ML20105B529
| ML20105B529 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/31/1992 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-92-2124, NUDOCS 9209210007 | |
| Download: ML20105B529 (7) | |
Text
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CPU Nuclear Corporation (aah.
U gf Post Office Box 480 Route 441 south Middl6 town, Pennsylvania 17057 0191 717 944 7621 1ELEX 84 2386 W.;?t's Direct Dial Number:
(717) 948-8005 September 14, 1992 C311-92-2124 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 August 1992 Enclosed are two copies of the August 1992 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, y
T. G. ir q hton Vice P.-csidei.t and Director, TMI-1 WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector
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l PDR GPU Nuclear Corporation is a subsidiaq of General Pubbc Utiktres Corporation 1
4 OPERATIONS
SUMMARY
AUGUST 1992 The plant entaed the month operating at 100% power producing 831 HWe.
It continued at that power level until August 20, when reactor power was increased an additional 1.6% through the implementation of a feedwater flow correction factor. A new, more accurate full power level is achieved by compensating for feedwater flow nozzle fouling with the correction factor.
The plant continued to operate at 100% power until August 31. A planned reduction to 50% power was completed at the clore of this reporting period due to condenser fouling caused by Asiatic clam buildup on the condenser tube sheets.
On August 26, fire watches were established in plant areas where Thermo-Lag fire barrier envelopes are installed.
The compensatory action was taken in response to information provided by the NRC in Bulletin 92-01 and Bulletin 92-01, Supplement 1.
MAJOR SAFETY RELATED MAINTENANCE During August, the following major safety related maintenance activities were performed:
Decay Heat Removal Pumo DH-P-1B Decay Heat Removal Pump DH-P-1B was removed from service for a scheduled system outage. While the pump / motor coupling spool was removed for coupling lubrication and a coupling alignment check, internal rubbing was noted during hand rotation of the pump. The pump was subsequently disassembled and inspected.
Inspection revealed slight scratches on the impeller and casing wearing ring surfaces and a small amount of metal filings in the vacinity of the wear ring in the bottom of the pump casing. There were no deficiencies found on either the bearings or shaft. After the impeller and casing wear ring clearances were measured and found to be within specified tolerances, they were hand " dressed".
The pump rotating assembly was reinstalled in the casing and the pump shaft was rotated during the torquing of the casing bolts.
The rubbing recurred prior to attaining the specified torque value.
Because there was no evidence of binding or change in pump vibration before the pump was taken out of service and the coupling spool piece removed, it was decided to reinstall the coupling spool piece and rotate the pump shaft. With the coupling spool reinstalled, the pump shaf t rotated freely with no evidence of rubbing or binding. The pump / motor coupling alignment was found to be within specified limits and DH-P-1B reassembly work was completed.
Post maintenance testing was completed with satisfactory vibration levels and required head and flow rate. The pump was returned to service.
Plant Engineering is investigating the cause of the rubbing.
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~ Miscellaneous Waste Transfer Pumo WDL-P-7B Hiscellaneous Waste Transfer Pump WDL-P-7A was remeved from service to repair mechanical seal leakage. While the pump was disassembled, components were inspected for damage.
The bearings were found worn and were determined to be the cause of the seal leakage. The pump shaft, bearings, oil seals, and mechanical seal were replaced during the reassembly of WDL-P-7A. The pump was returned to service after post maintenance testing was completed.
Reactor Protection System (RPS)
During routine RPS testing, the "B" Loop T-Hot trip circuit did not trip as designed. The " blue ribbon" connectors were exercised and when the., tem was retested, the trip circuit tripped as designed.
As required by Techni,21 Specifications, the RPS "A", "C",
and "D" Loop T-Hot trip functions were tested with no discrepancies.
Subsequent analysis determined that the conservative course of action was to replace the "B" Loop T-Hot bistable module. The bistable was replaced and the system was returned to service.
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OPERATING DATA REPORT 1
i DOCKET NO.
50-289 j
DATE September 14, 19_92 l
COMPLETED BY W G HEYSEK I
C?ERATING STATUS TELEPHONE (717) 948-8191 j
j
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
I
- 2. REPORTING PERIOD:
AUGUST 1992
[
- 3. LICENSED THERMAL POWER:
2568
}
- 4. NAMEPLATE RATING (GROSS MWe):
871 l
S. DESIGN ELECTRICAL RATING (NET MWe):
819
- 6. MAXINUM DEPENDABLE CAPACITY (GROSS MWe):
834 j
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
786 j
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:
i l
THIS MONTH YR-TO-DATE CUMMULATIVE j
- 11. HOURS IN REPORTING PERIOD (HRS) 744.0
=5855.0 157776.0 i
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5855.0 82586.0 i
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2245.6
- 14. HOURS GENERATOR ON-LINE (HRS) 744.0 5855.0 81511.2
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0' O.0 0.0 1
16 GROSS THERMAL ENERGY GENERATED (MWH) 1906278 15015404 198884449
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 623941 4972179 66966438-
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 589046 4694530 62851855 j
- 19. UNIT SERVICE FACTOR
(%)
100.0 100.0 51.7 l
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 100.0 51.7 j
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 100.7 102.0 50.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 96.7 97.9 48.6
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 42.7 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60648.7
- 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 September 14, 1992 COMPLE!*D W G HEYSEK TELEPHONE (717) 948-8191 MONTH:
AUGUST DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)
(MWe-NET) 1 791 17 791 2
791 18 787 3
787 19 791 4
788 20:
800-5 794 21 806 6
794 22 803 7
793 23 801 8
790 24
-797 9
782 25 791 10 784 26 788 11 782 27 786 12 789 28 783 13 791 29 801 14 792 30 799 15 794 31 783 16 794
)
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCIET NO.
50-289 LMIT NAME TMI-1 REPORT MONTH Aucust 1992 DATE September 14, 1992 COMPLETED BY W. G.
Heysek TELEPHONE (717) 948-8191 k
Method of Licensee System :omponent Cause & Corrective No.
Date Type' Duration Reason' Shutting Event Code Code Action to (Mours)
Dom Report #
Prevent Recurrence Reactor' 92-8/3I/92 F
0 B
4 NONE TBD TBD Condenser macrofouling (Asiatic clams) led to 01 a 50s power reduction for nearly five days beginning 8/31/92 to accociplish tube and waterbox cleaning. The subsequent preventative actions include installation of smaller mesh screens in the cooling water system and increa nd frequency of " clam kill
- chemistry treatment of the system.
4 1
2 3
4 F Forced iteason Method Exhibit G - Instructions for S Scheduled A-Equipnent Failure (Explain) 1-Manual preparation of Data Entry Sheets 4-Maintenance or Test 2-Manust Scram for Licensee Event Report (LER)
C-Refueling 3-Automatic Scram File (NtJREG-0161)
D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & Licensing Examination 5 Exhibit 1 same source F-Adninistrative G-Operational Error (Explain) 6 Actually used exhibits F & II NUREG 0161
.M-Other (Explain) 6
.]
REFUELING INFORMATION RE0 VEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.=
Scheduled date for next refueling shutdown:
September 17, 1993 (10R)
]
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? NA' i
If answer is yes, in general, what will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the cor'e reload (Ref. 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
5.
Scheduled date(s) for submitting proposed-licensing action and supporting information-None planned.
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:
GPU Nuclear has installed four Westinghouse Lead Test Assemblies during the reload of the TMI-1 core-for cycle 9 operation.
Westinghouse fuel technology will be utililad to the extent possible.
7.
The number.of fuel assemblies (a) in the core, and (b). in the spent fuel storage pool:
-(a) 177 (b) 521 8.
The present licensed spent fuel pool st'orage 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 1496. Reracking of spent fuel pool
' A' to attain the licensed capacity 1:, in progress.
9.
The projected date of the-last refueling that can be discharged to the spent fuel pool-assuming the present licensed capacity:
4.
- The 9R-(1991) refueling discharge was the 1ast to allow full core
~
off-load. capacity (177 fuel-assemblies). Upon completion of the reracking project, full core off-load is assured through the.end of 4
the current operating license and beyond.
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