ML20063A295

Monthly Operating Rept for Dec 1993 for TMI-1

ML20063A295
Person / Time
Site:	Crane
Issue date:	12/31/1993
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2006, NUDOCS 9401250221
Download: ML20063A295 (7)

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GPU Nuclear Corporation a Nuclear

omg 48o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number

(717) 948-800">

January 13, 1994 C311-94-2006 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 December 1993 Enclosed are two copies of the December 1993 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely,

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T. G. Br hton Vice President and Director, TMI-l WGH Attachments cc:

Administrator, Region I TMI Senior Resident Inspector 250001

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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation 9401250221 931231' T

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a OPERATING DATA REPORT DOCKET NO.

50-289 DATE January 13, 1994 j

COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

DECEMBER 1993 l

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3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWe):

871 l' l

S. 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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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:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 8760.0 169465.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 7749.4 93226.2'

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

-0.0 2283.8-

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14. HOURS GENERATOR ON-LINE (HRS) 744.0 7704.6 92104.7

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1906894 18819948-224866652;

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 643975-6341709 75686783

18. NET ELECTRICAL ENERGY GENERATED (MWH) 608452 5962212' 71064519

19. UNIT SERVICE FACTOR

(%)

100.0 88.0 54.4

20. UNIT. AVAILABILITY FACTOR

(%)

100.0-88.0 54.4 21.. UNIT CAPACITY FACTOR (USING MDC NET) 104.0 86.6' 53.4

22. UNIT CAPACITY FACTOR (USING DER NET) _

99,9-83.1 51 2 j

23. UNIT FORCED OUTAGE RATE

(%).

0.0

0. 9

.39.7 UNIT. FORCED OUTAGE HOURS (HRS) 0.0 69.7 60759.4

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24. SHUTDOWNS-SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH)*

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25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE January 13, 1994 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

DECEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(MWe-NET)

(MWe-NET)

)

1 819 17 821 2

817 18 820 3

816 19 817 4

814 20 818 5

812 21 818 6

818 22 820 7

817 23 820 8

819 24 821 9

820 25

.822

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-822 11 818 27 819 12 820 28 815 13 819 29 811 14 819 30 815 15 817 31 814 16 817 I

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UNIT SHUTDOWNS AND POWER REDUCTIONS

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DOCKET NO.

50-289 UNIT NAME TMI-1 REPORT MONTH December 1993 DATE January 13, 1994 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 i

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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?

NO 5.

Scheduled date(s) for submitting proposed licensing action and supporting inf's ation:

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 Technical 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)

TSCR 234 was submitted in November 1993 consistent with GL 88-16 and the BAW-10179P " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses" Safety Evaluation (March 16,1993) for the removal of cycle-specific protective and maximum allowable setpoint limits 4

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 refueline 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 er:d 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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