ML20195B890

Monthly Operating Rept for May 1988 for Hope Creek Generating Station Unit 1

ML20195B890
Person / Time
Site:	Hope Creek
Issue date:	05/31/1988
From:	Jensen H Public Service Enterprise Group
To:
Shared Package
ML20195B894	List: ML20195B890 ML20195H484 ML20195H520 ML20195H616
References
NUDOCS 8806220038
Download: ML20195B890 (13)

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AV3 RAGE DAILY UN'." POWER LEVEL .

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a L DOCKET No.86-354 .

4 UNIT Hoce Creek l DATE _iLJ5/88 .

COMPLETED BY H. Jensen'  !

1 TELEPHONE (609) 339-5261 i

HONTH May 1988 3 E

I DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

(MWc-Net) (MWe-Net)  !

1 1 0 17 1017 2 0 18 1012 ,

3 607 19 1005  ;

8 j 4 1044 20 1024

~

5 361 21 1012 j 6 396 22 1013  !

7 1017

• 23 994 -

l 8 1017 24 1007 l 9 1008 25 1021 ___

10 1031 26 1020

• i 11 1030 27 1013

! 12 998 28 1025 13 _ _ , 1013 29 989

14 1009 30 1010 l 15 1013 31 1000 3

16 1018

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• 8806220038 880 fi PDR ADOCK 050 54 ,

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4 Qf33ATING DATA REPj2fJ.

DOCKET NO. _86-354 UNIT __ Hope Creek DATE 6/15/88 COMPLETED BY TELEPHONE H. Jensqr (609) 339-5261 (N

OPERATING STATUS

1. REPORTING PERIOD May 1988 GROSS HOURS IN REPORTING DERIOD 744

2. CURP.ENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEDEND. CAPACITY (MWe-Net) 1067 (1)

DESIGN ELPSTRICAL RATING (HWe-Net) 1067 (1)

3. POWER LEVEL TO WHICH RESTkICTED (IF ANY) (MWe-Net) Nop.e

4. REASONS FOh RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE

5. NO. OF HOURS REACTOR WAS CRITICAL 688.7 2316.1 _10s074.2__

6. REACTOR RES5RVE SHUTDOWN HOURS 0- 0 0

7. HOURS GENERATOR ON LINE 666.8 _2060.0 .

9805.1

8. UNIT .iESERVE SHUTDOWN HOURS O ,

O O

9. GROSS THERMAL ENERGY GENERATED (MWH) 2,165.136 _6,668,99L_ 30,477,559

10. GROSS ELECTRICAL ENE*.GY GENERATED (MWH) 714,205 2,217.173 10,1212371

11. NET ELECTRICAL ENER9a 'MERATED (MWH) 68),964 2,107,845 9,672,873

12. REACTOR SERVICE FACTOR 92.6 60.8- __ 79.4

13. REACTOR AVAILABILITY FACTOR 92.6 60.8 , 79.4

14. UNIT SERVICE FACTOR 89.6 56.5 77.2

15. UNIT AVAILABILITY FACTOR 69.6 ___

56.5 77.2

16. UNIT CAPACITY FACTOR (Using Design MDC) 86.2 54.2 71.4 1

17. UNIT CAPACITY FACTOA (Usina Design HWei 86.2 54.2 71.4 l

18. UNIT FORCED OUTAGE RATE 10.4 4.3 8.0 l

19. SHUTLOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. & DURATION):

N/A

20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATE'u DATE OF STARTUP:

N/A (1) August 1987 data is under management review.

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i OPERATING DATA REPORT UNIT SHUTDOWUS AND POWER REDUCfIONS DOCKET NO.86-354 UNIT Hope Creek DATE 6/15/88 COMPLETED BY H. Jensen REPORT MONTH May. 1988 TELEPHONE (609) 339-5261 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) POWER (2) COMMENTS 5 5/1 F 50.4 A 4 CONTINUATION OF 4/30/88 FORCED OUTAGE 6 5/05 F 26.8 A 3 AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL DUE TO "B" REACTOR FEED PUMP TURBINE TRIP.

LER 88-013

SUMMARY

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REFUELING INFORMATION COMPLETED BY: Chris Brennan DOCKET NO.: 50-354 UNIT NAME: . Hope Creek Unit 1 DATE: 6/15/88 TELEPHONE: 3193 EXTENSION: N/A Month May 1988

1. Refueling information has changed.from last month:

YES liO X

2. Scheduled date for next refueling: 11-04-89

3. Scheduled date for restart following refueling:

12-18-89

4. A) Will Technical Specification changes or other license amendments be required?

YES X NO B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? 6-18-89

5. Scheduled date(s) for submitting proposed licensing action:

7-18-89

6. Important licensing considerations associated with refuelina:

Information not oresently available

7. Number of Fual Assemblies:

A) Incore 764 B) In Spent Fuel Storaae 232

8. Present licensed spent fuel storage capacity: 1108 Future spent fuel storage capacity: 4006

9. Pate of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: 12-18-89

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l l HOPE CREEK GENERATING STATION I MONTHLY OPERATING

SUMMARY

l MAY 1988 l

( The unit remained in shutdown at the beginning of May due to the

! manual reactor scram which occurred on April 30. The generator was synchronized to the grid at 2:22 am on May 3. There was an automatic reactor scram at 9:17 am on May 5 on low reactor water level due to the "B" Reactor Feed Pump Turbine trip. The unit was returned to service on May 6 and was synchronized to the arid-at 12:08 pm on that date. As of May 31, the unit has been online for 25 consecutive days.

R-011 RAR:tlb l

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS ,

1 FOR THE HOPE CREEK GENERATING STATION '

HAY 1988 I

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-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 chance 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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QQE Description of Desian Chance Packace 4-HMO-86-0514 This DCP removed the . splash guards and their holdown bolts from the Reactor Recirculation-Pumps.- The splash guards were removed'because of interference that was encountered involving vibration monitoring probes, thermocouples and'the splash guards. It was determined that the splash guards did not fulfill a necessary function and '

could, therefore, be removed.

4EC-10E9 This CCP permanently incorporated a Temporary Modification to the Reactor Feedwater Level control system. This modification added a function generator in the Start-Up Level Control portion of the system. This DCP verified the proper installation of the function generator.

4EC-1082/11 This DCP labeled indicators and recorders in the Control Room. The labelina will assist the operators in determining which parameters are part-of Accident-Monitoring Instrumentation or System Operation and Effluent-Monitoring Instrumentation.

4HM-0141 This DCP permanently installed 3 Temporary Modifications in the Filtration, Recirculation, and Ventilation System. The modification installed new flow sensors, temperature compensation resistors, and factory installed circuit modifications to isr vide increased ]

stability. l 4HM-0146 This DCP installed flanges and spool pieces on the steam and water supply lines to the Desuperheater in the Solid Radwaste system. This DCP allows i maintenance to be performed on the Desuperheater without cutting and re-welding piping, which was ,

required by the previous design.

4HM-0149 This DCP changed the alarm setpoints for the Generator Temperature High Annunciator to implement vendor recommendations and applicable operatina experience. It also corrected the Recorder Analog Calibration Span.

4HM-0189 This was a document chance only DCP to update drawings to reflect the deletion of the lantern rings in the packing gland of a control valve in the Safety Auxiliaries Cooling System. The lantern ring packing design represents an old technology and has been replaced with self-lubricating packing as the resolution for a Deficiency Report.

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DCP Description of Desion Chance Packace 4HM-0239 This DCP added a time delay to the Instrument Air Dryer Circuitry to allow for momentary high flow conditions during Dryer Towur Jycle Swaps. It will also prevent a local Hig't Flow Alarm from occurring during the swap.

4HM-0285 This DCP changed the Solid Radwaste Extruder Evaporator torque setpoints to allow the Extruder Evaporator to operate without spurious trips of the metering pumps. Changing the setpoints also allowed the high-high setpoint to be set. The

-previous high-high setpoint was at the top of the instrument range and did not allow for consistent calibration.

4HM-0303 This DCP was a component change out DCP which replaced the existing NA-200 type Local Power Range Monitors with a GE authorized replacement, the NA-300 detectors. The new model meets or exceeds the original design in fit, form and function.

4HM-0342 This DCP increased the reliability of the Control Room Chilled Water . System by replacing the High-Side Ball Floats with High-Side Ball Floats with Reinforcement Pads. The new Ball Float is identical to the original in fit, form, and 1 function; and meets or exceeds the existing I component specitications.

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The following Temporary Modification Requests (THRs) have been evaluated to determine:

1) if the probability of occurrence or the consequences of an accident or malfunction of quipment. 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 che 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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Eafety Evaluation Description of Temocrary Modification Recuest (THR) 88-0079 This THR added a jumper across contacts for a ,

defective High Oil Temperature Sensor until a replacem. int sensor is available. The sensor ~ is located -in the "B" Turbine Building Chiller, adding the jumper will allow . the chiller to operate. An operator will monitor the associated temperature indicator while the THR is in place and the chiller will be used as -a back-up only-during that time period.

88-0079 This TMR allowed for the installation of a temporary spool piece within the Cation Vessel of the Condensate Demineralizer system. The original spool piece required replacement; during the replacement it was discovered that the horizontal header was bent, necessitating a longer spool.

88-0080 This TMR installed a blank flange between 2 existing flanges in a line to a containment penetration. The additional flange reduced the leakage rate of the penetration and restored its integrity.

88-0081 This THR installed an isolation valve in the )

supply line and a cap on the discharge line of the Emergency Bearing Oil Pump Low Operating Oil Pressure Test Solenoid Valve. The solenoid was )

leaking by, causing a low operating oil pressure l signal which caused the pump to run continuously.

The installation of the valve will allow repair of the solenoid when parts are available and the cap l will eliminate the low pressure signal that starts the pump.

88-0082 This THR installed a jumper around the Automatic  !

Reset Switch for a Control Room Supply Vent Unit '

Temperature Switch. The temperature switch is designed to turn off the Control Room Supply Ventilation Heaters at 200*F and automatically resets at a lower value to prevent overheating of the heater coils while maintaining the Control Room within its designed environmental boundaries.

The switch limits the temperature of the heater element only and is backed up by a manually reset j trip at 250*F, which will function normally.

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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 cafe shutdown of the reactor. Those 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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e Epfety Evaluation Description of' Deficiency Recort (DR) 88-0072 This Safety Evaluation approves the use-as-is disposition of. 2 DR's dealing with check valve welds. The preheat temperatures of these welds were not recorded on the Code Job Package forms.

However, due to the location and function of these 2 valves, the failure to record the preheat temperatures did not adversely impact the ability of the valves to operate as designed.

88-0073 The torque wrenches used to torque pivot -mount bolts on 1/4" and 1/2" mechanical snubbers have an operating range of 30-200 inch-pounds.

However, the torque wrenches were adjusted to 22 inch-pounds because the vendor manual specified a torque range of 20-28 inch-pounds for these bolts.

A sample of the bolts was re-checked and verified to be acceptable.

88-0075 A pivot mount attachment bolted to a snubber was incorrectly torqued to 22 inch-pounds. The vendor manual specifies a torque valve of 45 inch-pounds.

The desian torque valve was selected assuming a load larger than exists in the current application; therefore, a torque valve of 22 inch-pounds is acceptable in this application.

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