ML20114A671
| ML20114A671 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/31/1992 |
| From: | J. J. Barton, Bradely E, Egan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-92-2234, NUDOCS 9208200057 | |
| Download: ML20114A671 (7) | |
Text
.
e GPU Nucleer Corporelion 5.,. t1 Nuclear
- en:;see o
Forked River, New Jersey 08731-0388 609 971 4000 Writer's Direct Dial Number:
C321-92-2234 August 13, 1992 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
Oyster Creek Hoclear Conerating Station Docket No. 50 219 Monthly Operating Report in accordance w'.th the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendiv. A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gr book information) for the Oyster Creek Nuclear Generating Station.
'If you should have any questions, please centact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
'ingrely
/
J.
arton V
e President and Director H
er Creek l-JJB/BDEM: Jc A.ttachment I,
cc:
Administrator, Region 1 Senior NRC Resident inspector Oyster Creek NRC Project Manager fI 9208200057 920731 PDR. ADOCK 05000219
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GPU Nuclear Corpora:en !s a subsidy, of uenerat Pubhc Umes Cogowen b
Monthly operating Report July 1992 Oyster Crack operated at full power for the month of July and had a capacity factor of 99.0%, generating 449,430 megawatts electric not output.
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tiOEll'lOPERATIJ3G REP 0RI
~The following Licensec Event Reports were submitted during the month of July, 1992:
LLLkQ91 A full reactor scram occurred during a reactor r,tartup on June 10, 1992 at 2301 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.755305e-4 months <br />. An Intermediate Range. Neutron lioniter Hi-Hi signal caused by electrical noise from a failed bypass switch initiated the scram.
All systems responded to the scram as expected and there was-no safety significance to this event. The plant was placed in COLD SHUTDOWN at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on June 11.
Both Intermediate Ranoe Neuf.ron Monitor bypass switches-were replaced before restart. _ A review of the same design switch in other applications has revealed reliability concerns. Anc,ther model switch has been evaluated and will be used-for all future replacements.
LfAJ2.QM During a plant startup on June 8,1992, one of-the isolation condensers became inoperable thus requiring a technical specification required shutdown This condition is considered to be reportable at defined in 10 CFR 50.73(a)(2)(1)(A).
The cause of the shutdown was a packing leak on V-14-33 which-has been attributed to a scored stcm.
The cause of the damaged stem is unknown at this time and will be provided in a supplement to this report after the valve is dismantled at some future date. The safety significance of this event is considered minimal since during this period the "A" isolation cor. denser was availabla for operation.
The stem was stoned and smoothed end the valve was repacked and returned to service.
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l UPERATING DATA REPORT r
OPERATING STATUS
~1.
DOCKET:--
50-219-
- 12. REPORTING PERIODt_
07/92
=3. UTILITY CONTACT:
ED BRADLEY (609)971-4097 4.-4ICFNSED THERMAL POWER (MWt):
1930
- 5.-NAMEPLATE. RATING.(GROSS MWe):
687.5 x 0.8 = 550-
- 6. DESICN ELECTRICAL RATING (NUT'MWe):
650
.7.=MA%IMUM DEPENDABLE CAPACITY'(GROSS MWe):
632
- 8. MAXIMUM DEPENDABLE CAPACITY-(NET MWe):-
610 9.-IF CHANGFS OCCUR ABOVE SINCE LAST REPORT, GIVE P.EASONS:
NONE
- 10. POWER LEVEL TO :'4HICH REiTRICTED, IF ANY (NET MWu):
NONE_
- 11. REASON.FOR-RESTA!CTIJN, ANY:
'QNR MONTH XEbH EUMULATIVE
'12.'PEPORT PERIOD HOURS.
744.0 5111.0 198167.0
- 13. HOURS ' RX C.. JAL
.744.0 4753.3 129116.0
- 14. RX RESERVE w.sTDOWN HRS 0.0 0.0 918.2
-15. HRS GENERATCR ON-LINE 744.0 4696.1 125778.4
'16. UT RESERVE SHTDWN HR$
0.0 0.0 1208.6 17._ GROSS.. THERM ENERGY (MWH) 1429291 8888836 213214194
- 16. GROSS-ELEC ENERGY !MWH) 467008 2973085 71658715
.19. NET'ELEC ENERGY ;MWH).
449430-2860882
-68767570
.53.4
-176.8 15868.0 26., SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
14-R NOVEMSER 27, 1992, 66 DAYS 27.
.F CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
L N / A _-
_NRC_RPT.WPD/59-1 0
n+
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AVERAGE DAILY POWER LEVEL NET MWe DOCKET J.
.50-219 OYSTER CREEK #1 UN!T..
REPORT.DATE.
AUGUST 4, 1992 COMPILED BY.
ED BRADLEY TELEPHONE
.609-971-4097 MONTH:
JULY, 1992 Dh1.
tEl Dh1 1.
535 16.
558 2,
610 17.
601 3.
611 18.
603 4.
.611-19.
604 5.
613 20.
601 6.
609 21.
531
-7, 610 2 ?..
600 8,
610 23.
601 9.
598 24, 610 10.
602 25.
609 11.
602 26.
611 12.
601 27.
608 13, 604-
. 2 8.
610 14.
603 29.
608
-15.
595 30.
603 31.
600
_NEC_EPT.WPD/58
4 oyster creek station #1 Docket No. 50-219 1
I REFUELING INFOPdtATION - JULY, 1992 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shu down:
November 27, 1992 Scheduled date for restart following refuelingt February 10, 1993 Will refueling or resumption of operation thereafter require a Technical specification change or other license amendment?
No Important licensing considerations associated with retueling, e.g.,
new or different fuel deutgn or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, natw operating procedures Fuel design and 1.
Genaral Elects.2c Fuel Aosemblies performance analysis methods have been approved by the NRC.
2.
Exxon Tuel Assemblies - No major changes have oeen made nor are there any anticipated.
560 The number of fuel assemblies (a) in the core
=
(b) in the spent fuel mtorage pool = 1708 44
{
(c) in dry storage
=
The present licensed spent fuel pool storage capacity and the size of any increano in licensed etcrage capacity that has been requested or is planned, in g
number of fuel assembliest Present Licensed Capacity:
2600 The projected date of thu last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity-Full core discharge capacity to the spent fuel pool wi.1 be available through the 1996 refueling outage.
NRC_RPT.WPD/57 i
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