ML20149M212

Monthly Operating Rept for Jan 1988

ML20149M212
Person / Time
Site:	Hope Creek
Issue date:	01/31/1988
From:	Jensen H, Labruna S, Ritzman R Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8802250413
Download: ML20149M212 (14)

Text

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OPERATING DATA REPORT DOCKET NO.86-354 UNIT Hope Creek DATE 2/15/88 COMPLETED BY H. Jensen '

TELEPHONE (609) 339-5261 OPERATING STATUS

1. REPORTING PERIOD Jan 1988 GROSS HOURS IN REPORTING PERIOD 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1067

• 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 744.0 744.0 8602.1

6. REACTOR RESERVE SHUTDOWN HOURS O O O

7. HOURS GENERATOR ON LINE 744.0 744.0 8489.1

8. UNIT RESERVE SHUTDOWN HOURS O O O

9. GROSS THERMAL ENERGY GENERATED (MWH) 2,440,287 2,440/287 26,248,854

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 819,520 819,520 8,731,218

11. NET ELECTRICAL ENERGY GENERATED (HWH) 788,217 788,217 8,353,255

12. REACTOR SERVICE FACTOR 100.0 100.0 87.8 4

13. REACTOR AVAILABILITY EACTOR 100.0 ___

100.0 87.8

14. UNIT SERVICE FACTOR 100.0 100.0 86.7

15. UNIT AVAILABILITY FACTOR 100.0 100.0 86.7

16. UNIT CAPACITY FACTOR (Using Design MDC) 99.3 99.3 80.0 ,

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17. UNIT CAPACITY FACTOR l (Usina Desian MWe) 99.3 99.3 80.0

18. UNIT FORCED OUTAGE RATE 0.0 0.0 8.2 l

19. SHUTDOWNS SCHEDULED OVER N"XT 6 MONTHS (TYPE, DATE, & DURATION): 1 Refueling 2/12/88, 55 days i

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

N/A

• Data obtained in August 1987 isundermanagementreview.j[g,h 8902250413 880131 PDR ADOCK 05000354 R PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.86-354 UNIT Hope Creek DATE 2/15/88 COMPLETED BY- H. Jensen TELEPHONE (609) 339-5261 MONTH January 1988 't DAY AVERAGE DAILY POWER LEVEL , DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 , 1012 17 1019 2 978 18 1028 3 1008 19 1024 4 1023 20 1019 5 1018 21 1014 6 1022 22 _ 1033 7 1010 23 1023 ___

8 1035 24 1017 9 967 25 1013 10 982 26 1016 11 1024 27 1016 12 1029 28 1018 13 1025 29 1036 14 1019 __ 30 1014 15 1028 31 1017 16 1024 d

OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.86-354 UNIT __ Hope Creek DATE 2/15/88 COMPLETED BY R. Ritzman REPORT MONTH Jan. 1988 TELEPHONE (609) 339-3737 METHOD OF SHUTTING DOWN THE TYPE 1 REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) POWER (2) COMMENTS NONE

SUMMARY

HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

JANUARY'1988 Hope Creek entered the month of January operating at approximately 100% power. The unit operated throughout the month and. did not experience any shutdowns or reportable power reductions. On January 31st, the plant completed its 52nd. day of continuous power operation.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION JANUARY 1988

The following Design Change Packages- (DCPs) 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 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 environraental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

QCE Description of Desion Chance Packace 4-EC-1072 This DCP verified the as-built condition of the Control Room Integrated Display System by investigating and dispositioning previously identified discrepancies. In addition, 20%-30% of the remainder of the database was reviewed. This database update allowed the control Room Integrated Display System to more . accurately reflect current field conditions.

4-HC-0019/3 This DCP rewired Control Room Overhead Annunciator Windows to allow the annunciator to clear when the corresponding remote panel alarm has been-acknowledged. This will eliminate nuisance alarms in the Control Room and reduce confusion by clearing alarms when they are no longer required to be displayed.

4-HC-0067 This DCP relocated Slurry Metering Pump Flow ,

Heters from the dischargo side of the pump to the suction side. The flow meters must have a steady flow rate for input to the ratio controller when processina waste and asphalt. When mounted on the discharge side of the pump, the flow meters detect the pulsation of the Slurry Metering Pumps, causing the ratio controller to follow these flow swings. This DCP will provide a more accurate flow signal into the ratio controller and a better waste / asphalt ratio in the treated solid radwaste.

4-HC-0110/1 This DCP installed drip pans on the Refueling Platform Monorail Hoist and splash shields on the Refueling Platform Main Hoist Grapple. The drip pans and splash shields will protect personnel from potential contamination.

4-HC-0110/2 Thic DCP installed a mechanism to ensure positive actuation of the Refueling Bridge Auxiliary Hoist Full Up Trip Switch. This mechanism prevents the up switch from being bypassed; bypassing the up switch would result in additional personnel exposure.

QCE pescription of Desian Chance Packace 4-HC-0110/3 This DCP installed a strain relief mechanism for the cables and air hoses on the Refueling Platform Main Hoist Grapple. This will prevent both the grapple rotation from becoming restricted and the air hose connector from being damaged by continuous. pull-up from the hose reel.

4-HC-Oll1/1 This DCP installed Core and Fuel Pool Index Scales on the Refueling Platform structure and on the refueling floor adjacent to the bridge rail. It also installed video equipment to view the index scales from the Refueling Main Hoist Cab. This allows for quicker positioning of the bridge and lessens the chance of loading the fuel improperly.

4-HC-Oll2/1 This DCP replaced the Hydraulic Refueling Platform Main Hois' Grapple Load Weighing System with a solid state load weiching system. The solid state -

system is more reliable.

4-HC-Oll2/2 This DCP up-araded- the Air Supply System on the Refueling Platform by replacing the compressor with a larger one, replacing the Air Receiver Tank with a larger one, adding a refrigerated air dryer, and replacing the air supply lines. The new system will perform its design functions and i will not be subject to excessive water accumulation as the original system was. ,

4-HH-0038 This DCP chanced the setpoints for the Emergency Diesel Generator Starting Air Compressor Automatic Start /Stop Pressure Switches. This change ensured that the Air Start Receivers remain above the Technical Specification limit of 380 psig.

4-HM-0152 This DCP revised the Emergency Diesel Generator Fuel Oil Storace Tank Level High Alarm logic to indicate a high low level alarm. It also changed the alarm so that it alarms on decreasing tank level, indicating that tank level is approaching the minimum level allowed by Technical i Specifications. This DCP clears a Control Room i annunciator that is always in alarm and provides a  !

more meaningful alarm.

4-HH-0160 This DCP installed bottle racks as a back-up I supply of air to the Fuel Pool Gate Seals in the event of a loss of service air. The seals prevent Fuel Pool water from leaking out into the Reactor Well or the Fuel Cask Storace Pit. Loss of air to the seals would allow them to deflate, causing a-loss of water from the Fuel Pool.

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DCP Descriotion of Desian Chance Packace 4-HM-0185 This DCP changed the cable terminations for the "A" Diesel Generator Start Command signal. This signal provides CRIDS and GETARS with information.

which is recorded for post-trip data.

4-HM-0213 This DCP revised the Instrument Calibration Data Cards and installed new Fuel Oil Storage Tank Scales to reflect the latest setpoint calculation.

It was . revised to provide a more accurate assessment of the volume in the storage tanks.

4-HM-0269 This DCP added wiring in a Liquid Radwaste Radiation Monitor to connect the Loss of Operate contacts to the Liquid Radwaste Discharge Isolation logic. It also added a spring-return pushbutton in series with relay contacts. to override the Loss of Operate condition that exists when'no Liquid Radwaste discharge.is in progress.

These changes provide an automatic isolation of the Liquid Radwaste Discharge valves on a Liquid Radwaste Radiation Monitor downscale failure, in compliance with the Technical Specifications.

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The following Temporary Modification Requests (THRP) 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 of safety as defined in the basis for any technical specification is reduced.

None of the THRs created a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These THRs 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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Safety Evaluation Description of Temporary Modification Recuest f' (TMR) 87-0200 This THR removed the- suction spool from the Centrifuce Feed Tank Decant Pump and. installed an air-driver positive displacement pump with .its discharge directed to a floor drain. -This THR will allow the station to determine if the screens currently installed in the Centrifuge Feed Tank will pass enough water to decant' it in- a reasonable time span. Although this equipment is part of the Solid Radwaste system,'the system .is in the pre-operational test -stage; therefore, there are no radiologica) concerns at this time.

88-0006 This THR increased the . alarm level setpoints for Channel 4 of the Vibration-and Loose. Parts Monitor for Feedwater Line AZ 210 to their' maximum levels.

This allowed the other 11 channels to alarm in the control room. Channel 4 was in constant alarm due to an undetermined stimuli and masked ~ other channels' alarms. This . problem is under investigation and will be tracked elsewhere. This-THR entrances the ability of the system to provide alarm capability for the remainder of the Vibration and Loose Parts Monitoring System.

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The following Deficiency Requests (DRs) 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 of safety as defined in the basis for any technical specification is reduced.

None of the DRs created a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These DRs 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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Safety Evaluation Description of Deliciency Report (DR) 88-0003 During routine preventive . maintenance, it .was discovered that the "D" , Diesel Generator Jacket Water Pressure Transmitter was out of calibration.

This transmitter is not adjustable and no parts ,

were available when the deficiency- was discovered. A caution tag was hung describing this condition. Because the transmitter is provided for indication only, no automatic _ actions are initiated by it and the deficiency affects the high pressure signal only, it may be used as is until replacement parts are available.

88-0004 During routine preventive maintenance, it was discovered that the "D" Diesel Generator Fuel Oil Header Pressure Transmitter was out of calibration. This transmitter is not adjustable and no parts were available when the deficiency was discovered. A caution tag was hung describing this condition. Because the transmitter is provided for indication only, no automatic actions are initiated by it and a separate transmitter annunciates Low- Fuel Oil Pressure, this transmitter may be used as-is until replacement parts are available.

88-0022 A Fire Pump Test Isolation Valve was discovered to be leaking, causing the Tesc Manifold to fill with water. It was determined that an internal cast flaw burr existed and came into contact with the valve disk, preventing positive seating and ,

causing water to leak through. This Fire Pump is back-up by the Diesel Generator Fire Pump, therefore, its unavailability does not create an unreviewed safety question.

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. Public Service Electric and Gas Cornpany P.O. Box L Hancocks Bridge, New Jersey 08038 Hope Creek Operations February 15, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

HONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operatina statistics for January are being forwarded to you. In addition, the summary of changes, tests, and experiments for January 1988 are included pursuant to the requirements of 10CFR50.59(b).

Sincerely yours,

$t[H S. LaBruna General Manager - ,

Hope Creek Operations h l tN1 TAR: tib Attachment C Distribution I

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The Energy People iI

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