ML20245F266
| ML20245F266 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/31/1989 |
| From: | Fitzpatrick E, Sharma H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8906280076 | |
| Download: ML20245F266 (7) | |
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D GPU Nuclear Corporation j
, Nuclear
- ==388 Forked River.New Jersey 08731-0388 i
609 971-4000 Writer's Direct Dial Number:
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 Katty Barnes, Oyster t
Creek Licensing at (609) 971-4390.
truly yoursy e
8 Fitzpatrick ice President and Director Oyster Creek EEF:KB:dmd (0841 A:1 )
Enclosures i
cc:
Director Office of Inspection and Enforcement u
U.S. Nuclear Regulatory Commission l
Washington, DC 20555 Mr. Williain T. Russell, Administrator m,y Region I U.S. Nuclear Regulatory Commission J
475 Allendale Avenue gga.
King of Prussia, PA 19406 C0 gg Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Washington, DC 20555 88 g<
NRC Resident Inspect]r pY
,o Oyster Creek Nuclear Generating Station t
a:
I GPU Nuclear Corporation is a subsidiary of the General Pubhc Utikties Corporation
MONTHLY OPERATING REPORT - MAY 1989 At the beginning of the report period, Oyster creek was shut down for the Cycle 12 Refueling Outage.
During startup on May 8, a torque switch on an isolation condenser isolation valve failed while the valve was cycled periodically during heatup, which resulted in a plant shutdown.
Following repair, reactor startup commenced on May 9.
The generator was l
placed on-line May 11 and full power was achieved on May 17.
On May 18, wnile at full power, a generator trip occurred leading oto a reactor scram and actuation of the isolation condensers.
The turbine / generator output breakers opened due to an over-excitation of the main generator while maintenance was being performed on control room instrumentation.
Following completion of root cause analysis of the plant trip and evaluation of the plant ;ondition, reactor startup commenced on May 21.
The generator was placed on-line May 22 and full power was achieved on May 24.
Maximum generator load was maintained for the balance of the report l
period except for brief power reductions to facilitate a control
~
rod pattern change and to support turbine valve testing.
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MONTHLY OPERATING REPORTLMAY 1989 The following Licensee Event Reports were submitted during the month of May
'1989:
LER 89-011: Manual' Scram-Due to Low Vacuum Condition Caused by' Operator Error During Planned Shutdown On Aprf1 '22,1989 at _1850 hours,' the mechanical vacuum pump was placed into service.in order to maintain condenser vacuum during a planned shutdown evolution. The equipment operator who placed the vacuum pump into' service failed to' properly align the seal water makeup supply. At 1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br /> a -
gradual decrease in the main condenser vacuum was noted. The rate'of decrease in condenser vacuum prevented any significant attempts to correct the problem i-so the Group Shift Supervisor directed the operators' to manually scram the reactor at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />.
The cause of this occurrence is_ attributed to operator error. The operator failed.to establish a complete valve lineup to the seal:
water makeup supply in accordance with the operating procedure.
Starting the mechanical vacuum pump is a simple evolution but infrequently performed by individual operetors.
Operators are not' required to have a procedure in. hand' when performing a simple or routine evolution. This contributed to the oversight by the operator.
Without seal water makeup the mechanical vacuum pump operated properly until the seal water tank emptied which then caused a significant air leak to the main condensers.
This caused the decrease in condenser vacuum which resulted in the reactor scram. The safety significance of this event is minimal because the reactor was at low power _(approximately 2%) when the event occurred. To prevent a.similar occurrence in the. future, other: infrequently performed evolutions that currently do not require a procedure in hand will be reviewed to determine if further ~ guidance' is
- warranted.
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'0PERATING DATA REPORT y,,
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. OPERATING STATUS.
y o
d E
(1. DOCKET:
50-219'
~
- 2.. REPORTING PERIOD: 05/89 3.
UTILITY CONTACT:
HARI S. SHARMA 609-971-4638 7
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):
642 g>
8.-
MAXI W M DEPENDABLE CAPACITY (NET MWe):
620 9.' IF CHANGES OCCUR AB0VE SINCE LAST. REPORT, GIVE REASONS:
NONE-
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):. NONE-r
- 11. REASON.FOR RESTRICTION, IF.ANY:
NONE MONTH
' YEAR' CUMJLATIVE 12.'
REPORT PERIOD HRS 744.0 3623.0 170399.0
+ 13. HOURS RX CRITICAL 472.6 556.6 106802.0
- 14.. RX RESERVE SHTDWN HRS 0.0 0.0 91 8. 2
- 15. HRS GENERATOR ON-LINE 403.6 41 7. 3 103960.8
~16.
UT RESERVE SHTDWN HRS 0.0 0.0 1208.6
- 17. GROSS THERM ENER (WH) 690500 704870 174225759
- 18. GROSS ELEC ENER (MWH) 226810 228840 58833024
- 19. NET ELEC-ENER (MWH) 215742 200739 56460607
- 20. UT SERVICE FACTOR 54.2 11.5 61.0 21-.
UT AVAIL FACTOR 54.2 11.5 61. 7
- 24. UT FORCED OUTAGE RATE 18.5 18.0 11.6
- 25. FORCED OUTAGE HRS 91. 8 91. 8 13602.5
' 26.. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
None 27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME: N/A
.1619B/0045X j
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AVERAGE DAILY POWER LEVEL NET MWe 4
DOCKET #........
50219 UNIT.......... 0YSTER CREEK #1 REPORT DATE....... June 2,1989 COMPILED 8Y.......HARI S. SHARMA TELEPHONE #......
609-971 -4638 s
MONTH MAY, 1989 DAY MW DAY MW l.
0 17.
631 2.
0 18.
287 3.
0 19.
0 4.
0 20.
0 5.
0 21.
0 6.
0 22.
153 7.
0 23.
463 8.
0 24.
606 9.
0 25.
61 9 10.
0 26.
61 3 11.
108 27.
611 12.
334 28.
626 13, 357 29.
625 14.
569 30, 620 15.
607 31, 6 21 16, 628 1619B/0045X i
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - MAY,1989 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: January ll,1991 pending necessary state approval.
Scheduled date for restart following refueling: April 13,1991 Will refueling or resumption of opera tion thereafter require a Technical Specification change or other license amendment?
Yes Scheduled date( s) for submi tting proposed licensing action and supporting i nformatf ort:
July 15,1990 Importa nt licensing considerations associated with refueli ng, 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 performa nce 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, j
in number of fuel assemblies:
Present licensed capacity:
2600 The projected date of the last refueling tnat can be discharged to the spent fuel pool assuming the present licensed capacity:
Reracking of the fuel pool is in progress.
Nine (9) out of ten (10) racks ha ve been installed te date.
When reracki ng is completed, discharge capacity to the spent fuel pool will be available until 1994 refueling outage.
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