ML18142B356

Forwards Monthly Operating Status Report for Month of May, 1978

ML18142B356
Person / Time
Site:	Ginna
Issue date:	06/14/1978
From:	Lang L Rochester Gas & Electric Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18142B356 (14)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-244 REC:

NRC ORG:

LANG L S ROCHESTER GAS 8( ELEC DOCDATE: 06/14/78 DATE RCVD: 06/20/78 DQCTYPE:

LET'1FR NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

FORWARDING SUBJECT FACILITY"S MQNTI-ILY OPERATING pRE/T FOR /HE MONTH OF MAY 1978.

PLANT NAME: RE GINNA UNIT 1

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".Lu"5~ L5M4:t>all PltiLL~ LI'~III. I zziz Lal(O fla III"'Z ZirrZur>S ROCHESTER GAS AND ELECTRIC CORPORATION R 89 EAST AVENUE, ROCHESTER, N.Y. 14649 RTP TOAK 51A1E TELEPHONE AREA COOK 756 546-2700 Ginna Station June 14, 1978

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"TCn C.. Xl wc CD Director Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.

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20555

Subject:

Monthly Report for May, 1978 Operating Status Information R. E. Ginna Nuclear Power Plant Unit No. 1 Docket No. 50-244 Gentlemen:

Pursuant to our Technical Specification 6.9.1 attached herewith is the aanthly operating status report for Ginna Station for the month of May, 1978.

Very truly yours, Lee S.

Lang Superintendent LSL/fa Attachments 78i720i76 gO~

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OPERATING DATA REPORT DOCKET NO.

DATE June 9

1978 COMPLETED BY Andrew E. McNamara, Operations Aide OPERATING STATUS

1. Unit Name:

GINNA STATION

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

490

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

490 TELEPHONE 1-716-546-2700 Ext. 291-205 Notes Annual Refueling Maintenance overhaul ended 5/21/78.

A new rotor was installed in the

//2 L.P.

turbine.

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, If Any:

This Month Yr:to-Date Cumulative 2 060.72 439.67 1

.25 2,876,544 841,399 54%

54%

47%

47%

10%

12. Number of Hours Reactor Was Critical 292.22

13. Reactor Reserve Shutdown Hours 421.70

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Gcncratcd (MWH) 245 784

17. Gross Electrical Energy Generated (MWH) e

19. Unit Service Factor 28%

28%

20. Unit AvailabilityFactor 21'1.

Unit Capacity Factor (Using MDC Nct)

22. Unit Capacity Factor (Using DER Net) 0%

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):

56 099.34 1,540.76

• 54 491.63 8.5

.71,313,586 23,029,259 73%

73%

65%

65%

11%

25. If Shut Down At End Of Report.Period, Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

~

INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION Fotecast Achieved

• Cumulative Data commencing January 1,

1975 l

49 88

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AVERAGE DAILYUNIT POWER UNIT MONTH MAY, 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

DOCKET NO.. 50-244 UNIT Nl @irma Statio June 9

1978 COMPLETED BY Andrew E. McNamara, Operations A de LEPHONE 1-716-546-2700 Ext. 291-205, At Ginna DAY, AVERAGE.DAILYPOWER LEVEL (MWe-Net) 17 18 10 12 13 15 16 0

0 20 21

~

22 23 24 25 26 27 28 29 30 31 56 117 23 249 388 392 394 394 394 396 399 INSTRUCTIONS 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.

40 ~ 87 (REVe 1/78)

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DOCKET NO.

UNITNAhlI'.

UNIT SHUTDOWN AND POWER REDUCTIONS COMPLETED BY Andrew E.

REPORT MONTH 1'E LE PI IONE 50-244 Nl Ginna Station June 9

1978

McNamara, Operations Aide Ext. 291-205 at Ginna Date r0 vs 4

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0 4 &

40 4

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ICL Licensee Event Report 0

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IA 0 cA 44lIll c

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Cause g Corrective Action to Prevent Recurrence 780325 S

496*

C zz zz Annual refueling and maintenance overhaul ends 5/21/78.

New rotor installed, 82 Low Pressure Turbine.

780522 S

36.5 Turbine overspeed trip test generator short circuit test.

F:

Forced S:

Scheduled 49.99 (Rave l/7dl Reason:

A-Equipmcnt Failure (Explain) 8-hlaintcnance or Test C-Refueling D-Regulatory Restriction E-Operator Training L Liccnsc Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain) 3 hlethod:

I-hfanual 2-hlanual Scram.

3-Automatic Scram.

4-Other (Explain)

Fxhibit G -. Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)

Exhibit 1 - Same Source

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-4 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO.

0-2

//1, Ginna Station June 9, 1978 COMPLETED BY

$rW Andrew E. McNamara, Operations Aide MONTH NAY> 1978 TELEPHONE 1-716-546-2700, Ext. 291-205, at Ginna The unit remained shutdown for annual refueling and maintenance until 5/21.

A new turbine rotor was installed in the 82 low pressure turbine.

The unit was shutdown on 5/22 for a scheduled turbine overspeed trip test and a

generator short circuit test.

The Reactor Power Level varied during the Report Period to a high of 93% on 5/31.

Subsequent reports will show an increase in the gross electrical and net electrical energy figures, due to the installation of the new turbine rotor.

49 123 u/78)

I

MAINTlXANCEREPORT FOR APRIL AND MAY, 1978 During the annual refueling-maintenance outage preventive maintenance inspections and minor maintenance was performed on much of the plant's safety related equipment.

Major maintenance activities during the shutdown included the following:

Seal inspection and maintenance to the 1B reactor coolant pump.

2.

Major inspection and overhaul to the 1B charging pump drive unit.

3.

Inspection and seal replacement of all steam generator snubbers with original seals still installed.

4 ~

Replacement of seal material in all pressurizer snubber units with ethylene-propylene seals.

5.

The pressurizer power operated relief valves were modified to meet the RCS overpressurization requirements.

6.

Further polarity changes were made in the control rod drive power cables to improve current traces.

7.

'lhe steam generators were eddy current examined and a tube sample was extracted from the 1B steam generator.

Fifteen tubes were plugged in the 1B steam generator and one in the lA.

8.

Replacement of the rotor assembly on the lB component cooling pump was done due to excessive wear on the rotor shaft in the areas of the pump bearings.

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