ML20050B140

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jan 1982
ML20050B140
Person / Time
Site: Oyster Creek
Issue date: 02/05/1982
From: Gary Young
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20050B134 List:
References
NUDOCS 8204050035
Download: ML20050B140 (12)
v • d • e


Text

.

/ MENTHLY OPERATIONS SUMRIE JANUAIN 1982 The report period began with Oyster Creek Nuclear Generating Station shut down and an investigation of Isolation Condenser valve operability in progress.

On January 9th, the Cleanup Systs Auxiliary Punp notor overheated causing initiation of #6 Deluge Systs (south side of the 51' elevation - Reactor Building) and subsequent inpleentation of the Eue.1.guncy Plan as an Unusual Event. ME?P Tower instrunentation was lost due to frozen instrument lines on January 14. The following day, Isolation Condenser valve maintenance was ompleted and both Isolation Condensers were returned to an operable status..

That evening the ME7f instrunentation thawed and became operational. Extre e cold tmperatures experienced on January 17 caused operability probles for both Diesel Fire Ptmps. With repairs conpleted, the Diesel Fire Punps were tested satisfactorily and the syst s returned to normal on January 18. On January 24, approximately 740 gallons of slightly contaminated water leaked frm a ruptured Condensate Storage Tank instrument line. On January 25, #1 Dnergency Diesel

. Generator failed surveillance testing due to a leak in its radiator. The radiator was repaired. The Diesel Generator was tested, and returned to service on January 28. The plant r m ained shutdown for the r e ainder of the reporting period.

The following events were identified as Reportable Occurrences during January:

On January 2 Containment Spray High Drywell Pressure Switches IP15A, B and C as found setpoints were greater than the value given in the Technical Specifications.

.On January 18 An improper modification was made to TIP Machine #3 and #4 ball valve circuit breakers that degraded containment iso-lation capability.

On January 21 Reactor Building Closed Cooling Water Isolation Valve V-5-167 failed to properly close during surveillance testing.

On January 22 Containment Spray High Drywell Pressure Switch IP15B setpoint was found to be greater than the value given in the Technical Specifications during surveillance testing.

On January 25 No.1 Emergency Diesel Generator became inoperable due to a radiator coolant leak.

On January 26 Main Steam Line High Flow Instrument RE22H setpoint was found out of the acceptable range.

The following event was identified during January as being reportable within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

On January 17 Fire suppression water syst m diesels 1-1 and 1-2 were rendered inoperable due to extrmely low ambient tspera-tures.

8204050035 820225 PDR ADOCK 05000219 R PDR

= _ - - _ _= __-_ __ __ __ - - _ _ - _ _ - _ _ , _ _ _ - _ _ _____ _

I' UNIT SIIUIDOWNS \ND .'OWER REDUCTIONS '- CreEE U! N. E DATE _Februarv 5,1982 C05tPLETED BY G W YOCnc REPORT MONIlg Jar.uary 1982 (609) 693-6787 TELEril0NE m

5g "g , .Y Licensee Eg 4 Cause & Corrective No. Date g E i;  ;; .2 s 5 Event gi g3O Action to F g :j 5 y<_ ;y, g Report # vi U u

o Pacient Recurrence o

O 22 12/9/81 F 744.0 B 1 N/A ZZ ZZZZZ Shutdown to investic3 ate and correct Isolation Condenser Isolation Valve operability concerns.

1 2 3 4 F: Forced Itcason: htethod: , Exhibit G Instrucilons S: Scheduled A Equipment Failure (Explain) 14tanual for Preparation cr osta ll412intensuce or Test 2412 su21 Scr i:-- Entry St.ects for 1.ieensee C Itefueling 3 Autoinstic:4:am. Esent Iteport (LliR) File (NUREG-D-Regulatory itestsiction 4 Other (Expt:i:.) 0161) 1:-Operator Training & License Exandnation _,

F-Adadnistrati.c 5 -

G-Operational Ee ror (Explain) Eshibit I-Sr.r source (9/17) II OILc (lingilain)

. . . . _ . . . - . . - . . . - - , . . . _ _ - - = - - ~ . - . - - - - - - - - . . . - - . . . . - - - - ,

i' i

I AW.'Rrinii un i L y Po!n:.R t. Lii,y. I i

i D O Cl4 E T . "- . . 50 ?iY

! t JtlIT . . . . . ,, O. C  ;' t a

! REPORi lin L . . . I e n i o. u i- ~ t0, 1702  ;

i COMPILED BY... J . [4 SKLAR

' TEL.EPHONE... . 600--6v3-6013 l i

i

! iiONTil Ja nito. y 1 Yn:'

l DAY- HW DAY rti,!

l i 1 o. i?. O j

o. in. ,,

l 3. O. i '/ . O.

t

4. O. 20, O.

l l

5. O. 21. O. 4 e
6. O. 22. O. f i.

! 7. O. 23. O. "

+

l i 8. O. 24. O.

t Y. O. 2'j . O.

10. O. 26. O.

ii. O. 27. O.

12. O. 28. O. r
13. O. 29. O.
14. O. 30. O.
15. O. 31 '. O.
16. O.

I S

9 9

- - - - - - - - = _ - _--vr-m.m.--- - - - - . -,v---- _ . - - - . . - - - - . . . - - . . - - - - - - , - ..:- - -

y%

a...

, ',is. , { tl' t i PI: PAT Ti40 ~ ? . : 1 i ll.

liti t i i!ntII: O'i /' l' El : CRi .! h e ilii ht. I ilthitM'I' "

't 609- 6V3-6013 IliILITY D AT t-i PREPARED D V , . . ...l . D . SKL/iR 8 iiist e i i '/ l C '

lel l'UR I I Hii l 'l"I' f U f ' .

l.lili-ISED l i-lE Rri6l_ POI,ll P ': Hl41 * . .1930

  1. 1N1 i .b' s l(.iil:1 1 e i l l: P61 'li f t r . a RO!

e UI.. Y t hil LLEGtkiCAL Rn I l HU ( dl: 1 rild E ) . . 6 '.i G n 6 ', I dt ! ri bl.I'l iliefes ti (. ( . Al'a it ' l i / >. t r R t il?

HUl' i .'.*'

t iU X i nut i til..P hilleii f f! f . ( . . I 'e il l l l' Y e' e ll . l # 4WE /

'i.

1. 6 l " I 'I si: OR l' t , i : ~i- ic ,

I 1: tilli Hi LEXi OCCilk [ 14 U .InC i I"i RtiT I H6 N f HCI::

HUWE l'Ul<.idR I.EVEL TO 1411 t Cli RE!'TR1LTED, 11 AHY t Hi:T nlAE i itu RF : < R t : : :'rr!

l '

kl16XUH I:ok kl l'sR IC l'1 feel, tF nHY..

IlO Rl: X'l R IC 1 i UN l

no OH YE6R Cih ilii c.1 I VI .

l 744.0 744.0 .v6iS3.0 ilullRS IN PERIOD 0.0 ,///o.4 Il0URS RX Cit!!a %  :

  • i 6j ' Jt * ' .t , -

tlj' .

1l1t , 1ll ll llll' ' i 1e J

.~

Januarv SlM@3Y O? QASL Electrical b'.M E ,NCE QUIPbE7T BT-J.2 W CTICN CDROICTIE N.TICN Double indication Ibplaced limit switches on both open and close Stand-by Gas Treat:nent System I indication. Cycled valve to show proper indi-Valve V-28-23 Ghm. _

125V DC System Panel B Alternate power light was out Bad light socket. Ibplaced light sodtet and placed back in service.

Electromatic Iblief Valw "C" Clean shorting switch at valve due to Cleaned shorting' switch on valve. Ibcorded new dirty contacts (PM identified) resistance on W. O. as acceptable.

Emergency Diesel Generator #1 After running 10 minutes unit loaded to Did one hour surveillance. Diesel Gen, loaded to 28501Gi from 27501Gi 2750lGi, remained stable, no adjustment necessary.

1-2 Condensate Transfer Punp bbtor Contactor chattering Cleaned contactor. Tested contactor after cleaningc Cbntrol Ccntactor checked satisfactorily.

Emergency Service Water Punp No indicaticn on Anp Meter while notor Indication needle on Anp bbter was sticking. Ib-bbtor Anpere bbter was running placed with new calibrated noter.

Shut Down Cooling System Valve Solenoid Coil for V-17-59 burnt-up Replaced solenoid coil for V-17-59. Cycled sat-V-17-59 isfactorily after replacement.

Aug: tented Off-Gas Reconbiner Wiring harness failed Replaced wiring harness and notor bearing. In-Blower bbt.or "A" sulation was cracked on harness.

Second Icvel Grid under Voltage Lanp burnt out cn "C" phase Ibplaced lanp.

4160V "C" Bus indicating lanp 1-7 Stmp Install new Seal-tite to Iligh Leml Installed new Seal-tite to High Level Isolation Switch Switdi. Filled Simp and Isolated Simp Valve to test switch, satisfactorily.

,k 4

l

, , e , a. .

__21 _: rt a W *b # ~ N Jantary sg.t.ngy OF QAsL Electrical var;Tm;c;G EQUIPfa7f FRIaiNCTION CORREC'fIVE JCTION

. "C" bus 4160V Second level Grid Indicating lanp burned out un& r Voltage Iblanped satisfactory.

Electrmatic Iblief Valve PM Geck. Take resistan of Pick-ip Ebund resistan on A, B, D, and E. Nor-Coil and Shorting Switch nel at 9.60 OliMS. IIad to clean shorting switch on "C" Electrmatic clean-up System Solenoid on FCV/ND22 Valve Ccntroller Ibplaced Solenoid Coil. Placed system chattering back in servi .

"D" 4160V Bus Second Invel Grid Indicating 2v:p burned out uni r Voltage Iblanped satisfactory.

lDrywellPurgeValveV-27-3 Will not close Ibbuilt Air Solenoid Pilot Valve. Valve i

t cycled properly after repairs.

  • NOO8A, CRD Ptmp Motor Oil Sight Glass shows dirty oil Ebtnd outboard bearing wiped. Ibplaced bearing. Ran notor;took vibration an current check. All tested nu;verly.
  • Core Spray System 1 Fill Punp Motor Control Center Breaker tripped obtor neggered bad. Ibplaced notor.

'i "C" Bus 4160V Second Invel Grid under lanp burned out Ibplaced lanp.

l Voltage NR108E Electrmatic Iblief Valve Seal-tite conduit obstructed valve operation Iblocated Seal-tite and retested valve.

Worked properly. Gecked other four Electrmatic Iblief Valves. All o.k.

1 Ibactor Building Ventilation System Did not restore to nornal after iso-i , lation Ebund Iblay XB Cmtact not working, cleaned contact and recycled relay, worked properly.

~

. o January g. m n_ :c g

.___ _ ____. sus.IGRY OF QAS..L Instrument EQUIPFENT FRIENCTION 03RRECTIVE PCTION p Ibactor Protection Relay, IKI8 Excessively noisy and vibrating Reolaced relay and tested satisfactorily.

i Control Iban Annunciators Various alarns did not respond to Ibpaired or replaced alarm modules with test operational soare.

Source Range bbnitor, Gannel 22 Slowly drifting upscale Ibplaced pre-am with ooerational spare.

l 1

New Rackraste EffluentRadiaticn Front panel checks unsatisfactory Electronic reoairs on Fate-meter circuit Monitor board - Performed connlete electronic l calibration.

Intermediate Range Monitor Oscillation on both monitor and

]' Gannel No. 16 Replaced pre-ano with operational spare.

recorder Area Radiaticn Fbnitor Power Front panel meter reading higher than Ibplaced front panel meter.

i Supply (IO-llc) normal Ibcorder for average Power Range Chart paper not advancing Ibpaired switch on chart drive notor.

Monitor, Channel No.1 Internediate Range Monitor, No Ili-IIi light during front panel Gannel No.16 test Ibpla d light bulb, tested satisfactorily.

Safety Valve Acoustic Monitors Monitors are questionable as to their Coupleted extensive trouble-shooting and NR-28F and NR-28N operability repairs on "all" safety and relief nonitoring system satisfactorily tested.

Varicus Scram Valve Position indi- Limit switches on various valves did Replaced or adjusted various micrcMuitches cating lights (Panel 4F) not operate

& * + ww. em. A . ~ *~v

_ January SD M:Zi OF GASL Xnstnrent FAINTEN7ijCE ,,

EQUIP *C Tf MALEUNCTIG4 n CDRRECTIVE PCTIO4 p Control Ibd Drim Selector Defectim relay (nechanical dannge)

. 4K38-31A Replaced relay and tested satisfactorily.

a

Control Rod Drive Diff. Pressure Partial plugged snubbers on sensing l indicating switch RD39 lines Ibplaced snubbers, calibrated indicating f switch, tested satisfactorily.

{ "C" Ibactor Circulating Water Defective 'Iherrowuple j Tenperature Replaced thernomuple with operational i spare, tested satifactorily,

, i 1

Pressure Switch RE-17D associated Water damage dm to fire protection with System II core spray ctluge system Replaced switch with ooerational spare, logic control tested satifactorily.

Ibdundant Fire Protection System Copper tubing to press. switch rup- Replaced copper tubing, tured dm to water freezing within i

4

?

I i

l l

I t

i I

- ~ ___-_.___.___ __ _ _ . , _ _ ,_ , _ _

i o

A l '*

Oyster Creek Station Docket No. 50-219 REFUELING INFORMATION -

Name of Facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: July 1, 1982 Scheduled date for restart following refueling: mid-1983 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendmant?

A Tech Spec Change Request to incorporate G.E. fuel assemblies will be submitted by May 1, 1982.

Scheduled date(s) for submitting proposed licensing action and supporting information:

March 9, 1981 - Complete NEDO document #24195 (G.E. Reload Fuel Application for Oyster Creek) was submitted.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or per-formance analysis methods, significant changes in fuel design, new operating procedures:

1. General Electric fuel assemblies - fuel design and perfor-mance analysis methods have been approved by the NRC. New operating procedures, if necessary, will be submitted at a later date.
2. Exxon Fuel Assemblies - No major changes have been made nor are there any anticipated.

The number of fuel assemblies (a) in the core - 560 (b) in the spent fuel storage pool - 781 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present: 1,800 Planned: 2,600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

The Spring 1987 Outage.*

  • NOTE: This is for a normal refueling. Full core off-load, however can only be accommodated through about 1983 or 1984 with 1800 licensed locations.

' , _

Retrieved from "https://kanterella.com/w/index.php?title=ML20050B140&oldid=2545653"