ML20069M388

Monthly Operating Rept for May 1994 for TMI-1

ML20069M388
Person / Time
Site:	Crane
Issue date:	05/31/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2084, NUDOCS 9406210329
Download: ML20069M388 (6)

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1 GPU Nuclear Corporation G U Nuclear "n::ur Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial Number:

(717) 948-8005 l

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June 13, 1994 C311-94-2084 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 May 1994 Enclosed are two copies of the May 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

1 Sincerely,

.J'dhm 4/~

T.G.Broudton Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector 9406210329 940531 PDR ADOCK 05000289 p

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PDR I

GPU Nuclear Corporation is a subsidiary of General Public Utihties Corporation (f

4 OPERATIONS

SUMMARY

May 1994 i

The plant entered the month operating at approximately 100% power until 0104 on May 30. At that time, power reduction to 50% was initiated in support of efforts to locate and repair main condenser tube leaks. At approximately 0200, power was stabilized at 50% and remained at that level through the end of the month. Unit electrical output averaged approximately 777 MWe during May.

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

Emergency Diesel Generators EG-Y-1A/B Emergency Diesel Generators EG-Y-1A and B were removed from service to perform the scheduled annual overhaul.

Work performed included instrument calibrations, circuit breaker tests, motor inspections, check and relief valve testing, and the engine overhaul and inspection.

The EG-Y-1A engine inspection was completed with no major discrepancies.

The engine was test run satisfactorily and returned to service.

Inspection of the EG-Y-1B engine revealed a cracked #8 lower piston which required replacement.

Six additional piston pairs were inspected with no other deficiencies found.

During the post maintenance run on EG-Y-1B, the generator recorded only 2.82 MWE instead of the required 3.0 MWE.

Fuel rack j

and governor inspections were performed and the engine loaded to 2.95 MWE during the subsequent test run.

The engine was determined to be operational and returned to service.

Further diesel operation and testing were performed with a gage installed on the engine governor to monitor oil pressure.

EG-Y-1B was test run for approximately 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> while oil pressure, MWE, governor temperature, and limit position indication readings were taken.

The test run verified the engine was capable of carring its required load.

Pl ant Engineering is evaluating the need for governor replacement.

Emergency Diesel Air Start Compressor EG-P-1B Emergency Diesel Air Start Compressor EG-P-1B was removed from service when it failed to start off the battery.

Inspection of the batteries found them maintaining insufficient charge to start the compressor. After new batteries were installed and tested, the compressor was returned to service.

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OPERATING DATA REPORT

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DOCKET NO.

50-289 DATE Juen 13, 1994 COMPLETED BY W G HEYSEK

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OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

2. REPORTING PERIOD:

MAY 1994

3. LICENSED THERMAL POWER:

2568

4. NAMEPLATE RATING (GROSS MWe):

871

5. DESIGN ELECTRICAL RATING (NET MWe):

819

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-l

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

10. REASONS FOR RESTRICTIONS, IF ANY:

1 THIS MONTH YR-TO '11d4 CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 3623.0 173088.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 3411.2 96637.4

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2283.8

14. HOURS GENERATOR ON-LINE (HRS) 744.0 3407,9 95512.6

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1848344 8550207 233416859

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 612078 2865181 78551964

18. NET ELECTRICAL ENERGY GENERATED (MWH) 577775 2694296 73758815

19. UNIT SERVICE FACTOR

(%)

100.0 94.1 55.2

20. UNIT AVAILABILITY FACTOR

(%)

100.0 94.1 55.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 98.8 94.6 54.2

22. UNIT CAPACITY FACTOR (USING DER NET) 94.8 90.8 52.0

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 38.8 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60759.4

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION OF EACH): The plant is scheduled to shutdown On June 1, 1994 fOr 9 days.

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

3

e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 l

UNIT TMI-1 DATE June 13, 1994 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

MAY f

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

(MWe-NET) 1 803 17 809 2

812 18 809 3

812 19 810 4

810 20 810 5

807 21 807 6

807 22 800 l

7 811 23 794 l

8 808 24 797 9

805 25 795 10 806 26 798 11 806 27 808 12 805 28 807 13 810 29 803 14 810 30 373 15 801 31 342 16 800 l

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9 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-289 UNIT NAME TMI-1 REPORT MONTH May 1994 DATE June 13, 1994-COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 c-a cornci une 4,aean c,,,,,,

mg Event Code Acekin to Type' Ibruke Remme' hating ca Pi-s Recurveme 04mwn)

Ik=wn hw s 3 94-04 5-30-94 S

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4 None SG COND The unit was reduced to 50% power on May 30 in stoport of efforts to locate and repair main condenser tube leaks.

Sequentially, the "A" and "B" sides of the condenser were removed from service, leak tested and repaired. The power reduction contirmed into the next month.

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3 4

F Forced Exhibit G - Instructions for Reason Method preparation of Data Entry Sheets S Scheduled A-Equipment Feiture (Emplain) 1-Manual for Licensee Event Report (LER)

B-Maintenance or Test 2 Manual Scram File (NUREG-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Explain) r E. Operator Training & Licensing Examination 3 Exhibit 1 some source F-Artmi n i s t r et i v e 6-operational Error (Explain) cU Actually used exhibits F & !! NUREG C161 94-Ot her (Emplain) 5

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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 l

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

NO l

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

NA i

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) 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 B9 provides a leaf-type cruciform assembly holddown spring to l

replace the previous coil spring designs that has experienced random l

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 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.

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 l

current operating license and beyond.

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