ML20105B704
| ML20105B704 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/31/1992 |
| From: | J. J. Barton, Bradley E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-92-2256, NUDOCS 9209210115 | |
| Download: ML20105B704 (7) | |
Text
.
g GPU Nuclest Corporstion Qgg[
Post Of$ce Box 388
/
Route 9 South Forked River, New Jersey 087310388 609 971-4000 Wnter's Direct D:al Number:
C321-92-2256 September 14, 1992 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclc r Generating Station Docket No. 50-219 Monthly Operating Rcport In accordance with the Oyste Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) ccpies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contact Brenda DeMerchant, Oyster Creek Licensing Engineer at (609) 971-4642.
6 in ely,n
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i J.J.jBaton Vic P esident and Director 0
Creek JJB/BDEM: jc Attachment
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Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager p$[ kDO
"'~V W D GPU Nuclear Corporahon is a subscay of Generai Pubf'c UNd,es Corporanon g
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Monthly operating Report i
l August, 195 i
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oyster Creek entered August at full power.
On August 13, j
1992, plant load was reduced to conform to an administrative j
operating limit of 1915 megawatts thermal. The administrative j
limit was imposed due to non-conservative thermal power indications on the plant computer system versus the manual I
j heat balance calculations.
On August 14,1992, the administrative load restriction was removed,- following the Instrumentation and Control Departments's performance of feed flow instrument loop calibration, allowing the plant to return to full power of 1930 megawatts thermal.
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The Reactor Water Clean Up Sys'.em was removed from service for maintenance from. August 18,1992-through August 21, 1992, but had no impact on plant output.
At 1255 on August 22,1992, the reactor shutdown automatically-duc to low water level in the
. i 2
reactor pressure vessel caused by loss of the steam - flow signal to the Feedwater Control System.
The plant was safely l
brought to cold shutdown following the scram.
A reactor scartup was commenced on August 24, 1992 but was terminated l
because of an automatic shutdown due to' low level in the reactor pressure vessel caused by a malfunction of the #2
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Turbine Stop Valve internal bypass.
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The reactor was restarted on August 25, 1992. The startup was successful and the generator;was placed.on line at 0612.o n
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August 26,1992. Oyster Creek returned to full load-at 1622 on l
August 27,1992 and remained at full power through the end of j
i the reporting period.
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MONTHLY OEE. RATING REPORI i
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The following Licensee Event Reports were submitted during the month of l
l August, 1992:'
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t OPERATING DATA REPORT l
OPERATING STATUS f
- 1. DOCKET 50-219
- 2. REPORTING PERIOD:
08/92
- 3. UTILITY CONTACT:
ED BRADLEY (609)971-4097 f
- 4. LICENSED THERMAL POWER (MWt):
1930 1
- 5. NAMEPLATE RATING (GROSS MWe):
687.5 x 0.8 = 550
- 6. DESIGN ELECTRICAL R.\\ TING (NET MWe):
C50 l
- 7. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
632 4
- 8. MAXIMUM DEPENDABLE CAPACITY (NET MWo):
610 t
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IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
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- 10. POWER LEVEL TO WHICH RESTRZ ITED, IF ANY (NET MWe):
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NONE f
11 REASOil FOR RESTRICTION, IF hhY:
MONE
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l MONTH YEAB CUMgLATIVE i
- 12. REPORT PERIOD HOURS 744.0 5855.0 198911.0 I
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- 13. HOURS RX CRITICAL 676.0 5429.3 129792.0
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- 14. RX RESERVE SHUTDOWN HRS 0.0 0.0 918.2 I
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- 15. HRS GZNERATOR ON-LINE 654.7 5350.8 126433.1
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- 17. GROSS THERM ENERGY (MWH) 1242269 10131104 214456463 l
- 18. GROSS ELEC FNERGY (MWH)
JO5467 3378552 72064182
- 19. NET ELEC ENERGY (MWH) 389504 3250386 69157074
- 20. UT SERVICE FACTOR B8.0 91.4 63.6
- 21. UT AVAIL FACTOR 88.0 91.4 64.2
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- 24. UT FORCED OUTAGE RATE 12.0 4.7 11.2 i
- 25. FORCED OUTAGE HRS 89.3
~266.1
.15957.3 j_
- 25. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
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14-R NOVEMBER 27, 1992, 75 DAYS I
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
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f AVERAGE DAILY POWER LEVEL ~
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DOCKET /.
.50-219 f
UNIT.
. OYSTER CREEK #1
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l R2 PORT DATE.
. SEPTEMBER 4, 1992 COMPILED BY.
..ED BRADLEY h
I TELEPHONE #.
.609-971-4097 i
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j MONTH:
. AUGUST, 1992 i
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DAY M
p_AX M
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1.
605 16.
616 i
I' 2.
608 17 616 t
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604 18.
615 t
4.
600 19.
612 l
5.
605 20.
611 t
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607 21, 607 7,
606 22.
325 I
4 4
4 8.
605 23.
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599 24.
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2 10.
602
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11, 603 26.
246 f
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602 27.
525 i
j 13, 600 28.
597
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611 29.=
602 j
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614 30.
605 i
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l Oyster Creek Station #1 Dockot No. 50-219 c
4 REFUELING INFOPRATION ~ AUGUST, 1992 l
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l Name of Facilicy: Oyster Creek Station #1 l
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Scheduled date for next refueling shutdown:
November 27, 1992 Scheduled date for restart following refueling:
February 10, 1993
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Will refueling or resumptien of operation thereafter require a Technical f
j Specification change or'other license amendment?
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No f
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i Importa*t licensing considerations associated with refueling, e.g.,
new or different. fuel des'.gn or supplier, unreviewed design er performance ana tysis l
methods, significant changes in fuel <*esign, new operating procedures:
I Fuel design and
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General 191ectric Fuel Assemblies prformance analysis meQods have been approved by the NRC.
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Exxon Fuel Assemblies - No major changus have been-made nor
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i are there any anticipated, j
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The numoer of fuel asss.mblies (a) in the core 560
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4-r (b) in-the spent fuel storage pool = -1708 s
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(c)'in dry storage
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'I The present licensed spent fuei pool storage. capacity and the. size of any
.t i-increase in licensed storage capacity that has bsten requested or is planned, in.
number of fuel assemblies
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l Present Licensed capacity: 2600
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The projected date of the last refueling that can be discharged to tha spent fuel i
3 pool assuming the present licensed capacity:
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Full core discharge capacity to the spent fuel pool wj ?.1 be -
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available through the.1996; refueling outage.
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UNIT SHUTDOWNS AND POWER RFpU,,Q{OFj
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- DOCKET NW
' 50-219 UNIT NAME:
Ovsrer Creek k
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DATE:
Ssetember 3. Q92
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I COMPLT*D BYr' David Eman' i
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97148,,j,8 l
TELEPHONE:
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REPORT Mr WT!?: _Aurust 1992
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TYPE METHOD OF SHUTTING CORRECTIVE v
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No.
DATE F: Forced CUBATION REASON (1)
.DCWN THE RCACTOR OR ACTIONS / COMMENTS S: scheduled (hours)
RFDUCING POWER (2) 7 122 920822-F 40.2 a
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' An automatic' scram i
. 1 occurred due to lov l
vater invel in the
-Reactor Pressure.
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Vessel which was.
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caused by loss of the steam fiev i-signal to the t
feedvater control system.
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t 123 920824 F
49.1 a
3 An automatic ser,m
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E Reactor Pressure Vessel which was i-ca.ased by a s;alfwiction d the r
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- 2 Turbine Stop 1
Valve internal bypass.
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SUMMARY
l' (1) RFA50N (2',
METHOD a.
Equipraent Fattar. (Emplata) a.
Operator Training & T.to Esam 1.
Henuat b.
Maintanar.ce or Test f.
dministrative 2.
Manual Scram c.
Refueling g.
Ope rat ional Er t er (Expir. 4) t.
Au:cuatic scram 4.
Regule ory Restriction h,
Other (ExplaLn) 4 Other (Explain)
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