ML20101E905
| ML20101E905 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/31/1992 |
| From: | J. J. Barton, Egan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-92-2162, NUDOCS 9206240161 | |
| Download: ML20101E905 (8) | |
Text
._ t s.
GPU Nuclear Corporation G' u Nuclear
- n:reee Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct D;al Number; June 11, 1992 C321-92-2162 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report 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,
/
d i
J.
.B arton V' e President and Director y
Creek JJB/BDEM: Jc Att.achment cc:
Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager r
I 9206240161 920531 q
/jy2 k PDR ADOCK 05000219 1
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PDR GPU Nuclear Corporahon is a subsdary of General Pubtc Utthties Corporatton
l MORTHLY OPERATING REPORT May. 1992 Oyster Creek entered May at full power, but almost immediately began a planned power reduction to 40% to perform the Main Steam Isolation Valve (MSIV) full closure surveillance. After completing the surveillance, the plant remained at reduced load to perform trunnion room recirculation fan preventive mair.tenance.
Full power was again achieved on 5/3/92.
At 1322 on 5/3/92, the plant automatically shutdown due to a rapid load rejection which occurred after off-site distribution breakers tripped.
This event was caused by forest fires in the area around the site. After completion of the post l
trip review on 5/6/92, the plant restarted and achieved full power two days L
later.
The plant maintained full power operation until 5/14/92 when a failed l
MSIV limit switch caused a trip of one division (of two divisions) in the reactor protective circuitry. Power was manually reduced until an alternate limit switch L
was utilized ano the trip signal was cleared.
l On 5/29/92, the. plant was manually shutdown for a maintenance outage to repair the 1-1 drywell recirculation fan.
Additional preventive and corrective maintenance was performed to enhance unit capability for the remainder of the current cycle.
l 8,
MONTHLY OPERATING REPORT MAY, 1992 The following Licensee Event Reports were submitted during the month of May, 1992.
LER 92-002 Diesel Generator 2 was out of service for greater than a seven-day period from March 23 to April 9, 1992.
The plant was operating at full power at the time.
The diesel generator failed to successfully complete its operability test at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> on March 23, 1992 but completed the test successfully later in the day.
The test failure was attributed to an auto synchronizer problem which would not have affected the diesel generator's emergency operation.
The diesel generator failed its next scheduled biweekly test on April 5,1992 at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />.
After an extensive evaluation, a broken component in the 4160 volt output breaker was discovered.
The breaker was replaced and Diesel Generator 2 was returned to service at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br /> on April 9, 1992.
The cause of the event was fatigue failure of the breaker's prop spring, which intermittently prevented the breaker from latching in the closed position.
Corrective actions included replacing the damaged breaker, inspecting and replacing the 4160 volt output breaker for Diesel Generator 1, and developing-a schedule for overhaul of other 4160 volt breakers.
This report will be made required reading for engineers normally involved in review of equipment operation for operability determinations.
Safety significance is minimal because the other diesel generator and its-associated engineered safety features remained operable while Diesel Generator 2 was out of service.
LER 92-003 On April 20, 1992 at approximately 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br />, the reactor was operating at approximately 100% power and Procedure 607.4.004, Containment Spray and Emergency Service Water System 1 Pump Operability and In-service Test was in progress.The operator performing the surveillance overlooked a portion of a step in the procedure to stop the Containment Spray pump and proceeded to next step which' positioned the system mode switch to the AUTO position, i;1is lines up the system valves for the Drywell Spray mode.
The operator recognized the error and secured the Containment Spray Pump within 29 seconds.
During this period approximately 825 gallons of Torus water entered the Drywell.
The cause of this occurrence is attributed to operator error.
A contributing cause to this event was the involved procedure step which contained several action statements. The Plant Transient Review Group (PTRG) was convened to determine the significance. The results of the review determined that all safety related functions would be unaffected by the event with the possible exception of the acoustic and thermocouple monitors associated with the main steam safety and electromatic relief valves. The PTRG recommended testing of these systems, which was started at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> and successfully completed at i
2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br />.
A critique was held, and appropriate personnel actions were taken with respect to the individual involved.
Procedural changes have also been made to separate the multiple action statements contained in the involved procedure step.
An ongoing procedure upgrade program includes a review of procedures for multiple action statements.
l l
LER 92-004 During a detailed review of the Reactor Recirculation System flow instrumentation, it was discovered that the testing methodology for the flow converter units associated with the Reactor Protection System resulted in the loss of high recirculation flow scram protection and non conservative settings for the flow biased APRM scram and rod block protection while surveillance testing was in progress.
The period of time the protection was lost was limited to approximately one minute per channel each time the test was conducted. This surveillance. test has been conducted durinn all modes of operation since initial plant operation.
This event is considered to have minimal safety significance due to the small amount of time that the protection was actually lost, because rod block protection is provided by either trip system, and because any reactor power increase due to actual recirculation flow increase would be limited by the fixed APRM High Flux trip at 115.7%.
Immediate corrective action was taken to eliminate testing of the flow converters by present methods. Additionally, the surveillance procedure is being rewritten to test the units without affecting the protective functions of the system.
t l
l l
Oyster Creek Station #1 Docket !J o.30-219 REFUELIllC If4 FORMATION - MAY, 1991 Name of Facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdown:
January 15, 1993 Scheduled date for restart following refueling:
March 30, 1993 Will refueling or resumption of operation thereafter require a Technical Specification change or other license aaendment?
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 teen approved by the 11RC.
2.
Exxon Fuel Assemblies - !;o rc.ajor 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 st.orage 44
=
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:
2600 The projected date of the last refueling that can be di scharged to the spent fuel pool assuming the present licensed capacity:
Full core discharge capacity tc the spent fuel pooi will be available through the 1996 retueiing outage.
NRC_RPT.WPD/51
A 6
AVERAGE DAILY POWER LEVEL 11ET MWe DOCKET #.
.50-219 UNIT.
OYSTEh CREEK #1 REPORT DATE.
JUNE 5, 1992 COMPILED BY ED ERADLEY TELEPHONE #.
.609-971-4097 MONTH:
MAY, 1492 DAY fj'd DAY MW 1.
601 16.
600 2.
427 17.
624 3.
337 623 4.
0 19, 621 5.
O 20.
623 6.
0 21 622 7.
305 22.
608 8.
579 23.
612 9.
625 24.
604 10.
625 25, 611 11.
626 46.
619 12.
626 27 619 13.
626 ab.
618 14.
271 29.
547 15.
292 30.
0 31.
O NRC_RPT.WPD/52
OPERATING DATA REPORT OPERATING STATUS
- 1. DOCKET:
50-219 2.
REPORTING PERIOD:
05/92
- 3. UTILITY CONTACT:
ED BRADLEY (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:
NONE MONTH YEAR CUMULATIVE
- 12. REPORT PERIOD HOURS 744.0 3647.0 196703.0
- 13. HOURS RX CRITICAL 625.6 3528.6 127891.2
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 610.6 3513.6 124595.9
- 18. GROSS ELEC ENERGY (MWH) 361395 2236723 70922353
- 19. NET ELEC ENERGY (MWH) 346984 2154166 68060854
- 20. UT SERVICE FACTOR 82.1 96.3 63.3
- 21. UT AVAIL FACTOR 62.1 96.3 64.0
-22. UT CAP Fl.CTOR (MDC NET) 76.5 96.6 55.9
53.2
- 24. UT FORCED OUTAGE RATE 12.3 2.4 11.2
- 25. FORCED OUTAGE HRS 85.8 85.5 15777.0
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
06-06-92 NRC_RPT.WPD/53
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