ML20086C451
| ML20086C451 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/31/1991 |
| From: | J. J. Barton, Bradley E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-91-2315, NUDOCS 9111220192 | |
| Download: ML20086C451 (7) | |
Text
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GPU Nuclear Corporation M. Nuclear
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Faked River, New Jersey 087310388 609 971-4000 Wnter's Direct D a! Number:
C321-91-2315 November 15, 1991 U.S. Nuclear Regulato-v nission ATTN: Document Cont Washington, D.C.
2-t e DeLr Sir:
Subj:.
Nuclear Generating Station Docket x-a :
Monthly Or In accordance with the Oyster Creek Nud,..w Generating Station O'perating 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 ha've any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
Sincerely
/
J.
arton Vi v) resident and Director ster Creek JJB/BDEM: Jc Attachment (MOR RPT)
Administrator, Region 1 cc:
Senior NRC Resident Inspector Oyster Creek NRC Project Manager 9111:201o2 911031
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FDR ADOCc: 05000:1v g
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GPU Nuclear Corporatton is a subsidiary of General Pubhc Ut6t.es Corpora 5on
l MONTHLY OPERATING REPORT - OCTOBER, 1991 At the beginning of October, Oyster Creek was operating at full power.
Beginning on October 20, a small, but persistent salt water leak on the "C" north condenser increased. Power was reduced to about 50%, and the condenser half was taken out of service. Power was further reduced on October 22 and the generator was taken off line for about two hours while a filter element in the stator cooling system was replaced.
The plant returned to full power on October 23.
On October 30, power was reduced in response to high tides associated with a large Atlantic storm. On October 31, a reactor building to torus vacuum breaker failed its surveillance test.
Due to previous problems with this valve, an immediate reactor shutdown commenced. The plant reached a shutdown condition on November 1.
l
MONTHLY OPERATING REPORT - OCTOBER 1991 The following Licensee Event Reports were submitted during the month of October 1991.
LER 91-006 On September 24, 1991, a routine calibration of the pipe break sensors was performed on Isolation Condenser Systems I and 2.
During the surveillance for each instrument, a check revealed a degradation in the flow dampening snubber performance for seven of the eight - sensors when - compared to the ' procedure criteria.
The flow dampening snubbers were removed and tested.
Based upon limited testing of the removed snubbers and an extrapolation of the test results, the pipe break sensors would have experienced a delay in response time such that the design basis isolation valve closure time of sixty seconds would not have been met for all postulated pipe break events. The cause of this occurrence has been attributed to inadequate design control. During the recent 13R refueling outage, the existing snubbers were replaced with a different manufacturer and type snubber without performing an evaluation to assess the impact on the sensor response time.
Corrective action consisted of removing the snubbers from the eight pipe break sensors.
Additional corrective action will consist of performing a review of other applications where snubber fittings are used on critical plant instrumentation to ensure appropriate use and proper design documentation.
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l Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - OCTOBER, 1991 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: November 27, 1992 Scheduled date for restart following refueling:
February 9, 1993 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.
2.
Exxon Fuel Assemblies - No major 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 storage 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 discharged to the spent fuel pool assuming the present licensed capacity:
Full core diacharge capacity to the spent fuel pool will be available through the 1996 refueling outage.
NRC_RPT.WPD/29
l AVERAGE DAILY POWER LEVEL NET MWe DOCKET #.
.50-219 UNIT.
OYSTER CREEK #1 REPORT DATE.
NOVEMBER 4, 1991 COMPILED BY ED BRADLEY TELEPHONE #.
.609-971-4097 MONTH:
OCTOBER, 1991 D.AX M
DAY M
1.
611 16.
611 2.
609 17, 614 3.
610 18, 619 4,
609 19.
614 5.
607 20.
561 6.
607 21.
377 7.
614 22, 224 8.
619 23.
487 9.
628 24, 618 10.
617 25.
617 11.
565 26.
620 12.
595 27.
620 13.
614 28.
621 14.
617 29, 618 15.
612 30.
567 31.
366 NRC_RPT.WPD/30 4
OPERATING DATR REPORT OPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
10/91
- 3. UTILITY CONTACT:
ED BRADLEY (609)971-4097
- 4. LICENSED THERMAL POWER (HWt):
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):
642
- 8. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
620 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 745.0 7296.0 191592.0
- 13. HOURS RX CRITICAL 745.0 3909.8 122974.9
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2-
- 15. HRS GENERATOR ON-LINE 741.5 3816.0 119729.0
- 17. GROSS THERM ENERGY (MWH) 1353797.0 6788019.0 201682975.0
- 18. GROSS ELEC ENERGY (MWH) 446330 2214890 67820813
- 19. NET ELEC ENERGY (MWH) 429645 2114165 65074197
- 20. UT SERVICE FACTOR 99.5 52.3 62.5
- 21. UT AVAIL FACTOR 99.5 52.3 63.1
- 24. UT FORCED OUTAGE RATE O.0 7.5 11.5
- 25. FORCED OUTAGE HRS 0.0 310.0 15580.5
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A NRC_RPT.WPD/31
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-219 c
UNIT NAME:
Oyster Creek DATE:
Nov. 1991 COMPLT'D BY:
R. Baran TELEPHONE:
971-4640 REPORT MONTH:
Octob_er D 991 TYPE HETHOD OF SHUTTING DOWN CORRECTIVE ACTIONS l F: Forced DURATION THE REACTOR OR REDUCING COMMENTS No.
DATE S: Scheduled (Hours)
REASON (1)
POWER (2) 110 911020 F
0 B
1 Repair Tube leak in
'C' North Condenser ill 911022 S
3.5 B
1 Main Generator taken off the line to replace the Stator Cooling System 112 911031 F
0 B
1 Commenced shutdown to repair Reactor Bldg to Torus Vacuum Breaker V-26-18. Shutdown in progress at end of report period.
r I
j Summary :
(1) REASON (2) HETHOD 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)
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