ML19269F503
| ML19269F503 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/14/1979 |
| From: | Mcclain C JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19269F502 | List: |
| References | |
| NUDOCS 7912210310 | |
| Download: ML19269F503 (8) | |
Text
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AVERAGE DAILY POWER LEVEL DOCKET 0......
50-219 UNIT..........
O.
C.
ti REPORT DATE... December 14, 1979 COMPILED BY...
C.M.
MCCLAIN TELEPHONE..... 201-455-8748 MONTH November 1979 DAY MW DAY MW 1.
631.
17.
567.
2.
589.
18.
586.
3.
609.
19.
595.
4.
615.
20.
595.
5.
617.
l' i.
600.
6.
614.
22.
612.
7.
560.
23.
428.
8.
578.
24.
O.
9.
620.
25.
O.
10.
614.
26.
287.
ii.
606.
27.
465.
12.
611.
28.
599.
13.
626.
29.
607.
14.
624.
30.
602.
15.
622.
16.
615.
2163 154 7912210 3/O
OPERATING DATA REPORT OPERATING STATUS UNIT NAME.. 0YSTER CREEK DOCKET NUMBER.. 50-219 UTILITY DATA PREPARED BY...C.M.
"CCLAIN 201-455-8748 REPORTING PERIOD... November 1979 LICENSED THERMAL POWER (MWT).. 1930 NAMEPLATE RATING (GROSS MWE).. 650 DESIGN ELECTRICAL RATING (NET MWE).. 650 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE).. 650 MAXIMUN DEPENDABLE CAPACITY (NET MWE).. 620 IF CHANGES OCCUR IN CAPACITY RATING SINCE LAST REPORT, GIVE REASON...
NONE POWER LEVEL TO WHICH RESTRICTED, IF ANY(NCT MWE)... NO RESTRICTION REASON FOR RESTRICTION, IF ANY...
NO RESTRICTION MONTH YEAR CUMULATIVE HOURS IN PERIOD 720.0 8016.0 87120.0 HOURS RX CRITICAL 683.2 6874.2 67895.3 RX RESERVE SHUTDOWN HRS.
0.0 0.0 468.2 HRS. GEN ON LINE 663.1 6780.2 66561.5 UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERMAL ENERGY 1182375.9 12563611.4 112599606.4 GROSS ELEC ENERGY 406050.0 4301430.0 38441435.0 NET ELEC ENERGY 390745.0 4139359.0 37057149.0 UT SERVICE FACTOR 92.1 84.6 76.4 UT AVAILABILITY FACTOR 92.1 84.6 76.4 UT CAPACITY FACTOR MDC 87.5 83.3 70.4 UT CAPACITY FACTOR DER 83.5 79.4 65.4 FORCED OUTAGE FACTOR 7.9 15.4 6.5 THE NEXT SCHEDULED OUTAGE IS TO BEGIN ON JANUARY 5, 1979 2163 155
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s DOCKET NO. 50-219 UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT N AhlE Oyster Creek #I December l 's, 1979 DATE C. H. McClain REPORT hl0N111 flovember 1979 COhlPLETED DY TELEril0NE 201 -'4 55-6 /'s o e.
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Licensee Eg f.
Cause & Corrective No.
Daic g
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Event gg g3 Action to I-
$E cE 5 ;;j c Report #
in O o
Psevent Recurrence o
3 u
8 112379 F
56.9 G
3 NA CD NA A scram resulted from the inadvertent opening of an isolation condenser return valve during backseating operations. This caused an inrush of cold water into the recirc system resulting in a power spike on the APRH channels.
N l
2 3
4 F: Forced Reason:
hiethod:
Exhibit G -Instructhins U
S: Scheduled A Equipment Failure (Expl.iin) 1-Alanual for Preparation of Data ll-hlaintenance ni Test 2-hlanual Scram.
Ent:y Sheets for 1.icensee C-Refueling 3 Automatic S, am.
Event Report (1.ER)l'ile INUltl.G-W D Regulatory Restriction 4-Other (E xplain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source l'i/77)
II.Other (E xplain)
Oyster Creek Statien ':;
h b
Dl OD occiet No. 50-213 u c...:.-... -s,o a s . - e e.. '.M., c ' t.'.a.. %c.- ~s "..~ ,- v i oi "~. .1... ~.... s c,s _~- - '.~e c- ~-... o.- s - d cutput. Cn ::c ce bor 6, "A" ela:trcratic relief calce lif tcd durinc c. :. I.V state.cc.cer cucratien. O.e valve. ras subse~.uentis c1cstd bv clacing its c:7. trol reitch to "Cff" and rcacter p:'.;er was reduced to 1700 L t to ec. pas. ate for less of the high prcssure relief func:icn fcr de affected valve. Tcliewing re.daccent of the pressure s.ritch for de "A" relief valve, the valve centrol tas returned to autratic and.clant cut. cat was restcred te. ear rated cut. cut. Cn "cV eter 23,1979 a 2cacter SCFJ.'4 cccurred it.en a tec.'nician inadvertently
- nitiated an isclation cc.,fenser Icep ttile backsaating the 1ccp valves fellc.s-inc a s rceillance test. ?.e plant was restcred to,reter cperati n cn ::crecar 26, fcilewine ccr-letien cf aintc ance activities..c:ferc.25 s _':sgent to the r
Si:. 4pcrt.ble Cccurrences were identified durin de rcn h. R.O. =79-37 cccurred en ::creier 3, '. hen Ccre spray bcester.cco. ':2033 did net start curing the replar : cne'.y surceillance test. R.C. 38 ccccrred cn :;cre2er 5, 7.cn Diesel C-2reratcr ':c.1 failed te c c,:lete t'ce sarting scquance during a rcutine s2 ;cilla ce test. R.C. 39 was identified en ::cvrier 5, tien the 100% ficw rcd block setpcint ..us fcund to be c.reater dan the Tech. S.tec. limit durin: sarfc: ance cf the rcutine surveillance test. R.O. #79-40 was identified en Nove-ler 2, when a :GC Audit noted that de Starr:by Gas Treat ent System charcoal filters were not being tested in full c m.pliance with the Technical Specifications. R.O. #79-41 identified en Neve-ter 2, vten a :GC Audit noted that the Fad saste Euilding Ventilation Fcnitcring System was not in service in a ranner that eculd yield accurate effluent data. ?.C. 42 ccrarred en :;cve;-ter 6, ' ten the pressure switch for "A" electre atic relief valve failed causiric. the valve to c.aen durinc. steadv state.reser c.ceraticn. .B 2163 157 o
Oyster Creek Station #1 Docket tio. 50- 21 <) COlU11L" RIVE ELIUrRICAL MAT?fflNANCE ON OASL I'IU1S FOIt 'IIIE Motfl11 OF NOV'74!!Elt 1979 T L('m 4 D uilment tblfunction Corrective Action i 1 DG fl Output breaker failed to close (1) Aljustal breaker position wilrh during surv. test (52illi) (2) Inspected 52iIII switch on 42 IG Breaker - fourvl satisfactory 2 Core Spray Dooster Ptsip NZO3B breaker failed to close a (1) Technician noted that FZ03n NZO3B second (2nd) tine af ter NZ0ln was closirvj fuse agyearnl loone - minually secured durirvJ perfourvuice checked fuse & conpleted surv. of core spray auto start surv. test satisfactor,/ 610.3.005 3 1-7 Sump Isol. Valve V-24-36 No open invlication during testiivj (1) Itealigned valve position swi tch 4 Fire Diesel 1-2 Battery B1 Failed to meet " specific gravity" iteplacal battery acceptance criteria of 1.25 af ter an oIoalizer charge 5 Air Ejector (gas) Isol Syst I solenoid coil shorted when Iteplaced solenoid coil durini Valve V-7-4 local fire nozzle initiated naint.cnance shutdown irudvertently in August 6 "C" Feedwater Ibrp Failed to trip when mutually lleplaced shorted trip coil securiny punp U Cl3 ~ a
Oyster Creek Station #1 Docket No. 50-219 CORRIIT. IVE Ift~i'11Gi[NP fMINfFNAfCIO ON QASL ITDtS FOR TIIH FDtJfil OF iWl~tBl31 1979 llem 4 Equipn2nt, i111 function Forrective Action 1 SIN #21, 22 & 24 Front panel test discrep's (10 cps) Meadjusted 2 AIN R010A Control Room Initiates alann prenuturely "crfonoxi calibration (as foon1 alication was high) 3 Intake Water Tenp Channel Ioss of IIP processor & recorder leplace & calibrated respective ru/T ciruulel indication 4 0 Analyzer Calibr. request to substantiate replaced defective recorder 2 inclication inplifier & calibrated 5 EIN "A" pressure switch Setpoint drifted down 1eplaced pressure switch (high pressure trip) 6 Rx Press Recorder (NR) Calibr. request to substantiate
- 1) Minor calibration required indication
- 2) Iteplace drive bushing as IN 7
IIN 616 Front panel test discreps (125'l.) Ieadjusted 8 TIP Detector R1 Detector failed electrically w/ Peplacal detector physical dannge evident (active aal seturated from bilance of spiral cable upon renoval). 9 SIN's Front pinel discrep's readjuslol 10 AIN - Old Itadwaste Outside I)2 Lector connector loose reconnectal connector & veri f int . inlication N u o
Dyster Creek Station #1 Docket IJo. 50-219 1L "Alet & Vent" ltadiation Out of stcp, (occasionally) Inbricalal strppinwg :;olenoid Itm order 12 S111 821 & 24 FronL txmet test discreps (10 cps) (1) SlJi #21 - replacol nnter (2) Siel #24 - adjustol raiole sigiul 13 APlet #5/I141 #1511ecorder Rmorder ten iionantarily drives cleanol (sprayed) contacts of downscale selector switch 14 tJ Purge Valve V-23-13 Closes 0 1 psig drywell press - Itecalibratal V-23-13 controller 2 preventing repressurization of IM following vac. bkr. surv. 15 DW/Ibnis Pressure Recorder Drive cord loose Tightenal cord pulley 16 "A" Elu Pressure Switch Foutyl setpoint had drif ted down Itcplacol pressure switch with 17 psig frcm previous surv. calib. re<xanditioned replacarent 17 API 41 FronL [unel test discreps Ita[uirol low voltage tour sutply readjust 2 rent 18 LP141 Upscale lites on 4F pnl Upscale lights dim during perial Iteplaced liglit 1xdb after fiivling (Jut an upscale on Irl41 12-17A circuit satisfactory was experienced 19 1151 #16 Itange 6/7 correlation requirol /vljust al It44 in preany 20 Scram Dump Vol Isolation Significant air leak 0 upper pilot itetxiill rJC-15A Solenoid Valve tX'-15A 21 Itx Icvel Recorder Erratic inlication Cleanol slidewire N U CD
Oyster Creek Station il Docket flo. 50-219 CORRICTIVE f RCilAfJICAL MAltll'I7W3CF Ot1 QASL I'll?-LS FOR '11IP. IOffill OV IKNI!iHEll 1979 Item !!
- Fquncnt, thlfunction CorrecLive Action 1
"A" CRD Ptup Oil leak on lower siglit glass to Itcluiral sight glass oil reservoir 2 CitD Acctmulator 38-27 V-111 valve leaking Installed rebuilt valve 3 CitD Accinuttlator 06-39 V--lll valve will not close Installed reluilt valve 4 Itefueling Bridge 119' Wire rope on bridge nounted aux. Iteplaced with new wire r<p2 hoist indly frayed 5 "A" Cleanup ptuip Inixurd ncchanical seal 1 caking Replaced with new seal 6 "A" Cleanup ptaup Seal water reservoir - sight Casket surface cleanni, glass gasket leaking replacal gasket aivl ti<iht enoel 7 Fire Protection System V-9-35 spring on lull civrk clrain Iteplaced spring valve niissing 8 "A" CitD Filter I)irty Installed new fil1.crs 9 "B" Cleanup Pump Outboard ncchanical seal l etik ii n i 1:oplacol with new seal N U o
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - NOVEMEER 1979 Name of facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: January 5, 1980 Scheduled date for restart following refueling: March 15, 1980 Vill refueling or resumption of operation the eafter recuire a Technical Specification change or other license a e 6t? No Technical Specification change relative to the refueling is anticipated. Scheduled date(s) for submitting proposed licensing action and supporting information: 1. December 1979 - Cycle independent General Electric fuel design information and safety analysis for future use. 2. No submittal is scheduled for the use of Exxon fuel. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: 1. General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by 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 are any anticipated. The number of fuel assemblies (a) in the core - 560 (b) in the spent fuel storage pool - 620 The. present licensed spent fuel cool 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 fue; pool assuming the present licensed capacity: The Spring 1987 Outage. 2163 162}}