ML20117M158

Monthly Operating Rept for May 1996 for Three Mile Island Unit 1

ML20117M158
Person / Time
Site:	Three Mile Island
Issue date:	05/31/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2198, NUDOCS 9606180159
Download: ML20117M158 (7)

Text

GPU Nuclear Corporation Nuclear -~4-P.O. Box 480 Middletown. Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Number; (717) 948-8005 June 11,1996 6710-96-2198 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 1996 Enclosed are two copies of the May 1996 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, 17007J 3. xnuhei Vice President and Director, TMl WGH e

cc: Administrator, Region I TMI Senier Resident Inspector 96001 t 9606180159 960531 goa noocs 05=gg9 ff}((

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OPERATIONS

SUMMARY

May 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 approximately 807 MWe during May.

MAJOR SAFETY RELATED MAINTENANCE ,

There were no major safety related maintenance items completed during the month.

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, m OPERATING DATA REPORT s

DOCKET NO. 50-289 DATE June 11, 1996 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

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

2. REPORTING PERIOD: MAY 1996

3. LICENSED THERMAL POWER: 2568

4. NAMEPLATE RATING (GROSS MWe): 872

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:

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMMULATIVE

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11. HOU';S IN REPORTING PERIOD (HRS) 744.0 3647.0 190632.0 l

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 , 3647.0 113190.1 1

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 744.0 3647.0 112028.3 ,

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

.16. GROSS THERMAL ENERGY GENERATED (MWH) 1,908,743.0 9,357,586.6 275,472.512.6 l

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 635,043.0 3,146,726.0 92,600,200.1

18. NET ELECTRICAL ENERGY GENERATED (MWH) 600,416.0 2,973,777.0 87,017,181.1

19. UNIT SERVICE FACTOR (%) 100.0 100.0 58.8

. 20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 58.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 102.7 103.7 58.1

22. UNIT CAPACITY FACTOR (USING DER NET) 98.5 99.6 55.7

23 UNIT FORCED OUTAGE RATE (%) 0.0 0.0 35 1 j

UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761 2 l

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

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

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. A.VERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 UNIT TMI-1 DATE g.ye 11, 1006 COMPLETED BY W G HEYSEK TELEPHONE- (717) 948-8191

. MONTH: MAY DAY AVERAGE DAILY POWER L EVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWe-NET) 1 812 17 808 2 808 18 799 3 808 19 789 4' 807 20 785 5 808 21 789 6 810 22 796 7 813 23 795 8 811 24 802 9 808 25 812 10- 804 26 814 11 801 27 813 -

12 bi5 28 813 13 818 29 813 14 817 30 812 15 814 31 810 16 813 i

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DOCKET NO. 50-289 UNIT NAME TMI-l -

DATE June 11, 1996 -

REPORT MONTH May 1996 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 Mehod of Ixsisee Sysaem Canyonent Cape & Camme No- Shurtmg Event Code Code Actum am Date Type' Duram Reason' Doms Reporte Prmet Recurence M8"") Reactor' *&* ,p None 1 2 3 4 F Forced Reason Method Exhibe G hiseuctxes fa S Sduduled A-Eqmpment Fahne @gdam) 14tanud preparanon of D.:a Entry Sheets B-Maantenance or Test 2-Marmal L: ram Lu laceensee Everd Report (LERJ C Refuelmg 1 Automanc Scrum Fde(NUREG4160 ERegulatory Restncton 44MurlExplam)

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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 restart following current refueling: NA ,

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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 include references to the GPU Nuclear analysis methods applied to the reload.

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.

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-087 (core thermal hydraulics), TR-078 (FSAR safety analyses) and TR-092P (design and setpoints methodology) submitted to the NRC.

The NRC has issued an SER for TR-071 on February 21,1996 and has recently indicated that Generic Letter 83-11 Supplement I is on hold.

Accordingly NRC review and approvalis needed for each of the three I remaining GPU Nuclear Topical Reports. A meeting with NRC staff reviewers was held on May 30,1996 during which the Cycle 12 reload j analysis schedules were discussed. At this time, completion of the NRC review and issuance of NRC SERs by the following critical approval dates is achieveable: TR-087 8/1/96 TR-078 10/1/96 TR-092P 10/1/96 d

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.

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

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 fulllicensed capacity will be attained. Phase 11 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 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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