ML17250A326
| ML17250A326 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 06/09/1980 |
| From: | Mcnamara A ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250A325 | List: |
| References | |
| NUDOCS 8006160038 | |
| Download: ML17250A326 (10) | |
Text
OPERATKG STATUS OPERATING DATA REPORT DOCKET NO.
June 9
1980 COMPLETED BY Andrew E.
McNam ra TEI.EPHONF 1
315 524-4446 Ext.
293
- 1. Unit Name:
GINNA STATION UN 1
0 p.,.pi,
- May, 980 3 ~ Licensed Thermal Power (hlWc):
- 4. Namcplatc Rating (Gross MWc):
S. Design I'.lectrical Rating (Net hlWc):
470
- 6. Maximum Dependable Capacity (Gross hlWe):
- 7. hlaximum Dependable Capacity (Nec hlWc):
490 Notes Refueling and Mainten-ance Shutdown ended 5/23/80.
Reactor Power Level was increased to 100%
on 5/27 and remained there until the end of the Period.
- 8. IfChanges Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level to Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, lfAny:
This hlonth Yr"ro-Da ce Cumulative 2 1
- 11. 1lours In Reporting Period 744
- 12. Number of Hours Reactor Was Critical 231.5
- 13. Reactor Reserve Shutdown Hours 0
- 14. Ilours Gcncrator On.Line 192.75
- 15. Unit Rescrvc Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (hlWH)
- 17. Gross Electrical Energy Generated (hfWH) 77 530
- 18. Nec Electrical Energy Gencraccd {hlWH)
- 19. Unit Service Faccor 25.91%
- 20. Unit Availabilicy Factor 25.90%
- 22. Unit Capacity Factor (Using DER Net) 20.92%
- 23. Unit Forced Outage Rate 2{. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
Scheduled
<< Steam Generator Ins ection and Modifications-2 346.25 2 307.25 3 357 600 1 043 963 63.26%
63.26%
60.9%
70 026.02 1 621.57
- 68 263.88 8.5 91 633 402 2
8 2
28 205 511 74.07%
74.08%
6 6'7.46%
9.61%
10/24 thru 11 23.
2S. If Shut Down At End Of Report.Period, Escimated Date of Startup:
- 26. Units In Test Stacus (Prior to Commercial Operation):
INITIALCRITICALITY INITIALELECTRICITY COhlhIERCIAL OPERATION
>> Cumulative total commincing January 1,
1975 Forecast Achieved
n A
AVERAGE DAILYUNIT PO'HER UNIT MONTH Ma 1980 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)
DOCKET NO.
50 244 UNIT Nl @irma Statio DATE June 9
1980 COMPLETED BY Andrew E. McNamara TELEPHON E 1-315 524-44 s6 Ext.
293 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1 2
ll 18 10 11 12 13 14 15 16 20 21-22 23 24 25 26 27 28 29 30 31 75 273 449 483 484 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to thc nearest whole megawatt.
40 ~ 87 IAKY I/le)
sy
DOCKET NO.
UNITNAME UNIT SHUTDOWN AND POWER REDUCTIONS COhIPLE11 D IIY 1'I'. LE PI IONI'.
50-244 Andrew E. McNa a
1 31 2-6 Ext.
293 No.
Dote 0
0 0 c0 Pl ol >>0 c 0 0
0 0
tx,'wnc E
0 Cl Licensee Event Report JI Ew 0
0 vl 00 Vl co ul c
0 0
E 0
EJ Cause L Corrective Act>on to Prevent Recurrence 5/23/80l'r S
1s339 ~ 7 C
+ Annual Refueling and Maintenance Shutdown which began on 3/29/80, ended on 5/23/80.
F: Forced S:
Schcdulcd 49 SQ tRCVo t/70)
Reason:
A.Equipmcnt Failure (Explain)
II-htaintenancc or Test C-Refueling D-Regulatory Restriction E-Operator Training 8: License Examination F-Administrative G-Operational Error (Explain)
II-Other (Explain) 3 hlcthod:
I-hie nua I 2-hlanual Scram.
3-Automatic Scram.
4-Other (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Rcport (LER) I'ilc (NUREG-0161)
Exhibit I - Same Source
4 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO.
0-2 UNiT Ginna Station Unit 81 DATE June 9
1980 COMPLETED BY Andrew E. McNamar MONTH May, 1980 TELEPHONE 1 (315) 524"4446 Ext.
293 The Annual Refueling and Maintenance Shutdown ended on 5/23/80 6 2315.
The Reactor Power Level was maintained atw25% until the Turbine Overspeed Trip Test was performed on 5/24.
The Reactor Power Level was increased to the 100% level by 5/27 and remained there until the end of the Period.
GINNA STATION MAINTENANCE REPORT FOR APRIL AND MAY, 1980 During the month of April and May the Unit was in its annual refueling and maintenance shutdown.
The required testing, inspections and maintenance were completed, including the designated preventive maintenance program.
Some of the major safety related maintenance included:
l.
Inspection of the 1B RCP motor and seals.
2.
Technical Specification required snubber testing and inspection program.
3.
Annual inspection of both emergency diesel generator units.
4.
Cleaning and inspection and multiamp testing of 3 of the safeguard busses.
5.
Replacement of the leaking mechanical seal on the IA RHR pump.
6.
Replacement of the boric acid flow control valve.
7.
Replacement of the 1A charging pump drain valve.
8.
Replacement of the Regenerative heat exchanger drain valve.
9.
Inspection of the SI pump suction valves.
10.
Replacement of the plug and seat on the 1B Steam Generator Blowdown Valve.
ll.
Inspection of boric acid transfer pumps.
12.
Replaced the batch circuit board on the pressurizer pressure controller.
13.
Replaced one intermediate range and one source range detector on the nuclear instrumentation system.
)
'J