ML19269C503

Monthly Operating Rept for Nov 1979, & Maint Summary Omitted from 781214 Transmmittal

ML19269C503
Person / Time
Site:	Oyster Creek
Issue date:	12/14/1978
From:	Mcclain C JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19269C499	List: ML19269C498 ML19269C503
References
NUDOCS 7902050143
Download: ML19269C503 (14)

Text

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a ggg. AVERAGE DAILY POWER LEVEL y;

DOCKET t...... 50-219 UNIT.......... O. C. ti REPORT DATE... December 14, 1978 COMPILED Bf... C.M. MCCLAIN TELEPHONE..... 201-455-8748 MONTH November 1978 DAY MW DAY MW

1. O. 17. O.

2. O. 18. O.

3. O. 19. O.

4. O. 20. O.

5. O. 21. O.

(C- 6. O. 22. O.

v

7. O. 23. O.

8. O. 24. O.

9. O. 25. O.

10. O. 26. O.

11. O. 27. O.

12. O. 28. O.

13. O. 29. O.

14. O. 30. O.

15. O.

16. O.

790205 O N 3

OPERATING DATA REPORT OPERATING STATUS UNIT NAME.. 0YSTER CREEK DOCKET NUMBER.. 50-219 UTILITY DATA PREPARED BY...C.M. MCCLAIN 201-455-8748 REPORTING PERIOD... November 1978 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(NET MWE)... NO RESTRICTION REASON FOR RESTRICTION, IF ANY...

7 NO RESTRICTION h0 NTH YEAR CUMULATIVE HOUPS IN PERIOD 720.0 8016.0 78360.0 HOURS RX CRITICAL 0.0 6105.4 60510.2 RX RESERVE SHUTDOWN HRS. 0.0 0.0 468.2 HRS. GEN ON LINE 0.0 6069.0 59340.3 UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERMAL ENERGY 0.0 10277193.6 99267730.9 GROSS ELEC ENERGY 0.0 3522180.0 33879515.0 NET ELEC ENERGY 0.0 3396123.0 32668231.0 UT SERVICE FACTOR 0.0 75.7 75.7 UT AVAILABILITY FACTOR 0.0 75.7 75.7 UT CAPACITY FACTOR MDC 0.0 60.3 69.2

$.I?CAPACITYFACTORDER 0.0 65.2 64.1 FORCED OUTAGE FACTOR 0.0 2.0 5.2 THE STATION IS SCHEDULED TO STARTUP DN DECEMBER 9, 1978

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKE T NO. 50-219 UN:T NA51E Oyster Creek 41 DATE December 14, 1978 C05fPLETED BY - McC1ain REPOR T 510N Ill November 1978 -455-8748 TELEPitONE e.

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Report =

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mU El yL Action to cC 2 32- Present Recurrente 5

8 780915 S 720 C 1 NA ZZ ZZ7ZZZ Refueling /rnalntenance outage.

I 2 3 4 F Forted Reason: M e t h od . Exhibit C Instructiont S 5,heduled A Equipment Failure (Explain) 1 Manual for Preparation of' Data 841aintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refuehng 3 Automatic Scram. Event Report (LI:R) File t M' REG-D-Regulatory Restriction 4 Other (Explain) Ol6l) i E-Operator Trainmg & License Examination

. F Administrative 5 G-Operational Error (Explaini Exhibit I Same Si.orce 19/77) II-Ot he r ( E xplain)

Oyster Creek Station #1

• ? DockeL No. 50-219 OPERATIONS

SUMMARY

- NOVEMBER 1978 The unit remained shut down through the nonth for refueling and maintenance.

A repair bracket assembly for Core Spray System 11 sparger was fabricated and installed under the provisions of 10CFR50.59 A Technical Specification change augmenting core spray sparger inspection and revising the Core Spray System Il flow requirements was submitted to the NRC.

The new radwaste liquid / solids system continued in limited operation through the month. Modifications and maintenance to the major components of this system continues.

A successful primary containment leak rate test was completed on November 24, following repairs to several components. The initial attempt at this test resul ted in a leak rate exceeding allowable limits.

A station evacuation drill was conducted on November 21, with State of New Jersey involvement.

At the end of this report period, preparations for reactor startup continue.

The reactor and containment heads are installed and final surveillance test-ing is in progress. No. I diesel generator is out of service for repairs following failure of the loss of power diesel generator initiation test.

Six reportable occurrences we-- identified during the report period.

R0 #78-26 occurred on November 21 when torus to reactor building vacuum breaker actuation switches DPS66A and DPS66B ruptured while pressurizing the containment for the integrated leak rate test. The switches were re-placed with a switch rated for higher pressure.

RO #78-27 occurred on November 25 While performing routine surveillance of reactor high pressure scram switches, RE03C was found to trip 9 psi above the allowable trip point.

R0 #78-28 occurred on November 29 when main steam line drain valve V-l-106 failed to close and two tip ball valves failed to close during the reactor low-low water level isolation surveillance test.

R0 #78-29 was identified on November 30 and involves initial failure to meet acceptable prima ry conta inment leakage limits. Drywell vent valves V-27-1 and 2 and the isolation condenser vent valves exceeded allowable leakage.

R0 #78-30 occurred on November 26 when containment spray pump "D" failed to start during routine surveillance testing.

R0 #78-31 occurred on November 30 when No. I diesel generator failed to pick up load during simulated loss of power testing.

Oyster Creek Station #1 Docket No. 50-219 IPETRIEENT CORRECTIVE MAINIDMNCE OF QASL ITENS FOR M0tTTII OF NOVEMBER,1978 ITD4 EQUIPMENT MATFUNCTION CORRDCTIVE 1CfION 1 Primary Containment Isolation V-24-29 did not close during Replaced defective Relay 6K27 testing with new one 2 LPRM 20-41D, 20-17B,04-17B, are Replaced LPIM's inoperative 3 Rx Protection Systen Faulty Relays in panel 6R Replaced 1Kl, 1K2, 2K1, 2K2, with and 7R new relays and c M Wed for proper operation 4 LPRM Faulty LPIN's36-33A, 36-09A, Tightened cmpression fittings on 28-49A,20-41C, 12-41C,12-33D, detectors; disassenbled, cleaned 04-17D and reassenbled 5 Rx sanple line off "A" Recirc. V-24-29 Faulty Air Solenoid Valve Replaced Air Solenoid Valve with a new model 6 Torus Invel Indicator Danaged Level Indicator Replaced and Calibrated Indicator with new parts 7 Stack Gas Monitor Cannot Clear Iow Sample Flow Adjusted Switches for Proper Alarm Operation 8 DWEDT Ievel Alarm IIigh Level Alarm is on con- Exercised and Adjusted Switch for tinuously and will not clear Proper Operation 9 IBM #18 Drive failed to withdraw or Disassenbled drive gear, inspected insert and reassenbled. Operation checked satisfactory 10 "A" Isolation Condenser Pipe Break Alarm caning in frequently Cleaned contacts on Relays 6K3A2 Alarm 6K5A 11 CRD Module 34-19 No Invel Alarm Flushed out Instrument Block and tested Ievel Switch. Satisfactory 12 IICU #46-19 Faulej Pressure Switch Replaced pressure switch and adjusted to proper setpoint

INSTIMEff CORRECTIVE MAINITNANCE OF Oyster Creek Station #1 QASL ITENS FOR MONTH OF NOVEMBER,1978 Docket No. 50-219 ,

ITEM EQUIPMEtIP MALFUfCTION CORRECfIVE JCTION 13 IMI-Output Buffer Faulty "Systm Start" Push- Cleaned Switch Mechanism and button Switch will rot bring worked satisfactorily without Systm on the line hanging up 14 Rx Invel Narrow Range Indicator Indicator reads about one foot Replaced meter lower than recorder when selected to A or B 15 "B" Service Water Pump Radwaste Discharge Pressure Gage not Calibrated Gage and Tested-working Satisfactorily 16 Core Spray Syst m RE17A - Root Valve Stm appears Replaced defect'_ve valve bent 17 CRD Position Indicator CRD 34-31 Indicator Green-Green Found short on Pin #22 to Ground in all positions fran ER-28 (Cable Rom) . Replaced with new probe and test satisfacto 18 APRM Ch. 1 Flow Converter Does not perform scram function Replaced new KIA & K2A Contacts 19 "B" Stack Gas Monitor Does not respond correctly to Detector does not fully seat in i source shielded chamber due to plastic

. covering hanging upon metal tip.

Pushed plastic covering back and reseated sensor.

20 Rx Protection Systm Systm I MSL Break Mercury Replaced mercroid switches in Re--

Switches Re-22A, Re-22B, Re-22E 22A, B, E, &F with new ones and

& Re-22F failed after MSL Hi calibrated

• Temp Switches in Trunnion Romi were installed 21 "A" Isolation Condenser Level Tramnitter is not working Flushed out transmitter and Transmitter properly calibrated

Oyster Creek Station #1 Docket No. 50-219 ,

QASL ITE24S FOR MCtEli OF NOVEMBER, 1978 ITEM QTIPMEIR MALEUNCTION CORRELTIVE ACTION 22 Old Radwaste - Waste Surge Tank IcVel Indication went from 60% Cleared lines of water and IcVel to 90% re-calibrated 23 NC30B Difficult to regulate pressure Checked calibration of I/p below 70 psig positioner and installed new filters 24 PS-lJ29 Clean-up Systan Tripped Replaced broken wire #368 on'CB2 in Panel 3F and tested satisfactory 25 Service Water Systan Malfunction in service water Re-calibrated transmitter and pressure indication in Control tested satisfactory Roan 26 1-1 & 1-3 Tip Drives In-Shield switches failed to Adjusted in-shield switches and

. . cane on tested, found satisfactory 27 (RN 05-E) Off-Gas Rad Mon. Ch. 1 Reset switch on drawer does Cleaned switch and performed front not reset panel check-results satisfactory 28 SRM (Front Panel Test) Ch. 21 surveillance discrepancy Adgustedsetpoincstoalarmat itan , 10 29 SRM Channel 21 No high light og 4F when mode Ad ust setpoints to alarm at switch is in 10 position also 10 SRM Ili Rod Block 30 Stack Gas Sample System Mercoid switch for sanple low Replaced with new switch, flow alarm will not reset when alaun clears 31 Stack Gas Monitoring Systan Vacuun switch not working Replaced with new switch 32 IRM Operability Check Investigation found IRM #145 Restored connector to normal cable was pulled out of cable and' tested satisfactory connector 33 Main Steam Line Monitor #3 Received no downscale alarm Repaired as per Procedure 721.3.001 during testing

d.

0yster Creek Station #1 INS'IRLMENT CORRIETIVE MAINTENA?CE OF Docket No. 50-219 . -

OASL ITEMS EUR FINDI OF NOVEMBER,1978 ITFM EQUIPMENT MAIEUNCTION CORRDCTIVE ACTION 34 Feedwater and condensate AP gauges LP Gauges diecked for calibration Calibrated (6) bartons RV 45 A, B, C,D,E,F 35 "A" Isolation Condenser level Instrumentation checked Calibrated level instrtment.per for calibration Procedure 112-1 36 B-CRD pumps Faulty low suction pressure alarm Cleaned contacts on relays RD 68 A&B 37 CRD position indicators Correct Misc. problans as Correction measures attached to attached sheet to Job Order Job Order 1130I 38 Outage Job RR-37 Replamd 11 SRWIRM connectors SRM/IRM with new ones 39 D. W. Monitoring - Install, connect and test D.W. Replaced detector and installed (critically) nonitors at top new cable of bio-shield-north-side failed downscale 40 Tip indexers ard Tip Tubing Outage Job RR-20 Inspected indexers,undervessel

- tip tubing o

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ELELTRICAL CORRECTIVE MAINTENANCE G' .

QASL ITEMS EDR MJNDI OF NOVB4BER,1978 Oyster Creek 5tatIon #1 Docket No. 50-219 .

ITB4 EQUIPMENT MALFUtCTION CORRELTIVE ACTION

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1 Containment Spray System Relay Relay malfunction Replaced Relays 6K22A & 6K22B 6K22A, 6K22B with new parts 2 Clean-up Systan Relays Overheatirq Replaced all VDC Relays on Clean-up Systan in 1F/2P Panel 3 Isolation Condenser Relays Overheating Replaced Relays with new parts 4 ND28B B Clean-up Filter outlet valve Replaced Relay in "B" filter panel will not open with new part 5 6K46 Panel llF Arching inside panel Replaced 6K46 Relay with new part 6 D.W. Recirc. Fan 1-1 Inspection of Motor Bearings Replaced notor with rebuilt notor 7 Clean-up Systen Relays 6Kl8 & 6K24 malfunction Replaced 6Kl8, 6K24, with new relays "D" Rx Recire. Pump Discharge By-Pass Valve failed Cleaned Valve as.necessary for 8

to open renotely proper operation Primary Containment Isolation V-1-106 Valve did not close during Incated and repaired a loose 9

Surveillance connection at the fuse block 10 Diesel Generator #1 Will not Unload Replaced with new EG Box as per vendors manual 11 Rotary Inverter Ibisy DC Motor TigL a ed metal cover over fly-wheel - motor satisfactory Bottan Entry Instrunentation Outage Job RR-21 Exchange BEI's Pulled detectors fran positions 12 44-41 B, C, D 09 A, B, C, D- Installed new detectors in-these positions.

Oyster Creek Station #1 MIDWIICAL CORRIETIVE MINTENANCE OF Docket No. 50-219 QASL ITEMS FOR FDffli OF IOVEMBER,1978 ,

mLFUICTION CORRBCTIVE ACTION ITEM EQUIPMENT 1 NC-30B Valve does not stroke smoothly Rebuilt Valve when air is applied to actuator 2 Control rod drive module 18-23 V-lll Valve leaking Replaced V-lll valve with rebuilt valve Control rod drive module 18-47 V-lll valve leaking Replaced V-lll valve with rebuilt 3

valve Cleanup System Valvcs Packing leak Adjusted packing on V-16-13 and 4

V-16-14 Rx Building 100 ton crane Bridge Hydraulic brake cylinder Replaced brake shoes and cylinder 5 with new parts leaking Excessive Vibration Inspected pm p and motor couplings 6 "B" CRD*Pmp -

and alignments; lubricated and clxx:ked vibration - satisfactory V-111 Valve leaking Replaced with a rebuilt valve 7 CRD Accumulator 26-31 Valve Packing Irak Adjust Packig 8 V-20-26 ,

Diesel Fire Pump 1-1 Inaking Coolant Tightened Hose clamps on cooling 9 systan

1. 2 Service Water Pump Pump discharge valve has Replaced with new valve operator 10 yoke and lubricated in,ternals sheared pin in actuator Icaking Welded plate over leak in floor-11 Condensate Tank Drain Build-up of borated water Tightened packing glands on both 12 "B" Liquid Poison Punp "A" & "B" Pt.ups around pump V-27-1, V-27-2 needs replace- Replaced V-27-1, V-27-2, with new 13 Drywell vent system valves ment valves

Oyster Creek Station #1 Docket No. 50-219 MIDIANICAL CORRIETIVE !%INTENANCE OF ,

QASL ITEMS FDR bnmi OF NOVEMBER,1978

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ITEM DJUIPMENT MAIEUNCTION CORRELTIVE ACTION 14 Isolation Cond. Vent Sys. Leakage on V-14-2, V-14-6, Disassanbled valves, lapped disc to V-12-1, V-14-19, V-14-5, seat and repacked valves. Inak V-14-20 test proved satisfactory 15 Torus /R.B. Vacuum Breaker Valve V-26-15 Inaks Int. Gled new disc seat and "O" Ri- 4 16 anergency Service Water Systan Corroded pipe supports & Replaced pipe supports and boltinJ foundation bolting need with new parts ard coated with replacing bitunastic Sparger Crack - Needs Repair Install fabricated clanp onto 17 Core Spray Sparger sparger according to special Procedure #78-111 18 C.U. Systen Demln Bypass Valve Valve has a broken yoke Repaired yoke by weldirq 19 l-6 and 1-7 sump transfer valve Actuator will not nove stan Corrected actuator to stan on valve position-freed valve 20 Rx dryer / separator strong back Engagenent. pins misaligned Straightened bent plates and tested to 20,000 lb. load Drywell Head RaTove & Replace Drywell Head Replaced with new gaskets 21 Gaskets .

Isolation cordenser valve V-14-37 Needs additional packing Added 4 rings of packing to V-14-37 22 for satisfactory operation Inspect for damage Disassanbled, inspected, lubricated 23 Off-Gas valves V-7-1 thru 6 bushings and reassanblal Water Icaking past seat into Disassembled valve, found seat 24 Core Spray System I-V-20-27 torus loose and tack weld on disc broken.

Repaired and reassenbled.

Oyster Creek Station #1 Doc.ket No. 50-219 '

MEDIANICAL CORRHXIVE MAINIDWEE OF QASL ITEMS EDR MONTII OF NOVH4BER,1978 ITH4 EQUIPMENT MALFUICTION CORRHXIVE ACTION 25 Rx Building Ventilation Systan V-28-21 and V-28 Rebuilt valve operator and installed malfunctioning new packing on V-28-22, V-28-21 inspected and found satisfactory 26 D4RV Actuator Solenoids Guide pins are scored Machined new guides and welded per Procedure 702.2.020 27 Core Spray II Fill Ptup Will not run Replaced puup with new one 28 D.W. Sunp Pumps Ptup Inoperable Replaced with new ptnp 29 Service water pipe (intake canal) Water pipe under intake needs Repaired as per Procedure 78-107 repair Air actuator needs to be Rebuilt air actuator as per 30 NS03A .- -

rebuilt Procedure 702.1.017 31 NS04A Same as Itan #30 Same as Itan #30 CRD Rebuilding Rebuilding of CRD's Rebuilt as per Procedure 717.1.008 32 ,

Outage job RR-09 CRD Exchange Exchanged 25 CRD's 33 Control Rod Drives control Roan Doors Existing doors are not security / Replaced 3 existirg doors with 34 fire doors - security / fire rated doors Recirculation Systen D Discharge Outage Job RR-l'. repack Repacked D discharge val,ve as per 35 Procedure 703.1.005 valve MSIV - NSO4A Outage Job RR-31 Ranoved and installed air actuator 36 as per Procedure 702.1.014 MSIV - NS03A Outage Job RR-31 RaToved and installed air actuator 37 as per Procedure 702.1.014

- Oyster Creek Station #1 Docket No. 50-219 MECHANICAL CORRECTIVE MAIhTENANCE OF OASL ITD1S FOR 10tTHI OF ?OVEMBER,1978 ITEM EQUIPMENP MALFU CTION CORRECTIVE ACTION 38 CRD P.I. Outage Job RR-35 Replaced 15 P.I. and repaired 3 cable connectors 39 Service water systen and screen Outage Job RP-37A Replaced service water ptrnp 1-1 wash pumps with new pting and notor 40 Emergency service water systen Corroded pipe supports and Replac d corroded supports and bolting needs replacanent bolting with new parts 41 MSIV - NS03A & NSO4A Outage Job RR-01 NS03A - Repaired poppet, replce d with new. stan, repaired weld inside body guide rib.

NS04A - Repaired poppet, replaced with new stan, replaced with new body seat 42 Electranatic relief valves Outage Job RR-04 Inspection Inspectal A atxi E valve as per Procedure 702.1.007 43 Electranatic relief pilot valves Outago Job RR-05 Inspection Inspected DIRV pilot valves E, A, C, & D as per Procedure 702.1.007.

44 Recirculating punp mechanical seals Outage Job RR-12 Rebuilt and replaced B and C mechanical seal 45 Feedwater check valves Outage Job RR-18 Inspected V-2-71, 72, 73, and 74 as per Procedure 728.1.004 e

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Oyster Creek Station #1 Docket No. 50-219 REFUEllNG INFORMATION - NOVEMBER 1978 Name of facility: Oyster Creek Station #1 Scheduled date for next refueling shutdown: Began September 16, 1978 Scheduled date for restart following refueling: December 9, 1978 Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?

No Technical Specification change relative to the refueling is anticipated. It has been determined that no unreviewed safety questions are associated with the reload core.

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

No submittal is scheduled.

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 des i 1, new operating procedures:

No major changes have been made, no. are there any anticipated.

The number of fuel assemblies (e) in the core - 560 (b) in the spent fuel storage pool - 620 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or i s planned, in number of fuel assemblies:

1,800 The projected date of the last refueline that can be discharged to the spent fuel pool assuming the present licensed capacity:

The Fall 1986 Outage.

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