ML20012A283

1989 Annual Operating Rept for Wolf Creek Nuclear Generating Station. W/900228 Ltr

ML20012A283
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1989
From:	Boyer G WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NO-90-0048, NO-90-48, NUDOCS 9003090151
Download: ML20012A283 (17)

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~WL$LF CREEK

. NUCLEAR OP.ERATING CORPORATION -

John A.Se% s February:28, 1990-

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NO 90-0048, L U. 7 S. Nuclear Regulatory Consnission .

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-ATTN : Document Control Desk '  ;"'

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$je 'Washingtoni D.:C. 20555 y

1989 Annual. Operating Report;for'

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Subjects Docket No,'50-482 m' Wolf Creek Nuclear Generating Station 7

',l <}c' W; Gentlemen:e

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.: The . attached Annual Operating ~ Report is being submitted pursuant ' to Wolf -

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Creek; Generating Station.1 Unit No. 1, . Technical Specifications 16.9.1.4 and o

Also included;in this report is'information1requiredS by: 10 ..CFR s g ,- '

L6,9.1.5.

i S(20;407. This report c.over's-operations-for the period'of January 1,/:1989.to

. December: 31', 1989.-

1 s W Very truly yours, ys'

.i John A. Bailey

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,', Vice President-

. Nuclear Operations Jia (

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. t'tachment.

cc t ; 'E. J. Holler (NRC), w/a

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'R~-D.' Martin (NRC), w/a D.'V.: Pickett.(NRC), w/a

' M.' E. Skow (NRC),: w/a

-i . 9003090151 900228 i PDR ADOCK 05000402 y p PNV r

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P.O. Box 411/ Bur",ington, KS 66639 / Phone: (316) 364 8s31 An Equal opportunity Ernployer hW/Hc/ VET =

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WOLF CREEK NUCLEAR OPERATING OCRPCRATICN

P NOLF CREEK GENERATDG STATICN .

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-i DOCKET NO: 50-482 FACIIJTY OPERATDG LICENSE: NPF-42  :

AleIURL OPERATEG REPCRP REPORT NO: 5' Reporting Period: January 01,-1989 through h '-x 31, 1989 i

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Prepared by: Merlin G.-Williams Approved'by:

" 'G."D.Uloyer l

Plant Manager  !

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EKBCUI'IVE StDMARY l 1 The purpose of the Annual Operating Report is to provide a u p dsensive sumary of the operating experience at Wolf Creek Generating Station, h Annual Operating Report also provides a sumnary of the major safety related neintenance activities ampleted during the year. 'Riis 7.wi. covers the period beginning on January 01, 1989, and.ending on December 31, 1989.- l h Annual Operating Report is subnitted in armenen with the requirenants of Technical specification 6.9.1.4 and contains the information required by Technical Specification 6.9.1.5. h format of this report is similar to '

that provided in Regulatory Position C.1.b of Regulatory Guide 1.16, Revision 4, August, 1975.

Also included in this report is the infonnation on personnel monitoring as required by 10CER20.407.

In 1989, Wolf Creek Generating Station was the nation's top energy producer .

with gross electric generation of 10,109,742 Megawatt-hours. h unit's availability factor was 98.4 percent and capacity factor-(using mav4==

dependable capacity) was 97.7 percent for 1989.

Wolf Creek Generating Station experienced two Reactor trips in 1989. N

'first trip occurred in January, 1989, and the second trip occurred in February, 1989. Pbilowing the second trip, the Reactor Isnained critical k'i through C+ +r 31, 1989.

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3 SLMmRY OF OPERATDG EXPERIENCE A sunmary of Wolf Creek Generating Station's operating experience arxi I major safety related maintenance activities cxmpleted during 1989.is provided by nonth below. 'Ihis infonnation has been previously subnitted in accordance with the requirenants of 'Dochnical Specification 6.9.1.8 - ,

in the Nanthly Operating Reports for January through December, 1989. '

' January

, Initial criticality following the third refueling outage was achieved at 0352 CST, on January 01, 1989. After ocupleting low-power physics testing, the unit entered Mode .1, Power .,

Operation at 0904 CST, and was synchronized to the grid on January 04, 1989, at 1620 CST. A normal post-refueling power L ,

ascension culminated with the unit at 100 percent power on-January 09, 1989, at 1035 CST.

On January 21, 1989, while implananting a plant modification on Fire Protection Systan local Halon Control Penal KC-230, it was

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diswvmel that several lugs were in- ,--rly crimped per current starviania . . Action was initiated to inspect the other six similar panels.' These inspections identified similar discrepancies. Evaluation of this condition concluded that the panels were still capable of pMnnning their intended functicms d based on successful canpletion of parirvlic survaillance *W, maintained continuity in the wiring and'the low voltage application.

Investigation into this event revealed that the wiring in question was installed by a es*=pplier to an original equipnent vendor. At the time these panels were installed there were no specific unique Wolf Creek Nuclear Operating Cw.gu.u_ tion (NCNOC)-

inrv = d cri ring standards for the panels. Since that time, the specifications for Fire Protection System conpanents have been revised and made are stringent. 'Ihe psy - for obtaining vendor servloes was revised to ensure adherence to NC2OC standards if any future panel wiring work-of this nature in involved. All~ halon control panels have been reworked. The other potentially affected similar Fire Protection Systen panels that serve to protect safety related equignent were inspected and reworked as necessary. Fire Protection Systan panels associated with the station transformers are to be insr=ce and reworked as unit conditions allow, but ccinpleted no later than the conclusion of Refuel IV. 'Ihere are several Fire Protection

- Systan panels which were procured frun a different vendor and may not be subject to this type of wiring discrepancy. A plan

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E for inspecting these panels was developed and inplemented.

', i L Based'on the results of the inspections performed, no further

[< COu.act.ive actions were required for these panels.i ('Ihis event D was reported to the NRC as Licensee Event Report 482/89-003-00.)'

l On January 23,1989, at 1322 CST, a Reactor trip occurred as the '

result of a spurious signal in the bearing vibraticn nonitoring - '

circuitry wnich inwu..ci.ly indicated high vibration on the Main Turbine Number 7 Bearing. 'Ib prevent additional unnar==ry

' challenges of Reactor Protection Systems, the Turbine high vibration trip circuitry was modified to provide an alarm (mly function rather than a trip function. -('Ihis event was reported as Licensee Event Report 482/89-002-00.) : Following the.

restoration of plant systes to normal configuration, the plant was restarted entering Mode.1, Power Operation, at 2100 CStr, and n

returning to 100 percent power on January 24, 1989, at 0730 CST.

Ch January 28, 1989, at 1210 CST, the failure of a speed sensor on the Main Feedwater Punp required a reduction of. power to 65 j

percent. Following the coupletion of the repair, the unit - j returned to 100 percent power on January 28, 1989, at 2300 CST.

Major safety related maintenance activities for January:

. a. Replacenant of Main Feedwater Isolation Valve AE-FV-42 red

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. trafn acctmulator.

b. Replacement of Reactor Coolant System Icop 4 -Delta-T r Isad/Iag' Circuit Card BB-TY-441K.

c. Replacanent of Chemical and Volume Coretol System Charging Punp Header Pressure hansmitter BG-r7.120.

d. Replacement of Neutron Monithring System High Range Reactor Trip B1 stable Circuit Card SE-3C-306.

e. Replacement of a Control hilriing Heating, Ventilation and .i' Air Canditioning System Control Room Pressure Filter AF+ M ec Pressure Transmitter GK-PDT-81.

February 1

On February 02,1989, at 1321 CST, a Reactor trip occurred fran 1 100 percent power as a result of Steam Generator "C" reaching the low-low level trip setpoint following closure of Main Steam Isolation Valve "C". The cause of the Reactor trip was detennined to be a loose screw on a tenninal strip in the Solid i l

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State F4uerdon System which as bW during the performance T of unrelated nedntenance resulting in a fast close signal to l Nain Steam Isciation Valve "C". %e Main Steam Isolation Valve u wsctions wre tightened and other terminations in the Solid .;

State F4 vection System and other Control Room process cabinets were checked and tightened as necessary. (his event a s-reported:as Licensee Event Report 482/89-004-00.). Following the restoration of plant systens to nomal configuration, the plant.

entered Mode 2, Startup, at 2252 CST, on February 03, 1989, and Mode-1,: Power Operation, at 0544 CST, on February 04, 1989.- 2e . .

unit returned to 100 percent power on February 05, 1989, at_0700. .

CST.

.On February 08,1989, at 1753 CST, the =avi=== electrical ~ l generation was reduced ~25 Megaatts as the result of declaring 3 Heater Drain Punp "B" ine=w=rable because of a defective  ;

mechanical seal. On February 10,1989, at 0535 CST, Heater L i Drain Ptap "B" as returned to service following the cxmpletion of repairs. '

Se unit operated at 100 percent power throughout the remainder of the nonth.

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_ Major safety related maintenance activities for February:

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e a. Checked electrical schene terminations on control circuitry 1 o =hinata of the Neutron Monitoring System, Reactor j Protection System, Engineered Safeguards Features Actuation l System, Ioad Shed and Bnergency Ioad Sequencer System, and 4 L, Miscellaneous Control Panels.

- March

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ne unit operated near 100 percent power throughout the nonth.

On March 06, 1989, at 0838 CST, survaillanne testing showed the l- Control Rods for Control Bank "C".and Shutdown Bank "A", Group 2 to be ineparable but trippable. Subsequently, it was determined

, that the problem was due to a cold solder joint on an associated circuit' board. .At 1025 CST, on March 08, 1989, Control Rods were restored to operable status.

• Ch March 24, -1989, at 1057 CST, Heater Drain Punp "B" was secured to facilitate repair of steam leak at a pipe plug al the -

casing. %is resulted in a reduction in generator load of approximately 23 Megawatts. At 1933 CST, Heater Drain Pump "B" was returned to service. l i

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[ d I Attachment to NO 90-0048; W Page 6 of ,, ~ qc p Major safety related naintenance activities for Marcht

a. Replacement of Centrifugal Charging Punp "A" to Reactor Coolant' Pimp. Isolation Valve Controller BG-EC-8357A.

b. Replacement of T-ring, 0-ring, and aanpression ring on Train i

"B" Essential Service Water to Turbine Driven Feed Pump

- Isolation Valve AL-HV-033.-

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} c. Raplacement of cylinder head gaskets on Positive Displacement Charging Pung PBG04.

d. Replacement of fast-speed starter coil on Cantainment Cooling Fan SGN01B.

m April

'the unit operated near 100 r.=vuut pcuer throughout the nonth.

On April 19, 1989, examinations of the Fire P46Mdon System (FPS) piping revealed that int =nlate penetration of the pipe seam welds existed in the discharge header for the Motor Driven Fire Punp (NDFP). ' Subsequent examinations detected linear indications in additional piping in the MDFP and Diesel Driven Fire Pung-(DDFP) discharge headers, indicating that the j candition of this piping was ques +irmahla. At P ry

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modification was installed to bypass the questionable piping, thereby removing it from service.

'Ihe root cause of the inconplete pi==ria.ation of the nanufacturer's electric resistance pipe seem welds is unknown.

To prevent recurrence of this-event, an evaluation of the FPS piping was conducted to determine an aau.vp.-iate permanent piping replacement for the NDPP and DDFP discharge headers. A section of pipe with a pin-hole was sa uvai for failure analysis. Following receipt of the failure analysis twi., the FPS was evaluated to ensure the potential for this piping

' failure mechanism is minimized. ('Ihis event was Koru.1.ed to the NRC as Licensee Event Report 482/89-009-00.)

._, a Major safety related maintenance activities for April:

a. Realignment of Safety Injection Punp "B" pump and notor,

b. Replaosnent of sensors on Control Building supply air chlorine nonitor.

M c. Replacement of controller for Centrifugal Charging Pumps Bypass Flow to Baron Injection Tank Valve EM-HV-8837A.

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- On May 07; 1989; at 0456 N, Heater Drain Punp Motor "A" suffared a' phase-to-grourd short resulting in a loss of 30 Megawatts. electrical.

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'On May 14,1989, at 1248 CDT, power as radw=4 to 96 percet..  !

, for isolation of a condenser eter box to plug a ' leaking tube.  !

'Jhe unit.was returned to 100 percent at 1642 CDr.

On May 15,1989,- at 2145 07F, a load rejection of 32 Megawatts .

occurred as the result of a 'Dnhine control ci.rcuitry problem.- '

On May 16, 1989, at 1338'CDT, a load rejection of 20 Megawatts occurred. Control was placed in manual, ~siabilized, and load ,

returned to nomal. 4 On May 22,1989, at 1956 Cyr, Heater Drain Pump "A" was returned to service. . On May 26,1989, at 2001 CDP, Heater Drain Punp "A" was removed from service for additional realignment. On May 27,- j

-1989, at 0140 CDP, load was reduced to 80 percent at the request? '

of System Operations. Heater Drain Punp "A" was returned to-service on May 28,1989, at 0015 CDP, On May 29,1989, at 1452 ~

CDT, load was increased to 100 piu.u:mit at the request of System  ;

Operaticms. '

._ Major safety related maintenance activities for May a.- Replacement of power supply in Engineered Safeguards s Features Actuation. System rahinet.SA075B.

b. Replacanent of mechanical seal on Fuel Pool Skimner Pung PEC03.

L c. Overhauled Pressurizer Backup Heater Breaker PG2201. I i>

d. Replacement of an instrument isolation valve on Centrifugal  ;

Charging Punp "A" discharge pressure instrument.

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E e. Replacement of the power factor meter on Li=u.yaicy Diesel '

i Generator "B".

l June On June 03,1989, at 0904 CDP, electrical generation was reduced 30 Megawatts due to Heater Drain Pung "A" being removed fra service to balance the shaft. At 1151 CDP, the punp was I

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retan:ned, to service. On June 07, 1989, at 0459 CDP, Heater Drain Punp "A" as removed frun service to rahalame the shaft.

It as returnnd to service to 1530 cur. t On June 09,1989,~at 2210 07f, the steam supply to High Pressure y Heater "7A" was secured-to repair a flow orifice flange leak.- '!

Ch June 11,1989, at 0000 CDP, the heater us returned to service. ,

On June 13,1989, at 2309 Cur, th1ating Wter Pump "A" was  ;

secured to repair an oil leak. Power as limited to 90 p=.At.

by the setback circuit. The setback circuit was ta-marily disabled and power returned to 100 percent on June 14, 1989, at-1412 CDP. On June 15,1989, at 0444 CDP, the punp was returned to service. On June 16,1989, at 0446 CDr, Circulating Water .;

Pump "B" es secured'to replace its cooling water outlet valve.  :

At 1233 Cur, the punp ms returned to service. At 1310 cur, the setback circuit as re-instated.

On June 25,1989, at 1745 CDT, Reactor power was 'radnmi to 98 .

percent in order to install a nodification on the Malance of

. Plant Omputer System. On June 26, 1989, at 0625 CDP, power was returned to 100 percent.

Major safety related maintenance activities for June:

a. Set limit switches for the Essential Service Water Systen

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Containment Isolation Valves EF-HV-47, 48, 49, and 50 for

' R flow adjustment.

L' b. Conducted Train "A" and'"B" outages on the Control M 1d bg Air Canditioning Units SGK04A and B and' Class 1E Electrical B;[uipnent Air Conditioning Unita SGK05A and B which included ranlacig or plugging sane of the

-derdier tubes.

July l

On July 10,1989, at- 2344 cur, comenced decreasing Reactor  ;

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power, entering Mode 2, Startup, on July 11, 1989, at 0217 cur,' '1 to replace four bolts on Main Feedwater Regulating Valve "A".

l With the unit in Mode 2, Startup, with Reactor power at

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approximately one percent, a Feedwater Isolation Signal occurred when the water in Steam Generator "A" increased to the high-high I

L level setpoint. Consequently, a Main Feedwater Pump trip, a '

Main Turbine trip signal, Steam Generator Blowdown and Sanple l' Isolation' Signal and an Auxiliary Feedwater Actuation Signal L were initiated. All Engineered Safety Features equipnent required to operate responded properly. 'lhe water level in -

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Steam Generator "A" was decreased below the high-high level ,

setpoint and the actuated systems were returned to nomal '

configuraticn at a um.imately a 0400 CDT.

'Ihe analysis of this event concluded that leakage through the - 1 Main Feedwater Bypass Control Valves ambined with the Steam l Generator ." swell" induced by opening of the Steam Dunp Valves caused Steam Generator "A" level to reach the high-high level'.

setpoint. 'Ib prevent recurrence of this event, the Licensee Event Report was aMarl'to required reading for all Operations e p==. u u al . A caution es aMari to the aa n.vplate pucsidre to '

serve as a reminder of the potential for leakage through the Main Feedwater Bypass Control Valves. ('Ihis event was Awan.i.ed 3 as Licensee Event Report 482/89-013-00.)L Four bolts were i ranlami on Main Esedwater Regulating Valve "A" and at 0517 CDT, n the unit entered Made 1, Power Operation. At 1720 CDP, the L..

I; Reactor a s at 100 percent power.  ;

On July 18; 1989, at 1912 CDP, Heater Drain Pump "A"' was secured '

'to tighten the stuffing box extension bolts. Electrical o generation was reduced 25 Megaatts electrical. At 2300 CDP, .[

Heater Drain Punp "A" was returned to service and electrical 1 generation as returned to normal. .1 On July 19,.1989, at 2202 CDP, Heater Drain Pmp "A" was secured to replace the stuffing box gasket.. Electrical generation was.

) reduced 25 Megawatts electric. On July 21,'1989, at 0735 CDP, Heater Drain Pep ."A" was returned to service and electrical' generation was returned to nomal.

On July 23,1989, at 0126. CDP, a Turbine runback to 995 Megawatts electric-(85 percent) occurred. h runback was the j f result of surveillance testing in su a ss at the same time the {

setpoint drifted causing a second channel to trip. Reactor L

L power was ruoimui to 100 percent at 0206 CDT.

On July 25,1989, at 0143 CDT, Heater Drain Pmp "A" was secured I

because of a steam leak at the p m p mechanical seal. Electrical generation was reduced 25 Negawatts electric. h seal was LP replaced and on July 26,1989, at 2311 CDP, Heater Drain PLmp l- "A" was returned to service and electrical generation was L returned to nornal.

Major safety related maintenance activities for July:

a. Reworked and/or replaced tubing on Control Building Air Conditioning Units SGK04A and B and the Class 1E Electrical Equipuent Air Conditioning Units SGK05A and B.

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m. . r August

'1he unit operated at 100 percent power until August 09,.1989, at:

1920 cur, when Reactor power as-lowered to 95 percent to repair a manway leak on Iow Pressure. Feedwater Heater "4B".- On August..

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10f 1989, at 0000 07r, Reactor power as at 99 percent with work l continuing on the manway leak. - At 1054' cur, Im Pressure l Feedwater Heater "4B" was returned to service and Reactor power =

m s restored to 100 percent. At 1723 CDT, Reactor power was 1 again rariwwi:to 95 percent to repair a level switch on High i Pressure Feechster Heater. "7B". ' On August 11, 1989, at 0300 1

. CDP, High Pressure Feedwater Heater "7B" ms returned to service '

and Reactor power was returned to 100 pu.-t.~ The unit - i remained at 100 percent power for the remainder of the month. q y . Major safety related maintenance activities for August:

Ly a. Repaired leak on instrument line to pressure sensor on Class-lE Electrical Equipnent Air Conditioning Unit SGK05A.

b.- Replacement of mechantem1 seals and Wings on Cmponent. t

N1 Lng Water Punp PEG 01C.  !

c. Replacement of motor on Containant Spray Punp Discharge Isolation Valve EN-HV-6.

I h September The unit operated near 100 percent power throughout the nonth.

Major safety related maintenance activities for Septaber:

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' .a. Replacement of Jacket Water Tenperature Switch K7-TS-50 on Limiu.ywacy Diesel Generator "A".  ;

b. Replacement of jacket eter pump seals on Emergency Diesel Generator "B".

. c. Replacement of 4-way slide valve and 0-ring on Feedwater R Isolation Valve AE-FV-40. '

d. Replacenant of Slave Relay K637 for Centrifugal Charging g Pmp "A" Recirculating Miniflow Valve' BG-HV-8110.

L October i F On October 01,1989, at 1550 CDP, Reactor power was reduced to 55 percent to replace a power supply on Main Feedwater Pump "B". At 2105 cur, Reactor power was returned to 100 percent.

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- y- x On G54- 17,1989,. at 1425 CDT, Reactor power was reduced to 30 percent to replace the power / load inbalance trap 4 m in the p Turbine control cabinet. At 2052 CDT, Reactor power was

[ .. returned to 100 percent.

'- On Gru.ir:u. 30,1989, at 1429 CST, Reactor power was incranar=1 1 2.2 percent because of a revicion to the calorimetric s vv lare

• which uses measured steam flow versus measured feedwater flow, his.was.ompleted in respcmse to an apparent feedwater venturi .

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fouling problem which caused indicated feedwater flow to exceed j actual-flow. his condition caused measured thennal power to be  :

higher than actual until the calorimetric' guvalore was revised.

Major safety related maintenance activities ~for Octr' hart L :a. Replacement of Train "A" Input Relay K129 in the Solid State L Fu.d.sction System.

s b .' Replacement of . engine driven jacket water pung mechanical seal on Emergency Diesel Generator "A". [

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c. Replacement of 4-way valve actuator on Feedwater Isolation Valve AE-FV-040.  :

November L- 1%e. unit operated near 100 percent throughout the month..

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i 01 November 17, 1989, it was determined by a calculation that }

'the as-built configuration of the housing for both trains of ;j Containment cooling fan heat exchangers was not seismically  !

g ul Hied to withstand a Safe Shutdown Earthquake. It was

' l further determined that this situation placed the Wolf _ Creek Generating Station in a condition outside the design basis of the plant.

! 4 L' his ' m1 & ation was parhnel in response to a notification by l

i the Architect / Engineer (Bechtel Power Corporation) of generic  ;

t errors / discrepancies in the original seismic gm1Mication H report. Upon canpletion of the m1mlation, both trains of Containment cooling fans were declared ingwahle. A plant p nodification package was developed to install additional seismic i '

restraints. We installation of the restraints was empleted on .

November 19, 1989, on Train "B" and November 20, 1989, on Train "A", thereby restoring both trains of Containment cooling fans to operable status.

A detailed review and evaluation of the original seismic analysis methodology in ocuparison to the conservative methodology utilized in Novmber,1989, is being performed.

(Wis event was Icported to the NRC as Licensee Event Report 482/89-020-00.)

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A Major safety related maintenance activities for Ncwenbart l 1

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a. Replaoumont of unloader head on Train *.B" Class 1E Switchgear Rocan Air Conditioning thit S3K05B.

b. Replacement of mLat eliminator filters on the Main Stamm and '

Peedwater Isolation Valves. ]

c Decenbar  !

'Ihe unit operated near 100 percent power throughout the month. l Major safety related maintmance activities for December: '

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a. Replacement of sensors on Control m41riing Supply Air .;

Chlorine Monitors GK-AT-2 and 3. '

b. Replacement of 4-way valve on red train Main Pee &mter ,

Isolation Valve AE-PV-40.

c. Replaosnant of synch check relay on anergency Diesel Generator NE02 Output Breaker 152NB0211.

d. Replacenant of stationary cantact on Essential Service Water '

Punp Supply Bmaker 152NB0215.

e. Replacement of thermal element in 'Ituperature Control Valve

K7 ' ICV-160 on Emergency Diesel Generator "B".

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l 2. StaemRY OF OUIRGES AND PtECED POWER REDUCTIONS Provided below is a sunnavy of the 1989 outages and forced power reductions of over 20 peromit of design power level where the reduction extended for nore than four hours. References to reports of reportable occurrences directly related to each outage or load reduction are

, included in pLrenthesis where arnlirwhle.

1. Start Date -10/07/88 Otmpletion Date: 01/04/89 Type: Scheduled Duration: 2151.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 1

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Reason: Continuation of refueling outage, resulting in 84.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of planned outage for January. 'Ibtal number of refueling outage hours was 2151.3.

Attachment to NO 90 0048 L

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2. ' Start Date: 01/23/89 canpletion Date: 01/23/89 Type: Pcrood Duration: 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Hanson: Reacta trip caused by Main 'nuinine high vilretion trip.

(Reported to Imc as Licensee Event Rep x t 482/89-003-00.)

3. Start Date: 01/28/89 canpletion Date: 01/28/89 Type: Pcrood Duration: 10.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Reason: Reacta power reduced to 65 percent to replace a faulty Main Peedwater Punp speed sensor.

4. Start Date: 02/02/89 Canpletion Date: 02/04/89 Type: Pcroed Duration: 42.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Reason: Reactor trip caused by Main Steam Isolatico Valve "C" closure. (Reported to NRC as Lloensee Event M r.ai. 482/89-004-00.)

5. Start Date: 05/27/89 Canpletion Date: 05/29/89 Type: Scheduled Duration: 61.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> g Reason: Reacta power reduced to 00 percent at request of the Ioad Dispatcher.

6. Start Date: 07/11/89 canpletion Date: 07/11/89

'Iype Scheduled Duration: 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Reason: Entered Mode 2 to replace four bolts on Main Feedwater Regulating Valve "A".

7. Start Date: 10/01/89 Canpletion Date: 10/01/89 Type Forced Duration: 5.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Reason: Reactx power reduced to 55 paroent to replace a power supply on Main Feedwater Punp "B".

8. Start Date: 10/17/89 Canpletion Date: 10/17/89 Type: Forced Duration: 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Reason: Reactx power reduced to 30 percent to replace a power / load inbalance transducer in Turbino control cabinet.

l Attachment to NO 90 0048 b , Page 14 cf 16

3. D30SWE INPGOOLTIN O. NLMBER OF PER!KNGL A10 MhN REM BY WORK AND JOB FiMCTIN REPORP - 1989 NW4BER OF PERSONNEL (>100 NREN)* 'IUml. M-REM 2 WORK & JOB PUNCTION S MPION UTILITY CONITUCT S MTIm UTILITY 00tmUcr MN O an gotims 8 8 . 86 . 88 .!!-

imarir Staff 1[Okf N Staff 8 b .1

.b3

• bb

.0 0

bh 0 0 . 49 Rout:me Plant Maintenance Ma;mteranco & Construction 0 2 .46 .

N hics & lab h 8

.8k  :

1.g98 h

att1*ig itEli

• St^" 8 8 :8! :88 .$

i t ce Construction 1 .3 . .4 th Physics & lab 8 Btta"ig itfili" 8**"

8 8 8 :883 :888 :8d Spec;al Plant Maintenance f

Mx atanance & Construction th Imb

.g *g

. 2.

7 csIficeStaff

&O . 5 .b8 Staff 0 . 27 . 00 . 48 Mb o Omstruction 0 0 0 .189 .000 .203 Hmfn' 1cs & Iab 2 8 8 1: :898 :881 BENTAME3it2fP*8**" 8 8 8 81)

b88 :888 :813 Refueling Maintenance & Oanstruction 0 . 0 .000 .

ations 0 8 .000 th ics & Iab 1 &O?fice Staff . . .

inser Staff

. 15 tenance & Construction 0 21 1. 8 . 00 S.21 hics&Iab 8'"" 1 k 8 4. 8 88 'h SU1'14 it2 fit

• e 8 8 8 :f11 :8f8- :li)

Grand 'Ibtals 22 1 24 7.492 .218 6.272 fNumber of perscnnel > 100 mmu based or PIC data lur.il man-rem based on ratio of PIC data applied to TID data

5 Att:chment to NO 90-0046 4 ..

Pogo 15 cf 16 v

b. PERS3MEL KMTKRIIG RERRT

1. In 1989, 2779 indivhls were pimidad personnel monitoring deviosa. 'this infomatica is prwided in accordance with 10CFR20.407(a)(2). 'Atis total includes the ntatier of individuals required to be reported under 10CPR20.407(a)(1).

2. Below is a statistical stannary report of the personnel nonitoring information recorded for individuals for whom pnzsonnel monitoring was ptwided in 1989 in accordance with the requirements of 10CFR20.407(b).

Estimated whole body exprtre range Number of individurlis (rems) in each range le manan wahl e exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 259 4 Haasurable exposure less than 0.1....................................... 137 0.1 to 0.25.............................................................. 36 0.25 to 0.5.............................................................. 11 0.5 to 0.75............................................................... 1 1

0.75 to 1.0............................................................... 0 1.0 to 2.0................................................................ 0 2.0 to 3.0................................................................ 0 3.0 to 4.0................................................................ 0 4.0 to 5.0................................................................ 0 5.0 to 6.0................................................................ 0 6.0 to 7.0................................................................ 0 7.0 to 8.0................................................................ 0 8.0 to 9.0................................................................ 0 9.0 to 10.0............................................................... 0 10.0 to 11.0.............................................................. 0 11.0 to 12.0.............................................................. 0 12 + ..................................................................... 0 1

1

Attk hment t2 NO 90-0048 Pag) 16 cf 16

c.

• SomCE T DMR

'Ihe infomation prwided in Section 3.a is based on estimated exposures obtained ima Pocket Ionization Ommber (PIC) readings.

'Jhe infomation prwided in Section 3.b.2 is obtained fran 'Ihemal Ianninneoant Detmeter (TLD) readings which is the official record of exposures. 'Jhare is a dis + cy in the total n=har of personnel having received greater than 100 ansn exposure during 1989 in the two sections. . Ihis discrepancy results from the difference in the ranges used in reporting exposure information. Regulatory Guide 1.16 requires infomation for personnel with greater than 100 mran whi.le 10CFR20.407 requires infomation in ranges, with one range beginning at 100.mrun. Therefore, an individual with 100 mram is reflected in Section 3.b.2 but is not reflected in Section 3.a.

4. SIIGLE RE[ EASE T RADIOhCTIVITY OR RADIATION EKPOSWE GRFJmR ' MAN 10 PERCEle & AIIDORE AleUAL VAIIJES For each outage or forced reduction in power during 1989, there were no single releases of radioactivity or single radiation exposures greater than ten percent of allowable annual values.

5. OIALLEIGES 'IO 'JHE PCRVS AND SAFEIT VALVES During 1989, there were no challenges to the Pressurizer power operated relief valves (PORVs) or safety valves.

R '

6. INDICATIONS T FAITED PUEL During 1989, no examinations of Ar= Hated fuel were pecfamed.

7. REACKR 000LANP SPBCIFIC ACTIVITY IN EXCESS OF TBCHtGCAL SPBCIFICATION 3.4.8 LIMI'IATICH During 1989, there were no instances in which the Reactor Coolant System exW the 'achnical specification 3.4.8 limit of one microcurie per gram Dose Bguivalent I-131.

.,