ML20078P858
| ML20078P858 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/31/1995 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-95-2077, NUDOCS 9502170268 | |
| Download: ML20078P858 (7) | |
Text
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GPU Nuclear Corporation 3 Nh. clear m:ne" Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial Number:
(717) 948-8005 February 9,1995 C311-95-2077 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 January 1995 Enclosed are two copies of the January 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, b$s
/drw T. G. Bro hton Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector T95001 170034 9502170268 950131 PDR ADOCK 05000289 R
PDR t j GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation
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OPERATIONS
SUMMARY
January 1995 The plant entered the month operating at 100% power and remained at that level throughout the entire month.
Net unit electrical output averaged approximately 822 MWe during January.
MAJOR SAFETY RELATED MAINTENANCE i
The following is a summary of major safety related maintenance items accomplished during the month.
i NUCLEAR SERVICE RIVER WATER PIPING A pin hole leak was discovered in a section of 12" piping downstream of NS-C-IB backwash valve NR-V-12B during December. Corrective maintenance performed in January involved welding a threaded half coupling over the defect and installing a threaded pipe plug in the half coupling. All post maintenance weld inspections and leak test results were satisfactory.
EMERGENCY DIESEL ENGINE EG-Y-1B i
Emergency Diesel EG-Y-1B was removed from service in January because of a fuel oil leak on the #5 injector pump on the control side of the engine. A new injector was installed and the engine tested satisfactory with no leakage evident.
i RIVER WATER HEAT EXCHANGER INSPECTION.
The River Water Heat Exchanger inspection program continued into January.
Three Heat Exchangers were inspected. Secondary Service Closed Cooler, SC-C-1A, was leak tested with no leaking tubes identified.
Eddy Current Testing of 80 tubes revealed no deficiencies that required tube plugging.
One tube was removed from the cooler for further inspection.
Its location in the tubesheet was plugged.
Leak testing of Secondary Service Closed Cooler, SC-C-1B, identified one leaking tube.
Eddy Current Testing of 235 tubes identified 12 tubes with defects. The 13 tubes were stabilized and plugged.
Nuclear Service Closed Cooler, NS-C-lD, was leak checked with no leaking tubes identified.
Eddy Current Testing of all 800 tubes revealed deficiencies in 10 l
tubes that required stabilizers and plugging.
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE February. 9,1995 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:
JANUARY 1995 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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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) 744.0 744.0 17'8969.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 744.0 102332.7
]
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2284.0
- 14. HOURS GENERATOR ON-LINE (HRS) 744.0 744.0 101199.1 l
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1908743 1908743 24782S014
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 647188 647188 83330442
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 611412 611412 78266830
- 19. UNIT SERVICE FACTOR
(%)
100.0 100.0 56.5
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 100.0 56.5
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 104.6 104.6 55.6
- 22. UNIT CAPACITY FACTOR (USING DER NET) 100.3 100.3 53.4
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 37.4 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 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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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE Eehrmary 4 144; COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:
JANUARY DAY AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL (MWe-NET)
(MWe-NET) 1 821 17 820 2
823 18 820 3
824 19 820 4
825 20 818 5
823 21 822 6
821 22 824 7
823 23 825 8
824 24 824 9
823 25 823 10 825 26 824 11 823 27 824 12 822 28 826 13 821 29 826 14 811 30 825 15 806 31 824 16 815
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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 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 EOC-9 due to detection of fuel rod failures caused by grid-to-rod fretting similar to that seen in W Vantage 5H 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 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 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 any safety or operating limits. The LTAs will
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remain bounded by existing UFSAR safety analyses results.
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- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 601 6
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- 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.
- 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 i
the rerack project full core off-load is assured through the end of the current operating license and beyond.
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