ML20066D133
| ML20066D133 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/12/1982 |
| From: | Frick R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20066D125 | List: |
| References | |
| NUDOCS 8211110175 | |
| Download: ML20066D133 (9) | |
Text
--
MONTHLY OPERATIONS
SUMMARY
September 1982 At the beginning of the report period, the Oyster Creek Nuclear Generating Station was operating at 413 MWe'with power limited by core reactivity.
The second stage steam reheaters were removed from service due to steam leaks in the drain system and resultant increase in airborne activity.
This action eliminated the airborne activity problem.
Emergency Service Water Pump 52A was temporarily de-clared inoperable when it failed to produce acceptable differential pressure during testing.
The pump was declared operable after cleaning, adjustment of its impeller, and retesting.
The voltage regulator on No. 2 Reactor Protection System Motor Generator Set shorted out during preventive maintenance. The system will be powered by the standby transformer until a new voltage regulator can be procured.
The Instrument Department is investigating a flow oscillation problem caused by "C" Reactor Recirculation Pump.
At the end of the report period, the Plant was operating at 376 MWe.
l l
l
[
I 8211110175 821015 PDR ADOCK 05000219 i
R PDR
The following events were identified as potential Reportable Occurrences:
On September 2, 1982, during tht performance of the Reactor Vessel Leak Test, two of the Five Electromatic Relief Valves were in the "OFF" position with Reactor pressure greater than 110 psig and Reactor temperature greater than 2120 F.
On September 9, 1982, the "A" Emergency Service Water Pump was made inoperable after it failed the pump differential pressure acceptance criteria during testing.
The pump was returned to service on September 13, 1982 following maintenance.
4 1
4
,s
+.
y g
p w
g y-3 r-.
y-y-
1 4
AVERAGE DAILY POWER LEVEL NET MWe Docket #.
. 50-219 Unit
. O. C. #1 Report Date..... October 12, 1982 Compiled by..... Robert Frick Telephone...... 609-971-4637 MONTH September 1982 DAY MW DAY MW 1
387 16 370 2
387 17 369 3
388 18 368 4
391 19 368 5
388 20 365 6
388 21 367 I
7 388 22 367 8
388 23 364 l
j 9
388 24 363 10 385 25 360 l
11 380 26 359 i
12 377 27 356 i
l 13 376,
28 355 r
14 373 29 353 15 372 30 352 l
e F'
..,.m r
_., - _,,.,,,. _, _, _ _. _ ~,.,
... ~. _ _ ~ _ _...,
,-.._..u..
v.,. - -_.,
l OPERATING DATA REPORT OPERATING STATUS ~
Unit Name... Oyster Creek Docket Number..
50-219 Utility Data Prepared By... Hari Sharma 609-971-4638 Reporting Period.. September 1982 Licensed Thermal Power (MWT)..
1930 Nameplate Rating (Gross MWE)..
687.5 x 0.8 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 Power Level to Which Restricted, if Any (Net MWE)..
380 Reason for Restriction, If any...
Fuel Depletion MONTH YEAR CUMULATIVE HOURS IN PERIOD 720.00 6551.0 111959.
HOURS RX CRITICAL 720.00 3619.91 83347.02 RX RESERVE SHUrDOWN HRS.
0.0 0.0 468.2 HRS. GEN ON LINE (SERVICE) 720.0 3516.1 80536.6 l
UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERMAL ENERGY 887800.
4752000.
134309300.
GROSS ELEC. ENERGY 282750.
1509140.
45425360.
r NET ELEC. ENERGY 268660.
1424300.
43665140.
UT SERVICE FACTOR 100.0 53.7 72.0 UT AVAILABILITY FACTOR-100.0 53.7 72.0
{
UT CAPACITY FACTOR MDC 60.0 35.0 62.9 UT CAPACITY FACTOR DER 57.4 33.4 60.2 FORCED OUTAGE FACTOR 0.0 52.0 11.7 The next scheduled outage is to begin on January 15, 1983.
UNITSilUTDOWNS AND POWER REDUCTIONS DOCKETNO.
50-219 UNITNAME Ovster creek DATE in /A /n?
REPORT &f0NTil September 1982 COMPS.ETED BY n
nevon TEt.EPilONE 971-4640
?
l i
n
.$E
}
I ikensee 5%
k*S" Cause & Corrective No.
Date g
3g
,, g ;
Event
%1 j
Action to
$6 5
ji$g Report
- Au Psevent Recurrence 8
ZZ ZZZZ Z
ZZ Z
Z NA ZZ ZZZZZZ No significant power reduction or shutdown during report period.
I i
i I
2 3
4 F: Forced Reason:
Method:
S: Scheduled Exhibit G-Instructions A Equiprnent Failure (Explain) 1 Manual for Preparation of Data i
B-Maintenance of Test 2 Manual Scram.
Entry Sheets for 1.icensee C-Refueling
- 3. Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4 O her(Explain) 0161)
E-Operatoe Training & Ucense Exandnation F Administrative 5
G-Operational Estor (Explain)
Exhibit I Same Source 19f??)
llother(Explain)
O o
D Page 1 of 1 Sept.
SUbNARY OF QASL Electrical MAINTENANCE ErJJIPbENT MALFUNCTION CORRECTIVE 1CTION Augmented Off Gas Building "A"
Recombiner Blower tripping Meggered motor.
Found all windings off line grounded.
Job Order initiated to disassemble Spencer Turbine.
Main Steam Isolation Valve Open light limit switch did not Adjusted open limit switch so switch NSO4B reset after 5% closure test would reset.
Did 5% closure test twice.
Switch tested satisfactorily.
1-2 Reactor Protection MG Inboard flywheel bearing running Replaced olo p se. Temperature de-Set above normal operating tempera-creased from 49' to 17.50 C.
Bearing ture temperature is now running satisfactorily.
Shut Down Cooling System Vibration indication on V-17-56 Cycled valve twice.
No significant noises or vibration.
All current readings were satisfactory.
R3 actor Manual Control Rod Worth Minimizer by-pass Replaced by-pass switch.
System tested Sys tem switch failed to by-pass satisfactorily.
Core Spray System Broken conduit connection in Repaired conduit connection.
Valve conduit to V-20-92.
tested satisfactorily.
Pago 1 of :1' Sep t.'
SUfEME OF QASL Mechanical MAINTENANCE EQUIPENT MAIRJNCPION CORRfX"PIVE ACTION Shutdown Cooling Valves Packing leaks Adjusted packing V-17-55, 56 and 57 CRD Scram Air Filters Filters dirty Filters removed and cleaned "B" Poison Pump Packing leak Adjusted packing CRD Accumulator, 42-35 Valve Packing leak Adjusted packing V-107 Isolation Condenser Valve Packing leak Added one ring of packing & adjusted.
V-14-32 Replaced packing gland eyebolt.
Stroke tested satisfactorily.
.CRD NC-30A Packing leak Adjusted packing Isolation Condenser Valve Packing leak Added two rings on packing and' adjusted.
V-14-31 Stroke tested satisfactorily.
"B" Reactor Clean-up Pump Water in the oil Changed oil' cooler and oil.
Oil samples taken periodically.- Tested ~
satisfactorily.
2 2
connections are leaking or.
Replaced caps on N connections.
38-31, 38-39, 46-35, 34-19 and Leak tested satisfactorily.
42-39 Inspected & cleaned suction.
Reset "A"
ESW Pump Low discharge pressure impeller adjustment.
Pump tested satisfactorily.
4 Paga 1 of 1
)
l c
Sept.
SUlHARY OF QASL Instrument MAINTENANCE 1
i EQUIPE NT MAIMNCTION 00RRECTIVE ACTION l
Avarage Power Range Monitor Intermittent half scrams while Replaced defective potentiometer l
Channel #2 adjusting power level R-10.
Observed operation after I
repairs - results satisfactory.
I Intermediate Range Monitor Downscale alarm on continuously, Replaced downscale relay.
Alarm j
i Channel #16 no downscale trip cleared.
Tested satisfactorily.
Local-Power Range Monitor Defective amplifier Replaced amplifier with operational 28-49A spare.
Satisfactorily performed front panel test.
Area Radiation Monitor Failed downscale Repaired loose wire in connector.
l RO14A-4 Tested and calibrated satisfactorily.
l l
Scram Air Header Pressure Abnormal indication Replaced pressure gauge with cali-Gauge brated spare.
Replaced transducer and transistor Scram Dump Volume Monitoring Failed sensor (UD-ll) in wall thickness P.C.
board.
Cali-System brated and tested satisfactorily.
i
=
1
e" Oyster Creek Station Docket No. 50-219 REFUELING INFORMATION -
Nane of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:
January 15, 1983 Scheduled date for restart following refueling: late - 1983 Mill refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?
Technical Specification Change Request No. 96 was submitted on August 31, 1982 for int arporation of GE fuel assemblies into the Cycle 10 core.
Scheduled date(s) for submitting proposed licensing action and supporting information:
March 9,1981 - Complete NEDO document #24195 (G.E. Reload Fuel ipplication for Oyster Creek) was submitted.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
1.
General Electric fuel assemblies - fuel design and performance 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 essemblies:
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.