ML20054H817

Monthly Operating Rept for May 1982

ML20054H817
Person / Time
Site:	Oyster Creek
Issue date:	06/10/1982
From:	Baran R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20054H816	List: ML20054H815 ML20054H817
References
NUDOCS 8206250014
Download: ML20054H817 (9)

Text

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o-Du y UNITS!!UIDOWNS AND POWER REDUCTIONS ETNO' E @50-219 ter N EO*

DATE 6/10/82 COMPLETED BY R. Baran

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• gg Cause & Corrective No. Date g 3g  ;; jg& Event g3 al Action to H

$5 5 ji 5 e Repori a mo gu Prevent Recurrence e g u O

24 5/23/82 1 112 B '

1 NA zz zzzz Ccmplete maintenance on second stage steam reheater marrey, t 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Scheduled A. Equipment Failure (Explain) 1-Manual for Prepasarion of Data B Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3-Automatic Scram. Event ReporI(LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F. Administrative 5 .

G4peratiu ..! Error (Explain) Exhibit I Same source 19/77) llother(Explain)

093 61 293 13 293 51 583 03 393 41 613 .

4" 783 31 6 82 493 21

.O 72 093 11 i

.O 62 493 01 I 6

.O 52 393 9 82- 42 293 8 I

'83 32 593 .7 283 22 593 4 383 12 893 5 873 02 593 4 l 183 . 91 104 3 {

i i 483 81 893 2 l I

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_j LEVEL REWOP YLIAD EGAREVA l' 4 1

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2, OPERATING DATA REPORT i

4 OPERATING STATUS l UNIT NAME,.. OYSTER CREEK I DOCKET NUMBER,. 50-219 4

U TILITY DATA PREPARED DY. . .J.B. SKLAR 609-693-6013 REPORTINO PERIOD... May. 1982 LICENSED THERMAL POWER (MWT) . .1930 NAMEPLATE RATING (GROSS MWE).. 650 DESIGN ELECTRICAL RATING (NET MWE).. 650 4

MAXIMUM DEPENDADLE CAPACITY (GROSS MWE).. 650 4

, MAXIMUM DEPENDABLE CAPACITY (NET MWE).. 620 I IF CHANGES' OCCUR IN CAPACITY RATING SINCE LAST-REPORT. GIVE REASON...

l NONE I

POWER LEVEL TO WHICH RESTRICTED. IFiANY(NET MWE)... 400

REASON-FOR-RESTRICTION, IF ANY...

CONDENSATE PUMP AVAILABILITY MONTH YEAR CUMULATIVE-HOURS IN PERIOD 744.0 3623.0 109031.0

> HOURS RX CRITICAL 659.2 1054.3 79030.6

RX RESERVE SHUTDOWN HRS. 0.0 0.0 468.2 HRS. GEN ON LINE 632.2 972.8 77182.0 i

, UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERMAL ENERGY 806800.0 1235100.0 12'?826130.5.

i GROSS ELEC ENERGY 253800.0 386260.0 44072235.0 NET ELEC-ENERGY 242210.0 366500.0 42433938.0 l-l UT SERVICE FACTOR 85.0 26.8 70.8 1

UT AVAILABILITY FACTOR 85.0 26.8 70.8 1

UT CAPACITY FACTOR MDC 52.5 16.3 64.0-i l UT' CAPACITY FACTOR DER 50.1 15.6 59.9-l FORCED OUTAGE FACTOR 15.0 73.2 i1.7 NO QUTAGE IS SCHEDULED-0VER THE NEXT SIX MONTHS L

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May styggt op QAsL Electrical E M NCE Page 1 of 2 EQUIPbENT MAIEUNCTICN COHKtLnG JCTICN Electromatic Relief Valves Valve open alarm continuously Alarm cleared af ter cleaning local "on" switch contacts.

Reactor Protection System Relay 1K21A would not pick up Satisfactorily replaced 1K21B relay .

(Failure of 1K21B coil) utilizing Relay Replacement Procedure )

732.2.006 Rotary Inverter Noisy operation Noise coming from flywheel lif ting holes.

Rotary inverter ran quiet af ter plugging l

holes. l t

l "C" Station Battery-Charger Door on charger would not close Repaired door so it would close correctly l C-1 l Reactor Protection System I Scram Reset Relay 1KTD2 would Replaced relay using Relay Replacement not pick-up Procedure 732.2.006. Relay tested satisfactorily.

l Augmented Off Gas Building Water Removal System #2, Repaired refrigeration unit Control Problems Fire Barrier in Cable Fire Barrier cracked Installed Fire Barrier between tray and Spreading Room conduit.  ;

1 1-1 Service Water Pump Oiler solenoid not working Removed and cleaned control valve and reservoir l

l Reactor Building Refueling Frame mounted auxiliary hoist Cleaned and inspected air solenoid l Crane air solenoid sticking valve. Operating satisfactorily. l Stand-By Gas Treatment Mounting bracket for P-16 ATC Anchored panel to wall.

System Panel loose l

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_a -' :o May SUM &W OF QASL Electrical NNCE: Page 2 of 2 EQUIPbE R MAIRECTICN CDm<EunVE JCTICN Drain Valve V-1-110 Motor Control Center Breaker Reshaped cable to prevent breaker from is rubbing power cable wearing power cable insulation.

"D" 4160V Bus Grid Under- Light socket not working Replaced light socket and relamped Voltage Light Socket Torus Valve V-26-3 Seal tite scorched Replaced seal tite. Wiring inside seal tite was checked satisf actory. Tested valve with Procedure 604.2.005.

Reactor Protection System Relay 6K37 auxiliary unit Performed relay replacement with binding Procedures 732.2.006 and 108.

May SUM 4ARY OF QASL Mechanical N NCE Page 1 of 1 EQUIPM2R MALFtNCTIOT (DRHEL'nVE N.TIOJ Reactor Building 75' ele- Various valve packing leaks Valve packing adjusted where required Vation Isolation Condenser Valves CRD Accumulator 30-07 V-107 valve hand wheel missing Installed new hand wheel CRD Accumulator 02-35 V-lll valve leaking through Installed rebuilt V-lll valve Reactor Building 2 3' ele- V-9-184 packing leak Packing adjusted Vation Fire Protection Sys tem 1-8 Sump Discharge Check Check valves not closing Foreign material was found inside valve.

Valves in Drywell properly Both valves cleaned and put back in service.

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May SQ.m OF (psL Ins trumen t MNNCE Page 1 of 2 EQUIP E 7r MAIJWCTION COHHtLnVE ILTICN Emergency Condenser Tempera- Switch failed Replaced Stepping Switch. Recorder ture Recorder operates satisfactorily.

Control Rod Position In- No numerical display dication Quadrant 4 Repaired cold solder joint on test jack

1. 4 at 6xR Panel. Indication restored.

Off-Gas Sys tem Low-flow alarm not operating Replaced alarm unit with operational.

properly spare. Tested satisfactorily.

Remote Reactor Water Level Lamp is burnt out Replaced lamp. Operates satisfactorily.

Indicator Source Range Monitor No. Upscale light burnt out Replaced lamp. Tes ted satisfactorily.

24 Thermocouple on Safety Valvc No output Repaired thermocouple and tested NR2 8A satisfactorily.

Thermocouple on Safety No output Replaced thermocouple and tested Valve NR28J satis factorily.

Control Rod Drive 18-47 Position switch "17" failed Replaced position probe and tested sa tis fac torily Emergency Service Water Defective oil level switch Repaired level switch and tested Pump 1-3 sa tis factorily.

Area Radiation Monitor for Detector failed upscale Replaced detector and calibrated same.

Containment Spray Heat Exchanger

Page 2 of 2 May SUbfRRY OF QASL Instrument mg EQUIPbENT MM11NCTIN 00HHtLnVE ICTICH Torus Temperature Recorder Recorder sluggish and requires Replaced balancing motor and calibrated calibration recorder. Operates satisfactorily.

"B" Main Steam Line Radia- Monitor failed downscale Replaced monitor with operational tion Monitor spare and tested satisfactorily.

"E" Recirc Pneumatic Speed Air failure. Indicator light Cleaned and adjusted switch for proper Control out operation. -

Solenoid Valve For Control Leaking air Replaced "0" ring and acorn nut. Scrainmed Rod Drive 34-39 rod and verified valve stroke.

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

Name of Facility: Oyster Creek Station il 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 assemblics 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.,

j 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 assemblics - 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 Assemblics - 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 off-load, however can only be accommodated through about 1983 or 1984 with 1800 licensed locations.

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