ML20095E052

Monthly Operating Rept for Nov 1995 for TMI-1

ML20095E052
Person / Time
Site:	Three Mile Island
Issue date:	11/30/1995
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-95-2519, NUDOCS 9512140160
Download: ML20095E052 (6)

Text

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GPU Nuclear Corporation M

eM Route 44' S ut" P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial Number:

(717) 948-8005 December 12, 1995 C311-95-2519 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 November 1995 Enclosed are two copies of the November 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, J. Knubel Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector T95001

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9512140150 951130

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1 FDR ADOCK 05000289 R..

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OPERATIONS

SUMMARY

November 1995 The plant entered the month operating at 100% power and remained at that power level for the remainder of the month. Net unit electrical output averaged approximately 820 MWe dunng i

November.

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

l Fire Service Pump Check Valve FS-V-27 Fire Service Pump FS-P-3 Discharge Check Valve FS-V-27 was inspected for Microbiological:s Induced Corrosion inspection by Plant Engineering. The valve internals and piping were accessed through the valve body to bonnet mechanical connection. This inspection was a follow-up to an inspection performed in 1994. Ultrasonic testing was performed to evaluate any variation in valve i

body material thickness since the last im.pection and samples were taken for microbiological study. Upon completion of the inspection, the valve was reassembled and returned to service.

1 The results of the inspection will be evaluated after the microbiological data has been received.

RC-P-lD #1 Seal Leakoff Flow Transmitter MU-9-FT4 Reactor Coolant Pump "D" #1 seal leakoff flow transmitter, MU-9-FT4, failed. A replacement transmitter assembly with amplifier and cable was obtained from the warehouse and installed during a Reactor Building entry, During this work, a tubing leak on MU-9-FE4 was corrected. In place checks were performed on the new transmitter prior to returning it to service and the results were satisfactory. Inspection of the old transmitter revealed a reddish substance on the cross hair divider and on the flow meter. During the next Reactor Building entry, scheduled for December, inspections are being planned for MU-9-FT2, Reactor Coolant Pump "B" #1 seal leakoff transnditer for comparison.

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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:

NOVEMBER 1995 l

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3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWe):

872 l l

5. DESIGN ELECTRICAL RATING (NET MWe):

819 l l

6. MAXIMUM DEPEN?.ABLE CAPACITY (GROSS MWe):

934 l l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l l

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

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

,l

10. REASONS FOR RESTRICTIONS, IF ANY:

i THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 720.0 8016.0

?86241.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 720.0 7210.4 108799.1

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

0. 0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 720.0 7182.2 107637.3

15. UNIT RESERVE C::"TDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS THERMIL ENP 2GY GENERATED (MWH) 1847111 18289296 264205567

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 624698 6124586 88807840

18. NET ELECTRICAL ENERGY GENERATED (MWH) 590553 5777793 83433211

19. UNIT SERVICE FACTOR

(%)

100.0 89.6 57.8

20. UNIT AVAILABILITY FACTOR

(%)

100.0 89.6 57.8

21. UNIT CAEACITY FACTOR (USING MDC NET) 104.4 91.7 57.0

22. UNIT CAPACITY FACTOR (USING DER NET) 100.1 88.0 54.7

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 36.0 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. 5F SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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AVERAGE DAILY UNIT POWER LEVEL

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i DOCKET NO.

50-289 UNIT TMI-1 DATE

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COMPLETED BY W G HEYSEK TELEPHONE (757) 948-8191 MONTH:

NOVEMBER i

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

(MWe-NET)

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1 813 17 825 l

2 804 18-823 3

808 19 821

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4' 822 20 821 5

823 21

'821 6

824 22 823 7

822

'23 823

)

s 8

819 24 823 5

9 822 25 825 l

10 820 26 821 11 811

'27 819 i

12 822 28 814 13 824 29 824 14 822 30 825 15 821 31 NA 16 824 4

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t DOCKET 180.

50-289

~ UNIT NAME TMI-1 DATE REPORT MONTH November 1995 COMPLETED bY W. G. Heysek

• TELEPHONE (717).948-8191 i

Method of lacemee Syesa Component Came & Corracave Even Code Code Actua to Rep,t shumng Date Type' Duranon Reason' preseni Recanence po,,,

NI Reactor'

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i None t

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2 3

4 F Fanzd Reason Method Exhiba G-Instructens fur S Scheduled A-Eqmpment Faihue(Explan) 3-Manual preparamon ofDt3 Eg. Sheets R-Mankmence ar Test 2-Manud Screen for Lacennes Event Repart(LElt)

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C-Refhehng 3-Automatic Senus File (NUREG4161)

SRegulatory Res:ncton 44ther(Explaud E4psemTmning &Imeng Examn**

5 Exhinain.nenoma F-A -

Goperanonal Erra(Expland floen(Expim0 6 AcantymedexhibeF&RNUREGOW S

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a REFUELING INFORMATION REOUEST

1. I4ame of Facility: Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown: September 12,1997 3.

Scheduled date for restart following current refueling: NA

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

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: NA 6.

Important licensing considerations associated with refueling, e.g. new or difTerent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: None

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 683

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. Phase II is 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 campletion of the rerack project full core off-load is assured through the end of the current operating license and beyond.

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