ML20079D609
| ML20079D609 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/30/1991 |
| From: | Hagan J, Zabielski V Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9107180302 | |
| Download: ML20079D609 (12) | |
Text
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- .0 PSIBG Pubhc Service Electnc and Gas Cornpany P.O. Box 236 Hancocks Bndge New Jersey 08038 -
' Hope Creek Generating Station July 12, 1991
'U.-S.. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear' Sir:
~
MONTHLY OPERATING REPORT HOPE CREEK GENERATION STATION UNIT 1
- DOCKr'.T NO. 3 54 In compliance with Section 6.9, Reporting Requirements for
,the Hope Creek--Technical Specifications,_the operating statistics for June are being forwarded-to you with the
-summary of changes, tests, and experiments for June 1991
. pursuant to the requirements of 10CFR50.59(b).
Sincer ly yours,
.-J Hag n Gene.
anager -
Hope Creek Operations 9kRAR:ld Attachments C
Dists'bution j._
l 107180302 910600 DR ADOCK 03000334 p
PDR p
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INDEX NUMBER SECTION OF PAGES Average Daily Unit Power Lev 21.
1 Operating Data Report 2
Refueling Information.
1 l
Monthly Operating Summary.
1 Summary of Changes, Tests, and Experiments.
5
i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-354 UNIT Hooo Creek DATE 7/12/91 COMPLETED BY V. Zabielski TELEPHONE isp9) 339-3506 MONTH June 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
1020 17.
1035 2.
1041*
18.
1042 3.
1041*
19.
221 4.
1051 20.
Eli 5.
1951 21.
1026 6.
1051 22.
1014 7.
1058 23.
1046 8.
1043 24.
1039 9.
1033 25.
1044 10.
1028 26.
1911 l
11.
1017 27.
1040 12.
1067 28.
943*
13.
948 29.
942*
14.
1047 30.
1021 15.
986 31.
EfA 16, 1991
- Due to an error in recording the meter readings, the exact average daily power levels for June 2, 3,
28 and 29 are unknown.
The listed averages for those four days represent the average of the appropriate two-day total.
l OPERATING DATA REPORT DOCKET NO.10-354 UNIT Hope Creek DATE
_7/12/91 COMPLETED BY V.
Zabielski TELEPHONE (609) 339-3506 OPERATING STATUS 1.
Reporting Period June 1991 Gross Hours in Report Period 720 2.
Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1Q11 Design Electrical Rating (MWe-Net) 1067 3.
Power Level to which restricted (if any) (MWe-Net)
None 4.
Reasons for restriction (if any)
This Yr To Month Date Cumulative 5.
No. of hours reactor was critical 720.0 2962.8 32.744.3 6.
Reactor reserve shutdown hours 0.0 0.0 quQ 7.
Hours generater on line 720.8 2864.5 12 157.6 8.
Unit reserve shutdown hours 929 929 0.0 9.
Groso thermal energy generated 2.352.120 9.124.158 101.666.565 (MWH)
- 10. Gross electrical energy 768.440 3.007.551 33.629.224 generated (MWH)
- 11. Net electrical energy generated 736.723 22 870.038 32.126.722 (MWH)
- 12. Reactor service factor 100.0 68.2 82.5
- 13. Reactor availability factor 300.0 68.2 82.5
- 14. Unit service factor 100.0 66.0 81.0
- 15. Unit availability factor 100.0 66.0 81 0 2
- 16. Unit capacity f actor (using MDC) 99.2 64.1 78.5
- 17. Unit capacity factor 95.9 61.9 75.9 (Using Design MWe)
- 18. Unit forced outage rate 922 9.7 5.9
- 19. Shutdowns scheduled over next 6 months (type, date, & duration):
None
- 20. If shutdown at end of report period, estimated date of start-up:
N/A l
OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-354 UNIT lione Creek l
DATE 7/12/9:
COMPLETED BY V.
Z ab:.e l skd__
TELEPHONE (609) 339-3506 MONTH gune 1991 METHOD OF SHUTTING DOWN THE i
TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE l
NO.
DATE S= SCHEDULED (HOURS)
(1)
POWER (2)
ACTION / COMMENTS NONE-J Summary i
P.EFUELING INFORMATION DOCKET NO.
50-354 UNIT liope Creej; DATE 7/12/91 COMPLETED BY S.
Hollinasworth TELEPHONE (609) 339-1051 MONTH June 1991 1.
Refueling information has changed from last month:
Yes No X
2.
Scheduled date for next refueling:
9/5/92 3.
Scheduled date for restart following refueling:
11/3/92 4.-
A.
Will Technical Specification changes or other license amendments be required?
Yes No X
B.
Has the reload fuel design been reviewed by the Station Operating Review Committee?
Yes No X
If no, when is it scheduled?
not currently scheduled 5.
Scheduled date(s) for submitting proposed licensing action:
ELA 6.
Important licensing considerations associated with refueling:
- Amendment 34 to the Hope Creek Tech Specs allows the cycle specific operating limits to be incorporated into the CORE OPERATING LIMITS REPORT; a submittal is therefore not required.
7.
Number of Fuel Assemblies:
A.
Incore 764 B.
In Spent Fuel Storage (prior to refueling) 496 C..
In Spent Fuel Storage (after refueling) 760 8.
Present licensed spent fuel storage capacity:
Appi Future spent fuel storage capacity:
1006 9.
Date of last refueling that can be discharged duly 22, 2007 to spent fuel pool assuming the present licensed capacity:
i
l HOPE CREEK GENERATING STATION MONTHLY OPERATING
SUMMARY
JUNE 1991 Hope Creek entered the month of June at approximately 100% power and operated for the entire month without experiencing any shutdowns or reportable power reductions.
On June 30, the plant completed its 49th day of continuous power operation.
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION JUNE 1991 I
l l
The following Temporary Modification Request (TMR) has been evaluated to determine:
1.
If the probability of occurrence or the coneequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or 2.
If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3.
If the margin of safety as defined in the basis for any technical specification is reduced.
The TMR did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
The TMR did not change the plant effluent releases and did not alter the existing environmental impact.
The Safety Evaluation determined that no unreviewed safety or environmental questions are involved.
I 1
T]iB Description of Temocrary Modification Reauest 91-029 This TMR installed a jumper across the High Bearing Oil Temperature Trip Switch of the
'B' Control Room chiller.
The jumper will permit the chiller to operate with a defective module / thermistor until a replacement part can be installed.
3 r
The following Deficiency' Reports (DR's) have been evaluated to determine:
^
1.
If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in-the safety analysis report may be increased; or 2.
If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3.
If the margin cf safety as defined in the basis for any technical specification is reduced.
The DR's did not create a new safety hazard to the plant nor did 4
they affect the safe shutdown of the reactur.
The DR's did not change the plant effluent releases and did not alter the existing environmental impact.
The Safety Evaluations determined that no unreviewed safety or environmental questions are involved, 4
,4 QB Descrintion of Deficiency Report HIC-91-138 The
'C' Diesel Generator Fuel Oil Header Low Pressure Alarm Tee Fitting was damaged while an 18 month preventive maintenance activity was being performed.
The tee fitting was replaced with an elbow because no replacement parts were available.
The two fittings are identical except that the elbow does not provide for a test connection.
HTE-91-139 This DR addresses a pinhole leak in Service Water pipe on the
'C' Spray Wash Pump Suction Header.
A leakage deflection device has been installed to protect the surrounding aquipment from potential water damage.
The pipe may be used-as-is until an outage of sufficient duration to restore the pipe to the ASME code.
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