ML17264A604

Monthly Operating Rept for July 1996 for Re Ginna Nuclear Power Plant.W/960813 Ltr

ML17264A604
Person / Time
Site:	Ginna
Issue date:	07/31/1996
From:	Walden J, Widay J ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9609240200
Download: ML17264A604 (6)

Text

CATEGORY 1 REGULAT INFORMATION DZSTRZBUTIOIIZSTEN (RIDE)E2:CESSION NBR:9609240200 DOC.DATE: 96/07/31 NOTARIZED:

NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION WALDEN,J.V.

Rochester Gas 6 Electric Corp.WIDAY,J.A.

Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT.

AFFILIATION VISSING,G.S.

'I

SUBJECT:

Monthly operating rept for July 1996 for RE Ginna Nuclear Power Plant.W/960813 ltr.DISTRIBUTION CODE: ZE24D COPIES RECEIVED:LTR J ENCL I SIZE: TITLE: Monthly Operating Report (per Tech Specs)NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

E 05000244 G RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DRPM/PECB EXTERNAL: LITCO BRYCE,J H NRC PDR COPIES LTTR ENCL 1 1 1 1 ,1 1 1 1 1 1 RECIPIENT ID CODE/NAME VISSINGFG.

ILE C NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 D M N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR, DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL-9 ROCHESTER GAS AND ELECTRIC CORPORATION

~89 EAST AVENUE, ROCHESTER, N.Y.14649-0001 Cgf'D Q%S aaci-ooc ia 546.2700 August 13, 1996 US Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, DC 20555

Subject:

Monthly Report for July, 1996 Operating Status Information R.E.Ginna Nuclear Power Plant Docket No.50-244

Dear Mr.Vissing:

Pursuant to Ginna Improved Technical Specifications Section 5.6.4, attached is the monthly operating status report for Ginna Station for the month of July, 1996.Included in this report is the documentation of a challenge to the pressurizer power operated relief valves which occurred on July 4, 1996.Very truly ours, s h.A.Wi~Plant Manage xc: U.S.Nuclear Regulatory Commission Mr.Guy S.Vissing (Mail Stop 14C7)Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 U.S.Nuclear Regulatory Commission Mr.W.H.Lovelace MNBB 7602 Washington, D.C.20555 U.S.NRC Ginna Senior Resident Inspector Attachments 9609240200 960731 t PDR ADOCK 05000244.R PDR 50-244 u ust 13 1996 V John V.Walden TELEPHO E (716)771-3588 COMPLETED BY PERATING DATA REPORT 1.Unit Name: R.E.GINNA NUCLEAR POWER PLANT Notes: 2.Reporting Period: Jul 1996 3.Licensed Thermal Power (MWI): 1520 4.Nameplate Rating (Gross MWe): 517 5.Design Electric Rating (Net MWe): 470 6.Maximum Dependable Capacity (Gross MWe): 490 7.Maximum Dependable Capacity (Net MWe): 470 8.If Changes Occur in Capacity Rating (Items Number 3 Through 7)Since Last Report, Give Reason: 9.Power Level to Which Restricted, If Any (Net MWe: 10.Reason For Restrictions, If An.This Month Yr.-to.Date Cumulative" 11.Hours in Reported 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)18.Net Electrical Energy Generated (MWH)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 (%)744.0 649.5 0.0 644.6 0.0 928606.0 310129.0 294668.0 86.6 86.6 13.4 5111.0 3262.0 0.0 3213.2 0.0 4632914.0 1569853.0 1491973.0 62.9 62.9 62.1 62.1 5.4 233879.0 186929.1 1687.6'83961.9 8.5'61496222.0 86632353.0 82239785.0 78.7 78.7 75.9 75.9 5.5 24.Shutdovms Scheduled Over Next 6 Months (Type, Date and Duration of Each): 25.If Shutdown At End of Report Period, Estimate Date of Startup: 26.Units ln Test Status (Prior to Commercial Operation):

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION'UMULATIVE TOTAL COMMENCING JANUARY 1, 1975" CUMULATIVE TOTAL COMMENCING NOVEMBER 8, 1969 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-244 UNIT: R.E.Ginna Nuclear Power Plant MONTH Jul 1996 DATE: Au ust 13 1996 COMPLETED BY: ale John Walden TELEPHONE:

716 771-3588 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)484 F 17'80 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)2.3.4.5.6.7.8.9.10.12.13.14.15.482 168 180 482 483 483 484 486 486 486'8.19.20.21.22.23.24.25.26.27.28.29.30.31.480 482 482 484 483 314 481 483 481 480 480 481 488 494 16.484 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in reporting month.Compute to the nearest whole megawatt.

l)O(:Kl'.T NO.UNIl NAMI'.R E.(8INNA NUCLEAR POWER PLANT UNIT SHUTDOWN AND POWER REDUCTIONS I)ATE" 3 1996 (:OMPLI TI:.I)IIY John V.'alcCen 1'I:LEPlloNE 716 771-3588 Ho.Dote 4 I.o ss 4 0 QX d~C 0 Vl 0 e~0 oco oto>cc 4(A a 0 d Licensee Event Report II Ew 0 0 Vl Q o an o C~I ln C, 0 Q so o Cause 8 Corrective Action to Prevent Recurrence 7/3/96'99.4 Pressurizer safety~alve began leaking while the unit was at full power.The unit was placed in mode 5 for valve maintenance.

7/>1/96 F l7.6 Leaking containment spray test line caused an administrative power reduction.

Repair activities stopped the leak and halted the power reduction prior to going off-line.F: Forced St Scheduled Rtv 4/89 i9.89 2 Reason: h-Equipment Failure (Explain)B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8c License Examination F-Administrative G-Operational Error (Explain)H-Other (Explain)3 hfethod: I-hfanual 2-Manual Scram.3-Automatic Scram./I-Other (Explain)Exhibit (i-Instructions for Preparation of Data Entry Sheets for Licensee Event Rcport (Ll!R)I'lc (NllRI (-0161)I'.xhibit I-Same Source NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO: 50-244 UNIT: R.E.Qinna Nuclear Power Plant DATE: Au ust 13 1996 COMPLETED BY: TELEPHONE:

v v2d John Walden 716 771-3588 MONTH Jul 1996 The unit began the month at full power.On July 3, 1996, a pressurizer safety valve began to leak.The unit was manually shut down and placed in mode 5.The reactor coolant system was drained=and safety valve replaced with a spare.While in mode 4, reactor coolant system pressure reached the activation setpoint of the low temperature overpressure protection system.Pressurizer power operated relief valves 430 and 431C opened momentarily and reduced reactor coolant system pressure.The remainder of the start up activities proceeded normally.The unit was placed on-line on July 8, 1996.Full power operations continued from July 9, 1996 to July 23, 1996.A power reduction occurred on July 23, 1996 due to a leaking containment spray test line.The power reduction was halted when the condition was cleared.The unit was brought back to full power on July 24, 1996 and remained there for the rest of the month.