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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20247M6281989-03-31031 March 1989 Nonproprietary Advanced Digital Feedwater Control Sys Median Signal Selector for Diablo Canyon Units 1 & 2 ML20247H0761988-11-30030 November 1988 Vol 1 to Bit Elimination Study for Diablo Canyon Units 1 & 2 ML20205S9071988-10-31031 October 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20206E7181988-05-30030 May 1988 Analysis of Capsule U from PG&E Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20151R0551988-03-31031 March 1988 Nonproprietary Calculation of Steam Generator Level Low & Lo-Lo Trip Setpoints W/Use of Rosemount 1154 Transmitter ML20151V8861988-02-29029 February 1988 LOFTTR2 Analysis for Steam Generator Tube Rupture for Diablo Canyon Power Plant Units 1 & 2 ML20236M6731987-07-31031 July 1987 Rev 2 to RHR Sys Autoclosure Interlock Removal Rept for Diablo Canyon Nuclear Power Plant 1997-01-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20141M0471991-12-31031 December 1991 Pge Annual Rept - 1991 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20085D2951991-08-21021 August 1991 Field Exercise Scenario,Aug 1991 ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20065R8731990-11-30030 November 1990 Monthly Operating Repts for Diablo Canyon Units 1 & 2 for Nov 1990 ML20058P5181990-05-11011 May 1990 Accident Sequence Precursor Program Event Analysis 323/87-005 R2, Loss of RHR Cooling Results in Reactor Vessel Bulk Boiling ML20058P5131990-04-0505 April 1990 Accident Sequence Precursor Program Event Analysis 424/PNO-IIT-90-02A, Loop,Diesel Generator Failure & 36 Min Interruption of SDC During Mid-Loop Operation ML20058P5221990-02-0303 February 1990 Accident Sequence Precursor Program Event Analysis Loss of Reactor Protection Sys Bus B Causes Loss of Shutdown Cooling ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20245G9881989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed DCL-89-117, Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 8904181989-04-27027 April 1989 Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 890418 ML20247M6281989-03-31031 March 1989 Nonproprietary Advanced Digital Feedwater Control Sys Median Signal Selector for Diablo Canyon Units 1 & 2 ML20246P4461989-03-23023 March 1989 Corrected Diablo Canyon Power Plant Unit 2 Second Refueling Outage Inservice Insp (ISI) Rept ML20236E0581988-12-31031 December 1988 Pacific Gas & Electric Co Annual Rept 1988 ML20247H0761988-11-30030 November 1988 Vol 1 to Bit Elimination Study for Diablo Canyon Units 1 & 2 ML20205S9071988-10-31031 October 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20206E7181988-05-30030 May 1988 Analysis of Capsule U from PG&E Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20195G3301988-04-30030 April 1988 Corrected Monthly Operating Repts for Apr 1988 for Diablo Canyon ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant 1999-07-12
[Table view] |
Text
Westinghouse Non-Proprietary Class 3 pocket I'~'cgaSS10A
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Instrumentation Calibration and Drift Evaluation Process for Diablo Canyon Units 1 and 2 24 Month Fuel Cycle Evaluation Westinghouse Energy Systems 9'702120285 9'70133.
PDR ADOCK 05000275 P PDR
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SZSTINGHOUSE NON-PROPRlETARY CL4SS 3 WCAP-14826 INSTRUMENTATIONCALIBRATIONAND DRIFT EVALUATIONPROCESS FOR DIABLO CANYON UNITS 1 AND 2 24 MONTH FUEL CYCLE EVALUATION January, 1997 R. W. Trozzo C. R. Tuley
'WESTINGHOUSE ELECTRIC CORPORATION Nuclear Services Divivion P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 1997 Westinghouse Electric Corp., All Rights Reserved
FOREWORD This information is being submitted in support of the PACIFIC GAS AND ELECTRIC DIABLO CANYON I/2 24 Month Extended Fuel Cycle Program.
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ACKNOWLEDGlVKÃTS The authors of this report wish to acknowledge L. Bates, T. Donat, and P. Kennevan for their cooperation and technical assistance throughout the Diablo Canyon Units 1 and 2 Extended Surveillance Interval Program.
I' TABLE OF CONTF2G'S
1.0 INTRODUCTION
................................... 2.0 PROCESS DESCRIPTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~
2.1 INPUT DATA ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
2.2 PROBABILITY/CONFIDENCELEVEL 2.3 DISTRIBUTION FUNCTION EVALUATION 2.4 OU'lI 'IER EVALUATION ...................... 2.5 DRIFT/CALIBRATIONACCURACY DETERMINATION 2.6 TIME DEPENDENCE 3.0 RES ULTS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
3.1 TRANSMITJKRS/SENSORS 3.1.1 CALIBRATIONACCURACY 3 .1.2 DRIFT ............e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3.2 PROCESS RACKS ........................... 3.2.1 CALIBRATIONACCURACY 3 .2.2 DRIFT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
4.0 CONCLUSION
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 16 Figure 1 WESTINGHOUSE CALIBRATIONACCURACY & DRIFT EVALUATIONPROCESS ............................ TABLE 1: DIABLO CANYON UNITS 1 & 2 DRIFT
SUMMARY
......... APPENDIX A DIABLO CANYON UNITS 1 & 2 SAMPLE DRIFT EVALUATIONOUTPUT NARROW RANGE STEVrI GENERATOR LEVEL TRANSMITTERS ...... - lll-
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'a INSTRUMENTATIONCALIBRATIONAND DRIFT EVALUATIONPROCESS FOR DIABLO CANYON UNITS 1/2 FUEL CYCLE EXTENSION TO 24 MONTHS
1.0 INTRODUCTION
In support of the extension of fuel cycles to 24 months, Enclosure 2 to Generic Letter 91-04 requires that plant instrument drift be reviewed for consistency with setpoint uncertainty calculations under the extended operating cycle. Westinghouse has developed a process to accomplish this for instrumentation calibration accuracy and drift for a 24 month fuel cycle. An overview of this process is shown in Figure 1. The plant as left and as found calibration data is first organized into computer spreadsheets and examined with respect to distribution type using commercially available software. Next, the sample data is extrapolated to the population using descriptive statistics and tolerance factors, resulting in calibration accuracy or drift allowances at specified probability (or proportion) and confidence levels. Finally, the drift data is examined for the indications of time dependence and adjustments are made, as appropriate, to yield instrumentation drift allowances applicable to a 24 month fuel cycle, i.e., a maximum surveillance interval of 30 calendar months. An integral part of this process is the continual screening of data integrity and the removal, as appropriate, of nonrepresentative data sets based on the identification of mechanistic causes or statistical outliers.
2.0 PROCESS DESCRIPTION 2.1 INPUT DATA
+a,c
x
+a,c Note that there typically exists several functions where past operating data is not available due to the replacement of the instrumentation with devices of a different manufacturer/model. For these cases, manufacturer's specifications along with engineering judgement and knowledge gained from evaluations of similar instruments at Diablo Canyon as well as other plants are used as the basis to estimate a conservative drift allowance.
2.2 PROBABILITY/CONFIDENCE LEVEL
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+a,c 2.3 DISTRIBUTION FUNCTION EVALUATION
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+a,c 2.4 OUTLIER EVALUATION
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+a,c DRIFT/CALIBRATIONACCURACY DET1<WMINATION
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+a,c 2.6 TIME DEPENDENCE Up to this point in the process, the x + ks drift values have been derived from as left and as found data without regard to the time interval associated with each surveillance. Since an objective of the drift evaluation process is to evaluate past performance for a nominal 18 month fuel cycle and to predict performance for a 24 month fuel cycle, an evaluation of the time dependence of drift is performed. The process involves a combination of qualitative and quantitative checks to determine whether a time dependency exists and, if so, to determine a drift value applicable to a 30 month surveillance period. [
~+a,c
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+a,c 3.0 RESULTS The calibration accuracy and drift evaluation process described in Section 2 was employed to evaluate the RPS/ESFAS functions affected by the Diablo Canyon Units 1 and 2 Fuel Cycle Extension program. The results of these evaluations will be discussed for transmitters/sensors and process racks.
t 3.1 TRANSMITTk&S/SENSORS All transmitters and sensors were evaluated for both calibration accuracy and drift.
3.1.1 CALIBRATIONACCURACY
+a,c 3.1.2 DRIFT
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+a,c 3.2 PROCESS RACKS Westinghouse evaluated several different types of process rack equipment which are affected by the 24 month surveillance extension. This equipment includes process computer point indication, control board indicators and a limited number of analog rack modules. All equipment was evaluated for both calibration accuracy and drift.
3.2.1 CALIBRATIONACCURACY
+a,c 3.2.2 DRIFT
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4.0 CONCLUSION
In support of the extension of fuel cycles to 24 months in accordance with Generic Letter 91-04, a process has been identified to evaluate instrument calibration accuracy and drift based on plant as left and as found calibration data. This process has been applied to the RPS/ESFAS functions affected by the Diablo Canyon 1 and 2 fuel cycle extension to 24 months. These evaluations have concluded that the calibration accuracy achieved by the plant I&C staff is within procedural tolerances and consistent with the assumptions of the statistical setpoint methodology, The as left and as found data has been evaluated to determine drift on a 95/95 basis, including an evaluation of potential time dependence.
The resulting drift allowances have been incorporated in setpoint uncertainty evaluations and will serve as a basis for evaluating drift at the increased surveillance interval.
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FIGURE 1 WESTINGHOUSE CALIBRATION ACCURAC Y 8 DRIF T EVALUATION PROCESS +a,c
TABLE 1: DIABLO CANYON UNITS 1 5 2 DRIFT SUIIlIIMARY Transmitter Channel Function Device Drift Approx. Max r Notes d Data Pts Prcssurizcr Pressure low, High, Low Si. ITDP Roscmount 1154SHSRC Pressurizer Level <<gh, Control Rosemount II53HD5 RCS Flow Low, ITDP Roscmount 1153HD5RC Barton 784 Narrow Range Stcam Generator Low Low, High High, Rosemount 1154DP4RC level Control Containment Pressure High, High-High Roscmount 1154DPSRC Steam Generator Prcssure Low Sl, ITDP Barton 783 High Negative Rate Rosemount 1154SH9RC Feedweter Flow ITDP Rosemount 1153HD5RC Turbine I'tage Pressure ITDP Barton 783 Roscmount 1153GD8RC RCP uV Rchrys Undervoltege Basler BE1.27 RCP uF Relays Underfrequancy Basler BE14II Seismic Triggers High Ianemetrics TS33A 4KV uV Relays Undervoltage Wasterghouse General Electric Feedwater Temperature ITDP Type E Thcrmocouplcs TCsf WP250
Rack Channel Function Device Drift Approx. Max r Notes I Data Pts Pressunter Pressure ITDP W VX.252 Indicator Pressuriter Level Control W VX 252 Indicator RCS Flow ITDP W VX.252 Indicator Narrow Range Steam Generator Control W VX.252 Indicator level Stcam Generator Pressure ITDP W VX.252 Indicator RCS T ITDP W VX.252 Indicator Pressurirsr Pressure ITDP W P.250 Computer Stcam Generator Pressure ITDP W P-250 Computer To*inc 1'tage Pressure ITDP W 7100 Analog Racks
APPENDIX A DIABLO CANYON UNITS 1 dk 2 SAMPLE DRIFT EVALUATIONOVIPUT NARROW RANGE STEAM GENFKATOR LEVEL TRANSMITTk&S
NARROW RANGE STE~ GENERATOR LEVEL TRANSMXITERS SENSOR DKFT - ROSEMOUNT 1154DP4RC
SPREAD SHEET DATA
SPREAD SHEET DATA (CORI~IED)
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+a,c pGE ss cvi so:t
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+a,c +a,c PGE SG LVL SDC
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PGE NR STEAM GENEEMTOR LEVEL SENSOR DRIFT
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PGE NR STEQvl GENERATOR LEVEL SENSOR DRIFT (CONTQ'RJED)
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'l PGE NR STEAM GENEHMTOR LEVEL SENSOR DRIFT (COKIVKJED)
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