ML20096E807
| ML20096E807 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1995 |
| From: | Edelmann P, Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 6730-96-2012, NUDOCS 9601230039 | |
| Download: ML20096E807 (7) | |
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GPU Nuclear Corporation Qggf Post Office Box 388 Route 9 South Forked River. New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:
January 15, 1996 6730-96-2012 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report - December,1995 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 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.
Sincerely, h.
Michael B. Roche Vice President and Director Oyster Creek MBR/BDe i
Attachment l
cc:
Administrator, Region 1 Senior NRC Resident inspector Oyster Creek NRC Project Manager 9601230039 951231 PDR ADOCK 05000219 R
PDR l
k GPU Nuclear Corporation is a subsidiary of General Pubhc Uhhties Corporation
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SUMMARY
DECEMBER,1995 Oyster Creek entered December operating at full power. On December 18 at 0437, the reactor automatically shut down due to high reactor pressure. The root cause of the event was the generator stator cooling heat exchanger discharge temperature control valve, Y-07, which failed causing a high temperature in the stator. The high stator temperature activated a generator protection relay which caused turbine runback (forced the Turbine Control Valves closed). With the Control Valves closing beyond the capacity of the Turbine Bypass Valves, pressure increased in the reactor causing a scram.
The forced outage window was used to perform secondary plant maintenance in addition to repairing Y-07. The plant was placed back on line at 1300 on December 28, but was operated at 98% power for the remainder of the month because the second stage reheaters had to be left out of service due to failure of Auxiliary Flash Tank level control valve, V-4-103.
The plant generated 307,964 MWh net electric which was 66.9% ofits MDC rated capacity for the month.
Oyster Creek generated 5,194,098 MWh net electric which was 95.8% ofits MDC rated capacity for 1995.
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MONTIILY OPERATING REPORT LICENSEE EVENT REPORTS No LER's were submitted during the month of December 1995.
1
t AVERAGE DAILY POWER LEVEL NET MWe DOCKET #..........
50-219 UNIT............. Oyster Creek #1 REPORT DATE........
1/2/96 COMPILED BY.........
Paul G. Edelmann TELEPHONE #.........
(609) 971-4097 j
Month: December,1995 DAY MW DAY MW 1
637 16 636 2
638 17 640 3
638 18 118 4
636 19 0
5 637 20 0
6 638 21 0
7 638 22 0
8 639 23 0
9 639 24 0
10 639 25 0
11 636 26 0
12 637 27 0
13 637 28 99 14 635 29 575 15 640 30 627 31 633
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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - DECEMBER,1995 i
Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:
September,1996 Scheduled date for restart following refueling: Currently projected for November,1996 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
L 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 operating procedures:
- 1. General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by the NRC.
= 560 The number of fuel assemblies (a) in the core (b) in the spent fuel storage pool = 2048 (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: 2645 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.
(p: Woes-96 3414-96cpdata.corupon:1)
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OPERATIN2 DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTWO PERIOD:
Dw -95 3.
UTILITY CONTACT:
Paul G. Edelmann (609) 971-4097 4.
LICENSED THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (GROSS MWe):
687.5 x 0.8 = 550 S.
DESIGN ELECTRICAL RATING (NET MWo):
650 7.
MAXIMUM DEPENDASLE CAPACITY (GROSS MWe):
641 S.
MAXIMUM DEPENDASLE CAPACITY (NET MWe):
619 9.
IF CHANGES OCCUR ASOVE SWCE LAST REPORT, GIVE REASONS:
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED,IF ANY (NET MWe):
NONE
- 11. REASON FOR RESTRICTION,IF ANY:
NONE i
MONTH YEAR CUMULATIVE
- 12. REPORT PERIOD HOURS 744.0 8760.0 228120.0
- 13. HOURS RX CRITICAL 516.2 8532.2 154332.9
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON LINE 495.6 8511.6 150810.7
- 17. GROSS THERM ENERGY (MWH) 941198 15995790 260519493
- 18. GROSS ELEC ENERGY (MWH) 321478 5391284 87417575
- 19. NET ELEC ENERGY (MWH) 307964 5194078 83869165
- 20. UT SERVICE FACTOR 66.6 97.2 66.1
- 21. UT AVAIL FACTOR 66.6 97.2 66.1
- 23. UT FORCED OUTAGE RATE 33.4 2.8 9.9
- 25. FORCED OUTAGE HRS 248.4 248.4 16538.2
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,DATE, DURATION):
MAINTENANCE OUTAGE SCHEDULED TO BEGIN JANUARY 5,1996 AT 2100, TO LAST APPROX. 2 DAYS.
- 27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP DATE:
N/A
?
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-219 UNIT NAME:
Ovster Creek DATE:
Januarv 09, 1996 COMPLT'D BY:
David M.
Ecan TELEPHONE:
971-4818 REPORT MONTH:
December 1995 TYPE METHOD OF COPJtECTIVE No.
DATE F: Forced DURATION REASON (1)
SHUTTING DOWN ACTIONS /COtetENTS S: Scheduled (hours)
THE REACTOR OR REDUCING POWER (2)
The reactor 9
12/18/95 F
248.4 a
3 automatically shut down on high reactor pressure caused by turbine runback. The turbine runback was caused by failure of Y-07, stator coolant heat exchanger discharge temperature control valve, causing a high generator stator temperature and activating generator protection.
SUMMARY
(1) REASON (2)
METHQD a.
Equipment Failure (Explain) e.
Operator Training & Lic Exam 1.
Manual b.
Maintenance or Test f.
Administrative 2.
Manual Scram c.
Refueling g.
Operational Error (Explain) 3.
Regulatory Restriction h.
Other (Explain) 4.
Other (Explain) e e q' e
m
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