ML20056D918
| ML20056D918 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/31/1993 |
| From: | J. J. Barton, Egan D, Krall J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-93-2221, NUDOCS 9308190009 | |
| Download: ML20056D918 (7) | |
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_i GPU Nuclear Corporation u U Muclear
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o Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
l C321-93-2221 j
August 13, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
Dear Sir:
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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.
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J.o. Barton Vi gjPresident and Director stir Creek JJB/BDEM: jc Attachment (MOR-RPT. NL)
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Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager
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Monthly 00eratino Report July 1993 f
i Oyster Creek entered July operating at full power and generated 430,300 net' i
electric megawatt hours during the month. Minor power reductions (due to high ambient intake water temperatures) were made throughout the month in order not to exceed our NJPDES discharge permit limit of 106 F.
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Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - JULY, 1993 Name of Facility: Oyster Creek Station #1 J
Scheduled date for next refueling shutdown:
Currently projected for September, 1994 Scheduled date for restart following refueling: Currently projected for December,1994 Will refueling or resumption of operaticn thereafter require a Technical Specification change or other license amendment?
I No i
Important licensing considerations associated with refueling, e.g.,
new or different f uel c'esign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
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1.
General Electric Fuel Assemblies - Fuel design and performarce analysis j
methods have been approved by tne NRC.
l The number of fuel assemblies (a) in the core 560
=
1878 l
(b) in the spent fuel storage pool
=
8
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(c) in dry storage
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The present licensed spent fuel pool storage capacity and the sire of any increase in licensed storage capacity that has been requested or is planned, in number of fuel J
assemblies:
1 1
Presenc Licensed capacity:
2600 l
The projected date of the last refueling that can be discharged to 'the spent fuel' pool
]i assuming the present licensed capacity:
.]
Full core discharge capacity to the spent fuel pool will be available through the.
I 1996 refueling outage.
NRC_RPT.WPD i
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AVERAGE DAILY POWER LEVEL NET MWe DOCKET #.
.50-219 UNIT.
. OYSTER CREEK #1 REPORT DATE.
. 08-05-93 COMPILED BY
. JIM KRALL TELEPHONE #.
.609-971-4115 l
-i MONTH:
JULY, 1993 M
M DAY M
1.
605 16.
596 l
2.
605 17.
600 3.
606 18.
598 4.
605 19.
590 5.
600 20.
590 6.
580 21.
604 7.
540 22.
605 8.
544 23.
604 1
9.
538 24.
603 10.
531 25.
600 i
11, 495 26.
597 i
3 -
12.
509 27.
597 13.
512 28.
593 i
14.
517 29.
592 f
15.
575 30.
600 31.
601 I
NRC_RPT.WPD T
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MONTHLY OPERATING REPORT LICENSEE EVENT REPORTS P
The following Licensee Event Report was submitted during the month of July, 1993:
LER 93-004 The Updated Final Safety Analysis Report Section 6.2.3.2 describes blow-out l
panels in the reactor building above the 119' elevation which would relieve t
reactor building internal pressure at 0.25 psig. During the performance of a recent engineering evaluation, the blow-out panels could not be located either by document review or inspection of visible sections of the reactor building.
Therefore, a reanalysis assuming the absence of blow-out panel pressure relieving capability demonstrated that the torus shell could experience a peak external pressure of 1.37 psid during a high energy line break outside i
primary containment. The external torus design pressure is 1.0 psid. A
[
structural analysis showed that the existing torus shell can safely sustain 1
the loading combination of 1.37 psid external pressure plus dead load. Other i
safety assessments were performed. Equipment qualification was not impacted.
l Failure of block walls in the southeast corner room can damage one train of the containment spray system; however, this system is not needed to mitigate a High Energy Line Break.
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OPERATING DATA REPORT OPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
07/93
- 3. UTILITY CONTACT:
JIM KRALL (609) 971-4115
- 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 5087.0 206927.0
- 13. HOURS RX CRITICAL 744.0 4017.6 135926.0
- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 744.0 3981.4 132528.7
- 17. GROSS THERM ENERGY (MWH) 1391796 7560560 226029195
- 18. GROSS ELEC ENERGY (MWH) 447566 2509747 75905885
- 19. NET ELEC ENERGY (MWH) 430300 2411644 72795268
- 20. UT SERVICE FACTOR 100.0 78.3 64.0
- 21. UT AVAIL FACTOR 100.0 78.3 64.0
- 24. UT FORCED OUTAGE RATE 0.0 0.0 10.7
- 25. FORCED OUTAGE HRS 0.0 0.0 15957.3
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
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