ML20058D127
| ML20058D127 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/14/1982 |
| From: | Baran R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20058D126 | List: |
| References | |
| NUDOCS 8207270031 | |
| Download: ML20058D127 (9) | |
Text
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1 ITNIHLY OPE. RATIONS SLMERY JUNE 1982 At the beginning of the reporting period, the Oyster Creek Nuclear' Generating Station was operating at 450 me with power limited by an
~
out-of-service condensate p mp.
On June 4,1982, a reactor scram occurred due to high reactor water level. he rapid level increase resulted frm feed pmp run out which occurred during the refill of the Reactor Cleanup Systs (following deineralizer resin replacment). Subsequently, a startup was cmmenced..
Criticality was achieved and the generator tied intib the grid on June 5, 1982.
The following day, "C" condensate punp was returned to service and load was increased to approximately 550 We. Powe'r is now limited by core reactivity.
A heavy grass accunulation at the Intake Structure on June 9,1982 caused a tmporary decrease in power of 50 We.
I r
Intermittent probles experienced with Off-Gas Systs valve V-7-31 made systs operability questionable and rcquired the ccmnenement of orderly shutdowns on June 15, 1982 and againson June 16, 1982. he investigation uncovered a faulty actuating solenoid which was removed from service and power level was returned to 528 W e.
4 Power was again ruinew1 on June 25th for four hours by approximately 40 MWe for rod shaping.
Also, during this period, corrective maintenance was required for 4 ~
"A" CRD pmp because of a leaky head gasket and excessive vibration.
Maintenance was empleted and the cmponent was returned to an operable status. In addition, the Chlorine Systs was isolated for two days in order to repair a leak. Standby Gas Treatment Syst s I was declared inoperable due to a high HEPA filter AP noted during surveillance.
N However, the ensuing investigation disclosed that the high indications were due to inaccurate instrumntation. Systm I was subsequently returned to operation.
At the end of the report period, the Station was operating at approximately 500 We.
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T 8207270031 820714 PDR ADOCK 05000219 R
/
'Ihe following events were identified as potential Reportable Occurrences:
On June 13,1982, "A" CRD ptxtp was renoved from service due to excessive vibration and decrease in discharge pressure.
On June 14, 1982, Diesel Generator No. 2 was renoved frm service for monthly maintenance while "A" CRD ptztp was inoperable.
On June 16, 1982, a nipple failed on Condensate Transfer Putp No. 2 causing an uncontrolled and unrtonitored release of water to the envircoment.
On June 15 and 16, 1982, Off Gas Isolation Valve V-7-31 failed to operate as expected, thus causing the operability of the valve to be questimable. One of two solenoid actuating valves failed preventing V-7-31 frm closing fully.
On June 18, 1982, Core Spray Ptxtp "A" was tetporarily retoved fr a service for a motor meggar check after it became wet during maintenance activities on "A" CRD punp.
On June 21, 1982, while blowing down and flushing the air receiver in the New Radwaste Facility Heat Exchanger Building approximately 300 gallons of contaminated water was released to the envircrrnent via the 30" service water header.
On June 25, 1982, it was discovered that one of the isolation condenser isolation sensors had been out of service greater than the time allowed by the Technical Specifications (one hour).
On June 30, 1982, it was discovered that the Thermocouple Valve Monitoring Systs monthly channel check was not performal within the time limit required by the Technical Specifications.
On June 30, 1982, during the perfonnance of the Thernoccuple Valve Monitoring Systen nonthly channel check, it was determined that the secondary lift monitor (thernoccuple) for Safety Valve NP28J was inoperable.
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UNITSilUIDOWNS AND POWER REDUCTIONS DOCKETNO.
50-219 UNIT NAME Oyster Creek DATE REPORT MONill June 1982 COMPLETED BY R_
Rnrnn TELEPIIONE 971-46an E
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,Y3 Licensee Eg go, Cause & Corrective No.
Date g
3g jg5 Event gg gu Action to 3
F
$E 5
jdig Report #
mO Prevent Recurrence g
25 6/4/82 F
38 11 3
NA ZZ ZZZZZZ Turbine trip greater than 40%
power. Turbine trip caused by high Reactor water level when feedwater pumps went to runout while filling the Reactor Clennup System.
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 Repor (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
EOperator Training & Ucense Examination F Administrative 5
G-Operational Error (Explain)
Exhibit I Same Source (9/77) 11-01her (Explain)
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I:TILII^i DATA PREPARED DY..
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di3 901 REP 01 TING PERTOD.. June 1902 k
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NAnEFLATE AAT.ING(GROSS t1WE).. 6SO DESIGN ELECTRICAL RATING (NET MWE).. 650 MAXIMUM DEPENDADLE CAPACITY (GROSS MUE)..650 I
i (1AVIMUM DEPENDABLE CAPACITY (NET HWE).. 620 l
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IF CHANGES OCCUR IN CAPACITY RATING SINCE LAST REFORT. GCVE REATON NONE i
t F0WER LEVEL TO WHICH RESTRICTED. IF ANY(NET MUE).
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i REASON FOR RESTPICTION. IF ANY...
7 FUEL DEPLETION - PLANT IS IN A COASTDOWN l
MONTH YEAR CUnULATIVE HOURS IN PERIOD 720.O 4343.0 10??51.0 t
HOURS RX CRITICAL 687.0 1743.2 797i9.6 l
f RX RESERVE SHUTDOWN HRS.
0.0 0.0 463.2 l
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HRS. GEN ON LINE 682.3 1655.1 77365.1 UI RESERVE' SHUTDOWN HRS 0.0 0.0 0.v i
t GROSS THERMAL ENERGY 103 30 C+0. 0 226.8i00.0 130SSY139.5 i
GROSS ELEC ENERGY 339040.0 725300.0 44411275.-
i NET ELEC ENERGY 324470.0 690970.0 4275G408.0 UT SERVICE FACTOR 94.8 38.1 70.9 UT AVAILABILITY FACTOR 94.8 38.i 70.9
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r UT CAPACITY FACTOR MDC 72.7 25.7 64.1 h
t UT CAPACITY FACTOR DER 69,3 24,5 59.9 f
FORCED OUTAGE FACTOR 5.2 61.C ii e f
NO OUTAGE IS SCHEDULED OVER THE NEXT SIX MONTHa i
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June SU'O'JJN OF 0?.SL Mechanical n l: Ti x v;ci; Page 1 of 1 iJ)UIP:.Fler MLFUNCTICN CORRECTIVE ICTICN "A" Control Rod Drive Pump Pump head gasket leaking Retorqued head bolts. Leak s topped.
Liquid Poison System V-19-36 Packing leak Adjusted packing.
Leak stopped.
480 Switch Gear Room Fire Barrier found partially 3 routed affected depressions.
p degraded CRD Accumulator 34-11 Leaking through Replaced V-lll with a rebuilt unit.
V-lll Drywell 1-8 Sump Discharge
' Foreign matter blocking valve Cleaned valves and returned to service.
Check Valves Accumulator 46-27 Leaking through Replaced V-lll with a rebuilt unit.
V-lll Clean-up Demin System Pre-Strainer plugged Cleaned strainer element and returned, to service.
l Clean-Up System Demineralizer resins depleted Changed resins.
Clean-Up System Post strainer plugged Cleaned strainer element and returned to service.
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- N.
June SU' 'JRt* OF On.SL Electrical MAINTaL6CE Page 1 of 1 EQUIP:3T
?OsIFUNCTIO:1 C)RRECTIVE ICI' ION Stack Gas Sample Pump "B"
Pump not performing properly Installed and tested new improved model pump using Procedure 82-059.
Tested satisfactory.
Stack Gas Sample Pump "B"
"B" Pump tripping on overload Replaced defective overload.
Tested and returned to service.
1-1 Service Water Pump Solenoid for oiler not working Replaced oiler solenoid with new coil.
y Oiler worked properly af ter installing new coil.
125 VDC Battery Room Ven-Low flow from 1-1 fan R2 relay was not operating dampers.
tilation Replaced relay and placed ventilation system back in service.
Clean-Up System Valve V-16-1 During routine maintenance, New breaker was installed and tested breaker tested low on current satisfactory.
Valve was operated and curve placed back into service.
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gt;,7,,JdiY OF O'.SL IRINTEN75 G, Page 1 of 1 June Instrument EQUIP:SJT MALFLECTIG1 WRIECTIVE iTTIG4 Drywell Temperature Recorder Failed downscale Replaced stepping switch and checked for satisfactory operation Augmented Off Gas System Recirculation flow is erratic Rebuilt actuator, calibrated and stroked satisfactorily.
9 9
Oyster greek, 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 - 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.,
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 assemblies - 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.
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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