ML20141G280

Monthly Operating Rept for Apr 1997 for TMI-1

ML20141G280
Person / Time
Site:	Three Mile Island
Issue date:	04/30/1997
From:	Heysek W, Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2190, NUDOCS 9705220254
Download: ML20141G280 (8)

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GPU Nuclear,Inc.

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Route 441 South Mi d e wn 17057-0480 Tel 717-944-7621 6710-97-2190 May 14,1997 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Three Mile Island Nuclear Stition, Unit I (TMI-1)

Operating License No. DPR 50 Docket No. 50-289 Monthly Operating Report for April 1997 Enclosed are two copies of the April 1997 Monthly Operathg Report for Three Mile Island Nuclear Station, Unit 1.

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J. W. Langenbach Vice President and Director, TMI WGli cc: Administrator, Region I TMI Senior Resident Inspectcr 97001

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p OPERATIONS

SUMMARY

April 1997 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 816 MWe during l

April.

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

Enctor Building Fans AH-E-1BIC During the March 1997 repairs were made to AH-E-1 A fan motor to correct a fault at a 4/0 cable connection into the weld connector. Engineering recommended that heat shrink. tubing be installed over the exposed metal and on to the spark plug porcelain to meet EQ configuration requirements. The recommendation was inconsistent with previous direction provided for maintenance performed on the AH-E-1 A/B/C fan motors in 1986 and 1993. On both these occasions, the motor connections were remade using the "as found" configuration.

i Differences between the recent direction and that used in 1986 and 1993 brought into question

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the EQ basis and the qualification of the configuration resulting from the prior maintenance. The 4

Plant Review Group met on April 24,1997 and concluded that AH-E-1B/C fan motors could not be expected to remain operable in a post LOCA environment (100% humidity being the concern

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4 on exposed metal conductors). AH-E-1B/C were declared inoperable with a seven day Technical j

Specification time clock applicable. The event was reported to the NRC under 10 CFR 50.72(b)(2)(iii)(D).

Temporary repairs were made on April 25,1997 to the connections on the B/C fan motors in accordance with directions mimicking those used by Commonwealth Edison to qualify a similar splice. Permanent repairs, providing a qualified EQ configuration will be completed during the j-12R outage.

Auxiliary and Fuel Handling Building Fan AH-E-14C Repairs to Auxiliary and Fuel Handling Building Ventilation Exhaust Fan AH-E-14C, begun in E

March, were completed during April. The fan / motor assembly was reassembled and tested prior

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' to installing it in the ducting. Once installed, AH-E-14C was aligned and the elecrticalleads j

terminated. Post-maintenance testing of the unit was completed satisfactorily and the fan was j

i-returned to semce.

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l Emergency 3iesel Generators EG-Y-1 A/B Emergency Diesel Generators EG-Y-1 A/B were removed from service to perform the scheduled l

annual inspection.' A reduced scope inspection was performed this year and the scheduled activities accomplished included engine oil changes, valve inspections and testing, fan drive unit l

inspections, instrument calibrations, and various corrective and preventative maintenance tasks.

. Work was started and was completed on EG-Y-1B during the week of April 7th. Work on EG-i Y-1 A was started and completed during the week of April 14th. It was during the inspection of the ve:tical drive on EG-Y-1 A, that lockwire on the bolts was found to be broken and undersized.

The lockwire was replaced on the vertical drive bolting and EG-Y-1 A was returned to service.

Subsequently, EG-Y-1B was removed from service to determine whether the lockwire was l

-deficient on that engine. No diserepancies were identified with the lockwire installed on the EG-l Y-1B vertical drive bolting and the engine was returned to service.

Sp.pnt Fuel Activities In order to support a root cause evaluation of the distinctive crud pattern (DCP), six irradiated fuel rods which were removed from assemblies were transferred to a fuel shipping canister in the Spent Fuel Pool. The DCP was identified on fuel rods contained in several fuel assemblies, during inspection of fuel discharged from the core following the completion of operating Cycle 10. The canister containing the rods will be loaded into an NRC licensed shipping cask in Iune 1997 for transport to a hot cell facility where the evaluation will be performed.

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OPERATING DATA REPORT L

DOCKET NO. 50-289 DATE M 14 1997 COMPLETUD Bt W. HEYSEK TELEPliONE (717)948-8191 OPERATING STATUS NOTES:

1.

UNIT NAME: TliREE MILE ISLAND UNIT 1 2.

REPORTING PERIOD: APRIL 1997 3.

LICENSED TilERMAL 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 WillCII RESTRICTED, IF ANY (NET MWe):

10.

REASONS FOR RESTRICTIONS,IF ANY:

Tills MONTIi YR.TO-DATE CUMMULATIVE

11. IlOURS IN REPORTING PERIOD:

(HRS) 719.0 2,879,0 198,648.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 719.0 2,879.0 121,206.1

13. REACTOR RESERVE SHUTDOWN ilOURS (HRS) 0.0 0.0 2,283 9

14. HOURS GENERATOR ON LINE (llRS) 719.0 2,879.0 120,044.3

15. UNIT RESERVE SIIUTDOWN IIOURS (HRS) 0.0 0.0 0.0

16. GROSS TIIERMAL ENERGY GENERATED (M'VH) 1,844,645.8 7,385,978.9 295,991,654.3

17. GROSS ELECTRICAL ENERGY GENERATED (MWil) 620,401.0 2,496,840.0 99,461,386.1

18. NET ELECTRICAL ENERGY GENERATED (MWH) 587,030.0 2,361.136.0 93,504,800.1 19 UNIT SERVICE FACTOR

(%)

100.0 100 0 60.4

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 60.4

21. UNIT CAPACITY FACTOR (MDC NET) 103.9 104.3 59.9

22. UNIT CAPACITY FACTOR (DER NET) 99.7 100.1 57.5

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 33.6 UNIT FORCED OUTAGE IlOURS (HRS) 0.0 0.0 60,761.2

24. SilUTDOWNS SCilEDULED 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 day s.

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

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a AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 -

-l DATE May 14 1997 COMPi.ETED BY,'W. HEYSEK

' TELEPIIONE (717) 948-8191

. MONTH: APRIL DAY.

AVERAGE DAILY POWER DAY

. AVERAGE DAILY POWER LEVEL (MWe NET)

LEVEL (MWe NET) 1 819 16 817 2

816 17 816-3 813 18 818 l

4 810 19 820 l

5 815 20 819 6

811 21 819 7

809 22.

818 8

818 23 816 9

823 24 815.

10 824 25 816 J

11 822 26 814 12 819 27 815 13 815 28 813 14 820 29 814 1

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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

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.

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Scheduled date(s) for submitting proposed licensing action and supporting information: Technical Specification Change Request Number 264 for the changes as discussed above will be submitted in early May 1997.

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:

4 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 1997 time frame.

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i 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 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 i

cladding corrosion calculations for all Cycle 12 fuel are being done by FCF using the COROS2 methodology described in Topical Report BAW 10186P,

" Extended Burnup Evaluation" which was approved by the NRC en April 29.1997. The TACO calculations are being done using power histories generated with the GPU Nuclear approved core physics codes 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) unnrtainty of 4.8%, was approved by NRC on October 4,1995 for application to TMI-1 only.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage 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 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 11 b expected to be started in 2002.

9. The projected date of the last refueling that can be discharged to the spent fuei 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 and beyond the end of the current operating 3icense.

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