ML20133G823

Monthly Operating Rept for Dec 1996 for TMI-1

ML20133G823
Person / Time
Site:	Three Mile Island
Issue date:	12/31/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2002, NUDOCS 9701160176
Download: ML20133G823 (7)

Text

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l GPU Nuc! ear, Inc.

( Route 441 South NUCLEAR Post Office Box 480 Middletown, PA 17057-0480 Tel717-944 7621 January 08, 1997 6710-97-2002 i

5 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 1996 Enclosed are two copies of the December 1996 Monthly Operating Repon for Three Mile Island Nuclear Station, Unit 1.

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Sincerely, 1

J.Knubel 4

Vice President and Director, TMI ,

WGH  !

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cc: Administrator, Region 1 O TMI Senior Resident Inspector [gb 96001 ) >

9701160176 961231 PDR ADOCK 05000289 R PDR

~ . . _ . _ . . . _ . _ _ . _ . . _ _ - _ _ _ _ . - . _ . _ . _ . . _ . _ _ _ _ . = _ _ _ . _

OPERATIONS

SUMMARY

December 1996.

The plant entemd the month operating at 100% power and remained at that power level f or the remainder of the month. Net unit electrical output averaged approximately 821 MWe during December.

MAJOR SAFETY RELATED MAINTENANCE The major safety related maintenance items completed during the month involved the folloving equipment:

Nuclear Services Closed Cooler NS-C-1C Nuclear Services Closed Cooler NS-C-lC was returned to service in December after the following tasks were accomplished; leak testing the cooler (no leaks were identified), clearing the tubes, Eddy Current Testing, plugging one tube, installing sacrificial magnesium anodes, and recoating the water boxes.

Control Building Exhaust Fan AH-E-94A Control Building Hallway exhaust fan AH-E-94A was removed from service because of naisy bearings. The fan / motor assembly was removed and both inboard and outboard motor bearings 1 were replaced. The fan inboard pillow block bearing was also replaced. After the fan wai reassembled, it was tested and returned to service.

Fire Service Relief Valve FS-V-248 Motor Driven Fire Service pump FS-P-2 was removed from service because of a pin hole leak in the body of discharge relief valve FS-V-248. The valve was removed from the system and replaced with a new valve. All retest results were satisfactory and the system was returned to service.

1 Makeup Valve MU-V-8 l

Makeup System Letdown valve MU-V-8 was removed from service because the motor operator.

to valve stem connector threads pulled loose from the valve stem. The damaged connector was repaired by retapping the threads. Afterwards, the repaired connector was reinstalled on the valve. MU-V-8 was tested with satisfactory results and returned to service. I 1

, . OPERATING DATA REPORT DOCKET NO. 50-289 DATE January 08, 1997 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

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

2. REPORTING PERIOD: DECEMB 1996

3. LICENSED THERMAL POWER: 2568

4. NAMEPLATE RATING (GROSS MWe): 872

5. DESIGN ELECTRICAL RATING (NET MWe): 819 4

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe) 834

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 786

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

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

10. REASONS FOR RESTRICTIONS, IF ANY:

I THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 8784.0 195769.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 8784.0 118327.1 ,

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

14. HOURS GENERATOR ON-LINE (HRS) 744.0 8784.0 117165.3

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,908,743.0 22,490,749.4 288,605,675.4

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 646,143.0 7,511,072.0 96,964,546.1

18. NET ELECTRICAL ENERGY GENERATED (MWH) 611,173.0 7,100,260.0 91,143,664.1 -

19. UNIT SERVICE FACTOR (%) 100.0 100.0 59.8

20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 59.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 104.5 102.8 59.2

22. UNIT CAPACITY FACTOR (USING DER NET) 100.3 98.7 56.8

23. UNIT FORCED OUTAGE RATE (%) 0.0 0.0 34.1 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; 2

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 UNIT TMl-1 I DATE January 08, 1997 '

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) l 1 811 17 818 2 820 18 819 3 822 19 824 4 820 20 827 5 822 21 826

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REFUELING INFORMATION REOUEST l -

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

2. Scheduled date for next refueling shutdown: September 5,1997

3. Scheduled date for restart following current refueling

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4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes. To support GPU Nuclear's independent reload analyses for Cycle 12 as discussed in response to Question 6 below, T.S. 6.9.5.2 will require revision to include references to the GPU Nuclear analysis methods applied to the reload.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: A Technical Specification Change Request for the changes as discussed above will be submitted once the GPU Nuclear topicals are 1 approved.

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:

a) CPU Nur! car Letter 6710-96-2092, dated March 28,1996 confirmed plans to perform independent reload design evaluations for Cycle 12, the next operation cycle, based on NRC approved methods described in GPU Nuclear Topical Reports TR-091 A (core physics), TR-087 (core thermal hydraulics), TR-078 (FSAR safety analyses) and TR-092P (design and setpoints methodology) submitted to the NRC. The latter three are in the i final NRC approval stage. Issuance of NRC SERs is expected soon.

The GPU Nuclear Cycle 12 reload program and results are expected to be ,

available for NRC review in the March to April 1997 time frame.

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b) Cycle 12 fuel rod performance calculations (e.g. internal pin pressure) will be performed by Framatome Cogema Fuels Company (FCF) using the  ;

approved TACO 3 (BAW-10162P-A) and GDTACO (BAW-10184P-A) fuel i codes. Results require minor changes to the Mark B9 fuel rod design (lower fill gas prepressure, increased plenum volume). The new design will meet all fuel criteria in the latest approved revision of BAW-10179P-A, Safety Criteria and Methodology for Acceptable Cycle Reload Analyses. Fuel rod cladding corrosion calculations for all Cycle 12 fuel are being done by FCF using the COROS2 methodology now under review by the NRC. Approval is expected soon. The TACO calculations are being done using power histories generated with the GPU Nuclear approved core physics codes CASMO-3/ SIMULATE-3 (TR-091A). Use of the SIMULATE-3 power peaking uncertainty of 5.5% with the TACO methodologies, rather than the current FCF NEMO physics code (BAW-10180A, Rev 1) uncertainty of 4.8%, was approved by NRC on October 4,1995 for application to TMI-1 only.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 864

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 -

fuel assemblies:

The present licensed capacity is 1990. Phase I 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 fulllicensed capacity will be attained. Phase IIis 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 and beyond the end of the current operating license.

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