ML20140D660

Monthly Operating Rept for Mar 1997 for Three Mile Island, Unit 1

ML20140D660
Person / Time
Site:	Three Mile Island
Issue date:	03/31/1997
From:	Heysek W, Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2149, NUDOCS 9704240015
Download: ML20140D660 (7)

Text

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I GPU Nuclear, Inc.

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Route 441 South NUCLEAR Post Office Box 480 Middletown, PA 17057-0480 Tel 717 944 7621 April 11,1997 6710-97-2149 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 March 1997 4

Enclosed are two copies of the March 1997 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, N

J. W. Langenbac Vice President and Director, TMI WGH

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cc: Administrator, Region I J((\\

TMI Senior Resident Inspector

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9704240013 970331 i

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OPERATIONS

SUMMARY

March 1997 The plant entemd the month operating at 100% power and remained at that power level for the remainder of the month. Net unit electrical output averaged approximately 820 MWe during March.

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

Auxiliary and Fuel Handling Building Fan AH-E-14C Repair of the Auxiliary and Fuel Handling Building Ventilation Exhaust Fan AH-E-14C was continued from last month. The work accomplished during March included completion of the fan / motor rigging assembly, installation of the fan blades onto the motor and test running /

balancing the fan assembly. Reinstaliation of the fan assembly into the duct is in progress and will continuein April.

Screen House Ventilation Fan AH-E-27B Screen House Ventilation Fan AH-E-27B was removed from service because the unit was.

becoming noisy. Investigation revealed that the pillow block bearings were worn and required replacement. New bearings were installed and AH-E-27B returned to service.

1 Beactor Buildine Fan AH-E-1 A Reactor Building Ventilation Fan AH-E-1 A was removed from service after the unit tripped two times. The unit was meggered and bridged from the MCC with unsatisfactory results. A physical-inspection was made and 'T' lead connector (A6) to spark plug connection was found burned causing the unit to trip. Connector A6 and the corresponding spark plug was replaced. All other electrical connections were cleaned and tightened. All testing was found to be satisfactory and AH-E-1 A returned to service.

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OPERATING DATA REPORT DOCKET NO. 50-289 DATE April 11,1997 COMPLETED BY W. HEYSEK 3

TELEPHONE (717)948-8191 OPERATING STATUS NOTES:

1.

UNIT NAME: THIEE MILE ISLAND UNIT 1 2.

REPORTING PERIOD: MARCH 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:

TIIIS MONTil YR-TO-DATE CUMMUIA1TVE I 1. HOURS IN REPORTING PERIOD:

(HRS) 744.0 2,160.0 197,929.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 2,160.0 120,487.1

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2,283.9

14. HOURS GENERATOR ON LINE (HRS) 744.0 2,160.0 119,325.3

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,908,743.0 5,541,333.1 294,147,008.5 17, GROSS ELECTRICAL ENERGY GENERATED (MWH) 645,393.0 1,876,439.0 98.840,985.i

18. NET ELECTRICAL ENERGY GENERATED (MWH) 610,350.0 1,774,106.0 92,917,770.1

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 60.3

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 60.3

21. UNIT CAPACITY FACTOR (MDC NET) 104.4 104.5 59.7

22. UNIT CAPACITY FACTOR (DER NET) 100.2 100.3 57.3

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 33.7 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):

The unit will shutdown for a refueling outage scheduled to begin on September 5,1997 with a duration of 55 days.

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

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l-l AVERAGE DAILY UNIT POWER LEVEL DOCKETNO. 50 289 a

DATE April 11, 1997 l

COMPLETEDBY W.HEYSEK TELEPHONE '(717) 948-8191 1

' DAY AVERAGE DAILY POWER DAY AVERAGE DAILY POWER l-LEVEL (MWe NET)

LEVEL (MWe NET) i t

l 820 16 826 2

814 17 824 i

3 823 18 820 L

4 823 19

'824 5

821 20 822 l

6 818 21 820 t.

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821 23 825 i

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i 10 821 25 821-1 11 820 26 816 12 823 27-814

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14 821 29 812

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15 823 30 813 31 820 i

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UNIT NAME TMI-1' DATE ' April 11, 1997, REPORT MONTH March 1997 COMPLETED BY W. G. Heysek-TELEPHONE (717) 948-8191 e

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i REFUELING INFORMATION REOUEST

l. 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 i

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

information: A Technical Specification Change Request for the changes as discussed above will be submitted once the GPU Nuclear topicals are approved.

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) 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-087-A (core thermal hydraulics), TR-078-A (FSAR safety analyses) and TR-092P-A (design and setpoints methodology) submitted to the NRC. The NRC has approved all of the associated topical reports.

The GPU Nuclear Cycle 12 reload program and results are expected to be available for NRC review in the May to June 1977 time frame.

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b) Cycle 12 fuel rod performance calculations (e.g. internal pin pressure) j will be performed by Framatome Cogema Fuels Company (FCF) using the approved TACO 3 (BAW-10162P-A) and GDTACO (BAW-10184P-A) fuel codes. Results require minor changes to the Mark B9 fuel rod design (lower i

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 CASMO-3/ SIMULATE-3 (TR-091A). Use of the SIMULATE-3 power l

peaking uncertainty of 5.5% with the TACO methodologies, rather than the current FCF NEMO physics code (BAW-10180A, Rev 1) uncertainty of j

4.8%, was approved by NRC on October 4,1995 for application to TMI-1 i

only.

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

pool: (a) 177 (b) 864 i

8. The present licensed spent fuel pool storage capacity and the size cf any increase t

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in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

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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 full licensed

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capacity will be attained. Phase It 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:

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Completion of hase.I of the reracking proiect permits full rnre nmload (177 fuel assemblies) through the end of Cycle 14 and on completion of the rerack project full core off-load is assured through and beyond the end of the current operating license.

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