ML20066E383

Monthly Operating Rept for Dec 1990 for Hope Creek Generating Station Unit 1

ML20066E383
Person / Time
Site:	Hope Creek
Issue date:	12/31/1990
From:	Hagan J, Hollingworth S, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9101180309
Download: ML20066E383 (14)

Text

. . . - - _ _ - - - - - _ . - - - - -

,\

D PSEG 3 Pubhc Service Electric and Gas Company P.O. Box 236 Hancocks Briope. New Jort.ey 08038 Hope Creek Generating Station January 14, 1991

,U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sirt MONTHLY OPERATING REPORT HOPE CREEK GENERATION STATION UNIT 1 DOCKET'No.--50-354

.In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics-forl December are being-forwarded to you with the summary of changes,Etests, and' experiments for December 1990 pursuant- to' the ' requirements of -10CFR00.59 (b) . ,

Sincer ly yours,

.J Ha an Gene al- nager -

Hope Dr -Operations

. gA h Rtld Attachments-C. Distribution-k -

9101180309 901231 PDR ADOCK 05000354 /

R PDR - I k L th. b trr y People ~ f \

q 95 Pl73($M) !? ........-...,_-,,..,..,,,,,..-...-,,,,,,,.-_.,_.__.#.,,,,,,._,_. .....rb.,....,m,, ,,.-.,,,,.......,7 ..J.4.-..---.,

l e e e ,

. ~

INDEX

(

NUMBER

-S.ECTION OF PAGES Average Daily Unit Power Level. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . . 2 Refueling Information . . . . . . . . . . . . . . . 1 lionthly operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments. . . . . 7 i

l 1

1 AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO. 50-354 )

UNIT Hope Creek DATE 1/14/91 COMPLETED BY V. Zabielski TELEPHONE (609) 339-3506 MONTH December 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 211 17. Eli

2. 1075 18. 1932

3. 1064 19. 1027 4 1048 20. 1110

3. 1064 21. 1071

6. 1083 22. 1044

7. 1035 23. 1018

-8. 1009 24. JA62

9. 1014 25. Als

10. AfD 26. 2

11. 1027 27. 2

12. 1030 28. 2

13. 1044 29. 2

14. 10jil 30, 2

15. 1015 31. 2

16. 1064 t

L . _ . - . .

OPERATING DATA REPORT DOCKET NO. Ap-LEA UNIT Hope Creek DATE 1/14/9,1 COMPLETED BY V. Zabielski TELEPHONE (609) 339-3506 OPERATING STATUS 10 Reporting Period December _122S Gross Hours in Report Period lid

2. Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWe-Net) 1067 30 Power Level to which restricted (if any) (MWe-Net) None

4. Reasons for restriction (if any)

This Yr To Ennth Date Cumulative 50 No. of hours reactor was critical 602.0 8020.0 29.781.5 60 Reactor reserve shutdown hours A20 222 220

7. Hours generator on line 601.0 7941.9 29.293.1 80 Unit reserve shutdown hours 222 229 922 4

9. Gross thermal energy generated 1.913.429 25.586.032 22 542.408 (MWH)

10. Gross electrical energy 649.080 8.465.410 30.621.673 generated (MWH)

11. Het electrical energy generated 619.598 8.100.135 29.256.684 (MWH)

12. Reactor service factor 80.9 91.6 84.2

13. Reactor availability factor 80.9 91.6 RA22

14. Unit service factor 80.8 90.7 1222

15. Unit availability factor 80.8 90.7 82.9

16. Unit capacity factor (using MDC) 80.8 A122 80.3

17. Unit capacity factor 78.0 86.7 2225 (Using Design MWe)

18. Unit forced' outage rate 222 122 521

19. Shutdowns scheduled over next 6 months (type, date, & duration):

None

20. If shutdown at end of report period, estimated date of start-up:

2/13/91

OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.10-354 UNIT Hope creek DATE 1/14/91 COMPLETED BY V. Zabielski TELEPHONE (609) 339-3506 MONTH December 1990 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS 13 12/26 S 143 C 1 Refuel Summary

n..---.. -- . - - _ ~ . - - . . _ - . - . - . - . . . . - - _ . -

4

' -+ ,

E. ,

14

' J i.

REFUELING INFORMATION 4

h DOCKET NO. 50-354 ,

UNIT. Hope Creek '

DATE 1/14/9:

COMPLETED BY S. Holl:.nasworth TELEPHONE (609) 339-1051 MONTH December 1990

1. Refueling information has changed from last month:

Yes No X 2e ' Scheduled date for next refueling: 12/26LEQ 3.- Scheduled date for restart following refueling: D2/13/91 <

40 A. Will Technical Specification changes or other license ,

amendments be required?

Yes No X B.- Has the reload fuel design been reviewed by the Station Operating. Review Committee?

L Yes. LNo X If no,1when is it scheduled? not currentiv scheduled

, Se Scheduled'date(s) for submitting proposed licensing action: HfA 3: 6. Important licensing considerations associated with refueling:

- Amendment 34 to the Hope Creek Tech Specs-allows the, cycle '

specific operating limits to be incorporated into the-CORE OPERATING LIMITS REPORT; a submittal is therefore not-required.

7o- Number of-Fuel Assemblies:

A. Incore -2fA B.. In Spent Fuel Storage (prior to= refueling) --AA1' C. In Spent Fuel Storage (after refueling) 212'

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

Future spont-fuel 1 storage capacity

. 4006

-90: Date of last-refueling that can-be discharged July 22, 2007 to spent. fuel pool assuming the present licensed-capacity -

l u

l o

,,, ,.e--_....- , , , _ . . . . ~ . . . . . . ..--,,_,,._,-.-m-_..-.-.,

HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

DECEMBER 1990 Hope Creek entered the month of December at approximately 100%

power. On December 26th, the unit was manually shutdown after completing 36 days of continuous power operation. The third refueling outage is currently underway with startup scheduled for February 13, 1991.

l.

i l

,. , m y .r,. .- ----- m-

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR TPE HOPE CREEK GENE 1ATING STATION DECEMBER 1990 l

l l

. . . ~ . _ . . _ _ _ _ . _ _ . _ . . . - . . _ _ . _ ..___ _ _.-._ ___. . . _ _ . . . _ _ . _ _ . _ . . . _ _

j 'l 4

The following Design Change Packages (DCP'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

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.

. The DCP's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.- The DCP's 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.

i f.

l 1

-t

, , , . ,r., -. ,m-.. . . . . , . -, ,._ m. . . . . . . . _ _ .. _-_w.--..-.~.-- -

.. - - . _ -- .-. . . _ ~ . _ - - - . - - - - . . - - . - - . . - . . - . . .

DCE Deccription of Desian Chance Packace 4EC-3149 This DCP added rigging attachment points to allow for easier removal and replacement of valves and actuators.. The valves and actuators addressed in this DCP are in the Puel Pool Cooling, Torus Water .

Cleanup, Safety Auxiliaries cooling, Instrument Gas, and Breathing Air Systems.

4EC-3187 This DCP added three pipe supports and modified two existing pipe supports on the outer radius instrumentation lines attached to the Reactor

-Recirculation System flow elbows. This DCP will improve the design by reducing the potential for fatigue induced failure due to vibration.

4HC-0212/01 This DCP upgraded the "A" Chilled Water Pump by replacing the motor and impeller. This upgrade will allow the Chilled Water System to operate with 2 pumps running and the other in standby.

4HC-0224 This DCP replaced-the early warning fire-detector in the Service Water Intake Structure with a condensation Nuclei Fire Detector. The original fire detection system was not able to withstand the harsh atmosphere of the Intake Structure. The new system is insensitive to dust, dirt, wind, vibration, humidity, temperature, and electronic noise.

4HC-0245/02 This DCP added new flow indicators and replaced

-existing pressure indicators in the "C" and "D"  ;~

Diesel Generator Fuel Oil Transfer Storage Tanks.

This will eliminate-the need to use portable Measurement and Test Equipment during the performance of the Diesel Fuel Oil Transfer Pump Surveillance Test.

4HC-0245/03 This DCP added new flow indicators.and replaced existing pressure indicators in the "E" and "F" Diesel Generator Fuel Oil-Transfer Storage Tanks.

This will eliminate the need to use portable Measurement and Test Equipment during the performance of the Diesel Fuel Oil Transfer Pump Surveillance Test.

4HC-0245/04 This DCP added new flow indicators and replaced existing pressure indicators in the "G" and "H" Diesel ~ Generator-Fuel Oil Transfer Storage Tanks.

This will eliminate the need to use portable Measurement-and Test Equipment during-the performance of the Diesel Fuel Oil Transfer Pump Surveillance Test.

~. - - . -. . . - _ . , . -. , . . _ . .

I 8- . .*

The following Temporary Modification Requests (TMR's) have been ,

evaluated to determines  ;

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.

The TMR's did not create a new safety hazard to the plant nor did they affect the safe. shutdown of the reactor. The THR's 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.

h I. t l

l l

l

- . - l IMB Descriotion of Tenocrary Modification Rqqugat 90-074 This TMR installed a jumper to disable an input to an overhead annunciator. This was a nuisance alarm due to a failed Trip Coil Continuity Alarm Card.

The TMR will be removed when a new card is available for installation.90-075 This TMR removed the Reactor Vessel Water Level Transmitter and installed a pressure transmitter in its place. It also rescaled the Reactor Level Shutdown Range Indicator. These modifications will provide the Control Room with reactor level indication during floodup.90-076 This THR installed an air compressor connection in the discharge line of a Service Air Compressor Aftercooler. This connection will provide an air supply for the Service Air System while the normal air compressors are out of service for system outages.

1 P

l l

l l

, . , . , . . , . . n - . - - - - -

. _. _ _ _ . _ . _ . . . ~_. _ . . .. - _ _ - _. _ _ _ . _ . - .._. _ _.._._ _ _ _ __._. _ _ _ _ _

The following Deficiency Report (DR) has been evaluated to determines <

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.

The'DR did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The DR did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluation determinod that no unreviewed safety or environmental questions are involved.

i

_ .u- _- - . _ _ _ _ . .._ _ ,- _ _ _ _ _ .- _ _ . . _ _ . _ _ . ,-

. .r DE DRacriotion of Deficiency ReDort HTE-90-0111 This DR addresses a pinhole leak in the Station i Service Water System. The leak is in the "A"  ;

Safety Auxiliaries cooling System Heat Exchanger Room, on the "A" Service-Water Supply Line to the "A" Safety Auxiliaries cooling System Heat l Exchangers. The DR authorizes the pipe to be "used-as-is" until the completion of the "B" Loop Service Water piping replacement work that is being conducted during the third refueling outage.

i 4

I:

l' n

i-L- - , - , . - - , - _ _ _ - _ ,