ML20101T013
| ML20101T013 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/30/1992 |
| From: | J. J. Barton, Bradley E, Egan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-92-2211, NUDOCS 9207200198 | |
| Download: ML20101T013 (7) | |
Text
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GPU Nuclear Corporat%n Nuclear
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Forked River, New Jersey 087310388 609 971 4000 Wnter's Direct Dial Number.
C321-92 2211 July 14, 1992 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50 219 Honthly Operating Report I
In accordance with the Oyster Creek Nuclear Canersting Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C. enclosed are two (2) copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
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~/A J.J. E arton VigejresidentandDirector fsnrCreek l
JJB/BDEM: Jc Attachment cc:
Administrator, Region 1 Senior NRC Resident Inspr. tor Oyster Creek NRC Project Manager 9207200398 920630 gDR A00CK0500g9
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GFU Nuclear Corporation is a subsdary of Genera! Pubhc Utstie: Corporation
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Monthly Operating Report June 1992 Oyster Creek entered June in a Maintenance Outage to perform preventive and corrective actions to enhance plant capability during the summer. On June 7,1992, t% nian'. Mgan a start-up, but ti.ually shutdown the following day due to-a substantial packing leak on isolation Condenser Valve V-14 33.
After repairing the valve, the plant commenced a start up and achieved criticality at 2240 on June 10, 1992, but twenty minutes later an automatic scram occured due to failed IRM bypass switches.
The bypass switches were replaced, and a start-up was again initiated on June 11, 1992. The plant was placed on line at 1728 on June 12, 1992, and continued power ascension until full power was attained on June 14, 1992.
The plant remained at full power for the remainder of the month and had a capacity factor of 58.6 %, generating 257,286 megawatts electric net output.
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e MONTHLY OPERATING REPORT The following Licensee Event Reports were submitted during the month of June, 1992:
LER 92-0 M A reactor scram and subsequent Engineered Safety features systems actuations were caused by a turbine load rejection due to faults on off-site 230kV transmission lines caused by a forest fire.
The scram occurred at 1326 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.04543e-4 months <br /> on May 3, 1992 and the event concluded at 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br /> on Itay 4, 1992. The reactor was operating at approximately 100% power before the scram.
Numerous other engineered safety features actuated including isolation Condensers, Containment Isolation, Diesel Generator fast start, Core S) ray and Standby Gas Treatment.
Several additional scram signals occurred in tie process of bringing the plant to cold shutdown and returning power supplies to off-site sources. An Unusual Event was declared based on high drywell temperature, and an Alert was declared based on the potential of the forest fire to further affect the plant.
The plant was brought to cold shutdown at 2234 hours0.0259 days <br />0.621 hours <br />0.00369 weeks <br />8.50037e-4 months <br /> on May 3, and the emergency c;ndition was terminated at 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br /> on Way 4, after off-site power was restored to vital electrical buses. Off-site power had been available since 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br /> on May 3, but plant management decided not to place the vital buses on off-site power until reliability could be assured.
No plant structures or equipment were damaged by the fire.
The forcst fire which caused the loss of off-site power was the root cause of the event, and the safety significance was minimal because all systems functioned as required. Corrective actions include a revision to the Diesel Generator operating procedure tu prevent an avoidable scram when securing diesel generator operation. Utility personnel inspected off-site power lines and found no damage. High resistance contacts on the control rod drive pump time delay relay were replaced due to the pump's failure to start on a diesel generator load sequence.
LER 92-006 On May 10, 1992 while performing an Electromatic Relief Valve (EMRV) Pressure Sensor surveillance, the "As Found" trip setpoint for the high pressure relief function on one EMRV was above that specified in the Technical Specifications.
The cause of this occurrence is attributed to setpoint repeatability and instrumer.t drift.
The design setpoint repeatability can tolerate instrument drift up to 2.5 psig of the Technical Specification limit.
Previous surveillance records indicate that these instr %ents frequently undergo additional drift within Technical Specifir:tton limits due to changing plant and environmental conditions.
This occorrence is considered to have minimal safety significance as the automati:. depressurization function of the EMRVs is not affected by these pressure switches, all five EMRVs would have actuated to relieve pressure, and the Isolation Condenser System and turbine bypass valves were fully oper. ole. The pressure switch was adjusted to actuate within the
' echnical Sper,1fication limit.
A new pressure sensing system is to be installed ir accordance with the Oyster Creek Integrated Schedule, which currently ',pecifies the Cycle 15 refueling outage for completion of this project.
OPERATING DATA REPORT OPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
06/92 3.-UTILITY CONTACT:
ED BRADLEY (609)971-4097
- 4. LICENSED THERMAL POWER (HWt):
1930 l
- 5. NAMEPLATE RATING (GROSS HWe):
687.5 x 0.8 = 550 I
6.. DESIGN ELECTRICAL RATING (NET MWe): 650
- 7. MAXIMUM DEPENDABLE CAPACITY (CROSS MWe):
632
- 8. MAX 1 MUM DEPENDABLE CAPACITY (NET MWe):
610
- 9. IF CHANGES OCCUR ABOVE SINCE LAST PEPORT, GIVE REASONS:
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET HWe):
NONE las REASON FOR RESTRICTION,--IF ANY:
NONE EONTH XEAB CUMULATIVE
- 12. REPCRT PERIOD HOURS 720.0 4367.0 397423.0
'13.-HOURS RX CRITICAL 480.8 4009.3 128372.0
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS.GENEPATOR ON-LINE 438.5 3902.1 125034.4
- 17. GROSS' THERM ENERGY (HWH) 825029 7454544 211784903
- 18. GROSS ELEC ENERGY (HWH) 269354 2506077 71191707
- 19. NET ELEC ENERGY (HWH) 257286 2411452 68318140
- 20. UT EERVICE FACTOR 60.9 90.5 63.3
- 21. UT AVAIL FACTOR 60.9 90.5 63.9
58.6 90.5 55.9
'24. UT. FORCED OUTAGE RATE 17.2 4.3 11.3
- 25. FORCED OUTAGE HRS 91.0 176.8 15868.0
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, DURATION):
14-R NOVEMBER 27, 1992, 66 - 75 DAYS
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A L
NRC_RPT.WPD/56 l
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l Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - JUNE, 1992 Name of Fac.tlity: Oyster Creek Station #1 Scheduled date for next refueling shutdown: November 27, 1992 Scheduled date for restart following refueling:
February 10, 1993 Will refueling or resurnption of oper< ion theccafter require a Technical Specification change or other license amendment?
No 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 optrating procedures:
Fuel design and 1.
General Electric Fuel Assemblies performance analysis methods have been approved by the NAC.
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 = 1708 (c) in dry storage a
44 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has b9en requested or is planned, in number of fuel assemblies:
Present Licensed Capacity:
2600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Full core discharge capacity to the spent fuel pool will be available through the 1996 refueling outage.
NRC_RPT.WPD/54
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AVERAGE DAILY POWER LEVEL NET HWo i
DOCKET #.
.50-219 UNIT.
. OYSTER CREEK #1 REPORT DATE.
. JULY 8, 1992 COMPILED BY.
. ED BRADLEY TELEPHONE #.
.609-971-4097 i
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MONTH:
JUNE, 1992 DAX
-M DAY.
HH 1.
0 16.
609 2.
0 17.
609 3.-
0 18, 609 4.
0 19.
609 5.
0 20.
608 6.
O 21.
618
'7.
0 22.
620
- 8. -
0 23, 620 j
1 9.
0 24.
649 10.
0 25.
618 11.
0 26.
613
'12.
58 27.
594 13, 429 28.
609 14.
533 29.
607 15.
610 30.
606 i
f NRC_RPT.WPD/55 i
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