ML20077R381

Monthly Operating Rept for Dec 1994 for TMI-1

ML20077R381
Person / Time
Site:	Crane
Issue date:	12/31/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2383, NUDOCS 9501200202
Download: ML20077R381 (7)

Text

-

GPU Nuclear Corporation Nuclear "r=!r*

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

(717) 948-8005 January 13, 1995 C311-94-2383 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555 Gentlemen:

Subject:

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

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

Sincerely, M

T.G.Brougfiton Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector T95001 2C 000!i ff

/ }0 2200202 941231 R

ADOCK 05000289 F

PDR GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation

l I

OPERATIONS

SUMMARY

December 1994 The plant entered the month operating at 100% power and remained at that level through December 3 when a chemistry anomaly indicated the existence of main condenser tube in-leakage. The unit was reduced to 50% power at 2000 to permit isolation and opening of the 'A' side of the main condenser for inspection and repair.

Following the completion of repairs and preventive plugging, the unit was returned to 100% power at 2315 on December 5.

It i

operated at that level for the remainder of the month.

Unit electrical output l

averaged approximately 788 MWe during December.

MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items l

accomplished during the month.

l Main Condenser C0-C-1A/B With the plant at approximately 50% power, the ' A' side of the Main Condenser was isolated and drained to repair tube leaks.

Testing found one leaking tube in the north tube bundle which was repaired by plugging. An additional 139 tubes were plugged (two were stabilized) in the north tube bundle as a preventive measure. Two tubes in the south bundle were also plugged and one stabilized. Upon completion of the repairs, the condenser was closed and returned to service.

e Miscellaneous Waste Transfer Pump WDL-P-78 l

Miscellaneous Waste Transfer Pump WDL-P-78 was removed from service to repair a mechanical seal leak.

The pump was disassembled, cleaned and a new mechanical seal was installed. The pump was reassembled and tested satisfactorily prior to its return to service.

Fire Service Pipe A leaking underground 12" Fire Service pipe was discovered and excavated in preparation for repair. A pipe repair clamp was installed and the pipe was pressurized to ensure leak tightness of the clamp prior to application of the protective coating.

Spot repairs to the existing coating were made where damaged occurred during excavation. The coating was ' Spark' tested and the excavation was backfilled.

Backup Instrument Air Compressor IA-P-2A j

Backup Instrument Air Compressor IA-P-2A was removed from service to support repair of the unloader valves. The valves were removed, disassembled and reassembled using new parts.

Post maintenance testing of IA-P-2A was satisfactory and the unit was returned to service.

2

9 Jes>

OPERATING DATA REPORT DOCKET NO.

50-289 DATE January 13, 1995 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

l

2. REPORTING PERIOD:

DECEMBER 1994 l

l

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

l l

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 178225.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 8362.7 101588.7

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0

-0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 744.0 8350.4 100455.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1847111 21049177 245916271

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 621696 6996471 82683254

18. NET ELECTRICAL ENERGY GENERATED (MWH) 586496 6590899 77655418

19. UNIT SERVICE FACTOR

(%)

100.0 95.3 56.4

20. UNIT AVAILABILITY FACTOR

( 's )

100.V 95.3 56.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.3 95.7 55.4

22. UNIT CAPACITY FACTOR (USING DER NET) 96.3 91.9 53.2

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 37.6 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:

3 1

't' f

.e i

i f

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

.50-289 UNIT TMI-1 DATE January 13, 1995 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) 1 816 17 818 2

814 18 818 3

744 19 819 i

f 4

355 20 820 5

429 21 818 5

6 802 22 819

[

7 808 23 816 l

8 819 24 815 9

821 25 815 j

10 819 26 818 11 818 27 820 3

12 823 28 821 13 822 29 821 14 821 30 826 15 820 31 825 16 819 l

i i

O 4

i n, - -

n

---..,.m.-

~,

a-,.

,m.,.

~

1 a

4 4

DOCKET NO.-

50-289 e

UNIT MAME

'IMI-1 REPORT MONTH December 1994 DATE January 13, 1995-CC4PLETED BY W. G. Heysek l

TELEPHONE (717) 948-8191 Came & P Licenme Synesis c,

Action to wg Ewse Cedo Type' Dwatice ResanuP heting ow>

n-.

Re,wis r==.s R----.

u s

94-12/03/94 F

0 A

4 None SG COND A chemistry anomaly indicating a main 08 condenser tube leak caused a reduction in power to 50% at 2000 on 32/3/94 to effect i

repairs to the main condenser. At 2315 on 12/5/94 following completion of the repairs, the unit was returned to 100% power.

i l

1 2

3 4

Ethihis O kmnusam Ar l

FFwed S Schedaded Afgalpnues Faihme (Explain) 144mmem!

Payana== d h Esary h i

a" 'piel)

E bWM r

B" or Tema 244mmalSame

(

C-Ren=lims 3-r Serum l

D-Reguhnary Reserkshm Scher (Emplaird 5 Exhibia i esos sowee l

EOpersaw Tmining & heingr F."

l Erwe EW 6 Amuntly used eahibite F & H MUREG Olet l

5

5, 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 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 89 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 BIO 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 M LTAs inserted in Cycle 9 were discharged at EOC-9 due to detection of fuel rod failures caused by grid-to-rod fretting similar to that seen in M Vantage 551 fuel designs. The Cycle 11 LTAs will use the generic M 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 and intermediate grids in place of Zircaloy 4 materials used for the Cycle 9 LTAs.

Otherwise, the cycle 11 LTA design is basically the same as the Cycle 9 design.

The LTAs will meet current M 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 any 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 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, r

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:

Completion of Phase I of the reracking project permits. full core off-load (177 fuel assemblits) 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.

l I

4 I

7 1

_ __....