATE AT CONTROL GROUP CABINET NO 2 3 CABLES FROM THE CONTAINMENT EZIT FROM ONE

( 1 )

PENETRATIONi SEPARATE SHORTLY THEREAFTER IN PAIRS AND ARE ROUTED THEIR RESPECT IVE LSI CABINETS INS IDE CONTAXNMENT THE FOUR

( 4 )

TRANSMXTTERS ARE LOCATED IN THE PIPE ANNULUS AROUND CONTAINMENT

( ONE IN EACH QUADRANT)

THE TRANSMITTERS ARE OF THE EQ TYPE

( FOZBORO NE 1 0 SERI ES )

BUT ARE LOCATED BELOW FLOOD ELEVATION 6 1 4 CABLES INSIDE CONTAINMENT ARE ROUTED FROM THEIR RESPECT IVE TRANSMXTTER TO A S INGLE P ENETRATXON F E EDTHROUGH THE CABLES ARE OF "THE EQ TYPE BUT ARE LOCATED BELOW FLOOD ELEVATION AS X S THE PENETRAT XON

~

~

TUBING INSIDE CONTAINMENT IS ROUTED FROM THE S) G SENS ING LINE S i THROUGH A CRANE WALL PENETRATIONi TO THE RESPECT IVE TRANSMITTERS NOTE =

EZISTING TUBING AND CABLE SUPPORTS IN CONTAINMENT AND AUZ BUILDING ARE INSTALLED TO MEET SE ISMIC REQUIREMENTS-

1

Existing Steam Generator Wide Range Level Instrumentation Installation

{ t.ooated In Oppoal te Unt.t)

Elect pen XMTR S/G S/G Contalnrnent IV I

XMT Mech pen (tvp)

C T'.5ne, wal I LSI 2

T To LSI 4 Outer Contalnrnent wal I To LSI 4 Recorders HSD Panel I ndlcators Indi cators Control Group Cabinet No. 23 CRID 4 Power To Plant Process and TSC Computers XMTR XMT LSI 1

Auxliary Building CR I D CR I D CR I D 1

2 3

power power power Control Room Area

C

'l v

RATIONALE FOR ORIGINAL POS IT XON ON

'S J'G WIDE RANGE LEVEL SER IS SUED ON AUZILXARY FEEDWATER SYSTEM IN 1 9 8 1 CONCLUDED THAT STEAM GE NERATOR NARROW RANGE LEVEL USED WITH AUZILIARY FE EDWATER FLOW INSTRUMENTATION WAS

'ATISFACTORY TO MONITOR THE OP ERATION OF THE.AUZILIARY FEEDWATER SYSTEM 'OOK NUCLEAR PLANT UNIT 1

AND 2 TECH 'SPECS FOR POST ACCIDENT MONITORING LIKEWISE LIST S) G NARROW RANGE LEVEL AND AUZILIARY FEEDWATER FLOW INSTRUMENTATION WE BELIEVED THAT THIS INSTRUMENTATION WAS ALSO APPLXCABLE FOR REG -

GUIDE 1

9 7 PURPOS E S AND THUS THE S p G WIDE RANGE LEVEL INSTRUMENTATION WAS SUFF ICIENT PER THE ORIGINAL WESTINGHOUSE DES IGN NOTE =

/G NARROW RANGE LEVEL AND AUZILIARY FEEDWATER FLOW INSTRUMENTATION COMPLY WXTH REG GUIDE 1

9 7 CATEGORY 1

CRITERIA PER OUR COMMITMENTS

1 PROPOSED UPGRADE OF STEAM GENERATOR WIDE RANGE LEVEL INSTRUMENTATION

( One Un9 t cieaaz z3oed.

t ~~a aa3 Sox Dot h )

REPLACE EZXSTING INDICATORS AND RECORDERS WXTH SE ISMXCALLY QUALIFIED INDICATORS AND RECORDERS IN THE CONTROL ROOM RE ROUTE CABLES IN THE AUZILIARY BUILDING ON TWO

( 2 )

CHANNELS TO OBTAIN THE NECESSARY SEPARATION OUTS XDE OF THE CONTROL ROOM EVALUATE ANY RE US ED CABLE RUNS FOR SE ISMIC REQUXREMENTS-RELOCATE FOUR

( 4 )

TRANSMITTERS ABOVE FLOODUP ELEVATION-RE TUBE FOUR

( 4 )

TRANSMITTERS FOR NEW LOCATION

( EIGHT RUNS )

ROUTE FOUR

( 4 )

NEW CABLES FROM TRANSMITTERS TO PENETRATIONS VXA FLOODUP BOZE S

( NEW )

AND FLOODUP TUBING

( NEW )

A NEW PENETRATXON FEEDTHROUGH X S TO BE SELECTED FOR TWO

( 2 )

CHANNELS'O PROVIDE PROPER S EPARATXON

I C

O BL1-130 LT 503 SG ¹3 WIDE RANGE LEVEL 0-100%

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I OO II QN 10-SomA LP 503 R23 INOTE-2 )

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1202 R27 LR-34 PNI. CR I/O CAB:Ol ZONE:

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APPROVALS

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COOK UNIT I TITI.E 5 G¹ 3 4. 4 wIDE RANCE LEVE1. A DWG.NO.

1-99020F REV SHEEl'F 01 1 RWC(1IAMl12-13'

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Control Room Cable Vault Area From LSI 1

Control Group Cabinet Rack 23 GRID 4 Power GRID 1 power GRID 2 power GRID 3 power To Plant Process and TSC Computers From LSI 2

To Indicators and Recorders Conceptual Design Sketch

AUX. Building Unit 2 Control Room

/'gbvQ Qh, VL-7 Cables for BLI-110 8. 140 Cables from Con ta Inmen t Penetration To LSI 4 Ex ls ting Cable Run I

"-400 ft.

See Note 1

To Control Group Cabinets LSI-2 New Cable Run See Note 2 Cables for BLI-120 8. 130 NOTES:

1. Cable to maintain IE separation criteria

2. New conduit supports to be seismic Conceptual Design Sketch

l s'

AUX. Building Unit 1 Control Room LSI -1 Cables for BLI-110 K 140 (seperate conduit)

Cables from Containment Penetration LSl - 2 To LSI 4 To LSI 4 Ex is ting Cable Run I

I New Cable See Note un e Note 1

To Control Group Cabinets Cables for BLI-120 3. 130 (seperate conduit)

NOTES: 1. Cable to maintain IE separation criteria

2. New conduit supports to be seismic Conceptual Design Sketch

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Penetration (tvp)

SG1 BLI 11 I

I BLI Iie SG 4 AOO 4

BLI 110, 120, 130, 140 New Qualified Tranmit ters at 614'levation (above F lood Ievel)

Containment Wall Auxiliary Building Area IV II III New

Inst, Tubing (typ)

I Flood-up Box and Tubing SG2 SG 3 Lst-2 OAaa Appen.dix R cables BI I I

BLI 120 I

13 I

Flood-up Box and Tvbing AoooIhoI%Ior Aoomo O

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/r rr Typical for both Units Conceptual Design Sketch

Steam Generator From Uppers Tap Accumulator Tank Area xI sting Reused Sensing LInes New Cable~

~Gun t at nme n t

. Gra,~e. Wall Gut and

Cap, New qTubtng

)

Tubing i

I Penetration El "818 Ex I sting Tubing (abandon

~

or Remove)

Transml t ter (relocated)

El "

818'loor El 812'x lstlng Gable (abandon or" remove)

F lood-up Box (new)

Cable with El "

818'lood-up Tubing (new)

Tubing Penetration EI "

808'ot to Scale Typical Installation inside Containment conceptual Design Sketch I

I I

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I Transml t ter (exlstlng locat lon)

E I 808'ipe Annulus Floor El " 699' I ~ ota Iaal Pan ~ IaatIon

REG -

GUIDE 1 - 9 7 C,OMPLXANCE AFTER UPGRADE COMPLETXON COOK NUCLEAR PLANT UNITS 1

AND 2

NILL EACH HAVE FOUR

( 4 )

STEAM GENE RATOR W XDE RANGE LEVEL INSTRUMENTATXON THAT WILL HAVE ENVIRONNENTAL AND SE ISMIC QUALXF XCATXON i ADEQUATE RANGE i QUALITY AS SURANCE r S E PARATION/INDEPE NDENC E i BATTERY BACKED SAFETYRELATED POWER SOURCES

~

AND DISPLAY) RECORDING CONS ISTENT NITH OUR COMMITMENTS FOR CATEGORY 1 VARIABLES GENERI C DEVIATIONS NOTED IN OUR COMMITMENT LETTER AND FOUND ACCEPTABLE IN THE SER FOR ENVIRONMENTAL AND SE ISMIC QUALIFICATIONS i 'UALITY ASSURANCE i AND SEPARATION IN THE CONTROL ROOM AREA ARE ALSO APPLIED TO THIS INSTRUMENTATION Washington January 24, 1991 XcldXNRCX0200-WP

Purpose Variable Cat Taq Nos E

S 0

S P

0 0

A t

S Display location Reaarhs/Action Rsq'd V 1 Schedule 0.2 schedule D 15 ocondary dys-S/0 Level tea (Stean oenerator)

$1I-Ilov120, 110,Iso (vide rance) tron 12" above~

A A

tube sheet, to

~Operators A

A Control Rooa None required Sse Panel so footnotes (I) a (oo)

(Deviation No. DV-11)

N/A N/A Revised D 15

~condary dys d/0 Level tea (Stean Oonoratcr)

BLI-IIO,120, ISO,IIO (vide ranqe)

A tube sheet to

~eparators-Control Roon Panel SO Install Salsa)cally qualified Control Roon indicators and recorders.

Re-route cable outside of Ccntrol Roon area to provide separation.

Relocate, re-tube, and revise cable routinq for level transaittars inside oontainaent to provide seisaic snd

~nvironasnta1 quell fication.

{Deviation No~ ~ o DV Ig DV 2e DV lr ahd DVi) 1991 Rt 1991 RF XcldINR01020I.NP

I l

TABLE 2. 3-1 Summar of Deviation Re uests from Re lator Guide 1.97 Rev.

3 Deviation No.

Descri tion Where Identified In Section 3.0 Where Ex lained DV-1 DV-2 DV-3 DV-4 Environmental Qualification Seismic Qualification Quality Assurance Redundancy Various Various Various Various Section 2.1.1 Section 2.1.2 Section 2.1.3 Section 2.1.4 held(NRC(0202.

WP

LEVEL OF DIFFICULTY WORK IN CONTROL ROOM AND AUXILIARYBUILDING IS RELATIVELY S IMPLE DUE TO SMALL WORK S COP E AND EAS E OF ACCESS IBXLITY WORK IN CONTAINMENT IS DIFFICULT AND TIME CONSUMING FOR BOTH DES,I GN AND INSTALLATION REASONS

=

EXTREME CONGE STION POOR ACCESS IBXLITY PARTICULARLY IN S j'G AREAS ALARA CONC E RNS CONFLICTING WORK ACTIVITIES IN SAME LIMITATIONS ON TUBING AND CONDUIT SUPPORT LOCATIONS

Activity Es tab I I s h Engineer lng soope of Work Projected Time-Line Done Present to Design Change Working Group.

Members from ALARA Operations,

ProJeots, Site Planning, Design, Llcenslng, Long Range Planning Feb.

91 Prellrnlnary Cost Estimate From Gona tructlon Prepare Packet Reviews ALARA Fire Protection Control Room Feb

~ 91 10GFR 60.69 Revl ew Plant Safety Revl ew Management:

Money Schedule Approval May 91 Start Procurement Aotlon For Long Lead I tems June 91

Activity Walkdown all acceslble areas In the Plant Projected Time-Line Aug. 91 Containment Walkdown Final Cost Es tlmate Complete Englneerlng Design Activities and Veri fIcation Englneerlng

& Design Actlvlties to establish proposed location for components, tubing and cable routlngs.

Place purchase orders.

Issue Walkdown dlrnensloned sketches

& drawings.

ALARA. Planning.

Outages U2 Jan. 92 U1 April 92 June 92 Assemble Quallflcatlon Docurne n tat Ion Prepare

& Issue Drawings Nov. 92 Site ProJect Office - assemble work orders and Issue Ins tal I non outage Install outage

& tie-In Dec. 92 Jan.

Apr. 93 May July 93-

'j f

a'UMMARY SGWRL UPGRADE X S NOT CONCEPTUALLY DIFFICULT DETAILS OF IMPLEMENTATION ARE VERY DXFFICULT DUE TO =

BUILDING,CONGE STION DXFFICULT WORKING CONDITIONS ACCESS XBILITY OF IN CONTAINMENT EQUIPMENT A SUB S TANTIAL AMOUNT OF PHYS XCAL INSTALLATION WORK IS RE QUIRE'D,-

AN ORDERLY IMPLEMENTATION PROGRAM HAS ALREADY STARTED A MINIMUM OF FOURS IZ

( 4 6 )

WEEKS OF XN CONTAXNMENT WALKDOWN '

S REQUXRED PERFORM ING THIS UPGRADE XN THE 1 9 9 2 REFUELXNG OUTAGES WOULD HAVE A S IGNIFICANT EFFECT ON OUTAGE LENGTH AND OVERALL QUALXTY XNSTALLATXON DURING THE 1 9 9 3 REFUEL XNG OUTAGES IS

" PRUDENT Washington January 24, 1991 XcldXNRCX0200.WP