ML20059G302
| ML20059G302 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1993 |
| From: | J. J. Barton, Egan D, Krall J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-94-2006, NUDOCS 9401240092 | |
| Download: ML20059G302 (8) | |
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ENuclear
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Route 9 South -
Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
C321-94-2006 i
January 14, 1994 U.S. Nuclear Regulatory Cammission ATrN: Document Contmi Desk Washington, D.C. 20555 t
3
Dear Sir:
Subject:
Oyster Creek Nuclear Genemting Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Cmek Nuclear Generating Station Openting 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, t
S h
J.J. Barto g
Vice Pmsident and Director Oyster Creek JJB/BDEM: jc Attachment (MOR RPT.DEC) cc:
Administrator, Region 1-Senior NRC Resident Inspector Oyster Creek NRC Troject Manager i
9401240092 931231 0
/ 1 (DR ADOCK 05000219 N I
PDR T
d4 0006 oeu uuciee, Corno,etior s e subsio,ary at eeneral Pubhc Utihties Corporation i
Monthly Operating ReDort December 1993 j
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Oyster Creek entered December operating at full power.
The ~ plant maintained full power operation throughout the month and generated 466,161 net electric megawatt hours during the month. Oyster Creek i
achieved a unit capacity factor (MDC NET) of 87.3 for the year' generating 4,664,090 net electric megawatt hours for 1993.
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MQ,NTHLY OPERATING REPQ_R_T f
LICENSEE EVENT REPORTS 5
The following Licensee Event Reports were submitted during the month of December,1993:
h IZR 90-005RU t
On April 21,1990 at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br />, power was lost to Unit Substation (USS) IB2 when a pc.wr supply cable shorted to ground. Several safety related components were affected by the loss of power, and drywell unidentified leak rate increased to gicater than 5 gpm due to l
loss of power to the Drywell Equipment Drain Tank Pump Contml Circuit. The plant was
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shutdown due to loss-of-power to required electrical busses, and on April 22nd at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />, the reactor reached cold shutdown. USS IB2 was isolated from the failed supply cable and reenergized from USS 1 A2 via the crossconnect breaker. During the cooldown, i
the A isolation condenser was declared inopemble due to the inability to electrically cycle a DC isolation valve because of thennal binding. This thennal binding problem was corrected by modifications completed during the 13R refueling outage. The cause of the cable failure was detennined to be a " void'in the insulation of the cable. A new supply cable was installed and the USS was repowered from it's nonnat source. A representative sample of other cables supplying safety related components were tested, and no generic concerns were found. On March 22,1991, the I A2 cable failed during the 13R outage. There appears to be no connection between the failures of these two cables.
LER 93-004R1 The Updated Final Safety Analysis Report, Section 6.2.3.2, describes blow out panels in the Reactor Building which would relieve Reactor Building internal pressure at a pressure of i
0.25 psig. During the perfonnance of a recent engineering evaluation, the blow out panels could not be located either by document review or inspection of the visible section of the 1
Reactor Building. Initially, a preliminary calculation indicater' dat Reactor Building internal pressure would reach 0.95 psig during a high energy line break outside of containment. This resulted in four areas of concern: 1) damage to the torus; 2) failure of internal masonry block walls adjacent to the southeast corner room; 3) Reactor Building structumi damage; and 4) Equipment Qualification profiles, j
A final calculation has demonstrated that the Reactoc Building siding will relieve pressure at O.20 psig. Therefore, the four previous potential concems were eliminated and this discovery has been detennined to be not reportable. The cause of this event was inadequate documentation. The UFSAR and any other affected document will be revised to include the results of the recent evaluation.
I a
MONTIILY OPERATING REPORT LICENSEE EVENT REPORTS DECEMBER.1993 (CONTINUED)
LER ')3-007 On November 17,1993 while the plant was in the RUN mode, it was discovered that the Average Power Range Monitor (APRM) system flux scram was not being tested with simulated recirculation flows greater than 100%. This condition has existed since initial plant operation and had resuhed from a misunderstanding of the Technical Specification requirements. The existing surveillance procedure required testing the flux scram setpoint with simualted Hows of 50% and maximum operating flow of 100%, but did not require testing flux scram setpoints with simualted flows greater than 100%.
Immediate corrective action was taken to surveil the flux scram setpoint with simulated recirculation flow greater than 100%. Seven of the eight APRM channels tested after the 3
discovery of the omission were found to be within Technical Specincation limits. The safety signincance of this event is considered minimal as: 1) controls specify the upper range of-6 recire Dow to be 61 x 10 lbm/hr which is equal to 100% rated flow; and 2) seven of the eight channels were found in specification. A review of Technical Specification section 2.3 1
was conducted to verify that appropriate setpoints were being surveilled.
LER 93-008 On December 3.1993 at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, the reactor was operating at approximately 100 % power and Pmcedure 610.3,105, Core Spray System I Instrument Channel Calibration Test and System Operability Surveillance was in progress. I & C Technicians perfonning this test removed fuses from System 11 rendering it inopemble. When System I was tested, it inadvenently initiated. Reactor Pressure Vessel injection did not occur because the Core Spray System is designed to inject at pressures less than 350 psig. This event was caused by inattention to duty.
Core Spray System I was returned to operation. System II was returned to operation and i
operability was demonstrated. A critique was held and appmpriate personnel actione were taken with respect to the individuals involved. Corrective actions will be incorporated into the I & C Personnel training program.
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- oyster Creek station #1 Docket No. 50-219 2
l REFUELING INFORMATION - DECEMBER, 1993 I
I 5
Name of Facility:
Oyster Creek Station #1 Scheduled date.for next refueling shutdown:
Currently projected for September 10, 1994
- t Scheduled date for restart following refueling:
Currently projteted for November 14, 1994
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Will refueling or resumption of operation thereafter require a Technical specification change or other license amendment?
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i Important licensing censiderations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis-
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methods, significant changes in fuel design, new operating procedures:
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1.
General Electric Fuel Assemblies - Fuel design and-performance i
analysis methods have been approved by the NRC.
l The number of fuel assemblies (a) in the core 560
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(b) in the spent fuel storage' pool 1900
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(c) in dry storage
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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:
4 Present Licensed Capacity:
2600 l
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
l Full core discharge capacity to the spent fuel pool will be available-
- j through the 19'96 refueling outage.
i NRC_RPT.WPD/108 1
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AVERAGE DAILY POWER LEVEL 1
u NET MWe DOCKET #.
.50-219 UNIT.
. OYSTER CREEK #1 REPORT DATE,
. 01-05-94 COMPILED BY
. JIM KRALL i
TELEPHONE #.
.609-971-4115 i
I MONTH:
DECEMBER, 1993 1
f DA1 M
DAL M
i 1.
628 16.
624
'i 2.
629 17.
627-3.
628 18.
627
'l i
4.
628 19.
626-5.
627 20.
628
'l 6.
626 21.
624-7.
618 22.
626 f
8.
625 23.
628 t
9.
625 24.
628 10.
623 25.
627
-i 11.
624 26.
629 i
12.
627 27.
628
.i 13.
627 28.
629 i
14.
627 29.
629 15.
627 30.
629 31.
629
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NRC,RPT.WPD/109 P
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OPERATING DATA REPORT
' N OPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
32/93
- 3. UTILITY CONTACT JIM KRALL (609)971-4115 4
4.
LICENSED. THERMAL POWER (MWt):
1930 5.'HAMEPLATE RATING (CROSS MWe):
687.5 x 0.8 = 550
- 6. DESIGN ELECTRICAL RATING (NET MWe):
650
-7.
MAXIMUM DEPENDABLE CAPACITY (GROSS-MWe):
632
- 8. MAXIMUM DEPENDABLE CAPACITY (NET-MWe):
610 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS.
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
NONE
- 11. REASON FOR RESTRICTION, IF ANY:
NONE MONIH YEAR CUMULATIVE
- 12. REPORT PERIOD HOURS 744.0 8760.0 210600.0
- 13. HOURS RX CRITICAL
'/ 4 4. 0 7690.6 139599.0
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 744.0 7654.4 136201.7 5
- 17. GROSS THERM 3rEPGY (MWH)
~1433441 14604623 233113377
- 18. GROSS ELEC ENERCY (PMH) 483417 4848176 78244314 i
- 19. NET ELEC ENERGY (MWH) 466161 4664090 75047714
- 20. UT SERVICE FACTOR 100.0 87.4 64.7 1
- 21. UT AVAIL FACTOR 100.0 87.4 64.7 l
- 24. UT FORCED OUTAGE RATE 0.0 0.0 10.5 i
- 25. FORCED OUTAGE HRS 0.0 0.0 15957.3
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A i
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NRC_RPT.WPD/110 i
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