ML20076E201
| ML20076E201 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/31/1991 |
| From: | Baran R, Bradley E GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20076E198 | List: |
| References | |
| NUDOCS 9108190029 | |
| Download: ML20076E201 (6) | |
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' MONTHLY OPERATING REPORT --JULY, 1991:
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, At the.beginning of July, Oyster Creek was increasing power as planned following
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the 13th refueling outage. Full power was achieved on J fly 2,1991. On July 13, -
1991, p)wer was reduced due to problems with the 'A' feedwater pump. On July 22, i
1991 the' reactor was - shutdown in a controlled manner due to a. leak in a i
condentate transfer line. Following completion of repairs and other maintenance, j
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reactor. start-up was commenced on July.31, 1991.- The generator was placed "on-t
- line" August 1 -1991.-
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i 9108190029 910812 PDR ADOCK 05000219 R
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n MONTHLY OPERATING REPORT, JULY 1991 The following Licensee Reports were submitted during the month of July,1991.
LER 91-001R1 l
On March 1,1991 at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br />, deluge systems were taken out of service without establishirg a continuous firewatch in accordance with Technical Specifications. The cause of this occurrence is attributed to a failure to adequately control firewatch activities. This event is considered to have minin.al safety significance because all of the fire detection sensors and systems for the affected areas were operable and would have provided an alarm to the control room had a fire condition occurred. A fire condition therefore would have been detected early and the deluge systems could have been manually actuated or any one of eight hose stations utilized to extinguish a fire.
Corrective action includes a lessons-learned lecture for fire watch personnel I
and a revision to the procedure controlling fire watches.
LER 91-002 During the.3R Refueling Outage, local leak rate testing (in accordance with 10CFR50, / pendix J) identified a Main Steam Isolation Valve (MSIV) with a
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leak rhe in excess of the acceptance criteria of 12.08 SCFH at 20 psig as sperMed in Technical Specifications 4.5.F.2.
The safety significance of tMr discovery is considered minimal since the other MSIV in the same header met the local leak rate test requirements.
Subsequent local leak rate testing identified a pair of isolation valves (in series) with a potential leak rate in excess of the acceptance criteria of 60%
of the maximum allowable limit (La) at 35 psig as specified in Technical Specifications 4.5.F.1.
Since the root cause for the excessive leakage past the Reactor Building-to-Torus vacuum breakers has not been identified, a root
- cause evaluation will be performed and a follow-up LER will be forwarded when the evaluation is completed.
These leaking valves were repaired and subsequent local leak rate testing verified that leakage rates were within the acceptance criteria.
Due to an improper interpretation of reporting requirements implemented by a recent Technical Specification Amendment, this condition was not reported within 30 days as required by 10CFR50.73.
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l Oyctor Crcok Station #1 Docket No. 50-219 REFUELING INFORMATION - JULY, 1991 Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: November 27, 1992 Scheduled date for restart following refueling:
February 9, 1993 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Fuel design and 1.
General Electric Fuel Assemblies performance analysis methods have been approved by the NRC.
2.
Exxon Fuel Assemblies - No major changes have been made nor are there any anticipated.
560 The number of fuel assemblies (a) in the core (b) in the spent fuel storage pool = 1708,
(c) in dry storage 44
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The presem licensed spent fuel pool storage capacity and the 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 projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
The reracking of the fuel pool is now complete.
All ten (10) racks are now installed.
Discharge capacity to the spent fuel pool will be available through the 1994 refueling outage.
NRC_RPT.WPD/19
AVERAGE DAILY POWER LEVEL NET MWe DOCKET #.
50219 UNIT.
. OYSTER CREEK #1 REPORT DATE.
.... AUGUST 2, 1991 COMPILED BY
. ED PRADLEY TELEPHONE #.
.609-971-4097 i
MONTH:
JULY, 1991 DAI MH DAX liW i
1.
433 16.
415 l
2, 571 17.
411 l
l 3.
560 18.
412 4.
602 19.
408 5.
449 20.
408 6.
600 21, 406 7.
597 22.
147 8.
592 23.
0 9.
599 24.
0 10.
599 25.
0 11.
602 26.
0 l
12.
594 27.
0 13.
445 28.
0 l
14.
417 29.
0 15.
417 30.
0 31.
O NRC_RPT.WPD/20
v UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
'50-219 UNIT NAME Ovster Creek
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DATE
~Auo, 1991 COMPLETED BY R. Baran TELEPHONE 971-4986 REPORT MONTH J:21v, 1991 TYPE METHOD OF SHUTTING F: Forced DURATION DOWN THE REACTOR OR NO.
-DATE S: Scheduled (Hours)'
REASON.(1)
REDUCING POWER (2)'
CORRECTIVE ACTIONS / COMMENTS 105 910628 S
0.9 B
1 Turbine Overspeed Test..
and Calibration.
(Procedure 625.4.001).
106 910713 F
.O H
N/A Load reduction due to loss of
'A' Rx Feed Water Pump.
107 910722 F
229 A
2 13-U-1 outage to repair Condensate Storage Tank Line Leak.-
I Summary :
(1) REASON METHOD a.
Equipment _ Failure (Explain) e.
Operator Training & License Exam 1.
Manual b.
Maintenance or Test f.
Administrative 2.
c.
Refueling g.
. Operational. Error (Explain)-
3.
Watomatic Scram d.
Regulatory Restriction h.
Other'(Explain) 4.
Other (Explain)
OPERATING DATA REPORT OPERATING STATUS
- 1. DOCKET:
50-219
- 2. REPORTING PERIOD:
7/91
- 3. UTILITY CONTACT:
ED BRADLEY (609)971-4097
- 4. LICENSED THERMAL POWER (MWt):
1930
- 5. NAMEPLATE RATING (GROSS MWe):
687.5x0.8=550
- 6. DESIGN ELECTRICAL RATING (NET MWe):
650
- 7. KAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
642
- 8. KAXIMUM DEPENDABLE CAPACITY (NET HWe):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE
- 10. POWER LEVEL TO bHICH RESTRICTED, IF ANY (NET HWe):
NONE
- 11. REASON FOR RESTRICTION, IF ANY:
NONE MONTH XEhB CURULATJYE
- 12. REPORT PERIOD HOURS 744,0 5087.0 189383.0
- 13. HOURS RX CRITICAL 517.9 1753.2 120818.4
- 14. RX RESERVE SFUTDOWN HRS 0.0 0.0 918.2
- 15. HRS GENERATOR ON-LINE 515.1 1693.0 117606.0
- 17. GROSS THERM ENERGY (MWH) 844241 3016361 197911317
- 18. GROSS ELEC ENERGY (MWH) 266920 991080 66597003
- 19. NET ELEC ENERGY (HWH) 255138 937522 63897554
- 20. UT SERVICE FACTOR 69.2 33.3 62.1
- 21. UT AVAIL FACTOR 69.2 33.3 B2.7
- 24. UT FORCED OUTAGE RATE 30.8 11.9 11.6
- 25. FORCED OUTAGE HRS 228.9 228.9 15498.9
- 26. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
NONE
- 27. IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE:
N/A I
I NRC_RP!.WPC/21
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