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

. Hope Creek Generating Station L*

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December 15, 1989-'

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'U./-S.: Nuclear Regulatory. Commission *,

Document Control Desk10 , ' Washington, DC 20555-

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Dear Sir:'

MONTHLY. OPERATING REPORT-HOPE CREEK GENERATING STATION UNIT 1DOCKET NO.?50-354-

In. compliance with Section'6.9, Reporting-Requirements for the

' Hope Creek Technical Specifications, the operating statistics for

'

November'are being. forwarded to you'with the summary of changes, ;t

; tests, and experiments for November-1989 pursuant to the

requirement's-_of 10CFR50,59(b). '_

.

Sincer ly.yours,'4

J H gan.

Gener Manager ->

. Hope Creek Operations,

M RAR:scAttachment

C: Distribution'

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p. 12f.; JCURRENTLY. AUTHORIZED'POWERiLEVEL-(MWt) 3293- m.

i A ' MAX.. DEPEND.--CAPACITY 1(MWe-Net)' 1031DESIGN; ELECTRICAL' RATING;(MWe-Net) 1067-''

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UNIT SHUTDOWNS AND POWER REDUCTIONS

DOCKET NO. 50-354

UNIT _ Hope Creek' Unit 1_

DATE 12/15/89 |

COMPLETED BY _S.Loeper

REPORT MONTH November 1989 TELEPHONE _(609) 339-5257'

METHOD OF' SHUTTING

DOWN THETYPE REACTOR OR-

' F FORCED : DURATION REASON REDUCING CORRECTIVE ACTION /NO. DATE S SCHEDULED (HOURS) (1) POWER (2)~ COMMENTS

|11 11/1 S 429.7 C 4 CONTINUATION OF j

REFUELING OUTAGE

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1COMPLETEDlBY:-|Chris_Brennan.

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UNIT NAME: Hope Creek: Unit 1" 4* - DATE::12/15/89- !'

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TELEPHONE: 43193MAY - ' , &-EXTENSION:'N1A d

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1 [ Month' December'1989-[!a' f .

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N ' 1+1*.i[Ref'uelingLinformation has=-chang'ed fromilast-month:< ''

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'YES .NO X J[g ;g , .

N'' dh1Sdheduled/:dateforinextrefueling: 01/19'/91.

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(M; [ ~3. ESbheduleddate fortrestart following refueli.ng _0_3105/ Jill...

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5WilliTechnica1. Specification changes or'other' license;* ~T f 4 '. - - A ) - ,

i' t' L : amendments,be-required?-c

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,'4 15? /ScheduledL date(s)-[for1 submitting proposed licensing action:: N/A- j''

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omc ::Iinportant Llicensingt considerations ; associ~ated L with Lref ueling :/ i- ..

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?-Aniendment' 34E to' the Hope Creek Tech Specs : allows tho' cycle q

0-specific op,erating-limits to be incorporated 11ntorthe CORE.-(<s

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--OPERATING LIJMITS' REPORT 1 a submittal isith_e nfore notq; .. required.>

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.(Number of FuelLAssemblies:e7.. :_

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764- dJA)sIncore-'

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'LB)"In' Spent [ Fuel ~ Storage-(prior to refueling). 496 4'

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*%' C)LIn Spent: Fuel' Storage.(after refueling)' 744 1

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6- 19..N Datelof;1ast refueling that can be- j

A ~ '' discharged to! spent fuel pool. assuming .jthe?present licensed capacity: 03-05-91

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4m- ;'I 'achievedicriticality.1;On November"19, the;generatorswas online. |1

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'

g Outage. The outage duration wasJ64.4'.

-days;':On November 121',Jthe; plant. reached 100% power. 'On1Novemberr - s<

_ ,je , 26, < po'wer.. was' reduced to; perform : Single Recirculation? Loo'p data - y6 - icollection...- Power -was freturne'd to rated : the. saine -day. - on tiM (November 30',7the:plantiLeompleted:-its 12th-day of-continuousi J;1

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. SUMMARY.0F CHANGES, TESTS, AND EXPERIMENTS

FOR THE HOPE CREEK GENERATING STATION-

' NOVEMBER-1989

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t$;r, -accidentLorcmalfunction.ofu quipment"important'to safety:- ei (previously!ovaluated|inithelsafety. analysis report'mayibe:

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' q w :_ _ , ..x- The?DCP's (didLnotj create y a new: saf ety ''hazardi to ' the plant 'nor- did i e

$yL' itheylaffect';theLsafeish'utdown of(the< reactor. The'.DCP'ssdid:not:M

N W ehange?thenplantieffluentireleases=and'did not alter the-existing. r

VW?o fenvironmental impacti .The1 Safety Evaluationstdetermined|thatino: 'te , Ounreviewed; safety:ior environmental 1 questions are' involved ',

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hp; gyp jl[DCP. Description ofLDesi.an Chang L ackace'-- ,PL3-; ;

4HCp0127/0i .This DCP re-routed-drain lines:'so:the-drainage- |k. i

M %_ a(' effluentssfrom various' Reactor: Building SampleL :t?^\ StationfSample Points wouldidrain'to:eitherqthe '[

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Condenser or..the Clean.Radwaste-Systemi- 'Re -* *s

routing the drain 111nes will reducelthe-. volume J*'

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Si in f' 'being: processed through theLDirty.Radwaste .

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This-DCP installed a steel' platform,-: gravity.14HC-0298r >

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$f <' - - Egates,' and:handreils inside the Drywell. 'It. M

.also modified:an existing ladder. The: addition! |'"

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of.thisLequipment will establish, safer workingD :sip,p?~

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4HC 0333/O'2 This DCP rewired a multiplexer to return it'to-fWits ori~ginel. configuration.- A pr'eviousy| , s

M? a' 'modificationLprovided this multiplexer with ant '

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01 ; uninterruptable power supply.. That'

MD :modifi' cation was requirediduring:the Loss of,

Loffsite Power Test to record: Reactor Protection~

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sf^ . System 1GETARS points'. This DCP disconnected- 1,

.the :uninterruptable power supply and ..

Ii"gF qb ' reconnected the multiplexer to its1 original ,

< .y--: Reactor Protection System' power supply,

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i4HM-0144, , Thia.DCP re-scaled two instruments that moniter. 1i -

The new' range?is 00F'to 1200F,.the1 previous- 4

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the! temperature;of the Cooling Tower Blowdown.-'

-range.was 0*F'to?100*F which causedLa failure-''

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| indication"at 98'F.a, -

m;n? 0 4HH-O'318_'

'near the Main Turbine: Control Valves.on anL.ThisEDCP installed temporary instrumentation

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. actuator and'the Electr6-Hydraulic Control *

System Tubing. .The~ instrumentation willibe :q- y.used'to'obtain' data-onEthe tubing support .

m 3g system'for analysis to determine the-optimum.*,

|j 1, . gy q:- ;. support configuration.

n-i4HM-0383' This DCP recalibrated the transmitter supplying-

|@ ' flow rate data from-the Cooling' Tower Blowdown [~ Weir' Gate to the Cooling Tower-Blowdown

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. Dechlorination System Flow Recorder. The flowyr meter was detecting a greater than actual flow

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This'DCP replaced the set screws on theL4HM-0391' sg;f ;p Refueling Bridge Wheel Shafts with set screws

with a dog point fitting into the recessed*

holes in the wheel shaft to prevent the wheelshaft from moving relative to its bearing.e

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Descr_iption__of Design Changg_ Package _.DCP e

CHM-04911 This DCP re-routed tubing from the "C"Condenser to a pressure transmitter. Thetubing was run near a Heating, Ventilation andAir Conditioning resistor which cooled down theline, allowing condensation to form. The >

condensation' caused erroneous high pressurereadings.

4HM-0548 This DCP added an Emergency Diesel GeneratorAnnunciator for "Barring. Device Engaged" to theRemote Engine Panel. This annunciator also-will go to the control Room Common Emergency jDiesel Generator Annunciator and the Control ,

Room Integrated Display System, providingadditional information to Control Roompersonnel.

~4HM-0607/03 This DCP eliminated air entrainment of the oilfrom the "C" Secondary condensate Pump Motor.Bearing Housings. The air entrainment causedthe oil to be forced into the= motor housing and

[ windings, and also was forced out of theexhaust hood onto the floor,

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l' 4HM-0643 This DCP changed the setpoints for the MainHoist Fuel Loaded Interlock and the Monorail

fL and Frame Auxiliary Hoist Uptravel Stop. Italso eliminated the Monorail and Frame J

fAuxiliary Hoist Fuel Loaded Interlock. These!modifications make the Refuel Bridge conform to

p: the operability requirements of the Technical j. /"Specifications. ]

kL o 4HM-0653 This DCP. rewired control panels to correct 3

discrepancies. The Radiation Monitoring System 1

Trouble Alarm was falsely indicating an alarmcondition, j

k4HM-0660 This DCP provided a visual /atdible annunciator a

alarm for Fuel Pool Low Level and Reactor fCavity Low Level and analog indication of

I|Reactor Cavity Level. The alarms andindicators are local indicators on the Refuel lFloor and were installed to comply with INPO j

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SOER 82-10 and 85-01.

4HM-0673 This DCP relocated the flow elements for the l'

Slurry Metering Pumps from the suction side of j

the pumps to the discharge side. Thismodification will enhance the operability andreliability of the system.

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g V; ;14,HM-b7081 . ThisiDCP;addedraRiock nut to'each of'.the valve' ;j

stems'ofxtwo Residual HeatiLRemoval Bypass. '!,

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;(AHM 0721/02 1This'DCP--added a lockinut tota Residual; Hear1,,

' Removal Bypass Valve. . The~1ock nut:will '!h *;~

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u#) previous.lyievaluat'edfin thersafety' analysis report <may be~

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jb 'analysisT; report:may befereated; tor:&

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The .THR'! sfdid"noticreate ; af riewisaf ety hazard to the plant nor did .-

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1: they|| affect 6thefsafe shutdown'of the' reactor. :The-THR's.didenot-changeithe' plant effluent releasesiand di_d notoal-ter the existing4-.' c

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% environmentalLimpact. The.SafetyLEvaluations determined thatino.@' 'unreviewed:safetySor environmental. questions are involved.

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(s:.% ' Safetr Evaluation Descriplipon of Tempora _ry Modification P questn r g>

f i,U[h.ss' -h *, , 89-147 This TMR removed the overload heaters from af bretker for the Residual Heat Removal Outboard[ Shutdown Cooling Isolation Valve. -It'also

h[:' ' olifted wires for bypass valves in the ResidualHeat. Removal System and the Core Spray System.

0= This TMR will prevent the valves from opening

[ during an Appendix R fire.p

b ' 89-152 This THR removed the pressure compensating

( piston.and spring from the Recirculation Pump

f "A" Seal' Purge Line Valve. The piston assembly

} was not allowing sealing water to pass through.Flow and pressure to.the Recirculation Pump

(- Seal'will be maintained via the needle valve inh the flow control valve and the manual globe

valve upstream of.the flow control valve,e,

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