Text

Monthly Operating Rept for Aug 1994 for TMI-1
	ML20073B176
Person / Time
Site:	Crane
Issue date:	08/31/1994
From:	Broughton T, Heysek W; GENERAL PUBLIC UTILITIES CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	C311-94-2130, NUDOCS 9409210210
	Download: ML20073B176 (7)
	v • d • e

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GPU Nuclear Corporation a Nuclear "n:ntr*

Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial Number:

(717) 948-8005 September 13, 1994 C311-94-2130 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 August 1994 Enclosed are two copies of the August 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, M

M T. G. Broug' on Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector.

T94001

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to cvvvJ 9409210210 940831 PDR ADOCK 05000289 i

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. GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation i

OPERATIONS

SUMMARY

August 1954 The plant entered the month operating at 100% power and remained essentially at that level through 1458 hours0.0169 days 0.405 hours 0.00241 weeks 5.54769e-4 months on August 31. At that time a power reduction was initiated to replace a faulty Main Turbine Electro-Hydraulic Control (EHC)

Load Reference Card.

The unit was taken off line at 1658 and the turbine work was performed while the reactor plant was maintained at 5-10% power.

Following the repair, the unit was brought back on line at 1843 and power was gradually escalated to 100%. Unit electrical output averaged approximately 786 MWe during August.

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

NR-V-13D Piping I

A pin hole leak in the 12" pipe upstream of Nuclear Service Closed Cooler NS-C-10 backwash valve NR-V-13D was repaired by welding a half coupling over the hole.

The weld was satisfactorily tested using the magnetic particle process prior to returning the system to service.

Intermediate Closed Cooling Water Pump IC-P-1A Intermediate Closed Cooling Water pump IC-P-1A was removed from service to replace a leaking mechanical seal.

IC-P-1A was retested satisfactorily and l

l returned to service.

Later in the month, shaft leakage was observed and is I

being monitored.

l Beckman Analyzer CA-G-1A l

l A failed pump diaphragm caused the removal of Beckman Analyzer CA-G-1A from service. The pump was disassembled and rebuilt using new parts.

Post maintenance testing was completed satisfactorily and the pump was returned to service.

Main Turbine Electro-H_ydraulic Control System

]

On August 31 at 1458 hours0.0169 days 0.405 hours 0.00241 weeks 5.54769e-4 months , a power reduction was initiated for the purpose of

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replacing a failed Main Turbine Electro-Hydraulic Control (EHC) system 3

computer card. The card provides a load control reference signal and its

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output had failed low causing plant oscillation. At 1658 hours0.0192 days 0.461 hours 0.00274 weeks 6.30869e-4 months , the breakers were opened, the turbine taken off-line, and the EHC card replaced.

The breakers were closed at 1843 hours0.0213 days 0.512 hours 0.00305 weeks 7.012615e-4 months and the plant returned to 100% power at I

0255 hours0.00295 days 0.0708 hours 4.21627e-4 weeks 9.70275e-5 months on September 1.

2

Integrated Control S_ystem With the turbine plant off-line for EHC repairs, an electronic module in the Plant Integrated Control System (ICS) was replaced. The ICS developed a problem in the 'B' Feedwater Control Loop which was attributed to the ICS module.

3 1

~

1 OPERATING DATA REPORT i

DOCKET NO.

50-289 i

DATE September 13, 1994 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948 8191 7

1. UNIT NAME:

THREE MILE ISLAND UNIT 1-l NOTES:

l

2. REPORTING PERIOD:

AUGUST 1994 l

l

3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWe):

811 l l

S. DESIGN ELECTRICAL RATING (NET MWe):

819 l

-l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

834 l l

l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l l

I I

B.

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:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 5831.0 175296.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5433.7 98659.7

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

-0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 742.3 5421.4 97526.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1891486 13677373 238544467

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 619264 4536463 80223246

18. NET ELECTRICAL ENERGY GENERATED (MWH) 584514 4267907 75332426

19. UNIT SERVICE FACTOR

(%)

99.8 93.0 55.6

20. UNIT AVAILABILITY FACTOR

(%)

99.8 93.0 55.6

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.0 93.1 54.7

22. UNIT CAPACITY FACTOR (USING DER NET) 95.9 89.4 52.5 j

23. UNIT FORCED OUTAGE RATE

(%)

0.2 0.0 38.3 UNIT FORCED OUTAGE HOURS (HRS) 1.8 1.8 60761.2

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

1

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

1 l

l i

4 i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE September 13, 1994 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

AUGUST i

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

(MWe-NET) 1 787 17 794 2

786 18 789 3

789 19 792 4

786 20 789 5

793 21 788 6

806 22 795 7

800 23 803 8

799 24 802 9

793 25 797 10 794 26 794 11 797 27 790 12 790 28 774 13 783 29 792 14 785 30 786 15 801 31 582 16 800 i

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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

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

NO

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:

c a) TMI will use the new Mark BIO fuel assembly in the Cycle 11 reload batch 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 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 current operating license and beyond.

7

_

ML20073B176

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Subject:

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