ML20077Q172
| ML20077Q172 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1991 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-91-2092, NUDOCS 9108210096 | |
| Download: ML20077Q172 (8) | |
Text
.
GPU Nuclear Corporation
- U Nuclear
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Hiddletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8005 August 14, 1991 C311-91-2092 c
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 July 1991 Enclosed are two copies of the July,1991 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, f
T. G. Broughton Vice President and Director, TMI-l WGH:
Attachments cc:
Administrator, Region I TMI Senior Resident Inspector
.- < p. ; o j w,LVU%
9108210096 ?10731 PDR ADOCK 05000289 fi FDP GPU Nuclear Corporat!on is a subsid,ary of Genera! Pubhc Utihttes Corporation
I OPERATIONS
SUMMARY
JULY 1991 TM1 Unit 1 entered the month of July operating at 92% power producing ~760 MWe gross electrical generation. This power level was maintained until 7/24/91 when a low pressure reactor trip occurred as a result of the Group 7 control rods dropping into the core. The post trip response was normal.
The reactor trip is being documented by LER 91-002. The unit completed a continuous on-line operating run of 479 days when the reactor trip occurred.
This is a world record for light water reactor operation.
During the unplanned shutdown, an instrument fitting leak on the "A" 0TSG was repaired which reduced leakage into the reactor building by ~1500 gallons per day.
Several feedwater heater tube leaks were also plugged which reduced heater leakage by
~1500 gallons per minute.
Restart of the unit occurred on 7/26/91 with a maximum power of 95% achieved on 7/27/91.
The unit closed the month operating at ~95% reactor power producing -811 MWe.
Power output continues to be limited by high levels in the 'B" 0TSG.
MAJOR SAFETf RELATED MAINTENANCE During July, the following major Safety Related maintenance items were completed:
Nuclear Service River Water Strainer NR-S-lC Nuclear Service River Water Strainer NR-S-lC was removed from service to repair drive unit oil leaks.
The drive unit and motor were removed and disassembled. The drive unit oil seal was replaced along with associated gaskets.
A new vented sightglass was installed and the drive unit cover drilled and tapped to provide for adding oil to the unit.
The motor was cleaned and the bearings and oil seal replaced. The drive unit and its motor were reinstalled and satisfactorily tested. NR-S-lC was then returned to service.
The following is a summary of maintenance items that were accomplished while the plant was in the " hot shutdown" condition.
1 TG-GN-2 The Turbine Generator Exciter brush holder E-2 was replaced because of weak spring tension.
Other work accomplished on the Exciter included removal of coupling weights that were installed during the 8R outage and performing a resonant frequency test on the Exciter.
2
i I'
2 MU-V
- An infra-red scan of the high pressure injection legs was performed to verify operability of check valves MU-V-86A, MU-V-868, MU-V-94, and MU-V-95.
3 LO-P-5 Main Turbine turning gear lube oil pump LO-P-5 tripped on thermal overload.
Inspections revealed that the "A" phase connection was loose. All line voltage connections were tightened and LO-P-5 returned to service.
4 TD-V-lD Turbine Drain valve TD-V-lD was stuck closed.
I contacts LS3 and LS5 were cleaned and aligned. The valve was cycled and returned to service.
5 M0 VATS
-M0 VATS differential pressure testing was performed on Main Steam valves MS-V-2A, MS-V-2B, MS-V-10A and MS-V-106.
^
6 HD-P-18/C Heater Drain Pump HD-P-1B and HD-P-lC motors were meggered and motor oil was changed. The pump bearing oil was changed cn all three pumps.
t 7
FW-J-1A The' "A"- 2" stage feedwater Heater, FW-J-1A was opened to repair tube leaks.
Leak checks revealed two leaking tubes.
and two leaking tapered plugs.
The leaking tubes were plugged and the tapered plugs reseated.
8 FW-J-2A The "A" 4" stage feedwater Heater, FW-J-2A was opened to repair tube leaks. A leak check revealed three leaking tubes.
The leaking tubes were plugged and FW-J-2A closed.
9 FW-J-3B The "B" 6" stage Feedwater Heater, FW-J-2B was opened to repair tube leaks. A leak check revealed five leaking tubes.
The leaking tubes were plugged and FW-J-3B closed.
10 FW-U-18 Main Feedwater Pump Turbine, FW-U-1B was inspected because of control linkage binding. A rod bushing on the linkage was replaced and the linkage tested without further binding.
The linkage will be inspected again during the 9R outage.
11 HV-V-13A Heater Vent Valve HV-V-13A was replaced because of a leaking blowdown plug.
12 MU-H-49/50 Repairs to pipe hangers MU-H-49 50 were made to prevent the
/
supports from being overloaded due to thermal expansion of i.he piping.
Repair work inclujed removal of the pipe lugs to clear the horizontal support member and tightening an anchor bolt on-MU-H-50, 13 FW-V-1088 Feedwater valve FW-V-1088 repair work performed consisted of replacing _a pipe to tubing fitting on the downstream side of the valve.
3
14 M0-V-2C Moisture separator valve M0-V-2C bonnet bolts were retorqued to repair a bonnet leak.
This effort was unsuccessful and the valve will be repaired during 9R.
15 Fire
. Replaced eight Reactor Building Fire Detectors and removed Detectors the associated counter zone modules.
16 FW-U-1B Repairs were made on the "B" Feedwater Pump Turbine due to the oil trip test lockout valve ' normal' light not re-lighting after testing.
A faulty light socket was repaired.
17
'EHC' Turbine Generator Electro-Hydraulic Control System repair System work accomplisned included replacing a meter relay on EHC-PS-2.
18 Control Rod Group 7 Rod Power repairs included repairing loose transistor Q1 and Q2 socket connections in the phase
'A' gate drive.
19 Control Rod Group 7 rods #1, #3, and #8 were found stuck during testing.
The rods were freed in accordance with the B&W Technical Manual by latching and pulling the rods in
" jog speed." Subsequent testing confirmed that the trip function was unaffected.
4 4
(._
l OPERATING DATA REPORT DOCKET NO.
50-289 DATE COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 OPERATING STATUS
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
- 2. REPORT 1MG Wihju3:
JULY 1991 2568
- 3. LICENSED THERMA. POWER:
871
- 4. NAMEPLATE RATING (GROSS MWe):
- 5. DESIGN ELECTRICAL RATING (NET MWe):
819
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
856
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
808 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. h0WER 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 5087.0 148248.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 697.5 5040.5 74204.7
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2245.6
- 14. HOURS GENERATOR ON-LINE (HK3) 692.1 5035.1 73154.8
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED
.(MWH) 1582093 11315635 177785967
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 534323 3988270 59949174
- 18. NE"' ELECTRICAL ENERGY GENERATED (MWH) 500147 3749517 56238937
- 19. UNIT SERVICE FACTOR
(%)
93.0 99.0 49.3
- 20. UNIT AVAILABILITY FACTOR
(%)
93.0 99.0 49.3
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 83.2 91.2 48.3
- 22. UNIT CAPACITY FACTOR (USING DER NET) 82.1 90.0 46.3
- 23. UNIT FORCED OUTAGE RATE
(%)
7.0 1.0 45.3
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
Cycle 9 Refueling Outage, scheduled to begin 9/?7/91. with a nominal 7 to 10 week duration.
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt 5
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 HONTH:
JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)
(MWe-NET) 1 730 17 718 2
726 18 715 J
726 19 710 4
729 20 710 5
731 21 709 6
723 22 709 7
720 23 705 8
719 24 125 9
724 25
-43 10 727 26 342 11 726 27 766 12 725 28 767 13 722 29 768 14 723 30 769 15 728 11 766 16 724 l
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NAME
- fMI-l REPORT MONTH July 1991 DATE COMPLETED BY W.
G. Heysek TELEPHONE (717) 948-8191 i
Nethod of Licensee System Coriponent cause & Corrective ko-Date Type' Duration Reason
- Shutting Event Code Code Action to (Hours)
Dom Report #
Prevent Recurrence Reactor'
- L*
I 91-07/24/91 F
51.9 H
3 LER 91-002 The reactor tripped on low pressure after 03 dropping the Group 7 rods.
When the ICS called for Group 7 to move, the group dropped when stepping through a de-energized phase.
Post trip response was good and a Plant Incident Report documents the event.
I 1
2 3
4 F Forced Reasm Method Exhibit G - Instructions for S Scheduled A-Equipnent Failure (Explain) 1-Manual preparation of Data Entry Sheets B-Aaintenance or Test 2-Manual Scram for Licensee Event Report (LE2)
C-Refueling 3-Automatic Scram File (WJREG-0161)
D-Regulatory Rest *iction 4-Other (Explain)
E-Operator Training & Licensing Examination 5 Exhibit 1 same source F-Achinistrative G-Operational Error (Explain) 6 Actually used exhibits F & !! WEG 0161 H-Other (Explain) t I
l l
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1 REFVELING INFORMATION RE0 VEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 i
2.
Scheduled date for next refueling shutdown:
September 27, 1991 (9R) 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.
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)? No.
If no such review has taken place, when is it scheduled? 8/91.
5.
Scheduled date(s) for submitting proposed licensing action and support-ing 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 plans to install four Westinghouse Lead Test Assem-blies during the reload of the TMI-1 core for cycle 9 operation.
Wastinghouse 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) 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 reracking 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:
1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
8