ML19332G144

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Monthly Operating Rept for Nov 1989 for Hope Creek Unit 1. Refueling Info for Dec 1989 Encl
ML19332G144
Person / Time
Site: Hope Creek 
Issue date: 11/30/1989
From: Hagan J, Loeper S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8912200213
Download: ML19332G144 (14)
v • d • e


Text

{{#Wiki_filter:,,id#t^"# 1 _y . y ;,, ;,-[- ' 'i -{ \\v-Public Service Elbetric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station L ) M /l December 15, 1989-l 2 y 'U./-S.: Nuclear Regulatory. Commission Document Control Desk 10, ' 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 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:sc Attachment C: Distribution 8912200213 891130 f PDR ADOCK 05000354 R PDC g ~The Energy People 95 2173 (5W 32-08

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+ ' ;c n M f 1 *'i ^ ~ & - COMPLETED?BY; zS.:Loeper1 a:. r e t':;f'$ '\\ f lt ll ' y ^g _.e m .e m TELEPHONE--- 3 0_9) 339-5257- .~. n' - ' + 4 4 1 $ ( k MONTHi (November ~19894. m.. W; -- w, . u-., c 8;e s DAY-AVERAGE ~ DAILY' POWER LEVEll' _ g-t ~ iJ A ~ (DAY'AVERAGExDAILYsPOWERLLEVEL: gMW 4 }(MWe~Ne t); J (MWe-Ne t ). 4 ~ 4 Y j 4 wi /1.; 20

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\\ h-p, ;9:> - g. $p& s.. s a' W,d 'e OPERATING DATA REPORT %9 * ' ' y Q' DOCRETJNO.: 5,0-354 g v- ~, l UNIT _._HopeiCreek: , :n.C _DATE7,1Jf_15/_89 ) w COMPLETED BY. . S._Loeper-

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TELEPHONE _1609) 339-5257 ~ m[ ~ W R OPERATING? STATUS!' my* -- gg ;- i , ] T.- 1REPORTINGDPERIODlNovembe_ril9_81 GROSS. HOURS:IN. REPORTING ~ PERIOD ~'7230,_ w p. 12f.; JCURRENTLY. AUTHORIZED'POWERiLEVEL-(MWt) 3293 m. i A ' MAX.. DEPEND.--CAPACITY 1(MWe-Net)' 1031 DESIGN; ELECTRICAL' RATING;(MWe-Net) 1067-' 3'.'LPOWER--LEVEL TO;WHICH1 RESTRICTED (IF ANY) (MWe-Net) None y ,mn W4. 2 UREASONS FOR'RESTRICTIONf(IF ANY) ,4 psl THIS: YR.TO V6 -35_1_.2 d6098.2-21,045.8 c5(?NO.LOFLHOURSREACTORLWAS; CRITICAL CUMULATIVEL MONTH DATE s + n, '16s tREACTOR: RESERVE-SHUTDOWN HOURS 0.0 0.O' O. 0- <i s 'hS i Q JHOURS GENERATORJON<LINE' 281;5- _,6;003,4 -2_0a,635.5 ..y. c m -y % )f8?;> UNIT!' RESERVE SHUTDOWN HOURS ~ 0.0 0.0' O.0- .c g. -a p 19.'1GROSSlTHERMAL? ENERGY' GENERATED- ? 2(MWH)E 8833697' 182_6_19,861' 164,623,575' 4 $g 00'. LGROSSiELECTRICAL; ENERGY.- 1 lQ (GENERATED (MWH) 293,620 1 6, 1 3 3a 6 9 9 __ _;21,360,143 q' O. s M 1,0 NETIELECTRICALLENERGY GENERATED I ?(MWH); 274,394: _5,,84.3,411 _20i393,511 L m M. REACTORISERVICE FACTOR-49.9-76.1 81.4 k' ^ l }7 fl134 1REACTORfAVAILABILITY FACTOR 49.9-76.1 81.4 j A 39.1 74.9 79;8-i s 14.v DUNITJSERVICE. FACTOR-~ V6;,

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JK Jy?M "- n. hi-C OPERATING DATA REPORT 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 THE TYPE 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 4

SUMMARY

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=f,y g is + ~w 4 + 3 y, E y+ ' n i3 , ~.. - ist i I ~$ hk' j 1 M. t, J-REFUELING INFORMATION l ?p ' f.. DOCKET *NO: 50-354 i i 'l k. 1COMPLETEDlBY:-lChris_Brennan UNIT NAME: Hope Creek: Unit 1 4* - DATE::12/15/89-TELEPHONE: 43193 MAY - EXTENSION:'N1A d 7+s. m< me j ~ 1 [ Month' December'1989- [ a f N ' 1+1*.i[Ref'uelingLinformation has=-chang'ed fromilast-month: %E, ; ' f ~ ~ 'YES .NO X J[ g ;g, N dh1Sdheduled/:dateforinextrefueling: 01/19'/91 s. (M; [ ~3. ESbheduleddate fortrestart following refueli.ng _0_3105/ Jill. lj .n. = 5 WilliTechnica1. Specification changes or'other' license; ~T f 4 '. - - A ) - i' t' L

amendments,be-required?-

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B)( Has.the reload; fuel designibeen reviewed by the' Station g

[ Operating Revi~ew? committee?- w YES: NO ' X W Ifino,-when is it scheduled?.-~ '02/01/_914 f b ,'4 15? /ScheduledL date(s)-[for1 submitting proposed licensing action:: N/A-j l. d. e y 4 o mc

Iinportant Llicensingt considerations ; associ~ated L with Lref ueling :/

i E' h, '. 6. ?-Aniendment' 34E to' the Hope Creek Tech Specs : allows tho' cycle q 0 -specific op,erating-limits to be incorporated 11ntorthe CORE.- ( s --OPERATING LIJMITS' REPORT 1 a submittal isith_e nfore not q; .. required. w 4;jn .(Number of FuelLAssemblies: e7.. : i 764-d JA)sIncore-4 'LB)"In' Spent [ Fuel ~ Storage-(prior to refueling). 496 4 4 C)LIn Spent: Fuel' Storage.(after refueling)' 744 1 N g'7 m,J18h.Present licensed spent eg fuel storage d f ," capacity: 1290 j W 4006 e 4< sy y;.~ iFuture spent fuel' storage capacity: .W a c 4 R JP 6-19..N Datelof;1ast refueling that can be-j A ~ discharged to! spent fuel pool. assuming .j the?present licensed capacity: 03-05-91 ja+ i 4 3.. . lie l b-( GE~ .f ';& f

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r wq ' yy, p;; 1 a I ,A" 2: zf;gs... yD %y . HOPE CREEK GENERATING l STATION: ' MONTHLY: OPERATING :,

SUMMARY

Vo 1 NOVEMBER 1989-r + L ~ V':1.,.. .. ) ':+ * 'q,,.

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=. 4 s. bp,ayHope Creek enteredt.thecmonth of-November with the second- } gg jf" ::madeito; restart theireactor'and:on; November 216,-the'reactorRefuelinglOutage:.i~n prog ~ress 4 m- 'I 'achievedicriticality.1;On November"19, the;generatorswas online. l 1 ? >, ' ' : ending?the second:: Refdelin' 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 - y 6 - icollection...- Power -was freturne'd to rated : the. saine -day. - on ti M (November 30',7the:plantiLeompleted:-its 12th-day of-continuousi J; 1 power operation.: h 1 i, . hl. ; lC j ). ( ~ e i:, i {' 4 '>. f'. e f =

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SUMMARY

.0F CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION- ' NOVEMBER-1989 1 I j j 1 i i k i l s 0 m

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.. :j :, .1 v _ Y+:q;hd iTheisfoll'owing1-DesignlChange; Packa'ges!:(DCP,'s)f have. beenTevaluated to.' S [#determin,eE g ~ a ..-t ' p r. ,1.m ; w m ,. =-. Qp Q1)L Iifd hejprobabilityfofLoccurrence or theEconsequences ofLan'. t$;r, -accidentLorcmalfunction.ofu quipment"important'to safety: e i (previously!ovaluatedlinithelsafety. analysis report'mayibe: g~ k 1 , Jincreased;ior i m _" 4 N . ~ _.. ..n = y 7

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giffaLpos'sibilityiforTan ac'cidentior" malfunction'of at ~ ? C 40 ~ ?different typeL than' any1 evaluated'previouslyfin^the: safety ? Janalys'i'sfreport=may be created; or f L 4 i P", E3)f -:ifithelmarginiofisafetyfas defined int the basisifor anyf d s j. etechnicalsspecification is ieduced.; ' 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 Evaluationstdeterminedlthatino: 't e, Ounreviewed; safety:ior environmental 1 questions are' involved 1 4 { . ~ q [ g .c t 2

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Description ofLDesi.an Chang L ackace'-- P L3 4HCp0127/0i .This DCP re-routed-drain lines:'so:the-drainage-l k. i M %_ a(' effluentssfrom various' Reactor: Building SampleL

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?^\\ StationfSample Points wouldidrain'to:eitherqthe '[ Condenser or..the Clean.Radwaste-Systemi- 'Re - s routing the drain 111nes will reducelthe-. volume J* Si in f' 'being: processed through theLDirty.Radwaste l[W "pL yg ' iSystemf.c ] s ....s 4 This-DCP installed a steel' platform,-: gravity. 14HC-0298r ,, x$f <' Egates,' and:handreils inside the Drywell. 'It. M .also modified:an existing ladder. The: addition! l 4 of.thisLequipment will establish, safer workingD

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- ^V -1 + 4HC 0333/O'2 This DCP rewired a multiplexer to return it'to-f W its ori~ginel. configuration.- A pr'evious yl, s M? a 'modificationLprovided this multiplexer with ant 01 uninterruptable power supply.. That MD

modifi' cation was requirediduring:the Loss of Loffsite Power Test to record: Reactor Protection

~ s sf^ . System 1GETARS points'. This DCP disconnected-1 .the :uninterruptable power supply and. I i gF qb ' reconnected the multiplexer to its1 original .y --: Reactor Protection System' power supply, i t - ? I c i4HM-0144, , Thia.DCP re-scaled two instruments that moniter. 1 i The new' range?is 00F'to 1200F,.the1 previous-4 the! temperature;of the Cooling Tower Blowdown.- -range.was 0*F'to?100*F which causedLa failure-s l indication"at 98'F. a, - m;n? 0 4HH-O'318 'near the Main Turbine: Control Valves.on anL .ThisEDCP installed temporary instrumentation v 4 . actuator and'the Electr6-Hydraulic Control System Tubing. .The~ instrumentation willibe

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used'to'obtain' data-onEthe tubing support m 3g system'for analysis to determine the-optimum. lj 1,. gy q:- ; . support configuration. n-i4HM-0383' This DCP recalibrated the transmitter supplying-l@ ' flow rate data from-the Cooling' Tower Blowdown [ ~ Weir' Gate to the Cooling Tower-Blowdown . Dechlorination System Flow Recorder. The flow y r meter was detecting a greater than actual flow rate. ) This'DCP replaced the set screws on the L4HM-0391' s g; 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 wheel shaft from moving relative to its bearing.

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f 3 3 ~ Descr_iption__of Design Changg_ Package _ .DCP e CHM-04911 This DCP re-routed tubing from the "C" Condenser to a pressure transmitter. The tubing was run near a Heating, Ventilation and Air Conditioning resistor which cooled down the line, allowing condensation to form. The condensation' caused erroneous high pressure readings. 4HM-0548 This DCP added an Emergency Diesel Generator Annunciator for "Barring. Device Engaged" to the Remote Engine Panel. This annunciator also-will go to the control Room Common Emergency j Diesel Generator Annunciator and the Control Room Integrated Display System, providing additional information to Control Room personnel. ~4HM-0607/03 This DCP eliminated air entrainment of the oil from the "C" Secondary condensate Pump Motor. Bearing Housings. The air entrainment caused the oil to be forced into the= motor housing and [ windings, and also was forced out of the exhaust hood onto the floor, j; rl' 4HM-0643 This DCP changed the setpoints for the Main Hoist Fuel Loaded Interlock and the Monorail f L and Frame Auxiliary Hoist Uptravel Stop. It also eliminated the Monorail and Frame J f Auxiliary Hoist Fuel Loaded Interlock. These modifications make the Refuel Bridge conform to p: the operability requirements of the Technical j . /" Specifications. ] k L o 4HM-0653 This DCP. rewired control panels to correct 3 discrepancies. The Radiation Monitoring System 1 Trouble Alarm was falsely indicating an alarm condition, j k 4HM-0660 This DCP provided a visual /atdible annunciator a alarm for Fuel Pool Low Level and Reactor f Cavity Low Level and analog indication of I Reactor Cavity Level. The alarms and indicators are local indicators on the Refuel l Floor and were installed to comply with INPO j 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. This modification will enhance the operability and reliability of the system. b

'mn.n3. pg%, _ qh s y4;, i L a. ads u a- .o c ,v - r e, n;p gg g y, l, * ,O q wg ; ', " '~' ,h :,, ., n .t r k[gg;v py Nl%;ia .[ n O + ~ 'l ',, Eff - - 4%g [DCPI 'D'es crit,tioniofiDesion: Chance! Pac, hale.. l + C G; ? 54HM-0706; This DCPgprovided permanent lifting lugs toi ii. s allow removal'of..the "D" Service: Water j ~ =. ]cby+ Discharge 1 Valve?and.:its' motor operator. This t V will allow.theTremovaljof'the1 valve and- ,~ l} g;p -operatorf.to facilitate: maintenance. j 7- + i. 5,.- k. j),'.'^ q g V; ; 14,HM-b7081 . ThisiDCP;addedraRiock nut to'each of'.the valve'

j stems'ofxtwo Residual HeatiLRemoval Bypass.

"m Valves and:twoiCore Spray Bypass' Test Valves. d ~ Theolock, nuts-,will: eliminate.the potential!forf valvessteml damage,when~ rotation'ofLthe. valve 1 (stem isirequired to removeJtheLactuator. Q y y. / W.. H S 'e ).4HMf0721/015 This DCP:addedia;1ock nuteto:a Residual' Heat' -. Removal,BypassiValve. <The' lock; nut.will fW",' 4 d. eliminate the potential'for. valves. stem; damage ~ when rotatio'n'of the valve' stem isirequired toi \\ , remove the actuator. 1

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

' Removal Bypass Valve.. The~1ock nut:will h *; ~ eliminate.the~ potential for1 valve? stem damage' m; i f -when rotation-of the valve' stem is. required-to ' L %,, iemove the actuater + k '[ s

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.Q [ *" q., 4 fl.y,*ypfhf? &I ' WN N, ' i' ~ yy n s e-y i N. _.k h. _1 i N M::4., n y ' Y_ }'. _", 3 ?_ R. _g ^[-[y,, y: _s q .w- ' Thei f ollowing: Temporary Modificat'i"onj Requests:-(THR's)fhave been. D 4 Q s.valuateditoidetermine:. e l x m' ' ._--lf_ f* .-'a occurrence 7or'the consequencesJof:an i, ,i P 4, p '.. -:. _ a 3 ?l) Sif thelprobabilityfofs "h accidenti:or:malfunctioniof equipmenthimportant1to-safety u# ) previous.lyievaluat'edfin thersafety' analysis report <may be ~

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rincreased;ior' ,ar ,:m e > Q )? ifKa:;possibilitysfor'aneaccidentvor-malfunction:of.a'. cdifferent:Jtypetthan'any,: evaluated:previously-in the safety-s- 4' jb 'analysisT; report:may befereated; tor: h $, i3)' 'if,the' margin-offsafetyt as definedsin thefbasis forJany: 2D 4 i. technical" specification;is reduced. e The.THR'! sfdid"noticreate ; af riewisaf ety hazard to the plant nor did. 1: theyll affect 6thefsafe shutdown'of the' reactor. :The-THR's.didenot-changeithe' plant effluent releasesiand di_d notoal-ter the existing 4-.' c environmentalLimpact. The.SafetyLEvaluations determined thatino. 'unreviewed:safetySor environmental. questions are involved. t e _Lja-@ - ' L, mt ^O h) e., 1 ?'9_k b

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ll-(s:. ' Safetr Evaluation Descriplipon of Tempora _ry Modification P quest n r g f i,U [h.s s' -h *,, 89-147 This TMR removed the overload heaters from a f bretker for the Residual Heat Removal Outboard [ Shutdown Cooling Isolation Valve. -It'also h[:' ' o lifted wires for bypass valves in the Residual Heat. 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 in h the flow control valve and the manual globe valve upstream of.the flow control valve, e, w 1 7 ) ~ s NM i}}

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