ML17309A432

Monthly Operating Rept for Jul 1989 for Re Ginna Nuclear Power Plant

ML17309A432
Person / Time
Site:	Ginna
Issue date:	07/31/1989
From:	Dodge R, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8909010027
Download: ML17309A432 (8)

Text

ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 GINNA STATION August 15, 1989 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Monthly Report for July, 1989 Operating Status Information 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 July, 1989.

Very truly yours,

'-/(.s'~(.))--

Robert C. Mecredy General Manager Nuclear Production RCM/eeh Attachments cc:

Mr. William T. Russell NRC (1) 890"~03 OOV7 8"tQr'.~3

PDP, ADQC;< !)50!lDAN?~

p tzg$ l

OPERATING STATUS OPERATING DATA REPORT DOCKET NO.

DATE Au st 15, 1989 COMPLETED BY Robert E. Dodge TELEPHONE 315-524-4446 ext.

396 G~a Station 1520

1. Unit Name.'.E. 6INNA NUCLEAR POWER PLANT

2. Reporting Period:

u vi

3. Licensed Thermal Power (MWt):

490

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

Notes The unit operated at approx.

100% power for the majority of the reporting period, with the exceptions detailed on page 4 of this report.

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 5,087 744 697.30 3,211.53 697.25 3, 153 1,040, 174 4,557,542 1,454,187 343,988 326,893 1,453,721

93. 72%

61.98%

61.98%

93.72%

93.48%

93.48%,

6.28%

60.82%

60.82%

4.75%

Type, Date and Duration of Each):

11. Hours In Reporting Period

12. Number of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

'8. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using,DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (

172,913.45 134,909.14 1,687.55*

132,424.88 8.5

• 186, 527, 956 61,330,375 58,198,645 76.76%

76.77%

73.14%

73. 14%,

6. 34%

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

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

INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast Achieved

• Cumnulative total comnencing January 1,

1975 Afv 449 498s

~

~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-244 UNIT R.E.

Ginna Nuclear Power Plant DATE u u 15 1989 COMPLETED BY Robert E.

Dodge TELEPHONE 1

315 524-4446 Ext.

396 at Ginna MONTH Jul 1989 DAY AVERAGE DAILY POWER LEVEL (MWe-Net}

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 473 17

~

471 2 ~

3 ~

4 ~

5.

6 ~

7 ~

8

~

472 471 472 474 410 466 471 18.

19.

20 ~

21.

22

'3

'4.

472 477 483 482 483 483 482 9 ~

470 25.

476 10'69 470 26.

27'66 464 12.

13.

469 471 28.

29.

435 14.

15'69 471 30

~

31 ~

-10

-10 16.

472 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.

l)O(:KE1'O.

SO-244 IGNI'I NAhll R.E. 6INNA NUCLEAR POWER PLANT UNIT SHUTDOWN AND POWER REDUCTIONS

(:OhIPLI'.1'ED IIY ~

Wm~c Robert E. Dodge PORT hIONTH JULY'989 1ELEpll()NE 315-524-4446 ext.

396 Ginna Station Date C ~

0 08O~

rIc C0Vl0O txl DI <<0 C u0 o

> CC 0M$

C 0O Licensee Event Report II Em 0

III D0

~1$

~ Ql C

0 0

0 lJ Cause gI Corrective Action to Prevent Recurrence 7-06-89 7-30-89 12.5 46.75 89-008 LER 89-009 1B Reactor Power level reduced to appmximately 50% due to dmpped md signal.

Manual controlled shutdown due to (MRPI System Failure) Micropmcesso Rod Position Indicator I

F:

Forced S:

Schcd u lcd AEV. 44$

49.89 Reason:

A-Equipmcnt Failure (Explain) 8-Maintenance or Test C-Refueling D-Regulatory Restr iction E-Operator Training 8c License Examination F-Administrative G-Operational Error (Explain)

II-Other (Explain) 3 hlcthod:

I-hlanual 2-hlanual Scram.

3-Automatic Scram.

4-Other (Explain) 4 Fxhibic G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)

Exhibit I - Same Source

• Power Reduction

NARRATIVE

SUMMARY

OP OPERATING EXPERIENCE DOCKET NO.

50-244 UNIT R.E.

Ginna Nuclear Power Plant DATE Au us 15 1989 COMPLETED BY Robert E.

Dodge TELEPHONE 1

315 524-4446 EXT.

396 at Ginna MONTH Jul 1989 The unit operated at 1004 reactor power level for the majority of the report period, with exceptions detailed* below.

On July 6, 1989 at 1557 EDST a turbine runback to 754 reactor power occurred due to dropped control rod.

Control Room operators reduced the reactor power to 50% for retrieval of a dropped RCC.

On July 29, 1989 at 1843 EDST the Control Room received annun-ciator alarm C-29 (MRPI System Failure) Microprocessor Rod Position Indication System.

The loss of all control rod position indication placed the plant in a condition not permitted by the plant's Tech Specs.

'I AT 1933 EDST, July 29, 1989 a plant shutdown was commenced to comply with the plant Tech Specs.

At 2035 EDST, July 29, 1989 the Operations Shift Supervisor declared an Unusual Event.

At 0118 EDST, July 30, 1989 the reactor was subcritical and at 0132 EDST the reactor trip breakers were opened with all control rods inserted.

At 0140 EDST, July 30, 1989 the Unusual Event was terminated.

/

September 15, 1989 DISTRIBUTION:

,'ocket PDI-3 Reading AJohnson MRushbrook DOCKET NO(S) 50-244 EIS Review Coordinator EPA Region XZ 26 Federal Plaza New Y'ork, New York 10276

SUBJECT:

ROCHESTER GAS

& ELECTRIC CORPORATION GINNA NUCLEAR PLANT The following documents concerning our review of the subject facility are transmitted for your information.

DESCRIPTION OF DOCUMENT Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.

Environmental Assessment and Finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating. Licenses Involvin No Si nifleant Hazards Conditions

.1 See Page(s)

Exemption DATED Construction Permit No. CPPR-Facility Operating License No..

Order Monthly Operating Report for

, Amendment No.

,Amendment No.

transmitted by Letter Annual/Semi.Annual Report: Semiannual Radioactive Effluent.Release 0

transmitted by Letter 8/2~/89 Other Office of Nuclear Reactor Regulation

Enclosures:

As Stated cc: w/enclosure:

g~/

OFFICE>

SURNAME>

0ATEN NRR:PDI-..3.

gpgqQbroo

..S/X5./.a9.

NRC FORM 318 tto/80) NRCM 0240 OFFICIAL RECORD COPY

Rochester Gas 6 Electric Corporation cc w/enclosure:

Chief, Division of Ecological Services Bureau of Sport Fisheries 6 Wildlife U.S. Department of the Interior Washington, D.C.

20240 Director, Office of Ecology and Conservation National Oceanic 6 Atmospheric Administration U.S. Department of Commerce 1335 East West Highway Silver Spring, Maryland 20910 Dr. William Cunningham FDA Research Chemist Bureau of Standards 6 Technology Reactor Building 235,,

Room B-108 Gaithersburg, Maryland 20899