ML17309A429

Monthly Operating Rept for June 1989 for Re Ginna Nuclear Power Plant.W/890724 Ltr

ML17309A429
Person / Time
Site:	Ginna
Issue date:	06/30/1989
From:	Dodge R, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8908030214
Download: ML17309A429 (7)

Text

A.C CElZ RATED Dl BU'EON DE M ONSTR TIO.'i SYSTEM 4 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)ACCESSION NBR:8908030214 DOC.DATE: 89/06/30 NOTARIZED:

NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION DODGE,R.E.

Rochester Gas&Electric Corp.MECREDY,R.C.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating rept for June 1989 for RE Ginna Nuclear Power Plant.W/890724 ltr.DISTRIBUTION CODE: IE24D COPIES RECEIWED:LTR ENCL SIZE: TITLE: Monthly Operating Report (per Tech Specs)NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)

.05000244 D RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DOA XRM TECH ADV NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RGN1 EXTERNAL EG&G S IMPSON I F NRC PDR COPIES LTTR ENCL 3 3 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DSP/TPAB NRR/DLPQ/PEB 10 NRR/JEEP/RPB 10 EG 01 LPDR NSXC COPXES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D NOTE'IO ALL"RIBS" MKXPZEPIS S PLEASE HELP US'IO REDUCE HASTE!CONI'ACZ'IHE DOCXJMKI'XWZROL DESK ROCN Pl-37 (EXT.20079)IO EIaIMZNATE KRR NAME HEM DISI%GH7ZXCN LISTS FOR DOCUKRPIS YOU DGN~T NEED!TOTAL NUMBER OF COPXES REQUIRED: LTTR 19 ENCL 19

, 0 t~'vzz<uze Eel (Al~*A~uiI"iI@au ROCHESTER GAS AND ELECTRIC CORPORATION o 69 EAST AVENUE, ROCHESTER, N.Y.14649-0001 TELEPHONE*ma*coos 7ia 546.2700 GINNA STATION July 24, 1989 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Monthly Report for June, 1989 Operating Status Information R.E.Ginna Nuclear Power Plant Docket No.50-244 r

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 June, 1989.Very truly yours, Robert C.Me re General Manager Nuclear Production RCM/eeh Attachments cc: Mr.William T.Russell NRC (1)aqppp3pg]4

+90&3 PDR PDQCK p~~.R OPERATING STATUS OPERAT(NG DATA REPORT DOCKET NO.50 244'l 24, 1989 COMPLETED BY Robert E.Dodg TELFPHONE 315-524-4446 x-396 Ginna Station I~Unit Name: R.E.6INNA NUCLEAR POWER 2.Reporting Period: June, 1989 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross MWe): 5.Design Electrical Rating (Nct MWe): 6.Maximum Dependable Capacity (Gross MWe)t 7.Maximum Dependable Capacity (Net MWe): PLANT 1520 490 470 490 470 Notes The unit operated at approx.100%power for the majority of the report period, with a few exceptions detailed on page 4 of the report.8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Rcport, Give Reasons: 9.Power Level to Which Restricted, If Any (Nct MWc): 10.Reasons For Restrictions, If Any: This Month Yr.-to-Date Cumulative 4,343 720 2,514.23 2,455.75 3,517,368 1,187,058 1,127,294 56.55 56.55 55.23 55.23 82.58 4.31 11.Hours In Reporting Period 12.Number of Hours Reactor Was Critical 636.74:~13.Reactor Reserve Shutdown Hours 14.Hours Gcncrator On-Line 630.5 15.Unit Reserve Shutdown Hours 0 16.Gross Thermal Energy Generated (MWH)878, 174 17.Gross Electrical Energy Generated (MWH)294, 833 18.Nct Flectrical Energy Gencratcd (MWH)19.Unit Service Factor 87.57 20.Unit Availability Factor 87.57 21.Unit Capacity Factor (Using MDC Nct)22.Unit Capacity Factor (UsingDER Net)82.58 23.Unit Forced Outage Rate 12.43 24.Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): 172,169.45 134,211.84 1,687.55*131,727.63 8.5*185,487,782 60,986,387 57,871,752 76.69 76.69 73.05 73.05 6.34 25.If Shut Down A't End Of Report.Period, Estimated Dace of Startup: 26.Units In Test Status (Prior to Commercial Operation):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMFRCIAL OPERATION Forecast Achieved*Cumnulative total comnencing January 1, 1975 Atv.44$49 88

>v AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-244 UNIT R.E.Ginna Nuclear Power Plant DATE Jul 4 989 COMPLETED BY r Robert E.D ge TELEPHONE 1 315 524-4446 Ext.396 at Ginna MONTH June 1989 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)DAY AVERAGE DAILY POWER LEVEL (MWe-Net)2~3~4~5.6.7~8.9~10.12.13~14.15'6.101 363 430 459 482 486 482 481 482 486 486 486 486 485 484 17.18'9~20.21.22'3'4.25.26.27'8.29'0.31.485 485 474 485 445-14 160 475 477 477 475 475 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.

DOCKI:.T NO.SO 244 liNITNAME.

R E-GINNA NUCLEAR POWER PLANT UNIT SHUTDOWN AND POWER REDUCTIONS DATE (:OhIPLETED BY Robert E.REPORT MONTH JULY 1989 TELEPIIONE 315-524-4446 x-396 sana a ion C Ho.Dote c~0 P o o&Q~C 0 0 o cd Pl cn>>0 o au 4 o>>4>n.'l Eo c 0 CL Licensee Event Report 0 Ew 5 0 0 EA (J c OIA o c Q E o'U Cause L Corrective Action to Prevent Recurrence 89-3 6-1-89 17 H 89-"004 IE Reactor trip was due to a turbine trip with reactor power greater than 509, due to an AMSAC actuation.

Corrective Action: affected procedures were changed to ensure ANSAC is reset.89-4*6-22-89 476 H 89-007 SF SF SI pump design flaw delivery con-cerns.Incorrect original calibration data.Corrective Action: correct calibra-tion data was confirmed for each orifice/flow transmitter combination 1 F: Forced S: Scheduled REV.4/85 4949 Reason: A-Equipmcnt Failure (Explain)B-Maintenance or Test C-Refueling D-Regulatory Restriction'-Operator Training gc License Examination F-Administrative G-Operational Error (Explain)H-Ocher (Explain)3 hlethod: 1-hlanual 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"Yearly Outage Number

'o tt V t(

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO.50-244 UNIT R.E.Ginna Nuclear Power Plant DATE Jul 2 19 9 COMPLETED BY obert E.Dod e TELEPHONE 1 315 524-4446 EXT.396 at Ginna MONTH June 1989 The unit operated at 100%reactor power level for the majority of the report period, with some exceptions, detailed below.On June 1, 1989 at 1332 EDST, with the reactor at approximately 534 power, a turbine trip with subsequent reactor trip occurred due to a ATNS Mitigation System Actuation Circuitry (AMSAC).On June 19, 1989 at 1440 EDST with the reactor at approximately 994 full power the"B" and"C" Safety Injection (SI)pumps were declared inoperable due to assessed design flow delivery concerns.On June 21, 1989 at 1401 a similar problem occurred with the"B" and"C" SI pumps and plant management decided to shut the plant down until the SI pump flow concerns were resolved.The plant was shutdown and subsecpxently cooled down to less than 350oF