ML20059M509

Monthly Operating Rept for Oct 1993 for TMI-1

ML20059M509
Person / Time
Site:	Crane
Issue date:	10/31/1993
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-93-2160, NUDOCS 9311190131
Download: ML20059M509 (9)

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N GPU Nuclear Corporation

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f Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8005 l

November 15, 1993 C311-93-2160 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555 I

Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for October 1993 Enclosed are two copies of the October 1993 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, T. G. Broubiton Vice President and Director, TMI-1 WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector 1900C2 931031

\\I 9311190131 ADOCK 05000289 @F-l1 PDR R

PDR_j;j GPU Nuciear Corporation is a subsidia y of Generai Public Uti%es Corporation

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OPERATIONS

SUMMARY

l October 1993 l

The plant entered the month in cold shutdown while in the scheduled 10R '

outage. The outage was completed in just over 36 days when the turbine was put on line on 16 October. Full power was reached on 19 October.

Power was j

reduced to about 70% for a day while an oil leak at a bearing on the "B" l

feedwater pump was corrected. The plant electrical output averaged approximately 740 MWe after its return to service.

A Pressurizer Code Safety Valve (RC-RV-1B),. installed during the outage, began to leak by its seat during performance of a Technical Specification required

-i operational leak test which took the Reactor Coolant System (RCS) to 2285 psig. The leak persisted after the RCS was returned to normal system pressure.

i Valve leakage is being monitored while plans are made to replace the valve in November if an effort to reseat it is unsuccessful.

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MAJOR SAFETY RELATED MAINTENANCE j

i As reported in September, the plant shutdown for the scheduled 10R re'ueling l

outage on September 10. Activities completed during the outage since the last reporting period include:

Control Rod Drive Mechanism Repair Repairs to the control rod drive mechanisms (CRDMs) were performed while the reactor vessel head was on the head stand. The tasks accomplished included 4

the installation of new split segment ring nuts on 18 nozzle flanges and new-motor tube gaskets on all nozzle flanges prior to reinstallation of the motor tubes.

CRDM #28 was disassembled in support of the BWOG CRDM inspection program: the mechanism had experienced a ratchet trip. During the inspection, a lead screw 1

nut was found galled. A new complete lead screw assembly was installed during the reassembly of the mechanism.

i A broken T/C connector was repaired in stator B-8.

Refueling Activities l

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The reactor vessel head was reinstalled and _ tensioned, the insulation was replaced and the head cooling fans reconnected. The Intermediate Closed i

Cooling Water and electrical connections were made up at the CRDMs. The CRDMs l

and axial power shaping rods were recoupled. The reactor vessel. missile shields were returned to their position above the reactor vessel.

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i Reactor Building Polar Crane MIS-A-1 While the polar crane was lifting the reactor vessel head for reinstallation, a shudder was felt coming from the crane. The lift was immediately stopped.

An immediate inspection of the crane found that the oil cooler fan and recirculating pump were not operating.

Whiting,~the crane manufacturer, attributed the problem to be a binding of the mechanical load brake due to overheating the oil.

Their recommendations were incorporated into a test plan i

performed in conjunction with the lift. With the oil cooler fan and recirculating pump operating, the load was raised to verify that the mechanical load brake had not locked up. Having determined the status of the j

mechanical load brake, the lift proceeded. _ The head was lifted, moved and lowered on the vessel without further incident. Additional testing involved defeating the crane solenoid brake with a missile shield lifted three inches to determine whether the mechanical brake would hold the load. The brake functioned properly and the missile shields were reinstalled.

Whiting recommended that various main and auxiliary hook brake components be replaced prior to the next reactor vessel head lift.

Once Through Steam Generators RC-H-21A/B Maintenance Once Through Steam Generator work completed during October included the i

reinstallation of the upper and lower primary handhole and manway covers.

i Reactor Coolant Pump Maintenance l

Lubricating oil leaks on the Reactor Coolant Pump (RC-P-1A/lB/lC and ID) motors repaired earlier in the outage were inspected to verify the adequacy of the repairs. The inspection technique utilized a fluorescent dye added to the oil which would make any leakage visible under " black" lights during operation of each pump's lubricating oil system.

Leaking connections identified by the j

" black" lights were tightened and the leakage stopped, i

Conversion of the 1A and ID RCPs to seal cartridges from the conventional seal package was completed. The conversion included modification of the seal t

leakoff lines to accommodate design differences associated with the seal cartridges.

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Turbine Generator Reassembly of the main turbine control valves and 'C' low pressure rotor proceeded with no significant problems upon completion of the inspection.

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Primary System Valve Repairs i

Primary coolant leaks at the packing and flange gaskets on-the "A" and "B" l

Reactor Coolant Pump differential pressure transmitter valves were eliminated.

Valves RC-V-1042 and RC-V-1043 on the "A" pump and valves RC-V-1044 and RC-V--

-1045 on the "B" pump were removed for repacking and reinstalled with new-l flange gaskets, studs, nuts, and tubing connectors as required.

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While the primary coolant loops were drained to support other work: difficulty in getting DH-V-22B to seat was corrected, a pressure seal ring gasket leak l

was repaired on CF-V-1B, bonnet gasket leaks on CF-V-14B and CF-V-31B were i'

corrected and MU-V-86A and MU-V-220 were opened for engineering inspection and reassembled.

j Miscellaneous Outage Work j

The following is a summary of various refueling outage activities accomplished-i Completed 184 of 184 valve repacks.

l Completed 32 of 32 motor operated valve diagnostic tests (M0 VATS / VOTES).

Completed 118 of 118 Local Leak Rate Tests.

.l Completed 100 of 100 welded valve replacements.

Completed cleaning of 34 of 35 Switchgear/MCC cabinets t

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OPERATING DATA REPORT DOCKET NO.

.50-289 ficvember 15, 1993 DATE COMPLETED BY W G HEYSEK l

OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT I l NOTES:

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2. REPORTING PERIOL:

OCTOBER 1993' l

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3. LICENSED THERMAL POWER:

2568 l l

4. NAMEPLATE RATING (GROSS MWe):

871 l l

5. DESIGN ELECTRICAL RATING (NET MWe):

819 l lt

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):

834 l l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l l

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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:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS)

'745.0

.7296,.0 168001.0 12.. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 400.1 6400.1 91876.8

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2283.81

14. HOURS GENERATOR ON-LINE (HRS) 365.9 6360.0 90760 1

15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 853603' 15379033 221425737

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 285427 5181623 74526697

18. NET ELECTRICAL ENERGY GENERATED (MWH) 262511

'4869485 69971792

19. UNIT SERVICE FACTOR

(%)

49.1 87.2 54,0.

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20. UNIT AVAILABILITY FACTOR

(%)

49.1 87.2 54.0.

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21. UNIT CAPAC.'Y FACTOR (USING MDC NET) 44.8

.84.9 53.0 l

22. UNIT CAPI.-

cY FACTOR (USING DER NET) 43.0 81.5 50.9 l

23. UNIT FORCED OUTAGE RATE

(%)

0.0 1.1 40.1 UNIT FORCED OUTAGE HOURS (HRS) 0.0 69.7 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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- _ - _ _ = _ _ _ - - _ - _ - _

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i AVERAGE DAILY UNIT POWER LEVEL f

DOCYIT NO.

50-289 i

UNIT TMI-I l

DATE November 15. 1993 i

COMPLETED BY W G HEYSEK

>j TELEPHONE (717) 948-8191 1

MONTH:

OCTOBER i

'I DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

{

(MWe-NET)

(MWe-NET) j 1

-6 17 469 2

-5 18 610 3

-5 19 776

'I 4

-5 20 537 5

-5 21 598 6

-5 22 788 i -

7

-10 23 814

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1 8

-8 24 813 9

-9 25 809 l

10

-10 26 806-l 11

-11 27 811

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12

-11 28 816 13

-20 29 815

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14

-42 30 815 15

-43 31' 818

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-289 UNIT NAME TMI-1 REPORT MONTH October 1993 DATE November 15, 1993-COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 h

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1 None N/A N/A The unit continued its refueling and 93-maintenance outage until returning to t

04 operation at 19:07 on October 16, 1993.

10-19-93 F

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4 None SL P

An oil leak on the

'B" Feedwater Pump led to 93-a small fire and subsequent removal of the-05 pump from service until a bearing repair was l

completed. The plant, which was reduced to 64%, gradually returned to full power operation on October 22, 1993 in accordance with Physics Test requirements.

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i REFUELING INFORMATION REQUEST

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

4. Will refueling or resumption of operation thereafter require a technical specificat ion change or other license amendment?

NO

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

NA 6.

Important licensing considerations ossociated 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) GPUN will continue to improve the review process by submittal of Technical Specification Change Requests (TSCR) concerning the reload-related areas of fuel assembly reconstitution and removal of cycle-i dependent core limits to the Core Operating Limits Report (COLR).

1) GPUN withdrew TSCR Nc 200 to modify the TMI-I Technical Specifications to permit the substitution of Zr-4 or stainless steel replacement rods for failed fuel rods, in accordance with USNRC Generic Letter 90-02, dated February 1, 1990.

Generic Letter 90-02, Supplement I was issued on July 31, 1992, to clarify limitations on the application of currently-approved analytical methods and withdraw and replace the model TS recommended by Generic Letter 90-02. The B&W Owners Group Topical Report BAW-2149, " Evaluation of Replacement Rods in BWFC Fuel Assemblies", December 1991, was approved in April 1993. This report justifies the use of up to ten replacement stainicss steel rods located anv-Sere in a single fuel assembly based on currently-approved methodo'.,9y.

BAW-2149 provides the basis for reconstitution repairs of BWFC Mark B assemblies to be done under the provisions of 10 CFR 50.59 (i.e., the repair does not represent an unreviewed safety question). TSCR 232 was submitted in August 1993 in response to Generic Letter 90-02, Supplement I referencing BAW-2149.

2)

B&W Owners Group Topical Report BAW-10179P, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses", February 1991, was approved in March 1993. This topical provides a basis for changes to cycle-specific limits and to the Mark B fuel design to be under the provisions of 10 CFR 50.59.

Per NRC Generic Letter (GL) 88-16, BAW-10179P also provides the basis for removal of additional cycle-specific limits from the T. S. to the COLR. A TSCR will be submitted in November 1993 consistent with GL 88-16 and the BAW-10179P Safety Evaluation (March 16,1993) for the removal of cycle-specific protective and ma:timum allowable setpoint limits for axial power imbalance and othtr applicable cycle-dependent limits.

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7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 177 (b) 601

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 1990.

Phase 1 of the reracking project to increase spent fuel pool storage capacity permits storage of 1342 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 i

fuel pool assuming the present licensed capacity:

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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