ML20077R483
| ML20077R483 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1994 |
| From: | J. J. Barton, Edelmann P, Egan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-95-2024, NUDOCS 9501200294 | |
| Download: ML20077R483 (8) | |
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1 GPU Nuclear Corporation 0 Ngg1gf Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
C321-95-2024 January 13, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Dear Sir:
3
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report - December,1994 In accordance with the Oyster Creek Nuclear Generating 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 infonnation) 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.
Sincerely, s
c kr J.J. Barton b
Vice President and Director Oyster Creek en r v n
a L t. s(. s. b, JJB/BDEM: jc Attachment ec:
Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager (C:\\wp51\\demercha\\MOR-RPT.DEC) 9501200294 941231 PDR ADOCK 05000219 i
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PDR l
GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation L
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SUMMARY
f DECEMBER, 1994 Oyster Creek completed the 15th refueling outage at 0400 on December 16, 1994 when the turbine-generator was placed on-line.
Full power was. achieved on December 20, 1994 at 2145 following the completion of the Digital Feedwater System testing.
The MDC net for the month was 43.8% and the MDC net for 1994 was 67.8%
The plant generated 200,103 net MWH in December and 3,627,373 net MWH during 1994.
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MONTHLY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of December,1994:
LER 94-020 On November 10,1994 the reactor was being refueled during an outage. During perfonnance of the Containment High Range Radiation Monitoring System test, the Channel 2 monitor was inadvertently tested causing two automatic drywell ventilation exhaust isolation valves to close.
This event was caused by an operator performance deficiency. The operator intended to test Channel 1 and did not self-check sufficiently, inadvertently testing Channel 2.
This event was not safety significant since the isolation function of these valves was not required to be operable during plant conditions at the time of the event.
The two isolated valves were reopened. Additional corrective action include a human engineering review of the panel layout, procedural instnictions and operator tmining.
LER 94-021 On November 19, 1994, during a refueling outage, an unexpected reactor scram occurred.
While perfonning troubleshooting and a wiring repair on the Reactor Recirculation Flow Control System computer, an inadvertent introduction of a low speed demand succeeded by a high speed demand from the digital control system (DCS) led to total recirculation flow exceeding the high flow scram setpoint.
The cause of this event was personnel error due to misoperation of the DCS computer.
There is no safety significance to this event. The high flow scram feature was believed necessary to tenninate a flow increase transient during power operation. GPUN has ',ince proved that this limiting safety system setting is not necessary and has obtained NRC approval to remove this feature from the technical specifications.
Interim corrective action l'as been taken to ensure DCS maintenance activities have technical support and supervising personnel present during such activities. Also, the conduct of maintenance activities will be proceduralized to help minimize misopemtion/misapplicatica of the DCS diagnostic tools.
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LICENSEE EVENT REPORTS
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(Continued).
LER 93-006. R1
- On September 5,1991, Technical Specification Amendment 153 became effective requiring a Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) reduction to less than 90% if one Core Spray loop / component becomes inoperable.
On October 21,1993, it was identified that several Core Spmy System surveillance procedures have both main pumps or main discharge valves of either loop disabled. On four occasions the MAPLHGR exceeded 90% during the execution of these procedures, thus placing the system outside of its design basis. The cause of this event was the omission of the above mentioned procedures to be revised subsequent to the issuance of the Technical Specification Amendment 153. Safety Significance is minimal since the design basis conservatism exceeds the amount by which the plant operated above the Technical Specification limits for MAPLHGR. In addition, operator actions could have brought the disabled Core Spray loop to full operating status, had an accident occurred.
Interim Corrective Action was taken to ensure that MAPLHGR does not exceed 90% during the execution of the subject pmcedures. All pertinent surveillance procedures have been revised to ensure MAPLHGR has been reduced to 90% or below prior to their execution.
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l AVERAGE DAILY POWER LEVEL NET MWe l
OGCNET #........... 50 218 UNIT......... SYSTER CREEK #1 REPORT DATE........ Il8I95 COMPILED BY........ PAUL G. EDELMANN TELEPHONE #...... 808 9714097 MONTH: DECEMBER,1984 I
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509 8.
0 21, 838 7.
0 22.
838 8.
0 23.
842 8.
0 24.
840 10.
0 25.
840 11.
0 28.
840 12.
0 27.
840 13.
0 28.
839 14.
0 29.
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Oyster Creek Station #1 Decket No. 50 219 REFUELING INFORMATION DECEM8ER,1994 Name of Facility: Syster Creek Station #1 Scheduled dets for next refueling shutdown.
September,1998 Scheduled date for restart following refueling Currently projected for November,1996 Will refueling er resumption of operation thereafter require a Technical Specification change er other license amendment?
[
No important licensing considerations asseclated with refueling, e.g., new or different fuel design er 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.
The number of fuel assemblies (a) in the core 560 i
(b) in the spent fuel storage peel
- 2048 I
(c) in dry storage 24 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 Licensed Capacity: 2000 Planned increase in Licensed Storage Capacity: 45 The actual fuel storage capacity of the spent fuel peel is 2845 assemblies.
The projected date of the last refueling that can be dinherged to the spent fuel pool assuming the present licensed capacity:
Full core discharge capacity to the spent fuel pool was lost after the 1994 refueling outage.
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OPERATING DATA REPORT OPERATING STATUS I
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- 1. 00Cuti:
50219
- 2. REPORTINGPEWOD:
Dec-M
- 3. UTILITY C0K( ACT:
PaulG.Edelmenn (80919714097
- 4. LICENSED THERMAL POWER NWO:
1930 E. NAMEPLATERATING(GROS $MWel:
687.5 0.8 - 550
- 6. DES 10N ELECTWCAL RATlW4 WET MWel:
650
- 7. MAXIMuld DEPENDABLE CAPACITY IBROSS MWel:
641
- 8. MAXIMUtd DEPENDABLE CAPACITY WET MWel:
619 S. IF CHANGES OCCUR A80VE SINCE LAST REPORT,GIVE REASONS:
.VJC increased due to twbine upgrade.
- 18. POWER LEVEL TO WHICH RESTRICTED.lf ANY WET MWel:
NONE
- 11. REASON FOR RESTMCTION,IF ANY:
NONE MONTH YEAR CUMULATIVE
- 12. REPORT PERIGO HOURS 744.0 8760.0 219360.0
- 13. HOURS RX CRITICAL 425.7 6201.7 145800.7
- 14. RX RESERVE SHUTD0WN HRS 0.0 0.0 918.2
- 15. lNIS SENERATOR ON LINE 380.0 6097.4 14229J.1
- 16. UT RESERVE SHTDWN HR$
0.0 0.0 0.0 j
- 17. GROSS THERM ENERGY WWit 625075 11410327 244523704
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- 18. GROSS ELEC ENERGY WWie 210475 3781977 82026291
- 19. NET ELEC ENERGY NWit 200103 3627373 78675087
- 28. UT SERVICE FACTOR 51.1 69.6 64.9
- 21. UT AVAll F ACTOR 51.1 69.6 64.9
- 24. UT FORCED 0UTAGE RATE 0.0 5.2 10.3
- 25. FORCED OUTAGE HR$
0.0 332.5 16289.8
- 26. SHUTDOWNS SCHEDULED 0VER NEXT $ MONTHS (TYPE.DATE.DURATl0N):
NONE
- 27. IF CUlulENTLY $NUTDOWN ESE2ATED STARTUP DATE:
N/A
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