ML18142B353
| ML18142B353 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/07/1978 |
| From: | Snow B Rochester Gas & Electric Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142B353 (14) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-244 REC: 'NRC ORG: SNOW B ROCHESTER GAS 8(ELEC DOCDATE: 09/07/78 DATE RCVD: 09/18/78 DOCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING SUBJECT FACILITY"8 MONTHLY OPERATING REPT FOR THE MONTH OF AUGUST>1978.PLANT NAME: RE GINNA-UNIT 1~wee w H+e%%%o+m+x DISTRIBUTION OF TH IS MATERIAL')'ANNUAL'EMI-ANNUAL 0 MONTflLY OPERATING RPTS (DISTRIBUTION CODE A008)FOR ACTION: BR CHIEF ORBS2 BC@->W/6 ENCL REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: IS AS FOLl OWS++w+ww+wwwwww+ww++(OL STAGE>INTERNAL: EXTERNAL: I 0 E~~~W/2 ENCL k<ANAUER+~W/ENCL AD FOR SYS 8(PROJ>+W/ENCL REACTOR SAFETY BR++W/ENCL EEB~~W/ENCL EFFLUENT TREAT SYS<NW/ENCL LPDR S ROCHESTER)
NY++W/ENCL NATL LAB ORNL+4W/ENCL TERA++W/ENCL NSIC>+W/ENCL BROOk'HAVEN>wW/ENCL ACRS CAT 8+NW/16 ENCL NRC PDR+4W/ENCL MIPC4>W/2 ENCL DIRECTOR DOR4~+W/ENCL ENGINEERING BR>>W/ENCL PLANT SYSTEMS BR<%W/ENCL CORE PERFORMANCE BR>4W/ENCL DISTRIBUTION:
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~89 EAST AVENUE, ROCHESTER, N.Y.14649 TELEPHONIC AREA coDc 7>6 546 2700'7 CD v<Gi'nna Stag.on September'~7, 1978 i~,~I gl:X;.2~j ,fJkg)~<<g n Vl C/)Director, Office of Management Information and Program Control U.S.NUCLEAR REGULATORY COMMISSION Washington, D.C.20555
Subject:
Monthly Report for August, 1978 Operating Status Information R.E.Ginna Nuclear Power Plant Unit No.1 Docket No.50-244
Dear Sir:
Pursuant to our Technical Specification 6.9.1, attached herewith is the aenthly operating status report for Ginna Station for the month of August, 1978.Very truly yours, Attachments Bruce Snow Superintendent 780870316 oof s+I]
0'I u II, OPERATlNG DATA REPORT DOCKET NO.DATF Se tember 8 1978 COMPLETED BY 2'Andrew E.Mc amara, Operat on e~OPERATING STATUS TELEPHONE 1-716-546-2700 Ext.291-205 at Ginna 1.Unit Name: GINNA STATION N Reporttng Period'u us t 1978 3.Licensed Thermal Power (MWt): 1520 4.Nameplate Rating (Gross MWe): 5.Design Electrical Rating (Net MWe): 470 6.hiaximum Dependable Capacity (Gross hfWe): 7.hiaximum Dependable Capacity (Net hiWe): Notes The.Unit experienced one outage during the Report Period, detailed on Page 3.A Power Level Reduction to~48%on 8/20 is detailed on Page 4.8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: 9.Power Level to Which Restricted, If Any (Net hIWe): 10.Reasons For Restrictions, If Any: This hionth Yr:to-Date Cumulative 5 831 744 11.Hours In Reporting Period 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)18.Net Electrical Energy Generated (hiWH)19.Unit Service Factor 20.Unit Availability Factor 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 (Type, 445.42 5.75 1 081 872 614802 355 865 338 684 1 928 512 1 831 418 71%96%69%96%69%96%2%6%Date and Duration of Each): 76 823 74 585 07 8.5 24 116 372 22 813 712 74%68%68%11%1 546.51>>25.If Shut Down At End Of Report.Period, Estimated Date of Startup: 26.Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALITY INITIAL ELECTRICITY COhihiERCIAL OPERATION>>Cumulative Total Commencing January 1, 1975 Forecast Achieved 49 dd (Rav 1/7dl S 1 1 S AVERAGE DAILY UNIT POWER UNIT MONTH August, 1978 DAY AVERAGE DAILY POWER LEVEL (M We-Net)DOCKET NO.UNIT III@irma Stat'o Se tember 8 1 8 COMPLETED BY Andrew E.McNamara, Operations Aide TELFPHON F 1-716-546-2700 Ext.291-205, at Ginna DAYAVERAGE DAlLY POWER LEVEL (MWe-Net)10 12 13 14 15 16 471 477 473 472 470 470 469 17 18 ls 20 21~22 23 24 25 26 27 28 29 30 31 468 46 409 468 4 0 474 477 474 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.'ompute to the nearest whole megawatt.4>87 (REVe 1/78)
I pr 4 I r I'~-~R~~~C 4 C/lW 4' UNIT SHUTDOWN AND POWER REDUCTIONS DOCKET NO.SO-244¹1 Ginna Station COMPLETED I3 Y Andrew E.HcNamara, Operations Aide TELEPllONE 1-716-546-2700 Ezt.291-205, at Ginna Ho.Dote 0 0 a 0 0 X,'0 0~l e~0 c 0 o~>L 0 n C 0 O Licensee Event Report¹Em=0 Ul 0 iA c 0 ltd c 0 E 0 O Couse&Corrective Action to Prevent Recurrencc 780826 F 18.25 A Not IA Applicable Instru.Burned out coil in Reactor Trip Logic.1 F: Forced S: Scheduled 49 89 (REV t/78)2 Reason: A-Equipment Failure (Explain)I3-hlaintcnancc or Test C-Refueling D-Regulatory Restriction E-Operator Training&License Examination F-Administrative G-Operational Error (Explain)H-Other (Explain)hlethod: 1 hlanual 2-hlanual 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
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'4 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO.0 2 UNIT Ginna Station Unit 81 DATE Se tember 8 1978 COMPLETED BY Andrew E.McNamara, Operations de MONTH AUGUST 1978 TELEPHONE 1-716-546-2700 Ext.291-205, at Ginna 4 The Reactor Power Level averaged 100%in the Report Month, with the following major exceptions:
On 8/20, the Reactor Power Level was reduced to~48%to perform the Turbine Main Steam Stop Valves Test.On 8/26, a Reactor Trip/Turbine Trip occurred, due to a burned out coil in Reactor Trip Logic.See Details, Page 3.The Unit was restored to service on 8/27 after repairs were effected.49 123 u/73)
'I~l~-r Ginna Station MAINTENANCE REPORT FOR AUGUST, 1978 During August, normal inspection and minor maintenance was performed.
Major safety related maintenance indluded: 1.Replacement of a diaphragm on the boric acid filter outlet valve.2.Repair of the fuse block stabs on the 1B Emergency Diesel Generator Tie Breaker to Bus 16 (LER 78-07).3.Completed replacement of the hinge assembly on the containment personnel hatch outer door due to a bent hinge pin.4.Repair of a defective torque switch to valve 3504 Main Steam to the Auxiliary Feedwater Pump.