ML20094E275
| ML20094E275 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1991 |
| From: | Bradley E GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20094E246 | List: |
| References | |
| NUDOCS 9201230043 | |
| Download: ML20094E275 (7) | |
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MONTHLY OPERATING REPORT - DECEMBER, 1991 As the beginning of the month, plant load was limited by control valve position, with the second stage reheaters out of service due to a steam leak on the 1-5 drain tank level column. This has been a recurring eroblem throughout the month, and typically limited generator output te 6fL MWe (reactor power 1907 MWth).
Repeated attempts to repair the steam leak proveJ unsuccessful, and the plant i
ended the report period with the second stage reheaters out of service.
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MONTHLY OPEilAllNG HEPORT - DECEMBER, 1991 The following Licensee Event Report was submitted during the month of December, 1991.
LER 91-008 On November 12, 1991 I difference between test measured and indicated feedwater flow was discovered as a result of a special lithium nitrate flow test.
This difference was 1.19% in the non conservative direction with respect to the feedwater flow impact on the heat balance.
The exact cause of the 1.19% difference in feedwater flow cannot be oe+crmined. Existing plant instrumentatien accuracy, calibration techniques, a change in nozzle discharge coefficient or feedwater piping errosion upstream of the feedwater nozzles may have contributed to th, difference observed.
Oyster Creek thermal limits are based, in part, on a 1.76% standard deviation for the uncertainty in feedwater flow. Therefore, the error found in the feedwater flow was within the accepted untertainty and the safety significance of this event is minimal.
Indicated reactor power was reduced by 1.2% to ar. count for the feedwater flow difference.
The heat balance calculations were revised to account for the observed difference in f eedwater flow.
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - DECEMiiER, 1991 Name of Facility: Oyster Creek Station #1 Scheduled date for f. ext refueling shutdown: January 15, 1993 Scheduled date for restart following refueling:
March 30, 1993 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No Im;wrtant ilcensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unroviewed design or performance analysis methods, significant changes in fuel design, new operating procedures Fuel design and 1.
Gn r.e ra l Electric Fuel Assemblies performance analysis methods have been approved by the NRC.
2.
Exxon Fuel Aeremblies - No major changes have been made nor are there any anticipated, f
560 The number of fuel assemblies (a) in tne core
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(b) in the spent fuel storage pool = 1708 44 (c) in dry storage
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The present licensed spent fuel pool etorage capacity and tne size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies present Licensed capacity:
2600 The projectod date of the last refueling that can be discharged to the spent fuel mol assuming the present licenced capacity:
Full core discharge capacity to the spent fuel pool will be available through the 1996 refueling outage.
NRC_RPT.WPD/37
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1 i
AVERACE DAILY POWER LEVEL NET HWe DOCKET #.
.50-219 UNIT.
. OYSTER CREEK #1 REPORT DATE.
. JANUARY 3, 1992 t
COMPILED BY.
ED BRADLEY TELEPHONE #..
.609-971-4097 HONTH:
DECEMBER, 1991
' D.hX Wl Dhl YE
-1.
623 16.
626 2.
624 17.
623 3.
621 16.
628 i
4.
627 19.
629 1
1 5.
628 20.
630 6.
629 21.
629
'7.
627 22.
629 8.
625 23.
629 i'
9.
624 24.
626 10.
627 2 5. -
626 1
11, 627 26.
615 12.
628 27 620 13.
628 28.
62b i
14.
628 29.
625 15.
627 30.
625 31.
626 l
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NRC_RPT.WPD/38
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OPEkhTENO DATA REPORT OPERATING STATUS
+
- 1. DOCKETS 50-219
- 2. REPORTING PERIOD:
12/91 L
- 3. UTILITY CONTACT:
ED 3RADLEY (603)971-4097
- 4. LICENSED THERMAL POVER (HWt):
1930
- 5. NAMEPLATE RATING (GROSS HWe):
687.5 x 0.8 = 550
- 6. DESIGN ELECTRICAL RATING (NET awe):
650
- 7. MAXIMUM DEPENDABLE ChPACITY (CROSS MWe)i 632
- 8. MAXIMUM DEPENDADLE CAPACITY (NET HWe):
610
- 9. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET HWe):
NONE
- 11. REASON FOR RESTRICTION, IF ANY:
NONE HQHIH XEAR gpjiVLATIVE-
- 12. REPORT PERIOD HOURS 744.0 8760.0 193056.0
- 13. HOURS RX CRITICAL 744.0
$297.6 124362.7
- 14. RX RESERVE SHUTDOWN HRS 0,0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 744.0 5169.3 131092.3 3
16.-UT RESERVE SHTDWN HRS 0.0 0.0 1208.6 l
- 17. GROSS TH2RM ENERGY (HWH) 1423764 9430403 204325719
- 18. GROSS ELEC ENERGY (H'fH) 483163 3079707 66685630
- 19. NET ELEC ENERGY (HWH) 465689 2946656 65906688
- 20. UT. SERVICE FACTOR 100.0 59.0 62.7
- 24. UT FORCED OUTAGE RATE 0.0 7.5 11.5
- 25. FORCED OUTAGE HRS 0.0 421.2 15631.2 L
L
-26. SHUTDOWNS SCHEDJLED OVER NEXT 6 HONTHS (TYPE, DATE, DURATION):
(.
NONE
- 27. IF CURRENTLY-SHUTDOWN, ESTIHATED STARTUP DATE:
N/A NRC_RPT.WPD/36
'.UNTT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-219 t
UNIT NAME:
Orster Creek l
DATE:
December, 1991 i
i COMPLT*D BT: R. Henriksen i
TELEPHCNE:
4972 i ' REPORT MOfflit-Deccebar, 1991' j
i TYPE METHOD OF SHUTTING DOWN F: Forced DURATION THE REACTOR OR REDUCING CORRECTIVE ACTIONS /
No.
DATE S
Scheduled (Hours)
REASON (1)
POWER (2)
COPNENTS No Unit Shutdowns or power reductions completed during this i
report month.
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- l. (1)
REASON (2) METHOD
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a.
Equipenent Failure (Explain) e.
Operator Training & Lic Exam.
1.
Manual b.
Maintenance or Test f.
Ad:dinistra*.ive 2.
Menual Scram c.
Refueling g.
Operationral Error (Explain) 3.
d.
. Regulatory Restriction h.
Other (Explain) 4.
Other (Explain) j l
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