ML17255A760

Forwards Addl Info Re App R Interim Actions to Provide Acceptable Level of Fire Protection Safety.Info Provides Justification for Exemption Request to Extend Schedule for Completion of Mod at Facility

ML17255A760
Person / Time
Site:	Ginna
Issue date:	04/09/1984
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
NUDOCS 8404160159
Download: ML17255A760 (32)

Text

REGULATORY NFORMATION DISTRIBUTION SY TEM (RIDS)

ACCESSION NOR;8004160159 DOC,DATE: 84/04/09 NOTARIZED+

NO DOCKET FACIL:50 244 Robert Emmet Ginna Nuclear Planti Unit ir Rochester G

05000244 AUTH,NAME AUTHOR AFFILIATION ROBER R,WE Rochester'as 8 Electric Corp+

RECIP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELDpD ~

Operating Reactors Branch 5

SUBJECT:

Forwards addi info re App R interim actions to provide acceptab)e level of fire protection safety, Info provides justification for-exemption'request to extend reschedule for completion of mod at. facility, DISTRIBUTION 'CODEX'006S COPIES RECEIVED:LTR

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IIIIIIIIII( IIIIIIIII IIIIII III/ IIIIIIIII ROCHESTER GAS AND llt'I LLNtOQIiA I

ttAtt ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W, KOBER vie pttestoeNT eLECTRIC 6 STEAM PROoVCTlON T S t. C P H0 Ne aREa cooc Ttd 546-2700 April 9, 1984 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Appendix R Compliance R.

E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

By a letter dated December 27,

1983, Rochester Gas and Electric requested an exemption from federal regulations to extend the schedule for completion of modifications at the R.

E. Ginna Nuclear Power Plant necessary to achieve compliance with 10 CFR Part 50 Appendix R.

A detailed report describing the analyses performed for Appendix R compliance and describing the resulting planned modifications was submitted with a letter dated January 16, 1984.

Subsequently, in discussions with NRC Staff members, RG&E was requested to provide additional information concerning interim actions that the company will take to provide an accept-able level of fire protection safety until full compliance with the regulation is achieved.

Those actions described in Attachment A, when coupled with the more than

$ 15 million dollars worth of fire protection features installed at Ginna since the Browns Ferry fire, assure that a stable plant shutdown can be achieved follow-ing a fire in each fire area, including the control room.

This combination of permanent modifications and temporary actions justify the schedule extension requested.

One of the reasons a schedule extension is required is that a

significant amount of modification work is already planned at Ginna for the next several years.

Much of this work is scheduled to comply with other NRC directives.

Information concerning this future work is contained in Attachment B.

Because we are anxious to have the schedule exemption acted upon before May 1, 1984, please contact me quickly if you require further information.

8404fh0159 840409 PDR ADaCW 05000244

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truly yours,

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ATTACHMENT A APPENDIX R INTERIM ACTIONS R.

E.

GINNA NUCLEAR POWER PLANT ROCHESTER GAS AND ELECTRIC CORPORATION MARCH 1984

The RGGE report titled "Appendix R Alternative Shutdown System",

dated December 1983, describes the analyses performed for the R.

E. Ginna Nuclear Power Plant for conformance with 10 CFR 50 Appendix R.

Certain fire areas of the plant will not conform to the requirements of Appendix R until modifications to the plant are completed.

However, during an interim period until the modifications are installed, actions can be taken to assure that a

stable shutdown of the plant can be achieved following a fire in each fire area.

Table 1 summarizes the fire areas requiring modifications and identifies interim actions that RG&E will take until the modifica-tions are completed.

Interim actions are identified for each of the safe shutdown functions which could be lost due to a fire in each of these areas.

These interim actions supersede the interim measures identified in a Rochester Gas and Electric letter dated December 27, 1983.

The definitions of fire areas and safe shutdown functions and equipment designators are consistent with the December 1983 report.

Interim actions considered for each of the fire areas were either supplementary fire protection measures such as barriers, suppression systems or fire watches, or were procedures and equipment which could be used to repair or compensate for the loss of safe shutdown equipment.

In arriving at the best interim

actions, both supplementary fire protection measures and procedures were considered for each fire area except the control room where procedures are provided to meet Staff guidance.

Each of the actions presented has been discussed with one or more Staff members and meets our understanding of current Staff requirements.

Barriers which have been identified to be upgraded in the December 1983 report will ultimately be installed with a one-hour or three-hour rating or justification will be provided for a different configuration.

In the interim period, all required barriers will at least be made contiguous (no openings).

Modifications to existing barriers for the interim period will be made with materials normally used to construct barriers with fire ratings but will not be rated.

Procedures which will be used for interim actions will be available for review on site in final draft form by April 9, 1984.

Plant modifications listed on the table will be completed prior to startup from our current refueling outage.

Fire watches will be provided whenever the plant is not in cold shutdown after startup from the current outage.

Each of these interim measures will remain in place until permanent modifications are completed which replace the specific interim actions.

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TABLE 1 R.

ED GINNA APPENDIX R INTERIM ACTIONS Page l of 9 PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTDOWN FUNCTION INTERIM PROCEIXJRE FIRE PROTECTION MODIFICATION FIRE AREA BRIB FUNCTION Support a) power feeds to EDG 1A and 1B dc distribution panels a,b,c) fire barriers between redundant trains b)

EDG 1A and 1B power feeds c)

ABDP 1A and 1B dc power feeds d)

EDG 1A and 1B control circuits d) procedure for local start and operation of EDG's including fuse pulling and control wire retermination to isolate EDG from CR e)

SW pump control FIRE AREA ABO FUNCTION NA e) procedure for local operation of SW pump breakers in SH a) unrated stairways and open hatches between ABO and ABBM FIRE AREA ABBM FUNCTION NA a) open stairways and hatches between ABO and ABBM a)

Fire watch in ABBM until suppression at openings upgraded a) fire watch in ABBM until suppression upgraded at openings

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R. E. GINNA APPENDIX R INTERIM ACTIONS PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHVXX)OAK FUNCTION INTERIM PROCEDURE FIRE PKEKTION MODIFICATION VZHER FIRE AREA ABBM FUNCTION Support a)

EDG 1A and lB power feeds b)

ABDP lA and lB power feeds c) battery charger lA and 1B power feeds c) existing procedure to use TSC battery and/or TSC charger (E4.4A and E 4.4B) a,b) cables covered by by detection and autanatic suppression.

No other action required.

FIRE AREA ABBM FUNCTION RCS Makeup a) charging pump 1A power feed L398 b) charging pump 1A control feeds L400, L400A c) charging and SI pump separation c) install contiguous barrier between CHG and ABBM or fire watch until barriers installed a,b) existing detection and autanatic sup-pression coverage over hazards adequate for inte~

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TABLE 1 R. E. GINNA APPENDIX R INTERIM ACTIONS Page 3 of 9

PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTIXMN FUNCTION INTIKIMPROCEDURE FIRE PROT~ION MODIFICATION FIRE AREA ABBM FUNCTION Process Instrumentation a) charging flow indications FI-115, 116 (only if operator controlling manually and can' see other RCS indication) a)

pressurizer level indication and o~

instrumentation adequate for interim FIRE AREA CHG FUNCTION NA a)

Charging and SI pump separation a) install contiguous barrier between CHG and ABBM or fire watch in ABBM until barriers installed.

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TABLE 1 R. E. GINNA APPENDIX R ZÃZERIM ACTIONS Page 4 of 9

PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTDOWN FUNCTION INT1RIM PROCEDURE FIRE PROQ CTION MODIFICATION FIRE AREA SH FUNCTION Support a) loss of service water b) loss of EDG lA and 1B FIRE AREA EDGV FUNCTION Support a)

EDG 1A and lB pcarer feeds (ac

& dc) a)

procedure for use of city water for EDG cooling and AFW supply a) upgrade fire barrier to provide separa-tion between trains with materials normally used for 3 hr barriers.

b) fire watch in SH or procedure to cut cables to isolate bus 17 if offsite power lost.

b)

SW pump control b) procedure for local operation of SW pump breaker or city water for EDGs and AFW c) manhole cover in -fire barrier c) revise submittal, barrier meets Generic Letter 83-33 require-ment.

No interim action required.

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TABLE l R. E. GINNA APPENDIX R INTERIM ACTIONS Page 5 of 9

PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTDOWN FUNCTION INTERIM PROCEDURE FIRE PROTECTION MODIFICATION FIRE AREA CT AND ZONES AHR RR FUNCTION Process Monitoring a)

RCS pressure b)

RCS temperature c) pressurizer level d)

SG pressure e)

SG level f)

CVCS flow g)

AFW flow h) source range Existing detection and autcmatic suppressio~

in all areas.

AHR has suppression over

hazards, RR and CT has suppression throughout limited access areas are not travel routes to other areas No inter'ction required

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TABLE l R. E. GINNA, APPENDIX R INTERIM ACTIONS Page 6 of 9

PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTIXSK FUNCZION INTERIM PROCEDURE FIRE PROTKTION MODIFICATION FIRE AREA CT AND ZONES AHR RR FUNCTION Support a) loss of EDG control b) loss of EDG breaker control c) loss of SW pump control d) loss battery chargers 3A and 1B FIRE AREA CT AND ZONES AHR RR FUNCTION NA aM) Existing detection and automatic su~

pression adequate~

limit damage.

No interim action required.

a) full area suppression in AHR a) existing detection, automatic suppress over hazards, lined

access, not on travel route to other areas.

No interim action required.

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TABLE l R, E. GINNA APPENDIX R INTERIM ACTIONS Page 7 of 9 PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTDOWN FUNCTION INTERIM PROCEDURE FIRE PROTECTION MODIFICATION FIRE AREA CT AND ZONES AHR RR FUNCTION RCS Makeup a) loss of charging pump and SI pump control FIRE AREA CT AND ZONES AHR RR FUNCTION Decay Heat Removal a) loss of control to MAFW, SAFW and TDAFW systems FIRE AREA IBN FUNCTION Process Monitoring a)

SG pressure b) source range c)

SW pump control c) procedure for local operation of SW pump breakers in SH a) install local pressure indication in TB b) use sampling as backup to source range a) existing detection and autcmatic suppression adequate to limit damage.

No interim action required.

a) see above note:

Alternative Shutdown Report ind routed through ABBM, CT, CC.

cates all primary temperature ndication routed through IBN,

owever, 408 A5B

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TABLE 1 R. E. GINNA APPENDIX R INTERIM ACTIONS Page-8 of 9 PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTDOWN FUNCTION INTERIM PROCEDURE FIRE PROTECTION MODIFICATION FIRE AREA ZONE CR FUNCTION RCS Makeup a) loss of CHG and SI control FIRE AREA ZONE CR FUNCTION Support a) loss of EDG control b) loss of Bus 14 and 16 EDG breaker control a) procedure to isolate and control charging pump in ABBM a) procedure for local start of EDG including fuse pulling and control wire retermina-tion to isolate EDG from CR b) procedure for local closure of breaker at Bus 14 c) loss of service water pump control FIRE AREA ZONE CR FUNCTION Decay Heat Rermval a) loss of control to TIRFW, MAFW or SAFW systems c) procedure for local operation of SW breakers or procedure for use of city water supply for EDG cooling and AFW supply a) procedure for local operation of MAFW or SAFW pumps.

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TABLE l-R. E. GINNA APPENDIX R INTERIM ACTIONS Page 9 of 9 PROPOSED ACTIONS FIRE AREA AND AFFECTED SAFE SHUTDOWN FUNCTION INTERIM PROCEDURE FIRE PROTECTION MODIFICATION FIRE AREA ZONE CR FUNCTION Process Monitoring a) primary pressure b) primary temperature c) pressurizer level d)

SG pressure e)

SG level f)

CHG flow g)

TDAFW flow h) source range a-e) procedures to get local indication by wire cutting and termination of temporary instrument box near transmitter or containment pene-tration f) pressurizer level adequate for RCS inventory.

Charg-ing flow not rqd.

g)

SG level adequate for SG inventory monitoring.

AFW flow not rqd.

h) source range not rqd. for interim.

Sampling can be used to annitor shutdown.

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ATTACHMENT B APPENDIX R AND OTHER PLANT MODIFICATION SCHEDULES R.

E.

GINNA NUCLEAR POWER PLANT ROCHESTER GAS AND ELECTRIC CORPORATION APRIL 1984

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An RGGE letter dated December 27, 1983 requested a schedular

'exemption for completion of plant modifications necessary to bring the plant into compliance with 10 CFR Part 50 Appendix R.

Justi-fication for the schedule extension was included with that letter.

The information given here is intended to supplement that material.

The number of people involved in plant modifications was discussed in the December submittal.

Over 250 people are scheduled to be on site during the 1984 refueling outage to perform only modification work.

The 1984 outage is not atypical of recent past outages and reflects what RGGE expects to occur in the next several outages.

These people are in addition to the normal plant complement and people required for refueling, maintenance,

tests, overhaul, inspections, calibration and normal plant activities.

The peak number of people on site during the 1983 refueling outage was 882 people.

The weekly average number of people on site during the first six weeks of that outage (before systems were being restored for restart) varied from 740 to 831.

The weekly averages during the current 1984 outage are similar.

The number of people that can effectively work on site is limited by the vintage and size of the two loop PWR plant.

Work space in an existing plant is often at a premium and security and job control conditions become complicated.

Table Bl is a listing of capital projects at Ginna which have been forecast for the years 1984 through 1987.

The list includes modifications which are necessary to meet regulatory requirements as well as modifications initiated by RGGE to improve plant safety or operations.

The identified forecast projects total more than

$ 40 million for both 1984 and 1985 and are approximately

$ 30 million for 1986 and 1987.

The total forecast projects for these years rise steadily from $ 42 million to

$ 60 million when the unidentified projects (projects as yet unspecified but which historically have arisen due to regulatory or other influences) are included.

It is possible that some of the identified projects will be deferred.

The list in Table Bl was developed for budget purposes.

Some of the projects involve only analysis or work which does not include hardware changes at Ginna.

However, the greatest amount of work which has been completed in any year in the past is approximately

$ 30 million.

In addition, more commitments have been made since this list was produced.

Obviously, completion of even the identified projects in the next several years will be difficult. Although the limitations result from restrictions such as work space, proper job supervision and review and control of work procedures and authorizations, the total budget figures have proven to be representative of the limitations on the steel,

concrete, cable and other modifications that can be built into the plant in any one year.

Imposition of a schedule more restrictive than that presented in the exemption request will require that certain other modifications be dis-placed.

Not all of the Appendix R modifications can be acceler-

ated, however, because of the lead times for procurement of qualified equipment.

Interim actions (identified in Attachment A

of this letter) provide assurance of plant safe shutdown until the final Appendix R modifications are completed.

Therefore, the proposed installation schedule is necessary, reasonable and adequate.

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~ ABLEBl PORECA'ST 0 PITAL PROJECTS i984 - i987 (000'S)

MiOi Paid DESCRIPTIOH ELECTRIC DEPT IH-SERV i984 H85 1986 i987 TOTAL HUCLEAR GEHE 0-0 0-0 0-0 0-0 0-0 0-0 0"0 0-0 0-0 0-0 0-0 0-0 0-0 0-0 0-0 21-1 2i-i 21-3 2i-4 22-0 22-1 22 3 23 2 23"7 24 8 26"0 26-3 26-7 26-9

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27-3 28-i 30-2 31"1 31-3 31"9 31-9 31"9 32-3 32-9 33-8 34-i 35-2 35-2 35-9 RATIOH O'RCP fi SEAL LEAKOFF FMR - 3072 0 FUEL TRAHSFER TUBE FLANGE FMR - 2663 0 COHTAIHHEHT GAS PENETRATIOH EMR - 3741 0 CONTROL ACCFSS VEHT EMR - 3102 0 HETEORLOGICAL/RADIATIOHHGHITORS 0 COHTROL CONFIGURATIOH UFGRADE 0 RCP HOTOR - aPARE 0 PRESSURIZER BLOCK VALVES EMR - 3755 0 AHI FIRE PROTECT+

PHASE 1

EMR - 3132 0 AHI FiRE PROTECT.

PHASE II EMR - 3i32 0

HEM RADMASTE FACILITY FMR - 3083 0 RHR SUMr UPGRADE FMR - 3:!3 0 SiISHGLOGY RE-EVALUATIOH EMR - 3669 0 FUEL HANDELXNG EGUXPHEHT EMR - 3590 0 TSC A/C UPGRADE 0 UPGRADE PLAHT LICEHSE 0 GROUNDMATER LEVEL EMR - 3645 0 ADHIH COHPUTER RELOCATXOH EMR - 3776 0 SECURXTY VEHiCLE BARRIERS 0

BLOCK MALLS FMR - 2486 0 SOLEHOID VALVES PHASE II EMR -3260 0

RCP ASS'Y AHD SHAFT 0 RECOHBXNER PXPIHG EMR - 2455 0 FIR PROTECTION EMR - 1832B 0 HYDPGGEH RECON FLOM INSTR 0 SriHT FUEL POOL COGLIHG rH II EMR -159 0 SEiSMIC GUAL HH COHTROL EMR - 3575 0 RECORDS HANAGEMEHT SYSTEH EMR - 3342 0 OVER FRESSURIZATIGH EMR - i660 0 AHHOHIA ADDITIOH SYS EMR - 2145 0 EHTRAIHHEHT SAHPLE SYS FMR - 287P 0 COHTROL ROOH REVIEM EMR - 3264 0 HSR UPGRADE PHASE II EMR - 3100 0

RMST NODS (SEP)

EMR - 3314 0 NASH TANKS EMR - 3572 0 SEISHIC UPGRADE PHASE 7 EMR - 2512 0 SEISHIC UFGRADE PHASE 8 EMR - 2512 0

IHTER BLDG STRUCTURAL NODS EMR - 3582 0 PLAHT,VEHT FMR - 3751 0 FENETi VEHTS/DRAIHS PHASE 3 EMR 2507 0 STEAM GEHERATOR SHUDDERS EMR - i483 0 SERVICE MATER PUHPS EMR - 3316 0 CGHTROL ROON HVAC PHASE I EMR - 35r5 0 CONTROL RGOH HVAC FHASE Ii EMR - 3595 0 TECH'UPPORT CFHTiR E'ViR - 2610 2"

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TABLE Bl (continued)

FORECAST OF PITAL PROJECTS 1984 - 1987 (000'S)

M+Oo PoEo DESCRIPTIOH IN-SERV 1984 198S 1986 1987 TOTAL 35-9 35-9 35-9 35-9 36-9 37-3 38-1 38-3 44"3 4S-1 45-1 45-1 45-1 45-1 45-3 49"3 53-1 53-1 53-2 53-3 54-1 54-3 54-3 55-2 55-2 55"3 57-3 60-3 61-3 64-3 91-3 0-0 0-0 0-0 0-0 r

47-3 0-0 62-3 0-0 0-0 0"0 0-0 63-3 0-0 22-4 0-0 0-0 54-2 0-0 2- 0 TMI MODS-RV NTER LEVFL EMR - 2799 2- 0 TMI MODS - SAS HARDMARE 46376 2" 0 RAD MASTE SYS MOD rHASE ii EMR 3037 2- 0 POST ACCIDEHT SAMPLIHG 2- 0 CONTAIHMEHT PURGE VALVES FMR - 2504 2- 0 BLOMBQMH VALVE RESTRAIHT EMR - 3674 2- 0 DEDICATED SHUTDOMH SYSTEH EMR - 3313 2- 0 CONTROL OF HEAVY LOADS EMR - 3059 2" 0 RELAY ROOH HALOH FAHS EMR - 3729 2- 0 S/G SLEEVIHG FrlASE 1

EMR - 2714 2- 0 S/G SLEEVIHG PHASE 2 EMR - 2714 2-O.S/G SLEEVIHG PHASE 3 EMR " 2714 2- 0 S/G SLEEVIHG PHASE 4

EMR - 2714 2- 0 S/G SLEE'VIHG PHASE 5 EMR - 2714 2- 0 HP TURBIHE UPGRADE 2- 0 AUX BLDG JET SHEILDS EMR - 3691 2- 0 FEEDNTFR ELBOMS FMR - 2469 2- 0 FEEDNTER ELBQMS EMR - 2469B 2- 0 STRUCTRAL REANALYSIS EMR - 3296 2- 0 SPEHT FUEL POOL RERACK EMR - 3666 2- 0 FLANT PROCESS COMPUTER REPLACEMEHT -3272 2- 0 SIMULATOR BUILDZHG EMR - 3882 2- 0 ?LAHT SIMULATOR EMR - 3786 2- 0 BORIC ACID PIPING PHASE I EMR " 3092 2- 0 BORIC ACID PZPIHG FHASE Zi FMR - 3092 2- 0 RMS SYSTEH UFGRADE 2- 0 COUNT ROOM A/C EMR - 3752 2- 0 COHTROL BLDG HVAC 0 40 TQH CRANE UPGRADE EMR - 3651 2- 0 FSAR UPDATE 2- 0 MAIN TRANSFORMS VEHT EMR - 1606 2-1 EDDY CURREHT IHSTRUMEHTATZOH 2-2 DRIVEMAY /'TORAGE AREA PAVIHG 2-3 DCA HODE FOF/SEC 2-S SI PUHP RECIRC+

2-6 DB-50 REPLACEMEHT/SPARES EMR - 3069 2-7 CABLE TRAY SEISHIC UPGRADE EMR " 3695 2-8 D/G BREAKERS fh AUX'PARES EMR - 3693, 2-9 CIRCUIT SCHEDULE DBMS 2-11 PLANT SECURITY EMR - 3733 2-12 FUEL rIAHBLING BRIDGE EMR - 1839 2-15 UPGRADE 'B'HAFT 2-16 SALEM ATMS REACTOR TRIr" MOD EMR - 3698 2-17 IHTAKE STRUCTURE SCREEHS 2-18 TRAHSFQRMER TEMPo HOHITQR 2-19 TURBIHE BLDG ROOF REFLACEMEHT 2-26 862A / 862B REPLACEMEHT 2-29 IHCORE THERMOCQUPLE CONNECTS EMR - 3744 2-30 AUX FM TURBZHE TRIP ATHS MOD 6/85 6/85 7/84 7/83 6/85 6/84 6/86 4/84 6/84 6/83 6/84 6/85 6/86 6/87 6/86 7/84 6/85 12/87 5/85 6/85 ll/84 2/87 6/85 6/86 5/84 1/84 6/84 9/84 2/85 6/84 2/84 8/a4 12/84 6/as 8/84 7/ 85 7/85 12/84 6/85 6/as 12/84 6/aS 6/87 5/84 6/84 6/a6 6/84 7/86 940 794 40 160 125 50 912 321 74 100 1446 510 1

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0 0

500 9711 0

0 24 36 0

257 6894 403 1196 240 485S 598 139 0

0 0

0 114 0

0 0

0 464 0

77 212 0

105 27 0

171 0

0 0

64 0

112 0

0 0

0 0

0 2315 0

0 0

0 0

9690 0

2518 0

0 0

0' 0

0 0

0 0

0 0

0 0

3608 2237 40 160 1589 50 5906 321 74 100 1946 0

10221 500 10191 9690 0

0 0

0 9691 2574 Sl 211 307 0

0 0

1831 0

589 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

199 0

164 0

1619 0

2023 0

1570 799 10368 0 '82 0

729 0

0 0

0 0

0 0

0 00.

0 0

0 0

103 0

0 0

0 0

69 40 212 2aS 1438 204 79 75 40 514 440 330 313 50 155 42 3S6 313 104 45 175 288 97 326 6690 10882 28316

h 7I TABLE B~(cont,inued)

FORECAST OF%SPITAL PROJECTS 1984 - 1987 (000'S)

HeOi PoEo DESCRIPTION IH-SERV 1984 1985 1986 1987 TOTAL 0-0 2-31 ROD POS IHD SYS ERR - 3797 0-0 2-33 VITAL BATTERY REP EelR - 3891 0-0 2-34 IHCORE THERMOCOUPLE SYS UPGRADE 0<

2-35 GINHA ROOF REPLACEMEHT PH1 0-0 2-36 GIHHA ROOF REPLACEMEHTS PH2 0-0 2-37,GIHHA ROOF REPLACEMEHTS PH3 0-0 2-41 LOM LEVEL BETA COUHTIHG EQUIP 0-0 2-45 S/G RECIRC CLEAHUP SYSTEM 0-0 2-46 CGMPUTER INPUT TIE-IHS 0-0 2-47 1A/2A 1B/2B FH HEATER REPLACEMEHT 0-0

&50 NUCLEAR PROD - BLDGS 1 EQUIP - MINOR 0-0 2-53 STAo 13 41 TRANSFER AUX'OOLER 0-0 2-53 SECURITY COMPUTER REPLACEMENT 0-0 2-54 EXPLOSIVE DETECTORS REPLACEMENT 0-0 2"57 X-RAY MACHIHE 0-0 2-90 UHIDEHTIFIED MAJOR PROJECTS - HUCLEAR 7/86 901 7/85 50

?/86 101 12/85 0

12/86 0

12/87 0

6/85 0

6/85 0

6/85 0

12/87 0

0/00 725 5/84 60 12/86 0

6/86 0

6/86 0

0/00 0

218 582 106 0

119 219 122 0

0 106 0

0 31 0

179 0

51 0

0 0

761 808 0

0 0

528 0

102 0

51 1658 22532 0

1701 0

156 0

439 0

122 0

106 85 85 0

31 0

179 0

51 687 687 857 3151 0

60 0

528 0

102 0

51 32130 56320 TOTAL NUCLEAR GEHERATIOH 42388 55102 206077 50027 5%500