ML20081B934

Monthly Operating Rept for Feb 1995 for TMI-1

ML20081B934
Person / Time
Site:	Three Mile Island
Issue date:	02/28/1995
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-95-2145, NUDOCS 9503170039
Download: ML20081B934 (7)

Text

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1. u GPU Nuclear Corporation

-Nuclear an:ntr*

Middletown. Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Number:

(717) 948-8005 March 10,1995 C311-95-2145 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 February 1995 Enclosed are two copies of the February 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely,

[ M~

T. G. Brou hton Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TM1 Senior Resident Inspac. tor T95001 170003 i i

9503170039 950228 I PDR ADOCK 05000289 \

R PDR GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation

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. '0PERATIONS

SUMMARY

February 1995  !

The plant entered the' month operating at 100% power and' remained-at that level -i throughout'the entire month. Net unit electrical' output averaged ,

approximately 822 MWe during February.

l MAJOR SAFETY'RELATED MAINTENANCE j

The following is a' summary of major safety related maintenance items  ;

accomplished during the month.

BUILDING SPRAY FLOW TRANSMITTERS BSIDTP1 AND BSIDPT2 The Building Spray Pump (BS-P-1A and B) discharge flow transmitters, BSIDPT1 ,

and BSIDPT2, were removed from service to reverse the 4-valve manifolds and i eliminate the drain valves. . Engineering Evaluation'#94-0311 directed that'the work be performed to eliminate previous valve manipulation errors which resulted from the orientation of the manifolds. After both manifolds were, reoriented,. post maintenance testing was completed satisfactorily on BSIDPT1 and only partially completed on BSIDPT2:-the signal verification was completed but the leak check of the tubing fittings was not performed and will be rescheduled. , ,

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1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 UNIT TMI-1 DATE March 10,1995 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH: FEBRUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) .

(MWe-NET) 1 822 17 822 2 823 18 823 3 826 19 822 4 824 20 820 5 825 21 821 6 821 22 823 7 817 23 822 8 815 24 821 9 816 25 824 10 821 26 823 '

11 823 27 824 12 825 .28 822 13 822 29 NA 14 821 30 NA 15 822 31 NA 16 822 i

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p, OPERATING DATA REPORT DOCKET NO. 50-289 DATE March 10,1995 COMPLETED BY. W G HEYSEK-OPERATING STATUS TELEPHONE (717) 948-8191

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

2. REPORTING PERIOD: FEBRUARY 1995 l l

3. LICENSED THERMAL POWER: 2568 l l

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

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

11. HOURS IN REPORTING PERIOD (HRS). 672.0 1416.0 179641.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 672.0 1416.0 103004.7

13. REACTOR RESERVE SHUTDL.?N HOURS (HRS) 0.0 0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 672.0 1416.0 101871.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1724463 3633206 249549477

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 584856 1232044 83915298

18. NET ELECTRICAL ENERGY GENERATED (MWH) 552322 1163734 78819152

19. UNIT SERVICE FACTOR (%) 100.0 .100.0 56.7

20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 56.7

21. UNIT CAPACITY FACTOR (USING MDC NET)- 104.6 104.6 55.8

22. UNIT CAPACITY FACTOR (USING DER NET) 100.4 100.3 53.6

23. UNIT FORCED OUTAGE RATE (%) 0.0 0.0 37.3 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2

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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REFUELING INFORMATION REQUEST t

m . 1.-Name of Facility: Three Mile Island Nuclear Station, Unit.1 i l

2. Scheduled date for next refueling shutdown:- September 8, 1995 l

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? N0  ;

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

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:

a) TMI will use the new Mark B10 fuel assembly in the Cycle 11' reload batch which is an upgraded design of the Mark B9 assembly used in Cycle.10.

The Mark B10 provides a leaf-type cruciform assembly holddown spring to t replace the previous coil spring design which has experienced random failures during operation and requires visual inspection each outage.  !

The Mark B10 design meets all current BWFC fuel design criteria and.is in.  !

use at other B&W 177 FA plants.-

b) TMI also will use fcur new Westinghouse Lead Test Assemblies -(LTA) in the Cycle 11 reload batch. Their planned operation' is for three consecutive ,

cycles with discharge at end-of-Cycle 13.  :

The four W LTAs inserted in Cycle 9 were discharged at E0C-9 due to  !

detection of fuel rod failures caused by grid-to-rod fretting similar to  !

that seen in W Vantage 5H fuel designs. The Cycle 11 LTAs will'use the ,

generic W recommended design fix'of rotated intermediate spacer grids;to minimize flow-induced fuel vibrations and thus eliminate fretting. A- i prototype LTA was flow-tested to demonstrate the effectiveness of the fix. The production LTA will use ZIRLO fuel rod cladding, guide tubes and instrumentation tube and intermediate grids in place of Zircaloy 4 ,

materials used for the Cycle 9 LTAs. , Otherwise, the Cycle 11 LTA design is basically the same as the Cycle 9 design. l The LTAs will meet current W fuel design criteria while operating within i TMI core operating limits. . LTA enrichment and core location will ensure i that an LTA will not be the lead (hot) assembly at any time during the i' cycle and will not set any safety or operating limits. The LTAs will remain bounded by existing UFSAR safety analyses results. l l

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 601 6

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8.4 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.

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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