ML20151V311

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

ML20151V311
Person / Time
Site:	Hope Creek
Issue date:	07/31/1988
From:	Jensen H, Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8808220226
Download: ML20151V311 (14)

Text

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AVERAGE DAILY UNIT POI.'ER LEVEL DOCKET NO.86-354 UNIT

_ Hope Creek DATE 8/15/88 COMPLETED BY H. Jensen TELEPHONE (609) 339-5261 MONTH July 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1021 17 995 2

1012 18 969 3

1000 19 989 4

996 20 986 5

993 21 981 6

997 22 982 7

992_

23 984 8

994 24 S89 9

993 25 1006 10 991 26 984 11 999 27 998 12 975 28 948 13 987 29 988 14 989 30 988 15 993 31 985 16 986 8808220226 880731 gDR ADOCK0500{g54

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OPERATING DATA RErp,11 DOCKET NG.86-354 UNIT Hope Creek DATE 8/15/88

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Jensen TELEPHONE (609) 339-5261 OPERATING STATUS 1.

REPORTING PERIOD July 1988 GROSS HOURS IN REPORTING PERIOD,,,,744 2.

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

DESIGN ELECTRICAL RATING (HWe-Net) 1067 (1) 3.

.OWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Net)

None 4.

REASONS FOR RESTRICTION (IF ANY)

THIS YR TO HONTH DATE CUMULATIVE 5.

NO. OF HOURS REACTOR WAS CRITICAL 744.0 3.680.1 11.538.2 6.

REACTOR RESERVE SHUTDOWN HOURS 0

0 0

7.

HOURS GENERATOR ON LINE 744.0 3.524.0 11.269.1 8.

UNIT RESERVE SHUTDOWN HOURS 0

0 0

9.

GROSS THFRMAL ENERGY GENERATED I

(HWH) 2.445.594,11.444.256 35.252,824 10.

GROSS ELECTRICAL ENERGY GENERATED (HWH) 791.843 3.772.394 11.684.092_

11.

NET ELECTRICAL ENERGY GENERATED (HWH) 759.077

__j.598.802 11,163.840 j

12.

REACTOR SERVICE FACTOR 100.0 72.0 81.5 l

13.

REACTOR AVAILABILITY FACTOR 100.0 72.0 81.5 l

14.

UNIT SERVICE FACTOR 100.0 68.9 79.6 t

15.

UNIT AVAILABILITY FACTOR 100.0 68.9 79.6 16.

UNIT CAPACITY FACTOR i

(Using Design HDC) 95.6 66.0 73.9

• 7.

UNIT CAPACITY FACTOR (Using Design HWe) 95.6 66.0 73.9 18.

UNIT FORCED OUTAGE RATE 0.0 2.6 7.0 i

19.

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

i 1/14/89, mid-cycle, 21 days 20.

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

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

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OPERATING DATA REPORT UNIT SHUTDOWNS AND PN!5R REDUCTIONS DOCK'T No.86-354 UNIT Hope Cr_eek DATE 8/15/88 1

COMPLETED BY Ku h n REPORT MONTH July, 1988 _

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

No.

DATE S SCHEDULED (HOURS)

(1)

POWER (2)

CONHENTS NONE 4

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SUMMARY

RE'UELING INFORMATION COMPLETED BY:

Chris Brennan DOCKET NO.: 50-354 UNIT NAME: Hope Creek Uni _t_1.,,

DATE: 8/15/88 TELEPHONE: 3193 EXTENSION: N/A Honth July 1988 1.

Refueling information has changed from la.st 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 l

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:

l Information not oresentiv available J

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7.

Number of Fuel Assemblies:

A) Incore 764 B) In Spent Fuel Storage 232 8.

Present licensed spent fuel storage capacity:

1108 i

Future spent fuel storage capacity:

4006 l

9.

Date of last refueling that can be discharged to spent fuel pool assuming l

the present licensed capacity:

11-07-89 i

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I HOPE CREEK GENERATING STATION l

HONTHLY OPERATING

SUMMARY

JULY 1988 Hope Creek entered the month of July operating at approximately 100% pcwor.

The unit operated throughout the month and did not experience.any shutdowns or reportable power reductions.

On July 31st, the plant completed it 86th day of continuous power i

operation.

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SUMMARY

OF CHANGES; TESTS, AND EXPERIMENTS.

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FOR THE HOPE CREEK GENERATING STATION JULY 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 e.nalysis 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 environmental impact.

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

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EqE Description of Desian Chance Packsoe 4EC-1002/01 This DCP provided for the structural and civil modifications that are needed to enlarge applicable areas to contain the Control Rod Drive Rebuild and Maintenance equipment.

This DCP also added add $tional access to the area.

It is part of the modifications to expand the Control Rod Drive Rebuild and Maintenance Facility to reduce radiation exposure and to increase maintenance efficiency.

4EC-1002/12 This DCP provided for the construction of a room to house the control consolo and the computer equipment that will be used for the Control Rod Drive Rebuild and Haintenance equipment.

It l

provided for the

civil, electrical,

heating, ventilation and air conditioning portions of the room construction.

It is part of the modifications to expand the Control Rod Drive Rebuild and Haintenance Facility to reduce radiation exposure and to increase maintenance efficiency.

4HH-0373 This DCP changed setpoints on flow meters to i

l obtain the correct flowrate over the Cooling Tower l

Blowdown Weir.

The new setpoints are based on vendor recommendtions and will provide a

more accurate head versus flow relationship.

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The following Temporary Hodification Requests (THRs) have been i

ovaluated to determine j

i 1) if the probability of occurrence or the consequences of an i

accident or malfunction of equipment important to

. safety previously evaluated in the safety analysis report may be

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2) if a possibility for an accident or malfunction of a different l

1 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 I

affect the safe shutdown of the reactor.

These THRs did not change the plant effluent releases and did not alter the existing l

4 cnvironmental impact.

The safety Evaluations determined that no unraviewed safety or environtaental questions are involved.

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Safety Evaluation Descrintion of Tennorary Modification Reauest (TMR) 88-0088 This THR lowered the setpoint of a pressure switch i

to allow the switch to reset.

The test solenoid was leaking

through, preventing the pressure l

switch from reseting.-

This caused the Turbine Gear Oil Pump to start automatically and to run continuously.

88-0091 This THR installed a

patch on a

line in the Service Water System.

This patch was welded onto i

the existing pipe to prevent leakage due to pipe wall thinning.

3 88-0094 This TMR added a

jumper across contacts on a

I temperature switch to operate the "A"

Turbine Building Chiller until a

defective temperature sensor can either be repaired or replaced.

.The defective sensor is used to shut down the chiller i

on high oil bearing temperature.

The. modified chiller will be used as a backup during the time period which the THR is installed.

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t 88-0097 This THR installed a blank in the exhaust port of an Alternate Rod Insertion Valve.

The valve

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internals were leaking through which could drain l

1 the Scram Air Header and scram the reactor.

The

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blank will make the valve inoperable, but based on 1

the redundant design, does not prevent the system l

from fulfilling its intended function.

i 88-0100 This TMR installed strip chart recorders to j

monitor the 24 volt DC input power, the 24 volt DC i

trip output and the analog signal on the e

J transmitters for the "H" and "P" Low-Low Set Main i

i Steam Safety / Relief Valves.

The recorders will j

not affect the operation of the relief valves.

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The following Deficiency Request (DR) has been evaluated to determine:

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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 i

j 2) if a possibility for un accident or malfunction of a different j

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.

The DR did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.

This DR 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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i Safety Evaluation Descriction of Deficiency Recort (DR) 88-0087 During welding on stainless steel piping in the Reactor Recirculation system, the weld pre-heat temperatures were not recorded.

These welds may be used as is because Section IX of the ASME Code allows a 100 degree F

change to the minimum temperature of 70 degrees F.

The room temperature in the Drywell did not approach the low end of the range; therefore, the piping in the Drywell could r

l not have reached the low end temperature.

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O PSEG Pu%c Service Electric and Gas Company P.O. Box 236 Hancocks Brwjge, New Jersey 08038 Hope Creek Operations August 15, 1983 U. S. Nuclear Regulatory Commission Document Control Desk washington, DC 20555

Dear Sir:

HONTHLY OFERATING 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 July are being forwarded to you.

In addition, the summary of

changes, tests, and experiments for July 1988 is included pursuant to the requirements of 10CFR50.59(b).

Sincerely yours, UU S. LaBruna General Manager -

Hope Creek Operations RARttib Attachment C Distribution i

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The Energy People

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i n im m, u m.

i INDEX NUNSER

SECTIQU, OF PAGES

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Average Daily Unit Power Leve1........................

1 Operating Data Report..................................

2 Refueling Information..................................

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i Monthly Operating Summary..............................

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

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