ML20149G367

Monthly Operating Rept for Sept 1994 for Three Mile Island Nuclear Station,Unit 1

ML20149G367
Person / Time
Site:	Crane
Issue date:	09/30/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2139, NUDOCS 9410200300
Download: ML20149G367 (7)

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GPU Nuclear Corporation 6 0 Nuclear "n:n="*

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

(717) 948-8005 October 11, 1994 C311-94-2139 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

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Gentlemen:

Subject:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for September 1994 Enclosed are two copies of the September 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, W

g T. G. Brough.tbn Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector T94001 9410200300 940930 PDR ADOCK 05000289 i

GPU Nuclear Corpora son is a subsidiary of General Public Utilities Corporation

1 OPERATIONS SUNMARY September 1994 The plant entered the month escalating to 100% power following completion of the Main Turbine Electro-Hydraulic Control System repairs.

Full power operation was achieved at 0255 on September 1 and remained essentially at that level through 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on September 16. At that time a power reduction was initiated to perform a leak check of the main condenser. At 1405, the plant reached 49% power and remained at that level throughout the duration of the leak checking and subsequent tube plugging activities.

Following the condenser repairs at 0140 on September 19, power was gradually escalated to 100%. The plant returned to 100% power operation at 0643.

Unit electrical output averaged approximately 760 MWe during September.

MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items accomplished during the month.

Main Condenser CO-C-1B Power was reduced to approximately 49% on September 16 and maintained at that level to allow for maintenance of the 'B' side of the Main Condenser, C0-C-18.

The condenser was opened to locate and repair leaking tubes.

Testing with SF6 gas identified three leaking tubes which were subsequently plugged.

One tube plug found out of position and loosely fit in a tube end was removed and replaced in the correct location.

An additional 67 tubes, five of which were stabilized, on the condenser periphery were plugged based on Eddy Current test results.

Upon completion of the work on September 19, the condenser was closed and returned to service.

Miscellaneous Warte Evaporator Distillate Pump WDL-P-21 Miscellaneous Waste Evaporator Distillate Pump WDL-P-21 was replaced during the month due to motor grounds.

A new pump / motor assembly was installed, tested satisfactorily, and returned to service.

Precoat Filter Holding Pumo CA-P-5B Precoat Filter Holding Pump CA-P-5B was removed from service because of a leaking mechanical seal. After the pump was disassembled, the existing seal assembly was removed and replaced with a new seal assembly.

CA-P-5B was reassembled, aligned to the motor and tested. CA-P-5B was returned to service after satisfactory completion of the post maintenance testing.

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h OPERATING DATA REPORT DOCKET NO.

50-289 October 11, 1994 DATE COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948 8191 i

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

SEPTEMBER 1994 l

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3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWe):

871 l l

5. 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

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1 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: _

i THIS MONTH YR-TO-DATE CUMMULATIVE

11. HLURS IN REPORTING PERIOD (HRS) 720.0 6551.0 176016.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 720.0 6153,7 99379.7

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

-0.0 2284.0

14. HOURS GENERATOR CN-LINE (HRS) 720.0 6141.4 98246.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1765140 15442514 240309608

17. CROSS ELECTRICAL ENERGY GENERATED (MWH) 580165 5116628 80803411

18. NET ELECTRICAL ENERGY GENERATED (MWH) 546927 4814834 75879353

19. UNIT SERVICE FACTOR

(%)

100.0 93.7 55.8

20. UNIT AVAILABILITY FACTOR

(%)

100.0 93.7 55.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 96.6 93.5 54.8

22. UNIT CAPACITY FACTOR (USING DER NET) 92.7 89.7 52.6

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 38.1 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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I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-I DATE Octobert 11, 1994 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

SEPTEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWe-NET) 1 783 17 331 I

2 800 18 336 3

802 19 727 4

802 20 802 5

804 21 802 6

804 22 804 e

7 801 23 804 8

802 24 802 9

799 25 798

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10 801 26 794 11 805 27 797 12 802 28 804 13 795 29 807 i

14 789 30 809 15 792 31 NA 16 593 1

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-289

• UNIT NAME TMI-1 REPORT MONTH September 1994 DATE October 11, 1994 COMPLETED BY W. G. Heyssk TELEPHONE (717) 948-8191 u**

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4 None SG COND The unit was reduced to 49% power on September 16 in support of efforts to 07 locate and repair main condenser tube leaks. Following the completion of the condenser maintenance activity, the unit was gradually escalated to 100% power.

100% power operation was achieved at 0643 on September 19.1994.

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REFUELING INFORMATION RE0 VEST

1. Name of Facility:

Three Mile Island Nuclear Station, Unit 1

2. Scheduled date for next rr. fueling shutdown:

September 8, 1995

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?

NO

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 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 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 W LTAs inserted in Cycle 9 were discharged at E00-9 due to detection of fuel rod failures caused by grid-to-rod fretting similar to that seen in W Vantage SH 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 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 in place of Zircaloy 4 materials used for the Cycle 9 LTAs. Otherwise, the Cycle 11 LTA design is basically the same

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as'the Cycle 9 design.

The LTAs will meet current W 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 aru safety or operating limits. The LTAs will remain bounded by existing UFSAR safety analyses results.

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

storage pool:

(a) 177 (b) 601

8. The present licensed spent fuel pool storage capacity and the size of any incre,ase 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:

j Completion of Phase I of the reracking project permits full core off-load f

(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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