ML19332C069

Monthly Operating Rept for Oct 1989 for Hope Creek Station Unit 1

ML19332C069
Person / Time
Site:	Hope Creek
Issue date:	10/31/1989
From:	Brennan C, Hagan J, Jensen H Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8911220274
Download: ML19332C069 (15)

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New. Jersey 08038 l Hope Creek Generating Station =

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% November 15, 1989

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a. ; 7 l'.,

tO U.IS.' Nuclear. Regulatory Commissio'n' 1

44 DDocument' Control Desk C

7 Washington, DC 20555-k, Dea'rl' Sir:4 i

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'MONTHLYIOPERATING' REPORT HOPE CREEK GENERATING STATION. UNIT ~1 O

p' DOCKET.NO. 50-354-g a.

[;M.

-lIn compliance with Section 6.9, Reporting Requirements for the i

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Hope Creek Technica1' Specifications, the operating statistics.for N

.Obtober are being. forwarded to;you with-the' summary 1of. chang'es, I

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1 tests,.Jand experriments for October 1989 pursuant to 'the P.--

I requirements of'10CFR50.59(b).

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Sincerely yours, J.

J.

Hagan General Manager -

Hope Creek Operations RARisc iAttachment C' distribution-

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COMPLETED BY-H.1Jensen

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50-354:

' UNIT- _ Hope' Creek

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DATE!ill/15/89-N iif,

-COMPLETED BY H '.

Jensen-i i.

. TELEPHONE: (609)-339-5261

[

-(OPERATING) STATUS!

%'...17 l REPORTING / PERIOD' October 1989_, GROSS 1 HOURS 2IN REPORTING' PERIOD 745__

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I,/2hLCURRENTLY'AUTHORIZF,D.-POWERLEVEL:(MWt)-

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l REASONS.FORERESTRICTIONI(IF ANY)-

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THIS-YR TO:

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MONTH-DATE CUMULATIVE.

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NO. OFJHOURS REACTOR'WAS' CRITICAL 0.0 5739.0:

--20,686.6'

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REACTOR RESERVE SHUTDOWN-HOURS

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0. 0' 172 LHOURS? GENERATOR ON LINE-0.0

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-UNIT' RESERVE SHUTDOWN HOURS' O.O

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GROSS THERMAL ENERGY GENERATED D(MWH)'

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?10$s GROSS: ELECTRICAL' ENERGY GENERATED (MWH) 0.0

_5 840,079' 21.066.523 1

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NET ELECTRICAL. ENERGY GENERATED

(MWH) 0.0

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__20;119,117' l

=.l12.

REACTOR; SERVICE. FACTOR N/A

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^ REACTOR AVAILABILITY FACTOR N/A 78.7 8 2.Q;__

413.

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UNIT? SERVICE FACTOR-N/A.

'78.4 81.0 115~.1 : UNIT! AVAILABILITY' FACTOR N/A 78.4 81.0 16 L : UNIT CAPACITY-FACTOR 4"? (Using MDC)'

O.0 74.0 77.7

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UNIT CAPACITY FACTOR er:

(Using Design MWe) 0.0 71.5 75.0

( 18.. UNITJFORCED OUTAGE RATE 0.0 1.2 5.7

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

N/A 1

L20.

IFESHUT'DOWN AT.END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:

11/15/89 t

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' DATE L-11/15/8 9' q

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~. REPORT; MONTH'_ OCTOBER 19 8 9 ' : TELEPHONE ' __- ( 609 )^^ 3 39-5261--

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DURATION.

REASON REDUCING l2 CORRECTIVE ACTION /:

I NO. = DATE.

S'. SCHEDULED

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POWER 1(2)-

1 COMMENTS 1 10 10/1.

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.4-CONTINU.1TIONLOF 7

0 REFUELING. OUTAGE..

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SUMMARY

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COMPLETED BY: Chris Brennan DOCKET NO :

50-354

' UNIT NAME :

Hope Creek Unit 1 1

1E DATE 11/14/09 1

TELEPHONE : -(609)339-3193 1

Month: November 1989 3-7

1. _

' Refueling'information has changed from last month:

YES X

'NO ju 2.

Scheduled:dato for next refueling:

01/19/91 3..

Scheduled date for restart following refueling:

03/05/91-

,.3 -

4._

A)-

Will' Technical Specification changes or other license amendments be required?

YES NO X

-B)

HasLthe-reload fuel-design been reviewed'by the Station Operating Review Committee?

YES NO X

LIf.no,1when is it scheduled?

02/01/91 5.

~ Scheduled date(sf for submitting proposed-licensing action:

N/A ez. -

6.

Important.lidensing considerations associated with refueling:

' Amendment'34 to the Hope Creek Tech Specs allgwp the cycle

-specific operatino limits to be incorporated into the CORE

OPERATING LIMITS REPORT: a submittal is therefore not reauired i

7.

Number of Fuel Assemblies:

A)

Incore 764

-B)

In Spent Fuel Storage (prior ~to refueling) 496

C).

In Spent Fuel Storage (after refueling) 744 8.

Presently licensed spent fuel storage capacity:

1290 Future spent fuel storage capacity:

4006 9.

Date of last refueling that can be discharged to spent fusi pool assuming the present licensed capacity:

03/05/91 I

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-(The[followinglDesign Change. Packages?(DCP'oOhave'been evaluated to

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1F Tif t the Lprobability of >. occurrence: or ;the consequences: of 2 an

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saccident?or!. malfunction:of equipment"importantL..to' safety'

! pre'viously;evaluatedTin the' safety analy' sis'reportLmayfbe '

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fincreased;?or-

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if/aopossibi~11ty for~an-accident'or! malfunction ~ofla

'differentLtype;than any evaluated.previously inLthe-~ safety 4

> analysis >reportJmay be--created;.or '

3)l "if the' margin 1of!s'afety'as defined in the: basis"for any; y

^ technical specification'is reduced.:

"TheiDCP?s did~not(create a new safety-hazard to the plantinor'did:

they affect::theisafe?shutdownioffthe reactor. <The DCPis didcnot; ichange1 theTplantueffluent; releases.and did not. alter-the.existingc 7environmentaltimpact.---The; Safety Evaluationsidetermined that:no

-unreviewed;: safety-or;environmenta1Lquestions are involved.

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DnscriptioniofLDesian:Chanov Packace-4 p

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. This DCP modified"the. removable monorailLat:the

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[Drywell1 Personnel-Airlock. :The modifications.

34

' '7 include theiadditionnof permanent support lugs,.

the installation of end supports to provide p;3>

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-stability, and;theLremoval of the monorail ~and.

3 Jits7 components for storage.. The: monorail' f.

expedites the removal ~of equipment and tools' used'for;maintenancefactivities.

1

-This DCP added steel beams'and lifting lugs to-of!4EC-1030/094 the Main. Steam Tunneloto allow for the. removal.

of feedwater valves.

This.will: facilitate q

T" 2;

maintenance activities being performed.onithese-valves.

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!4EC-1030/10 This'DCP added stee'l beamsLand lifting lugstto.

' Steam Seal Evaporator.Roomlin the Turbine-.

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, Building.

This will allow the removaloof the 2

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' Steam Seal 1 Evaporator.Headsand willtfacilitate maintenance activities.

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4HC-0032-This'DCP changed the position of the bypass valve associated' wit.h the Reactor' Auxiliaries

' Cooling System-Temperature Control' Valve from~

J 7g closed.to three turr.s open.

The--original a

configuration could not~sufficiently-cool the

- Emergency Instrument Air Compressor.

I4HC-0059/02 This DCP-installed an additionallairidryer to' enhance 1the availability of the Instrument Air system.

The new air' dryer will serve as a backup forHthe other' air' dryers, a

-t 4HC-0074/06.

-This DCPL installed lead shielding around the

-Turbine Building Exhaust Monitor and the

-i

'TurbineLBuilding: Compartment Exhaust Monitor.

1 These monitors supply an alarm. based on High Duct Gas activity.

The shielding will filter l

radiation caused by the-turbines.so.that more accurate readings of duct activity can'be obtained.

'4HC-0077/01 This DCP supported the installation of three Condensate Cooling Heat Exchanges to act as heat sinks for condensate from the Plant Steam Heating System by installing tie-ins to the Turbine Auxiliaries Cooling System.

This change will eliminate the hazard of non-(

condensed steam escaping from the vents in the l

r Condensate Collection Tanks.

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'iDescription__of_Desian__ Change Package

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(4KC-0128/02-

Thio DCP Cupport3'the futuro installotion ef o

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crainage system-which will-transport _the Coudensate Effluent from the Technical" Support-8,e Center' Air' Supply Units and the Reactor.

Building, Venti 19 tion System Air Supply Units to

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-the Circulating Water Sump.1 This package is' i' *m

limited to' installing pipe, whieh will,not be

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used until;the entire' drainage sys' n is in place.

~ 4HC-0151/ 01' ThisEtemporary DCP to the Station Service-Water system' diverted the 3ervice Water flowing to the Cooling Tower Basin,=or. cooling Tower Bypass Line to'a manhole in the y&rd during Mode'5.

This modification wiii. permit draining, of the Cooling Tower and the buried yard piping.

to perform modifications to the Service Water

. System' Return to the Cooling Tower piping.

4HC-0151/05-This DCP modified an elbow in the Reactor

(

Auxiliaries Cooling System "B" Heat' Exchanger

' Outlet portionsof the Service Water piping.

The modification includes the addition of flanges to facilitate maintenance on the elbow.

4HC-0195/0E

.This DCP' replaced the Inboard and the Outboard-Containment Isolation Valven'for the Process Sampling Line off of the "B" Recirculation Loop.

The new valves will permit more flow to the sample panel.

The additional flow will be utilized by the Crack Monitoring System, which 15 was installed by nCP 4HC-0195/02.

7 4HC-0195/02 This DCP installed a crack Monitoring-System, which ties into the Recirculation Sample Line.

The system will_ analyze Recirculation Water to monitor the effectiveness of Hydrogen Water Chemistry 1and_the potential for crack. growth'in the' Recirculation Line.

4HC-0207 This-CCP modified the 5 out of 6Eautomatic trip arming circuits to the Secondary condensate System and the Reactor Feed Pump System.- An-automatic trip will now be initAaled according to which pumps are running to_ avoid tripping the pumps in strings.

'4HC-0217 This DCP increased the number of Fuel Pool Plate Heat Exchanger Channel Plates from 73 per 14 unit to 100 per unit.

This increases the heat tv exchanger capability and provides an alternate udkci decay. heat' removal path when combined with the

'M bypass of the Reactor Water Cleanup Non-Regenerative heat exchangers during refueling.

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f RCl Descrip_t_ ion of_Desion Change _Packag_e_

4HC-0222 This DCP installed an orifice in the Safety Auxi?.iaries Cooling System Loop "A" Piping b

controlling cooling water flow to a Residual Heat Removal Heat Exchanger.

4HC-0225 This DCP modified the Reactor Feedwater Runback control to arm on the loss of one Primary Condensate Pump or one Secondary Condensate Pump with 2 of 3 Reactor Feed Pump Turbines on line and feedwater flow at the required level.

4HC-0256 This DCP added an interlock to the manual start circuit of the High Pressure Coolant Injection Auxiliary oil Pump to prevent the overpressurization of the High Pressure Coolant Injection Discharge Piping during startup.

This interlock will prevent the Auxiliary oil Pump from starting until the Steam Admission Valve has lifted off its seat or until 12 seconds after tho' pump start switch has been engaged.

4HC-0282/01 This DCP added a synchrocheck relay to the "A"

^

Emergency Diesel Generator.

The addition of the synchrocheck relay provides a permissive to the operator, preventing the synchronization of the generator unless the incoming and running voltages are in phase.

Synchronizing the generator when it is out of phase could cause extensive damage.

4HC-0282/02 This DCP added a synchrocheck relay to the "B" Emergency Diesel Generator.

The addition of the synchrocheck relay provides a permissive to the operator, preventing the synchronization of the generator unless the incoming and running "oltages are in phase.

Synchronizing the generator when it is out of phase could cause extensive damage.

i 4HC-0282/03 This DCP added a synchrocheck relay to the "C"

Emergency Diesel Generator.

The addition of the synchrocheck relay provides a permissive to the operator, preventing the synchronization of the generator unless the incoming and running voltages are in phase.

Synchronizing the generator when it is out of phase could cause extensive damage,

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This1DCP ladded: alsynchrocheck rel'ay. toJ the

'.'D"' M L, Emergency Diesel. Generator. The? addition,ofi, d .g. M al. tV the synchrocheck. relay provides a. permissive.to N 1 ig the operator, preventing the'.: synchronization of) ? m 4 ed C 1

the; generator:unless the incoming and runningi 7"

W4 voltages.are inephase.. Synchronizing the [

generator when it is out of phaseLcouldi

causei t

y extensive-damage.

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W i;; b r 's T 3 f ^1 Midg DefihiccyRCp;rts'(DR'h)/'hsv0bOCnCydluatOdto 2 '.T 9 [;ttrainot: f,4 d tv -:i O L -- 1)* 'if the' probability 7of occurrence or-the. consequences of an > accident.or malfunction of equipment importantato safety-6 previously; evaluated in.the safety analysis report may be [ ' increased; or. I$ ' 2) 'if-a: possibility for an accident or malfunction of a different i K' type.than:any. evaluated.previously in'the safety analysis f;, . report may be; created; or i '3) . ifJtheimargin.of. safety;as-defined in the' basis for any .i de . technical specification is reduced. The:DR's 'did not create a.new saf ety hazard.to the plant nor: didt .they affect: the safe shutdown of the reactor. The DR's didinot i changeEthe'plantieffluent releases and did'not alter the existing environmental' impact. - The Safety Evaluation determined that no V,-unreviewed safety or environmental questions are: involved. i 't s .h, - f A i I C 9 k s s P 1 -lil _ { f a .I f h r 6 e

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[ Safety' Evaluation DescripM on__of Deficiency _ Report-89-01k0 'A control rod blade (position 30-15) would not ', recouple to its associated drive inLaccordance 6 'with RE-FR.ZZ-002(Q),-Control-Rod Removal and, Installation.- The uncoupling /rodEwasi preventing: recoupling;'therefore,.it was-

removed and the

Contro11 Rod was.recoupled.

- l Operating'without the Uncoupling Rod:has.been . analyzed and the.DR has beenfdispositioned " user as is". 89-0141' iA coritrol rod-blade (' position 14-23)-would not-Erecouple'to-its~ associated 1 drive incaccordance

with-RE-FR.ZZ-002(Q),' Control Rod Removal and' Inste11ation.

The uncoupling rod was-- preventing recoupling;'therefore, Lit was '.a . removed and the Control Rod..was recoupled'. ^ Loperating without'the Uncoupling Rod has.been analyzed and the DR has been-dispositioned "use as is". 89-0144' 'There is.an area in the "A" Feedwater-Line Inlet Check Valve, where the present wall thickness is less than the required wall thickness for a class 900 valve. Thir1DR~has, UU been dispositioned "use as is and rework during: the, third refueling outage". Thisidisposition is acceptable becauseLthe maximum design. pressure;for this valve is 1800 psis compared .to the 2250 psi rating for class 900 valves. g 8 s b; {'-_ .a 4 l? t ~ i 'i v 2$1 ~ l}}