ML20072E268

Monthly Operating Rept for Jul 1994 for TMI-1

ML20072E268
Person / Time
Site:	Three Mile Island
Issue date:	07/31/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2110, NUDOCS 9408220177
Download: ML20072E268 (6)

Text

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GPU Nuclear Corporation g

Route 441 South p3 t

+y.J UCuear 3.hjr e o So 48o Middletown, Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Number:

(717) 948-8005 August 12, 1994 C311-94-2110 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 July 1994 Enclosed are two copies of the July 1994 Monthly Operating Report f - Three Mile Island Nuclear Station, Unit 1.

Sincerely, hY% Os T. G. Broug'kton Vice President and Director, TMI WGH 1

Attachments cc: Administrator, Region I TMI Senior Resident Inspector T94001 190112 9408220177 94o733 PDR ADOCK 05000289 t

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GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporabon

n OPERATIONS

SUMMARY

July 1994 The plant entered the month operating at 100% power and remained at that level through the entire month.

Unit electrical output averaged approximately 788 MWe during July.

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

Boric Acid Supply To Bleed Tank Isolation Valve WDL-V-62 As a result leakage past Waste Disposal liquid system valve WOL-V-62, the valve was removed _ from service for repair.

Inspection of the disassembled valve components found the diaphragm finger plate and the gasket to be corroded. WDL-V-62 was rebuilt using a new diaphragm, diaphragm finger plate, gasket, and new studs and nuts.

The valve was tested with no leakage evident and returned to service.

Pressurizer Heater Bank #5 The fault detection circuit for Pressurizer Heater Bank #5 was removed from service after it initiated numerous erroneous alarms.

Troubleshooting of the system revealed failed capacitors which were replaced. All retests were performed satisfactorily and the detector returned to service.

Position Transmitter FW-ZT-ll20 Feedwater Control Valve FW-V-178 position transmitter FW-ZT-ll20 was removed from service due to intermittent failure. _ Troubleshooting identified the problem to be a failed rheostat. The rheostat was replaced and FW-ZT-ll20 was

'j returned to service.

NR-V-130 Pipino A pinhole leak was found in the 12" pipe upstream of Nuclear Service Closed' Cooler NS-C-lD backwash valve NR-V-130.

Ultrasonic testing (UT) of the pipe revealed only localized wall thinning adjacent to the through wall leak. No i

further wall thinning was identified.

The through wall leak was repaired by welding a half coupling over the defect area and installing a pipe plug in the coupling. A hydrostatic test of the repair will be performed in August.

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i OPERATING DATA REPORT DOCKET NO.

50-289 DATE COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

JULY 1994 l

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3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWo):

871 l l

S. DESIGN ELECTRICAL RATING (NET MWe):

819 l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

834 l l

7.

MAXIMUM DEPENDADLE CAPACITY (NET MWe):

786 l l

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8.

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

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

10. REASGNS FOR RESTRICTIONS, IF ANY:

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THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 5087.0 174552.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 4689.7 97915.7

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

-0.0 2284.0

14. HOURS GENERATOR ON_LINE (HRS) 744.0 4679.2 96783.9

15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0 16, GROSS THERMAL ENERGY GENERATED (MWH) 1907510 11785887 236652981

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 620897 3917199 79603982

18. NET ELECTRICAL ENERGY GENERATED (MWH) 586117 3683393 74747912

19. UNIT SERVICE FACTOR

(%)

100.0 92.0 55.4

20. UNIT AVAILABILITY FACTOR

(%)

100.0 92.0 55.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.2 92.1 54.5

22. UNIT CAPACITY FACTOR (USING DER NFT) 96.2 88.4 52.3

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 38.5 UNIT FORCED OUTAGE HOURS (HRS) 0.0' O.0 60759.4

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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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE 1

COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

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

(MWe-NET) 1 796 17 791 2

793 18 788 3

789 19 785 l

4 789 20 780 5

787 21 781 6

782 22 783 7

785 23 786 8

775 24 786 9

780 25 790 10 787 26 790 11 798 27 793

)

12 794 28 796 13 787 29 793 14 787 30 788 15 785 31 790 16 788 1

1 4

• 9

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-289 UNIT NAME TMI-1 REPORT MONTH July 1994 DATE COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 i

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..1 REFUELING INFORMATION REQUEST

1. Name of Facility:

Three Mile Island Nuclear Station, Unit 1

2. Scheduled date for next refueling shutdown:

September 8, 1995

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

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment 7 N0

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

NA l

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:

i a) TMI will use the new Mark B10 fuel assembly in the Cycle 11 reload batch l

which is an upgraded design of the Mark B9 assembly used in Cycle 10.

The Mark B10 provides a leaf-type cruciform assembly holddown spring to replace the previous coil spring design which has experienced random failures during operation and requires visual inspection each outage.

The Mark B10 design meets all current BWFC fuel design criteria and is in use at other B&W 177 FA plants.

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

(a) 177 (b) 601

8. The present licensed spent fuel pool storaga 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.

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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