ML20058Q203
| ML20058Q203 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/31/1990 |
| From: | Baran R, Fitzpatrick E, Sharma H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9008210153 | |
| Download: ML20058Q203 (8) | |
Text
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OpU Nuclear Corporation I
ou e ou h Forked River, New Jersey 08781-0388 609 971-4000 Wrtter's Direct Dia! Nurnber; 1
August-15, 1990 l
U.S._ Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C.
20555
Dear Sir:
1 Subjects Oyster Creek Nuclear Generating Station 4
l 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 int %rmation) for the Oyster Creek Nuclear Generating Station.
l If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
very truly yours, E. E. Fitzpatrick l
Vice President and Director Oyster Creek
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EEF:BDEM:jc (MOR)
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Enclosures l
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cc Mr. Thomas Martin, Administrator i
. Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 l
Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station 9008210153 900731 PDR ADOCK 05000219
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R PDC
. GPU Nuclear Corporation is a subsidiary of General Public Utilrbes Corporation gQp
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e MONTHLY OPERATING REPORT - JULY 1990 On June 25th, a reactor scram occurred due to a low condenser vacuum condition caused by a tripped condenser backwash outlet valve. The plant remained shutdown for maintenance until a reactor startup on July 4th.
The plant reached full power on July 6th.
On July 17th, a load reduction was required to clean the turbine building closed cooling water heat exchangers.
Both heat exchangers were matted with sea (eel) grass. The plant returned to full power on July 19th.
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MONTHLY OPERATING REPORT JULY. 1990 The following Licensee Event Report was submitted during the month of July, 1990:
LER 90-07:
Individual Components Exceed TS Max Test Interval Due to Personnel Error On June 14, 1990 during the performance of an Internal Quality Assurance Audit it was discovered that numerous fire detection instruments were exceeding their maximum allowable interval for thw six month operability test as required by Plant Technical Specifications.
The cause of this occurrence is attributed to personnel error due to a procedure deficiency. The procedure that specifies the methods of scheduling failed to recognize that the time it takes to complete the entire surveillanco (four to six weeks) could cause individual components to exceed the maximum test interval required by Technical Specifications.
The procedure that specifies the method of scheduling surveillance tests will be changed to ensure all test intwrval requirements are met and appropriate schedules will be modified.
LER 90-08:
Reactor Scram on Low Condenser Vacuum During Initiation of Condenser Backwashing on June 25, 1990, at approximately 6:18 AM, a reactor scram occurred on low condenser vacuum. The scram occurred during initiation of backwashing of the A north main condenser. The scram was caused by the failure of the backwash outlet valve to open, causing a loss of circulating water to the A condenser.
The backwash outlet valve f ailed to open due to a breaker trip of the motor operator. The plant was stabilized in a hot standby condition and subsequently taken to cold shutdown.
The motor operator, the breaker and the valve were all inspected and tested satisfactorily.
The auxiliary contacts on the motor close coil were replaced and auxiliary contacts on the motor open coil were realigned. The remainirig 20 circulating water valves manipulated during backwashing evolutions were tested and verified to be operating properly.
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,o OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219 l
2.
REPORTING PERIOD:
07/90 3.
UTILITY CONTACT:-
HARI S. SHARMA 609-971-4638 4.
LICENSED THERMAL POWER (MWs):
1930 5.
NAMEPLATE RATING (Gross MWe):
687.5 X 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET MWJ):
650 7.
MAXIMUM DEPENDABLE CAPACITY (Gross MWe):
642 8.
MAXIM?M 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 HRS 744.0 5087.0 180623.0
- 13. HOURS RX CRITICAL 665.8 4131.6
'115392.2
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2 f
- 15. HRS GENERATOR ON-LINE 649.9 4006.2
'112240.0
- 17. GROSS THERM ENER (MWH) 1206341 7046461 188319520
- 18. GROSS ELEC ENER (MWH) 391040 2322650
-6344C20
- 19. NET ELEC ENER (MWH) 375408 2227078 50882056
- 20. UT SERVICE FACTOR 87.3 78.8 62.1
- 21. UT AVAIL FACTOR 87.3 78.8 62.8
- 24. UT FORCED OUTAGE RATE-12.6 17.7 12.0
- 25. FORCED OUTAGE HRS 94.1 859.9 15270.0
- 26. SHUTDOWNS SCHEDULED OVER NEXT SIX (6) MONTHS (TYPE, DATE, DURATION):
Refueling Outage 13R commencing January 11, 1991, scheduled to end j
l-May 19, 1991
- 27. IF CURRENTLY SHUTDOWN ESTIMATED STARTUP DATE:
N/A l-o
____y AVERAGE DAILY POWatR LEVEL NET HWe DOCKET /.
.50219 UNIT.
. OYSTER CRtEK #1 REPORT DATE.
. AUGUST 2, 1990 COMPILED BY.
.HARI S. SHARMA TELEPHONE #..
.609-971-4638 HONTH JULY, 1990 D&1 E
DAI E
1.
0 17.
593 2.
0 18.
469 3.
0 19.
595 4.
3 20.
586 5.
403 21.
588 6.
558 22.
579 7.
606 23.
596 8.
603 24.
589 9.
602 25.
577 10.
578 26.
600 11.
587 27.
601 l
12.
561 28.
603 13.
618 29.
606 14.
618 30.
604 15.
613 31.
517 16.
611 1
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-1619B/31
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4 Oyster Creek Stction #1 Docket No. 50-219 REFUELING INFORMATION - JULY, 1990 Name of Facility:
Dyster Creek Station #1 Scheduled date for next refueling shutdown: January 11, 1991 pending necessary state approval.
Scheduled date for restart following refueling: May 19, 1991 Will refueling or resumption of operation thereafter require a Technical Specification change or other license smendment?
Yes Technical Specification Change Request 180 was submitted to the URC on 5-07-90.
This submittal was made in accordance with GL 88-16 to incorporate cycle specific parameters in a core operating limits report.
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 1595
=
(c) in dry storage 37
=
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 o 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:
Roracking of the fuel pool is in progress.
Nine-(9) out of ten (10) racks have been installed to date.
When raracking is completed, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.
' 1619B/30 1
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.o; UNIT SHUTDONNS AND POWER REDUCTIONS DOCKET.NO.
50-229 UNIT MAIEE Oyster Creek DATE Amaust.'1990
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COse*IETED BY R. Saran l
T"TJtPEONE 971-4640 REPORT MONTE July. 1990 TYPE METHOD OF THIUTTI3fG F: Forced DURATION DONN THE REACTOR'OR-NO. -
DATE
,S: Scheduled (Hours)
REASON (1)
REDUCING POWER (2)
CORRECTIVE ACTIONS /COOSEENTS 103 6/25 F
~94.1' A
3
. comatic full scram due to main condenser low vacuum.- Iow vacuum caused by a loss of circulating.
water when backwash valve V-3-18' failed to open during condenser I
backwashing.
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104 7/11 F
0 H
1 Load reduction tol387 HNe (gross)'
due to heavy.seagrass conditions at the intake canal.
105 7/17 F
0 H
1 Load reduction to Olean both TBCCN I
Heat Exchangers (407 MWe Cross).
.1 106 7/22 F
0 H
1
,D.sd reduction required to backwash j
a.3 e W onsors (438 BENE Gross) 107 7/24 F
"O E
1 Load reduction required to backwash
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main condensers (474 BENE Gross),
i Summary':
^
l (1) REASON
. -s m i a.
Equipment Failure (Explain) e.
Operator Training & License Exam 1.
Manual b.-
Maint= nance or Test f.
Administrative 2.~
c.
Refueling g.
Operational Error-(Explain) 3.
Regulatory Restriction h.
Other (Explain) 4..
Other (Explain)
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