ML20236D297
| ML20236D297 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/28/1989 |
| From: | Hagan J, Jensen H Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903230043 | |
| Download: ML20236D297 (16) | |
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-354 UNIT Hope Creek DATE 3/15/89 COMPLETED BY H.
Jensen TELEPHONE (609) 339-5261 MONTH February 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 993 17 904 2
1014 18 0
3 987 19 0
4 989 20 0
5 978 21 0
6 902 22 0
7 1014 23 0
8 1028 24 0
9 1029 25 0
10 1021 26 0
11 1007 27 0
12 1029 28 0
13 1027 29 l
l 14 1005 30 15 1011 31 l
16 990 NOTE:
The above values are only available from station meters which read low due to a design problem scheduled for correction by the second quarter of 1989.
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OPERATING DATA REPORT DOCKET NO. _j0-354 UNIT Hope Creek DATE 3/15/89 COMPLETED BY H.
Jensen TELEPHONE (609) 339-5261
-OPERATING STATUS 1.
REPORTING PERIOD February 1989 GROSS HOURS IN REPORTING PERIOD 672 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1031 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 409.7 1,153.7 16,101.3 6.
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 7.
HOURS GENERATOR ON LINE 409.6 1,153.6 15,785.7 l
8.
UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 j
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GROSS THERMAL ENERGY GENERATED (MWH) 1,323,762 3,765,616 49,769,330 10.
GROSS ELECTRICAL ENERGY l
GENERATED (MWH) 440,977 1,251,269 16,477,713 11.
NET ELECTRICAL ENERGY GENERATED (MWH) 419,429 1,196,021 15,746,121 12.
REACTOR SERVICE FACTOR 61.0 81.5 83.7 13.
REACTOR AVAILABILITY FACTOR 61.0 81.5 83.7 14.
UNIT SERVICE FACTOR 61.0 81.5 82.0 1
l 15.
UNIT AVAILABILITY FACTOR 61.0 81.5 82.0 l
l 16.
UNIT CAPACITY FACTOR
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(Using MDC) 60.5 81.9 79.3 17.
UNIT CAPACITY FACTOR (Using Design MWe) 58.5 79.2 76.7 18.
UNIT FORCED OUTAGE RATE 0.0 0.0 6.9 19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):
l N/A 20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
3/6/89
o OPERATING DATA REPOR1 i
UNIT SHUTDOWNS AND POWER REDUCTION $
I DOCKET NO.
_50-354 UNIT Eqpe Cre_ek jrnt_i_
DATE'
-'3/15/89 COMPLETED BY H 'Jensen i
REPORT MONTH February 1989 TELEPHONE (6091 339-S261 1
METHOD OF SHUTTING l
1 DOWN THE I
TYPE l
REACTOR OR F FORCED'-
DURATION REASON REDUCING CORRECTIVE. ACTION /
NO.
DATE S SCHEDULED (HOURS)
(11 POWER (2)
COMMENTS 1
2/18 S
262.4 8
2 SCHEDULED MIOCYCLE OUrAGE e
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SUMMARY
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l REFUELING INFORMATION l
COMPLETED BY:
Chris Brennan DOCKET NO.: 50-354 i
UNIT NAME:' Hope Creek Unit 1 l
DATE: 3/15/89 l
TELEPHONE: (609) 339-3193 l
l Month February 1989 1.
Refueling information has changed from last month:
l YES NO X
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2.
Scheduled date for next refueling:
09-22-89 j
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Scheduled date for restart following refueling:
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11-07-89 I
4.
A)
Will Technical Specification changes or other license amendments
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be required?
I YES X
NO I
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Has the reload fuel design been reviewed by the Station Operating
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Review Committee?
YES NO X
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l If no, when is it scheduled?
5-07-89 l
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5.
Scheduled date(s) for submitting proposed licensing action:
I 6-07-89 j
6.
Important licensing considerations associated with refueling:
Information not presently available l
7.
Number of Fuel Assemblies:
A) Incore 764 B) In Spent Fuel Storage 232 8.
Present licensed spent fuel storage capacity:
1108 Future spent fuel storage capacity:
4006 l
9.
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
11-07-89 i
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HOPE CREEK GENERATING-STATION j
MONTHLY OPERATING.
SUMMARY
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February 1988 l
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I Hope Creek entered the month of February operating at 100% power.-
l On February 17th a power reduction commenced, and on the 18th at j
0144, the reactor was manually scrammed from approximately 20%
1 power to begin a planned maintenance and surveillance outage.-
i The plant had completed its 100th day of power operation prior to j
the. manual scram.
The outage continued through the end_of the I
- month, l
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SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS l
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FOR THE HOPE CREEK GENERATING STATION-l 1
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February 1989 l
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1 The following Design Change Packages (DCPs) have been evaluated to determine:
1 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 l
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.
None of the DCPs created a new safety hazard to the plant nor did they affect ~the safe shutdown of the reactor.
These DCPs 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.
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l DCP Description of Desian Chance Packace 4EC-1002/16 This DCP installed the structural, electrical, and mechanical portions of the Control Rod Drive Facility Bridge Crane System.
It is part of the modifications to the Control Rod Drive Removal l
and Repair Area and will result in reduced i
radiation exposure.
4EC-1053 This DCP replaced terminal block connections with splice connections and seismically reinforced' the enclosure for the splices.
These changes were related to the Main Steam Isolation Valve Solenoids and will improve their environmental and seismic conditions, 4EC-1061 This DCP added two mechanical flow totalizers on i
l the Feedwater Heater Effluent Sample Lines located l
within the Process Sampling Panel.
The totalizers will provide a way to determine the total flow so the conditions required to obtain an accurate sample can be maintained.
4EC-1076/06 This DCP added the "All Rods In" input to the Safety Parameters Display System Digital Cabinet.
This DCP is part of the installation of a new l
Safety Parameters Display System that will comply l
with NUREG 0737.
4HC-0144 This DCP added splices to shielding supports and l
added lifting lugs to the shielding, which is associated with a Primary Containment penetration.
l This DCP will facilitate the removal and i
installation of shielding without loosening and tightening the associated expansion anchor bolts.
I 4HC-0235 This DCP removed the billing and metering watthour meters connected to the Main Transformer circuitry and connected the new watthour meters to the Main Generator circuitry.
The new watthour meters will i
provide a more accurate reading.
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4HM-0196 This DCP expanded the deadband on pressure I
switches which are part of the Circulating.
l Water Discharge Valve Hydraulic Control Units.
l Expanding the deadband will reduce the cycling of l
the Hydraulic Control Unit Pump, which will reduce maintenance.
l 4HM-0218 This DCP installed time delay relays in series I
with the basket strainers for the Condensate l
Demineralized Polisher Beds.
The time delay i
relays will prevent erroneous high pressure spikes and reduce nuisance alarms.
EqE Description of Desion Chance Packace 4HM-0270 This DCP changed the Instrument Calibration Data Card Setpoints for High conductivity Alarms.
The setpoint had been set too low, resulting in a constant nuisance alarm.
l 4HM-0273 This DCP installed stiffeners on the Flow l
Distribution Vanes in the transition duct between l
the Filtration, Recirculation and Ventilation
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System Recirculation Fen and filter housing.
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stiffeners will strengthen the transition duct, which will result in increased equipment reliability.
4HM-0310 This DCP installed temporary accelerometers near feedwater check valves located in the drywell.
The accelerometers are being installed to analyze potential valve chattering which was detected by the Loose Parts Monitoring System.
4HM-0334 This DCP placed an aluminum threshold under 2 fire doors.
The threshold lessened the gap between the doors and the floor to less than 3/4 inch, conforming to the National Fire Protection Association Code.
4HM-0434 The DCP substituted a different type of pipe and permitted the use of an alternate detail for the fabrication of thermowells and pressure taps.
The changes were made to the Service Water System at the inlet and outlet elbows of the Safety Auxiliaries Cooling System Heat Exchangers.
The original materials were not available and the new material has been determined to be satisfactory for this application.
4HM-0453 This DCP eliminated the Main Turbine Electro-Hydraulic Control System loss of 125VDC Control Power Trip feature.
This implements the recommen-dations of General Electric TIL 878 and reduces the susceptibility of the Turbine Control System to battery transients which could cause turbine trips and safety system actuations.
4HH-0495 This DCP was a document change only which revised a piping specification.
The piping which was originally specified is no longer being produced.
4HM-0506 This DCP replaced an automatic control valve in the Service Water Hypochlorination System with a manual isolation valve.
The automatic control valve failed.
Neither a new valve nor spare parts for the original valve are available.
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4HM-0510 This DCP changed th'e rating-for the Secondary-Condensate Pump Auxiliary 011 Pump Overload Heaters.to a higher rating. 'This will increase the pumps efficiency and reliability.
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4 The following Temporary Modification Requests (TMR'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 ne created; or 3) if the margin of safety as defined in the basis for any technical specification is reduced.
j The THR'S did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.
The TMR'S 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.
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Safety Evaluation Qascriotion of Temoorary Modification Recuest f
(TMR) 89-0002 This THR installed a plate over a thin area in I
the Service Water piping.
The plate is at the Service Water outlet to the "B"
Safety Auxiliaries Cooling System.
The installation of the plate
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will prevent water from spraying on the equipment 1
in the area in the event of pipe failure, j
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L 89-0011 This THR-replaced the valve. operator on the 1
Service Water Rinse Outlet Valve with a
manual lever.
The valve failed open, the lever will allow the valve to be manually operated.
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1 89-0015 This THR lifted leads in the "A" and "B" Channel
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Class 1E Digital Termination Cabinets.
The lifted leads removed the power source from the Core. Spray Testable Check Bypass Valves to comply with 10CFR50 Appendix R.
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The following Deficiency Request (DR) has 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 l
' type than any evaluated previously in the safety analysis report may be created; or l
1 3) if the margin of safety as defined in the. basis for any technical specification is reduced.
The DR did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
The DR did not change the plant effluent releases and did not alter the ~ existing environmental I
impact.
The Safety Evaluation determined that no unreviewed safety or j
environmental questions are' involved.
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Safety Evaluation Description of Deficiency ReDort (DR) l I
89-0013 While removing an Acoustic Monitor Sensor from l
a Main Steam Relief Valve Tailpipe, a technician discovered a damaged outer rubber cable jacket.
The sensor was determined to be functional by a functional test.
The damaged cable will be repaired utilizing Raychem shrink tubing.
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4 INDEX' NUMBER SECTION OF PAGES-Average' Daily Unit Power.Leve1.........................
1
. Operating Data Report..................................
2
' Refueling Information..................................
1 Monthly Operating Summary..............................
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U Summary of. Changes, Tests, and Experiments.......'......
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station L March 15, 1989
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Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l
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Dear Sir:
MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 l
In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for l
February are being forwarded to you with the summary of changes, tests, and experiments for February 1989 pursuant to the requirements of 10CFR50.59(b).
Sincer ly yours, l
. Hagan General Manager -
Hope Creek Operations
%h*RAR:bjh Attachment l
C Distribution l
The Energy People o I (.
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