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Monthly Operating Rept for Nov 1982
	ML20070R081
Person / Time
Site:	Oyster Creek
Issue date:	12/15/1982
From:	Baran R, Frick R; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20070R071	List: ML20070R068; ML20070R081;
References
	NUDOCS 8301270276
	Download: ML20070R081 (11)
	v • d • e

l OPEPATIONS NOV94BER At the beginning of the report period, the OC Station was operating at 335 MWe with load limited by core reactivity.

The Plant is still experiencing problems with intermittent salt leaks on "A" Main Condenser and problems with the Plant's air compressors. Corrective Maintenance was required on two of the PJ ant's air compressors at various times within the report period. Air Compmssor 1-2 has been out of service since November 19, 1982. The plant is also experiencing problems with the operation of the air dryers causing periodic low air pressure conditions during swapping of units.

A trip of the Fuel Pool Cooling Pump was exoerlenced due to low-low level in the Fuel Pool Surge Tank. Water from the Fuel Pool (approximately 8000 to 10,000 gallons) was transferred to the Condensate Storage Tank (CST), (there is only one path for the Fuel Pool water to get to the CST). The Plant could not simulate the conditions that caused the Fuel Pool level to decrease without operation of the air operated isolation valve in the line from the Fuel Pool to the CST. The isolation valve is operated from the 75' Elev. of the Reactor Building. Contractors working in this area were questioned on Operation of the valve; however, they stated they did not touch the valve operator switch. The Fuel Pool System was returned to service within the day and contractor work has been susperded in this area pending further evaluation e

by Operations Management.

At 1510 hours0.0175 days 0.419 hours 0.0025 weeks 5.74555e-4 months on November 20, 1982, a Reactor shutdown was commenced when the "A" 24 Volt DC System was lost during battery equalizing charge. Loss of "A" 24 Volt System caused a downscale failure of all Intemediate Range Monitors (IRM's) in System I and both Stack Gas Sample Systems. Subsequently, the DC output breaker on Charger "A2" was found tripped at 1525 hours0.0177 days 0.424 hours 0.00252 weeks 5.802625e-4 months . The breaker was reset and the shutdown terminated at 1535 hours0.0178 days 0.426 hours 0.00254 weeks 5.840675e-4 months . Load was increased from 300 MWe to 313 MWe. The ensuing investigation revealed that the DC over voltage breaker trip setpoint was too low. The overload trip setpoint was re set.

Reactor Recirculation Pump "A" was removed from service on November 24, 1982 due to a defective pump seal. Plant load was initially reduced from 306 MWe to 280 MWe for removal of the pump from service. Load was increased from 280 MWe to 300 MWe over a ten hour period after securing the pump. As a result of this event the Drywell Unidentified Leak Rate has exhibited an increasing trend.

8301270276 821215 PDR ADOCK 05000219 R PDR

i~ The following maintenance activities were' performed during' the report period:

1. The impellers on Emergency Service . Water Pump '. 52C and 52D were- .

adjusted.

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2. Replaced the brushes on "A" Reactor Recirculation Pump MG Set.

3. Repaired Stack Gas Sample Pump "B".

4. Condensate Transfer Pump No. 2 was repaired and returned to service.

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The following events were identified as potential Reportable Occurrences:

On November 5, 1982, the Primary Containment Isolation ball valve 'for TIP Machine No. 3 failed to close.

On November 15, 1982, "B" Stack' Gas Sample Pump tripped causing an interruption in the Stack Cas Sample Monitoring System.

On November 16, 1982, Dilution Pump No. 3 tripped thus leaving the Plant operating without the minimum number of dilution pumps required by the Technical Specifications for a period of 21 minutes.

On November 18, 1982, the Backseating Terminal Board for Isolation Condenser Valve V-14-37 failed, causing inoperability of the valve.

On November 20, 1982, both Stack Gas Sample Systems were lost due to the DC output breaker on 24 Volt DC Charger "A-2" tripping.

On November 22, 1982, Dilution Pump No. 3 was removed from service with intake temperature less than 600 F to repair a ground in the vacuum breaker limit switch, thus leaving only one (1) pump running.

On November 28,1982, V-1-106 and V-1-110 did not fully close during the MSIV -

Closure Test.

On November 30, 1982, Dilution Pump No. 2 was removed from service with intake temperature I?ss than 600F to clean clogged trash grates, thus leaving only one pump running..

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50-219 UNIf SilUIDOWNS AND POWER REDUC 110NS DOCKETNO.

UNIT NMIE Oyster Creek DA IE 12-1-82 COMPLETED 3Y R. Baran REPOR T MONilUovembe r 1982 IELEPif0NE 971-4640

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$5 5 jd Repo t x iEU Pievent Recurrence Q

28 11-28-82 S 0 H 4 NA ZZ ZZZZZZ Power Reduction of 80 MWe for a period of 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to per-form the Main Steam Isolation Valve Closure Test.

i I '2 3 . 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparallon of Data B Maintenance or Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Event ReporI(:.ER) File (NUREG.

D Regulatory Restriction 4-Other (Explain) 0161)

E4perator Training & Ucense Exandnation F-Administrative 5 .

G4perational Enor (Explain) Exhibit I-Same Source 19/77) I14:her(Explain)

AVERAGE DAILY POWER LEVEL ,

Net MWe

.I Docket # . . . . .50219 Unit . . . . . . .O.C. #1-

. Report'Date. . . . December 6, 1982 Compiled by. . . . Robert J. Frick .!

Telephone. . . . .609-971-4637 4

f Month: November, 1982 Day MW Day MW 1 309 16 291 2 307 17 290 3 303 18 290 i

4 300 19 290 5 300 20 284 6 301 21 285 7 300 22 283 8 299 23 281 9 296 24 268

10 297 25 276

11 297 26 274 12 295 27 271

" J { 13 , 292 28 265 i

'14 293 29 270 15~ 292 30 268 4

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1 1 PACE- 2 .

20. UT SFXVICE FACTOR 106.0 62.I 72.3

21. UT AVI.IL FACTOR 100.0 62.1 72.3

22. UT CAP FAGott (MDC NET) 46.6 37.8 62.7

23. UT CAP FACTOR (DER NET) 44.4 36.0 59.8

24. UT Foa.CED OUTAGE RATE 0.0 37.9 9.6

25. FORCED OUTAGE Ill1S 0.0 3641.5 8674.1

26. SIIUTDOWNS SCIIED OVER NEXT 6 MONTHS (TYPE.DATE. DURATION):

REFUELINC AND MAINTENANCE. 1/15/83 I1 M0! mis

27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME

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Page 1 cf 1 November

SUMMARY

CF QASL El'ctrical MAINTENANCE -

EQUIPMENT MALFUNCTION CORRECTIVE ACTION -

DG #1 Output Breaker Control

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Tripped at 600 KW, Set Point is 500 Reset to 480 KW 50 KW 1-2 Condensate Transfer Pump Noisy contactor Cleaned contactor Fira Detection System, Diesel Found bad 2N-31 module. Replacer" same.

Spurious yellow trouble alarms Gen ratoc Fuel Storage Area

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Alarm malfunction Replaced one thermal detector R

R actor Building, SE, airlock Electromagnetic control plunger sticks Cleaned plunger (outside door) g rm M ster h Will not return to neutral Replaced spring in control switch CRD Room Airlock Switchbox Loose bolts Replaced bolts and tightened act Bu ing NW Airlock Electromagnetic control plunger sticks Cleaned plunger i

Cleaned all potentiometers and satisfactorily Di:sel Generator #2 Oscillating ! 175 KW at full load performed surveillance.

Building Airlock, 51' Repaired loose wire on interlock switch Not working

Page 1 cf 1

November

SUMMARY

OF QASL I6;trument- MAINTENANCE .

EQUIPMENT MALFUNCTION CORRECTIVE ACTION .

Cor Spray Sys II High Pressure No repeatability Replaced switch with engineering approved replace-Altra Switch ment. Tested satisfactorily.

Reactor Feedwater Flow Recor- Calibration requested - not tracking Replaced wiper and support assembly, calibrated dar properly and tested satisfactorily.

"C" Reactor Feed Pump Low Switch leaking Replaced switch with engineering approved Pr:ssure Suction Switch replacement. Tested satisfactorily.

Traversing In-Core #3 Shield Adjustment required Adjusted / cleaned and tightened loose fitting.

Switch Verified proper operation after maintenance.

Augmented Off-Gas Building "A" Inoperative Replaced signal conditioning card, calibrated R: combiner Temperature Moni- and tested satisfactorily, tor.

Main Steam Line Radiation Front panel discrepancy Replaced Cl 50 MF capacitor in recorder power Ricorder #3 supply. Calibrated and tested satisfactorily.

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Dyster Creek Station Docket No. 50-219 REFUELING INFORMATION -

4 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: January 15, 1983 Scheduled date for restart following refueling: late - 1983 Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?

I Technical Specification Change Request No. 96 was submitted on August 31, 1982 for incorporation of CE fuel assemblies into the Cycle 10 core.

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

June 1,1983 - The final supplement to the reload analysis, delineating the specific core configuration for Cycle 10 operation, will be submitted.

Important licensing considerations associated with refueling, e.g., new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

1. General Electric fuel assemblies - fuel design and performance analysis methods have been approved by the NRC. New operating procedures, if necessary, will be submitted at a 3ater date.

2. Exxon Fuel Assemblies - No major changes have been made nor are there any anticipated.

The number of fuel assemblies (a) in the core -

560 (b) in the spent fuel storage pool - .781 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:

Present: 1,800 Planned: 2,600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

The Spring 1987' Outage.*

NOTE: This is for a normal refueling. Full core of f-load, however, can only be accommodated through about 1983 or 1984 with 1800 licensed locations.

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ML20070R081

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SUMMARY

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