ML20206F671
| ML20206F671 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/31/1988 |
| From: | Brennan C, Hagan J, Jensen H Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8811210260 | |
| Download: ML20206F671 (15) | |
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l AVERAGE DAILY UNIT POWER LEVEL DOCKET No.86-354 UNIT Hope Creek
'DATE 10/14/88 COMPLETED BY
_H.
Jensen TELEPHONE (609) 339-5261 MONTH October 1988 D$YAVERAGEDAILYPOWERLEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 974 17 109 2
974 18 959 3
981 19 1008-4 983 20 1015 l
5 985 21 1053 1
6 987 22 1018 7
987-23 1014 8
1004 24 1024 9
1007 25 997 10 999 26 1016 11 955 27 1016 12 768 28 1009 13 773 29 1012 14 897 30 996 15 631 31 1036 16 0
I I /
OhA$$$O5$34 9
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OPERATING _ DATA REPORT
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DOCKET NO.86-354 UNIT Hope Creek DATE 11/10/88 COMPLETED BY H. Jensen TELEPHONE (609) 339-5261 OPERATING STATUS 1.
REPORTING PERIOD October 1988 GROSS HOURS IN REPORTING-PERIOD 745 2.
CURRENTLY AUTHORIZED POWER LEVEL (HWt) __ 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1067 (1)
DESIGN' ELECTRICAL RATING (MWe-Net)__
1067 NAMEPLATE RATING (GROSS MWe) 1170 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MNe-Neti None 4.
REASONS FOR RESTRICTION (IF ANY)
L.2S YR TO MONTH DATE CUMULATIVE 5.
NO. OF HOURS REACTOR WAS CRITICAL 710.5 5,805.8 13,663.9.
F 6.
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 702.3 5,628.1
_1).373.2 7.
HOURS GENERATOR ON LINE 0.0 0.0 0.0 8.
UNIT RESERVE SHUTDOWN HOURS 9.
GROSS THERMAL ENERGY GENERATED 2,187,572 18,130,375__
41,938,942_
(HWH) 10.
GROSS ELECTRICAL ENERGY GENERATED (MWH) 728,654_
5,964,303 13,876,001 11.
NET ELECTRICAL ENERGY GENERATED 697,022_
5,696,058 13,261,096 (MWH) 95.4 79.3 83.5 12.
REACTOR SERVICE FACTOR 13.
REACTOR AVAILABILITY FACTOR 95.4 79.3 83.5 i
94.2 76.9 81.7 14.
UNIT SERVICE FACTOR UNIT AVAILABILITY FACTOR 94.2 76.9 81.7 15, 16.
UNIT CAPACITY FACTOR 87.7 72.9 75.9 l
(Using HDC)
I 17.
UNIT CAPACITY FACTOR 87.7 72.9 75.9 (Using Design HWe)
I 18.
UNIT FORCED OUTAGE RATE 5.7 3.4 6.7 19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):
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1/14/89, mid-cycle. 21 dass 20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
N/A 1987 data is under management review.
(1) August
s OPERAT7.NG DATA REPORT UNIT SKUTLOWNS AND POWER PEDUCTIONS DOCKFT do.86-354 UNIT- _Home Creek DATE
_10/14/8e COMPLETED BY
.H.
Januen REPORT MONTH October 1988 TELEPHONE 1609) 3?9-5261 METHOD OF SHUTTING DOWN THE TYPE-REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /
NO.
DATE S SCHEDULED (HOURS)
(1)
POWER (2)
COMMENTS 10 10/11 F
0 A
5 High Offgas Flow 11 10/15 F
42.7 A
3 Reactor Scram on High Discharge Pressure due to all Reactor Feed Pumps tripping on a Spurious Signal LER 88-027
4 REFUELING INFORMATION COMPLETED BY:
(h_r_i s B r e n n a n i}g%
DOCKET NO : jig-354 UNIT NAME : Hope Creek Unit 1 OATE 11/03/88 TELEPHONE : 1609)J39-319}
Month:
_0 & ber_1988 1.
Refueiing in format i on has changed from last month:
YFS NO X
2.
Scheduled date for next refueling:
_Q9222/89 3.
Scheduled dete for r e s t a r't following refueling:
_11_/07/39 4.
A)
Will Technical $pecification changes or other license amendments be reoutred?
YES X
NO B)
Has the reload fuel design been reviewed by the Stat t >n Operating Review Committee?
YES NO X
If noi when is it scheduled?
_Q5f022@9 5.
Scheduled date(s) for submitting proposed I tcensing action:
06/07/89 6.
Important Incensing considerations associated with refueling:
J n f.pr mait _on_n_o tat e s en t l y_a va.t I a b l e 7.
Number of Fuel Assembines:
Al Incore 764 B)
In Spent Fuel Storage
__])2 8.
Presentiv Itcensed spent fuel storage caoactiv:
1.109 Future noent fuel storage caparttv:
40.06 9.
Date of last refueling that can be discharged to spent fuel oool assuming the present i ncensed capac tiv
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l HOPE CREEK GENERATING STATION HONTHLY OPERATING
SUMMARY
t October 1988 Hopa Creek entered the month of October operating at approximately 98%
power.
This power level was due to a
continuation of a
detailed investigation into Feedwater Flow Nozzle Transmitter Calibration Data problems from the previous month.
The investigation was completed on October 7 and the plant returned to 100% power.
On October 11 power was reduced to 85% then to 50% due to high offgas flow.
This was due to a crack found in a weld on a condenser line.
The plant returned to 100%
power following repair of the line.
On October 15 the plant automatic lly chutdown due to low reactor level caused by three Reactor Feed Pumps tripping on high discharge header pressure.
Troubleshooting indicated that this was the result of an apparent signal failure within the common logic module associated with the three redundant high discharge pressure switches.
Prior to the shutdown, the plant had completed its 46th day of continuous power operation.
On October 17, the reactor achieved criticality and on October 18, the plant reached 100%
power.
On October 31st, the plant completed its 14th day of continuous power operation.
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SUMMARY
OF CHA!iGES, TESTS, A?ID EXPERIMENTS FOR THE HOPE CREEK GEliERATIliG STATIOli October 1988 i
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.The following Design Change Packages (DCPs) have been evaluated to i
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 an accident or malfunction of a different if a possibility for 2) than any evaluated previously in the safety analysis report type may be created; or if the margin of safety as defined in the basis for any technical 3) specification is reduced.
t the DCPs created a new safety hazard co the plant nor did they None of 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 unreviewod safety or environmental questions are involved.
RCP Descriotion of Desian Chance Packace 4-EMM-86-0968 The as-built penetration seal configuration did not meet the design criteria for movement, spare commodities,
- hydro, radiation, and fire requirements.
This DCP provided direction for performing a
walkdown and upgrading the penetration seals to meet design requiremente.
4EC-1050/01 This DCP changed ths operation of the Travelling Water Screens from continuous to intermittent to reduce maintenance and to increase service life and reliability.
The Travelling Water Screens are new activated by high differential pressure across the screens.
They are also started by a preset timer once a day.
- cable, installed
- conduit, and terminated non-Q analog and digital inputs for the new Safety Parameter Display System.
This is part of the project to separate the Safety Parameter Display System from the Control Room Integrated Display
- System, improving the realiability of both systems.
4EC-1085/02 This DCP rebalanced the Reactor Building
- Heating, Ventilation, and Air Conditioning System to provide additional cooling to the High Pressure Coolant Injection Pump Room and the Reactor Core l
Isolation Cooling Pump Room.
4HC-0015 This DCP increased the capacity of the Emergency Instrument Air Compressor.
This was accomplished i
by replacing the motor with a larger motor and enlarging the First-Stage cylinder of. the compressor to allow extra air-drawing capacity.
This DCP ensures that the Emergency Instrument Air Compressor has sufficient reserve capacity to maintain the Instrument Air System at operating pressure.
4HC-0050/03 This DCP installed a portion of the Underground Waste Transfer Line From Hope Creek Generating Station to Salem Nuclear Generating Station.
It covers the portion of the line within the Salem Unit 2 Turbine Building and includes piping and hangers.
The Waste Transfer Line will reduce operating costs by piping non-radioactive demineralizer waste to Salem instead of trucking it.
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,RCP Description of Desian Chance Packace 4HM-0122 This DCP added a splice' box to the cable running to the High Pressure Coolant Injection Drain Pot Level Switch.
The splice box will allow for easier-replacement'of damaged cable.
4HM-0123 This DCP added a splice box to the cable running to the Reactor Core Isolation Cooling Drain Pot
. Level Switah.
The splice box will allow for easier replacement of damaged cable.
This DCP installed a page system (5 handsets and 6 4HH-0240 speakers) in the Unit 2 Class 1E Switchgear Rooms and hallway.
These areas are anticipated to be used during outages for the life of the plant.
l 4HM-0340 This DCP raised the alarm delay times for the Primar" Condensate Pumps.
Raising the delay times compensates for the response time of the vibration absorber which had previously been installed on the "A" Primary Condensate Pump Motor.
This DCP also eliminates nuisance alarms in the Control Room.
4HM-0345 This DCP revised the setpoints for the Rotating Machinery Vibration Monitoring System on the "B"
The pump has i
scratches on its coupling surface which creates a
higher than actual vibration indication, causing a nuisance annunciation in the Control Room.
Revising the setpoints compensates for the t
scratch.
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.The following Temporary Hodification Request (TMR) has been evaluated' to determine:
1) if the probability of occurrer.:e 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 of safety as defined in the basis for any technical specification is reduced.
The T!!R did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
The THR 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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o Safety Evaluation Qescriotion of Temporary Modification Recuest (THR) 87-0111 This THR installed a plate over a leak and wall thinning area in the Service Water piping.
The plate is located on the line at the Service Water Inlet to a safety Auxiliaries Cooling System Heat Exchanger.
The plate prevents spraying of water onto equipment in the area.
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.The following Deficiency Request (DR) has been evaluated to determine:
1) if the probability of occurrence or the consequence =
of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or 2) if a pdssibility 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 DR did not create a new aafety hazard to the plant nor did it affect the safe shutdown of t'te reactor.
This DR did not change the plant effluent releases and did not alter the existing environraental impact.
The Safety Evaluation determined that no unreviewed safety or environr.antal questions are involved.
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Safety Eva uat on Description'of Deficiency Report (DR) l i
88-0114 During disassembly of a valve in the condensate Storage and Transfer System, it was discovered that the valve had been modified.
The velve body clearance in the bottom lo f the packing ' gland stuffing box had been enlarged to allow the shaft to be removed through the stuffing box.
Administrative controls w'ill ensure that this portion of the condensate storage and transfer system is isolated from the Core. Spray System.
Therefore, this_ valve may be used as is.
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ZMDEX llUMBER OF PAGES SECTION 1
Average Daily Unit Power Leve1.........................
2 Operating Data Report..................................
1 Refueling Information..................................
1 Monthly Operating Summary..............................
8 Summary of Changes, Tests, and Experiments.............
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"...O PSIEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department November 15, ".988 U.
S.
Nuclear Regulatory Commission I'
Document Control Desk washington, DC 20555
Dear Sir:
MONTitLY OPERATING REPORT
!! OPE CREEK GENERATING STATION UNIT 1 DOCKET No. 50-354 In compliance with Section 6.9, Reporting Requirements for the
!! ope Creek Technical Specifications, the operating statistics for October are being forwarded to you.
In addition, the summary of changes, tests, and experiments for October 1988 is included pursuant to the requirements of 10CFR50.59(b).
Sincerely yours, k
v _
llag General Manager -
llope Creek Operations TAE RAR : tlb A t;tachme n t C Distribution i
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rno enoweanie
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