ML19253B825
| ML19253B825 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/15/1979 |
| From: | Mcclain C JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19253B820 | List: |
| References | |
| NUDOCS 7910220286 | |
| Download: ML19253B825 (8) | |
Text
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AVERAGE DAILY POWER LEVEL DOCKET 4......
50-219 UNIT..........
O. C.
?i REPORT DATE... October 15, 1979 COMPILED BY...
C.M. MCCLAIN TELEPHONE..... 201-455-8748 MONTH September 1979 DAY MW DAY MW i.
607.
17.
356.
2.
604.
18.
9.
3.
612.
19.
354.
4.
614.
20.
574.
5.
615.
21.
613.
6.
614.
22.
626.
7.
621.
23.
636.
8.
620.
24.
618.
9.
626.
25.
616.
10.
628.
26.
631.
11.
547.
27.
638.
12.
518.
28.
638.
13.
619.
29.
634.
14.
545.
30.
633.
15.
594.
16.
628.
1150 126 7 91022 0 ZE65
OPERATING DATA REPORT OPERATING STATUS UNIT NAME.. 0YSTER CREEK DOCKET NUMBER.. 50-219 UTILITY DATA PREPARED BY...C.M.
MCCLAIN 201-435-8748 REPORTING PERIOD... September 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(NET MWE)... NO RESTRICTION REASON FOR RESTRICTION, IF ANY...
NO RESTRICTION MONTH YEAR CUMULATIVE HOURS IN PERIOD 720.0 6551.0 85655.0 HOURS RX CRITICAL 697.0 5446.0 66467.1 RX RESERVE SHUTDOWN HRS.
0.0 0.0 468.2 HRS. GEN ON LINE 688.4 5372.1 65153.4 UT RESERVE SHUTDOWN HRS 0.0 0.0 0.0 GROSS THERMAL ENERGY 1265658.4 9966888.7 110002883.7 GROSS ELEC ENERGY 428090.0 3405870.0 37545875.0 NET ELEC ENERGY 412415.0 3276286.0 36194076.0 UT SERVICE FACTOR 95.6 82.s 76.1 UT AVAILABILITY FACTOR 95.6 82.0 76.1 UT CAPACITY FACTOR MDC 92.4 80.7 69.9 UT CAPACITY FACTOR DER 88.4 76.9 65.0 FORCED OUTAGE FACTOR 4.4 18.0 6.6 THE NEXT SCHEDULED OUTAGE IS TO BEGIN ON JANUARY 5, 1980
}7
50-219 UNIT SilUTDOWNS AND POWER REDUC 110NS DOCKET NO.
UNIT NAME Oyster Creek #1,
DATE October 15, 1979 REPORT MONTII September 1979 COMPLETED BY C. M. McC1ain TELEPilONE 20I-455-8748 e.
.! E 3
.E Licensee 5%
t, Cause & Corrective No.
Date g
g sj
,, g 5 Event u? [l a
Action to H
$E jgg Report #
(NU u
Prevent Recurrence S
7 091779 F
31.6 H
3 NA lA NA The scram occurred when a worker struck a cable tray attached to reactor protection instrument rack RK01 causing a spurious high pressure trip.
l 2
3 4
~
F: Forced Reason:
Method:
Exhibit G - Instructions W
S: Scheduled A Equipment Failure (Explain) 1-Manual for Pteperation of Data O
B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-01her (Explain) 0161)
N E-Operator Training & Ucense Examination CD F-Administrative 5
G-Operational Errer (Explain)
Exhibit 1 Same Source (9/77)
Il-Other (Explain)
Oyster Creek Station #1 Docket No. 50-219 Operatims Sanry - 92ptc_ car 1979 At the beginaing of the reporting pcriod the unit was operating at near ratcd output. Tne plant output was limited at tines during the first three days of the r.onth by the EnvironT. ental Technical Specification limiting condenser discharge teg. erature. On September.11, 1979 plant output was reduced to 175 Xe to reduce radiation levels in the steam tunnel..hile repairing two leaking fce bater check valve hinge pins.
On Septerbar 14, 1979 plant output was reduced to reduce radiation levels in the drain tank pit while replacing neber two auxilliarf flash tank pcrp rotor. At 1:37 PM on September 17, 1979 a Beactor Scram occurred when a worker struck a cable tray attached to reactor protection sys azn instrumnt rack RM01 causing a spurious reactor high pressure trip.
Feactor startup cmnenced on Septe:rbar 18, 1979 following replacerent of reactor recirculation p'mp M-G set exciter brushes and repair of a leaking condensate transfer line.
Three events were mportel during the nonth.
Non-routin? Environnental Operating Report #79-5 occurred on September 5,1979 when the plant was operated for 26 ninutes with greater than 87 F discharge bridge teg. erature and only one dilution pump operating.
Reportable Occurrence #79-32 occurred on September 14, 1979 when Con' m Tent spray System II was renoved from service to repair leaking heat exchanger relief valve piping.
Reportable Occurrence #79-33 occurred on September 17, 1979 when the pressure switch for "A" Electrcratic Relief valve was found to be inoperable during a routine surveillance test.
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e e
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Oyster Creek Station #1 Docket No. 50-219 CORRDCTIVE MlIHANICAL MAINTENVCE ON QASL ITEMS FOR ' HIE MONTII OF SEPTEMEER 1979 Item #
Equipment Malfunction Corrective Action 1
CRD 02-31 V-lll Valve Icaks Replaced with rebuilt spare 2
1-1 Fire Diesel Coolant dripping from lower Replaced hose heater hose 3
Feedwater Systan Check Valves Hinge pin plug leaking - south Used rurmanite process to stop V-2-72, V-2-71 pin on V-2-71 and north pin on both leaks V-2-72 4
"B" CRD Filter Dirty Installed clean filter 5
CRD 06-43 Scram inlet valve leaking Rebuilt valve 6
CRD 46-39 Scram inlet valve leaking Replaced with rebuilt spare
~
7 CRD 02-19 V-ill valve leaks Replaced with rebuilt spare' 8
Containment Spray Systan II Iratrument piping taps leaking Replaced nipples with stainless steal Heat exchangers 9
Containment spray Systen I Instrument piping taps leaking Replaced nipples with stainless stcol IIeat Exchangers 10 Containnent Spray Systen II Relief valve nipples leaking Replaced nipples with stainless steel Heat exchangers M
O mo b O
Oyster Creek Station #1 Docket No. 50-219 CORRECTIVE ELDCTRICAL MAINIDWCE CN QASL ITEMS FOR Tile FONITI OF SEPT.1979 Item #
Equignant Fulfunction Corrective Action 1
Rx Bldg. Vent Syst.
'Ibrus No position indication Readjusted switch actuator Vent Valve V-28-18 (panel llF) 2 Annunc. Syst. " Scram Contactor Receiving erroneous alarm Replaced aux contacts on lK21A Open" Alarm 3
Ibtary Inverter Brushes worn (noted during Changed brushes routine inspection) 4 Rx Prot. Syst. MG Set 1-2 During surv. testing UV coil in Installed new breaker gen output breaker opened 5
Cleanup Syst. "B" filter Will not open Replaced solenoid on ND28B '
outlet vlv. ND-28B 4
s CD s.
- -= = - - =.
1 e * *W W e-D1 P+7 7
9*
Oyster Creek Station #1 Docket No. 50-219
~
CORRECTIVE INSTRUMENT fMINTEIWCE ON OASL ITEMS FOR TIIE MOtml OF SEPT.1979 Itan #
Equirinent Malfunction Corrective Action 1
New F(d Vent Effluent Radiation Particulate filter paper feed Replaced takeup spool &
Monitor is not driving realigned capstan asseichly 2
'Ibrus - O An lyz r Erratic indication Replaced capacitor in heater ckt.
2 3
ARM /RB Vent Isol.
Surv. discrepancies (B9 & C9)
Readjusted downscale trippoint 4
'5BM'#2'3 Failed downscale Corrected fuse placenent 5
,NDOG Rad. Mon. #1 Surv. discrepancy Mjusted hi alarm setpoint 6
Unidentified Irak Rate tLnitor Integrator reading is higher Output (zero) of respective than that calculated fran pump (s) sq. rt. converter drifted causing o
running time integrator to drive while purg>(s)
'l were off. Readjusted pg. rt. conr.
7 1-1 Fire Diesel Water tenp. gage stuck @ 110 F Replaced gage 8
ERV "A" Pressure Switch During surv. - found trippoint Replaced ERV "A" pressure switch erratic assembly 9
ARM - Mnun. Bldg. Ent, to Inoperative Replaced sensor & convertor unit Turb. Bldg.
10 ERV "A" Pressure Switch ERV "A" opened twice @ nonnal Newly installed pressure switch operating pressure setpoint drif ted into operating pressure band. Recalibrated switch.
11 Core Spray Suct. Press. Gage Gage, not supported by Installed original style pressure nounting plate gage (s) & mounted to backplate M
CD N
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - SEPTEMBER 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 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.
Scheduled date(s) for submitting proposed, licensing action and supporting information:
1.
October 1979 - Cycle independent General Electric fuel design information and safety analysis for future use.
as submittal is scheduled for the use of Exxon fuel.
Important licensing considerations associated w: b refueling, e.g., new or di f fe rent fuel design or supplier, unreviewed de ign 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 pool storage capacity and the size of any inc ase 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 IIcensed capacity:
The Spring 1987 Outage.
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