ML20117D369

Monthly Operating Rept for March 1996 for TMI-1

ML20117D369
Person / Time
Site:	Crane
Issue date:	03/31/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2130, NUDOCS 9604230073
Download: ML20117D369 (7)

Text

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f 4-48 tRC TMI 717 948 1163 P.02 GPU Nuclear Corporation M 98r aoute dd' Sout" P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717) 944 7621 Writer's Direct Dial Number:

d (717) 948-8005 Aprtl 15, 1996 6710-96-2130 U. S. Nuclear Regulatory Commission Atta: 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 March 1996 Enclosed are two copies of the March 1996 Monthly Operating Report for Thme Mile Island Nuclear Station, Unit 1.

Sincerely, j

9604230073 960331 PDR ADOCK 05000209 J. Knubel P DIT R

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Attachment cc: Administrator,ltegion I TMI Senior Resident Inspector 96001-hu

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" 7 % 1 417 949 1163 '

P.03 I

i OPERATIONS

SUMMARY

March 1996 4'

The plant entered the month operating at 100% power and remained at that power level for the i

remainder of the month. Net unit electrical output avenged approximately.819 MWe during March.

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

2 Auxiliary and Fuel Handfine hildine Fihers AH-F-2A/C l

j The Auxilairy and Fuel Handling Building charcoal filters were replaced in filtration units AH-P-2A and AH-F-2C. In addition, the 72 HEPA filters were replaced in AH-F-2A. Following 1

completion of the work, the units were tested and found to perform satisfactorily. AH-F-2A and C were returned to service.

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l OPERATING DATA REPORT DOCKET NO.

50 289

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~ 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:

MARCH 1996 l.

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3. LICENSED THERMI' POWER:

2568 l l

4, NAMEPLATE RATI!h,'(GROSS MWe):

8'/2 j l

5. DESIGN ELECTRICAL RATING (NET MWe):

819 l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS,MWe):

834 l l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l

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8. IF CRANGES 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 MONTE YR-TO-DATE CUMMULATIVE I i

11. HOURS IN, REPORTING PERIOD, (NRS) 744.0 2184.0 189169.0-

12. NUMBER OF HOURS REACTOR WAS CRITICAL (NRS) 744.0 2184.0 111727.1 i

'13. REACTOR RESERVE SNUTDOWN NOURS (NRS) 0.0

,2184.0.

110565.3 0.0 2284.0

14. HOURS GENERATOR ON-LINE (hrs)'

744.0

15. UNIT RESERVE SNUTDOWN HOURS (NRS) ~

0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWN) 1909976 5604198 271719124

17. GROSS ELECTRICAL ENERGY GENERATED

( MWN ) '

644869 1894350 91347824

18. NET ELECTRICAL ENERGY GENERATED (MWN) 609344.

1789496 85832900

19. UNIT SERVICE FACTOR (t) 100.0 100.0 58.4

20. UNIT AVAILABILITY FACTOR tt) 100.0 100.0 98.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 104.2 104.2' 51.7 22.. UNIT CAPACITY FACTOR (USING DER NET) 100.0' 100.0 55.4

23. UNIT FORCED OUTAGE RATE (t) 0.0 0.0 35.4 UNIT FORCED OUTAGE NOURS (NRS) 0.0 0.0 60761.2

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

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

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r%Y-31-1S HRC Tr1!

717 948 1163 P.05

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

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

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

.(MWe-NET) 1 823 17 821 3

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. 822 18 817 j.

3 823 19 814 4

823 20 819 5

818 21 819 6

817 22' 821 7

821 23 820 l

8 824 24 820 9

821 25 812 10 818 26 817 11 819 27 822 12 820 28 822 13 819 29 821 14 815 30 818 15 811 31 815 819 16 4

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l REEUEllNGINFORMATION REQUEST

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

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

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3. Scheduled date for restart following current re'veling: NA l

4. Will refueling or resumption of operation thereaAer require a technical 3

i specification change or other license amendment?. Yes. To support GPU Nuclear plans to de ladependent reload analyses for Cycle 12 as discussed l

In response to question 6 below, T.S. 6.5.9.2'would require revision to l

Include references to the GPU Nuclear analysis methods applied to the reload consistent with the guidance of Draft Generic I4tter (GL) 83-11.

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5. Scheduled date(s) for submitting proposed licensing action and supporting i

infciw.stiori: A Technical Specification Change Raquest for the changes as discumnad above would be sulunitted after formal issuance of GL 83-11.

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6. Important licensing considerations assoc'inted with refueling, e.g. new or

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different fuel design or supplier, unreviewed design or performance analysis j

methods, significant changes in fuel design, new apar=dag procedures: GPU l

Nuclear IAtter 671496-2092, dated March 28,1996 confirmed plans to perfonn reload design evaluations for Cycle 12, the mat l

operation cycle, based on e':r'y approved vender methods described i

in GPU Nuclear Topical Reports TR-091 (core physics), TR-078 (core j

thermal hydraulles), TR-087 (FSAR safety analyses) and TR-092P (design -

and setpoints methodology) subadtted to the NRC. As subenitted in the March 28 letter,, Cycle 12 ledarandant reload design actistles and i

appHeatlan results anticipate the use of fonnauy issued NRC Draft l

Generic IAtter 83-11, Supplement 1, " Licensee Qualification for.

i Perforsning Safety Analyses". Per the Draft GL 83-11 guidanea, the GPU l

Nuclear Cycle 12 reload program and results are espected to be available for NRC review in the March to Aprl! 1997 time ftsers.~ It is expected that the Cycle 12 risults will be llemaand in accordance'with the j

requirements of 10 CFR 50.59 safety eval==tiana for changes.

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7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage i

pool: (a) 177 (b) 683 l

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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 i

increase spent fuel pool storage capacity pennits storage of 1342 assemblies. Upen completion of Phase H of the reracking prqject, the full licensed capacity will be attained. Phase H is espected 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 and 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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