ML20112A217

Monthly Operating Rept for Apr 1996 for Three Mile Island Nuclear Station Unit 1

ML20112A217
Person / Time
Site:	Three Mile Island
Issue date:	04/30/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2166, NUDOCS 9605200407
Download: ML20112A217 (7)

Text

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' GPU Nuclear Corporation

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

i (717) 948-8005 May 13,1996 6710-96-2166 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 Repon for April 1996 Enclosed are two copies of the April 1996 Monthly Operating Repon for Three Mile Island Nuclear Station, Unit 1.

Sincerely,

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9605200407 960430 t PDR ADOCK 05000289 PDR J. Knubel R _

Vice President and Director, TMI WGH Attachment cc: Administrator, Region I TMI Senior Resident Inspector 96001 //qv '

/O GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation

OPERATIONS

SUMMARY

April 1996 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 appmximately 812 MWe during April.

MAJOR SAFETY RELATED MAINTENANCE The following major safety related maintenance item was accomplished during the month:

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Emergency Diesel Genemtors EG-Y-1 A and B l

.The Emergency Diesel Generators EG-Y-1 A and B were removed from service for their j scheduled annual overhauls. EG-Y-1B was removed from service during the week of April l 15th and EG-Y-1 A was removed from service during the week of April 22nd. The work accomplished on both engines and associated equipment us identical: a major engine inspection and overhaul, relief valve testing, oil changes, instrument calibrations, breaker j tests, and electrical motor inspections. All work was accomplished with no major i discrepancies found on either Emergency Diesel Generators. EG-Y-1 A and B were retested i satisfactorily and returned to service.

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OPERATING DATA REPORT DOCKET NO. 50-289 DATE COMPLETED BY W G HEYSEK l OPERATING STATUS TELEPHONE (717) 948-8191 l l

1. UNIT NAME: THREE MILE ISLAND UNIT 1 l NOTES: l l

2. REPORTING PERIOD: APRIL 1996 l l l

3. LICENSED THERMAL POWER: 2568 l l

4. NAMEPLATE RATING (GROSS MWe): 872 l l

5. DESIGN ELECTRICAL RATING (NET MWe): 819 l l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 834 l l 1

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 786 l l I I

8. 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: I TH*iS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 719.0 2903.0 189888.0

13. NUMBER OF HOURS REACTOR WAS CRITICAL (MRS) 719.0 2903.0 112446.1 l 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 719.0 2903.0 111284.3 l

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1844646 7448844 273563770 i 27. GROSS ELECTRICAL ENERGY GENERATED (MWH) 617333 2511683 91965157

18. NET ELECTRICAL ENERGY GENERATED (MWH) 583865 2373361 86116765 l

19. UNIT SERVICE FACTOR (%) 100.0 100.0 58.6 l 20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 58.6 57.9

21. UNIT CAPACITY FACTOR (USING MDC NET) 103.3 104.0

33. UNIT CAPACITY FACTOR (USING DER ACT) 99.2 99.8 55.6

23. UNIT FORCED OUTAGE RATE (t) 0.0 0.0 35.2 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. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: __

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I AVERAGE DAILY UNIT POWER LEVEL  !

DOCKET NO. 50-289 UNIT TMI-1 6 DATE COMPLETED B W G HEYSEK TELEPHONE (717) 948-8191 MONTH: APRIL l

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-NET) (MWe-NET) i 1 817 17 817 2 818 18 814 3 814 19 812 ,

4 816 20 802 5- 818 21 802.

6 821 22. 798 l 7 821 23 794 8 821 24 l 814  !

9 822 25 809  ;

i 10 820 26 806 '

11 813 27 815 12 804 28 813 13 811 29 801 ,

14 816 30 802 f 15 818 31 $N/A i 16 815.

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DOCKET No. 50-289 '

UNIT NAME TMI-l DATE .

REPORT MONTH April 1996 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 1

Method of Licensee System Component Cause & Comcave Shuteng Event Code Code Actum to No- Dare Type' Duranon Reason' Ikm1s Reporte Prenne Recurrence

@"I Reactor 8

'A'~ , ,

None i

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1 2 3 4 F Forced Reason Method Exlutet G. Instrucaans 6r 5 Scheduled A-Eqinpment Fadure(Eglars) 1-Manual preparem ofData Enny Sheets EMantenance or Tem 2-Manual Scrarn forlacensee Event Report (LER)

C-Refuehng 3-Ausornanc Scran Fee (NUltEG 0161)

D-Rgulatory Resenctum 40ther(Exphen)

EOperator Teng a Ucenug Emunam 5 Exhide i .ame.ource F-A-G(Wanrud Emu (Explaso H-Other(Explam) 6 ActumEy used extubits F & G NLREG 0161 4

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I REFUELING INFORMATION REOUEST

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

2. Scheduled date for next refueling shutdown: September 5,1997

3. Scheduled date for restait following current refueling: NA

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes. To support GPU Nuclear plans to do independent reload analyses for Cycle 12 as discussed in response to question 6 below, T.S. 6.9.5.2 would require revision to i include references to the GPU Nuclear analysis methods applied to the reload consistent with the guidance of Draft Generic Letter (GL) 83-11.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: A Technical Specification Change Request for the changes as discussed above would be submitted after f9rmal issuance of GL 83-11.

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: GPU Nuclear Letter 6710-96-2092, dated March 28,1996 confirmed plans to perform independent reload design evaluations for Cycle 12, the next operation cycle, based on NRC approved methods described in GPU Nuclear Topical Reports TR-091 (core physics), TR-078 (core thermal hydraulics), TR 087 (FSAR safety analyses) and TR-092P (design and setpoints meth ., logy) submitted to the NRC. As submitted in the March 28 letter, Cycle 12 independent reload design activities and application results anticipate the use of formally issued NRC Draft Generic Letter 83-11, Supplement 1, " Licensee Qualification for Performing Safety Analyses". Per the Draft GL 83-11 guidance, the GPU Nuclear Cycle 12 reload program and results are expected to be available for NRC review in the March to April 1997 time frame. It is expected that the Cycle 12 results will be licensed in accordance with the requirements of 10 CFR 50.59 safety evaluations for changes.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 864 5

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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 I 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.

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

l 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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