ML19344B538

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Monthly Operating Rept for Sept 1980
ML19344B538
Person / Time
Site: Oyster Creek
Issue date: 10/07/1980
From: Sklar J
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19344B531 List:
References
NUDOCS 8010210425
Download: ML19344B538 (8)


Text

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v OPERATICNS SGNARY Septmoer 1980 At the beginning~of the reporting period, the plant was operating at 504 MNe. On Septemoer 18 tne reactor was shut dcwn as a result of increasing drywell unidentified leak rate. 'Ihe leak rate was e anciad by a leaking drain line on a feedwater check valve. After empletion of minor maintenance the plant was restarted on September

23. 'Ihe generator was placed on line at 2011 on September 23. 'Ihroughout the rest of the reporting period the plant power level was raised to rated 1 cad ard operated at this level.

During the nonth, tw DmLn.gency Conditions occurred. Ch Septaber 8, a temporary Class I amLn.gency occurred when an air pt.ge valve in the distribution Pandar caused a chlorine leak. On September 29, a Class II Emergency occurred when a discharge hose frcm the Floor Drain Sample Tank Processing Unit in the truck bay of the Old Radwaste Anilaing ruptured. About 5 gallons of water ran under the roll-up door and across the loading dock to the grourd.

Five Reportable Occurrences and tw Non-Ibutine Envi-ental Operating Reports were identified during September.

RC# 80-40 occurrec on September 4 when a Hydraulic Shock and Sway failed functional testing.

rot 80-41 occurred on September 5 when Core Spray System II was renoved frcm service for corrective maintenance to repair a leak arourd a thraadad fitting.

R04 80-42 occurred on September 11 wran, during surveillance testing, Drywell High Pressure Switch IP15 for the Contairmant Spray System was found to have a setting less conservative than Technical Specification requmanents.

RO# 80-43 occurred on September 25 when, during surveillance testing, Reactor Triple Icw Sensor RE 18D was found to have a setting less conservative than W hni< 1 Specification requirements.

rot 80-44 occurred on Sept aber 30 when the h a.nt initiation of the fire protection system caused Core Spray System I to be considered inoperable.

NRECR# 80-7 occurred on Septeber 1, 2, and '4 when~ Dilution Pumps 1-1 and 1-3 tripped and two reserve puxps could not be placed in service within the required fifteen minute period. In each instance, tPa temperature at the U.S. Route 9 bridge exceeded 87"F.

NRECR$ 80-8 occurred on Septecber 10,11,13,17 and 18 when il1 Dilutien Pump was taken out of service due to a damaged bearing and a backup pump could not be started as required haemm it was out of service for maintenance. In each case, the U.S. Peute 9 bridge temperature exceeded-87 F.

  1. 01021043E

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  • OPERATING DATA REPORT OPERATING STATUS UNIT NAME... OYSTER CREEK DOCKET NUMBER.. 50-219 UTILITY DATA. PREPARED BY...J.B.

SKLAR.

609-693-6013 REPORTING PERIOD... September 1980 LICENSED THERMAL POWER (MWT).. 1930 NAMEPLATE RATINC' GROSS MWE).. 650 DESIGN ELECTRICAL RATING (NET MWE).. 650 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE).. 650 MAXIMUN DEPENDABLE CAPACITY (NET MWE).. 620 IF CHANGES OCCUR IN CAPACIT.Y RATING SINCE LAST REPORT, GI'JE REASON...

NONE POWER LEVEL TO UHICH RESTRICTED, IF ANY(NET MWE)...

650 REASON FOR RESTRICTION, IF ANY...

CONDENSATE DEMINERALIZER DIFFERENTIAL PRESSURE

' MONTH YEAR CUMULATIVE HOURS IN PERIOD 720.0 6575.0 94439.0 HOURS RX CRITICAL 621.0 1733.4 70377.7 RX RESERVE SHUTDOWN HRS.

0.0 0.0 468.2 HRS. GEN ON LINE 604.0 1639.2 68944.7 UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERMAL ENERGY 1055690.0 2661620.9 116540730.2 GROSS ELEC ENERGY 333920.0 836630.0 39718945.0

. NET ELEC ENERGY 319951.0 794811.0 38275824.0 UT SERVICE FACTOR 83.9 24.9 73.0 UT AVAILABILITY FACTOR 33.9 24.9 T3.0 UT CAPACITY FACTOR-MDC 71.7 19.5 66.?

UT~ CAPACITY FACTOR DER 68.4 18.6 62,4-FORCED QUTAGE FACTOR 16.1 11.9 6.6 THE NEXT SCHEDULED OUTAGE IS TO BEGIN ON SPRING 1981

AVERAGE DAILY POWER LEVEL i

DOCKET 4......

50-219 UNIT..........

O. C.

41 REPORT DATE... October 7, 1980 COMPILED BY...

J.B.

SKLAR TELEPHO.NE..... 609-693-6013 MONTH September 1980-DAY MW-DAY MW i.

392.

17.

532.

2.

408.

18.

505.

-3.

.490.

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4 518.

20.

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504 21.

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510.

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464.

23.

38.

8.

515.

24.

433.

9.

544.

25.

592.

10.

573.

26. -

603.

- 11.

571.

27.

615.

12.

549.

28.

617.

13..

541.

29.

615.

14.

534.

30.

618.

15.

537.

16.

540.

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50-219 DOCKET NO.

UNITSilHTDOWNS AND POWER REDUC'I1ONS UNITNAME n r_ mi DATE MA~ 'ar1980 J. B. Skl COMPLETED BY REPORT MONI13 _ mnt- - 14R0 TELEril0NE 609-693-6013 l

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4 F: Fosced Reason:

Method:

Exhibit G.las sucilans S: Scheduled A Eigulpawns Failure (Emplain) 1 Manual fos Psepasation of Data 4,

B-Maintenance of Test 2 Manual Scrasn.

Entry $4wess for Licensee C Refueling 3 Aulomalle Scsani.

Event Repost (LER) File (NUREG.

D Regulatosy Restsictimi 4 Othes (Emplain) 0161)

E Opesatos Tsaining A (Jccusc Emendaallon F-Adndnistsative 5

G Opesallonal Essus (Emplain)

Exhibh 1 Same Sousee (9/77)

Il Othes (Emplain) i 1

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t CORRECPIVE MBCllANICAL MAINIDIANCE ON OASL IOJIPMENT Septaiber 1980 Systan Problan Corrective Action 1.

Fire Protection dystan Sprinkler valve leaks Ibplard valve 2.

Fire Protection Systan 00 Control Valve fitting leaks PZ. ace teflon tape on fitting 2

3.

Fire Protection Systen Sprinkler valve V-9-298 leaks Adjust packing on valve 4.

' Fire Protection Systan Rebuild fire main post indicating Replace internal cagx)nents of valve valves 5.

Dnergency condenser Sys.

Valve V-14-19 packing leak Packing to Valve 6.

Energency Condenser Sys.

Valve V-4-57 packing leak Replaced entire valve 7.

Core Spray Systan Nipple on 'D' core Replaced nipple on 'D' core spray ptmp spray ptmp vent leaking 8.

Energency Service Water Sys. Ptmp 52B has low discharge, Cleaned inside of ptop casing pressure and low anperage 9.

Recirculation Systen Nut missing frm

' unp Replaced the stud and added two nuts discharge riser el-10.

Reactor Feedwater Systan Valve V-2-10 packing leak Replaced packing a

9 CORRIEPIVE EllEIRICAL MMtilDWCE Of OASL IOUIPME2TP S12"IU4BER 1980

.g Ittm #

Equipnent '

Malfunction Corrective Action

'1 Floor Penetration -Ibc Bldg. TIP Not sealed Dow (brning foam applied to isolate areas Shield Area to Elev. 51' 2

Fim Diesel #2 - Battery Bank Failed battery test Bank "A" put on equalizing charge ~

3 MG Set #1 Output breaker trippx1 Gecked breaker protective functions, cause of trip not found 4

Liquid Poison - Squib Open Alarm Incorrect indication Changed neter relay 5

Turbine Stop Valve #3

.lialf-scram due to loss Retaired limit switch valve open indication 6

"B" Station Battery Ground indication Dried & cleaned limit switch at V-1-90, wet frun previous fire system actuation 7

"C" Station Battery Ground indication Dried & cleaned limit switch - wet frun steam leak frun valve V-14-19 O

CORRICPIVE ItBlMIMENP MAINIUMCE 01 OASL EQUIPMENP SEPIDEER 1980 j

4 Itun 8 B]ui[ ment Malfunction Corrective Action

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l Offgas Transmitter B Indication fallal downscale Tightened loose connection l

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2 CIO Tenperature Alarms Repetitive alarus Jtugered re[mtitive alarms 3

Instnmentation Rack RK01-Water leak Tightened fitting on RE05-19A 4

Turbine Instnnentation - Ioad Check pressure switch PSil-A R ylaced switch

.i Rejection Scram 5

1-7 Stmp level Switch Unreliable operation Installed new float level switch 6

Main Steam Line Radiation Monitors Variation between channels Readjusted

Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION -

Name of Facility:

Oyster Creek Station #1 Scheduled date for next refueling shutdown:

M " 30, 1981 Scheduled date for restart following refueling: March 31, 1980 Will refueling or resumption of operation thereafter require a Technical Specification" change or other license amendment?

No 'Dachn_4t-=1 Specification change relative to the refueling is anticipated.

Scheduled date(s) for submit:Ing proposed licensing action and supporting i

in fo rma ticn:

No subnittals are scheduled.

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

1.

General Electric Fuel Assemblies - Fuel design & performance analysis methods have been approved by the NBC. New operating procederes, if necessary, will be subnitted at a later date.

2.

Docn Fuel MW14es --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 scent fuel pcol storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in numeer of fuel assemblies:

1 l

Present: 1,800

. Planned:2,600 j

i The projected date of the last refueling that can be d scharged to the spent fuel pool assuming the present IIcensed capacity:

The Spring 1987 Outage i

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