ML19282C154

Monthly Operating Rept for Feb 1979

ML19282C154
Person / Time
Site:	Oyster Creek
Issue date:	03/12/1979
From:	Mcclain C JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19282C152	List: ML19282C151 ML19282C154
References
NUDOCS 7903210102
Download: ML19282C154 (8)

Text

". .

AVERAGE DAILY POWER LEVEL DOCKET ?...... 50-219

' UNIT.......... O. C. ?1 REPORT DATE... March 12, 1979 COMPILED BY... C.M. MCCLAIN TELEPHONE..... 201-455-8748 MONTH February 1979 DAY MW DAY MW

1. 649. 17. 649.

2. 649. 18. 649.

3. 649. 19. 647.

4. 649. 20. 648.

5. 648. 21. 648.

6. 299. 22. 649.

7. 328. - 2 3 ., 640.

O. 629, 24. 649.

9 604. 25, 649.

10. 647. 26. 649.

ii, 640, 27 649.

12. 649. 20. 649.

13. 642.

14. 531.

15. 650.

16. 647.

7903210102_

OPERATING DATA REPORT OPERATING STATUS UNIT NAME.. 0YSTER CREEK DOCKET NUMBER.. 50-219 UTILITY DATA PREPARED BY...C.M. MCCLAIN 201-455-8748 REPORTING PERIOD... February 1979 LICENSED THERtiAL POWER (MWT)...i930 NAMEPLATE RATING (GROSS MWE).. 650 DESIGN ELECTRICAL RATING (NET MWE).. 650 MAXIMUM DEPENDADLE CAPACITY (GROSS MWE).. 650 MAXIhUN DEPENDABLE CAPACITY (NET MWE).. 620 IF CHANGES OCCUR IN CAPACITY RATING SINCE LAST REPORT, GIVE REASON...

NONE POWER LEVEL TO WHICH RESTRICTED, IF ANY< NET MUE)... NO RESTRICTION REASON FOR RESTRICTION, IF ANY...

NO RESTRICTION MONTH YEAR CUnULATIVE HOURT IN PERIOD 672.0 1 4 1 6 ., 0 80520.0 HOUR ' FW CRITICAL 660.7 1330.0 6235i.9 R RE!ERVE SHUTDOMN HRS. 0.0 0.0 168.2 HR . GEN ON LINE 655,5 ,6i3.4 61094 ~7 UT RESERVE SHUTDOUN HRS 0.6 00 0.0 GROSS T HERMAL Et!ERGY 1238169.0 2478875.5 102514870.5 GROSS ELEC ENERGY 431000.0 860390.0 35000395.0 NET ELEC ENERGY 4163(?1.0 8291Si.0 3374694i.0 UT SERVICE F' ACTOR 97.5 (?2.8 75.9 UT AVAILADILITY FACTOR (77.5 92.0 '75.9 UT CAPACITY FACTOR tiDC 99.9 o4.4 69.5 UT CAPACITY FACTOR DER 95.3 90.1 64.5 FORCED OUTAGE FACTOR 2.5 7.2 5.4 NO OUTAGE IS SCHEDULED OVER THE NEYT l' I X MONTHS

'

DOCK ET NO.

50-219 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Oyster Creek #1 DATE Mar'ch 12, 1979 -

COMPLETED BY C. H. McClain REPORT MONTII February 1979 TELEPl!ONE 201-455-8748 9.

No . Dat e g

.5E 3g 3

@ jg5 E Licensee Esent 5-r,

g h

o- 3 Cause & Corrective Action to H

$E 5 j@g Report : NU h' Prevent Recurrence 6

2 790206 F 16.5 G 3 NA CH RELAYX "C" feedwater pump tripped when the breaker cubicle door was closed, shaking the "C" di f ferential relay.

The scram occurred from a low water level after the pump trip.

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

E-Operator Training & License Exannnation F Administralise 5 G-Operational I.i ror ( E xplain ) Exhibit I- Same Source 19/77) Il-Ot he r ( E xplain)

Oyster Creek Station #1 -

Docket No. 50-219 OPERATIONS Sl WARY - FEBRUARY 1979 The unit was operating at full load at the beginning of this report period.

On February 6,1979, "C" feedwater pump tripped when the breaker cubicle door was closed, shaking the "C" differential relay. A reactor scram occurred at 11:15 a.m. frcm low water level following the feedwater pump trip. All systems functioned normally. The unit was returned to service at 3:41 a.m. on February 7.

On February 9, poaer level was reduced frca rated load to approximately 35% when condenser vacuum rapidly decreased. Steam jet air ejector 1C1 was shutdown and IC2 was started. Ioad was increased to rated.

On February 13, power was reduced to approximately 65% to insert control rod 34-39 and replace a leaking scram pilot solenoid valve. Power was increased to rated following withdrawal of rod 34-39.

Two (2) reportable occurrences were identified during the tronth:

RO 79-2 occurred on Febnary 6 when one (1) reactor high pressure switch for isolation condenser initiation tripped above the allowable setpoint during routine surveillaire testing.

RO 79-3 occurred on Febnary 26, 1979 when the drywell to torus differential pressure dropped below the technical specification limit for 10 minutes during a reactor building closed cooling water tenperature transient.

Oyster Creek Station #1 Docket No. 50-219 ,,

CORIiECTIVE INSTRUIEETF MAltIIDIANCE ON OASL ITEMS FOR THE MotTI11 OF FEBICARY 1979 Item # Equipnent Malfunction Corrective Action 1 APal Ch. 6 Upscale spiking causing half- Bypassed 12-41B in APIN scrams drawer and aux, drawer 2 CRD 34-39 Scram solenoid air leak Rebuilt scram pilot valves with new parts and tested 3 APM1 Ch. 4 Rod block from faulty diode Replaced diode and conducted APIN surveillance test & cal.

4 SIN Front Panel ICR meter out of spec Mjusted trip module and zeroed DC amp for 10-1 on zero position 5 'D' Recirc Pump AP trans Icaking water at RK03 Tlghtened pacidng on root val 6 Core Spray Sys I Alarms did not flash Peplaced "B" acknowledge butt 7 AIX)G Front Panel Potential faulty indications Mjusted zero and set alann on recorder and checked recirc. valves

Oyster Creek Station #1 '

Docket No. 50-219 ,

ODRRDCTIVE ILDCTRICAL PAINTENANCE ON GASL ITENS 10R TIIE BOtml OF FEBRUATE 1979 Itan # Equipnent' Malfunction Corrective Action 1 Service Water Pump #1 Breaker trip unable to reclose Changed undervoltage coil and perfo. M PM on breaker l

e

Oyster Creek Statation #1 .

Docket No. 50-219 CORRECTIVE MECIIRJICAL MM!7IEWJCE CN OASL ITD1S EUR TIE FOTIll OF FEBRUARY 1979 . .

Itan # Equipment Malfunction Cbrrective Action 1 CRD 46-27 IICU Nipple on fill connection Ramved connector & retapped leaking around threads 2 Core Spray System V-20-41 leaking Mjusted packing to stop leakage 3 Condensate Transfer V-ll-41 leaking Tightened bonnet bolts as necessary Isolation to Isol. Cond. , to stop leak 4 Fire Protection System Packing leak on the pond pump Repacked the pump as necessary at the fire pump house to stop leak 5 CRD accumulator 14-11 V-lll valva nulfunction Replaced valve bonnet with a rebuilt spare 6 1-1 RDCCW Pump Leak from inboard seal Replaced seals

Oyster Creek Station #I Docket No. 50-219 REFUELING INFORMATION-- FEBRUARY 1979 Name of facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: September 15, 1979 Scheduled date for restart following refueling: November 10, 1979 Vill refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

No Technical Specification change relative to the refueling is anticipated.

Scheduled date(s) for submitting proposed licensing action and supporting In fo rmat ion :

1. July 1979 - Cycle independent General Electric fuel design information and safety analysis for future use.

2. No submittal is scheduled for the use of Exxon fuel.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unrevi~ewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

1. General Electric Fuel Assemblies - Fuel design and performance analysit methods have been approved by NRC. New operating procedures, if necessary, will be subnitted 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 - 620 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:

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

The Fall 1986 Outage.