ML20097F914

Monthly Operating Rept for May 1992 for TMI-1

ML20097F914
Person / Time
Site:	Crane
Issue date:	05/31/1992
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-92-2082, NUDOCS 9206160167
Download: ML20097F914 (7)

Text

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GPU Nuclear Corporation a Nuclear

,o;'es:reo Middletran. Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 1

Writer's Direct Dial Number.'

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(717) 948-8005 June 11, 1992 i

C311-92-2082 a

i U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555 4

Gentlemen:

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Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. OPR-50 Docket No. 50-289 Monthly Operating Report for May 1992 Enclosed are two copies of the May 1992 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, Q%Ik tJ~

T.G.Broudton Vice President and Director, TMI-l WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector i

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9206160167 920531 PDR ADOCK 05000289

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GPU Nuclear Corporation is a subsidiary of General Pubke Utihties Corporation

OPERATIONS

SUMMARY

MAY 1992 The unit entered the month operating-at 100% power producing 858 MWe and continued full power operation for the entire month of May. On May 21st the annu-' emergency plan drill was completed successfully. During the month, the Seco.ity department completed an investigation of control room snd auxiliary 1

operator logging practices. The investigation was initiated as result of problems identified at several other plants where operators were fuand falsifying records associated with routine plant log taking rounds. One abnormality resulted in an auxiliary operator being suspended for a period cf five days. As a result of irregularities in some Control Room Operator logs, more definitive guidance was provided for documenting late or missed readings.

MAJOR SAFETY RELATED MAINTENANCE During May, the following major safety related maintenance activities were performed:

Station Blackout Diesel Generator EG-Y-4 The Station Blackout Diesel EG-Y-4 manufacturer, Coltec Industries, identified cracks resulting from mishandling of piston castings by a supplier during removal of casting risers. THI-1 was listed as having received two pistons of unknown origin. A review of maintenance records identified that the pistons had been installed in the number 2.and 5 upper cylinders of the SB0 diesel.

Fiber optic inspection of the number 2 and 5 piston skirts verified that these were the suspect pistons.

In accordance vith the manufacturer's recommendation, the engine was removed from service to replace the pistons.

Reassembly and testing will be completed in early June.

Reactor Coolant Pumo RC-P-1A The Reactor Coolant Pump RC-P-1A horizontal shaft vibration probe indicated high vibrations. Upon investigation, it was determined that the horizontal probe was giving erroneous readings and was declared out-of-service Input is being supplied via a cable connected from the motor frame vibration terminal box located in the relay room to PLF in the control room.

Vibration is now analyzed by collecting synchronous time average data-from the good vertical shaft probe and the two motor frame vibration probes.

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Feedwater Valve FW-V-16A Main feedwater Control Valve FW-V-16A was. intermittently cycling approximately 10% without a change in demand. Corrective maintenance-actionsLincluded-

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cleaning-the interior of the pilot valve and= replacing the following component parts: the Instrument Air in-line filters, IA-V-2217 (a tubing valve) and a summing module in the ICS.

FW-V-16A is currently operating as designed but-is-baing monitored for the short: term to ensure continued-satisfactory operation.

Feedwater Valve FW-V-928 feedwater System block valve FW-V-928 -limitorque operator ' closed' torque switch setting was increased to ensure that the operational:AP would be.

overcome in the event that valve closure would be: required. The~Limitorque-operator spring pack _was replaced during the 9R Outage.- The ' closed' setting-adjustment made after spring pack-replacement was based on =a calculation which-assumed that the feed water regulating valves would be closed.

1The-torque switch setting was increased after reevaluation to provide-additional thrust margin without exceeding the valve motor operator limits as recommended by Plant Engineering.

Auxiliary and Fuel Handlina Buildina Fan AH-E-14D Auxiliary and Fuel Handling Building exhaust fan AH-E-14D motor wasLremoved-to repair a motor ground. The fan motor was sent off-site for. rewinding-and is due back in June.

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OPERATING DATA REPORT DOCKET NO.

50-289 DATE June 13, 1992 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

3. REPORTING PERIOD:

MAY 1992

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 4

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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 MWo):

10. REASONS FOR RESTRICTIONS, IF ANY:

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THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 3647.0 155568.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744,0 3647.0 80378.0-

13. REACTOR RESERVE SHUTDOWN-HOURS (HRS) 0.0 0.0 2245.6

14. HOURS GENERATOR ON-LINE (HRS) 744.0-3647.0.

79303.2

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

16. GROSS THERMAL ENERGY GENERATED (MWH)-

1908127 9353272 193222318

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 632116 3122103 65116362

18. NET ELECTRICAL ENERGY GENERATED

( M'J")

596962 2947926 61105251

19. UNIT SERVICE FACTOR i.)

100.0 100.0 51.0

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 51.0

21. UNIT CAPACITY FACTOR (USING MDC NET) 102.1 102.8 50.0

32. UNIT CAPACITY FACTOR (USING DER NET) 98.0-98.7 48.0

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0

-43.3 I

UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60648.7

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

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

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4 AVERAGE DAILY Uh1T POWER LEVEL DOCKET NO.

50-289 UNIT THI-1 I

DATE Junn 11, 1492 COMPLETED BY W G HEYSEK TELEPHONE (717).948-8191 4

MONTH:

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

(MWe-NET) 1 805 17 800 j

2

.794 18 796 3

796 19 801 4

806 20 804 5

809 21 802 4

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809 22 798 7

809 23-794 8

806 24 800-9 803 25 809 4

10 802 26 806 1

11 798 27-807-l 12 802 28 807 13 798 29 805 14 798 30 805 4

15 802 31

-798 16 801 4

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UNIT SHUT 30WNS AND POWER REDUCTIONS DOCKET No.

50-289 UNIT NAME TMI-1 REFORT MONTH May 1992 DATE June ll, 1992 j

COMPLETED BY W. G. Heysek i

TELEPHONE (717) 948-G191 Method of Licensee System :caponent Cause & Corrective No-Date Type

• Duration Reason' Shutting Event k.le Code Action to (Hours)

Down.

Report #

Prevent Recurrence Reactor' NONE 1

2 3

4 F Forced Reason Method Exhibit G - Inst.uctions for S Scheduled A-Equipnent Falture (Explain) 1 Manual preparation of Data Entry Sheets B-Maintenance or Test 2-Manual scram for Licensee Event Report (LER)

C-Refueting-3-Automatic Scrare File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain) l t

E-Operator Training & Licensing Examirr '.on 5 Exhibit 1 same source

' F-Administrative G-Operational Error (Explein) 6 Actually used exhibits F & II MUREG 0151 N-Other (Explain) 6

s REFUELING INFORMATION RE00EST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

September 17, 1993 (10R) 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? NA If answer is yes, in general, what will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Saft.ty Review Committee to determine 4

i whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

If no such review has taken place, when is it scheduled?

5.

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

None planned.

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 GPU Nuclear has installed four Westinghouse Lead Test Assemblies during the reload of the TMI-1 core for cycle 9 operation.

Westinghouse fuel technology will be utilized to the extant possible.

7.

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

(a) 177 (b) 521 8.

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

The present licensed capacity is 1496. Reracking of spent fuel pool

'A' to attain the licensed capacity is in progress.

9.

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

The 9R (1991) refueling discharge was the last to allow full core off-load capacity (177 fuel assemblies).

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