ML20062E646
| ML20062E646 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1990 |
| From: | Heysek W, Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-90-2143, NUDOCS 9011210149 | |
| Download: ML20062E646 (6) | |
Text
O GPU Nuclear Corporation
^, U Nuclear
- ,o"rs:reo Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
November 15, 1990 C311-90-2143 U. S. Nuclear Regulatory Commission Attna Document Control Desk Washington, D.C.
20555 centlement
Subject:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report October 1990 Enclosed are two copies of the October, 1990 Monthly Operating Repert for Three Mile Island Nuclear Station, Unit 1.
Sincerely,
- 1.
D.-
kill Vice President & Director, THI~1 HLH/WGH cc Administrator, Region I THI Senior Resident Inepector Attachmente 9011210149 90103:1 F'DR ADOCK 0500o2ap R
,..u GPU Nuclear Corporation is a subsidiary of General Public Utilities Cc rporation
OPERATIONS
SUMMARY
OCTOBER 1990 l
The unit entered the month operating at -50% power producing 360 MWe. The "A"
side of the main condenser was out of service to repair tube leaks. A -2. 5'F ATc was being used to offset the fouling in the "B" OTSO.
On October 3rd, reactor power was increased following the condencer tube leak repairs and the plant reached 96% pNor on October 4th. A -4.5'r ATc was input to of f set the high OTSO on the "B" side. The plant closed the month operating at 95% power producing 820 MWo.
T*.e unit continues to experience additional OTSO fouling that further limits power output.
MAJOR SAFETY RELATED MAINTENANCE During october, the following major safety related maintenance activity was performed:
Emeraency Diesel Generator EG-Y-1A/B Surveillance overhaul Both Emergency Diesel Generators EG-Y-1A and IB were removed f rom service to perform the annual surveillance overhaul. Maintenance on the 1A diesel included repair of fuel oil leaks at the fuel pump tappet assemblies, replacement of the number 13 and 14 main bearings and the air start compressor.
No major discrepancies were noted during the 1B diesel surveillance.
Both EG-Y-1A and IB were returned to service after satisfactory test runs.
Hydroaen Recombiner HR-R-1B The modification work performed to replace the HR-R-1B expansion jrints with hard p',pe completed in October.
The new piping sections were weldr.d in place and radiography examination of the welds was performed.
Satisfactory results were obtained.
After the flange connections were made up r.id a satisfactory hydrostatic test was complettd, a surveillance run of the recombiner was performed and the unit was returned to service.
2
OPE 2.OTING DATQ REPORT 3
m p
c DOCKET NO.
50-289 DATE 10-31-90 COMPLETED BY W.G, Heysek L
TELEPHONE (717) 948-8191 OPERATING STATUS L-I NOTES I
- 1. UNIT NAME:
THREE M.*LE ISLAND UNIT I I l
2.! REPORTING PERIOD:
OCTOBER
,1990. I I
- 3. LICENSED THERMAL POWER (MWT):
25GB. I i
14 NAMEPLATE RATING (GROSS MWE):
071. I I
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819. 1 I
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
856. l l
7.. MAXIMUM DEPENDABLE CAPACITY-(NET MWE):
808. I I
I l
I'O. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
1 9.: POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
- 10. REASONS:FOR RESTRICTIONS, IF ANY:
L
[:.
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THIS MONTH YR-TO-DATE CUMMULATIVE l11. HOURS IN. REPORTING" PERIOD 745.
7296.-
141697.
[12. NUMBER OF HOURS REACTOR WAS CRITICAL 745.0-5701.6 67700.2
<!3.: REACTOR RESERVE SHUTDOWN HOURS 0.0 242.0 2245.0 10." HOURS GENERATOR ON-LINE 745.0 5659.6 66655.7
!15. UNIT, RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 F16.' GROSSLTHERMAL ENERGY GENERATED (MWH) 172G929.
13420904.
162992879.
L17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 575020.
4480574.
54787243.
L 18. NET ELECTRICAL' ENERGY GENERATED (MWH).
540935.
4198095.
51384584.
'lO.LUNIT SERVICE FACTOR 100.0 77.6 47.0
- 20.: UNIT AVAILABILITY FACTOR 100.0 77.6 47.0
'21.; UNIT CAPACITY FACTOR (USING'MDC' NET) 89.9 71'.2 46.2
)22.; UNIT CAPACITY FACTOR (USING4 DER NET) 88.7 70.3 44.3 "23. UNIT FORCED OUTAGE RATE O.O' 4.0 47.6-ll2Q.fSHUTDOWNS' SCHEDULED OVER NEXT 6 MONTHS kTYPE, DATE.fAND--DURATION OF:EACH "25.,IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP -
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- DOCKET NO.
50-289 UNIT TMI-!
1 DATE 10-31-90 1
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COMPLETED BY W d Heysek i!
TELEPHONE T717) 948-8191
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MONTH's. OCTOBER' DAY AVER GE DAILY POWER: LEVEL DAY AVERAGE DAILY POWER LEVEL d
-(MWE-NET)
(MWE-NET)
- I-322.
17 772.
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=322.
18-
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3
.332.
19 777.
',4 2746.
20 700.
2
-5' 776.
21 776.
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22 773..
A 7
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- 770..23-76G.
18 768.'
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26 774.
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27 778.-
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28 774 6
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29 776.
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30 775.
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UNIT S" N S AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NAME TMI-1 REPORT MONTH October 1990 DATE 11/15/90 CosqFLETED BY W. G. Heysek TELEPROUWE (717) 948-8191 Meth'd of Licensee Systen Component Cause & Corrective l
No.
Date Type Duration Reason shutting Event Code Code Action to (Neurs)
Ocun Report #
Prevent Recurrence 3
6
- eactor 5 6 g
90-10/1-S 77 B
4 NA SG HTEXCH The unit was reduced to 50% reactor power 04 10/4/90 to locate and repair main condenser tube leaks.
1 2
3 4
F Ferced Reesen Method Ezhibit G - trstructions for S Scheduled A-Equipment Failure (Exclain) 1-Manuet preperation of Cata Entry Sheets 8-Maintenance or Test 2-Manuet Scree fer Licensee Event Report (LER)
C-Refueling 3-Automatic scram File (NUREG-0161)
D-Regulatory Restriction 4-Other (Explain)
E-Operater Training & Licensing Er. amination 5 Exhibit 1 same source F-A&tinistrative G-Operational Error (Emptain) 6 Actustly used exhibits F & II IRJItEG 0161 R-Other (Explain) 6
I 1.,
REFUELING INFORMATION REOUEST
- 1. Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
October 4, 1991 (9R)
- 3. Scheduled date for restart following current refuelings NA
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No.
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 core reload (Ref. 10 CPR Section 50.59)?
No.
If no such review has taken place, when is it scheduled? 6/1/91.
- 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 Wuclear intends to install four Westinghouse Lead Test Assemblies during the reload of the TNI-1 core for cycle 9 operation. Westinghouse fuel technology will be utilised to the extent possible.
- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 177 (b) 441
- 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 752.
Planning to increase licensed capacity through fuel pool raracking is in progress.
- 9. The projected date of the last refueling that can be discharged to the m
l spent fuel pool assuming the present licensed capacity:
1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
7
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