ML20136G389

Monthly Operating Rept for Feb 1997 for Three Mile Island Nuclear Station,Unit 1

ML20136G389
Person / Time
Site:	Crane
Issue date:	02/28/1997
From:	Heysek W, Ross M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2084, NUDOCS 9703180024
Download: ML20136G389 (7)

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GPU Nuclear. Inc.

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Route 441 South NUCLEAR Post Office Box 480 Middletown. PA 17057 0480 Tel 717 944-7621 March 13,1997 6710-97-2084 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 1997 Enclosed are two copies of the February 1997 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, M.

oss Director, TMI(Acting)

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cc: Administrator, Region I

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TMI Senior Resident Inspector 97001 9703180024 970228 Y

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OPERATIONS

SUMMARY

February 1997 l

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 821 MWe during February.

MAJOR SAFETY RELATED MAINTENANCE The major safety related maintenance items completed during the month involved the following equipment:

Air Intake Tunnel Fire System Alarm Numerous false alarms in the Control Room for the Air Intake Tunnel Fire System (Alarm PLA 5-

9) were found attributable to an open circuit between the Control Room and a heat actuated detector (HAD) during troubleshooting activities. Alarm PLA 5-9 cleared following corrective actions which involved replacing the defective wire and the associated HAD.

I S1ation Blackout Diesel Valve EG-V-137A j

Station Blackout Diesel air start valve EG-V-137A failed to open duiing a February diesel mn. A new solenoid was installed on the valve and it performed satisfactorily during subsequent testing.

l An analysis being performed to determine the root cause of the solenoid failure will continue into March.

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Ouality Classification List Engineering Data Base On 02/28/97, Maintenance promulgated conservative guidance to address recently identified concerns with the Quality Classification List (QCL) Engineering data base. The guidance will ensure that parts of appropriate quality and correct procedures are used until the NRC issues j

raised with Engineering over the accuracy of certain QCL component classifications are resolved.

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4 OPERATING DATA REPORT DOCKET NO. 50-289 DATE March 13, 1997 COMPLETED BY W. HEYSEK TELEPHONE (717) 948-8191 OPERATING STATUS NOTES:

1.

UNIT NAME: THREE MILE ISLAND UNIT 1 2.

REPORTING PERIOD: FEBRUARY 1997 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:

Tills MONTil YR-TO-DATE CUMMULATIVE i1 HOURS IN REPORTING PERIOD:

. (HRS) 672.0 1416.0 197,185.0 12 NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 672.0 1416.0

-119,743.1 13 REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2,284.0' 14 HOURS GENERATOR ON LINE (HRS) 672.0 1416.0 118,581.3 15 UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0 16 GROSS THERMAL ENERGY GENERATED (MWH) 1,723,847.0 3,632,590.1 292,238,265.4 17 GROSS ELECTRICAL ENERGY GENERATED (MWH) 583,923.0 1,231,046.0 98,195,592.1 18 NET ELECTRICAL ENERGY GENERATED (MWH) 551,986.0 1,163,756.0 92,307,420.1 19 UNIT SERVICE FACTOR

(%)

100.0 100.0 60.1 20_. UNIT AVAILABILITY FACTOR

-(%)

100.0 -

100.0 60.1 21 UNIT CAPACITY FACTOR (MDC NET) 104.5 104.6 59.6 22 UNIT CAPACITY FACTOR (DER NET) 100.3 100.3 57.2 23 UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 33.9 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60,761.2

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

- 25. IF SHITIDOWN AT THE END OF THE REPORT PERIOD, ESTIMATE DATE OF STARTUP:

2

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.' 50-289 DATE March 13, 1997 COMPLETED BY W. HEYSEK TELEPHONE (717)948-8191 MONTH: FEBRUARY-DAY AVERAGE DAILY POWER DAY AVERAGE DAILY POWER LEVEL (htWe NET)

LEVEL (htWe NET) 1 821 16 825 2

823 17 825 3

822 18 821-4 824 19 812 5

822 20 819 6

822 21 813 7

824 22 812 8

825 23 823 9

825 24 822 10 825 25 826 11 825 26 821 12 822 27 808 13 825 28 819 14 825 29 15 823 30 31 l

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n-DOCKET NO. ~~50-289 ~

UNIT..NAME TMI-l DATE March 13* 1997-February 1997 REPORT MONTH COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191.

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l 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 I

specification change or other license amendment? Yes. To support GPU Nuclear's independent reload analyses for Cycle 12 as discussed in response to Question 6 below, T.S. 6.9.5.2 will 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 will be submitted once the GPU Nuclear topicals are

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approved.

6.

Important licensing considerations associated with refueling, e.g. new or different l

fuel design or supplier, unreviewed design or performance analysis methods, i

significant changes in fuel design, new operating procedures:

a) 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 A (core physics), TR-087A (core thermal hydraulics), TR-078 (FSAR safety analyses) and TR-092P (design and setpoints methodology) submitted to the NRC. The last one is in the final NRC approval stage.

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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.l b) Cycle 12 fuel rod performance calculations (e.g. internal pin pressure) will be performed by Framatome Cogema Fuels Company (FCF) using the approved TACO 3 (BAW-10162P-A) and GDTACO (BAW-10184P-A) fuel

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codes. Results require minor changes to the Mark B9 fuel rod design (lower fill gas prepressure, increased plenum volume). The new design will meet all fuel criteria in the latest approved revision of BAW-10179P-A, Safety Criteria and Methodology for Acceptable Cycle Reload Analyses. Fuel rod cladding corrosion calculations for all Cycle 12 fuel are being done by FCF using the COROS2 methodology now under review by the NRC. Approval is expected soon. The TACO calculations are being done using power histories generated with the GPU Nuclear approved core physics codes

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CASMO-3/ SIMULATE-3 (TR-091 A). Use of the SIMULATE-3 power peaking uncertainty of 5.5% with the TACO methodologies, rather than the current FCF NEMO physics code (BAW-10180A, Rev 1) uncertainty of 4.8%, was approved by NRC on October 4,1995 for application to TMl-1

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

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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

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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 II is expected to be started in 2002.

i 9 The projected date of the last refueling that can be discharged to the spent fuel

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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 2 -

rerack project full core off-load is assured through and beyond the end of the current operating license.

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