ML20070F208
| ML20070F208 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/30/1994 |
| From: | J. J. Barton, Edelman P GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-94-2112, NUDOCS 9407180222 | |
| Download: ML20070F208 (7) | |
Text
'.
~. *.
r GPU Nuclear Corporation Nuclear
- e;;;388 o
Forked River. New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
July 13,1994 C321-94-2112 U.S. Nuclear Regulatory Coinmission ATrN: Document Control Desk Washington, D.C. 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Repon - June,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 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.
crel. M J. 3,rton 7 ce President and Director Oyster Creek JJB/BDEM: jc i
Attachment (MOR-RPT. JUNE) cc:
Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager 94071e0222 940630 PDR ADOCK 05000219 R
PDR GPU Nuclear Corporation is a subscary of General Pubic Utihties Corporabon 7,
7, p,
kun vud V
SUMMARY
JUNE, 1994 Oyster Creek entered June shutdown following a reactor scram from full power on May 31 at 1332 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.06826e-4 months <br />.
The automatic reactor scran occurred on a turbine-generator trip due to JCP&L work in the switchyard which inadvertently actuated a generator protective relay. Reactor start-up began on June 1 at 2020, and the generator went on line at 0829 on June 2. There were six days during the month when reactor power was reduced due to canal temperature limits ( discharge temperature cannot exceed 106 F). The plant ended the reporting period operating at full power.
The plant generated 409,649 net megawatt-hours electric and attained a MDC net capacity factor of 93.3% for the month.
l l
l
=.
- c
~
MONTHLY OPERATING REPORT LICENSEE EVENT REPORTS The following Licensee Event Reports were submitted during the month of June,1994:
LER 94-005 - VOLUNTARY On March 8,1994, during an inspection it was discovered that the Turbine Building overhead 150 ton crane main hoist motor to gear box flex coupling exhibited casting defects and a through wall hole. On May 6,1994, during an inspection it was discovered that the Reactor Building overhead 100 ton crane main hoist motor to gear box flex coupling exhibited casting defects and a crack. GPUN decided to voluntarily report these conditions. The main hoist motor to gear box flex couplings have been installed on the overhead cranes since initial plant startup. The flex couplings are scheduled to be sent to the laboratory for failure analysis. A supplement to this mport will be issued after the failure analysis is completed.
Since the overhead crane meets NUREG-0612 requirements and no historical record of failure exists for the flex coupling, this condition is considered to have low safety significance. The main hoist motor to gear box flex couplings are being replaced on both overhead cranes.
LER 94-006 A technical specification required plant shutdown commenced on May 22,1994 at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> when both Control Rod Drive (CRD) Pumps were found to be inoperable during surveillance testing. The plant was placed in cold shutdown at 0639 hours0.0074 days <br />0.178 hours <br />0.00106 weeks <br />2.431395e-4 months <br /> on May 23,1994. The single discharge stop check valve on CRD pump "B" would not close. This resulted in both pumps failing their operability test.
Valve failure was determined to be valve body erosion which allowed the disc to become lodged between a groove in the body and the valve seat. The safety significance was minimal. The corrective action taken was to replace the stop check valve on CRD pump "B" with separate check and globe valves. Performance of the new valve configuration will be evaluated during the mn cycle.
LER 94-007 A mactor scram occurred due to modification work in the <witchyard on May 31,1994 at 1332 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.06826e-4 months <br />.
While loosening a wire connected to an auxiliary relay of the 230 KV bus section differential relay, to install a Digital Fault Recorder, the relay actuated causing a generator and turbine trip resulting in a reactor scram. All five Recirculation Pumps tripped, two Electromatic Relief Valves opened and both Isolation Condensers initiated. All systems responded to the scram as expected and therefore, there was no safety significance to this event. The plant was placed in cold shutdown at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br /> on May 31. Corrective actions included placing the modification on hold pending engineering review and strengthening procedural controls over switchyard work.
-. ~
l Oyster Creek Station #1 Docket No. 50-219 REFUFLING INFORMATION - JUNE, 1994 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown:
Currently projected for September 10, 1994 Scheduled date for restart following refueling: Currently projected for November 14, 1994 Will refueling or resumption of operation thereafter 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 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
=
(b) in the spent fuel storage pool 2040
=
(c) in dry storage 32
=
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:
f Present Licensed capacity:
2600 Planned Increase in Licensed Storage Capacity:
45 l
i The actual fuel storage capacity of the spent fuel pool is 2645 assemblies.
l The projected date of the last refueling that can be discharged to the spent fuel I
pool assuming the present licensed capacity:
i i
Based on a projected reload of 172 bundles, full core discharge capacity f
to the spent fuel pool will be lost after the 1994 refueling outage.
NRC_RPT.WPD/126 1
i I
,.s t
AVERAGE DAILY POWER LEVEL-l f
NET MWe DOCKET #.
........50-219 I
f OYSTER CREEK #1 UNIT.
07-08-94 REPORT DATE.
. PAUL G.
EDELMANN l
COMPILED BY
.609-971-4097
^
TELEPHONE #...
1 l
l i
k MONTH:
JUNE, 1994
-l t
DAY Fid DAY M
j 1.
0 16.
600 i
?
2.
264 17.
605 3.
609 18.
601 l
l 4.
609 19.
599 j
i 5.
607 20.
601 i
6.
604 21.
595 I
l 7
606 22.
602 8.
609 23.
601 9.
609 24.
597 l
10.
609 25.
580 l
r 11.
607 26.
592 12.
602 27.
591 I
13.
600 28.
598 l
14.
591 29.
597 15.
593 30.
599 l
1 i
l l
NRC_RPT.WPD/127
- f..*
OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
6/94 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 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:
6 NONE MONTH YEAR CUMULATIVE
- 12. REPORT PERIOD HOURS 720.0 4343.0 214943.0
- 13. HOURS RX CRITICAL 696.5 4064.0 143663.0
{
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 687.5 4010.6 140212.3 1
- 17. GROSS THERM ENERGY (MWH) 1314468 7576744 240690121
- 18. GROSS ELEC ENERGY (MWH) 426263 2532103 80776417
- 19. NET ELEC ENERGY (MWH) 409649 2435649 77483363
- 20. UT SERVICE FACTOR 95.5 92.3 65.2
- 21. UT AVAIL FACTOR 95.5 92.3 65.2
- 24. UT FORCED OUTAGE RATE 4.5 7.7 10.4
- 25. FORCED OUTAGE HRS 32.5 332.5 16289.8 j
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION) :
15-R OUTAGE, SEPTEMBER 10, 1994, 65 DAYS j
i
- 27. IF CURRENTLY SHUTDOW!i, ESTIMATED STARTUP DATE:
NRC_RPT.WPD/128
a
- *e 1.' TIT SFJTXN'NS AND PCwER REDUCTIONS DOCKET NO:
50-219 UNIT NAMER Oyster Creek DATE:
Julv C5. 1994 COMPLT*D BT:
David M Ezan IELEPHONE:
971-4918 REPORT MONTH:
June 1994 TYPE METHOD OF SHUTTING CORRECTIVE No.
DATE F: Forced DI* RATION REASON (1)
ECWN THE REACTOR OR ACTIONS / COMMENTS St Scheduled (hours)
REDUCINO POWER (2) 5 940531 F
32.5 a
3 Automatic Reactor SCRAM en turbine-generater trip due to JCPLL work in switchyard inadve rt ently actuating a generator protective relay.
SUMMARY
(1) REASON (2) METHOD a.
Equipment Failure (Explain) e.
Operator Training L Lie 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)