ML20080C613

Monthly Operating Rept for Nov 1994 for TMI-1

ML20080C613
Person / Time
Site:	Crane
Issue date:	11/30/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2342, NUDOCS 9412190089
Download: ML20080C613 (7)

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GPU Nuclear Corpore. ion Middletown, Pennsylvania 17057-0480

~ (717) 944-7621 Writer's Direct Dial Nurnber:

(717) 948-8005-December 8, 1994 C311-94-2342 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 1994 Enclosed are two copies of the November 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, h

N~

T. G. Broughton Vice President and Director, TMI WGH' Attachments cc: Administrator, Region I TMI Senior Resident Inspector T94001 94121h0b89 941130 PDR ADOCK 05000289 R

PDR GPU Nuclear Corporation is a subsidery of General Public Utilites Corporation

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..s TOPERATIONS

SUMMARY

f NovemberL1994 o

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'The plant entered the month operating at 100% power.and= remained at that' level

.throughout the month. _ Unit electrical o,utputLaveraged approximate 1y'809.MWe

during November.

4, MAJOR SAFETY RELATED MAINTENANCE The following is'a summary!of. major. safety.related maintenance items:

,c) t accomplished during the month'..

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Screen House Ventilation Pump Strainer-SW-S-24:

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' Screen House Ventilation Pump Strainer. SW-S-2A was removed from service after it was found that the: strainer continued to run in ' AUTO' when the pump was-J shut off.

Investigation identified that the reset timer was faulty and as a result it was replaced.

Post maintenance testing of'SW-S-2A was satisfactory.

and the pump was returned to service, j

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' Auxiliary and Fuel Handina Buildina~ Exhaust Fan AH-E-148

. Auxiliary and Fuel' Handing Building Exhaust Fan AH-E-14B was removed from o

1 service because of a motor phase short.

Investigation revealed thatLa short had been caused by the 'B' lead rubbing within the connection box: the rubbing action wore thru the lead insulation at the duct seal and tape. To reduce contact with the connection box, the leads for all three phases were -

shortened.' After the shortened leads were terminated, AH-E-14B tested satisfactorily and was returned to service.

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OPERATING DATA REPORT DOCKET NO.

50-289 December 8, 1994 DATE COMPLETT. GY W'G HEYSEK m,

, OPERATING STATUS TELEPHONE (717);948-8191

1. UNIT. NAMES.

THREE MILE ISLAND UNIT 1 NOTES:

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2, REPORTING PERIOD:

NOVEMBER.1994

3. LICENSED THERMAL POWER:

2568-l

4. NAMEPLATE RATING (GROSS MWe):

871

5. DESIGN ELECTRICAL RATING (NET MWe):

819

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

834

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 i

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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):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMM,ULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 720.0 8016.0 177481.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 720.0 7618.7 100841.7

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

-0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 720.0 7606.4 99711.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1847111.

19202066 244069160

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 619344 6374775 82061558

18. NET ELECTRICAL ENERGY GENERATED (MWH) 585607 6004403 77068922 19.. UNIT SERVICE FACTOR

(%)

100.0 94.9 56.2

20. UNIT AVAILABILITY FACTOR

(%)

100.0 94.9 56.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 103.5 95.3 55.2-

22. UNIT CAPACITY FACTOR (USING DER NET) 99.3 91.5 53.0

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 37.8 i

UNIT FORCED OUTAGE HOURS (HRS) 0.0 1.8

.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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1 REFUELING INFORMATION REQUEST J

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?1. Name.of Facility::

Three Mile Island Nuclear Station, Unit l' j

2l. Scheduled date for next refueling shutdown:

September 8, 1995 n

3. c Scheduled date for restart following current refueling: NA 4

4. 'Will refueling or. resumption of operation thereafter require a technical.

specification change or other license amendment?.

NO

--5.

Scheduled date(s) for submitting _ proposed licensing actionT and' supporting Li

-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 BIO fuel assembly in the Cycle 11 reload bat'ch which is an upgraded design of the Mark 89 assembly used'in Cycle 10.

The Mark B10 provides a leaf-type cruciform assembly holddown spring.to

.j replace the previous. coil spring design which has experienced random-

-l failures during' operation and requires visual inspection each outage.

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-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 four 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 M LTAs inserted in Cycle 9 were discharged at EOC-9 due to detection of fuel rod failures caused by grid-to-rod fretting similar to that seen in H Vantage 5H fuel designs. The Cycle 11 LTAs will use the generic M recommended design fix of rotated intermediate spacer grids to minimize flow-induced fuel vibrations and thus eliminate fretting.

A-prototype LTA will be 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.

The LTAs will meet current y fuel design criteria while operating within TMI core operating limits.

LTA enrichment and core-location will ensure that an LTA will not be the lead (hot) assembly at any time during the cycle and will not set any safety or operating limits. The LTAs will remain bounded by existing UFSAR safety analyses results.

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

(a) la (b) 601 6

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8. The, present~1icen' sed spe'nt: fuel. pool storage casacity' and the size of any increase in' licensed storage capacity that has )een requested ' r is: planned, o

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 3,

assemblies. Upon completion of Phase II of theLreracking project, the full licensed capacity will be attained.

9. The projected date of-the last refueling that 'can be discharged to-thel 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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