ML20246B735

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

ML20246B735
Person / Time
Site:	Hope Creek
Issue date:	07/31/1989
From:	Brennan C, Hagan J, Jensen H Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8908230449
Download: ML20246B735 (14)

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, Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 y

Hope Creek Generating Station August 15, 1989 4

=Ub.S.

f Nuclear Regulatory Commission-Document. Control-Desk

. Washington, DCl 20555

Dear' Sir:

1 MONTHLY OPERATING, REPORT

%--- . HOPE CREEK GENERATING STATION' UNIT 1 4 DOCKET.NO. 50-354 In compliance.with Section 6.9, Reporting Requirements for the

' Hope Creek Technical Specifications, the operating statistics for

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' July.'are being forwarded'to you with-the summary-of changes, s . tests,>and experiments for July 1989 pursuant _to,the requirements of 10CFR50.59(b).

S'ncerely yours, NV w ,

.)fsg* y J agan G neral Manager -

Hope Creek Operations

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' Attachment C Distribution 8908230449 890731 PDR p

ADOCK 05000354 PDC %2f j

' t i The Energy People - h 95 2173 (SM) 12 88

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INDEX.

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, NUMBER fg_CTIOff ,

OE.PAGXS

.y;

. Average' Daily-Unit Power Level........................... 1-Operating'D'te a Report..........'..'..................... 2-Refueling:Information......................~............ '1 1 Monthly Operating Summery.............................. :1 Summary- of Changes, .' Test s,1 and Experiments............. 7 e

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~ AVERAGE DAILY UNIT POWER LEVEL-

-DOCKET NO. _5R 13jlf _

UNIT _dqoe_ Creek L!b DATE _S/1Q/89~

OOMPLETED.BY _li,_.Jg_q s e n TELEPHONE _1609) 439-5,2kJ MONT.H Jy.l_r._1989

^ DAY. AVERAGE DAILY POWER LEVEL- DAY AVERAGE DAILY-POWER LEVEL

_ ( MWe-Ne't ) - (MWe-Net)'

1 842 17 968

. 2l 1AQ2 18 964 13 LQ28 - 19' 946 4 870 20 971

$ 1018 21 943 b

p 6 999 22 937 7 1_Q.05 23 962 1

L 8 $93 24 946 L

L 9 1015 25 945 10 988 26 436 Li 11: 9 47 27 931 11 2 -975 28 943 13 979 29 936 o

14 9$4 30 939 o -l s

~15 974 31 913

.16 969 I

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OPERATI1JQ_.QeTA- REPORT

'- DOCKET ' NO., _50-314 L

UNIT. _H_ppe Creek F ' '

DATE u8111/89 COMPLETED BY. -H. Jensen-TELEPHONE' & Q9) 339-5261-

' OPER4 TING STATUS.

1;- REPORTING' PERIOD July _1989 _ GROSS HOURS IN REPORTING. PERIOD '744_.

2. JCURRENTLY-AUTHORIZED POWER LEVEL (MWt). 3293

. MAX. DEPEND.- CAPACITY ~(MWe-Net) 1QJ1 og '

DESIGN ELECTRICAL' RATING-(MWe-Net)' 1067'

- 3. POWER. LEVEL.TO WHICH RESTRICTED (IF ANY.) (MWe-Net)' None 1

4. ' REASONS'FOR RESTRICTION (IF ANY)

,. THIS YR TO MONTH- 'DATE- CUMULATIVE

5. NO..OF-HOURS REACTOR WAS CRITICAL .744.O 4,_6469 19,632,.3

6.  : REACT'ORL RESERVE' SHUTDOWN HOURS ~O iO 'O.O O ,_O

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7. HOURS. GENERATOR ON1LINE. 744.O _b 679.6 19,311.7

[n  ; 8. UNIT. RESERVE' SHUTDOWN HOURS O ,_O Op m LQ, O l' .

f. 9 .' GROSS-THERMAL-. ENERGY GENERATED (MWH)' ._2 2.6 4_x798 , 2,.L 991.41% __60.995d29 I# L10. GROSS ELECTRICAL' ENERGY-

1. '

GENERATED (MWH)- 747t 700_ .4i4}Jx2h9 _RO.159.713

. < I 1I . NET ELECTRICAL ENERGY GENERATED-

) '(MWH) 714,494 - -- 4 t212QhQ7 19.R7_12JiQ

. I2.  ! REACTOR SEm/ ICE FACTOR 1 QQ_,. O 9Eul 8]A .

1 12 ,1L REACTOR AVAILABILITY FACTOR- IQO.O 92.1 S_q, 7 I

. 14. UNIF SERVICE FACTOR 10_Q, Q 92.O 4.b]

15. UNIT' AVAILABILITY FACTOR 100uQ 92.2 O S4,3

16. UNIT: CAPACITY FACTOR L (Using MDC) 93.1 90,_O _ ._JJ_,_6 .

/ ,

[j l17. UNIT. CAPACITY FACTOR

'(Using Design MWe) 90_xp 8 7 . O __ ,,_ 7 8.,.J.___

' 18. - UNIT: FORCED OUTAGE RATE O. O_ _ . _ _ , , 0.1 1, 7

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

Refueling, 9/15/89, 50 days e 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

N/A a

na____._._______ __-_ - _ _ _ . . - . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . . _ - _ _ _ ._ _ _ . _ . - _

y ;- _

V.:

,s OPERATING' DATA REPORT

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. UNIT ' SHUTDOWNS AND POWER REDUCTIONS!

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< DOCKET NO. 5_O-J 54 1

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l- UNIT _lippe Creek Unit 1 __

DATE: 8/15_/_,$ 9

1. .

4' COMPLETED'BY- .__H . Jensen p

! REPORT' MONTH J_uJ r ,_1 9 8 9 TELEPHONE-__1609)~339-5261 i

METHOD OF SHUTTING DOWN THE TYPE. REACTOR OR F~ FORCED DURATION REASON REDUCING CORRECTIVE' ACTION / ),

NO, ' DATE' S SCHEDULED (HOURS) (1)- POWER (2) COMMENTS None l

)

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3

$ j' I

. .S U M M A R Y -

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Y REFUELING'INFORMATION j

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COMPLETED BY:Chris Brennan' DOCKET NO: 50-354

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UNIT NAME: Hooe Creek Unit 1 DATE: 8/15/89 .;

1 TELEPHONE: 3193 1

'JW EXTENSION: N/A  ;

m

g Month. Auaust 1989  ;

i 1,r ; Refueling information has changed from last' month: ) '

YES~ X NO

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2. Scheduled date for next. refueling: -

09-15-89' 3 '. - ' Scheduled date.for restart following refueling:. 11-05-89

'4 . - A): LWill 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?

YES > NO X' LIf no, when is it' scheduled? 9-01 1 5 '. . Scheduled.date(s) for submitting proposed licensing action: .:

5-03-89 .)

c 6. , Important licensing considerations associated with~ refueling: l NRC Generic Letter 88-16 type submittal _has been made sni j

._idlJ be used for Cvele 3 operation. Re. actor _Encineerina j

.311,1 recuire an LCR foI_1 heir control blade desion chance. 'I l

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7. Number of Fuel Assemblies: '

A) Incore 764 ,

232

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'B)~In-Spent Fuel Storage (prior to refueling) __ ,

C)"In Spent Fuel Storage (after refueling) 496 l

8. Present-licensed spent fuel storage  !

capacity: 1290 _

Future spent' fuel storage capacity: 4006  !

i L 3 9L .Date of last refueling that can be l

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discharged to spent fuel pool assuming j f

the present licensed capacity: ' 3-13-91  !

=_= _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

s July'1989-1 0 '(l Hope' Creek' entered the. month of July operating at 100% power. On

' July 5,-coastdown began et.a rate of.' approximately .'34% per day.

- On . July;.- 31, the plent7 completed its 147th. day of continuous power

., operation,. operating at approximately 90%.

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SUMMARY

fOFL. CHANGES, TESTS,'AND EXPERIMENTS e FOR.THE HOPE' CREEK GENERATING STATION July 1989 t

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.The folloui'ng , Design ' Change Package (DCP) has been ' evaluated to jl determine.:

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1) 'if'the probability of occurrence or -the consequences of' en accident or malfunction of equipment important to safety 1previously ' evaluated in thel safety analysis 1 report may be-

increased; or i..

2) 'if a' possibility'for an accident or- malfunction of a different' typesthan any. evaluated'previously in the safety analysis reportL

'.c , Emmy be created; or-3 ') - if the margin ofusafetymas defined in the basis for any technical.

specification is reduced.

LThe'DCP did not' credte a'neu safety hazard to the plant nor did it affect the safe shutdoun of the' reactor. This DCP.did not change the plant" effluent releases and did not' alter the existing environmental.

impact. The Safety' Evaluations. -determined that no unrevieued- safetr or environmental questions are involved.

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D.CP Qescrip_tjon ?1_[gsign_Chaope Packepe 4HM-0301 This DCP installed a lower pressure reaulating valve coming off the span gas bottles for the Of f-Gas Hydrogen Aney1::ers. The addition of the regulating valves will allow the pressure to be maintained more accurately.

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i T.h'e-following. Temporary. Modification Request' (TMR) has been evaluated.-to. determine. 3

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' " , - 1) - if the' probability'of.' occurrence or the. consequences of an acpident'or malfunction of eouipment'important to safety l.'

previously evaluated in the safety analysis report may be increased;.or

2) if a possibi'lity for an accident or malfunction of a

(' dif f erent - t ype: than any evaluated previously in the safety analysis-report may be created; or

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

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

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(( .' es9-DO53' . This'TMR. installed straight stream nozzles in

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' the-piece ofLfog nozzles.for.3Lhose. stations in'the Reactor-Building. The straight stream

, ' nozzles-will' reduce. .the possibility.' of en

' inadvertent' reactivity -.' ec c i dent during fuel.

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1 Reques'ts h The-following Deficiency. (DR's) have been evaluated to

' determine:-

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1) - if the probability of occurrence or 'the consequences of an-E accident 'or malfunction of equipment. important to safety previously evaluated in. the safety analysis report may be.

i- increased;-or 1

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

- type than any evaluated previously in the. safety analysis report-

[ mey be created; or

3) if'the margin of safetyJes' defined in the basis for any technical specif.ication is reduced.

The DR'S did not create a new safety hazard to the plant nor did they affect the' safe shutdown of the-reactor. The DR'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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89-0058 The Liouid Redweste Radiation Monitor provides status and readings to the Radiation. Monitoring )

' System Computer; however, the Liould Radweste  ;

Discharge.High Flow condition is not alarmed on )

the console. The Liouid Radweste Discharge Line is isolated from the Liouid- Radweste 'Rediation l Monitor. The Radiation Monitoring System Computer is utilized for display only and may therefore be used "as is".

1 89-0059' The Main Steam Line Radiation Monitors provide an isolated analog output to a processor to ' drive  :

strip chart ' recorders. This DR identified a.

situation where a processor failure is not alarmed on the console or on the Radiation Monitoring ,

System. Common Annunciator,- indication freezes on e processor voscele failure, and indication drops.to 000 on a downscale failure. The processor.is used for indication. only and may be used "as is" j because isolation functions are provided by the l Main Steam Line Radiation Monitors.  !

89-0061 A Main Steam Line Drain Header Valve fails in the l closed position. ine valve is designed to fall in ,

I the open position. However, the valve performs its intended' function and may be used "as is".  ;

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.E9-0063 The Alert Alarm for the Main Control Room Area Radiation Monitor was found to be out of tolerence. The alarin ectuates at . J .72 Hx instead  ;

of 2.50 + .05Hz. This discrepancy affects the j High Alert Alarm only and may .be used "as is" I because the error is in a conse vat ive ciirec tion. 'l 89-006S A smal) leek was susp<ct3d in the 'B" Sterdoy Diesel G rne<'ator< Combustion Air Intercooler. The j leak has en insi gni f ic ant effect on the Scandby j Die sel . Generator s ability to perform its intended ]

function and mey therefore, be Jaed "ae is".

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