ML20096D578

Monthly Operating Rept for Dec 1995 for TMI Nuclear Station

ML20096D578
Person / Time
Site:	Crane
Issue date:	12/31/1995
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-96-2001, NUDOCS 9601190184
Download: ML20096D578 (6)

Text

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GPU Nuclear Corporation U

GM Route 441 South P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Number; (717) 948-8005 January 11, 1996 C311 96-2001 U. S Nuclear Regulatory Commission Attn: 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 December 1995 Enclosed are two copies of the December 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, 4

9601190184 951231

[

PDR ADOCK 05000289 J. Knubel DR Vice President and Director, TM1 WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector T95001 190049

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OPERATIONS

SUMMARY

December 1995 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 December.

MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items accomplished during the month:

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Makeuo Pumo MU-P-1 A Makeup Pump MU-P-1 A was removed from service due to increased vibration. To alleviate the l

balance problem, split balance rings were installed on the exposed areas of the pump shaft between the bearing oil seals and the mechanical seals. Additional work performed included a i

visual inspection of the speed increaser gears, a coupling alignment check, and inboard and

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outboard bearing to shaft clearance checks. All inspection results were satisfactory. The pump was reassembled, tested per IST 1300-3H with satisfactory results and returned to service.

Beactor Coolant Recorder RC7 TAR Reactor Coolant Temperature Recorder RC7 TAR was removed form service because the recorder was not advancing. During troubleshooting and corrective maintenance activities, the

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motor gear was found cracked and was replaced. RC7 TAR operated correctly during post j

maintetance tests and was returned to service.

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Diesel Driven Fire Pump FS-P-1 Diesel Driven Fire Service Pump FS-P-1 was removed from service due to the inoperability of the block heater. The block heater thermostat was found to be failed and was replaced. The maintenance effort included cleaning the heater elements and replacing a cracked flexible hose on the heater. Following the work, the block heater was tested and based on its satisfactory operation, FS-P-1 was returned to service.

Cation Demineralizer Piping Weld repairs to two pin hole leaks in piping between the Cation Demineralizer and the Reactor Coolant Waste Evaporator were completed. The leaks were located at a welded coupling and a welded tee downstream of valves WDL-V-73 and WDL-V-74. They were determined to be thru wall leaks in the heat affected zone at the toe of the socket welds. The defects were excavated and liquid dye penetrant tested to ensure that they were completely removed. The areas were then welded and visually and PT inspected. After testing, the system was returned to service.

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1 OPERATING DATA REPORT DOCKET'NO.

50-289 DATE COMPLETED BY W G HEYSEK i

OPERATING STATUS TELEPHONE

(.717 ) 948-8191 l

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1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

DECEMBER 1995 l

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3. LICENSED THERMAL POWER:

2568 l l

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4. NAMEPLATE RATING (GROSS MWe):

872 l l

l S. DESIGN ELECTRICAL RATING (NET MWe):

819 l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

834 l l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l l

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6 8.

IF CHANGES OCCUR IN (ITEMS 3 7) SINCE LAST REPORT, GIVE REASONS:

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

10. REASONS FOR RESTRICTIONS, IF ANY:

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THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 8760.0 186985.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 7954.4 109543.1

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

14. HOURS GENERATOR ON_LINE (HRS) 744.0 7926.2 108381.3

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 190935'9 20198655 266114926

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 645634 6770220 89453474

18. NET ELECTRICAL ENERGY GENERATED (MWH) 610193 6387986 84043404

19. UNIT SERVICE FACTOR

(%)

100.0 90.5 58.0

20. UNIT AVAILABILITY FACTOR

(%)

100.0 90.5 58.0

21. UNIT CAPACITY FACTOR (USING MDC NET) 104.3 92.8 57.2

22. UNIT CAPACITY FACTOR (USING DER NET) 100.1 89.0 54.9

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 35.9 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2

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

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

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-l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

DECEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWe-NET) 1 820 17 824 2

821 18 825 3

822 19 816 4

820 20 818 5

824 21 816 6

824 22 815 7

824 23 816 8

826 24 817 9

825 25 817 10 827 26 816 11 824 27 814 12 819 28 815 13 817 29 818 14 819 30 820 15 823 31 820 16 823 4

DOCKET No.

50-289 UNIT NAME TMI-l DATE REPORT MONTH December 1995 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191

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l 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

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

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 fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: None.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 683

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

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

Upon completion of Phase II of the reracking project, the full licensed capacity will be attained. Phase II is expected to be started in 2002.

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

Completion of Phase I of the reracking project permits full core off-load (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.

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