ML20070F260
| ML20070F260 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1994 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-94-2103, NUDOCS 9407180252 | |
| Download: ML20070F260 (7) | |
Text
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GPU Nuclear Corporation 0 0 Muclear art;gr*
Middletown, Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Nurnber:
(717) 948-8005 July 13, 1994 C311-94-2103 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 June 1994 Enclosed are two copies of the June 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, h)
. Skr T. G. Bro hton Vice President and Director, TMI WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector T94001 9407180252 940630 PDR ADOCK 05000289 R
PDR 1C(([{
GPU Nuclear Corporation is a subsidiary of General Pubhc Utikties Corporation
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OPERATIONS
SUMMARY
June 1994 The plant entered the month operating at 50% power, continuing the derate in power output which began on May 30 to support of efforts to locate and repair main condenser tube leaks. The unit was shutdown at 1655 on June 1 to perform scheduled control rod drop time testing.
Three rods exceeded the 3/4 insertion time Technical Specification (TS) limit of 1.66 seconds. The thermal barriers on those control rods and that of an additional rod which had previously been out of spec were replaced.
Upon completion of the work, the i
four control rods were dropped and the times achieved satisfied the TS requirement. On June 9 the unit resumed power operation, achieving 100% full power operation at approximately 0030 on June 10.
It remained at that level through the end of the month.
Unit electrical output averaged approximately 731 MWe during June.
MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items accomplished during the month.
i Control Rod Drive Mechanism Repair j
The plant was shutdown for the purpose of performing control rod drop time testing. Three rods exceeded the Technical Specification 1.66 seund time limit for full out to three quarter full insertion. The plant was cooled down and preparations made to remove the three control rod drive mechanisms (CRDMs) and one additional CRDM that met the 1.66 second requirement during this test but had been slow during previous tests.
The effort included removal of the CRDM missile shields, closures, PI tubes,
'A' to 'B' cables, and stators.
A shielded work platform was installed to reduce radiological exposure to maintenance personnel.
The four CRDMs were fitted with new thermal barriers and new flexicarb gaskets before being reinstalled on the reactor vessel head.
The plant was returned to a hot shutdown condition and control rod drop time testing of the four CRDMs with the new thermal barriers was performed.
The test results were satisfactory.
Reactor Building Polar Crane MIS-A-1 Repairs With the plant off line for CRDM repairs, the Reactor Building Polar Crane, MIS-A-1 was removed from service to perform inspection and repairs. Work accomplished included cleaning the trolley span wires, replacement of one collector shoe and an auxiliary hoist gearbox oil seal, and repairing various oil piping leaks. The main hoist (185 Ton) mechanical load brake was found to be out of adjustment and was re-adjusted to the manufacturers specification.
A 25% (min.) of rated load (46.25 Tons) test was performed after the adjustment by lifting two CRDM missile shields with a spreader bar (total 2
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weight 57.07 Tons) with the solenoid load brake defeated.
The test was performed four times with the load at different heights with satisfactory results. Other work items accomplished included removal of the auxiliary hoist oil recirculation pump and motor.
The motor will be rewound during the Plant operating cycle and reinstalled in the llR outage.
Miscellaneous Outage Work Items The following is a summary of additional maintenance activities accomplished with the plant off-line for CRDM thermal barrier replacement:
- replaced Limitorque Operator grease in valves FW-V-1A and FW-V-2A.
- adjusted Pressure Switches C0-PS-447A/B/C.
- relocated valve IA-V-2366.
- installed grease relief plugs On LO-P-8A/B thrust bearing housings.
- repaired gasket leaks on RC4ATEl and RC4BTEl, MS-V-56A operator, MU-V-6A bonnet
- installed a modified declutch lever on FW-V-92A operator.
- performed a ' Ring' test on the Main Generator TG-GN-1.
- replaced the levering device on Circuit Breaker El-02.
- replaced solenoids on FW-V-17A/B operators.
- repaired indicating lights on valves TD-V-10A and TD-V-12A.
- performed troubleshooting of Incore Thermocouple IM-SPND-48 and determined future Incore replacement is necessary.
- replaced check valve IA-V-1424 and relief valve C0-V-161.
- relocated the tubing unions on RC-V-10ll.
- replaced IL-480V switchgear U-2A left racking rail.
- repaired relief valve EHC-V-FV25.
- repaired
'B' Reactor Coolant Pump Coupling vibration probe RC-VE-77A.
- repaired mechanical seal and casing leaks on GN-P-5B.
- replaced the Reactor Building Equipment Hatch inner door seal.
- repacked valves MU-V-10ll, MU-V-1012, MU-V-1035, MU-V-1036, MU-V-1037, MU-V-1038, MU-V-1031, MU-V-1032, MU-V-1033, MU-V-1034, MU-V-6B, and EX-V-llA/B.
- replaced Auxiliary Condenser Expansion Joints CW-XJ-3B, CW-XJ-3D, CW-XJ-4B, and CW-XJ-40.
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OPERATING DATA REPORT DOCKET NO.
50_289 DATE July 13. 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:
JUNE 1994 l
l
- 3. LICENSED THERMAL POWER:
2568 l l
4.
NAMEPLATE RATING (GROSS MWe):
871 l l
- 5. 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
I l
t 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
r 9, POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
1 THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD (HRS) 720.0 4343.0 173808.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 534.4 3945.7 97171.9
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0
_0.0 2283.8
- 14. HOURS GENERATOR ON-LINE (HRS) 527.3 3935.2 96039.9 7
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0 l
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1328170 9878377 234745029
[
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 431121 3296302 78983085
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 402980 3097276 74161795
- 19. UNIT SERVICE FACTOR
(%)
73.2 90.6 55.3
- 20. UNIT AVAILABILITY FACTOR
(%)
73.2 90.6 55.3
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 71.2 90.7 54.3
- 22. UNIT CAPACITY FACTOR (USING DER NET) 68.3 87.1 52.1
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 38.7 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60759.4
- 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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4
i AVERAGE DAILY UNIT POWER LEVEL i
I DOCKET NO.
50-289 UNIT TMI-1 f
DATE July 13,1994 COMPLETED BY W G HEYSEK l
TELEPHONE (717) 948-8191 MONTH:
JUNE I
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
( MWe-. NET )
(MWe-NET) l 1
220 17 787 2
-25 18 784 i
3
-12 19 783 j
4
-12 20 790 5
-11 21 790 6
-10 22 793 7
-13 23 793 8
-24 24 785 l
9 94 25 789 10 797 26 793 i
f 11 800 27 790 12 793 28 793 13 790 29 789 14 784 30 792 l
15 784 31 NA l
16 785
(
i I
i t
1 l
5
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NAME TMI-1 REPORT MONTH June 1994 DATE July 13, 1994 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 th hm ce=, a re,eci.e
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M Ad O gw W
owkm wm' Shuning ce Oh, gw rep""#
Ptegent Recwience RmW
- A*
- ge 94-04 5-30-94 S
0 8
4 None SG COND The Unit continued the power derate to 50% initiated on May 30 in support of efforts to locate and repair main condenser tube leaks. Sequentially, the "A" and "B" sides of the condenser were removed tTom service, ieak tested and repaired.
The unit 94-05 6-1-94 S
192.7 B
1 94-004 AA Roo shutdown from 50% power to perform scheduled control rod drop time testing. Three rods exceeded the TS specified limit of 1.66 seconds. The thermal barriers on those control rods and that of a rod which had been previously out of spec were replaced. Upon completion of the work, the four control rods were dropped and the times achieved satisfied the TS requirement. On June 9 the unit resumed power operation.
i 1
2 3
4 F Forced Enhibit G - Instructions for Reason Method properet ton of Data Entry Sheets S Scheduled A-Equipment ratture (Explain) 1-Manuel for Licensee Event Report (LER)
B Maintenance or Test F-Menval Scram File (NUREG-o161) c-mofueling 3, Automatic Scram D Regulatory Resteietion 4-other (Emplain)
E
~
E-ooecoter Training & Licensing Esemination J Exhibit I same source F-Administrative RM;** R";laig" ""O")
6 Actua ny use4 e h..its r & n nuREs om o
t' 6
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f REFUELING INFORMATION RE0 VEST r
- 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 l
- 4. Will refueling or resumption of operation thereafter require a technical l
specification change or other license amendment?
NO
- 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 B9 provides a leaf-type cruciform assembly holddown spring to replace the previous coil spring designs that 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.
- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 601 j
- 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, i
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 i
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:
l 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.
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