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g GPU Nuclear Corporation4 ,s

.?; o #;j. QQ f Pvst Of fice Box 480I- ' Route 441 South

Middletown, Pennsylvania 17057 0191717 944 7621TELEX 84 2386Writer's Direct Dial Number:(717) 948-8005

March 12, 1992C311-92-2043

U;-S. Nuclear Regulatory CommissionAttn: Document Control Desk

-Washington, D.C, 20555

Gentlemen:

Subject: Three Mile Island Nuclear Station, Unit I (THI-1)Operating License No. DPR-50Docket No. 50-289Honthly Operating Report for February 1992

Enclosed are two copies of the February 1992. Monthly Operating Report forThree Mile Island Nuclear Station, Unit 1.

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Sincerely,,

&qWT. G. BrougWtonVice President and Director, THI-J

WGH

Attachmentscc: ' Administrator, Region I '

TMI Senior Resident Inspector

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9203170042 920229 f-

[). k.]PDR ADOCK 05000289~

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GPU Nuc: ear Corporation is a subsdary of Generar Putcc Utinfies Corporanon s''

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OPERATIONS SUMMARYFEBRUARY 1992

The unit entered the month operating at 100% power producing 868 MWe, As aresult of a partial EFW actuation on 1/22/92, modifications to the emergencyfeedwater control valve circuitry were performed and testeo. The feedwatervalve controllers were replaced at the same time. On 2/13/92, a meeting washeld between GPUN management and the NRC to discuss the TMI-l SALP results.The unit closed the month operating at 100% power.

MAJ0LSAFli t RELATED MilNTSNMG1

During February, the following major safety related maintenu ce activitieswere performed:

S13 tion Blackout Diesel Generater EG-Y-4' The Station Blackout Diesel Generator lubricating oil modification was

completed during the ronth. Work accomplished included installation of avolume booster to increase the oil supply to the upper bearings during enginestarts and repair of various engine oil leaks. Upon completion of the work, atest run of the engine was satisfactorily completed and the SB0 dieselgenerator was returned to service.

Instrument Air Compressor IA-P-4

Increasing temperatures on Instrument Air Compressor (IA-P-4) caused itsremoval from service. The compressor inner and after coolers were ramoved andinspected by maintenance personnel. Both cooler bundles were found coated -

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. ith NALCO corrosion inhibitor which adversely affected their heat exchangew

; capability. The tube bundles were cleaned and reinstalled. IA-P-4 testeasatisfactorily and was retarned to service.-

"Dperav Heat _ River Water Strainer DR-S_la

Decay Heat River Water Strainer (DR-S-1A) was removed from service to repairoil leaks and install a vented oil sightglass on the drive unit. New motorbearings were. installed while the drive unit motor was removed anddisassembled. The motor oil seals were also replaced and the motor wasreassembled. New drive unit oil seals and a vented sightglass were installed.A modification was made to add oil 'tarough the drive unit cover. DR-S-1A wasreassembled, satisfactorily tested and returned to service.

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OPERATING DATA REPORT

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DOCKET NO. 50-289DATE Maren 12, 1992COMPLETED BY W G HEYSEK i

OPERATING STATUS TELEPHONE (717) 948-8191*

1.. UNIT NAME: THREE MILE ISLAND UNIT 1 NOTES:2. REPORTING PER.IOD: FEBRUARY 19923. LICENSED THERMAL POWER: 2568

-4,. NAMEPLATE RATING (GRO'S MWe): 8715. DESIGN ELECTRICAL. RATING (NET MWe): _819.

6.' MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 8567. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 808

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B. (F CHANGES. OCCUR IN (ITEMS 3-7) SINCE.LAST REPORT, GIVE REASONS:._

:9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):. 10. AEASONS FOR RESTRICYIONS, IF ANY:

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THIS MONTH YR-TO-DATE CUMMULATIVE_____ . . . ___ _ _ _ _ . .

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-11. HOURS IN: REPORTING PERIOD (RRS) 696.0 1440.0 153361.012. ' NUMBER .Or 60URS REACTOR WP" CRIT 1 CAL (HRS) 696.0 1440.0 *8171.0s

13. REACTCL RESERVE SHUTDOWN % VS (HRS) 0.0 0.0 224,5.6

i14.KHOURS GENERATOR ON-LINE- (HRS) 696.0 3440.0 7 709 A;15. UNIT KESERVE SHUTDOWN HOURS (HRS) 0.0 6.0 00'16. GROSS THERMAL' ENERGY GENERATED (MWH) 1784246 3692373 18786% .8

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17.JCROSS ELECTHICAL ENERGY.' GENERATED (MWH) 597823 12372E4 632M 02338. NET ELECTRICAL ENERGY GENERATED (MWH) 564208 1167900' 5932!.' 25-

19. UNIT SERVICE' FACTOR _ (%) 100.0 100.0 50.34

-20.JUNIT AVAILABILITY FACTOR _ (%) 100.0 100.0 50.3'31. UNIT _ CAPACITY' FACTOR (USING MDC NET) 100.3 100.4 49.222.' UNIT CAPACITY FACTOR (USING DER NET) 99.0 99.0 47.2'23. UNIT FORCF,0 OUTAGE RATE (4) 0.O_ -0.0 44.0

_ UNIT. FORCED OUTAGE HOURS. (HRS) 0.O' O.0 60648.7e

| -24,' SHUTDOWNS; SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):|:

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,$25. ~IF SHUT DOWN AT END OF REPORT. PERIOD, ESTIMATED DAff. OF STARTUP:

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AVERAGE DAII.Y UNIT POWER LEVEL

DOCKET NO. 50-289UNIT THI-1DATE March 12, 1992COMPLETED BY U G HEYSEK4

TELEPHONE (717, 948-8191,

MONTII: FEBRUARYr-

DAL ' AVERAGE DhII! POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i

(MWe-NET) (MWe-NET)-

1 811 17 810,

2 811 18 809'3 811 19 8074 811 20 808

- 6 813 21 809-6 814 22 810

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7 ,813 23- 807'8 813 24 8099- 814 25 all,-

i ~10 ' 814 26 811 -

11- 811 27 810 j12' 815 28 808 i

13 812 29 81214 811 30 !!A15 806 31 NA'16 B07

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. UNIT SHUTDOWNS AND PCWER' REDUCTIONS

DOCKET NO. 50-289 .

t? NIT N?)(E TMI-1REPORT MONTH -February 1992 DATE . March 12, 1992

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COMPLI"IED BY W. G. HevsekTELEPHoliE (117) 948-8191

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Method of ^ Licensee Mystem :ornpoemt Cause & Corre;tiveNo- Date Type' Duration Reason' . Shutting Event Code : Code Actfon to

(Hours) Doim Report #~

Present Recurre y .

|| . Reactor * &* *&' I*

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- |1 ' 2 3 4F Forced Reason Method Exhibit G - Instructions forS Scheduled A-Ecpipment f ailure (Explain) 1-Manual pr<paration of Data Entry Sheets

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a-Maintenance or Test 2-Nml Scrara for Licensee Event Report (LER) |C-Refueling 3- Autonutic Scram File (WREG-0161) ;

D-Regulatory Restriction 4-Other (Explain)E-operator Training & Licensing Examination S Exhibit 1 same sourceF* AchinistrativeC-Operational Error (Explain) 6 Actually used exhibits F & II NUREG 0161 I

W-Other (Explain):

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BEVELUi(LIEORMATION RE00EST

1. Name of Facility: Three Mile Island Nuclear Station, Unit 1|

2. Scheduled date for next refueling shutdown: September 17, 1993 (10R)

3. - Scheduled date for restart following current refueling: NA

4. Will refueling or resumption of operation thereafter require a technicalspecification change or other license amendment? NA

If answer is yes, in general, what will these be?

If answer is no, has the reload fuel design and core configurationbeen reviewed by your Plant Safety Review Committee to determinewhether any unreviewed safety questions are associated with the corereload (Ref.10 CFR Section 50.59)?

If no such review has taken place, when is it scheduled?

5. Scheduled date(s) for submitting proposed licensing action and supportinginformation:

None , planned.'

6. Important licensing considerations associated with refueling, e.g. new ordifferent fuel design or supplier, unreviewed design or performanceanalysis methods, significant changes in fuel design, new operatingprocedures:

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GPU Nuclear has installed four Westinghouse Lead Test Assembliesduring the reload of the TMI-1 core for cycle 9 operation.Westinghouse fuel technology will be utilized to the extentpossible.

7. The number of fuel assemolies (a) in the core, and (b) in the spent fuelstorage pool: (a) 177 (b) 521

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8. The present licensed spent fuel pool storage capacity and the size of cnyincrease in licensed storage capacity that has oeen requested or isplanned, in number of fuel assemblies:

The present licensed capacity is 752. Planning to increase licensedcapacity through fuel pool reracking is in progress.

- 9. The projected date of the last refueling that can be discharged to thespent fuel pool assuming the present licensed capacity:

The 9R (1991) refueling discharge was the last to allow full coreoff-load capacity (177 fuel assemblies).

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