ML20154R108

Monthly Operating Rept for Aug 1988 for Hope Creek Unit 1

ML20154R108
Person / Time
Site:	Hope Creek
Issue date:	08/31/1988
From:	Brennan C, Hagan J, Jensen H Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8810040164
Download: ML20154R108 (13)

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AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO.86-354 UNIT Hoce Creek DATE 9/15/88 COMPLETED BY H. Jensen TELEPHONE (609) 339-5261 MONTH _Auaust 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (liWe-Ne t )

1 989 17 995 2 983 18 1014 3 980 19 996 4 990 20 822 5 950 21 1011 6 533 22 1009 7 570 23 1014 8 997 24 1005 9 867 25 992 10 999 26 744 11 1003 27 0 12 972 28 0 13 996 29 454 14 989 30 1010 15 969 31 993 16 1001

/f 8G10040164 880831 PDR ADOCK 05000354 R PDC

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OPERATING DATA REPORT DOCKET NO.86-354 UNIT Hope Creek DATE 9/15/88 COMPLETED BY H. Jensen Al[f' h TELEPHONE (609) 339-5261 OPERATING STATUS

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

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt) 3293 HAX. DEPEND. CAPACITY (HWe-Net) 1067 (1)

DESIGN ELECTRICAL RATING (HWe-Net) 1067 NAMEPLATE RATING (GROSS HWe) 1170

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Not) None

4. REASONS FOR RESTRICTION (IF ANY)

THIS YR TO HONTH DATE CUMULATIVE

5. NO. OF HOURS REACTOR WAS CRITICAL 695.2 4,375.3 12,333.4

6. REACTOR RESERVE SHUTDOWN HOURS 0 0 0

7. HOURS GENERATOR ON LINE 681.8 4,205.8 11,950.9

8. UNIT RESERVE SHUTDOWN HOURS 0 0 0

9. GROSS THERHAL ENERGY GENERATED (HWH) __2,161,396 13,605,653 37,414,220

10. GROSS ELECTRICAL ENERGY GENERATED (HWH) 691.963_ 4,464,357 12.376,055

11. NET ELECTRICAL ENERGY GENERATED (HWH) 660,565 4,259,367 11,824.405

12. REACTOR SERVICE FACTOR 93.4 74.7 82.1

13. REACTOR AVAILABILITY FACTOR 93.4 74.7 82.1

14. UNIT SERVICE FACTOR 91.6 71.8 80.2

15. UNIT AVAILABILITY FACTOR 91.6 71.8 __

80.2

16. UNIT CAPACITY FACTOR (Using HDC) 83.2 68.2 74.4

17. UNIT CAPACITY FACTOR (Using Design HWe) 83.2 68.2 74.4

18. UNIT FORCED OUTAGE RATE 8.4 3.5 7.1

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

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

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

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

OPERATING DATA REPORT-UNIT SHUTDOWNS AND POPER REDUCTIONS DOCKET NO.86-354 UNIT Home Creek DATE 9/15/48 COMPLETED BY H. Jensen REPORT MONTH Aucust, 1988 TELEPHONE (609) 339-5261 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F "ORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S aHEDULED (HOURS) (1) POWER (2) COMMENTS 8 8,' 6 F 0 A 5 'A' REACTOR RECIRCULATION PUMP PROBLEMS 9 8/26 F 62.2 A 3 AUTOMATIC REACTOR SCRAM DUE TO A TURBINE TRIP DURING THE PERFORMANCE OF A WEEKLY MAIN TURBINE FUNCTIONAL

' TEST. LER 88-022 l

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REFUELING INFORMATION COMPLETED BY: Chris Brennan DOCKET NO.: 50-354 UNIT NAME: Noce Creek Unit 1 l DATE: 9/15/88  :

TELEPHONE: (609) 935- '

F M: nth Auaust 1988

1. Refueling information has changed from last month:

YES NO X l

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

3. Scheduled date for restart following refueling i 11-07-89 l I

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

YES X NO p B) Has the reload fuel design been reviewed by the Station Operating  ;

Review Committee?

YES NO X j If no, when is it scheduled? 5-07-89 f

5. Scheduled date(s) for submitting proposed licensing action-6-07-89

6. Important licensing considerations associated with refueling:

Information not oresentiv available ,

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7. Number of Fuel Assemblies:

Al Incore 764 ,

B) In Spent ruel Storage 232 I

8. Present licensed spent fuel storage  !

capacity: 1108 l

, Future spent fuel storage capacity: 4006 L

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

{ the present licensed capacity: 11-07-89  !

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HOPE CREEK GENERATING STATION HONTHLY OPERATING

SUMMARY

, AUGUST 1988 The unit entered the month of August at approximately 100% power.

Power was reduced on August 6 due to problems with the "A" Reactor Recirculation Pump. The pump was repaired and power was restored to 100%. At 6:25 PM on August 26, the reactor scrammed due to a turbine trip during the performance of a weekly Main Turbine Functional Test. The plant had been on-line for 112 consecutive days. The unit was returned to the grid at 7:30 AM on August 29.

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SUMMARY

OF CHAliGtl., TESTS, AllD EXPERIMENTS FOR THE HOPE CREEK GENERATING STATIO!!

AUGUST 1988 l

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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.

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

1 QEE Description of Desian Chance Packace 4EC-1082/02 This DCP incorporated a fix for a human engineering deficiency that was reported during the Control Room Design Review. The Off-Gas section of the Hain Control Panel contained unnecessary components. The unnecessary lenses were removed and replaced with a single blank, which was weighted to comply with seismic considerations.

4HC-0074/03 This DCP upgraded the firmware and software in the Liquid Radwaste Radiation Monitoring System. The upgrades included a logic table defining monitor operate status, a digital input representing flow, a software time delay to monitor operate status change, a digital reset to reset monitor operate status, and a manual override switch to override a system isolation signal under false indication.

These changes eliminated the need for operator aids, THRs, and operator intervention.

4HC-0089 This DCP provided for the proper routing of conduit associated with the Crystallizer vapor Body Level Control instruments. The DCP shortens the distance from tre transmitters to the level probes to obtain a more precise instrument reading. This DCP also installed new scales in the Radwaste Control Room.

4HH-0004 This DCP replaced temperature switches in the Turbine Building Chilled Water System. The original switches did not have an adjustable deadband. The new switches will also support a setpoint change to prevent excessive chiller recycling.

4HH-0109 This DCP relocated the Reactor Recirculation Motor / Generator Set Fluid Coupler Pressure Differential Switches to eliminate oil from leaking into the switch housing. It also re-tubed the sensing lines to maintain a positive downward slope from the instrument to the fluid drive.

Additionally, this DCP changed the associated computer points from "close to alarm" to "open to alarm".

4HH-023G This DCP deleted the bridge third speed of the 7 1/2 ton Radwaste crane. The speed was deleted because it was determined to be too fast for the available space. The DCP also corrected a drawing error dealing with the wiring for the Honorail Hoist Stop Limit Switch.  ;

Egg Egarrintion of Desian Chance Packaae 4HH-0299 This DCP raised the alarm setpoints on 228 heat trace controllers from a 10 deviation to a- 15 deviation. Raising the setpoints eliminated nuisance alarms and ensured that future "Heat Trace System Trouble" alarms would be more meaningful.

4HH-0312 This DCP was a change-out DCP that replaced the  ;

High Voltage Power Supply in the In-line Duct  !

Monitors and the Drywell Leak Detection Radiation i Monitoring System Noble Gas Monitor. The new power supplies are an improved design that provide l additional reliability by eliminating the failure l mechanisms due to heat buildup.  !

4HM-0315 This DCP installed Secondary Turbine Vibration i Instrumentation on existing shaft rider detectors for diagnostic and monitoring purposes. The information obtained through the monitoring will  ;

be used to improve the reliability of the Main '

Turbine.

4HM-0369 This DCP was a paper change only DCP. It corrected discrepancies between vendor documents, '

plant design documents, and Instrument Calibration Data Cards. The documentation now reflects current plant configuration for the Chilled Water system.

4HM-0389 This DCP replaced the steam trap in a section of ,

pipe that is isolated on a High Pressure Coolant '

i Injection start signal. The old steam trap is no longer being manofactured, the new steam trap is  !

equally qualified for the application, t

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The following Temporary Hodification Reqttests (THRs) have been l ovaluated 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 3

increased; or 1

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.

4 None of the THRs created a new safety hazard to the plant nor did they offect the safe shutdown of the reactor. These THRs did not change j the plant effluent releases and did not alter the existing

! cnvironmental impact. The Safety Evaluations determined that no

' unreviewed safety or environmental questions are involved.

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'. '.' l Safety Evaluation Descriotion of Temocrary Modification Recuest 1T1181 88-0101 This THR raised the radial vibration alarm setpoint on the 'B' Secondary Condensate Pump.

This change allows the retention of the ability to detect vibration changes and the elimination of nuisance annunciator alarms in the Control Room, without affecting the associated danger setpoint.

88-0104 This THR added a jumper across contacts on pressure switches to operate the Turbine Building chillers until data for a design change to increase the setpoint can be developed. Each chiller is equipped with two pressure switches.

This THR jumpers out the pressure switches with the lower setpoint. This THR is required due to higher than normal Chiller Condenser pressure caused by abnormally hot weather.

88-0106 This THR removed the operator from a valve in the Turbine Auxiliaries Cooling System Domineralizers and gagged the valve open. This allows the Demineralizer to be returned to service to maintain the systems water chemistry within specifications.

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,o O PSIRG Putal c Serv ce Dectnc and Gas Cce pany PO Box 236 Hancoch Bndge. New Jersey 03033 Nuclear Department September 15, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sir MO!!THLY OPERATIllG REPORT HOPE CREEK GEllERATI!!G STATIO!! UllIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for August are being forwarded to you. In addition, the summary of changes, tests, and experiments for August 1988 4, s included pursuant to the requirements of 10CFR50.59(b).

Sincerely yours,

.,[s}Ad J.i Hagan Geheral Manager -

Hope Creek Operations RKARAR:tib Attachment C Distribution w e, , w ,t

INDEX NUMBER SECTION OF PAGES Average Daily Unit Power Leve1......................... 1 Operating Data Report.................................. 2 Refueling Information.................................. 1 Monthly Operating Summary.............................. 1  !

Summary of Changes, Tests, and Experiments............. 6 i

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