ML20053B813
| ML20053B813 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/12/1982 |
| From: | Sklar J GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20053B809 | List: |
| References | |
| NUDOCS 8206010252 | |
| Download: ML20053B813 (11) | |
Text
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MONTHLY OPERATIONS
SUMMARY
APRIL 1982 At the beginning of the reporting period, the Oyster Creek Nuclear Generating Station was shutdown with the reactor mode switch locked in the shutdown position to complete maintenance and testing required for startup.
The Primary Containmer.t (Drywell) Integrated Leak Rate Test (ILRT) and the Leak Rate Testing of MSIV NS03A and 4A was completed satisfactorily.
Due to securing the service air system to the Reactor Building for the Primary Containment ILRT, the Reactor Building Service Air System became contaminated. Ef forts were initiated to flush out hot spots in the Service Air System piping.
A reactor startup was commenced and criticality achieved at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on April 12.
Subsequently, the plant experienced the following delays in its ascension to power: a scram due to inadvertant closure of the MSIV; a flange leak on the.second stage reheater PRV valve; and a leak on "A" EMRV pilot l
valve. Repairs were completed and a reactor startsp was initiated with the generator being placed on the line at 1735 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.601675e-4 months <br />, April 15.
However, on April 16, due to a combination of inefficiencies with the nitrogen inerting system and 02 analyzer calibration problems, the inerting of the drywell was not completed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit required by Technical i
Specifications. A reactor shutdown was commenced until continued inerting reduced the 02 content in the drywell to within the limits, at which time the shutdown was terminated.
On April 17, a reactor scram occurred due to low vacuum.
The low vacuum was due to saturation of the of f gas absolute filter while filling the Augmented Of f-Cas ( A0G) flame arrestor.
Subsequently, a reactor startup was commenced.
Load was increased to 425 MWe and is limited to approximately 65%
due to "C" Condensate Pump being out of service.
On April 18, "A" CRD pump was removed from service for maintenance due to vibration and bearing problems.
The following events were identified as potential Reportable Occurrences:
On April 1, Main Steam Isolation Valves NS03A and NSO4A failed their leak rate test.
On April 14, three reactor high pressure Electromatic Relief Valve (EMRV) initiation switches actuated at a value greater than that specified in the station's Technical Specifications.
82060 1 0MA
4 On April 16, the primary containment atmosphere was not reduced to less than 5.0% oxygen concentration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter the reactor mode selector switch was placed in the RUN mode.
On April 16, a fuse in the closing circuit for Bank 6 startup transformer breaker SlB blew, thus preventing the breaker from automatically closing.
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On April 18, "A" CRD pump was taken out of service due to vibration problems and its outboard bearing running hot.
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OPERATING DATA REPORT OPERATING STATUS
-UNIT-NAME.. 0YSTER CREEK DOCKET NUMBER.. 50-21(?
UTILITY DATA PREPARED BY...J.B.
SKLA:<
609-693-6013 REPORTING PERIOD... April 1982 LICENSED THERMAL POWER (MWT).. 1930 NAMEPLATE RATING (GROSS MUE).. 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 i
POWER LEVEL f0 WHICH RESTRICTED. IF ANY/ NET MWE)...
400 REASON FOR RESTRICTION. IF ANY...
CONDENSATE PUMP AVAILABILITY MONTH YEAR CUMULATIVE HOUPS IN PERIOD 720.0 2880.0 108288.0 HOURS RX CRITICAL 396.1 396.1 78372.4 lRXRESERVESHUTDOWNHRS.
0.0 0.0 468.2 i
a
! HRS. GEN ON LINE 341.6 341.6 76551.6 1
UT RESERVE SHUTDOWN HRS 0.0 0.0 O_0 GROSS THERMAL ENERGY 428300.0 428300.0 129019330.5 GROSS ELEC ENERGY 132460.0 132460.0 43818435.0 jNET.ELEC ENERGY 124290.0 124290.0 42191.728.0 UT SERVICE FACTOR 47.4 11.9 70.7 LUT AVAILABILITY FACTOR 47.4
- 11. 9 ~
70.7 UT CAPACITY FACTOR MDC 27.8 7.0 64.1 UT CAPACITY FACTOR DER 26.6 6.6 59.9 FORCEDl0UTAGE FACTOR 52.6 88.1 11.6 NO 0UTAGE IS SCHEDULED DVER THE NEXT-SIX HUNTHS-t--.
_ _ _ _ _. _ _ _ _ _ _ _. - _. - _ - _ _ - - _ - - _ _ _ _ _ _ _ _ - _ _ -. ~. - - -
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AVERAGE DAILY POWER LEVEL DOCNET 4......
50-219 UNIT..........
O. C.
01 REPORT DATE... May 12, 1982 COMPILED BY...
J.B.
SKLAR l
TELEPHONE..... 609-693-6013 i
i MONTH Aprii 1982 DAY MW DAY MW i.
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17.
99.
j 2.
O.
18.
132.
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3.
O.
19.
373.
4.
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20.
397.
5.
O.
21.
403.
6.
O.
22.
399.
7.
O.
23.
388.
8.
O.
24.
372.
I 9.
G.
25.
377.
10.
O.
26.
390.
11.
O.
27.
396.
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12.
O.
28.
396.
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j i3.
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29.
396.
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30.
399.
15.
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i 16.
300.
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Oyster Creek, Station Docket No. 50-219 REFUELING INFORMATION -
Name of Facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdown:
January 15, 1983 Scheduled date for restart following refueling: late - 3983 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
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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:
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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 Assemblies - No major changes have been made nor
- are there any anticipated.
i 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:
I The Spring 1987 Outage.*
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- NOTE:
This is for a normal refueling.
Full core off-load, however j
can only be accommodated through about 1983 or 1984 with 1800 licensed locations.
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April SUhNARY OF QASL Electrical MAINTENJ6CE 1
1 EQUIPSDTP MALRNCTION (DRREC'IT!E ACTION No indication on breaker open Repaired loose resistor socket for Diesel Generator #2 light on 4160 V breaker indicating light, proper indication af ter repair Replaced bad set of contacts on re^ 3y.
Diesel Generator #2
, Relay - FSR-A has bad contact Did fast start test to prove relay operation per Procedure 636.2.002.
Note:
Diesel would have started if recuired.
24 Volt D C System Charger A-1 low output voltage Replaced voltage regulator diode -
returned to service Reactor Protection System IKTDI scram reset - relay not Replaced IKTDI Relay.
Placed system working back in service - tested satisfactorily 24 Volt D C System "Of f Normal" Alarm in Control Cleaned contact en relay for Charger Room A alarm clears V-27-3 Drywell Ventilation No position indication Adjusted actuator arm for proper in-Valve dication Reactor Building Air Lock Inner door interlock switch Repaired switch - placed door back in Door 51' Level hanging up service 1-2 Fire Diesel Noted hesitation when starting Installed new pilot solenoid contactor.
Tested satisfactorily.
Reactor Building Air Lock Interlock solenoid rod s tick-Cleaned switch contacts for solenoid -
Door 23' level S/E ing worked correctly after cleaning Control Room Vital Door Door latch not locking Replaced latch - placed back in service Latch
Page 2 of 2 April SUbNARY OF QASL Electrical PM'TENKG EQUIP >ENT MALEUNCITON CDRRR.:nVE JCTICN Emergency Service Water Install temporary heater in Installed temporary heater in ESW Pump Pump Motor 1-1 motor 1-1 until permanent heater arrives Drywell Oxygen Sample Iso-V-38-10 failed close Found dirty contact on 6K37 relay lation valve V-38-10 cleaned contacts - valve operated properly "C" Battery Room Ventilla-Low temperature alarm "on" Adjusted dampers for proper air flow tion to clear alarm Recirculating Pump "C" By-Motor contactor noisy Phase monitorina relay RF2 binding, pass Valve NG08C cleaned relay, return to service
.. Stack Gas Panel Insulation on tiire needs repair Replaced wire.
System lef t operable 1-8 Drywell Sump Hi-Level Alarm in with sump Found debris interfering with Hi-Level empty Switch movement.
Cleaned sump and tested system satisfactory.
125 VDC Station Battery "B"
Low Voltage / Low Room Ventila-Found low air flow due to dirty filter.
tion Flow Alarm continuously in Mechanical Maintenance removed dirty filters.
Alarm reset to normal.
1-8 Drywell Sump Motor contactor overload reset Repaired reset and placed back in will not reset service "B"
Recombiner Pre-heater Pre-heater will not start Replaced pre-heater relay.
Placed heater back in service.
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Page 1 of 2 April SGIGRf OF QASL I &C MAINTENANCE g]P>ENT MAIFUNC1' ION C01ce:nVE ACTION
- Fuel Pool Cooling Discharge Low discharge pressure lights Replaced defective light bulb in meter
, pressure indication on elev. 119' "on",
- however, relay - system operating satisfactorily discharge pressure normal Clean-up System instrument Pressure gauge isolation valve Replaced valve and hydro tested -
valvo to pressure gauge (IJ leaking checks satisfactorily 033) on non-regen Hx.
Valve Monitoring System Remote indicators on Panel 1F/
Repaired mechanical linkage and zero Channels 13 & 21 2F (VMS-13 & VMS 21) not in-adjustment.
Satisfactorily performed dicating-properly Surveillance Test 602.3.008 Test fittings for Reactor High Swage lock test fittings Replaced test fittings and satis-Pressure Scram Switches stripped factorily performed Surveillance Test RE-03 A, C, D
619.3.017 Dif ferential pressure indica-High differential reading, Replaced snubbers on both high & low tor for A&B Control Rod Drive check snubber on sensing lines sensing lines.
Satisfactorily per-Filters (RD-39) for cleanliness /blcckage formed instrument calibration.
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Control Rod Drive 30-03 Rod will not scram from test Replaced defective test switch on switch on Panel 6XR Panel 6XR, tested for proper operation after repairs Reactor Low Water Level Small leak on sensor observed Tightened Hex Bolts on cell, Hydro Sensor RE05A during vessel hydro Tested Sensor, tested and satisfactorily performed Surveillance 619.3.013 Augmented Off-Gas Building Flow Control Valve not working Changed control valve from reverse "A" Recombiner Recirc Flow properly acting to direct acting.
Calibrated control loop.
Observed proper operation.
Valve Monitoring System Damaged Coaxial Cable Replaced damaged cable, replaced Safety Valve NR 28R accelerometer, satisfactorily tested Electromatic Relief Valve Thermocouple has open or loose Replaced thermocouple element - verified Thermocouple NR-10 8 "B"
connection proper temperature reading
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April I &C SWIGRf OF QASL FRINIENXWE FRLFUSCrION Q RRDCTIVI:ICTION DNIPMNT Recirc Pump No. 2 Seal Pres-Panel meter reading lower than Replaced meter indicators for C&E sure Indicators normal Pumps checked calibration as per j
Procedure 703.3.001 satisfactorily Sarvice water remote pressure Motor out of Spec / Tolerance Replaced meter and satisfactorily calibrated indica tor Drywell/ Torus temperature Recorder points out of step Replaced contact brush assembly, adjusted worn gear clutch, calibrated and reset alarm points "B" Reactor Recirc Pump Low differential alarm annun-Repaired loose wire on "B"
Recirc Pump ciated and panel meter down dif ferential pressure transmitter checked scale transmitters on all recirc pumps.
Local power range monitor Alarm Annunciated on Penel 3F Replaced defective fuse, alarm cleared power supply
- operates satisf actorily Torus Pressure Recorder Not responding Replaced servo motor and defective amplifier - checked calibration Stack Gas "A" Recorder Inoperative Replaced broken drive cord - recali-brated recorder Condensate Transfer Pump 1-1 Discharge Pressure Gauge Calibration questionable Replaced gauge with new calibrated spare Condensate Transfer Pump No.
Calibration / Replacement 2 Discharge Pressure Gauge required.
Gauge overranges wher Installed new calibrated (glycerine) pump starts liquid filled gauge for snubber action.
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Aori1 SUbfRRY OF QASL MechanicalMAINTEtMCB EQUIP >ENT hmIMNCTION QR,63nm
" A" Control Rod Drive Pump Outboard bearing housing oil Adjusted & installed additional shims leak on bearing cover to provide tight seal 1-1 Se rvice Wa te r Pump Vibration appears abnormal Replaced throttle bushing - vibration readings satis factory Drywell Airlock Door Door seal leakage excessive Installed new door gaskets - leak rate tested satisfactory Clean-up system valve V-16-1 Valve packing leaks Packing adjusted on all valves - leakage and Isolation Condenser valves stopped V-14-36 and 37 Isolation Condenser Valves Valve packing leaks Packing adjusted - leakage stopped V14-31 and 32 Isolation Condenser Vent Valve packing leaks Packing adjusted on all valves - leakage Valves V-14-6,7 and 8 stopped "A"
CRD Pump Excessive vibration Installed new rotating element and bearings - pump operation satisfactory
" A" CRD Pump Suction Strainer Inspect strainer for possible Strainer removed, inspected, and cleaned.
plugging No restrictions found.
Water leakage at welded "T"
Condensate Transfer System between main header and hose Line removed and capped Torus Area south side station Inspected and adjusted linkage on valve Drywell vent valves V-27 -1 Failed Leak Rate Test operators and satisfactorily passed Leak and 2 Rate Test 1
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