ML17262A313
| ML17262A313 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/31/1990 |
| From: | Dodge R, Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9101230218 | |
| Download: ML17262A313 (11) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9101230218 DOC.DATE: &07T27$X NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION DODGE,R.E.
Rochester Gas
& Electric Corp.
MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000244
SUBJECT:
Monthly oper in for Dec 1990 for RE Ginna Nuclear Power Plant W/910117 tr.
DISTRIBUTION CODE IE OPIES RECEIVED LTR ENCL SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DOA IRM TECH ADV NRR/DOEA/OEAB RGN1 EXTERNAL: EG&G BRYCE,J.H NSIC COPIES LTTR ENCL 3
3 1
1 1
1 2
2 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DSP/TPAB
~DLP~LPEB10 REG FILE 01 NRC PDR COPIES LTTR ENCL 1
1 1
1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,
'OOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL 16
~zan r rrrrrrrIIIf rrrrrrr ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER N.Y. 14649.0001 ROBERT C. MECREDY Vice Ptetident Cinna Nudeat Production TELEPHONE AREACODE7te 546-2700 GXNNA STATION January 17, 1991 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Monthly, Report for December, 1990 Operating Status Xnformation R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Sir:
Pursuant to our Technical Specification 6.9.1, attached herewith is the monthly operating status report for Ginna Station for the month of December, 1990.
Very truly yours, Robert C.
Me red, RCM/eeh Attachments cc:
Mr. Thomas T. Martin NRC (1) 9iOi2302ie 90i23i PDR ADOCK 05000244 R
PDR z(p)
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OPERATING STATUS OPERATING DATA REPORT DOCKET NO.
50.244 DATE Ja ar 17 1991 COMPLETED BY Robert E. Dodge TELEPHONE 315 524.4446 ext. 396 1 ~
2.'.
4.
5.
6.
7.
8.
Unit Name:
R.E.
GINNA NUCLEAR POWER PLANT Reporting Period:
December 1990 Licensed Thermal Power (MWt):
Nameplate Rating (Gross HWe):
Design Electrical Rating (Net HWe):
Maximm Dependable Capacity (Gross HWe):
Maximus Dependable Capacity (Net MWe):
tf Changes Occur in Capacity Ratings (Items Notes:
The unit operated at " 97K power level except for the events detailed on page 4
of this report.
1520 490 470 490 470 Nunber 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level to Which Restricted, If Any (Net HWe):
10.
Reasons For Restrictions, If Any:
This Honth Yr.-to-Date Cwuiative 11.
12 ~
13.
14.
15.
16.
17.
18.
19.
20.
21.
22
'3
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Hours In Report Period Nunber of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On. Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWN)
Gross Electrical Energy Generated (MWH)
Net Electrical Energy Generated (HWH)
Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net)
Unit Capacity Factor (Using DER Het)
Unit Forced Outage Rate 744 527.36 500.25 715 030 242 826 230 708 67.24 67.24 65.98 65.98 32.76 8 760 7 393.17 7 327 10 728 247 3 629 129 3 451 380 83.64 83.64 83.83 83.83 4.58 185 346.45 145 739.31 1 687.55 143 168.38 8.5 202 350 697 66 662 474 63 269 293 77.41 77.42 74.07 74.07 6.33 24.
Shutdowns Scheduled Over Next 6 Honths (Type, Date and Duration of Each):
Annual Refuel in and Maintenance Shutdown:
March 15 1991 38 da 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
26.
Units In Test Status (Prior to Carmercial Operation):
Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- CUHULATIVE TOTAL COMMENCING JANUARY 1, 1975
c' 4
II
o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-244 UNIT R.E.
Ginna Nuclear Power Plant DATE Janu 17 1991 COMPLETED BY Robert E.
Dodge TELEPHONE 1
315 524-4446 ext.
396 MONTH December 1990 DAY AVERAGE DAXLY POWER LEVEL (MWe-Net) 476 DAY AVERAGE DAXLY POWER LEVEL (MWe-Net) 17 ~
2 ~
475 18.
-12 3
~
476 19.
-12 4 ~
476 20.
5.
476 21.
6.
477 22.
219 7 ~
477 23'74 8.
476 24.
475 9.
476 25.
475 10.
477 26.
475 299 27.
475 12.
-12 28.
475 13.
-12 29.
476 14.
-12 30.
476 15.
-12 31.
475 16.
-12 INSTRUCTXONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
l)O(:KI".I'O.
~0 244 UNITNAMl'.E INNA NUCLEAR POWER'LANT UNIT SHUTDOWN AND POWER REDUCTIONS
(:OhfPLI'.l I'.D !3Y REPORT hfONTH TEI.I:pllONI: (315) 524-4446 ext.396 No.
Date P4 c0 OO IY cn>>0 c v o>>
o own c 0O Licensee Event Report ff Em O
vl u0 tA c0 LCl 0c Q
l70 Cause L Corrective Action to Prevent Recurrence 90-07 12-11-90 F
210.38 LER-90-013 Design deficiency in Foxboro AMSAC Control Module.
Installed jumper to correct design deficiency.
90-08 90-09 12-20-90 12-21-90 F
33.12 A
LER-90-018 LER-90-019 Degraded Thyristor Capacitors Feeding Rods Stationary,
- rmvable, and liftcoil.
Replaced the degraded capacitors.
Rx tripped from low power
(
20%)
due to automatic trip of MEW Pump and resulting 3iow SG level.
This was due to inappropriate condensate system alignment.
1 F: Forced S:
Scheduled REV. 4IBS 4949 Reason:
A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction Eperator Training &: License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain) hfethod:
1-Manual 2-hfanual Scram.
3-Automatic Scram.
4-Other (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)
Exhibit 1 - Same Source
4
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1 D
NARRATXVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO.
50-244 UNIT R.E.
Ginna Nuclear Power Plant DATE Januar 7
1991 COMPLETED BY Robert E.
Dodg TELEPHONE 1
315 524-4446 ext.
396 MONTH December 1990 The unit operated at.
974 reactor power level except for the following events:
On December 11, 1990 at 1517 EST a reactor trip occurred during logic system testing.
The ATWS Mitigation System Actuation Circuitry (AMSAC).
Installed jumper to correct design deficiency in Foxboro AMSAC control module.
On December 20, 1990 at 1323 EST a turbine runback occurred due to a dropped control rod.
Control Room operators manually tripped the turbine to prevent reverse power to the generator.,
The underlying cause of the event is believed to be degraded Thyristor Capacitors feeding the affected rods stationary,
- movable, and liftcoil.
Corrective action was to replace the degraded capacitors of the affected rod.
On December 21, mately 164 with reactor tripped pump.
This was alignment.
1990 at 1234 EST, with reactor power at approxi-preparation in progress for turbine roll, the on Lo Lo SG level due to the loss of the MFW caused by inappropriate condensate system
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