ML20027D481
| ML20027D481 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/14/1981 |
| From: | Sklar J JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20027D478 | List: |
| References | |
| NUDOCS 8211040352 | |
| Download: ML20027D481 (11) | |
Text
bmIHLY OPERATIONS SG1MRY NOVEMBER 1981 At the beginning of the reporting period, the Oyster Creek Nuclear Generating Station was shut down to correct Second Stage Reheater Manway Steam leaks and perform maintenance on Electrunatic Relief Valve (D4RV) Acoustic Manitors.
The maintenance was empleted and a reactor startup was performed on Novmber 1 with the subsequent turbine loading, Nov m ber 2.
However, due to the unavailability of #2 Traversing Incore Probe (TIP #2), power was limited to 652 FMe. The malfunctioning TIP was partially repaired and on Novmber 11 full power was achieved. Malfunctions in the Acoustic Valve Monitoring Systs for D4RV position indication on Novmber 17 caused a power reduction On November 19, a half scram was experienced due to a failed to 653 MWe.
power supply in #2 Average Power Range Monitor (APRM). The instrument was A tmporary load reduction to 400 MWe was performed on Novmber repaired.
21 in order to facilitate maintenance on A and B Condensate Pump Oil Coolers.
Upon completion the plant load was increased to that level' limited by the EMRV amustic nonitoring probim, approximately 650 FWe.
Extensive trouble-shooting and calibration was cmpleted on the Safety and Relief Valve bbnitoring Systcm. There are two defective nonitoring channels associated with "F" and "N" safety valves. I&C is working with Plant Engineering and will further investigate during the next plant shutdown as drywell access is rcquired. An mergency Tech Spec change rcquest was approved by the NRC to allow operation with degraded monitoring on the safety valves.
~
j The following events were identified as potential Reportable Ocettrences during Novmber:
On Novmber 16 the setpoint for Isolation Condenser Linebreak Sensor switches IBilAl and IBllA2 were found to have settings less mnserva-tive than Technical Specification requirments.
l On Novmber 11 switches IP15 B & D for the Containment Spray Systs were found to have settings less conservative than Technical Speci-fications requirments.
On Novmber 19 the III-F fuel on the core periphery was not ronitored.
On Novmber 21 the MAPIRGR was 103% of limit.
1 On Novmber 24 and 27 snubbers failed functional testing.
On Novmber 25 High Drywell Pressure sensing switch RV-46C was found to have a setting less conservative than Technical Specification requirments.
On Novmber 19 V-17-30 in the Isolation Condenser Systm would not close on a signal frm the control Rom.
8211040352 821215 PDR ADOCK 05000219 PDR R
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UPLia. i s k-m...i i,E i liki OPERATING STATUS UNIT NAME... OYSTER CREEK DUCKET NUMBER.. 50-219 UTILITY DATA PREPARED DY...J.B.
SKLAR 609-693-6013 REPORTING PERIOD... November 1981 LICENSED THERMAL POWER (MUT).. 1930 NAHEPLATE RATING (GROSS MWE).. 650 DESIGN ELECTRICAL RATING (NET MWE).. 650 MAXIMUM DEPENDADLE CAPACITY (GROSS MWE).,. 650 MAXIMUM DEPENDADLE CAPACITY (NET MWE).. 620 IF CHANGES OCCUR IN CAPACITY RATING SINCE LAST REPORT. GIVE REASON...
NONE PUWER LEVEL TO WilICH RESTRICTED, IF ANY(NET MWE)...
650
+
REASON FOR RESTRICTION, IF ANY...
ACOUSTIC MONITOR POSITION INDICATION (10 NTH YEAR CUMULATIVE ilOURS IN PERIOD 720.0 0015.0 104663.0 HOURS RX CRITICAL 697.8 5332.0 77762.6 RX RESERVE SHUTDOWN HRS.
0.0 0.0 468.2 HRS. GEN UN LINE 604.5 5027.7 75996.7 IIT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 UROSS TilERMAL ENERGY 1254000.0 8056250.0 120202730.5 GROSS ELEC ENERGY 432950.0 2622460.A 43550705.0 NLf ELEC ENERGY 416050.0 2501830.0 41940488.0 U f SERVICE FACTOR 95.i 62.7 72.6 UI AVAILABILITY FACTOR 95.1 62.7 72.6 UT CAPACITY FACTOR MDC 93.4 50.3 i
66.0 UT CAPACITY FACTOR DER 89.1 48.0 61.6 FORCED OUTAGE FACTOR 4.9 20.3 '
8.5 Tile NEXT SCHEDULED OUTAGE IS TO BEGIN ON APRIL 16, 1982
AVERAGE DAILY POWER LEVEL DOCKET ?......
50-219 UNIT..........
P C.
Ci aanber 14. 1981 REPORT DATE...
am COMPILED BY... J.B. SKLAR TELEPHONE..... 609-693-6013 MON TH Novevaber 1981 DAY MW DAY NW i.
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50-219 DOCKET NO.
UNITSilUTDOWNS AND POWER REDUC 110NS UNIT NAME Oyster Creek DATE December 10, 1981 November 1981 COMPLETED BY J.
B.
Sk1ar REPORT MONill TELErilONE 609-693-6013 B
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[ r, Cause & Corrective No.
Date g
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21 10-30-81 F
35:26 B
1 N/A ZZ ZZZZZ Shutdown to correct steam leaks from the Second S tage Reheater Manway
/
I 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failuse(Explain) 1:blaqual for Preparation of Data ll-Maintenance of Test 2-MarTual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4 Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
Goperational Error (Explain)
Exhibit I.Same Source (9/77) 11-Other (Explain)
NOVEMBER SUMRY OF QASL MEDIANICE ST,INM4CE gp,eq 57-&m4CTION CDRRELTIVE ICTIN CRD Accunulator 42-11 106 Valve Packing Icak Adjusted Packing CRD Accumulator 38-43 107 Valve Stem is Bad Installed New Stem 1-2 S.W. PuTp Running Noisy Disassembled and inspected punp Found no Inajor problem, reassembled V-lll CRD Nitrogen Irak Installed Rebuilt V-lll Valve V-17-56 Packing leak Adjusted Packing Snubber Cont. Spray 51' elevaticn Ieaking Oil Ibplaced Snubber with a new one Reactor Building Ibfteling Bridge Iloist 119' Air IIose Ieak m Iloist Repaired IIose Icak Elevation Ibactor Building V-20-21 Packing Icak Adjusted Packing
/
RB001 SDC Valves on A&B IIcat Icak 'Ihrough
- +
Adjusted Valve Operators Exchanger's Disc.
j 10G - 006B Valve Icaking By Disassembled valve and inspected Found dirt on seat (flushed out and cleaned).
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IM EMBER SUNI@.RY OF QASL ELECTRICAL :'AINTEMCE HJJIPMEITT
!",IMNCTION CDRRECTIVE iTTICN IEactor Manual Scram Buttcn Switch Sticking in TRIP position Pdmoved switch collar and inspected switch.
Switch operated freely during subsequent testing.
CRD Acctmulator #14-07 Repair seal-tite which separated Reconnected seal-tite to connector frun flexible fitting Demin water and ccmchnsate Invel transmitter freezing Installed heaters to prevent level transmitter storage tank-level indication on demin water and condensate storage tank transmitter fran freezing.
Valve V-5-106 Remote indicator Ibmote valve indicator en V-5-106 Refasten renote valve indicator cm panel 1F/2F on shutdown heat exchanger in in control room falling out of panel in ocntrol room ocntrol room Clean-up system - filter by-pass Double indicaticn on valve V-16-83 Adjusted limit switch on valve V-16-83 for valve V-16-83 proper indication Aucynented Off Gas Building Befasten ccnduit to Beactor Building Re-suoported conduit with five inch Ililti bolts Cbnduit on Ibactor Building wall wall conduit, fasteners failed.
and torqued to 35 foot pounds Manual Ibd Control - Notch over-Switch is over-travelling Ibolaced stop plate. Switch working properly now.
ride switch a
Clean-up Systan, Valve V-16-14 Control Switch llandle will not spring Switch shaft rtbbing on cover plate. Mjusted return to normal switch and place back in service Cbntainnent Spray System II lost indication of valve positnog Mjusted primary stab at motor control center Valve V-21-3 to make better contact.
Reactor Building Southeast Air Interlock cn Ddor not working.
Cleaned interlock switch and door plunger. Place Iock Door into service.
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NCf1DBER SUMM OF OASL INSTIRENT raEW4CE DJJIP'ENT S M M CZION CDR?3CTIVE ACTICN Source Range Mmitor Surveillance Discrepancy Calibration Pequired and Qxnoleted 01annel No. 23 (Front Panel Test)
Internediate Range Monitors Surveillan Discrepancy Calibration Required and Completed (Front Panel Test)
Control Ibd No. 38-31 Select button does not latch in Ibinstalled 4K 38-31 Relay Retainer or light Drywell Humidity Pecorder Not Printing Replaced missing pens Air Ejector Off Gas Surveillan Discrepancy Ibcorchr Calibration Required and Ccxnpleted Radiation Monitor No.1 (Front Panel Test)
No. 2 Traversing In-Oore Probe Detector noch. damaged Replaced detector Source Range Mcnitor No. 23 Period noter on 4F defectim Ibplaced meter with calibrated spare Sluggish response Clean-up System, Iow Pressure " Alarm" mntinuously in Alarm Actuator (Switch) on Recorder defective replaced same Area Radiaticn htnitor No Power to Unit
+
Ibpaired multi-pin connector New Packraste Building i
Liquid Poiscn System Iocal pressure gauge has cracked Reolaced broken glass and performed housekeeping glass k
i i
NOVEMBER SGMW OF QASL INSTRUMENT E T UNCE B7JIPSENT SEM1NCTICN 001EX.TIVE ACTICN Iocal Power Range Itnitors LPIN's indicate downscale, however Calibration Required and Omnleted no downscale light on local panel Internediate Range Monitor Frayed section of input cable Renoved bad section of cable and installed extension, checked satisfactory.
Average Power Range No. 2 Power supply failed downscale Replaced power supply with calibrated spare Power Supply Intermediate Range Ftnitor No.16 Failed downscale Replaced connector m range switch cable 4
Drywell Air Tenperature Recorder Inoperative, broken drive cord Peplaced broken drive cord.
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Oyster Crack Station #1 Occket No. 50-219 REFUELING INFORMATION -
Name of Facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdown:
July 1, 1982 following refueling: mid-1983 Scheduled date for restart refueling or resumption of operation thereaf ter require a Technical Vill Specification change or other 1icensa amendment?
A 'Iuch Spec Change Request to incorporate G.E. fuel yeamblies Will be submitted by January 1, 1982.
for submitting proposed licensing action and supporting Scheduled date(s) in fo rmat ion:
March 9,1981 - Ccmplete NCD0 docunent #24195 (G.E. Beload Fuel Application for Oyster Creek) was submitted.
licensing considerations associated with refueling, e.g., new or fuel design or suppiier, unreviewed design or performance + analysis important methods, significant changes in fuel design, new operating procedur(ps:
.different General Electric fuel assenblies - fuel design & perfonnance analysis New opcrating pr W n e, if 1.
methods have been approved by the NIC.
ssary, will be submitted at a later date.
ne Exmn Fuel Assemblies - No major changes have been made nor are there 2.
any anticipated.
560 The number of fuel assemblies (a) in cna core (b) in the spent fuel storage pool. 781 1icensed spent fuel pool storage capacity and the size of any The present increase in licensed storage capacity that has been requested or is planned, in number of fuul assemblies:
i Present: 1,800 Planned: 2,600 i
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
l
'Ihe Spring 1987 Outage.*
'lhis is for a nonnal refueling. Full core off-load, however can only be
[
- N:7IE:
accomnxlited throuch. bout 1983 or 1984 with 1800 limnsed locations, i
I L