ML20207N476

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

ML20207N476
Person / Time
Site:	Hope Creek
Issue date:	09/30/1988
From:	Hagan J, Jensen H Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8810190175
Download: ML20207N476 (12)

Text

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INDEX NUMBER SECTION OF PAGES I

Average Daily Unit Power Level......................... 1 ,

Operating Data Report.................................. 2 Refueling Information..................................- 1 Monthly Operating Summary.............................. 1 1 Summary of Changes, Tests, and Experiments............. 5 i L

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.86-354 UNIT Hope Creek DATE 10/14/88 COMPLETED BY H. Jensen TELEPHONE (609) 239-5261 MONTH September 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (MWe-Net) 1 1008 17 937 2 1004 18 999 3 1023 19 978 4 1008 20 1005 5 961 21 1006 6 1040 22 996 7 1014 23 962 8 1017 24 947 9 998 25 913 10 991 26 1007 11 1027 27 1033 12 1009 28 947 13 995 29 1013 14 995 30 981 15 1013 16 1013

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• OPERATING DATA REPORT DOCKET NO. _86-354 UNIT Hope Creek DATE 10/14/88 COMPLETED BY H. Jensen s TELEPHONE (609) 339-5261 "p7' OPERATING STATUS

1. REPORTING PERIOD September 1988 GROSS HOURS IN REPORTING PERIOD __720__

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 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) (MWe-Net) None

4. REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE 720.0 5,095.3 12.953.4

5. NO. OF HOURS REACTOR WAS CRITICAL

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 720.0 4,925.8 12,670.9

7. HOURS GENERATOR ON LINE

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED 15,942,803 39,751,370 (MWH) 2.337,150

10. GROSS ELECTRICAL ENERGY 5,235,650 13,147,347 GENERATED (MWH) 771,292

11. NET ELECTRICAL ENERGY GENERATED 4,999,036 12,564,074 739,669 (MWH)

12. REACTOR SERVICE FACTOR 100.0 77.5 82.9 100.0 77.5 82.9

13. REACTOR AVAILABILITY FACTOR

14. UNIT SERVICE FACTOR 100.0 74.9 81.1

15. UNIT AVAILABILITY FACTOR 100.0 74.9 81.1

16. UNIT CAPACITY FACTOR 75.4 (Using MDC) 96.3 71.3

17. UNIT CAPACITY FACTOR (Using Design MWe) 96.3 71.3 75.4 0.0 3.0 6.7

18. UNIT FORCED OUTAGE RATE I

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

1/14/89, mid-cycle, 21 days

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

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

OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTION 3 DOCKET NO.86-354 UNIT Hope Creek DATE 10/14/88 COMPLETED BY H. Jensen' ,

REPORT MONTH. September 1988 '

TELEPHONE (609) 339-5261 HETHOD OF SHUTTING DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

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

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REFUELING INFORMATION COMP 6E'TED'BY: Chris Brennan DOCKET NO.: 50-354 UNIT NAME: Hope Creek Unit 1 DATE: 10/14/88 TELEPHONE: (609) 339-3193 Month September 1988

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: 09-22-89

3. Scheduled date for restart following refueling:

11-07-89

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? 5-07-89

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

6-07-89

6. Important licensing considerations associated with refueling:

_Information not presently available

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

9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: 11-07-89

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HOPE CREEK 1ENERATING STATION MONTHLY Ot' RATING

SUMMARY

SEPTL1BER 1988 Hope Creek entered the month of -September operating at approximately 100% power. On September 21st, power was reduced to 98% when it was discovered that the Feedwater Flow Nozzle Transmitters had incorrect calibration values. A high line pressure correction had not been- included. The calibration ,

values were corrected, the transmitters recalibrated, and the i unit returned to 100%. However power was again reduced to 98% E when the flow nozzle supplier notified unit personnel that they had made an error involving temperature correction factors. The -

unit remained at 98% power for the rest of the month while detailed investigations continued. On September 30th the plant l completed its 32nd day of continuous power operation. l

SUMMARY

OF CHAllGES, TESTS, AllD EXPERIMEliTS FOR THE HOPE CREEK GEllERATIllG STATIO!!

September 1988

'Tho.following Design Changa Packages (DCPo) have been ovaluated to do,termina:

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 a -:ident 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 affluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

7 RCE ' Description of Desien Chance Packace

'4HMM-86-0861 This DCP replaced Filter Aid Pump Discharge Relief Valves in the Solid Radwaste system with a different model. The original model is no longer available. The new model meets all design requirements.

4EC-1002/17 This DCP relocated the Source Range Moniter/

Intermediate Range Monitor Preamp Panel and reworked the associated conduits. The. panel ,

needed to be moved so that it.would not interfere with the other modificiations that are required to complete work on the Control Rod Drive Repair and Removal Room.

4HC-0041 This DCP permanently installed a flow totalizer ,

and a square root extractor which had been previously installed by a Temporary Modification Request. These two instruments provide indication of the total amount of fuel oil consumed by the i Auxiliary Boilers.

4HC-0050/02 This DCP installed an underground waste transfer line from the Hope Creek Makeup Demineralizer Regenerant Waste Tank Recirculation Pump to the transfer line in the Salem Nuclear Generating Station yard area. The waste transfer line will reduce operating expenses associated with the transportation of regenerant waste.

4HH-0237 This DCP modified the temperature control loops on the Solid Radwaste Extruder / Evaporator. It established new setpoints based upon the actual  !

operating band and the ability of the Extruder /

Evaporator to produce a good end product. It also revised the Instrument Calibration Data Cards.

4HH-0360 This DCP rerouted the Inlet Line Feeding Radiation '

Monitor from the downstream side of the Circulating Sump Pumps to the upstream side of the the pumps. Rolocating the monitor will avoid the 1 backflow from the cooling tower. -

4HH-0408 This DCP changed the damping adjustment on the Average Power Range Monitor / Rod Block Monitor recorders and Low Power Range Monitor indicators in the Control Room. This will result in the ,

minimum damping required to provide adequate response to core power oscillations.

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The following Temporcry Modificction Rcqusste (THRc) hevo bacn ovaluated to d2 termino:

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 l

environmental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

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n0 . Safety Evaluation Q1scription'of Temporary Modification Reauest

,' (TMR) 87-0086 This TMR installed a steam hose from the Solid Radwaste ' Auxiliary Boiler to the Nitrogen Vapori,z er . This temporary hose allows the Auxiliary Boilers to be removed from service.

The Radwaste steam supply will therefore . provide the steam for the vaporization of the Nitrogen.

This THR had previously- been installed and removed. It is again required to support an, Auxiliary Boiler outage.

88-0107 This THR lifted the leads to the relay that positions the "B" Reactor Recirculation Pump Scoop Tube for a' restart. This relay had inadvertently energized, resulting in a Recirculation Pump runback. This THR also installed a recorder on the lifted leads to record additional unexpected contact closures to assist in the troubleshooting process.

88-0109 This THR installed a plate over a leak in a weld on an elbow joint at the common supply of Service Water and the Reactor Auxiliaries Cooling System.

The plate prevents spraying of water onto equipment in the area.

88-0110 This THR installed a plate over a leak and wall-thinning area in the Service Water piping. This area is located near the outlet of the "B" Reactor Auxiliaries Cooling System Heat-Exchanger. The plate prevents spraying of water onto equipment in the area.

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O PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Operations October 14, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY 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 operating statistics for September are being forwarded to you. In addition, the summary of changes, tests, and experiments for September 1988 is included pursuant to the requirements of 10CFR50.59(b).

Sincer ly yours,

. Haga General Manager - 4 Hope Creek Operations dRAR:tib V Attachment  !

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