ML20099G441
| ML20099G441 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1992 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-92-2113, NUDOCS 9208170048 | |
| Download: ML20099G441 (7) | |
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GPU Nucigar Corporation ff Nuclear
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Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2380 Writer's Direct Dial Number:
(717) 948-8005 August 10, 1992 C311-92-2113 U. S. fM 1 ear 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 July 1992 Enclosed are two copies of the July 1992 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Silicerely,
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"'p T. G. Broughton Vice President and Director, THI-l WGl!
Attachments cc: Administrator, Region I THI~ Senior Resident Inspector l.
9200170048 920731 13 l
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GPU Nuclear Corporation is a Pubsidiary of GCneral Pub!:c Utihtes Corporation b
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OPERATIONS
SUMMARY
JULY 1992 i
i The unit enter 9d the month operating at 100% power producing 838 MWe.
It continued full power operation for the entire month of July, closing the month producing 835 MWe. An INPO team was on site for two weeks to perform an evaluation of plant activities.
On July 16th, an underground fuel oil leak was detected via a routine sample from site monitoring wells. The leak was found and the repair effort completed by July 22nd.
The entire line was leak tested satisfactorily.
Both a "7 kV Bus Ground" and a "7 kv Bus Trouble" alarm were received in the con'rol room on July 25th for the "B" 7ky bus. Smoke from the associated bus duct was reported and all station loads were transferred to the "A" cuxiliary transformer. The "A" diesel was started to satisfy an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Technical Specification (TS) time clock. A TS 30 Day time clock was l
subsequently entered as a result of h: Wing only one auxiliary transformer in l
service. The problem resulted from a ground on the "B" phase of the bus resulting from water intrusion from the outside duct in combination with the degradation-of the insulation on the bus bar. After repairs were made to the bus bar insulation and the duct was sealad, all loads were realigned. At 0430 on July 26th, the TS time clock was teiminated.
NRC Chairman Selin toured THI-1 on July 27th.
F%dback on the tour was positive.
MAJOR SAFETY RELATED MAINTENANCE During July, the following major safety related maintenance activities were performed:
Miscellaneous Waste Transfer Pumo WDL-P-7B Miscellaneous Waste Transfer Pump WOL-P-78 was removed from service to repair mechanical-seal leakage.
The Pump was disassembled.and inspected. Due to wear, the pump' shaft, bearings, oil seals, and oil slinger were replaced. The reassembled r.np was fitted with a new mechanical seal, aligned and coupled to the motor.
WDL-P-7D was returned to service after it was satisfactorily tested.
Air Intake Tunnel Fire System During a thunderstorm, a portion of the Air Intake Tunnel Fire Suppression System actuated. Lightening actuated six inside curtain wall halon bottles and sat off the Grinnell deluge system.
Investigations revealed that ultra-2
violet detector 41H was full of water and pressure detectors BS-42A, BS-420, BS-42E and BS-42F were grounded. The ultra-violet detector and pressure detectors were removed, cleaned, dried, and tested.
The six (6) halon bottles were replaced and ultra-violet detector and pressure detectors installed.
Functional testing was performed and the system returned to service.
@xiliary Transformed "B" A "7 kv Bus Ground" and a "7 kv Bus Trouble" were received on the plant alarm panel. The plant computer indicatad that the problem was on the "B" 7 kv bus.
Targets were found showing on the ground and 27-2 undervoltage relays.
Operators observed smoke entering the ventilation slots in the turbine building wall near the "B" Auxiliary Transformer (AT).
The electric load was switched to the "A" AT and the "B" AT was isolated from the 6.9kv bus. While meggering the 6.9ky bus, the "B" phase was found to be grounded.
The bus duct was disassembled on both sides of the Turbine Building wall and inspected.
The inspection revealed that the heat shrink tubing was buried or eroded away from the bottom of the "B" phase bus bar. Voltage h d tracked between two layers of insulating board, which acts as a fire stop/ air seal inside the bus ducts housing, to ground via a bolt which holds the insulating board in place.
It appeared that moisture had seeped into the duct between the two layers of fiberglass, allowing the voltage to arc from the bus bar to the bolt.
The heat shrink tubing was rep 1 ced with HVBT tape rated at 15 kv and the insulating board replaced with a single layer of polyethylene. The duct, a short crack in the concrete wall and th: jap between the barrier board and the bus bars was scaled to prevent the entry of moisture.
The "B" AT was satisfactorily tested and returned to service.
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I OPERATING DATA REPORT l
DOCKET No.
50-289 DATE August 10. 1992 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191
- 1. UNIT NAME:
THREE HILE ISLAND UNIT 1 NOTES:
- 2. REPORTING PERIOD:
JULY 1992
- 3. LICENSED THERMAL POWER:
2568
- 4. NAMEPLATE RATING (GROSS HWe):
871
- 5. DESIGN ELECTRICAL RATING (NET HWe):
819
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS HWe):
834 7.,MAXIMUH DEPENDABLE CAPACITY (NET MWe):
786 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET HWe):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS HONTH YR-TO-DATE CUHHULATIVE 11.. HOURS IN REPORTING PERIOD (HRS) 744.0 5111.0 157032.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5111.0 81842.0
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2245.6
~ 14. HOURS GENERATOR OH-LINE (HRS) 744.0 5111.0 80767.2
. 15.' UNIT RESERVE SHUTDOWN HOV35 (HRS) 0.0 0.0 0.0
- 16. - GROSS THERHAL ENERGY GENERATED (HWH) 1908743 13109126 196978172
- 17. GROSS ELECTRICAL ENERGY GENERATED (HWH) 619532 4348238 66342497
- 18. NET ELECTRICAL. ENERGY GENERATED' (MWM) 584736 4105484 62262809
- 19. UNIT SERVICE FACTOR
(%)
100.0 100.0 51.4 30.' UNIT AVAILABILITY FACTOR
(%)
100.0 100.0 51.4
- 31. UNIT CAPACITY FACTOR (USING MDC NET) 100.0 102.2 50.4
- 22. UNIT CAPACITY FACTOR (USING DER NET) 96.0 98.1 48.4
- 23. UNIT FORCED OUTAGE. RATE
(%)
0.0 0.0 42.9 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60648.7
- 84. SHUTDOWNS SCHEDULtD OVER NEXT 6 HONTHS (TYPE, DATE AND DURATION OF EACH):
- 35. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
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. 4 AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO.
50-289 UN7T TMI-1 DATE Auoust 10. 1992 COMPLETED ~DY W G HEYSEK TELEPHONE (717) 948-8191 MONTMs JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
.MWe-NET)
(MWe-NET)
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785 17 784 2
794 18 782 3
797 19 784 4
-793 20 783
.5 791 21
-785 6
791.
22 791 7
794-23 789 8
7?C 24 791 9.
778 25 796 10 783 26 789 11
'780
-27 780 12 781 28 790 13 776 29 786 14-715 30 785
.15 T7 31 780~
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- r UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NANE TMI-l REPORT MONTH July 1992 DATE ' August 10, 1992; COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 I
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Mett.ed of Licensee.
System :orponent Cause & Correcti n N*-
Date Typ Durt+.lon Reason" Shutting Event Code Code Action to (Mours)
Down Report #
Prevent Necurrence Reactor *
- 8. &
- NONE 1
2 3
4 F Forced Reason Method.
Exhibit G - Instruction: for S Scheduled A-Equiprren Falture (Explain) 1-Manual preparation of Data Entry Sheets B-Mainter.ence or Test 2-Manual Scram for Licensee Eveni Rwt (LER)
C-Refueting 3-Automatie Scra:p Fi1e (NUREG-0161)
D-Regulato y Restriction 4-Other (Explain)
E-Operator Trair ing & Licensing Examination 5 Exhibit 1 sane sou ce F-Ackninistrative G-Operational Error (Explain) 6 Actuelty used exhibits F & 11 !dtREG 0161 H-Other (Explain) 6
REFVEl.ING 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 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 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 inforrcation:
None planned.
6.
Important licensing considerations associated with refueling, e.g. new or different fual 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 THI-1 core for cycle 9 operation.
Westinghouse fuel technology will be utilized 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 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 1496.
Roracking of spent fuel pool
'A' to attain the licensed capacity is in progress.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
The CR (1991) refueling discharge was the last 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 the current operating license and beyond.
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