ML20065C622

Monthly Operating Rept for Jul 1982

ML20065C622
Person / Time
Site:	Oyster Creek
Issue date:	08/02/1982
From:	Baran R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20065C621	List: ML20065C618 ML20065C622
References
NUDOCS 8209240255
Download: ML20065C622 (9)

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M0tmILY OPEPATIONS SlFNARY JULY 1982 At the beginning of the report period, the Oyster Creek Nuclear Generating Station was operating at 502 We with power limited by core reactivity.

On July 7 and again on July 8, a Reactor shutdown was ommenced due to a loss of the Stack Gas Sartple Systs. Each shutdown was terminated, within minutes, upon restoration of the Stack Gas Sartple Systen. The loss of the systan was attributed to the pmp notor tripping on themal overload. Consequently, a higher rated thermal overload was installed.

On July 9 and July 27, load was tmporarily reduced approximately 25 se for brush replacment on "C" and "E" Reactor Recirculation Pmp FC Sets (respectively) .

Contalment Spray Systen II was unavailable for use for a two (2) day period because of a problan in the auto start feature which was due to faulty tine delay relays. In addition, the backup position indicator (thermocouple) on Safety Valve NR28J was declared inoperable.

-l l At the end of the report period, the Station was operating at approximately 437 m e.

i B209240255 820016 PDR ADOCK 05000219 R PDR

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% e following events were identified as potential Reportable Occurrences:

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On July 1,1982, during the perfonnance of the Wernoccuple Valve Mcnitoring Systen monthly channel check, it was determined that secondary lift nonitor for Safety Valve NR28J was inoperable.

On July 7,1982, the input cable for the primary lift monitor (acoustical l monitor) frcm Reactor Safety Valve NR28D was found disconnected.

On July 7 and July 8,1982, the Stack Gas Sapple Punp tripped due to i

thermal overload.

On July 16, 1982, during nonnal routine surveillance testing, it was l discovered that Contairrnent Spray System II would not auto start due to failure of Time Delay Relay 16K14B (Containment Spray Ptrnp "51C") .

On July 17, 1982, it was discovered that Contairunent spray Systen II would not auto start due to failure of Time Delay Relay 16KilB (Emergscy l Service Water Punp 52C) .

On July 19, 1982, a procedural error was identified which renoved the l capability to autanatically isolate an Isolation condenser during a

surveillance test.

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AVEPAGE DAILY POhTR IEVEL NET MWe Docket # . . . . . 50-219 Unit . . . . . . . . O. C. #1 Report Date . . . . . August 10, 1982 O mpiled by . . . . . J. B. Sklar Telephone . . . . . (609) 971-4613 F O Irli July 1982 DAY FM DAY FM 1 476 17 429 2 474 18 424 3 472 19 424 4 471 20 423 5 466 , 21 424 6 461 22 425 7 457 23 424 8 454 24 422 9 454 25 421 10 441 26 413 11 442 27 412 12 441 28 409 13 440 29 410 14 440 30 411 15 435 31 409 16 431

OPERATING DATA REPORT OPERATING STATUS UNIT NAME .. 0YSTER CREEK DOCKET NUMBER . . 50-219 UTILITY DATA PREPARED BY . . . J. B. SKL AR (609) 971-6013 REPORTING PERIOD . . . JULY 1982 LICENSED THERMAL POWER (MWT) . . 1930 NAMEPLATE RATING (GROSS MWE) ... 650 DESIGN ELECTRICAL RATING (NET MWE) .. 650 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) .. 650 MAXIMUM DEPENDABLE CAPACITY (NET MWE) . . 620 IF CHANGES OCCUR IN CAPACITY RATING SINCE LAST REPORT, GIVE REASON ... NONE POWER L" VEL TO WHICH RESTRICTED, IF ANY (NET MWE) .. 400 REASON FOR RESTRICTION, IF ANY . . . FUEL DEPLETION MONTH YEAR CUMULATIVE HOURS IN PERIOD 744.0 5087.0 110495 0 HOURS RX CRITICAL 744 0 2487 2 80463.6 RX RESERVE SHUTDOWN HRS. 0.0 0.0 468.2 HRS. GEN ON LINE 744 0 2399 1 78609 1 UT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 GROSS THERMAL ENERGY 1074000.0 3342100.0 131933130 5 GROSS ELEC ENERGY 340570.0 1065870.0 44751845.0 NET ELEC ENERGY 324830.0 1015800.0 43083238.0 UT SERVICE FACTOR 100.0 47.2 71.1 UT AVAILABILITY FACTOR 100.0 47.2 71.1 UT CAPACITY FACTOR MDC 70 4 32.2 64.1 UT CAPACITY FACTOR DER 67.2 30.7 60.0 FORCED OUTAGE FACTOR 0.0 52.8 11 5 THE NEXT SCHEDULED OUTAGE IS TO BEGIN ON JANUARY 15, 1983

DOCKET NO. 50-219 UNIT SilVTDOWNS AND POWER REDUC 110NS UNIT NAME Oyst or (' rock DATE m'M COMPLETED BY R. Enrnn REPORT MON Til July 1982 971-4640 TELErilONE m

-, .$? "g ,Y Licensee $%

• o Cause & Corrective No. Date g g  ;; jg& Event g,g Action to

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~ Report # mO nb" Psevent Recurrence c$ E Q

25 6/4/82 F 38 H 3 NA ZZ ZZZZZZ Turbine trip greater than 40%

power. Turbine trip caused by high Reactor water level when feedwater pumps went to runout while filling the Reactor Cleanup System.

There 5 ere rio unit shutdc wns or reportable po eer reductions c uring t'le mor th of July.

I 2 3 4 F: Forced Reason: Method: Exhibit G. Instauctions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets foe 1icensee C Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4 Other (Explain) 0161)

, E Operator Training & License Examination F Administrative 5 -

G-Operational Error (Explain) Exhibit I-Same Source (9/77) Il-Other (Explain)

Julv

SUMMARY

OF QASL Mechanical MAIN'lHWE '

DNIPSD4T  %\LPLNCTIO4 QRRECTIW ICTIOJ Fire Protection Valves Packing leaks Adjusted packing.

V-9-299 and V-9-301 -

1-2 Condensate Transfer Broken nipple on discharge line Welded new nipple in line.

Pump CRD System Valves Leaking through Installed new ball and cage in Valves NC-30 A and B NC-30 A and NC-30 B Condensate Transfer Valve Leaking through Installed new stem, bushing, and V-ll-17 Make-Up to Fuel Pool diaphram in valve.

Old Radwaste Temporary Plugged Installed new filters Demineralizer Post Filters 1-2 Condensate Transfer Pump bearing worn Rebuilt pump Pump

July m "W/ T ' PN , In s t rume n t IM D.'Il NCis EQUIRSTP {pTRONTj CDRRICIVE TCPION Drywell Humidity Recorder Printing pens jammed Repaired printing pens and checked for proper operation Shutdown cooling room Erroneous temperature reading Replaced resis tance temperature temperature indicator detector and checked for satisfactory (lB06-H) operation Reactor Building Area Spiking, causing spurious alarms Replaced detector and satis f actorily Radiation Monitor (C7) performed calibration procedure.

Returned to service.

Stack Gas Monitoring Sys tem Built-in check source inopera- Replaced blown fuse. Tested satis-tive f ac torily.

Fuel Pool Flow Controller Flow controller inoperable Repaired defective slide wire.

Calibrated and returned to service.

Traversing In-core Probe No "re ady 'ligh ts Replaced lamps - tested satisfactorily Control Units 1, 2, 4 Intermediate Range Monitor Failed front panel surveillance Repaired cold solder joint on am-No. 16 test plifier module - front panel surveillance tested satis f actorily.

Containment Spray Sys tem II Pumps f ailed to start during Replaced defective relay in auto start auto start surveillance test logic and t. performed satis factory surveill ance_tes Emergency Service Water Pump Relay premature ; time out of Replaced time delay section of (52C) Logic Control Relay synchronization. associated relay and performed satis-(actory surveillance tes t.

July' SUFtMRY OF OASL Electrical RUNE;/WCE , '

EQUIPFENT WJEUNCPION _CDMurf1VE ICPIC11 Stack Tritium Sampler Defective furnace Installed new furnace. Tested satis-factorily.

Reactor Protection System Fuse 2F16 Open Fuse internal link pulled out of soldered connection. Fuse failure, noc component failure.

Augmented Of f Gas System #2 water removal train blown Found shorted strip heater. Replaced fuse heater and returned to service.

Augmented Off Gas System # 3 water removal train blown Found grounded crank case heater.

fuse Replaced heater and returned to service.

DC Invertastat for Public DC feed breaker found tripped Breaker tested satisfactorily. Re-Address System installed breaker and returned to service Reactor Building Air Lock Faulty door interlock switch Replaced inside door switch. Door Door to CRD Room operating satisfactorily.

Reactor Building Northwest Door interlock fails inter- Adjusted air lock solenoids. Dcors Air Lock Door mitten tly working satisfactorily.

Drywell Oxygen Sample Valve Valve would not open in auto- Relay 6K37 not working. Replaced V-3 8- 10 matic relay. Valve working satisf actorily.

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

Name of Facility: Oyster Crock 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 thereafter require a Technical Specification change or other license amendment?

A Tech Spec Change Request to incorporate G.E. fuel assemblies will be submitted by September 1, 1982 Scheduled date(s) for submitting proposed licensing action and supporting information:

March 9, 1981 - Complete NEDO document #24195 (G.E. Reload Fuel Application for Oyster Creek) was submitted.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or per-formance analysis methods, significant changes in fuel design, new operating procedures:

1. General Electric fuel assemblies - fuel design and perfor-mance analysis methods have been approved by the NRC. New operating procedures, if necessary, will be submitted at a later 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.*

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

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