ML19261B423

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Monthly Operating Rept for Jan 1979
ML19261B423
Person / Time
Site: Oyster Creek
Issue date: 02/14/1979
From: Mcclain C
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19261B422 List:
References
NUDOCS 7902230107
Download: ML19261B423 (8)


Text

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, AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-219 UNIT Oyster Creek #1 DATE February 14, 1979 COMPLETED BY C. M. McClain TELEPHONE 201-455-8748 MONTil January 1979 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net )

643 37 0 2 644 18 0 3 641 237 39 4 636 20 576 5 630 21 638 6 622 22 646 7 637 23 648 ,

8 636 24 649 9 637 25 649 10 635 26 649 II 635 27 649 12 633 33 650 13 609 79 648 i4 627 3g 650 15 411 649 3

16 0 INSTRUCTIONS On this format,hst the average daily unit power leselin MWe-Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

cit 771 7902230(07

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OPERATING DATA REPORT DOCKE'd NO. 50-219 DATE February 14, 1979 COMPLETED BY C. M. McClain TELEPHO.g 301-455-8748 OPERATING STATUS Oyster Creek #1 Notes

1. Unit Name:
2. Reporting Period: January 1979
3. Licensed Thermal Power (MWt): 19'40
4. Nameplate Rating (Gross MWe): 650
5. Design Electrical Rating (Net MWe): 650
6. Maximum Dependable Capacity (Gross MWe): 650
7. Maximum Dependable Capacity (Net MWe): 620
d. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gi e Reasons:

None

9. Power Level To Which Restricted,If Any (Net MWe): No restrietion.
10. Reasons Fcr Restrictions. If Any: No restriction.

This Month Yr..to-Date Cumulative

11. Hours in Reporting Penod 744.0 744.0 79848.0
12. Number Of Hours Reactor Was Critical 670.I 670.1 61691.2
13. Reactor Reserve Shutdown Hours 0.0 0.0 468.2
14. Hours Generator On-Line 657.9 657.9 60439.2
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1200706.5 1240706.5 101276701.5
17. Gross Electrical Energy Generated (MWH) 428590.0 __

428590.0 34568595.0

18. Net Electrical Energy Generated (MWH) 412760.0 412760.0 33330550.0
19. Unit Senice Factor 88.4 88.4 75.7
20. Unit Availability Factor 88.4 88.4 75.7
21. Unit Capacity Factor (Using MDC Net) 89.5 89.5 69.2
22. Unit Capacity Factor (Using DER Net) 85.4 85.4 64.2
23. Unit Forced Outage Rate 11.6 11.6 5.4
24. Shutdowns Scheduled Over Next 6 Months (Type. Date and Duration of Eacht:

No outage is scheduled over the next six months.

25. If Shut Down At Enc' Of Report Period. Estimated Date of Startur
26. Units in Test Statu. , 'rior to Commercial Operationi: Forecast Achiesed INili A L CRITICALITY INITI AL ELECTRICITY COMM ERCI A L OPER ATION Nr;i

t UNIT SilUIDOWNS A'<D POWER REDUCTIONS DOCKET NO. 50-219

' UNIT NAM E 0_yster Creek #1 DATE Fehronrv 14. 1979 REPORT MONTil January 1979 COMPLETED BY C. H. M2:Clain TELEPilONE 201-4558748

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[2 E 5 j di - Report e r$ C U Prevent Recurrence 6

79-01 011579 F 86.1 G 3 NA NA NA While valving in the clean-up system, a water harnmer occurred setting off sensors.

I 2 3 4 T Forted Reason : Method: Exhibit G - Instructions S S< hed uled A-Equipment Failure (Explain) 1 -Man ual for Preparation of Data ll Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event ReporI (LERI Fde INUREG-D-Regulatory Restriction 4-Ot her ( E xplain) 0161)

E-Operator Training & License Examination F-Administratise 5 G-Operational I. ror (Explain) Exhibit i . Same Source 19/77) Il-Other (E xplain)

OPERATIONS

SUMMARY

- JANUARY 1979 The unit remained in operation at near full power at the start of this report period. On January 5, load was reduced to 600 MWe to cycle the "E" electromatic relief valve. This operation was successful in eliminating leakage into the torus. On January 12, load was reduced to 600 MWe to isolate, sequentially, each high pressure feedwater heater to locate a suspected tube leak. This operation was inconclusive.

On January 15, while attempting to return the cleanup system to service, a reactor scram occurred as a result of cleanup system pipe vibration transmitted to instrument rack RK02. The vibration tripped two (2) reactor high pressure sensors, causing a scram. The unit remained shutdown until January 18 to repa!r leaking tubes in 1C3 high pressure feedwater heater. Additional maintenance work was performed during the shutdown.

At the end of the report period, the unit remained in operation at 100% power.

One (1) reportable occurrence occurred during the report period:

RO #79-1 occurred on January 18 when isolation condenser valve V-14-35 failed to open during a routine surveillance test.

CORRECTIVE ELECTRICAL MTIlffENANCE Ot1 OASL ITH4S FOR Ti!E FDNfil OF JANUARY 1979 Item Equipnent Fhlfunction ' Corrective Action 1 Diesel Gen. #2 Hunting problem Replaced RSV relay and tested 2 Fire Diesel Pump #1 Faulty battery Replaa d 12V battery 3 Rx Bldg 23' IM Airlock Problans with interlock Lubricated plunger 4 FSR-A Relay (Dies. Gen) Faulty relay Replaced relay 5 CR120 Relays (Panel llR) Potential fire hazard Replaced plastic contact retainer (IE Bulletin) in relays 6 CR120 Relays (Panel 4F) Potential Fire Hazard Replaced plastic contact retainer (IE Bulletin) in relays 7 Ikcirc. MG Sets Check and rebrush if Rebrushed 'D' & 'A' Generator necessary 8 CTC 20 Relays (Panel 10F) Potential fire hazard Replaced plastic contact retainer (IE Bulletin) in relays 9 V-28-15, V-28-16 leaking air Rebuilt V-28-15 & V-28-16 solenoids 10 V-14-35 Failed to open during Cleaned contacts on opening torque surveillance switch 11 DG-1 and DG-II Check battery box heater Replaced all eight thermostats thentostats 12 24 Volt Sys Off Normal Alarm Intermittent alarm Checked 24 volt sys & cleara3 alarm 13 Fire Diesel #2 Delayed starting due to Repaired, replaced and tested new a faulty solenoid

CORRIrrIVE INSTRUfMATIO1 MAINTENANCE ON GASL I' IDS FOR 'IIIE MONITI OF JANUARY 1979 Item Equi [mant Malfunction Corrective Action 1 Reactor Vessel 'Ibnp Recorder Broken string Replaced string 2 Stack Gas Sample Sys Iow Flow Switch Switch will not reset Replaced with two new vacuum switches (alarm) 3 B Stack Gas bbnitor Erratic Operation Replaced two capacitors on amplifier board and corrected interference on recorder 4 Waste Sample Tank level Indication Level discrepancy between Icose slidewire in recorder was (high purity) new & old radwaste control repaired and then calibrated for room both A & B 5 Shutdown and fuel pool temp recorder Recorder not printing Repaired open input wire to recorder 6 Solids Packagings-IIold up tanks Faulty level indication Installed new transducers for (new radwaste) inventron with a flush option 7 APRM 1 Failed during LPRM Replaced defective flux amplifier amplifier calibration 8 CRD 46-23 Scram Pilot Solenoid Valve Icaky valves Replaced both scram pilot valves 9 CRD Cooling Water Pressure Transmitter Inoperative Replaced cam and coil 10 Environs bbnitor Recorder Not working properly Selected spare cables and returned to service 11 APRM Channel 1 Iligh scram function Replaced defective dual trip unit inoperable 12 Offgas Monitor Recorder and gauge differ Perfonned calibration on nonitor and recorder 13 CR-120 Relays (Panel llF) Requested replacement Replaced plastic contact retainer in relays

00RRICTIVE MEEIIANICM. bnI!71T2WJCE OF QASL ITEMS FOR THE MCtml OF JANUARY 1979 -

Item # Equip ant bblfunction Corrective Action 1 1-2 Fire Diesel loosing coolant when running Replaced radiator caps on 1-1 and 1-2 fire diesels 3 FIX7PA connection New radwaste return to sample Installed new 1 1/2" valve to h"IrB tank; valve frozen and broken 4 Condensate demin. Outboard seal leaking and Cleaned drains and adjusted packing drain line is plugged S "B" Liquid Poison Pump Stuffing box floodcx3 Repacked pump 6 Cleanup System Root valve for Pl-lJ01 Replaced bonnet has a packing leak 7 "B" Fuel Pool Pump Outboard seal leaking Replaced shaft, mechanical seals and bearings 8 "B" Stack Sample Pump Unable to maintain oil level Feplaced gasket on oil sight glass 9 1-1 air ccmpressor Suction valves and unloaders Cleaned and lapped HP & LP unloaders and nvilfunctioning suction valves

Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - JANUARY 1979 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.

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

1. July 19, 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 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.