ML20247D162

Monthly Operating Rept for Apr 1989 for Hope Creek Generating Station Unit 1

ML20247D162
Person / Time
Site:	Hope Creek
Issue date:	04/30/1989
From:	Hagan J, Jensen H Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905250194
Download: ML20247D162 (12)

Text

i

+

V PSEG a

. Public Service Electric and Gas Company. P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station May 15, 1989 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 April are being forwarded to you with the' summary of changes, tests, and experiments for April 1989 pursuant to the requirements of 10CFR50.59(b).

Sincerely yours,

. j O Cfi^

~i; 3.!Hagan

~

General Manager -

Hope Creek Operations

.a gbA RAR:bjh:

Attachment C Distribution 8905250194 890430 PDR ADOCK 00000354 R

PDC g

The Energy People 96 2173 ($M) 12-88

INDEX NUMBER SE_CTION 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.............

5

1. s

.n' S

\\

l f

L_--___--__-___--

i' 4

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

_5.0-354 UNIT

.. Hope _Qneeg DATE

_5/1j5fg9 COMPLETED BY

.H.

Jensen TELEPHONE

_1609) 339-5261.

I MONTH _Apr,1,1_1989 j

1 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LE, VEL (MWe-Net)

(MWe-Net) 1 LQ_3 5 17 1M2 2

100a 1a 1030 1

3 1017 19 tR46 4

1016 20 1018 5

(0.09 21 1032 6

1p36 22 1015 7

1.0 3 5 23 1_ca.2 8

1Q30 24 1936 9

1052 25 1021 10 1044 26 969 11 1030 27 9.8 4 1

12 (Q_5_o 28 1054 13 1Q33 29 1Q28 14 1.0 1 6 30 1043 15 9 7 7 _._

31 1

16 1.0 0 5 1

1 1

O P E R A T.I.N G. D A T A_ R E P O R T P

DOCKET'NO.

,_50-3._54 UNIT

,, H.o p e_._C t :. t_.

DATE

_5L15Mc p

COMPLETED SY

__H.__ J ens e n,,,,,,,

f TELEPHONE

_16 Q_9,.1,._3 3 9 - 5 2_6.1 OPERATING STATUS 1.

REPORTING PERICO April..1989 ___,,, GROSS HOURS IN REPORTING PERIOD 219,_

2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3.2 13 MAX. DEFEND. CAPACITY (MWe-Net) 1.03.1 DESIGN ELECTRICAL RATING'(MWe-Net) _

1062 3.

POWER LEVEL TO WHICH RESTRICTED (i ANY) iMWe-Net)

None 4.

REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE l

5.

NO. OF HOURS REACTOR.WAS CRITICAL

,_/.1.9. _Q

_,,2 476.9 1 7_,,_4 2 4.5 2

3 6.

REACTOR RESERVE SHUTDOWN HOURS 0._O O.0 O.Q 7.

HOURS. GENERATOR ON LINE 71.L_O

.2 dZ.L A _. 12,103.7 8.

UNIT RESERVE SHUTDOWN HOUR 5' 0 O _,..,_

_ _O.0 00 2

2 9.

GROSS THERMAL ENERGY GENERATED (MWH)

_2,J.40,8_8?._,_

.,_L.Q 12d59_

__5 4.,.0;'t 1 Q.Z ?

10.

GROSS ELECTRICAL ENERGY GENERATED (MWH)

~/64.260_

_2 d44.,_Q89 17 3Z1;;17J.

2 11.

NET ELECTRICAL ENERGY GENERATED (MWH) 757,596 2.32bj43

_12,.07% Q43 12.

REACTOR SERVICE FACTOR 100.Q 86,_Q 24.1__

13.

REACTOR AVAILABILITY FACTOR 1.0 Q.. O.

8 6,_O.

3 4..J _,

14 UNIT SERVICE FACTOR 1.OOmp 8 5_, 8 5 2. y _,_

15.

UNIT AVAILABILITY FACTOR 100.0 85.8 3.0. 6. _

16.

UNIT CAPACITY FACTOR (Using MDC.)

99.S 8 5,. 2.,_

?O.Q.

l I

17.

UNIT CAPACITY FACTOR (Using Design MWel

_, ___,, % 1

_ _,., 8 2. 4 _

3,._

~ ' - '

13.

UNIT FORCED OUTAGE RATE O.0 0.2

c. 3 1

19.

SHUTDOWNS SCHEDULED OVER NEXT e MONTHS (TYPE, DATE, & D';R A T I ON )

Fefueling. C 15/S0 50 days 20.

IF SHUT DOWN AT END OF FEPORT PERIOD. ESTIMATED DATE OF STARTUF-l N/A l

, A.

.I' l_

e6^

, ' s.':

l s

!~

/1

' OPERATING DATA REPORT 7

.:ft t UNIT. SHUTDOWNS AND POWER-REDUCTIONS

. DOCKET NO.

_5_Q-3 5/.

B-UNIT

_H_,,op e' C r e e.k_ydi t l'

~DATE 5/134.8.9'

.4

-COMPLETED ~BY

_t!..__Jens.en e

~

REPORT MONTH A.pril 1989-TELEPHONE _(k_O9)-339-3261 METHOD OF-l SHUTTING DOWN THE

-TYPE.

REACTOR OR.

' F' FORCED DURATION' REASON

" REDUCING.

CORRECTIVE ACTION /.

NO.

DATE.

S' SCHEDULED (HOURS)

(1)

POWER (2)

COMMENT $'-

a NONE.

9 l

SUMMARY

_A

_m___2__,__:_ _ _ _

.-_m___

________=_-_____

'l 1

i n

VE REFUELING INFORMATION T

COMPLETED BY: : Chris Brennan

. DOCKET NO :

50-354-UNIT NAME :

Hope Creek Unit 1 DATE 05/10/89 TELEPHONE : -(609)339-3193

{' J

' Month: May 1989 1.

Refueling information has changed from last month:

YES X

NO L

2.

Scheduled date for next refueling:

09/15/89 3.

Scheduled date for restart following refueling:

11/05/89 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?

06/01/89 5.

Scheduled date(s) for submitting proposed licensing action: 05/03/89 6.

Important licensing considerations associated with refueling:

NRC Generic Letter 88-16,tvoe submittal has been made and will be used for Cycle ) operation.

Reactor Enoineerino will recuire an LCR for their control blade desion chance.

7.

Number of Fuel Assemblies:

A)

Incore 764 B)

In Spent Fuel Storage (prior to refueling) 232 C)

In Socnt Fuel Storage (after refueling) 496 8.

Presently licensed spent fuel storage capacity:

1108 Future spent fuel storage capacity:

4006

~9.

Date of last refueling that can be discharged to spent l

fuel pool assuming the present licensed capacity:

11/05/89 l

l l

n

4 HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

APRIL 1989 Hope Creek entered the month of Aoril at approximately 100% power and operated throughout the month uithout any shutdowns or reportable power reductions.

On April 30 the plant completed its 55th day of continuous power operation.

i g

s s

T

SUMMARY

OF-CHANGES, TESTS. AND EXPERIMENTS Li i FOR THE HOPE CREEK GENERATING' STATION APRIL 1989

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 ecuipment important to safety oreviously 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 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 cuestions are involved.

.__ ________________ a

QQf.

D,e s pr i g tlon,_ o f_Disign_ C h an g e_ P a ch as e 4EC-1024/09 This DCP installed platforms and ladders to provide access to Safety Auxiliaries Cooling System Supply Valves and Turbine Auxiliaries Cooling System Suppiy Valves.

The platforms and ladders will improve safety conditions and access to the valves.

4EC-1076/06 This DCP added the "All Rods In" input to a Safety Parameters Display System Cabinet.

This DCP is part of the project to upgrade the Safety Parameters Display System to meet the requirements of NUREG 0737.

4HM-0201 This DCP added an internal relief valve to the "A"

and "B"

Asphalt Recirculation Pumps.

The relief valves will protect the pumps and associated piping from overpressurization.

4HM-0414 This DCP revised the wiring and relay contact points for the Diesel Generator Room Recirculation Fan System to allow the " Auto Standby" fan to run if the Auto Lead Fan fails and to utilize.the existing 45 minute operating for the subject time span in all modes of operation.

4HM-0449 This DCP revised the Instrument Calibration Data Cards for 2 high pressure switches in the Solid Radwaste Boiler.

e

i 4

The followine Temporary Modification Recuests (TMR'S) have been evaluated to~ determine:

1) if the probability of occurrence or the consequences of an accident or malfunction of ecuipment 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 TMR'S did not change the plant effluent releases end.did not alter the existing environmental impact.

The Safety Evaluation determined that no unreviewed safety or environmental cuestions are involved.

,f l

l

4

• '~

.e,.,'_.

Salq_t y EvmLuat.f.Lon ~ Desqr ip_ tion _off_ Tempo _r_ary Mocji11_qa.t;.inf3eg.uest LT_MRl 89-0023 Thisx TMR installed. a jumper in' the Volume Reduction System

_ Panel-to defeat the Solid.

Radwaste Extruder "B"' Dome High Level Switches.

The switches-are not working as designed. and defeating then will allow waste to be processed.

89-0026 This TMR. installed a jumper in the.VRS Panel-to defeat the Solid.Radweste Extruder."B"' Dome High Level Switches' The switches are not working as designed ~and defeating then will allow waste to be.

processed.

89-0027 This TMR. installed a 3/8" three way balluvalve to the underside of the actuator oiston of the Startuo' -Feedwater Level Control Valve.

The oneumatic valve-oositioner failed-and cannot be reworkedLat this time.

The ball' valve will allow manual control of the air sucoly to prevent the valve from opening' when it is cesired for..it.' to remain closed.

_ _ _ - _ _ - _ _ _ _