ML20067B126

Monthly Operating Rept for Jan 1994 for TMI-1

ML20067B126
Person / Time
Site:	Crane
Issue date:	01/31/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2020, NUDOCS 9402230251
Download: ML20067B126 (7)

Text

E GPU Nuclear Corporation

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Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8005 February 13, 1994 C311-94-2020 U. S. Nuclear Regulatory Commission Attn: Document Control L'esk 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 January 1994 Enclosed are two copies of the January 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, b

T. G. Broug on Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector I

9402230251 940131 PDR ADDCK 05000289 R

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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation l ll j

OPERATIONS

SUMMARY

January 1994 The plant entered and ended the month operating at approximately 100% power.

The plant electrical output averaged approximately 816 MWe during the period.

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MAJOR SAFETY RELATED MAINTENANCE During January the following major safety related maintenance was performed:

Makeup Pump MU D-1B Makeup Pump MJ-P-1B was removed from service due to high vibration on the f

outboard bearings and an outboard mechanical seal leak. After disassembly of the bearing housing, inspection of the outboard thrust bearing identified no abnormal conditions while inspection of the outboard line bearing found excessive wear.

The outboard line bearing was replaced.

During reassembly, a new outboard mechanical seal was also installed. MU-P-1B test run and although vibration levels were found acceptable, the outboard seal had excessive leakage (pencil stream).

In accordance with a Plant Engineering recommendation, the torque on the seal gland plate was. relaxed and the leakage was reduced to " dripping".

At present, the leak-off is being monitored.

Boric Acid Recycle Pump WDI.-P-13A Boric Acid Recycle Pump WDL-P-13A was removed from service to repair a mechanical seal leak.

The pump was disassembled and a new seal installed.

After pump reassembly, the pump was tested satisfactorily and was returned to service.

Intermediate Closed Cooling Water Pump IC-P-1B I

Intermediate Closed Cooling Water Pump IC-P-1B was removed from service due to a noisy outboard motor bearing. After the bearing was replaced, IC-P-1B motor testing was completed satisfactorily and the pump returned to service.

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OPERATING DATA REPORT I

DOCKET NO.

50-289 DATE February 13, 1994 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191 1.

UNIT NAME:

TilREE MILE ISLAND UNIT 1 l NOTES:

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2.

REPORTING PERIOD:

JANUARY 1994 l

l 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 DEPENDADLE CAPACITY (NET MWe):

786 l l

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8.

IF CHANGES OCCUR IN (ITEMS-3-7) SINCE LAST REPORT, GIVE REASONS:

9, POWER LEVEL TO WHICll RESTRICTED, IF ANY (NET MWe):

10. REASONS FOR RESTRICTIONS, IF ANY:

i THIS MONTH YR-TO-DATE CUMMULATIVE

11. IJOURS IN REPORTING PERIOD (HRS) 744.0 744.0 170209.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 744.0 93970.2

13. REACTOR RESERVE SHUTDOWN HOUPS (IIRS )

0.0 0.0 2283.8

14. IlOURS GENERATOR ON-LINE (HRS) 744.0 744.0 92848.7

15. UNIT RESERVE SHUTDOWN llOURS (llRS )

0.0 0.0 0.0

16. GROSS TilERMAL ENERGY GENERATED (MWH) 1908743 1908743 226775395-t

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 642841 642841 76329624

' 18. NET, ELECTRICAL ENERGY GENERATED (MWH) 606912 606912 71671431

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 54.5

20. UNIT AVAILADILITY FACTOR

(%)

'100.0 100.0 54.5

21. UNIT CAPACITY FACTOR (USING MDC NET) 103.8 103.8-53.6

22. UNIT CAPACITY FACTOR (USING DER NET) 99.6 99.6 51.4

23. UNIT FORCED OUTAGE RATE (1) 0.0 0.0 39.5 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0

'60759.4

24. SHUTDOWNS SCilEDULED 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 P^AER LEVEL i

1 DOCKET NO.

50-289 UNIT TMI-I i

DATE.

February 13, 1994' COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191

- MONTH:

JANUARY DAY AVERAGE DAILY POWER LEVEL DAY AVTRAGL DA: LY POWER LEVEL If (MWe-NET)

(MWe-NET) 1 819 17 812 2

819 18 810 3

821 19 797 4

819 20 800 5

818 21 797 6

821 22 810 7

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-289 UNIT NAME TMI-1

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REPORT MONTH January 1994 DATE February 13, 1994 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 4

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REFUELING INFORMATION REQUEST

1. Name of Facility:

Three Mile Island Nuclear Station, Unit 1

2. Scheduled date for next refueling 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?

N0

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) GPUN will continue to improve the review process by submittal of Ter.hnical Specification Change Requests (TSCR) concerning the reload-related areas of fuel assembly reconstitution and removal of cycle-dependent core limits to the Core Operating Limits Report (COLR).

1) The B&W Owners Group Topical Report BAW-2149, " Evaluation of Replacement Rods in BWFC Fuel Assemblies", December 1991, was approved in April 1993.

This report justifies the use of up to ten replacement stainless steel rods located anywhere in a single fuel assembly based on currently-approved methodology.

BAW-2149 provides the basis for reconstitution repairs of BWFC Mark B assemblies to be done under the provisions of 10 CFR 50.59 (i.e., the repair does not represent an unreviewed safety question). TSCR 232 was submitted in August 1993 in response to Generic Letter 90-02, Supplement I referencing BAW-2149.

2)

ISCR 234 was submitted in November 1993 consistent with GL 88-16 and the BAW-10179P " Safety Criteria and Methodology for Acceptable Cycle Reload Analvses" Safety Evaluation (March 16,1993) for the removal of cycle-specific protective and maximum allowable setpoint limits for axial power imbalance and other applicable cycle-dependent limits.

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

(a) 177 (b) 601

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 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.

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