ML19289C702
| ML19289C702 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/15/1979 |
| From: | Mcclain C JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19289C700 | List: |
| References | |
| NUDOCS 7901220129 | |
| Download: ML19289C702 (10) | |
Text
AVERAGE DAILY POWER LEVEL DOCKET
?......
50-219 UNIT..........
O.
C.
ti REPORT DATE... January 15, 1979 COMPILED BY...
C.M.
MCCLAIN TELEPHONE..... 201-455-8748 MONTH December 1978 DAY MW DAY MW 1.
O.
17.
O.
2.
O.
18.
O.
3.
O.
19.
373.
4.
O.
20.
539.
5.
O.
21.
639.
6.
O.
22 640.
7.
O.
23.
644.
8.
64.
2A.
644.
9.
252.
25.
646.
10.
438.
26.
645.
1 578.
27.
647.-
12.
637.
28.
646.
13.
501.
29.
647.
14.
O.
30.
647.
15.
O.
31.
647.
16.
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OPERATING DATA REPORT OPERATING STATUS UNIT NAME.. 0YSTER CREEK DOCKET NUMBER.. 50-219 UTILITY DATA PREPARED BY...C.M.
MCCLAIN 201-455-8748 REPORTING PERlOD... December 1978 LICENSED THERMAL POWER (MWT).. 1930 b
\\
NAMEPLATE RATING (GROSS MWE).. 650 g
DESIGN E'.ECTRICAL RATING (NET MWE).. 650 M A>'IMUM DEPEND ADLE ' C AP ACITY(GROSS tiWE ).. 650 MAXIMUN DEPENDADLE CAPACITY (NET MWE).. 620 IF CHANGES OCCUR IN CAPACITY RATING SINCE LAST REPORT, GIVE REASON...
NONE POWER LEVEL TO WHICH RESTRICTED, IF ANY ( NET tiWE )... NO RESTRICTION REASON FOR RESTRICTION, IF ANY...
NO RESTRICTION MONTH YEAR CUMULATIVE HOURS IN PERIOD 744.0 8760.0 79104.0 HOURS 4X CRITICAL 510.9 6616.3 61021.1 RX RESERVE SHUTDOWN HRS.
0.0 0.0 468.2 HRS. GEN ON LINE 441.0 6510.0 59 ~l81. 3 UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERnAL ENERGY 768264.1.
11045457.7 100035995.0 GROSS ELEC ENERGY 260490.0 3782670.0 34140005.0 NET ELEC ENERGY 249559.0 3645682,0 32917790.0 UT SERVICE FACTOR 59.3 74.3 75.6 UT AVAILABILITY FACTOR 59.3 74.3 75.6 UT CAPACITY FACTOR MDC 5 #.
1 67.1 69.0 UT CAPACITY FACTOR DER 51.6 64.0 64.0 FORCED OUTAGE FACTOR 21.7 3.6 5.4 NO OUTAGE IS JCHEDULED OVER THE NEXT SIX MONTHS
I 50-219 UNIT SilUIDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME OC #1 DATE December 15, 1978 REPORT MONTil December 1978 COMPLETED BY C. M. McC1ain TELEPil0NE 455-8748 "i
e E"o ei 3 :n Cause & Corrective
.=2._,
., s X Licensee 5%
c 8-No.
Date g
gg g
_g g 5 Event u '?
j'3 Action to Report "
M
$5 5
j6g Prevent Recurrence C
8 780915 5
178.6 C
1 NA ZZ ZZZZZZ Refueling /Haintenance Outage 9
781213 F
122.4 B
3 NA CC INSTRU HSIV closed while performing a surveillance test on steam line flow sensors.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain)
- 1. Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File INUREG-D Regulatory Restriction 4-O:her ( Explain) 0161)
E-Operator Training & License 82.xamination F-Administrative 5
G-Operational Error (Explain)
Exhibit I-Same Source 19/77)
Il-Other (E xplain)
OPERATIONS
SUMMARY
- DECEMBER 1978 Refueling outage activities were completed on December 5,1978, and a reactor startup commenced.
On December 7, while continuing startup, the reactor was manually scrammed as reactor water conductivity approached 10 pmho. The conductivity increase was attributed to resin fines in the reactor from refueling activities and replacement of all seven (7) condensate demineralizer beds.
The reactor was again brought critical on December 7, 1978.
The turbine generator was placed in service on December 8,1978.
On December 13, 1978, while performing a routine surveillance test on steam line low pressure sensors, the main steam isolation valves closed and a reactor scram occurred.
During startup of the reactor at peak xenon conditions, a reactor scram occurred in IRM Range 1 (RO#78-33).
The unit remained shut down and a drywell entry was made to repair two (2) leaking electromatic relief valves.
The unit was returned to service on December 18, 1978, and remains in operation at the end of the report period.
Five (5) reportable occurrences were identified during the report period:
R0 #78-32 occurred on December 4 when containment spray valve V 18 failed to open during rou+.ine surveillance testing.
R0 #78-33 occurred on December 14 when a 2.8 second period resulted
, from control rod withdrawal during reactor'startup.
R0 #78-34 was identified on December 13 and involves an omitted weekly surveillance of the diesel generator and station batteries.
R0 #78-35 occurred on December 22 when tne torus water temperature exceeded the Technical Specification normal high limit.
R0 #78-36 occurred on December 12 when standby gas treatment system valve V-28-30 failed during routine surveillance testing.
CORRIETIVE MirilANICAL MAINTF1WJCE ON GASL 11U1S FOR TilB MOtIPII OF DICEMBER 1978 I'lut 10GI1Y4FNP MALFUNCTION CORREUPIVE ACTION 1
CIO V-111 Valves Valves 30-19, 70-11, 38-31, 10-27 Rebuilt and replaced valves 22-43 require replacanent 2
Fire Water Sprinkler Pipe Irak located over #1 sump Repaired leak Systen #2 3
- 1--l Fire Diesel Flex line on cooling water dis-Replacal with a new one charge line leaking 4
"A" Shutriown cooling punp V-17-1 is leaking Aljust packirr3 to stop leaking suction valve S
- 2 Fire Diesel Unit rpn varies bett.een 1675-Replaced fuel oil filters and 1700 rpn adjust throttle linkage 6
- 2 Fire Diesel Ptunp Very noisy during surveillance Aljusted and tightened throttle test operation linkage for satisfactory operation 7
Vacutnu Breakers on Down-Check valve on the north down-Installed valve to the correct caner pipe for C&D M4HV's caner is installul wrong position 8
Cleanup Systen Pre-strainer needs cleaning Ranoved; cleaned; and re-installed strainer 9
CRD Acetin. 26-47 arxl 26-23 V-lll Iraking Replaced valves with rebuilt spares 10 CRD Module 22-19 Scrbm inlet valve Icaking Installed ncs inlet seat and gasket Installed new V-lll valve 11 CRD 46-23 Scram inlet valve leaks Installed new teflon seat 32 Overixurd discharge line Ground caval in at southside Dug hole along side pad, repaired of exhaust fan pad discharge line elbow leak, and rein-forced entire area with concrete 13 FMRV's A&E FMRV's leaking Ibth valves runoved, disassenbled lapped and reassenbled. Prior to installing, leak check performed at 1000 psi
~
CORillCTJVE MII'llAtlICAL MAItT11NAtK'E G1 OASI, ITIM3 FOR Tile tOffril OF DIELMBEll 1978 I'11M FUJIIMINr MALIUCrlOfJ CORRELTIVE ACTIOtJ 14 Cleanup Systen IXsnin. pre--strainer needs Iteplaced strainer with.new one replacity 15 Scram Air ifeader - 23' El.
Dirty air filters IMplaced with new air filters
CORRICTIVE ILIrrRICAL FM1flfl24ANCE Of1 OASL ITH4S 1OR TIIE MOffrl! OF DICINBER 1978 ITIN IOUliNfWP MALMJBUTION CORRIrfIVE ACTION 1
"A" 1NRV Valve failure Inspected, checked resistance and stroked valve 2
Standby gas treatment sys.
Routine inspection of valves Replaced all plunjers
- 1 & 2 solenoid valves 3
Cleanup Systen 6K22B Relay Relay failure Aljusted slider retaininj clip 4
V-20-27 Keyswitch Inose internals Tightened mounting nut 5
IX'r-1 & II FIG /SC Relays fJo generator voltage buildup Ranoved OOS mechanical targets frun on DG-1 due to januni relay FFCO and 111 relays in DG #1 & 2 6
V-1-106 Valve failure during surveillance Repaired loose connection at fuse
~
test block 7
SJAH valves Faulty valve inlicators Repaired aml adjusted limit switju3s 8
V-16-61 Inlicator Faulty valve imiicator Aljusted limit switch 9
24 VIX' Systen False alarm indications Clean alann contacts 10 V-1-llt Isolation Relay 6K32 Noisy operation replaced relay 11
- 2 Diesel Generator Tripped 0 700 IM on shutdown Changed rack settinJ to trip at 400 KW 12 "C" Recire. Pump Bypass Breaker vibrates Replaced RF-1, cleaned RF-2, and Valve monitor relay 13 1-1 Fire Diesel Punp Investigate starter operation Clean carmutator & brush holder, lube pinion gear & shaft. Verify operation.
WRIUCI'IVE FIJCIRICAL fMIN1'l1WCE Ot1 (MSL ITIMS 1u'l 'IllE FOffril OF DICH4BER 1978
- 11M, IJJUIINF2ff MATEUtCPIOt1 WRRICTIVE ACTION 14 1-1 Fire Diesel limp Icose voltage regulator, Inttery Roaount voltage reg, clean batteries corrosion, missing caps
& termirnis, replace missirx3 caps 15 D.G. #1 Failure to pickup deadload Replace governor actuator and adjust per manual JS 1%er Ikxl in Switch IIandle overtravels 5, opening Replaced stop plate
- .. witch contacts 17 SGIS #1 V-28-24 Double indication when valve is Adjust limit switch closed 38 V-17-54 Broken control switch Repaired with orignal parts 19 D.G. #1 Failo:1 in start on Ioss of Replaced goverror Ibwer Test
CORRIrrlVE IfLSTRUMEtIP MAIfffIl WJCE Of1 QASL ITI51S IG '11[E MorfIll OF DEC15tB121978 l'11N IUJIINIIIP MAIFUNCTION CORREUPIVE PCPION 1
IIN Channel 36 Inoperative Installed new drive cable 2
Core Spray Sys (IOc Prot.
Broken Valve Peplaced with new valve System) RE-17A 3
APIN Bypass Switch Switch failed in APIN #2 bypass Fixed switch pin lever and replaced position switch assemblies for all channels 4
M3L T/C near V-1-34 Ibnt and nroken Ibplaced 5
"A" Isolation Condenser Ievel Inst. out of calib.
Calibrated and checked 6
MSI, Ili. ' lung Sensor IB]OA Broken Ibplace, calibrate & perform surv.
test 7
f1SL Break Sensor LK15 Faulty relay Jumpered and proved faulty see J.O.
13331 (above) 8 MSL Rad Monitors IWO6-C Faulty detector Ibplaced and calibrated 9
'Ibrus Ievel Recorder Not responding Ibplaced fuse and calibrated 10 APIN Channel I Failed downscale due to Ibplaced diode and perfornul defective diode surveillance proc. #721.3.001 11 Iter. Cond. IN Disch.
Faulty indicators due to Cleaned switch and terq). recorder dirty stelping switch and checked wiring loose wires 12 RX Ibeirc Winding 'Ibnp Erratic readings from rdD Junper #105 lbc.arder I'r 10 (E recire pmp) 13 SIN Chan 21 Ibfective dual trip unit Ibplaced and checked setpoints 14 INent Ibcorder Pens not tracing Tighten all connections
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - DECEMBER 1978 Name of facility:
Oyster Creek Station #1 Scheduled date for next refueling shutdown:
September 15, 1979 Scheduled date for restart following refueling:
November 10, 1979 Will refueling or resumption of operation thereafter 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 nroposed licensing action and supporting info rmat ion:
No submittal is scheduled.
Important licensing considerations associated with refualing, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
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 - 620 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:
1,800 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
The Fall 1986 Outage.