ML20246P952

Monthly Operating Rept for June 1989 for Hope Creek Generating Station,Unit 1

ML20246P952
Person / Time
Site:	Hope Creek
Issue date:	06/30/1989
From:	Brennan C, Hagan J, Jensen H Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8907200376
Download: ML20246P952 (13)

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.Putilic Service Electric a' n d Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038

. Hope Creek Generating Station '

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.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 Incompliance.with Section 6.9, Reporting Requirements for'the Hope Creek Technical Specifications, the. operating statistics for June are'being forwarded to you with the summary of changes, tests, and experiments for June 1989 pursuant to the requirements of 10CFR50.59(b).

Sincerely yours,

. Hagan General Manager -

Hope Creek Operations h AR:bjh Attachment

'C Distribution 8907200376 890630  ?

. ~lR ADOCK 05000354 .

R PDC On

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Daily Unit-Power l Level............"..........'...< 1D H ,

j H Operating:Dat'a Report;.....-.'..'............~............. . : 2' , I 4 ,q E ' Refueling;Information.................'.............'....- 10 I b ,

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H' i M o n t h l y ' O p e r a t i n g ' S u m m a r y . .~. . . . . . . . . . . . . . .'... . . . . . . . .'. .'. . L 1'-

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s SL .SummaryLof. Changes, Tests,-and Experiments..............

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< , .l t e t LAVERAGE DAILY UNIT POWER LEVEL h

DOCKET'NO. 50-354 UNIT Hope' Creek s DATE- 7/15/89 COMPLETED.BY H. Jensen TELEPHONE (609) 339-5261 MONTH June 1989 DAY AVERAGE DAILY POWER LEVEL DAY' AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1050 17 1022 2- 976 18 1065 3 1065 19 1021 4 1020- 20 1013 5 1033 21 946 6 1025 '22 1018

.7 1032 23 1020 8 1003 24- 989 9 1032 25 1040 10 892 26 999 11 1026 27 1026 12 __

1023 28 1008 13 1037 29 1047 14 1009 30 1040 15 1019 16 1025 s

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OPERATING DATA REPORT y 4 DOCKET NO. 50-354 UNIT Hope Creek DATE 7/15/89 COMPLETED'BY H. Jensen 48'/_

TELEPHONE' -(609) 339-5261 - 7 -

OPERATING 1 STATUS L 1.- REPORTING PERIOD June 1989 ' GROSS HOURS IN REPORTING PERIOD 720

2. CURRENTLY AUTHORIZED POWER LEVEL-(MWt) 3293 MAX. DEPEND.: CAPACITY (MWe-Net) 1031

. DESIGN ELECTRICAL RATING (MWe-Net) 1067

13. 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 720.0 -3.940.9- 18,888.5

'6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0- 0.0

7. HOURS GENERATOR ON LINE 720.0 3,935.6 18,567.7

8. ' UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. ' GROSS THERMAL ENERGY GENERATED (MWH) 2,348,368 12,706,617 58,710,331

10. GROSS ELECTRICAL ENERGY GENERATED-(MWH) 762,970- 4,185,569 19,412,013

11. NET ELECTRICAL ENERGY GENERATED (MWH) 731,385 4,006,566 18,556,666

-12. REACTOR SERVICE FACTOR- 100.0 90.7 85.2

13. REACTOR. AVAILABILITY FACTOR 100.0 90.7 85.2

14. UNIT SERVICE FACTOR 100.0 90.6 83.7

15. UNIT AVAILABILITY FACTOR 100.0 90.6 83.7

- 16 . - UNIT CAPACITY FACTOR (Using MDC) 98.5 89.5 81.2

17. UNIT CAPACITY FACTOR (Using Design MWe) 95.2 86.5 78.4.

18. UNIT FORCED OUTAGE RATE 0.0 0.2 5.9

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

Refueling, 9/15/89, 50 days

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

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l OPERATING DATA REPORT UNIT' SHUTDOWN 6 AND POWER REDUCTIONS DOCKET NO. ,_50 ,,A54 UNIT ligge Creek Unit._1 DATE ~7/15/89 COMPLETED BY _H. . Jenper REPORT MONTH JuO_e_1989 TELEPHONE _(AQ9)-339_,52bj METHOD OF .,

SHUTTING ,,

DOWN THE ,

. TYPE REACTOR OR ,

F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) -(1) POWER (2) COMMENTS ,

6 6/10 F 0 B 5- Circulating. Water j Pump Maintenance .

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SUMMARY

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REFUELING INFORMATION l

-I COMPLETED BY: Chris Brennan ' DOCKET NO: 50-354 UNIT NAME: Hope Creek Unit 1 DATE: ~7/15/69-TELEPHONE: 3193 s EXTENCION: N/A j l

-Month July 1989 j i

1. Refueling information has changed from icst month: -j YES NO X -]

2. Scheduled date'for'next refueling: 09-15-89 j

3. Scheduled date for restart following refueling: 11-05-89

4. A) Will Technical Specification changes or other license amendments.  :

be required? l

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

i YES NO X If no, when-is it scheduled? 8-01-89 S. Scheduled'date(s) for submitting proposed licensing action:

1 03-89

6. Important. licensing considerations associated with refueling:.

-NRC Generic Letter 88-16 type submittal has been-made and will be used for Cycle 3 operation. Reactor Encineerina will recuire an LCR for their control blade desian chance.

7. Number of Fuel Assemblies:

A) Incore 764 B) In Spent Fuel Storage.(prior to refueling) 232 C) In Spent Fuel Storage (after refueling) 496

8. Present licensed spent fuel storage capacity: 1290 Future Spent' fuel storage capacity: 40J6

9. Date of last refueling'that can be discharged to spent fuel pool assuming

'the present licensed capacity: 3-13-91

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• + 1 HOPE CREEK GENERATING STATION MONTHLY OPERATING'

SUMMARY

June 1989 e

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, - Hope Creek' entered the. month.of~ June operating at 100% power. On f.': June.10, power was reduced to 80% to support surveillance-testing

( and circulating water pump maintenance.. Later the same-day power I was returned'to 100%.- On June :30 the plant completed its 116th day of continuous power' operation.

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SUMMARY

OF CHANGES TESTS, AND EXPERIMENTS i i

FOR THE HOPE CREEK GENERATING STATION June 1989 1

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qThe'following Design Change Packages (DCPs) have- been evaluatedt 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 ibe ~ ~ '

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 bc. 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.

i 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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EdE ' Description of Desian Chance Packaae-4EC-1024/10 i This DCP~added ladders-and platforms tolaccess the j I

Emergency Diese1L. Generator Jacket-. Water ' Cooling Expansion l Tanks. This DCPL is a -part of .the-project.to improve. safety conditions.and.to

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compliance'with' OSHA requirements. ij

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' 4EC-1024/17: This DCP added :a' platform ~ for: access'- to. 'and 11

. maintenance of the' Iso-phase Generator Bus.. This -l DCP is a part.of the project- to' improve _ _ safety ,

conditions and- to ensure-; compliance' with- OSHA requirements.-

4HC-0240 This DCP replaced manually _ operated bypass- valvest in the Reactor Water Cleanup System with- air aj operated remote . control valves. 1This. DCP' will~  ;

reduce radiation exposure.which .occ'rredu during- l

. valve manipulation -j

.I 4HM-0134 This. DCP relocated the instrument tap for'the Low 1 Discharge Pressure Switch on the: Decontaminated' )

concentrate Waste Transfer Pump. The switch.  ;

sensed a low pressure condition on each surge of! l the. pump at its original location. d 4HM-0156. This DCP replaced Struthers Dunn. relays. with.

Agastat relays. The new relays Ewill. reduce the-  ;

susceptibility of :the Standby _ Liquid = Control:

System Pump start circuit to spurious actuations _

from 'the Redundant ~' Reactivity Control System self-test pulses.- 1 4HM-0158 This DCP added an Oil Recovery'. System to the ..;

Turbine' Building Chillers to maintain a constant sump level. The- constant. level will help .to -

preclude trips due to either low lube oil level or  !

high' oil temperature.

4HM-0245 This DCP added 4 flange sets to the discharge-piping of the Reactor Building Equipment Drain Sump Pumps. 'One set was installed upstream of each discharge valve and 1 set downstream of each recirculation valve. This will reduce the radiation exposure required to perform maintenance on the pumps and will allow one= pump to be. removed without taking the other one out of service.

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E < hqi' Description of-Desian Chance'Fackaae-L 4HM-0272 This DCP relocated smoke detectors .:Ln the : Reactor' Building. In their' original position, their'

?- Esignal beams were' often obstructed- by the cable drum.on the polar' crane, causing false alarms.

4HM-0289' This DCP relocated the . upper level' probe.for- the g Steam Dome Boilout- Tank.- Relocating 'the probe will reduce. the amountof water exiting the L Extruder / Evaporator..

, 4HM-0402 This DCP raisedethe trip- setpoints of thel. low pressure switches on' the Turbine Build 2ng!

Chillers. The revised- setpoints. will. prevent:

f water'from freezing in the Evaporator,TubesE while shutting down or trippingithe. chillers due to -low.

L Freon level or charge.

F "4HM-0413- This DCP decreased the size.of the orifice in the'  ;

Inlet Valve Bypass Line- to the- Filter

' Demineralized. + This will increase the. I pressurization time. when placing a filter.

Demineralized i'a service.and will' limit.the ' flow I through the orifice. This will prevent. ESF actuations during demineralized's pressurization 4HM-0516 This test DCP aligned the Core Spray system for: 1 full flow test and operated. each pump discharge .j valve to simulate' strong-weak pump flows. This allows data to be gathered and evaluated to

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F establish acceptance criteria for the In-Service Test Program, k

4HM-0547 This DCP installed a filter / dryer assembly to the I "D" Turbine Building Chiller. This assembly will  !

filter the refrigerant in'the machine against any ,

contamination or acid which may have formed. 1 o  : '

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h 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 n 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 1 l

3) if the margin of safety as defined in the basis for any technical specification is reduced.

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 Description of Temporary Modification Request (TMR) 89-0042 This THR lif ted a lead in the "C" Class :US Digital Termination Cabinet and- one in the "D" Class lE Digital Termination ~ Cabinet. The lifted leads will eliminate spurious nuisance alarms in the Control Room. The spurious alarms-were the " Low Inlet Pressure" alarms for the "A" and "B" Control:

Room Supply Fans.

89-0045 This TMR bypassed a' failed vibration monitoring probe for the "A" Reactor Recirculation- Pump.

Bypassing the failed probe will . eliminate a nuisance alarm in the Control Room. . Indication will be provided- from a second probe located on the "A" Reactor Recirculation Pump.

89-0048 This TMR added a jumper to the High Oil Temperature Switch-to permit the "A" Control Room Chiller to run with a defective module and/or thermistor until a replacement part can be

! procured and installed. The installation of this jumper disabled the High Bearing Oil Temperature trip. The oil temperature will be periodically monitored by an operator while, the trip. is y disabled.

89-0052 This THR installed a manually operated valve in lieu of the air operated Waste Sludge- Phase Separator valve. The valve- was leaking through and no spares are immediately available.

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