ML20076C467
| ML20076C467 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/15/1983 |
| From: | Baran R, Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8308230002 | |
| Download: ML20076C467 (7) | |
Text
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MONTHLY OPERATIONS REPORT JULY 15183 At the beginning of the report period, the OC Station was shutdown for the l'183 Refueling /Maintenar.ce Outage.
All fuel remains out of the reactor vessel which is drained for maintenance.
The Condensate System was restarted af ter the startup transformer (Bank b) was returned to service.
The plant experienced a lightning strike on July 5, 1983 which caused a trip of substation breakers "N7" and "08".
Consequently, various plant loads were lost including the plant Security Computer.
While replacing Reactor Protection System Relay 1K72 (Drywell Isolation), fuse LF7 in Panel llF failed causing a Drywell Isolation.
The fuse was replaced and the isolation signal reset.
Additionally, the following items were considered roteworthy:
1 Due to a wiring error, a temporary transformer to provide power service was destroyed when it was initially energized.
A result of this incident caused a drywell isolation, a loss of the ventilation systems in the Reactor and Turbine Buildings, initiation of the standby gas treatment system, trip of the running air compressor and loss of lighting in various parts of the plant.
2.
_The bearings in Standby Gas Treatment System Fan EF 1-8 were replaced.
3 A tube leak in "A" Fuel Pool Heat Exchanger was repaired.
4 No. 2 boiler was returned to service after an extensive tube replacement which took approximately two months.
5.
Diesel Generator No. I was taken out of service for one (1) day in order to troubleshoot a relay problem discovered during surveillance testing.
6 RBCGJ Pump 1-1 was returned to service af ter motor replacement.
8308230002 830815 gDRADOCK 05000219 PDR
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The following Licensee Event Reports were submitted during July 1983:
Reportable Occurrence No. 50-219/83-04/03L:
During preventive maintenance on CRD Pung NCO8A circuit breaker it was found that with the undervoltage trip device de-energized the trip shaft mechanism could not prevent breaker closure due to binding. Binding and friction in the trip shaft bearing was caused by oxidized lubricant.
Reportable Occurrence No. 50-219/83-15/03L:
While performing preventive maintenance on Reactor Building Closed Cooling Water Pump 1-1 circuit breaker a twisted wire gag was found tied around the armature of the undervoltage trip device. Placenent of the wire around the armature obstructed free movement of the device which prevented the circuit breaker from tripping upon loss of power. This condition also caused damage to the static time delay box and the blowing of its control power fuses. The cause was attributed to personnel error and lack of procedural control.
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1 UNIT SilUTDOWNS AND FOWER REDUCTIONS DOCKETNO. 50-219 UNITNAME uyster Creek DATE 8-15-83 REPORTAIONill July, 1983 COMPLETEDRY R.
Baran TELEPil0NE - 4640 i
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Cause & Corrective No.
Date R
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dE j 55 g ReposI a mtf Pacvens Resussence S
I 31 2-11-83 S
4080 C
1 NA ZZ ZZZZZZ Start of 1983 Refueling Maintenance Outage.
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3 4E F: Fosc:d Reason:
Efethod:
if Exhibit G. instructions S: Scheduled A. Equipment Failure (Explain) 14fanual
? Entry Sheels foe Lkensce for Prepasallon o(Data I-84f aintenance of Test 2-hfanual Scram.
C-Reructing 3-Automaile Scram.
Event Report (LER) File (NUREG.
D-Regulatory Restikilun 4-Other(Explain) l0161)
EOperator Taarning & Ucense Emandna: Ion F Administrative 5'
G4perallonal Enur(Explain)
Exhibli! SanwSource (9/77) lierher(Explain)
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-4 OPERATING DATA REPORT
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OPERATING STATUS 1.
DOCKET:
50-219 2.
UTILITY CONTACT:
Joseph R. Molnar 609-971-4699
-3.
REPORTING PERIOD:
JULY, 1983 4.
LICENSED THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (CROSS MWe):
687.5
- 0.8 - 550 6.
DESIGN ELECTRICAL RATING (NET MWe):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 650 8.
MAXIMUM DEPENDABLE CAPACITY (NET MWe):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS: NONE 10.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
N/A 11.
REASON FOR RESTRICTION, F'ANY:
N/A MONTH YEAR CUMULATIVE 12.
REPORT PERIOD HRS 744 5,087.0 119,255.0 13.
HOURS RX CRITICAL 0
1,009.6 84,622.8 e
14.
RX RESERVE SHUTDOWN HOURS 0
0.0 468.2 15.
HRS GENERATOR ON-LINE O
1,007.8 82,693.5 16.
UT RESERVE SHUTDOWN HOURS 0
0.0 0.0 17.
GROSS THERMAL ENER (MWH) 0 853,300.0 136,224,730.5 18.
GROSS ELEC ENER (MWH) 0 244,630.0 46,056,905.0 19.
NET ELEC ENER (MWH)
-1,907 213,528.0 44,294,056.0 20.
UT SERVICE FACTOR 0
19.8 69.3 21.
UT AVAIL FACTOR 0
19.8 69.3 22.
UT CAP FACTOR (MDC NET) 0 6.8 59.9 23.
UT CAP FACTOR (DER NET) 0 6.5 57.1 24.
UT FORCED OUTAGE RATE O
0.0 9.7 25.
FORCED OUTAGE HOURS 0
0.0 8,916.8 26.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION): N/A 27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:
1/12/84
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PAGE 3 l
l AVERAGE DAILY POWER LEVEL l
ET We DOCKET #...............
50-219 UNIT.
O.C. #1 REPORT DATE............... AUGUST 2, 1983 COMPILED BY.
.. ROBERT J. FRICK TELEPHONE................
609-971-4699 l
MONTH: JULY, 1983 DAY MW DAY MW t
1 0
16 0
i 2
0 17 0
i 3
0 18 0
i 4
0 19 0
5 0
20 0
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0 21 0
7 0
22 0
8 0
23 0
9 0
24 0
10 0
25 0
11 0
26 0
i 12 0
27 0
13 0
28 0
14 0
29 0
l 15 0
30 0
l 31 0
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l Oyster Creek Station #1 Docket No. 50-219 REEUELING INFORMATION - JULY,1983 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Presently shutdown for Refueling Scheduled date for restart following refueling: January 12, 1984 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Technical Specification Change Request No. 96 was submitted on August 31, 1982 for incorporation of GE fuel assemblies into the Cycle 10 core.
]
Scheduled date(s) for submitting proposed licensing action and supporting information:
j September, 1983 - The final supplement to the reload analysis, delineating the specific core configuration for Cycle 10 operation, will be 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 0
(b) in the spent fuel storage pool
- 1341 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 the 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 accomodated through about 1983 or 1984 with 1,800 licensed locations.
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P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:
August 18, 1983 Director Of fice of Management Information U.S. Nuclear Regulatory Commission Washing ton, D.C.
20555
Dear Sir:
Subj ect: Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contact Mr. Michael Laggart at (609) 971-4643.
Very truly yours, a
/ W e [-.,o Ja - A h
Pdter B. Fiedler Vice President and Director Oyster Creek PBF:PFC:jal Enclosure s cc: Director (10)
Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Wa shing ton, D.C.
20555 Regional Administrator (1)
Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector (1)
Oyster Creek Nuclear Generating Station
[
d Forked River, NJ 08731 GPU Nuclear is a part of the General Pubhc Utihties System