ML20078J326
| ML20078J326 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1994 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-94-2302, NUDOCS 9411210137 | |
| Download: ML20078J326 (8) | |
Text
s GPU Nuclear Corporation i B Nuclear m:nir*
Middletown, Pennsylvania 17057-0480 (717)944 7621 Writer's Direct Dial Number:
(717) 948-8005 November 8,1994 C311-94-2302 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 October 1994 Enclosed are two copies of the October 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, M; bib 7
T. G. Broucjhton Vice President and Director, TMI WGH Attachments cc: Administrator, Region 1 TMI Senior Resident Inspector T94001
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9411210137 941031 PDR ADOCK 05000209 f
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GPU Nuclear Corporat on is a subsidiary of General Pubhc Utilities Corporation I
OPERATIONS
SUMMARY
October 1994 The plant entered the month operating at 100% power and remained at that level throughout the duration of the month.
Unit electrical output averaged approximately 811 MWe during October.
MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items accomplished during the month.
Make-Up Pump MU-P-12 Make-Up Pump MU-P-1B was removed from service to repair an outboard mechanical seal leak. Because a new type seal was being installed, a manufacturer's technical representative was on-site to oversee the seal installation.
Additional tasks performed included installation of balancing rings on the inboard and outboard shafts to improve vibration levels and the repair /
replacement of oil tubing and piping on the pump and the speed increaser.
Post maintenance test results were satisfactory and the pump was returned to service.
Containment Monitoring Valve CM-V-2 Containment Monitoring System valve CM-V-2 was removed from service to replace the valve actuator spring.
During bench testing of the reassembled actuator, an air leak from the actuator was observed. As a result, the shaft seat o-ring and the torque plug o-ring were replaced.
The actuator was retested and operated satisfactorily.
It was reinstalled on the valve, tested, and returned to service.
Nuclear Service Closed Cooling Water Pump NS-P-lC Nuclear Service Closed Cooling Water Pump NS-P-lC was removed from service because of noisy motor bearings.
The pump and motor were uncoupled and the motor end bells were removed to replace the bearings.
During reassembly of the motor, a Machinist rotated the pump by hand and felt continued movement in the pump after the pump shaft had stopped. As a result, the pump was disassembled and inspected. The impeller was loose on the shaft and the condition was caused by a loose impeller bolt and installation of a slightly undersized impeller key. A new key was installed and the impeller bolt torqued to the specified value.
Following the maintenance, NS-P-lC was reassembled, tested, and returned to service.
2
Diesel Driven Fire Service Puma FS-P-3 Diesel Driven Fire Service Pump FS-P-3 was removed from service for trouble-shooting after the pump failed to start on a loss of A/C power.
Trouble-shooting revealed that Agastat relay R9 was not working.
The relay was replaced and following a satisfactory test of FS-P-3, the pump was returned to service.
Miscellaneous Waste Evaporator Pump WDL-P-20 Miscellaneous Waste Evaporator Pump, WDL-P-20, was removed from service due to low output.
Investigation revealed that the pump shaft has broken and that the impeller was damaged. The wet end of the pump was replaced and WDL-P-20 was tested and returned to service.
The pump manufacturer and Plant Engineering are in the process of determining the cause of failure.
3
OPERATING DATA REPORT DOCKET NO.
50-289 OAre November 8, 1994 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:
OCTOBER 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 1
8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST P.EPORT, 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) 745.0 7296.0 176761.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 745.0 6898.7 100124.7
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0
-0.0 2284.0
- 14. HOURS GENERATOR ON-LINE (HRS) 745.0 6886.4 98991.1
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1912441 17354955 242222049
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 638803 5755431 81442214
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 603962-5418796 76483315
- 19. UNIT SERVICE FACTOR (1) 100.0 94.4 56.0 1
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 94.4 56.0-
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 103.1 94.5 55.1 22, UNIT CAPACITY FACTOR (USING DER NET) 99.0 90.7 52.8
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 38.0 UNIT FORCED OUTAGE HOURS (HRS) 0.0 1.8 60761.'2
- 24. SHUTDOWNS SCHEDULED CVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH).
J
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
4 l
AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO.
50-289 UNIT TMI-1 DATE N0vember 8, 1994 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:
. OCTOBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)
(MWe-NET) 1 808 17 814 2
808 18 811 3
814 19 807 4
813 20 801 5
813 21 805 6
815 22 807 7
812 23 806 8
810 24 808 9
805 25 810 10 813 76 812 11 816 27 811 12 815 28 814 13 814 29 812 14 811 30 811 15 812 31 807 16 81*
l i
5
=
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NAME TMI-1 REPORT MONTH October 1994 DATE November 8. 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 thereaf ter 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) 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 E0C-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 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 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 1
- 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 the rerack project full core off-load is assured through the end of the current operating license and beyond.
8