ML20149K755

Monthly Operating Rept for Jan 1996 for TMI-1

ML20149K755
Person / Time
Site:	Three Mile Island
Issue date:	01/31/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2045, NUDOCS 9602220127
Download: ML20149K755 (6)

Text

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1, o 9' k 'O MU GPU Nuclear Corporation ear "oute dd' Sout" l P.O. Box 480 Middletown. Pennsylvania 1705,7-0480 ,

(717)944-7621 l Writer s Direct Dial Number.

(717) 948-8005 February 14, 1996 6710-96-2045 l

U. S. Nuclear Regulatory Commission Atta

Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 ,

Docket No. 50-289 Monthly Operating Report for January 1996 Enclosed are two copies of the January 1996 Monthly Operating Report for Three Mile Island l Nuclear Station, Unit 1.

Sincerely, J. Knubel Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector ,

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, 9602220127 960131 I

1. PDR ADOCK 05000289 R PDR \

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OPERATIONS

SUMMARY

January 1996 The plant entered the month operating at 100% power and remained at that power level for the remainder of the month. Net unit electrical output averaged approximately 820 MWe during January.

MAJOR S AFETY RELATED MAINTENANCE The following major safety related maintenance item was accomplished during the month:

Air Intake Tunnel Fire Protection System The Air Intake Tunnel Fire Protection System was removed from service when trouble, fire and pressure alarms were received in the Control Room. Investigation identified that pressure wave detectors for the vertical shaR inlet section of the tunnel had caused actuation of Halon and water deluge. All eleven Halon containers in the vertical shan were found discharged. These eleven containers along with their explosive actuators were replaced. Pressure wave detectors BS42A and BS42B were also replaced due to a zero ground on the system. Other work performed included replacement of all the explosive actuators in the tunnel, heat trace checks, and Halon checks on one container on each of the three remaining sections of the tunnel. All retests of the system were satisfactory and the Fire System was returned to service. A root cause evaluation of the event is being prepared by Plant Engineering. 1 I l l

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A . 1 OPERATING DATA REPORT DOCKET No. 50-289 DATE COMPLETED BY M G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT'NAME: THREE MILE ISLAND UNIT 1 l NOTES: l

'2. REPORTING PERIOD: JANUARY 1996 l l

3. LICENSED THERMAL POWER: 2568 l l

4. NAMEPLATE RATING (GROSS MWe): 872 l l t 5. DESIGN ELECTRICAL RATING (NET MWe): 819 l l

'6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 834 l l

7. MAXIMJM DEPENDABLE CAPACITY (NET MWe): 786 l l l l ,

8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS

- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): l l

10. REASONS IOR RESTRICTIONS, IF ANY:

i THIS MONTH YR-TO-DATE CUMMULATIVE s

11. HOURS IN REPORTING PERIOD (HRS) 744.0 744.0 187729.0 '

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 744.0 110287.1

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2284.0

14. HOURS GENERATOR ON.LINE (HRS) 744,0 744.0 109125.3

15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0 ,

16. GROSS THERMAL ENERGY GENERATED (MWH) 1908127 1908127 268023053 '

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 645638 645638 90099112 18.-NET ELECTRICAL ENERGY GENERATED (MWH) 609845 609845 84653249

19. UNIT SERVICE FACTOR (%) 100.0 100.0 58.1 l

20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 58.1 l

21. UNIT CAPACITY FACTOR (USING MDC NET) 104.3 104.3 57.4 1

22. UNIT CAPACITY FACTOR (USING DER NET) 100.1 100.1 55.1 j

23. UNIT FORCED OUTAGE RATE (t) 0.0 0.0 35.7  :

UNIT. FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761 2 l

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH): l

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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AVERAGE' DAILY UNIT POWER LEVEL DOCKET NO, 50-289 UNIT TMI-1 DATE COMPLETED BY W G HEYSEK l TELEPHONE (717) 948-8191 MONTH: JANUARY l

DAY f.VERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWe-NET) 1 820 17 821 l 2 -819 18 817 3 822 19 811 4 . 824 20 824

, 5 824 21 822 6' 821 ,22 821 7 816 23 822 8 818 24 818 9 816 25 822 10 816 26 822 11 811 27 815 12 811 28 823 13 817 29 823 14 820 30 822 15 822 31 825 2

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REPORT MONTH January 1996 W. G. Heysek /

COMPLETED BY TELEPHO'.eE (717) 948-8191 - - s.

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REFUELING INFORMATION REOUEST

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

2. Scheduled date for next refueling shutdown: September 12,1997

3. Scheduled date for restart following current refueling: NA

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

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5. Scheduled date(s) for submitting proposed licensing action and supporting information: NA

6. Important licensing considerations associated with refueling, e.g. new or different i fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: None.

2 7, The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage p )ol: (a) 177 (b) 683 1

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8. 'I Se present licensed spent fuel pool storage capacity and the size of any increase in@ensed storage capacity that has been requested or is planned, in number of fuel asamblies:

l The present licensed capacity is 1990. Phase 1 of the reracking project to j increase spent fuel pool storage capacity permits storage of 1342 assemblies. l

. Upon completion of Phase II of the reracking project, the fulllicensed  ;

capacity will be attained. Phase II is expected to be started in 2002. k i  !

9. The projected date of the last refueling that can be discharged to the spent fuel i pool assuming the present licensed capacity: j l

! Completion of Phase I of the reracking project permits full core off-load j (177 fuel assemblies) through the end of Cycle 14 and on completion of the rerack project full core off-load is assured through the end of the current operating license and beyond. l

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