ML20058P410

Monthly Operating Rept for Jul 1990 for Hope Creek Generating Station,Unit 1

ML20058P410
Person / Time
Site:	Hope Creek
Issue date:	07/31/1990
From:	Hagan J, Zapolski M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HSE-90-279, NUDOCS 9008170024
Download: ML20058P410 (14)

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Public Service Electric and Gas Cornpany P.O. Box 236 Hancocks Breige, New Josey 08038 r Hope Creek Generating Station August 10, 1990 HSE-90-279 i U. S. Nuclear Regulatory Commission i Document Control Desk l Washington, DC 20555 l

Dear Sir:

MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT l' .

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 viUn .the I

summary of changes, tests, and experiments for July 1990 e pursuant to the requirements of 10CFR50.59(b).

i sincerely yours,  !

1:

. J. agan '

General Manager.-

Hope Creek Operations RAR:ld '

Attachment 1 C Distribution , .

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DATE,' 8/10/90 J COMPLETED BY ,H Zapols)Li  ;

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=' OPERATING DATA REPORT:

DOCKET NO. 354 UNIT _ Hope Creek DATE _8/10/90 COMPLETED BY M2_Zapolski

- TELEPHONE _(199) 319-3738 OPERATING STATUS

,1( REPORTING PERIOD <[ull j,'J_Q_, GROSS; HOURS IN REPORTING PERIOD 7441

2. CURRENTLYaAUTHORIZED POWER. LEVEL'(MWt)' 3293 HAX. DEPEND. CAPACITY (MWe-Net) 1011 DESIGN ELECTRICAL RATINOf(MWe-Net) 1067__

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3. - POWER LEVEL 1TO WHICH RESTRICTED - IIF A!TY)~ -(MWe-Net)'

4.. REASONSiFOR' RESTRICTION?(IF ANY) THISJ --YR- TO

. MONTH" DATE- CUMULATIVE.

No. OF HOURS-REACTOR,WAS. CRITICAL- '744.0 4771.8 _26;533.3~

5.

0.0 O.0 0. 0;

6. REACTOR RESERVE. SHUTDOWN HOURS r b 744.0 4735.3 ._@6,086 4 1._

7. HOURS GENERATOR ON LINE

0. 0' O.0- 'O.0-

8. UNIT RESERVE SHUTDOWN HOURS

9. GROSS THERMAL ENERGY GENERATEb

_15,232a545 -82,188,921 (HWH) _2,415 t190 10.- GROSS 1 ELECTRICAL ENERGY 792,010 5;028i820. _2701855083_;

GENERATED (HWH)

NET ELECTRICAL-ENERGY GENERATED l 11.

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. 757,962 4,817',580 225,974,129.

(MWH) 100~.0 93.8 83.8

12. . REACTOR SERVICE FACTOR 100'.0 93.8' 83'8 .

13. REACTOR AVAILABILITY' FACTOR' 100.0 93.1' 82.3

14. . UNIT SERVICE FACTOR' UNIT AVAILABILITY FACTOR 100.0 9 3 1 ' 82 t.3

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16. UNIT CAPACITY FACTOR 98.8 91.9 ' 7 9 . 51__,

(Using MDC)

17. UNIT CAPACITY FACTOR 76'.S (Using Design;MWe)L

'I 95.5 88.8 R18 . ' UNIT: FORCED OUTAGE: RATE 0.0 4.2 -5i3 19 ; z . SHUTDOWNS SCHEDULED OVER NEXT'6 MONTHS-(TYPE, DATE, &JDURATION)':

Refueling, 1/19/91, 45 days 20 IF. SHUT DOWN AT END.0F REPORT; PERIOD, ESTIMATED DATE 0F-START-UP:

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[: W' l UNIT SHUTDOWNSiAND POWER REDUCTIOllS, 4

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DOCKET NO.'J50'-354 UllIT , lHape'_. Cre ek DATE"l8/10/93

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~ REPORT MONTHfJuly;1990': TELEPHONE (609)D339-3738 y

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11 0 . DATE S SCHADULED (HOURS)" (1)! POWER (2)  : COMMENTS ,

s 7/6- F.i 0 .- ;B: . .

.5 Power. reduced'to! . is ,

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in" block? tiermination . t eliminating. erratic r TCV operation.;,;,'

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REFUELING INFORMATION I

COMPLETED BY: Chris Brennan DOCKET NO: $_0-154 UNIT NAME: [ Lop 1 Creek Unit 1 DATE: _8L10_L90 TELEPHONE: .1609) 33_95232_

EXTENSION: IJLA Month Lu.Ly_19.9 0

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: _ ._01]_1_9]_9_1

3. Scheduled date for restart following refueling ,,_03L05191_

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

YES NO X B) Has the reload fuel des 1;n been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? not_ currently _s_cheduled l

5. Scheduled date(s) for submitting proposed licensing action: IMA

6. Important licensing considerations associated with refueling:

_Ameadnent J 34 to the_ Hope Creek Te_ch_S_pecs a QQws the_cy.cle f 1speci[ic operating limits to be incorppIaled_i.n.to the CORE

QfERATI.NG LIMITS _R.EPORT1 a submittal is therefore_not r_equir.ed.

7. Number of Fuel Assemblies:

A) Incore 764_

B) In Spent Fuel Storage (prior to refueling) ,,_41$

C) In Spent Fuel Storage (after refueling) _7 69___

B. Present licensed spent fuel storage I capacity: 4006_

Future spent fuel storage capacity: 4006__ _

9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: Luly 22, 2007 1

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' HOPE CREEK. GENERATING: STATION MONTHLY OPERATING

SUMMARY

JULY 1990~-

Hope Creek entered the month of July _ at approximately 100% powen

-i On July.6th:. power was' reduced to: correct Turbine Control Valve wiring block termination eliminating, erratic, Turbine Control Valve operation. Power was returned-to approximately11004. The. unit-operated throughout the remainder ofsthe month,without experiencing

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any shutdownsior other reportable power reductions. on July 30,.

the plant-completed it's'126th-day of continuous power,' operation.

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.0F CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION-JULY 1990 b

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Tho following D cign ChCngo Package (DCPs) have boon evolucted to dothrmino:

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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

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 specific 4 tion is reduced.

The DCPs did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The DCPs 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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DCP D e s c r i.p t i o n io fle s.ig n_Q'.laag_e _P a c k a g e 4HC-0128/03 This DCP rerouted drain lines from Heating, Ventilation and Air Conditioning air supply units. The lines originally drained to the dirty radwaste system. Some air supply units will now drain to a circulating water sump and some will drain to the Low Volume Oily Waste System. This DCP will reduce the volume of water which is treated by the Radwaste System, 4HC-0299/03 This DCP installed a reinforced concrete access  !

pit to provide access to manually operated valves in the Service Water Yard Return Lines.

SSC-2097 This DCP upgraded Hope Creek's Meteorological 1 Information and Dose Assessment System and Hope Creek's Engineering Data Base System. These upgrades will increase the systems' accuracy, efficiency, and effectiveness.

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M4 The0followingiTemporary HodificationvRequestsL(THRs)fhave-been;q ' 4- E

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Jaccident or malfunctionloffequipment?importanttto safety? .

R previously:' evaluated in thevsatety_ analysis) report may be_ . ~

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2) lifi.a.p6ssibility;for ancaccident-or; malfunction,o'fxa:differenti

,> typeithan;anyEevaluated'previously:in:the-safety analysisF report may/be created;?or; m' ._ ' "

'3) .ifrthe margin (of, safety:assdetineddin tNe bssisifor any? ,

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- The THRs did noticreate tai newysafetyl; hazard t.o1 the' plantjiiorldidk

..they' affect thetsafeyshutdownlof theEreactora The]THRsSdidi. noti-ichange thefplant: etfluentf releases 'and did' not alter' thelexisting K '

m environmental. impact.1:The: Safety Evaluations;determinedEthatEno unreviewed safety orienvironmental(questions;are: involved.,'

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ThislTHR installed'airubberlpatch and'a Belzona '

> coating. covered.by aJcarbon steel 1 plate _. . . .

secured'.byibrace, over a leakiinLService: Water!

7' , 1  : pip ~ing. : - Tha .THRuwill'remainfin; place untilJthef 3rd Refueling; Outage,iwhenithespipingi.will2 be ,

,, restored tojthe origina1L'ASME requirements.. <

-l 90-045i This THR: replaced?a: gasket;iniservice. Waters,s The ?

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piping.withJajgasket.of afdifferentttype.e W -gasketiwill be returned'to itsloriginal?. 7

configuration duringfthe'3rd Refueling: Outage..

_. ..90-047c ThislTMR t removed thefinputisignalsEfromi _ .

H defactive reedIswitches for1 Control'!RodL34-27. '

The l. input " signallwasi removed i byJ modif ying.M thej Rod Position: infornation; System l Prob'e ~

Multiplexor-Carditoielectronically!disconEect

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' th? fillcwing D ficicncy R port (DR) h2s b2 n Ovalu3tCd to

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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

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 they 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 determined that no unreviewed safety or environmental questions are involved.

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,.g -l * '. 6, -iG y l pb 1 ' DESCRIPTION'0F; DEFICIENCY REPORT' <

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' .This - D'eficiency Rep' ort ,was.' wrf tten 1 to ' docunente

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the: discovery.of paint.on'.theninside:of the: '

upper?bearingireservoirLon the "C"' Residual: - ,

Heat Removal' Pump' Motor- and the' misalignment. r 0 .l

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,the' lower connection lofJthe-uppers. oil bearing

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-cooler. TheLSafety Evaluationc associated with '

]j this:Deticiency ReportJdispositioned~the "C"

,Residualc Heat Removal Pump,,"UseLAs-Is" ; until"' -;

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'the'3rd Refueling Outage,;.when the-paint'can;be

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- repaired land the oil bearing; cooler'can--be a replaced.) e ,.

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