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#REDIRECT [[RS-07-034, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection (TAC Nos. MD0540 and MD0541)]]
| number = ML070990338
| issue date = 04/06/2007
| title = LaSalle County Station, Units 1 and 2, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection (TAC Nos. MD0540 and MD0541)
| author name = Benyak D M
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/ADRO
| docket = 05000373, 05000374
| license number = NPF-011, NPF-018
| contact person =
| case reference number = RS-07-034, TAC MD0540, TAC MD0541
| document type = Letter, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specification, Amendment
| page count = 314
| project = TAC:MD0540, TAC:MD0541
| stage = Other
}}
 
=Text=
{{#Wiki_filter:Exelon Generation www.exelo-tcorp.co m 4300 Winfield Road Warrenville, IL 60555 E xe~+ I ' nsM Nuclear RS-07-034 10 CFR 50.90 April 6, 2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
 
==Subject:==
Additional Information Supporting the License Amendment Request Associated With Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection (TAC Nos. MD0540 and MD0541) References
: 1. Letter from K. R. Jury (Exelon Generation Corporation, LLC) to U. S. NRC, "Request for a License Amendment to Revise Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection," dated March 16, 2006 2. U. S. NRC to C. M. Crane (Exelon Generation Company, LLC), "LaSalle County Station, Units 1 and 2 - Request for Additional Information Related to License Amendment Request to Technical Specification Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," dated February 21, 2007 In Reference 1, Exelon Generation Company, LLC, (EGC), requested an amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-11 and NPF-18 for LaSalle County Station (LSCS) Units 1 and 2 respectively. Specifically, the proposed changes will modify TS 3.3.6.1, "Primary Containment Isolation Instrumentation," Table 3.3.6.1-1 to revise the Allowable Values for Reactor Core Isolation Cooling (RCIC) temperature based leak detection. The proposed change is a result of revising the setpoint calculation for the subject temperature instruments based on the current reactor coolant leak detection analytical limit. In Reference 2, the NRC requested additional information to complete the review of the license amendment. Attachment 1 of this letter provides the requested information. Attachments 2a through 2f provide supporting reference documents. EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment 1 of Reference
: 1. The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.
April 6, 2007 U. S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Ms. Alison Mackellar at (630) 657-2817. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 6th day of April 2007. Darin M. Benyak Manager, Licensing and Regulatory Affairs Attachment 1: Response to Request for Additional Information Attachment 2a: NED-I-EIC-0213, Revision 00 Attachment 2b: NED-I-EIC-0213, Revision 1 G Attachment 2c: EIC-20.04, Revision 4 Attachment 2d: ER-AA-520, Revision 3 Attachment 2e: LIS-RI-103A Attachment 2f: LIS-RI-103B In reviewing the Exelon Generation Company's (Exelon's) submittal dated March 16, 2006, requesting a change to Technical Specification (TS) 3.3.6.1, "Primary Containment Isolation Instrumentation," Table 3.3.6.1-1, to revise allowable values for reactor core isolation cooling (RCIC) temperature based leak detection, for the LaSalle County Station, Units 1 and 2, as shown below: Question No. 1 R esponse ATTACHMENT 1 Increase the Allowable Value for Function 3.e., "RCIC Equipment Roam Temperature - High," from s 291.0&deg;F to <_ 297.0&deg;F Decrease the Allowable Value for Function 3.f., "RCIC Equipment Room Differential Temperature - High," from <_ 189.0&deg;F to s 188.0&deg;F Decrease the Allowable Value for Function 3.g., "RCIC Steam Line Tunnel Temperature - High," from <_ 277.0&deg;F to <_ 267.0&deg;F Increase the Allowable Value for Function 3.h., "RCIC Steam Line Tunnel Differential Temperature - High," from :5 155.0&deg;F to s 163.0&deg;F The NRC staff has determined that the following information is needed in order to complete its review: Setpoint calculation methodology
: provide documentation (including sample calculations) of the methodology used for establishing the limiting setpoint and the limiting acceptable values for the as-found and as-left setpoints as measured in periodic surveillance testing described below. Indicate the related analytical limits and other limiting design values (and the sources of these values) for each setpoint. LaSalle County Station (LSCS) Engineering Calculation, "NED-I-EIC-0213, Revision 1 G," (i.e., Attachment 2b) is the latest revision of the original Engineering Calculation, "NED-I-EIC-0213, Revision 00," (i.e., Attachment 2a). Calculation NED-I-EIC-0213, Revision 1 G determined the current setpoints and acceptable values for the RCIC temperature based leak detection. As shown in Attachment 2b, the related Analytical Limits are design inputs to the calculation. NED-I-EIC-0213, Revision 1 G was prepared using the Exelon Generation Company, LLC (EGC) setpoint methodology as detailed in the EGC Nuclear Engineering Standard, NES-EIC-20
.04, Revision 4, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy," (i.e., Attachment 2c). Func tion 3.e., "RCIC Equipment Room Temperature - High" Calculation NED-I-EIC-0213, Revision 1 G, item 3 (revising Section 4.5) identifies the design input for the RCIC Equipment Area ambient temperature Analytical Limit (AL) as 299.6&deg;F. Item 7 (revising Section 14.2.1) determined the Allowable Value (AV) and Expanded Tolerance (ET) or "As-Found" tolerance for the RCIC Equipment Area ambient temperature trip. The AV value determined was :5 297&deg;F and the ET value determined was +/- 7.0&deg;F. The Setting Tolerance (ST) or "As-Left' tolerance remains +/- 3.0&deg;F. Page 1 of 4 ATTACHMENT 1 Function 3.f., "RCIC Equip ment Room Differential Temperature - High" Calculation NED-I-EIC-0213, Revision 1 G, item 2 (revising Section 4.4), identifies the design input for the RCIC Equipment Area differential temperature Analytical Limit (AL) as 195.6&deg;F. Item 7 (revising Section 14.2.3) determined the Allowable Value (AV) and Expanded Tolerance (ET) or "As-Found" tolerance for the RCIC Equipment Area differential temperature trip. The AV value determined was s 188&deg;F and the ET value determined was +/- 1.5&deg;F. The Setting Tolerance (ST) or "As-Left' tolerance remains +/- 1.5&deg;F. Function 3.g., "RCIC Steam Li ne Tunnel Temperature - High" Calculation NED-I-EIC-0213, Revision 1 G, item 3 (revising Section 4.5) identifies the design input for the RCIC Pipe Routing Area ambient temperature Analytical Limit (AL) as 270.5&deg;F. Item 7 (revising Section 14.2.2) determined the Allowable Value (AV) and Expanded Tolerance (ET) or "As-Found" tolerance for the RCIC Pipe Tunnel Area ambient temperature trip. The AV value determined was <_ 267&deg;F and the ET value determined was +/- 7.0&deg;F. The Setting Tolerance (ST) or "As-Left' tolerance remains +/- 3.0&deg;F. Function 3.h.t "RC IC Steam Line Tunnel Differential Temperature - High" Calculation NED-I-EIC-0213, Revision 1 G, item 2 (revising Section 4.4), identifies the design input for the RCIC Pipe Routing Area differential temperature Analytical Limit (AL) as 170.5&deg;F. Item 7 (revising Section 14.2.4) determined the Allowable Value (AV) and Expanded Tolerance (ET) or "As-Found" tolerance for RCIC Pipe Tunnel Area differential temperature trip. The AV value determined was :5 163&deg;F and the ET value determined was +/- 1.5&deg;F. The Setting Tolerance (ST) or "As-Left' tolerance remains +/- 1.5&deg;F. The source of the design input for the above Analytical Limits as stated in Calculation NED-I-EIC-0213, Revision 1 G item 1 (revising Reference 3.22) is LaSalle County Station Calculation L-001324, Revision 005A, "Area Ambient and Differential Temperature Design Basis Calc for Reactor Coolant Leak Detection." Question No. 2 Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion, information on the controls you employ to ensure that the as-left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. Also, discuss the plant corrective action processes (including any procedures) for restoring channels to operable status when channels are determined to be "inoperable" or "operable but degraded." If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it is ensured that the controls will be implemented.
Re sponse EGC procedure ER-AA-520, "Instrument Performance Trending," (i.e., Attachment 2d) Section 4.2 requires that any safety related, Technical Specification related, Regulatory Guide 1.97, or Maintenance Rule instrumentation found out of calibration limits is entered into an appropriate trending process and that the trends are evaluated. An Issue Report (IR) will be initiated for any instruments in these categories that are found out of calibration limits during periodic surveillances. An IR is the entry point into the EGC Corrective Action Program (CAP). If an instrument is found to be outside of the "as-found" calibration limits and outside of the Allowable Value (AV), the calibration information is documented in the IR and LSCS station management is notified of the potential of inoperability in accordance with the EGC CAP. Specifically, an IR that is associated with equipment operability requires a formal review by Operations Shift Management in accordance with the EGC CAP. The EGC CAP is also the tracking process used to ensure the condition is evaluated, corrected and the appropriate resolution documented. Section 4.2 of ER-AA-520 documents the requirements for reporting instruments that are found outside of the "as-found" calibration limits but within the AV. If this is the case, the calibration information is documented and entered into the CAP as a Condition Report (CR) for periodic trending evaluation. All instruments are required to be left within the "as-left' calibration limits for the instrument in accordance with ER-AA-520 and the individual calibration surveillance procedures. If the instrument cannot be recalibrated to the "as-left' calibration limits, the instrument must be repaired or replaced and documented in the CR. (Note that in the current revision of ER-AA-520, an "Issue Report' is referred to as a "Condition Report," the terms are synonymous
.) The LSCS calibration surveillance procedures LIS-RI-1(2)03A, "Unit 1(2) RCIC Equipment Room/Steam Line Tunnel High Ambient and Differential Temperature Outboard Isolation (DIV 1) Calibration," (i.e., Attachment 2e) and LIS-RI-1(2)03B, "Unit 1(2) RCIC Equipment Room/Steam Line Tunnel High Ambient and Differential Temperature Inboard Isolation (DIV 2) Calibration," (i.e., Attachment 2f) each contain a step to verify that the "as-found" data is within the required calibration limits. If the "as-found" data is not within the required calibration limits, the applicable procedure directs the instrument technician to identify (circle) the "as-found" data and contact the Instrument Maintenance Supervisor for further instructions and, if appropriate, calibrate the instrument and record the "as-left" data. Attachments ATTACHMENT 1 2a: Commonwealth Edison (ComEd) LaSalle County Station Engineering Calculation NED-I-EIC-0213, Revision 00, "RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard and Inboard Isolation Error Analysis" 2b: LaSalle County Station Engineering Calculation NED-I-EIC-0213, Revision 1 G, "Derived Technical Specification Allowable Values for the Instrument Loop Channels that detect RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature based on Corrected Values for Analytical Limits" 2c: Exelon Nuclear Engineering Standard NES-EIC-20
.04, Revision 4, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy" Page 3 of 4 ATTACHMENT 1 2d: Exelon Nuclear Procedure ER-AA-520, Revision 3, "Instrument Performance Trending" 2e: LaSalle County Station Instrument Maintenance Surveillance Procedure LIS-RI-103A, Revision 10, "Unit 1 RCIC Equipment Room/Steam Line Tunnel High Ambient and Differential Temperature Outboard Isolation (DIV 1) Calibration" 2f: LaSalle County Station Instrument Maintenance Surveillance Procedure LIS-RI-10313, Revision 10, "Unit 1 RCIC Equipment Room/Steam Line Tunnel High Ambient and Differential Temperature Inboard Isolation (DIV 2) Calibration" ATTACHMENT 2a Commonwealth Edison (ComEd) LaSalle County Station Engineering Calculation NED-I-EIC-0213, Revision 00, "RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard and Inboard Isolation Error Analysis" NED-I-EIC-0213, Revision 00 RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard and Inboard Isolation Error Analysis 
^OMPONENT EPN EPN 1(2.)E31-N004A. B 1(2_)E31-N005A. B 1(2)E31-N006A. B 1(.2) E31-N024A. B 1(2_)E31-N025A. B 1(2)E31-N026A.B 1(2)E31-N602A. B i _1(2)E31-N603A.B-1(2_)E31-N612A. B 1(2)E31-N613A
.8 Compt Type TE TE TE TE TE TE TS TS TS TS CALCULATION TITLE PAGE DOCUMENT NUMBERS: Doc Type/Sub Type Document Number Exhibit C NEP-12-02 Revision 5 DESCRIPTION CODE: 103 (Setg_oint/Settingss/Margin)
DISCIPLINE CODE: I (Instrumentation)
SYSTEM CODE: E31 COMMONWEALTH EDISON COMPANY CALCULATION REVISION PAGE Exhibit C NEP-12-02 Revision 5 CALCULATION NO. NED-I-EIC-0213 PAGE NO.: 2 of 37 REVISION SU NEW AREES REV: 0 REVISION
 
==SUMMARY==
: Initial Issue ELECTRONIC CALCULATION DATA FILES REVISED: (Program Name, Version, File name extlsizeldate/hour. min) Word Perfect 6.1 File Name: LS0213.6R0/208KB/II-10-97/3
:09pm PREPARED BY: ' .- , 11 - )- DATE: o Print/S' REVIEWED BY: J ~ ~ ul ~ ~AJJ Ot~5 ) DATE: 11-l0-g 1 Type of Review  Detailed o Alternate o Test DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION o YES  NO Tracked by: REV: REVISION
 
==SUMMARY==
: ELECTRONIC CALCULATION DATA FILES REVISED: (Program Name, Version, File name cu/size/date/hour-. min) PREPARED BY: DATE: Print/Sign REVIEWE D BY: DATE: Print/Si Type of Review o Detailed o Alternate o Test DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION o YES o NO Tracked by:
Exhibit D NEP-12-02 Revision 5 COMMONWEALTH EDISON COMPANY CALCULATION TABLE OF CONTENTS I TITLE PAGE CALCULATION NO.
NED-I-EIC-02 I3 DESCRIPTION CALGULATlON SECTION 1.0 PURPOSE and OBJECTIVE I SECTION 2.0 METHODOLOGY aal ACCEPTANCE CRlTERIA REV. NO. 0 PAGE NO. 1 SECTION
 
==3.0 REFERENCES==
 
PAGE NO. 3 OF 37 SUB-PAGE NO. 1 SECTION 4.0 DESIGN INPUTS I SECTION 5.0 ASSUMPTIONS I SECTION 6.0 INSTRUMENT CHANNEL CONFIGURATION ECTION 7.0 PROCESS PARAMETERS I SECTION 8.0 LaOP ELEMENT DATA I SECTION 9.0 CALLBRATION INSTRUMENT DATA I SECTION 10.0 CALIBRATION PROCEDURE DATA / SECTION 11.0 MODULE ERRORS - THERMOCOWLE I SECTION 12.0 MODULE ERRORS - TEMPERATURE SWITCH I SECTION 13.0 INSTRUMENT CHANNEL TOTAL ERROR ( SECTION 14.0 ERROR ANALYSIS SECTION 15.0 ERROR ANALYSIS
 
==SUMMARY==
 
& CONCLUSIONS ATTACHMENTS I A'ITACHMENT A ASTh4, American National Standard C96.2-1973, "Standard Temperature - Electromotive Force(J5MF)
Tables for Thermocouples" (2 pagea) I ATTACHMENT B COMED NDF LAS-ENDIT-0503, dated 10117197, "Analytical Limits for Leak Detection Instrumentation"(2 pages) ATTACHMENT C Transmation IS 1061 ntermocouple Calibrators Spec, Fluke 2190A Digital Thermometers Spec Sheets, and Fluke 8500A Digital Multimeter Resistive value Spec (10 pages) .ITACHMENT D Fluke and Phillips Company, Digital Thermometers (2190A), dated 1990 ' I Fluke Model 2190 ~pec Sheets", and M&TE calculation (5 pages)
TE-1 E31-NO04A, B TE-1E31-NO05A,B TE-1E31-NO06A,B TS-IE31-N602A,B TS-IE31-N603A,B TS-1 E31-N612A, B TS-IE31-N613A,B COMMONWEALTH EDISON COMPANY PURPOSE/OBJECTIVE OF CALCULATION The purpose of this calculation is to determine the margin between the Analytical Limit (AL) and the Calibrated Trip Setpoints (SPc), and the margin between the Allowable Value (AV) and the Calibrated Trip Setpoint, for the instrument loop channels that detect RCIC Equipment Area/Pipe Tunnel high ambient and differential temperature. These channels initiate an Outboard and Inboard Isolation Logic channel trip upon detection of high ambient or differential temperature in either the RCIC pipe routing area or the RCIC Equipment Area. The calculation is valid under normal operating and accident environmental conditions and allows for all normal operating and accident errors, for the following instruments
: TE-2E31-NO04A,B TE-2E31-NO05A, B TE-2E31-NO06A,B TS-2E31-N602A,B TS-2E31-N603A, B TS-2E31-N612A,B TS-2E31-N613A,B TE-IE31-NO24A,B TE-1E31-NO25A,B TE-1E31-NO26A,B TE-2E31-NO24A,B TE-2E31-NO25A, B TE-2E31-NO26A,B The methodology used herein is based on ComEd documents; References 3.2 and 3.3 with the following exception: The setting tolerance is assumed to describe the limits of the as-left component outputs. For a random error, this corresponds to 100% of the population and can be statistically represented by a 3a value. Per References 3.2 and 3.3, the "Setting Tolerance" (ST) is defined as a random error that is due to procedural allowances given to the technician performing the calibration. For this calculation
: ST = (Calibration Tolerance)/3 (1a] The following clarifications to the existing methodology in References 3.2 and 3.3 are applicable to this calculation
: Where values for error effects (such as drift, seismic, radiation, etc.) are not available in vendor specifications or from test results, industry experience with similar devices shall be considered prior to concluding that the effect is negligible. Exhibit E NEP-12-0: Revision .'
2.2.2 2.2.3 2.2.4 2.2.5 2.3 2.4 2.5 COMMONWEALTH EDISON COMPANY The standard methodology uses a 2o (standard deviation) criteria as the probability and confidence level for instrumentation, which corresponds to a 95% probability at a high confidence level. Published instrument vendor specifications are considered to be based on sufficiently large samples so that the probability and confidence level meets the 2o criteria. If specific information to the contrary is provided by the vendor, then the vendor information must be converted to a 2a value. Decimal precision is limited to either three decimal places or that necessary to prevent rounding errors in the conclusion. The final results are to be rounded to the number of decimal places appropriate for the calibration procedure. The only temperature induced M&TE errors evaluated are those specified by the manufacturer for a specific model number. This methodology uses the most conservative error evaluation by considering the full range of ambient temperature change as specified for the applicable EQ zone. Per Reference 3.21, the drift error is defined as a random, 2a error term, unless another design document or design input exists that defines the drift error for that specific component. Instrument errors are evaluated for normal and accident conditions. Random error standard deviations or sigma (a) values are noted in brackets [ j following the value. The symbols used herein will designate module number for the module errors, e.g. RA 1 represents reference accuracy error RA for Module 1 (see Figure 1). 2.6 Process errors are not considered in determination of the total error (TEn) normal conditions 2.7 As stated in Section 1.0, the objective of this calculation is to determine the available margin between the analytical limit and the calibration setpoint (SPc) for normal and accident conditions, and the available margin between the allowable value and the calibration setpoint (SPc) for normal and accident conditions. The acceptance criteria for this calculation is that there is positive margin between these values. Exhibit E NEP-12-0: Revision `.
3.3 3.5 3.9 3.10 COMMONWEALTH EDISON COMPANY ANSI/ISA-S67
.04-1994, "Setpoints for Nuclear Safety Related Instrumentation
." TID-E/I&C-20, "Basis for Analysis of Instrument Channel Setpoint Error & Loop Accuracy" dated 4/6/92. TID-E/I&C-10, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy", Rev. 0, dated 4/6/92. 3.4 LaSalle Station Procedures LIS-RI-103A (Rev. 2), "Unit 1 RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard Isolation Instrument Channel A Calibration", dated 03/31/97. LI - I-103B (Rev. 2), "Unit 1 RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Inboard Isolation Instrument Channel B Calibration", dated 03/3/97. LIS-RI-203A (Rev. 1), "Unit 2 RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard Isolation Instrument Channel A Calibration", dated 12/11/96. LIS-RI- 0 B (Rev. 2), "Unit 2 RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Inboard Isolation Instrument Channel B Calibration", dated 01/31/97. USalle Station UFSAR, Rev 11, Tables 3.11-7, 16, 24. 3.6 Riley Company, Instruction and Operating Manual, Model 86 Temp-Matic Thermocouple Monitor, Revision 1. 3.7 Commonwealth Edison Company Calculation No. NED-I-EIC-0255, "Measurement
& Test Equipment Accuracy Calculation For Use With CECo BWRs", Rev. 0, CHRON # 208597. 3.8 Commonwealth Edison Company Instrument Database, Specific and Supplemental Data Sheet for the following instruments
: TE-lE31-N004A,B TE-1E31-N005A,B TE-1E31-N006A,B TS-1 E31-N602A,B TS-IE31-N603A,B TS-IE31-N612A,B TS-1 E31-N613A, B Revision 000 TE-2E31-N004A,B TE-2E31-N005A,B TE-2E31-N006A,B TS-2E31-N602A,B TS-2E31-N603A,B TS-2E31-N612A,B TS-2E31-N613A,B TE-1E31-N024A,B TE-IE31-N025A,B TE-1 E31-N026A,B TE-2E31-N024A,B TE-2E31-N025A,B TE-2E31-N026A,B CECo Environmental Qualification Equipment Identification Binder, LaSalle Units 1 & 2, Project No. 6548/49-00, CQD File No. 017141, Rev. 05, Sheet D1 of D4, approval date 9/12/91. GE Data Sheet Drawing No. 145C3224, "Temperature Element", Rev. 2, dated 3/22/74. Rev. 0, Exhibit E NEP-12-t)
Revision 3.11 3.12 3.13 3.15 3.16 3.20 COMMONWEALTH EDISON COMPANY ASTM, American National Standard C96.2-1973, "Standard Temperature - Electromotive Force (EMF) Tables for Thermocouples". (Attachment A) Sargent & Lundy Report SL-4493, "Final Report on Insulation Resistance and Its Presumed Effects on Circuit Accuracy LaSalle County Station", dated October 12, 1988. Sargent & Lundy Calculation CID-MISC-O1, "Instrument Loop Evaluation for Parasitic Resistance", Rev. 0, dated 2/3/87. 3.14 Acton Environmental Testing Corporation Test Report No. 16436-82N, "Nuclear Qualification Testing of Temperature Measurement Devices Per IEEE Std. 323-1974 and IEEE Std. 344-1975", Revision 3, dated 1/31/84. LaSalle Station Unit I Technical Specifications, as amended through Amendment 117, and LaSalle Station Unit 2 Technical Specifications, as amended through Amendment 102, Section 4.3.2.1 and Table 4.3.2.1-1 items AAA through h. Transmation IS 1061 Thermocouple Calibrators Specification (fax dated 10/15/93), Fluke 2190A Digital Thermometers Specification Data Sheets (1990), and Fluke 8500A Digital Multimeter Resistive value Specification (fax dated 4/13/95) (Attachment C) 3.17 LaSalle County Station UFSAR, Rev. 11, Section 3.11.5, "Estimated Chemical and Radiation Environment", page 3.11-18. 3.18 LaSalle Station Drawings: 1E-1-4224AC , Schematic Diagram Leak Detection Sys. LD PT.3 Revision L, Dated 8/23/96 1E-1-4224AD , Schematic Diagram Leak Detection Sys. LD PTA Revision M, Dated 8/23/96 1E-1-4224 AE , Schematic Diagram Leak Detection Sys. LD PT.5 Revision D, Dated 10/21/96 1E-1-4224 AF , Schematic Diagram Leak Detection Sys. LD PT.6 Revision D, Dated 1/31/90 1E-1-4224AG , Schematic Diagram Leak Detection Sys. LD PT.7 Revision D, Dated 10/21/93 1E-1-4224AH , Schematic Diagram Leak Detection Sys. LD PT.8 Revision E, Dated 10/21/93 1 E-1-4224AM , Schematic Diagram Leak Detection Alarms Sys. LD PT. 12, Revision N, Dated 8/23/96 1E-2-4224AC , Schematic Diagram Leak Detection Sys. LD PT.3 Revision J, Dated 6/16/92 tE-2-4224AD , Schematic Diagram Leak Detection Sys. LD PTA Revision K, Dated 3/19/96 IE-2-4224AE , Schematic Diagram Leak Detection Sys. LD PT.5 Revision C, Dated 12/11/92 1E-2-4224AF , Schematic Diagram Leak Detection Sys. LD PT.6 Revision B, Dated 6/16/92 I_E-2-4224AG , Schematic Diagram Leak Detection Sys. LD PT.7 Revision C, Dated 12/11/92 1E-2-4224AH , Schematic Diagram Leak Detection Sys. LD PT.8 Revision D, Dated 12/11/92 1E-2-4224AM , Schematic Diagram Leak Detection Alarms Sys. LD PT. 12, Revision K, Dated 6/16/92 3.19 General Electric letter, K Utsumi to D. Eagan, "PanAlarm.DOC", dated 1/17/96, revised 1/24/96. Fluke and Phillips Company, Digital Thermometers (2190A), dated 1990 " Fluke Model 2190 specification cut Sheets", and M&TE calculation. (Attachment D) Exhibit E NEP-12-0: Revision 3.21 DG 97-001088, Reclassification of the drift errror term in the Corned Setpoint Accuracy Methodology, from Pete VandeVisse, dated 08125/97 3.22 COMED NDIT No. LAS-ENDIT-0503, Analytical Limits for ambient and differential temperature lek detection sensors in the RCIC pipe routing area and Equipment area, 10/17/97 (Attachment B) 4.0 4.3 4.4 DESIGN INPUTS COMMONWEALTH EDISON COMPANY Reference
 
===3.6 states===
that thermocouple extension wire has the identical conductor types as the thermocouple and the thermocouple head terminals. Therefore there is no emf drop or rise at the point of connection on the thermocouple. Per Reference 3.6, page 4, the operating influence of the Reference Junction Compensation will introduce an error of t3&deg;F. Basic Statistics
: A Modern Approach by Morris Hamburg, Published by Harcourt Bruce Jovanovich, Inc., 1974, provides Formula 3.7 for computing standard deviation (on page 64.) Per reference 3.22 the analytical limit for the RCIC Equipment Area and Pipe Tunnel Differential High Temperature is = 196 &deg;F 4T RCIC Equipment area AT RCIC Pipe Routing Area = 162 &deg;F 4.5 Per reference 3.22 the analytical limit for the RCIC Equipment Area and Pipe Tunnel Ambient High Temperature is 212&deg;F. Ambient T RCIC Equipment area = 294 &deg;F Ambient T RCIC Pipe Routing Area = 280 &deg;F 4.6 For a Type E thermocouple, the output span for 32&deg;F to 350&deg;F is 11.706 mV and for 0&deg;F to 150&deg;F is 5.411 mV, based on a reference junction temperature of 32&deg;F and Reference
 
===3.4. Because===
the installed reference junctions are not maintained at 32&deg;F, the actual thermocouple output will vary by a constant equal to the emf developed between 32&deg;F and the actual temperature of the reference junctions. Because the thermocouple output varies by a constant, the spans of 11.706 and 5.411 mV remains the same, and is used in this calculation. 5.0 ASSUMPTIONS
 
===5.1 Evaluation===
 
of M&TE errors is based on the assumption that the test equipment listed in Section 9.0 is used. Use of test equipment less accurate than that listed will require evaluation of the effect on calculation results. Exhibit E NEP-12-0 2 Revision 5 COMMONWEALTH EDISON COMPANY In accordance with Reference 3.7, it is assumed that the M&TE listed in Section 9.0 is calibrated to the required manufacturer's recommendations and within the manufacturer's required environmental conditions. As such, it is assumed that the calibration standard accuracy error of M&TE is negligible with respect to the other terms (STD =0). Per Reference 3.6, the Riley reference junction compensation circuit produces an equal but opposite compensating signal to the reference junction and introduces an Operating Influence Error over the range of normal operating temperatures. Per Reference 3.4, during calibration the thermocouple input at the reference junction is disabled. This action requires the calibration performer to measure the actual junction temperature and manually offset the junction compensator circuit such that the net millivolt calibration signal is correct for the desired measure junction temperature simulated. Error involved with the ability to measure reference junction temperature limits the precision of calibration. Per Design Input 4.3, using a configuration of a Fluke 2190A and type E thermocouple to measure reference junction temperature, the limit of error is t 3.092 &deg;F. As such, it is assumed that the Reference Junction Operating Influence Error of t 3.0 &deg;F is bounded by the error induced by the M&TE used to perform the reference junction temperature compensation during calibration. Temperature, radiation, and humidity errors, when available from the manufacturer, were evaluated with respect to the conditions specified in the LaSalle EQ zones. The EQ zone requirements for each instrument were obtained from the LaSalle EQ zone maps (Reference 3.5) . If these errors were not provided, the EQ zone conditions were analyzed to ensure that they were within the manufacturer specified operational conditions. If the environmental conditions were bounded, these error effects were considered to be negligible. Exhibit E NEP-12-0 2 Revision 5 
 
===6.0 INSTRUMENT===
 
CHANNEL CONFIGURATION COMMONWEALTH EDISON COMPANY Per Reference 3.18 and Figure 1 below, the RCIC equipment area and pipe tunnel ambient temperature instrument loop consists of a thermocouple temperature element TE-1(2)E31-N004A,B(N024A,B), thermocouple extension wire, and a temperature switch TS-1(2)E31-N602A,B(N612A,B). The RCIC equipment area and pipe tunnel differential temperature loop consists of two thermocouples TE-1(2)E31-N005A,B(N0025A,B) and TE-I(2)E3l-N006A,B(N0026A,B) each equipped with thermocouple extension wire, and then feeding a differential temperature switch TS-1(2)E31-N603A,B(N613A,B). The Instrument Loop initiates an Inboard or Outboard Isolation channel trip when the RCIC equipment area/pipe tunnel ambient temperature or differential temperature increases to the instrument setpoints. The loops are powered by an external power supply. The symbols used herein will designate module and figure for the module errors, e.g. RA In represents normal environment (n) reference accuracy error RA for Module 1. From Thermocouple (Module 1) TE-1(2)E31-N004A,B TE-1(2)E3l-N005A,B TE-1(2)E31-N006A,B Figure 7 TS-1(2)E3l-N602A,B TS-1(2)-N612A,B TS-1(2)E31-N603A,B TS-1(2)-N613A,B TE-1(2)E31-N024A,B TE-I (2)E3 I -N025A,B "FE-1(2)E31-14026A,13 Exhibit E NEP-12-02 Revision 5 
.5, 3.15, and TE-1(2)E31-NO04A,B TE-1(2)E31-NO24A,B TE-1(2)E31-NO05A,B TE-1(2)E31-NO25A,B TE-1(2)E31-N006A,B TE-1(2)E31-NO26A,B PYCO Model 102-9039-11-6 Thermocouple (Reference 3.9) Thermocouple Locations (Reference 3.8): Reactor Building Normal Operating Conditions for Environmental Zone H5A. (Reference 3.5) Temperature Pressure Radiation Relative Humidity COMMONWEALTH EDISON COMPANY 100'F-124"F
-0.4" W.G. 5 x 10 5 Rads (40-Year Dose) 20-29% Exhibit E NEP-12-0; Revision 7.0 PROCESS PARAMETER The following process conditions are based on pressures and temperatures from References 3.22. Temperature RCIC Equipment area (Max) 294 0 F Temperature RCIC Pipe Routing Area (Max) 280"F Pressure(Max) 40 PSIG for first 10 sec. Radiation 1 x IOE7 Rads (Integrated)
Relative Humidity Steam 8.0 LOOP ELEMENT DATA 8.1 Module 1, from Figure 1 (Reference 3.8) TE-1(2)E31-NO04A,B Local Mount EQ Zone H5A TE-1(2)E31-NO05A,B Local Mount EQ Zone H5A TE-1(2)E31-NO06A,B Local Mount EQ Zone H5A TE-1(2)E31-NO24A,B Local Mount EQ Zone H5B TE-1(2)E31-NO25A,B Local Mount EQ Zone H5B TE-1(2)E31-NO26A,B Local Mount EQ Zone H5B Per References 3.10, 3. 11 Thermocouple Type: Chromel-Const. (Type E) Temperature Range: 32&deg; to 600&deg;F Accuracy: t 3'F 8.1.1 Environmental Data for Thermocouple Location Normal Operating Conditions for Environmental Zone H5B. (Reference 3.5) Temperature Pressure Radiation Relative Humidity Accident Conditions for Environmental Zone H5A and Zone H5B. (Reference 3.5) Temperature Zone H5A Zone H5B Pressure Radiation Relative Humidity Module 2,from Figure 1 (Reference 3.8) TS-1(2)E31-N602A,B TS-1(2)E31-612A,B TS-1(2)E31-N603A,B TS-1(2)E31-613A,B From Reference
 
===3.6 unless===
otherwise noted, Drift (18 months) Temperature Limits: Line Voltage Effect: Normal Operating Voltage: Maximum loop Resistance
: Impedance: Setpoint Resolution COMMONWEALTH EDISON COMPANY 136"F-160&deg;F
-0.4" W. G. 5 x 10 5 Rads (40-Year Dose) 8-10.5% 100&deg;F-212&deg;F (per Reference 3.5) 100&deg;F-294&deg;F (per Reference 3.22) 136&deg;F-280&deg;F (per Reference 3.22) 40 PSIG for first 10 sec. 1 x 10' Rads (40-Year Dose) Steam Riley Model 86, Temp-Matic Thermocouple Monitor (Reference 3.8) Reference Accuracy : f 2 % of span (Reference 3.19) (includes Repeatability, Hysteresis, Sensitivity, and Conformity) t 2% of span (Reference 3.19) 14&deg; to 140&deg;F f 0.5% of span over range of normal operating voltages 120 VAC f 10% 5000 250 KU 0.25% of span Exhibit E NEP-12-02 Revision 5 
 
====8.2.1 Environmental====
 
Conditions (Reference 3.8) EQ Zone CIA Control Room Elevation 768 feet COMMONWEALTH EDISON COMPANY TS-1(2)E31-N602A located at 1(2)H13-P632 TS-1(2)E31-N603A located at 1(2)H13-P632 TS-1(2)E31-N612A located at 1(2)H13-P632 TS-1(2)E31-N613A located at 1(2)H13-P632 TS-1(2)E31-N602B located at TS-1(2)E31-N603B located at TS- 1(2)E31-N612B located at TS- 1(2)E31-N612B located at Temperature Pressure Radiation Relative Humidity 1(2)H 13-P642 1(2)H13-P642 1(2)H13-P642 1(2)H 13-P642 Normal Operating and Accident Conditions for Environmental Zone CIA. (Reference 3.5) 72"F-74&deg;F 0" to +0.25" W.G. 1 x 10 3 Rads (40-Year Dose) 35-45% Exhibit E NEP-12-02 Revision 5 Calculation NED-I-EIC-0255, Measurement and Test Equipment (M&TE) Accuracy Calculation For Use With CECo BWR(s), Reference 3.7, is used to provide the errors for the calibration instruments noted herein. The following list of calibration instruments are acceptable for use per LIS-RI-1(2)03A,B (Reference 3.4). The list provides the errors for these instruments from the above noted calculation. list also provides the evaluation parameters used in NED-I-EIC-0255. The loop(s) are calibrated according to LaSalle Unit 1(2), LIS RI-1(2)03A,B (Reference 3.4). The accuracy of the measurement and test equipment (M&TE) listed in LIS-RI-1(2)03A,B was evaluated in Section 9.0. The following M&TE device was chosen to determine the calibration error of the loop. 0 Digital Multimeter COMMONWEALTH EDISON COMPANY Fluke 8500A (5 '/2 Digit Resolution)
MTE = +/-0.004610 V (100 mVdc Range) Exhibit E NEP-12-02 Revision 5 The Calibration Instrument MTE Error f lal Evaluation Parameters Fluke 8500A (100mVdc)
+/-0.004610 mV Q 64.4-82.4'F, 20 mV 5 '/2 Digit Resolution Fluke 8500A (IOOmVdc)
+/-0.000906 mV 64.4-82.4'F, 20 mV 6 1/2 Digit Resolution High Ambient Temperature Switches 1(2)E31-N602A,B, and 1(2)E31-N612A,B (Reference 3.4) Calibrated Span: Setting Tolerance: Calibrated Setpoint (SPc): Allowable Range: Allowable Value (AV): Analytical Limit (AL): 1(2)E31-N602A,B 1(2)E31-N612A,B High Differential Temperature Switches COMMONWEALTH EDISON COMPANY 50&deg; to 350&deg;F +/-3&deg;F 192&deg;F (5.572 mVdc) 5.461 to 5.683 mVdc (+/-0.111 mVdc 206'F (6.092 m Vdc) 294&deg;F (Design Input 4.5) 280&deg;F (Design Input 4.5) 1(2)E31-N603A,B and 1(2)E31-N613A,B (Reference 3.4) Calibrated Span: 0&deg; to 150&deg;F AT Setting Tolerance: +/- 1.5)F Calibrated Setpoint (SPc): 108.5&deg;F (3.855 mVdc) Allowable Range: 3.799 to 3.910 mVdc (-0.056/+0.055 mVdc corresponds to +/-1.5&deg;F ) Allowable Value (AV): 1(2)-E31-N603A,B 126&deg;F (4.506 mVdc) 1(2)-E31-N613A,B 123&deg;F (4.393 mVdc) Analytical Limit: 1(2)E31-N603A,B 196&deg;F (Design Input 4.4) 1(2)E31-N613A,B 162&deg;F (Design Input 4.4) Hiah Ambient and Differential Switches Calibration Frequency: 3 months (Reference 3.15) Late Factor: 0.75 months corresponds to +/-3'F) Exhibit E NEP-'12-02 Revision 5 11.0 THERMOCOUPLE ERRORS MODULE 11 The thermocouple has an analog input and an analog output. Therefore, it is classified as an analog module. The following errors and equations given in this section are evaluated per References 3.2 and 3.3. Random Error, Normal Operating Conditions (o In) Thermocouple Reference Accuracy (RAln) The thermocouple Reference Accuracy is determined by direct application of the specifications listed in Section 8.1. [2a] Per Section 2.2.2, the specification for accuracy is a 2a value. = +/-(3.0'F/2) = t 1.5&deg;F 11.1.2 Thermocouple Calibration Error (CAL In) The existing Station Procedures do not calibrate the thermocouples. Therefore, CALIn = 0 11.1.3 Thermocouple Setting Tolerance Error (STIn) The thermocouples are not calibrated, therefore, RAIn RA1 nc,(,) 11.1.4 Drift Error (eD ln) STIn = 0 eDln = 0 COMMONWEALTH EDISON COMPANY = t 3.0&deg;F [la] A thermocouple is an electrical device that is formed by the welded junction of two dissimilar metals. The thermocouple generates a millivolt signal proportional to the junction temperature. As such, the thermocouple does not have a drift error term. Therefore, Exhibit E NEP-12-02 Revision 5 a0lln 0011%') COMMONWEALTH EDISON COMPANY 11.1.5 Operating Influence of the Reference Junction Compensation (a0I ln) Per Design Input 4.1, the thermocouple extension wires consist of the same material as the thermocouple itself, and therefore, the emf rise or drop across the thermocouple head terminals is considered negligible. However, per Assumption
 
===5.3 there===
is an error from the reference junction compensation that results in an error of +/-3.092&deg;F. Therefore, = +/- 3.092 &deg; F Per Section 2.2.2 the reference junction compensation is a 2a value. _ +/- 3.092 &deg;F / 2 _ +/- 1.546&deg;F 11.1.6 Random Input Errors (o 1 inn) The thermocouple is the first module in the loop. a Jinn 0 11.1.7 Calculation of Thermocouple Random Error (aIn) aln = +/-[(RAln)2 + (CALln)2 + (STln)2 + (eDln)2 + (alinn)2 + ((3011n)211rz
= +/-[(1.5&deg;F)' + (0)2 + (0)2 + (0)2 + (0)2 + (1.546 &deg; FA112 = +/- 2.154&deg;F 11.2 Random Error, Accident Conditions (ala) ala = a In = +/- 2.154&deg;F Therefore: [20] [1a] For the purpose of this calculation, the random error determined for normal operating conditions (Section 11.1.7) is the same error that would occur during accident conditions since random errors are not dependent on the environmental conditions. Exhibit E NEP-12-02 Revision 5 11.3 Non-Random Errors Normal Operating Conditions (Eeln) 11.3.1 The thermocouples are passive devices which produce a millivolt signal proportional to temperature. As such, they are not affected by the following non-random errors: 11.3.2 Humidity Errors: Radiation Errors: Seismic Errors: Static Pressure Effects: Ambient Pressure Errors: Power Supply Effects: Temperature Error (eT 1 n) The thermocouples are designed to exhibit a precise temperature effect, which is used to develop the signal provided to the loop. Since the thermocouples are designed to function in temperatures well above the system design temperature, there is no temperature effect error. Therefore, eTln = 0 11.3.3 Insulation Resistance Error (eIRln) Per Reference 3.12, page 2-2, there are no terminal blocks in 100% relative humidity areas. References 3.12 and 3.13 state that insulation resistance error for thermocouples is negligible, therefore, eIR l n = 0 11.3.4 Process Error (epln) Per Section 2.6 process error is not applicable to the normal operating conditions. Therefore, epln 11.3.5 Input Errors (elinn) =0 The thermocouple is the first module in the loop. Therefore, elinn = 0 COMMONWEALTH EDISON COMPANY eHln = 0 eRln = 0 eSln = 0 eSPln = 0 ePln = 0 eVln = 0 11.3.6 Non-Random error for Normal Operating Conditions (Ee l n) Eeln = eHln + eRln + eSln + eSPln + ePln + eVln + eTln + eIRln + elpn + elinn =0+0+0+0+0+0+0+0+0+0
= t 0&deg;F Exhibit E NEP-120; Revision 11.4 Non-Random Errors Accident Conditions (Eela) 11.4.1 The thermocouples are passive devices which produce a millivolt signal proportional to temperature. As such, they are not affected by the following non-random errors: 11.4.2 11.4.3 Seismic Error (eSla) COMMONWEALTH EDISON COMPANY Per Reference 3.14, seismic testing was performed on selected Pyco thermocouple models.The tested units demonstrated consistent calibration readings both prior to and following seismic tests. Therefore, seismic error is considered negligible. Radiation Error (eRla) There are no radiation errors described in the Vendor's specification for the thermocouple. Per Reference 3.14, the equipment qualification radiation dose rate for the exposure of the instrument was 0.80 x 10 6 rads per hour for 276.4 hours, which resulted in a radiation dose of 2.2112 x 10 8 rads. Per Section 8.1. l, for accident conditions, a 40-year dose is 1 x 10' rads. The accident dose is bounded by the qualification test exposure and no unexpected deviation in output was observed during testing, therefore, per Assumption 5.4, radiation error is considered negligible. eRla = 0 11.4.4 Temperature Error (eT la) The thermocouples are designed to exhibit a precise temperature effect, which is used to develop the signal provided to the loop. Since the thermocouples are designed to function in temperatures well above the system design temperature, there is no temperature effect error, therefore, 11.4.5 Process Error (elpa) The thermocouples are designed to exhibit a precise temperature effect, which is used to develop the signal provided to the loop. Since the thermocouples are designed to function in temperatures well above the system design temperature there are no errors due to process changes. Therefore, epla =0 Exhibit E NEP-12-02 Revision 5 Humidity Errors: eHla = 0 Static Pressure Effects: eSPla = 0 Ambient Pressure Errors: ePla = 0 Power Supply Effects: eVla = 0 11.4.6 Input Errors (e lira) 12.0 The thermocouple is the first module in the loop. Therefore: elina = 0 11.4.7 Non-random error, Accident Operating Conditions Eela Ee la TEMPERATURE SWITCH ERRORS (MODULE 2) The temperature switch has an analog input and a discrete output. Therefore, it is classified as a bistable module. The following errors and equations given in this section are evaluated per References 3.2 and 3.3. 12.1 Random Error (o2n) 12.1.1 Reference Accuracy (RA2n) From Section 8.2, the vendor reference accuracy is f 2 % and includes the effects of repeatability, sensivity, hysteresis, and conformity. From Section 10.0, the calibrated spans are (350' - 50') = 300'F for the high temperature switches TS-1(2)E31-N602A,B andTS-1(2)E31-N612A,B and 150'F for the high differential temperature switches TS-1(2)E31-N603A,B and TS-1(2)E31-N613A,B. Therefore, RA2n is determined as follows: 1(2)E31-N602A.B, an 1(2)E31-N612A.B Similarly, l.(2)E31-N603A,.B, and 1(2)E31-N613A.B COMMONWEALTH EDISON COMPANY = eHla + eRla + eSla + eSPla + ePla + eVla + eTla + eIRla + epla + e lina =0+0+0+0+0+0+0+0+0+0
= t 0&deg;F = (Reference Accuracy % *Span) = (+/-0.02
* 300'F) = t 6'F [2o] _ (0.02
* 150"F) = f 3 &deg; F [2o] Exhibit E NEP-12-02 Revision 5 Per Section 2.2.2, reference accuracy is a 2o value, therefore: 12.1.2 Calibration Error (CAL2n) COMMONWEALTH EDISON COMPANY [la] Per Reference 3.4, the calibration procedure test setup applies a resistance decade box while measuring the voltage with a DMM temperature (voltage) at which the switch contact opens. The Calibration Error consists of the following errors: DMM Error (MTE) present at the switch input Calibration Standard Error (STD) 12.1.2.1 Measurement
& Test Equipment Error (MTE2) For conservatism, the DMM with the worst accuracy is used in the error determination. From Section 10.0 the worst case is the Fluke 8500A (5 'h digit resolution, 100mVdc range). MTE2 = t 0.004610 mV _ +/- 0.005 mVdc 12.1.2.2 Calibration Standard Error (STD2) The error due to calibration accuracy of calibration equipment is negligible (Assumption 5.2). Therefore, STD2 = 0 12.1.2.3 Determination of Calibration Error for RCIC pipe tunnel or equipment area High Temperature (CAL2n r) CAL2n T = [+/-(MTE2 2 + STD2)]1i2
= [+/-(0.005 mV)' + (0)2]'.z +/- 0.005 mV [lo] test voltage to the switch through a listed in Section 9.0, and recording the [1a] [lo] Exhibit E NEP-12-02 Revision 5 RA2 r(ia) _ +/- (6&deg;F)/2 _ +/- 3&deg;F Similarly, RA'araa) _ +/- (3&deg;F)/2 _ +/- 1.5&deg;F 12.1.2.4 Determination of Calibration Error for RCIC pipe tunnel/equipment area High Differential Temperature (CAL2, T) 12.1.3 CAL2n, T COMMONWEALTH EDISON COMPANY _ [+/-(MTE2 2 + STD2)]'/2
_ [+/-(0.005 MV)2+ (0)2]lt2 _ +/-0.005 mV Millivolts are converted to&deg;F using the tables given in the calibration procedure (Reference 3.4) and interpolating with a 1 &deg;F interval. Therefore, at the calibrated setpoint (SPc = 192&deg;F) CAL2n T = +/- 0.005 mVdc = +/-0.135 &deg;F Similarly, using the tables given in the calibration procedure (Reference 3.4) for the differential temperature switches and interpolating with a 1&deg;F interval, at the calibrated setpoint (Spc = 108.5&deg;F), CAL2n, T Setting Tolerance (ST2n) = +/- 0.005 mVdc = +/-0.137&deg;F Per data in Section 10.0, the setting tolerances for both switches at the point of interest are not equally negative and positive. For conservatism and to ease combining error terms, the greater of the two values for each switch will be considered as the setting tolerance. Therefore, Ntillivolts can be converted to&deg;F using the tables given in the calibration procedure (Reference 3.4). Therefore at the calibrated setpoint (SPc = 192&deg;F) ST2n r +/- 3 &deg;F [3a] Similarly, for the differential temperature switches (Spc = 108.5&deg;F) and, ST2n r +/- 0.111 mVdc [3o] Per Sec [la] [la] [la] r Exhibit 1~ NEP-12-02 Revision 5 ST2n, T = +/- 0.056 _ +/- 1.5 &deg;F [3o] [3o] ion 2.1, ST2 is considered a 3a value, therefore, ST2 = ST2/3 [la] ST2n T = +/- (3&deg;F)/3 = +/- 10F [lol ST2n, T = +/- (1.5`F)/3 = +/- 0.5&deg;F [la]
12.1.4 Temperature Switch Drift Error (eD2n) 12.1.5 e2Dn T eD2n, T Random Input Error (a2inn) 1ME31-N602A.B and 1(2)E31-N612A.B 1(2)E31-N603A,B and 1(2)E31_-N613A B COMMONWEALTH EDISON COMPANY Per Reference 3.21 drift is considered to be a random, 2a variable. Per Section 8.2 the value for drift is 2 % of span for 18 months. Per Section 10.0 a three month surveillance interval with 25% late factor is given per the calibration prodecure. For conservatism the vendor specification of 2% will be used with no extrapolation. Therefore, switch drift is calculated as follows: 1(2)E31-N602A,B and 1QE31-N612A
.$(e2D T l _ +/-2 % (span) _ +/-0.02*(300&deg;F)/2
=+/-3&deg;F 1(2)E31-N603A,B and 1(2)E31-N613A,B (e2D , T) = +/-2%(span)
= +/-0.02*(150&deg;F)/2
= +/- 1.500"F o2inn = al" = +/-oln o2inn = +/- 2.154&deg;F a2inn = +/- (a ln A 2 + o l n,)'-2 _ +/-[(2.154)2 + (2.154)2]"2
=+/-3.046&deg;F [2o] [la] [2a] [la] The random error present at the input to the switch is due to the thermocouple and was calculated in Section 11.1.7. The calculation of a I" is equivalent to the scaling conversion due to the linearity of the devices. The value for a 1 determined in Section 11.1.7 is provided in terms of the thermocouple output error. Therefore, The differential temperature switch is configured with two thermocouples connected "series-opposing". The random error present at the input to the switch is due to the total thermocouple error. Each thermocouple has the same thermocouple input error, as calculated in Section 11.1.7 (o In =+/-2.154&deg;F). Per Reference 3.3, the two random thermocouple errors that makeup the total random error present at the input to the switch can be combined statistically. Therefore; Exhibit E NEP-12-02 Revision 5 12.1.6 12.2 Determination of Total Random Errors (o2n) TS- 1(2)E31-N602A.B and TS- 1(2)E31_-N612A.B o2n T TS-1(2)E31-N603A,B and TS-1(2)E31-N613A.B o2M T Random Error, Accident Conditions (o2a) COMMONWEALTH EDISON COMPANY The temperature switch is located in a controlled environmental area such that Normal Operating Conditions and Accident Conditions are the same (Section 8.2.1). Therefore, for the purpose of this calculation, random error for normal and accident conditions are the same. 12.3 Non-Random Errors Normal Operating Conditions (Ee2n) 12.3.1 Humidity Error (e2Hn) The temperature switches are located in the Main Control Room which is a controlled environment (Section 8.2.1). Therefore humidity effects are considered negligible. e2Hn = t [(RA2n T)2 + (CAL2n T)2 + (ST2n T)2 +(eD2n)2 + (o2inn)2]'h
= t[(3&deg;F)2 + (0.135&deg;F)2 + (1&deg;F)2 + (3cF)2 + (2.154&deg;F)2]'h
= t 4.864&deg;F = t [(RA2n,T)2
+ (CAL2n, T)2 + (ST2n, T)2 + (eD2n, T)2 + (a2inn)j'h
= +/-[(1.500 0 F)2 + (0.137 c F)2 + (0.500"F)' + (1.500"F)2 + (3.046 &deg;F)21"' t 3.748&deg;F =0 Exhibit E NEP-12-02 Revision 5 12.2.1 Total Random Error (o2a) TS-1(2)E31_-N602A,B and TS-1_(2)E31_-N612A B o2a T = o2nT = t 4.760&deg;F TS-1_(2)E31-N603A,B and TS-1(2)E31_-N613A.B o2a, T =a2n, T = f 3.748&deg;F 12.3.2 Temperature Error (e2Tn) 12.3.4 Seismic Error (e2Sn) COMMONWEALTH EDISON COMPANY The Vendor does not provide a temperature effect specification. However, the operating temperature limits for the switch are from 14"F to 140&deg;F. The normal operating ambient temperature at the switch location is 72&deg;F-74&deg;F (Section 8.2.1). Therefore, per Assumption 5.4, the ambient temperature is bounded by the switch operating temperature limits. e2Tn = 0 12.3.3 Radiation Error (e2Rn) The temperature switches are located in the Main Control Room which is a controlled environment (Section 8.2.1). Therefore radiation effects are considered negligible . e2Rn =0 A seismic event defines a particular type of accident condition. Errors included on the instrument due to seismic vibrations are defined only for accident conditions and therefore, are not applicable during normal plant conditions. e2Sn = 0 12.3.5 Static Pressure Offset (e2SPn) The temperature switch is an electrical device and as such is not affected by static pressure. Therefore, e2SPn = 0 12.3.6 Pressure Error (e2Pn) The temperature switch is an electrical device and as such is not affected by ambient pressure. Therefore, e2Pn = 0 12.3.7 Process Error (e2pn) Per Section 2.6, this calculation does not consider process error applicable to the normal operating conditions. Therefore, e2pn =0 Exhibit E NEP-12-02 Revision 5 12.3.8 12.3.9 Power Supply Effects (e2Vn) Per Section 8.2, the power supply effects are 1(2)E31-N602A,B and 1 2)E31-N612A,B e2Vn,. 112,)E31 N603A,B and I2)F3I-N613A.B e2Vn, T Insulation Resistance Error (e2lRn) Insulation resistance effect is only applicable to components of the instrument signal transmission system (i.e. cable, splices, connectors, etc.). Per Reference 3.12 and 3.13, insulation resistance is negligible with respect to other error terms. Therefore, e21Rn = 0 12.3.10 Non-Random Input Error (e2inn) COMMONWEALTH EDISON COMPANY = t (0.5 % *span) = +/-(0.005
* 3000F) _ +/- 1.500&deg;F = +/-(0.5% *span) = +/-(0.005
* 150"F) = t 0.750&deg;F as follows: The non-random input error is calculated in Section 11.3.5, and is as follows: e2inn = eln = 0 12.3.11 Total Non-Random Error Normal Operating Conditions (Ee2n) Ee2n = t (e2Hn + e2Tn + e2Rn + e2Sn + e2SPn + e2Pn + e2pn + e2Vn + e2lRn + e2inn) 1(2)E31-N602A,B and 1(2)E31-N612A.B Ee2n T t(0+0+0+0+0+0+0+
1.500&deg;F+0 +0) = f 1.500&deg;F 1(2)E31-N603A,B and 1(2)E31-N613A.B Ee2n, T f(0+0+0+0+0+0+0+0
.750&deg;F+0 +0) = t 0.750'-F Exhibit E NEP-12-02 Revision 5 12.4 12.4.1 12.4.2 12.4.3 Non-Random Error, Accident Conditions (Ee2a) Humidity Error (e2Ha) The temperature switches are located in the Main Control Room which is a (Section 8.2.1). Therefore humidity effects are considered negligible . e2Ha = 0 Temperature Error (e2Ta) The Vendor does not provide a temperature effect specification. However, the operating temperature limits for the switch are from 14&deg;F to 140&deg;F. The operating ambient temperature at the switch location is 72&deg;F-74&deg;F (Section 8.2.1). Therefore, per Assumption 5.4, e2Ta Radiation Error (e2Ra) e2Ra 12.4.4 Seismic Error (e2Sa) COMMONWEALTH EDISON COMPANY =0 controlled environment The temperature switches are located in the Main Control Room which is a controlled environment (Section 8.2.1). Therefore radiation effects are considered negligible . =0 The switch is seismically qualified and no vendor specification's are given due to a seismic event (Reference 3.9). Therefore, e2Sa = 0 12.4.5 Static Pressure Offset (e2SPa) The temperature switch is an electrical device and as such is not affected by static pressure. Therefore, e2SPa = 0 12.4.6 Pressure Error (e2Pa) The temperature switch is an electrical device and as such is not affected by ambient pressure. Therefore, e2Pa = 0 Exhibit E NEP-12-02 Revision 5 12.4.7 12.4.8 Process Error (e2pa) Per Section 8.2.1, the temperature switch is located in a controlled environment and not directly connected to the process, hence, it is not affected by induced error from the physical properties of the process. Therefore, e2pa Power Supply Effects (e2Va) Per Section 8.2, the power supply effects are as follows: 1(2)E31-N602A,B and 1(2)E31-N612A.B e2Va T 1(2)E31-N603A.B and 1(2)E31-N613A B e2Va, T t [0.5 % span] = t [0.005
* 150&deg;F] = t 0.750&deg;F 12.4.9 Insulation Resistance Error (e21Ra) Insulation resistance effect is only applicable to components of the instrument signal transmission system (i.e. cable, splices, connectors, etc.). Per Reference 3.12 and 3.13, insulation resistance is negligible with respect to other error terms. Therefore, e21Ra = 0 COMMONWEALTH EDISON COMPANY 0 = +/-[0.5% span] = t[0.005
* 300&deg;F] = f 1.500&deg;F 12.4.10 Non-Random Input Error (e2ina) The non-random input error for accident conditions is calculated in Section 11.4.6. e2ina = ela = 0 Exhibit E NEP-12-02 Revision 5 12.4.11 Total Non-Random Error Accident Operating Conditions (Ee2a) Ze2a 1(2)E31-N602A.B and 1 2)E31-N612A.B Ee2a T 1(2)E31-N603A.B and 1(2)E31-N613A.B COMMONWEALTH EDISON COMPANY = +/-(e2Ha + e2Ta + e2Ra + e2Sa + e2SPa + e2Pa + e2pa + e2Va + e21Ra + e2ina) =+/-(0+0+0+0+0+0+0+
1.500&deg;F+0+0)
=+/- 1.500&deg;F Ee2a T
.750&deg;F+0 +0) = +/-0.750&deg;F Exhibit E NEP-12-02 Revision 5 COMMONWEALTH EDISON COMPANY 13.0 TOTAL ERROR NORMAL OPERATING AND ACCIDENT CONDITIONS (TE) Per References 3.2 and 3.3 the total error is determined as follows: = 2*(o2) + Ee2 Total Error, Normal Operating Conditions (TE2n) High TemWratnre Switches - TS-1(2)E31-N602A,B and TS-1(2)E31-N612A.B From Section 12.1.6, o2n r = t 4.864&deg;F From Section 12.3. 11, Ee2n T = f 1.500&deg;F 13.1 TEn, TE = t (2
* 4.76&deg;F) t 1.500&deg;F = f 11.228&deg;F High Differential Temperature Switches - TS-1(2)E31-N603A,B and TS-1(2)E31-N613A.B From Section 12.1.6, o2n.T = f 3.748&deg;F From Section 12.3. 11, Ee2n, T = f 0.750&deg;F TEn.T f (2
* 3.748'F) f 0.750'F = t 8.246 &deg; F 13.2 Total Error, Accident Operating Conditions (TE2a) From Section 12.2.1, o2a T = +/- 4.864` F From Section 12.4. 11, Ee2a T = f 1.500&deg;F High_ Temperature Switches - TS-1(2)E31-N602A,B and TS-1(2)E31-N612A,,B TEa, = +/- (2
* 4.864&deg;F) t 1.500&deg;F _ + 11.228&deg;F Exhibit E N EP-12-02 Revision 5 High Differential Temperature Switches - TS-1(2)E31-N603A,B and TS-1(2)E31-N613A.B From Section 12.2.1, o2a, T = t 3.748'F Ee2a, T = f 0.750&deg;F = f (2
* 3.748&deg;F) f 0.750&deg;F = f 8.246&deg;F From Section 12.4. 11, TEa, T COMMONWEALTH EDISON COMPANY ERROR ANALYSIS Analytical Limit (AL), Limiting Condition of Operation (AV), and Calibrated Trip Setpoint (SPc) From Section 10.0, High Ambient Temperature Switches-TS-1(2)E31-N602A,B (EgWpment Area) AV(Tech Spec LCO T) SPc <_ 206&deg;F = 294&deg;F = 192&deg;F High Ambient Temperature Switches-TS- 1QE31-N612A,B (FiM Routing Area) AV(Tech Spec LCO T) s 206&deg;F AL,. = 280&deg;F SPc = 192&deg;F High Differential Temperature Switch-TS-1(2)E31-N603A.B (EgWpment Area) AV(Teeh Spec LCO, T) - 126&deg;F AL, T 196 &deg; F = 108.5&deg;F SPc Exhibit E NEP-12-02 Revision 5 High Differential_
Temperature Switch-TS-1(2)E31-N613A,B (PipQRouting Area) AV(Tech Spec LCO~T) s 123&deg;F = 162&deg;F = 108.5&deg;F SPc Determination of Margin (MARn) between Allowable Value (AV) and Calibrated Trip Setpoint (SPc) Per Reference 3.3, the margin can be determined by adding the calculated TEn to the SPc. Therefore, for an increasing process the margin is determined by: MARn 14.2.1 Margin Value for RCIC Equipment Area /Pipe Tunnel Ambient Temperature Trip Setpoint Temperature Switches -TS-1(2)E31-N602A,B and TS-1(2)E31-N612A.B From data in Section 14.1, SPc =192&deg;F AV T 206&deg;F COMMONWEALTH EDISON COMPANY = AV - (SPc + TEn+) From data in Sections 13.1, total error is: TEn T t 11.228'F Therefore, MARn T AV T - (SPc.,. + TEnT) = 206&deg;F - (192 &deg;F + 11.228&deg;F) = 2.772 &deg;F 14.2.2 Margin Value for RCIC Equipment Area/Pipe Tunnel Differential Temperature Trip Setpoint RCIC Equipment Area Differential Temperature Switches - 1(2)E31-N603A.B From data in Section 14.1, Exhibit E N EP-12-02 Revision 5 SPC, T AV, T Therefore, MAR n e T From data in Section 14.1, Therefore, neT SPe, T AV, T From data in Sections 13.1, COMMONWEALTH EDISON COMPANY = 108.5&deg;F ;126&deg;F From data in Sections 13.1, total error is as follows: = f 8.246&deg;F = AV, T - (SPC, T + TEn,T) = 126&deg;F -(108.5&deg;F + 8.246&deg;F) = 9.254&deg;F R_ c'IG Pine Tunnel Differential Temperature Switches - 1(2)E31-N613A B = 108.5&deg;F s 123&deg;F TEn.T f 8.246 &deg; F MARn,T =AV, T - (SPC, T + TEn,T) = 123&deg;F - (108.5&deg;F +8.246 9 F) = 6.254&deg;F Exhibit E NEP-12-02 Revision 5 SPc T AL T From data in Section 10.0, SPc T 192&deg;F AL T 280&deg;F COMMONWEALTH EDISON COMPANY Determination of Margin (MARa) Between Analytical Limit (AL) and Calibrated Trip Setpoint SPc Per Reference 3.3, the margin can be determined by adding the calculated TEa to the SPc. Therefore, an increasing process the margin is determined by: = AL - (SPc + TEa+) Margin Value for RCIC Equipment Area /Pipe Tunnel Ambient Temperature Trip Setpoint RCIC Equipment Area Tempraturre Switches-TS-1(2)E31-N602A.B = 192&deg;F = 294&deg;F From data in Sections 13.2, total error is as follows: TEa T t 11.228&deg;F Therefore, from Reference 3.3, the margin (MARa) for actuation on increasing process parameter is given as, MARa T AL T - (SPc + TFAT+) = 294&deg;F - (192&deg;F + 11.228&deg;F) = +90.772&deg;F $(_IC PiM Routing Area Temperature Switches-TS-1(2)E31-N612A.B From data in Sections 13.2, total error is as follows: Therefore, from Reference 3.3, the margin (MARa) for actuation on increasing process parameter is given as, MARa T AL T - (SPc + TEaT+) = 280&deg;F -(192&deg;F + 11.228&deg;F) = +76.772 0 F Exhibit E NEP-12-02 Revision 5 for Margin Between Analytical Limit and RCIC equipment area/pipe tunnel Differential Temperature Trip Setpoint R I Equipment Area Differential Tem ra it 2)E31-N603A.B From data in Section 10.0, SPc, T ALaT From data in Sections 13.2, total error is as follows: TEa, T Therefore, MARa, T RCIC Pipe Tunnel Differential Temperature 1(2)E31-N613A.B From data in Section 10.0, Therefore, SPC, T AL, T TEa, T COMMONWEALTH EDISON COMPANY = 108.5&deg;F = 196&deg;F = t 8.246&deg;F = AL, T - (SPC, T + TEa,T+) = 196&deg;F - (108.5&deg;F + 8.246&deg;F) = 79.254&deg;F = 108.5&deg;F = 162&deg;F From data in Sections 13.2, total error is as follows: = t 8.246&deg;F MARa, T AL, T - (SPC~T + TEa,T+) = 162&deg;F - (108.5&deg;F +8.246&deg;F) = 45.254&deg;F Exhibit E NEP-12-02 Revision 5 15.0 ERROR ANALYSIS
 
==SUMMARY==
& CONCLUSIONS 15.1 Error Analysis Summary The calculation demonstrates that for the instrument loops that isolate the RCIC Equipment Area/Pipe Tunnel Inboard and Outboard Isolation valves, the following margins exist: For the RCIC EQWpment Area/Pipe Tunnel High Ambient Temperature Loops For 1(2)E31-602A.B Between the Analytical Limit and the Calibrated Trip Setpoint (Section 14.3.1): Between the Allowable Value and the Calibrated Trip Setpoint (Section 14.2.1): For 1(2)E31-612A.B COMMONWEALTH EDISON COMPANY Positive 90.772&deg;F Positive 2.772&deg;F Between the Analytical-4L rflit and the Calibrated Trip Setpoint (Section 14.3.1): Positive 76.772&deg;F Between the Allowable Value and the Calibrated Trip Setpoint (Section 14.2.1): Positive 2.772&deg;F Exhibit E NEP-12-02 Revision 5 COMMONWEALTH EDISON COMPANY For the RCIC E lipment Area/Pine Tunnel Differential Temneraturre Loops For 1(2)E31-603A.B Between the Analytical Limit and the Calibrated Trip Setpoint (Section 14.3.2): Between the Allowable Value and the Calibrated Trip Setpoint (Section 14.2.2): For 1(2)E31_-613A.B Between the Analytical Limit and the Calibrated Trip Setpoint (Section 14.3.2): Between the Allowable Value and the Calibrated Trip Setpoint (Section 14.2.2): 15.2 Conclusions Positive 79.254&deg;F Positive 9,254'F Positive 45.254&deg;F Positive 6.254&deg;F Per Section 2.7 this calculation indicates that a positive margin exists between the analytical limit and the calibration setpoint, and the allowable value and the calibration setpoint. Therefore, the Acceptance Criteria has been met as stated in Section 2.7. This analysis is for normal operating and accident conditions, when the switches are calibrated per Reference 3.4, with the M&TE specified in Section 10.0. Note - Section 8.2 lists the high temperature limits from the UFSAR (Reference 3.5) and NDIT No. LAS-ENDIT-0503 (Reference 3.22). All calculations were done using the NDIT temperature limits. Exhibit E NEP-12-(12 Revision 5 ATTACHMENT 2b LaSalle County Station Engineering Calculation NED-I-EIC-0213, Revision 1G "Derived Technical Specification Allowable Values for the Instrument Loop Channels that detect RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature based on Corrected Values for Analytical Limits" NED-I-EIC-0213, Revision 1 G Derived Technical Specification Allowable Values for the Instrument Loop Channels that detect RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature based on Corrected Values for Analytical Limits ATTACHMENT 2 Design Analysis Minor Revision Cover Sheet P age 1 of 1 CC-AA-309-1001 Revision 1 Last Page No. 10 Analysis No. NED-I-EIC-0213 Revision 001G EC/ECR No. 355600 Revision 000 Title: RCIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard and Inboard Isolation Error Analysis. Station(s)
LaSalle Is this Design Analysis Safeguards?
Yes F] No 0041 Unit No.: 1 and 2 Does this Design Analysis Contain Unverified Assumptions?
Yes E] No OV Safety Class SR System Code E31 ATI/AR# N/A Description of Change Minor Revision 001 G updates the allowable values based on corrected design input for Analytical Limits. Disposition of Changes (include additional pages as required)
New Technical Specification Allowable Values were calculated based on revised design input (Analytical Values) from Calculation L-001324. This design analysis does not supersede any other design analysis. Preparer T. J. Van Wyk , . ), NOr .5 ~d OS Print Name ~~ ~~1m Da Reviewer R. A. Fredricksen
~/ Print Name -~ Sign Name Date Method of Review 041 Detailed Review E7 Alternate Calculations E] Testing Review Notes: Approver 8MON A, CsINT"ER 2r Print Name Sign Name Date (For External Analyses Only) Exelon Revi ewer Print Name Sign Name Date Approver Print Name Sign Name Date CALCULATION TABLE OF CONTENTS CALCULATION NO. NED-I-EIC-0213 REV. N O. OOIG PAGE NO. 2 SECTION: PAGE NO. SUB-PAGE NO. TABLE OF CONTENTS 2 NA 1.0 PURPOSE / OBJECTIVE 3 NA 2.0 METHODOLOGY AND ACCEPTANCE CRITERIA N/A NA 3.0 ASSUMPTIONS
/ ENGINEERING JUDGEMENTS N/A NA 4.0 DESIGN INPUT N/A NA
 
==5.0 REFERENCES==
 
N/A NA 6.0 CALCULATIONS 3-10 NA 7.0
 
==SUMMARY==
AND CONCLUSIONS NIA NA 8.0 ATTACHMENTS N/A NA Purvose/Obiective CALCULATION PAGE CALCULATION NO. NED-I-EIC-0213 REVISION NO. OOIG PAGE NO. 3 of 10 J The purpose of this minor revision is to derive Technical Specification Allowable Values for the Instrument loop channels that detect RCIC Equipment AreaJPipe Tunnel high ambient and differential temperature based on corrected values for the Analytical Limits. This minor revision also verifies that the current instrument setpoints for isolation are still conservative with respect to the new Allowable Values. [Note: The Electrical/I&C Design Engineering Supervisor approved using a minor revision for revision of this calculation (required per CC-AA-309 because there are already five minor revisions against the base calculation)
.] Calculations Detailed description of changes to NED-I-EIC-0213
[as revised previously by DCRs 990760 (Minor Rev. 1 C), 991048 (Minor Rev. 1 D), 992055 (Minor Rev. 1 E), 992089 (Minor Rev. 1 F), and Minor Rev. IA)]: 1. _Replace Reference 3.22 with the fo llowing: 3.22 Calculation L-001324, Rev. 005A, "Area Ambient and Differential Temp. Design Basis Calc for Reactor Coolant Leak Detection." 2. Replace Design_ Input 4.4 with the following: 4.4 Per reference 3.22, the analytical limit for the RCIC Equipment Area and Pipe Tunnel Differential High Temperature is: AT RCIC Equipment Area = 195.6 &deg;F AT RCIC Pipe Routing Area = 170.5 &deg;F 3. Replace Design Input 4.5 with the following: 4.5 Per reference 3.22, the analytical limit for the RCIC Equipment Area and Pipe Tunnel Ambient High Temperature is: Ambient T RCIC Equipment Area Ambient T RCIC Pipe Routing Area 299.6 &deg;F 270.5 &deg;F CALCULATION PAGE CALCULATION NO. NED-I-EIC-0213 REVISION NO. OOIG PAGE NO. 4 of 10 4. Revise Section 8.1.1 as follows: In the "Accident Conditions for Environmental Zone H5A and Zone H5B" section, revise the Temperatures listed from Reference 3.22 to read: Zone H5A 100&deg;F - 299.6&deg;F Zone H513 136 0 F - 270.50F 5. In Section 10.0, revise the Analytical Limits as follows: (For the High Ambient Temperature Switches the new analytical limits are): Analytical Limit (AL): 1(2)E31-N602A, B (Now 1(2)E31-ROOK, 2C, Ch. 5) 299.6 &deg;F (Design Input 4.5) 1(2)E31-N612A, B (Now 1(2)E31-ROO I C, 2C, Ch. 9) 270.5 &deg;F (Design Input 4.5) (For the High Differential Temperature Switches the new analytical limits are): Analytical Limit (AL): 1(2)E31-N603A, B (Now 1(2)E31-ROOK, 2C, Ch. 7) 195.6 &deg;F (Design Input 4.4) 1(2)E31-N613A, B (Now 1(2)E31-ROOK, 2C, Ch. 11) 170.5'F (Design Input 4.4) 6. In Section 14.0, r evise the Ana lyti ca l Lim its as follows: High Ambient Temperature Switches - TS-1(2)E31-N602A, B (Equipment Area) (Now Recorder 1(2)E31-ROOI C, 2C, Channel 5) AL T = 299.6&deg;F High Ambient Temperature Switches - TS- 1(2)E31-N612A, B (Pipe Routing Area) (Now Recorder 1(2)E31-ROOK, 2C, Channel 9) AL T = 270.5&deg;F High Differential Temperature Switch -TS-1(2)E31-N603A, B (EQuipment Area) (Now Recorder 1(2)E31-ROOK, 2C, Channel 7) AL A T = 195.6&deg;F C r ALCULATION NO. NED-I-EIC-0213 REVISION NO. 001G PAGE NO. 5 of 10 7 J High Differential Temperature Switch - TS-1 (2)E31-N613A. B (Pipe Routing Area) (Now Recorder 1(2)E31-ROOK, 2C, Channel 11) AL A T = 170.5&deg;F 7. Replace Sections 14.2.1, 14.2.2, 14.2.3, and 14.2.4 with the followine: (Incorporates all changes from previous outstanding minor revisions to this calculation) 14.2.1 RCIC Equipment Area Ambient Temperature Trip (was Switches 1(2)E31-N602A, B, now Recorder 1(2)E31-R001 C, & 2C, Ch. 5) The calibrated setpoint requirement is computed as follows: SPc <_ AL - TEaT24M <_ 299.6&deg;F - 11.244&deg;F _< 288.3567 Since the existing calibrated setpoint of 1927 meets this requirement with 96.3567 margin, this value will be retained for the ITS / 24 Month Cycle Extension Project. SPc = 192.0&deg;F The Allowable Value is computed using the calculated setpoint requirement as follows: CALCULATION PAGE SPc + DTIc 288.356&deg;F + 8.739&deg;F 297.095&deg;F or S 297 0 F Per Reference 3.24, the Expanded Tolerance for these switches is determined, based on the following equation. ET =[0.7*(AV-NTSP-ST)]
+ ST ST = 3.0&deg;F [12.1.3] ET = [ 0.7 * (297.095 - 288.356 - 3.0) ] + 3.0&deg;F = 7.0173&deg;F or +/- 7&deg;F CALCULATION PAGE CALCULATION NO. NED-I-EIC-0213 REVISION NO. OOIG PAGE NO. 6 of 10 1 The Expanded Tolerance for calibration is determined to be ET = +/- 7 &deg;F 14.2.2 RCIC Pipe Tunnel Ambient Temperature Trip (was Switches 1(2)E31-N612A, B, now Recorder 1(2)E31-ROOI C, & 2C, Ch. 9) The calibrated setpoint requirement is computed as follows: SPc <- AL - TEaT24M < 270.5&deg;F - 11.244&deg;F <_ 259.256&deg;F Since the existing calibrated setpoint of 192&deg;F meets this requirement with 67.256&deg;F margin, this value will be retained for the ITS / 24 Month Cycle Extension Project. SPc = 192.0&deg;F The Allowable Value is computed using the calculated setpoint requirement as follows: AV <- SPc + DTIc S 259.256&deg;F + 8.739&deg;F <_ 267.995&deg;F or 5 267&deg;F Per Reference 3.24, the Expanded Tolerance for these switches is determined, based on the following equation. ET =[0.7*(AV-NTSP-ST)]
+ ST ST = 3.0&deg;F [12.1.3] ET = [ 0.7 * (267.995 - 259.256 - 3.0) ] + 3.0 &deg;F = 7.0173&deg;F or +/- 7&deg;F The Expanded Tolerance for calibration is determined to be ET = +/- 7 &deg;F CALCULATION PAGE [CALCULATION NO. NED-I-EIC-0213 REVISION NO. 001G PAGE NO. 7 of 10 14.2.3 RCIC Equipment Area Differential Temp. Trip (was Switches 1(2)E31-N603A, B, now Recorder 1(2)E31-R001 C, & 2C, Ch. 7) The calibrated setpoint requirement is computed as follows: SPc <_ AL - TE-T24M <_ 195.6&deg;F - 8.246&deg;F < 187.354&deg;F Since the existing calibrated setpoint of 108.5&deg;F meets this requirement with 78.854&deg;F margin, this value will be retained for the ITS / 24 Month Cycle Extension Project. SPc = 108.5&deg;F The Allowable Value is computed using the calculated setpoint requirement as follows: AV <_ SPc + DTIc <_ 187.354&deg;F + 1.398&deg;F < 188.752&deg;F or S 188&deg;F Per Reference 3.24, the Expanded Tolerance for these switches is determined, based on the following equation. ET =[0.7*(AV-NTSP-ST)]+ST ST = 1.5&deg;F [12.1.3] ET = [ 0.7 * (188.752 - 187.354 - 1.5) ] + 1.5&deg;F = 1.429&deg;F Since the expanded tolerance is within the setting tolerance, the Expanded Tolerance for calibration is determined to be the same as ST; therefore, ET - +/-1.5&deg;F CALCULATION PAGE CALCULATION NO. NED-I-EIC-0213 REVISION NO. 001G PAGE NO. 8 of 10 14.2.4 RCIC Pipe Tunnel Differential Temperature Trip (was Switches 1(2)E31-N613A, B, now Recorder 1(2)E31-ROOK, & 2C, Ch. 11) The calibrated setpoint requirement is computed as follows: SPc <_ AL - TeaAT 24M 5 170.5&deg;F - 8.246&deg;F <_ 162.254&deg;F Since the existing calibrated setpoint of 108.5&deg;F meets this requirement with 53.754&deg;F margin, this value will be retained for the ITS / 24 Month Cycle Extension Project. SPc = 108.5&deg;F The Allowable Value is computed using the calculated setpoint requirement as follows: AV S SPc + DTIc <_ 162.254&deg;F + 1.3987 <_ 163.652&deg;F or 5163&deg;F Per Reference 3.24, the Expanded Tolerance for these switches is determined, based on the following equation. Since the expanded tolerance is within the setting tolerance, the Expanded Tolerance for calibration is determined to be the same as ST; therefore, ET - +/- 1.5 &deg;F ET =[0.7*(AV-NTSP-ST)]+ST ST = 1.5&deg;F [12.1.3] ET =[0.7*(163.652-162.254-1.5)]+1.5&deg;F = 1.429&deg;F CALCULATION PAGE CALCULATION NO. NED-I-EIC-0213 REVISION NO. OO1G PAGE NO. 9 of 10 8. Replace S ections 15.1 and 15.2 with the following: 15.1 Error Analysis Summary This calculation has determined the following recommended calibration setpoints, Allowable Values, and Expanded Tolerances for use in the Improved Technical Specification
/ 24 Month Cycle Extension Project for the subject switches. These conclusions are derived for a nominal 24 month calibration interval (maximum of 30 months) for these switches. High Ambient Temperature Switches l(2)E3 1-N602A,B (RCIC Equipment Area) (Now Recorder 1(2)E31-ROOK, 2C, Channel 5) High Ambient Temperature Switches 1(2)E31-N612A,B (RCIC Pine Tunnel) (Now Recorder 1(2)E31-ROOK, 2C, Channel 9) High Differential Temperature Switches 1(2)E31-N603A,B (RCIC Equipment Area) (Now Recorder 1(2)E31-ROOK, 2C, Channel 7) High Differential Temperature Switches 1(2)E31-N613A B (RCIC Pipe Tunnel) (Now Recorder 1(2)E31-ROO I C, 2C, Channel 11) SP = 108.5&deg;F AV 5 163&deg;F ET = f 1.5&deg;F SP = 108.5&deg;F AV <_ 188&deg;F ET = +/- 1.5&deg;F SP = 192.0&deg;F AV _ 267&deg;F ET = +/- 7.O&deg;F SP = 192.0&deg;F AV 5 297&deg;F ET = +/- 7.0&deg;F CALCULATION PAGE CALCULATION NO. NED-I-EIC-0213 REVISION NO. 001G PAGE NO. 10 of 10 15.2 Conclusions Setpoints, Allowable Values and Expanded Tolerances are determined for the subject temperature switches as shown in Section 15.1. This analysis is for normal and accident conditions, when the switches are calibrated per Ref. 3.4, with the M&TE specified in Section 10.0. Note - Section 8.1.1 lists the high temperature limits from the UFSAR (Reference 3.5) and Calculation L-001324 (Reference 3.22). All calculations were done using the analytical limits from Reference 3.22.
ATTACHMENT 2c Exelon Nuclear Engineering Standard NES-EIC-20
.04, Revision 4 "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy" Revision 41 1 NES-E102104 ANALYSIS OF INSTRUMENT CHANNEL SETPOINT ERROR AND INSTRUMENT LOOP ACCURACY If this standard does not address your particular application, or is not appropriate to your application, contact the Engineering Administration group. Copyright Protected. Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) 2000. All rights reserved. Duplication and distribution of this document without the expressed written consent of Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) is prohibited. Rev Description Prepared Reviewed Approved No by by by Approved for use 10/23/ --R~Beavers W. Kurth R. Hall Latest Revision indicated by a bar in right hand margin. Braidwood, Byron, Dresden, Tile STANDARD NES-EIC-20
.04 LaSalle, and (Quad Cities - Analysis of Instrument Channel SetpWnt Error and Instrument Loop Sheet 1 of 22 Nuclear Engineering Standards Accuracy I I Revision 4 Braidwood, Byron, Dresden, Title STANDARD LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel '- Setpoint Error and Instrument Loop Sheet 2 of 22 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 _ _ ( NES-EIC-20
.04 Table of Contents Section Title Page 1.0 PURPOSE 4 2.0 SCOPE 4
 
==3.0 REFERENCES==
 
5 4.0 DEFINITIONS 6 5.0 METHODOLOGY 10 5.1 BASIC CONCEPTS 10 5.2 ESTABLISHMENT OF SETPOINTS AND ALLOWABLE 12 VALUES 5.3 UNCERTAINTY ANALYSIS AND SETPOINT 15 CALCULATION PROCESS Appendix A SOURCES OF ERROR AND UNCERTAINTY AI-A17 Appendix B PROPAGATION OF ERRORS AND UNCERTAINTIES BI-B7 Appendix C EQUATIONS FOR INSTRUMENT CHANNEL CI-C8 UNCERTAINTIES, SETPOINTS AND ALLOWABLE VALUES Appendix D GRADED APPROACH TO DETERMINATION OF DI-D8 INSTRUMENT CHANNEL ACCURACY Appendix E REACTOR WATER LEVEL TO SENSOR dP CONVERSION El-E8 Appendix F TEMPERATURE EFFECTS ON LEVEL MEASUREMENT FI-F14 Appendix G DELTA-P MEASUREMENTS EXPRESSED IN FLOW UNITS GI-G9 Appendix H CALCULATION OF EQUIVALENT POINTS ON NON- Hl-H6 LINEAR SCALES Appendix I NEGLIGIBLE UNCERTAINTIES II-I7 Appendix J GUIDELINE FOR THE ANALYSIS AND USE OF AS- JI-J24 FOUND/AS-LEFT DATA Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title STANDARD NES-EIC-20
.04 Analysis of Instrument Channel --Setpoint Error and Instrument Loop Sheet 3 of 22 Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 List of Figures Figure Title Page 1 Setpoint Relationships 13 2 Setpoint Calculation Flowchart 16 3 Input, Calibration Block and Output Errors and Uncertainties 18 4 Typical Instrument Channel Layout 20 Al Graphical Specification of Device Error A8 C 1 Uncertainty Model C4 El Reactor Vessel Water Level and Sensor dP E8 F1 Level Bias Error Due to Process Fluid Density Changes F5 F2 Level Bias Error Due to Reference Leg Heatup F8 F3 % Level vs. dP F9 F4 Level Bias Error Due to Both Process Fluid Density Changes and F12 Reference Leg Heatup it Example Spreadsheet data Entry J5 J2 Typical Probability Plot for Approximately Normally Distributed J12 Data J3 Coverage Analysis Histogram J13 List of Tables Table Title Page A 1 Classification of Error Terms A16 B 1 Uncertainty Symbols B2 D 1 Graded Methodology D7 F1 Error Fraction Effect on Instrument Setpoints F3 11 Negligible Errors and Uncertainties for Relays and Timers 15 12 Negligible Errors and Uncertainties for Limit Switches 16 13 Negligible Errors and Uncertainties for Mechanical Displacer - 17 Type Switches J 1 Critical Values for T J8 J2 Instrument Drift Sample Data J9 J3 Sample ANOVA Table J17 J4 Time Dependence Evaluation ANOVA Table J18 Revision 4 I NES-EIC-20
.04 1.0 PURPOSE 2.0 SCOPE This engineering standard defines a methodology for the determination of instrument setpoints, allowable values and instrument loop accuracy, that is consistent with ANSI/ISA-67.04.01-2000 (reference 3.1). This standard may be used to: " combine instrument uncertainties and errors used in the determination of instrument channel and setpoint accuracy, " develop a basis for establishing instrument setpoints with respect to applicable acceptance criteria, and " provide criteria to ensure that setpoints are maintained within specified limits. ANSVISA RP67.04.02-2000 (reference 3.2) shall be used when this document does not provide the necessary guidance for a particular application. Upon issue, this document replaces in their entirety: TID-E/I&C-10, Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy, rev. 0, and TID-E/I&C-20, Basis for Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy, rev. 0. This standard defines an acceptable method for establishing the uncertainties associated with instruments, instrument loops, and instrument setpoints and for applying these uncertainties in the determination of instrument loop accuracy, allowable values and calculated setpoints at Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) nuclear stations. This document shall be used when establishing specific values for loop accuracy, allowable values, and instrument setpoints. This standard shall be utilized by qualified Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) personnel, non-Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) organizations and integrated teams in the development of uncertainty analyses for the purpose of: " establishing new setpoints (both safety and non-safety related), " evaluation or justification of existing setpoints, " determining instrument indication uncertainties and indication accuracies, and " performing uncertainty analyses as required by other engineering evaluations. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title STANDARD NES-E IC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 4 of 22 Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04
 
==3.0 REFERENCES==
 
3.1 ANSUISA-67
.04.01-2000, Setpoints for Nuclear Safety-Related Instrumentation, Approved February 29, 2000 3.2 ISA- RP67.04.02-2000, Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation, Approved January 1, 2000 3.3 ISA-TR67.04.08-1996, Setpoints for Sequenced Actions, Approved March 21, 1996 3.4 ISA-dTR67.04.09-1996, Graded Approaches to Setpoint Determination (draft) 3.5 ANSVISA S37.1-1969, Electrical Transducer Nomenclature and Terminology (formerly ANSI MC6.1-1975) 3.6 ANSI/ISA 551.1 - 1979, Process Instrumentation Terminology 3.7 ISA Aerospace Industries Division, Measurement Uncertainty Handbook, revised 1980 3.8 ISA-MC96.1-1982, Temperature Measurement Thermocouples 3.9 ISO/TAG 4/WG 3: June 1992, Guide to the Expression of Uncertainty in Measurement 3.10 ANSI/ASME PTC6 Report - 1985, Guidance for Evaluation of Measurement Uncertainty in Performance Tests of Steam Turbines 3.11 ANSI/ASME PTC 19.1 - 1985, Part 1, Measurement Uncertainty 3.12 ANSI/ASME MFC-2M-1983, Measurement Uncertainty for Fluid Flow in Closed Conduits 3.13 ASME MFC-3M-1989, Measurement of Fluid Flow in Pipes Using Orifice, Nozzle and Venturi 3.14 ASME Application, Part II of Fluid Meters, Sixth Edition 1971, Interim Supplement 19.5 on Instruments and Apparatus 3.15 SAMA PMC 20.1-1973, Process Measurement
& Control Terminology (for information only, standard withdrawn) 3.16 NUREG/CR-3659, A Mathematical Model for Assessing the Uncertainties of Instrumentation Measurements for Power and Flow of PWR Reactors, February 1985 3.17 Commonwealth Edison company Procedure CC-AA-309, Control of Design Analysis Braidwood, Byron, Dresden, Title STANDARD LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 5 of 22 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 3.18 ANSI/IEEE Std 344-1975, IEEE Recommended Practices for Seismic Qualification of Class I E Equipment for Nuclear Power Generating Stations 3.19 EPRI TR-103335, Guidelines for Instrument Calibration ExtensiorvReduction Programs, October 1998, Revision 1 3.20 EPRI AP-106752, Instrument Performance Analysis Software System, IPASS User's Guide, August 1996 3.21 Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) Nuclear Operating Division Standard NES- EIC -20.01, Standard for Evaluation of M&TE Accuracy When Calibrating Instrument Components and Channels, rev. 0, January 23, 1996 3.22 Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) Nuclear Operating Division Standard ER-AA-520, Instrument Performance Trending 3.23 Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) Nuclear Operating Division Standard NES-G-14, Calculations
 
===4.0 DEFINITIONS===
 
Note: symbols in parenthesis represent the Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) methodology symbols used in setpoint accuracy calculations. 4.1 allowable value (AV): the limiting value that the trip setpoint may have when tested periodically, beyond which appropriate action shall be taken. The allowable value provides operability criteria for those setpoints or channels that have a limiting operating condition. This limiting condition is typically imposed by the Technical Specification, but may also result from regulatory requirements, vendor requirements, design basis criteria or other operational limits. The allowable value applies to the "as-found" condition or "as-found" calibration values. 4.2 allowance for spurious trip avoidance (AST): an evaluation to ensure that sufficient margin exists between the steady state operating value and the trip setpoint. May include a statistical combination of instrument channel accuracy (normal environment) including drift, processes effects and the effect of the limiting operating transient. 4.3 analytical limit (AL): limit of a measured or calculated variable established by the safety analysis to ensure that a safety limit is not exceeded. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 6 of 22 Accuracy Title Revision 4 Revision 4 T NES-EIC-20
.04 4.4 bias (e): an uncertainty component that consistently has the same algebraic sign and is expressed as an estimated limit of error. Bias error terms may also be represented by: 1) Symmetrical bias errors: the estimated limit of error is known but not its sign. The limit of error is evaluated separately in both the positive and negative directions. 2) Deterministic errors that may not be sufficiently random or independent to be combined with other random errors using the square-root-sum-of-squares (SRSS) methodology. 4.5 calibration block: the basic unit of evaluation in this standard. A calibration block is that part of the instrument channel between the point(s) where input test signals are applied and the point where the module performance is monitored (e.g. signal output, bi-stable actuation, etc.). A calibration block may be a single component or module, or an assembly of interconnected components that are calibrated as a single unit (commonly referred to as a "string calibration"). 4.6 calibration error (CAL): an uncertainty affecting the accuracy of an instrument channel or component resulting from the calibration method and calibration components. Calibration components include the uncertainties and errors associated with use of M&TE (e.g. reference accuracy, reading error, environmental effects, etc.) and uncertainties associated with the calibration and maintenance of the M&TE (e.g. calibration standard error or STD). 4.7 calibration standard error (STD): an uncertainty affecting the accuracy of an instrument channel or component resulting from the standards used to calibrate or validate the M&TE accuracy. 4.8 drift (D): an undesired change in output over a period of time where change is unrelated to the input, environment, or load. 4.9 error: the algebraic difference between the indication and the ideal value of the measured signal. Refer to sections 5.1.1 and 5.1.2 for a discussion of measurement uncertainty and measurement error. 4.10 humidity error (eH): an uncertainty affecting the accuracy of an instrument channel or component resulting from variations in ambient humidity. 4.11 insulation resistance error (eIR): an uncertainty affecting the accuracy of an instrument channel or component resulting from leakage currents caused by the degradation of the insulating properties of instrument channel components. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel -'-"'-Setpoint Error and Instrument Loop Sheet 7 of 22 Accuracy Title Revision 4 Revision 4 (NES-EIC-20
.04 4.12 limiting safety system setting (LSSS): limiting safety system settings for nuclear reactors are settings for automatic protective devices related to those variables having significant safety functions. The LSSS values may have been defined by the station Technical Specifications to correspond to either the allowable value or the trip setpoint. The LSSS values used in setpoint error analysis must be consistent with each stations Technical Specifications. 4.13 margin (m): in setpoint determination, an allowance added to the instrument channel uncertainty. Margin moves the setpoint farther away from the analytical limit. Margin may result from 2 conditions
: 1) margin is a method for arbitrarily adding additional conservatism or confidence, often as a result of engineering judgment, and 2) margin may exist where the instrument channel uncertainty is less than the difference between the calculated setpoint and the analytical limit. This margin may be utilized as an additional conservatism. 4.14 module: any assembly of interconnected components that constitutes an identifiable device, instrument, or piece of equipment. A module can be removed as a unit and replaced with a spare. It has definable performance characteristics that permit it to be tested as a unit. A module can be a card, a drawout circuit breaker, or other subassembly of a larger device, provided it meets the requirements of this definition 4.15 power supply error (eV): an uncertainty affecting the accuracy of an instrument channel or component resulting from variations in the electrical power supply voltage, current or frequency. 4.16 pressure error (eP): an uncertainty affecting the accuracy of an instrument channel or component resulting from changes in either 1) process pressure or 2) ambient pressure. 4.17 process error (ep): an uncertainty affecting the accuracy of an instrument channel or component resulting from process effects, e.g. flow turbulence, temperature stratification, process fluid density changes, etc.. The process error may also include uncertainties resulting from the metering device itself, e.g. nozzle fouling. This uncertainty may also be referred to as "process measurement error" in some Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) calculations. 4.18 radiation error (eR): an uncertainty affecting the accuracy of an instrument channel or component resulting from exposure to ionizing radiation. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 8 of 22 Accuracy Title Revision 4 Revision 4 --1 NES-EIC-20
.04 4.19 random (6): a variable whose value at a particular future instant cannot be predicted exactly but can only be estimated by a probability distribution function. As used in this standard, the term "random" means random and approximately normally distributed. 4.20 reading error (RE): an uncertainty affecting the accuracy of an instrument channel or component resulting from the ability to interpret an indicated value. 4.21 reference accuracy (RA): a number or quantity that defines a limit that errors will not exceed, when a device is used under specified operating conditions. Reference accuracy includes the combined effects of linearity, hysteresis, deadband, and repeatability. Caution should be used when applying vendor supplied values for reference accuracy to ensure that all of the above components that contribute to reference accuracy are included. 4.22 safety limit: a limit on an important process variable that is necessary to reasonably protect the integrity of physical barriers that guard against the uncontrolled release of radioactivity. 4.23 seismic error (e5): a temporary or permanent uncertainty affecting the accuracy of an instrument channel or component caused by seismic activity or vibration. 4.24 setting tolerance (ST): the accuracy to which a module is calibrated or maintained by a station calibration procedure. As used in this standard, the setting tolerance is equivalent to the "calibration tolerance" specified in the station calibration procedure. 4.25 static pressure error (eSP): an uncertainty affecting the accuracy of dP sensors resulting from operation at a pressure different from that to which it was calibrated. Static pressure error may consist of zero error and span error components. 4.26 temperature error (eT): an uncertainty affecting the accuracy of an instrument channel or component resulting from the effects of ambient temperature changes. The temperature error can effect component accuracy, M&TE accuracy, or process error. 4.27 trip setpoint(SP)
: a predetermined value for actuation of the final setpoint device to initiate a protective action. The actual calibrated setpoint may be more conservative than the calculated setpoint obtained from the analysis of instrument channel setpoint error. 4.28 uncertainty
: the amount to which an instrument channel's output is in doubt (or the allowance made therefore) due to possible errors, either random or systematic, that have not been corrected. The uncertainty is generally identified within a probability and confidence level. Refer to sections 5.1.1 and 5.1.2 for a discussion of measurement uncertainty and measurement error. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 9 of 22 Accuracy Title Revision 4 Revision 4 l N ES-EIC-20.04 5.0 METHODOLOGY
 
===5.1 BASIC===
CONCEPTS 5.1.1 Measurement Error The objective of a measurement is to determine the value of the measurand (ref. 3.8). The following contributors are included in the measurement
: " the specification of the measurand, " the method of measurement and " the measurement procedure. The result of a measurement is an approximation or estimate of the value of the measurand due to errors, effects and corrections to these three contributors. For this reason, a measurement must be accompanied by a statement of the uncertainty of that estimate. The measurement process includes imperfections that result in an error in the measurement result. Errors may be of 2 types: random or systematic. Random error results from unpredictable variations and is evidenced by variations in repeated observations or measurements of the measurand. Random errors of a measurement result cannot be compensated by correction. They can be minimized or reduced by increasing the number of observations, increasing the accuracy of the measurement device or by incorporating a measurement procedure that reduces sources of error. Similarly, systematic error also cannot be eliminated. Systematic errors resulting from identified effects can be quantified and a correction or correction factor may be applied to the measurement result to compensate for this type of error An error in the measurement results is not the same as measurement uncertainty, and should not be confused in the process of instrument channel setpoint error analysis or instrument loop accuracy. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-2 0.04 Analysis of Instrument Channel --Setpoint Error and Instrument Loop Sheet 10 of 22 Accuracy (Title Revision 4 Revision 4 1 N ES-EIC-20.04 5.1.2 Measurement Uncertainty "The word `uncertainty' means `doubt', and thus in its broadest sense uncertainty of measurement means doubt about the exactness or accuracy of the result of a measurement" (reference 3.$). Typically, uncertainty is defined and quantified using a parameter associated with the result of the measurement, e.g. standard deviation, width or confidence interval, dispersion interval, etc. The uncertainty of measurement is a combination of a number of components. Some of these components may be determined from the statistical evaluation of the distribution of a number of measurement results. These are characterized by a level of confidence in the uncertainty and a level of confidence in the distribution of the results. Some components may rely on assumed probability distributions based on experience or other information. 5.1.3 Methodology Methodology defines a consistent means of: " identifying sources of uncertainties and errors that may effect instrument channel accuracy, " defining the mechanisms and processes used to evaluate the magnitude of these effects, " defining the process for combining individual effects into a channel accuracy, and " defining the equations used to determine setpoints and allowable values. Given the uniqueness of many of the instrument channels and the special requirements of many instrument setpoints, situations that are not consistent with this methodology are expected. Where specific documentation, references or experience exists that dictates a deviation from this methodology, this information may be incorporated in the basis for channel accuracy and instrument setpoints. Changes to this methodology require the review and approval of the NES Electrical/I&C Chief Engineer. Deviations from this methodology shall be documented in an associated engineering calculation as required by NEP-12-02, Preparation, Review, and Approval of Calculations. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title STANDARD NES-EIC-20
.04 Analysis of Instrument Channel '-Setpoint Error and Instrument Loop Sheet 11 of 22 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 5.1.4 Accuracy Accuracy is the combination of: " known or expected process effects, " known or expected instrument or instrument channel performance characteristics, " known or expected measurement errors, " known or expected measurement uncertainties, and " allowances for conservatism (margin). Determination of instrument loop accuracy, instrument setpoints and the associated allowable values must consider all of these areas. Appendix A provides a minimum list of the errors and uncertainties that must be included in this analysis. 5.2 ESTABLISHMENT OF SETPOINTS AND ALLOWABLE VALUES This methodology should be used to provide sufficient allowance between the trip setpoint and an analytical limit, safety limit or other acceptance limit, to account for instrument channel accuracy. The relationship between the analytical limit and the trip setpoint is shown in Figure 1. Figure l also indicates the relation ship between the safety limit, the analytical limit, the allowable value, the trip setpoint and the normal process condition. These relationships are described by the following allowances. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel ---Setpoint Error and Instrument Loop Sheet 12 of 22 Accuracy Title Revision 4 Revision 4 1 NES-EIC-20
.04 Setpoint Allowance SAFEIY LIMIT ANALYTICAL LINIIT Channel nuy be inoperable in t1ris region - ; - ALLOWABLE VALVE Allowable Value Allowance TRIP SLIT OM Cal ibration Tolerance (acceptable as-left condition)
Safety Unit: A lim i t on an urportm process variable that is necessary to teasothably protect the integrity of the physical barriers that guard agairnt the uncontrolled release of tadioactiviry. Trip5gpoirt The calculated trip value that will provide tlu necessary level Of corfdeice that the analytical limit will rut be exceeded. Allow able Value: The criteria used for the determination of operability. NOME: This figure is intended to provide relative position and not to inply direction. NORMAL PROCESS CONDITION Analytical Limit: The limit of a rreasuned o- calculated variable established by the safety analysis to ermue that a safety 1 irrit is not exceed. 2.1 Setpoint Allowance: The setpoint allowance describes the relationship between the trip setpoint and the analytical limit. This allowance may be determined through the evaluation of the instrument channel accuracy, operating experience (including as-found/as-left analysis), equipment qualification tests, vendor design specifications, engineering analyses, laboratory tests, engineering drawings, etc. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Figure 1, Setpoint Relationships Title STANDARD NES-EIC-20
.04 Analysis of Instrument Channel 'Setpoint Error and Instrument Loop Sheet 13 of 22 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 The setpoint allowance shall account for all applicable design basis events (normal and abnormal) and the following process instrument uncertainties unless they were included in the determination of the analytical limit. Instrument uncertainties included in the setpoint allowance: 1) Instrumentation calibration uncertainties
; including: " calibration standards, " calibration M&TE, and " setting tolerances. 2) Calibration methods 3) Instrument uncertainties during normal operation; including: " reference accuracy, " power supply voltage and frequency changes, " ambient temperature changes, " humidity changes, " pressure changes, " in service vibration allowances, " radiation exposure, and " A/D and D/A conversion. 4) Instrument drift 5) Uncertainties caused by design basis events 6) Process dependent effects 7) Calculation effects 8) Dynamic effects 9) Installation biases It is often difficult to determine what errors and uncertainties have been included by the NSSS supplier or AIE in the determination of the original design basis analytical limit. This is especially true for the environmental conditions. It should not be assumed that analytical limits contained in Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) documents andlor Tech Specs are correctly implemented as LSSS setpoints or calculated setpoints without evaluation of the original setpoint accuracy analysis or preparation of a new analysis using this standard. 5.2.2 Allowable Value Allowance: This allowance describes the relationship between the trip setpoint and the allowable value. The purpose of the allowable value is to identify a value that, if exceeded, may mean that the instrument, device or channel has not performed within the basis of the setpoint calculation. A channel whose as-found condition exceeds the allowable value should be evaluated for operability, taking into account the setpoint calculation methodology. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel --Setpoint Error and Instrument Loop Sheet 14 of 22 Accuracy (Title Revision 4 Revision 4 I NES-EIC-20
.04 At Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) nuclear stations, non-reactor protection setpoints frequently have administrative limits, reportable tolerances or other station specific criteria to evaluate the as found condition of a setpoint, calibration or operational test. Refer to ER-AA-520, Instrument Performance Trending, for additional information associated with these limits. Instrument uncertainties included in the Allowable Value allowance: 1) Instrument calibration uncertainties
: 2) Instrument uncertainties during normal operation
: 3) Instrument drift 5.2.3 Operating Margin: This allowance describes the relationship between the normal process condition and the trip setpoint. It is considered good practice to evaluate this relationship in order to determine the effect of normal operating transients on the trip setpoint. The operating margin may consider instrument channel accuracy, transient analysis, "allowance for spurious trip allowance", operating experience (including as-found/as-left analysis), equipment qualification tests, vendor design specifications, engineering analysis, laboratory tests, engineering drawings, etc. 5.3 UNCERTAINTY ANALYSIS AND SETPOINT CALCULATION PROCESS The process for determining instrument setpoints and allowable values is based on the analysis of the instrument loop accuracy and the identification of the acceptance criteria for each setpoint. This process is shown in figure 2. 5.3.1 Block Diagram the Instrument Channel and Identify Components, Modules and Calibration Blocks The instrument channel to be analyzed should first be diagrammed to ensure that all errors and uncertainties affecting instrument channel accuracy are identified and correctly applied. The process for determining instrument channel accuracy is based on the propagation of errors and uncertainties through the instrument channel from the process to the final output, i.e. actuation or indication. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 15 of 22 Accuracy Title Revision 4 Revision 4 j NES-EIC-20
.04 MORE CALIBRATION BLOCKS? DIAGRAM THE INSTRUMENT CHANNEL AND IDENTIFY THE COMPONENTS OR MODULES DETERMINE THE REQUIRED ACTUATION FUNCTIONS PROCESS/ENVIRONMENTAL CONDITIONS ASSUMED FOR EACH FUNCTION IDENTIFY DESIGN PARAMETERS AND SOURCES OF UN CERTAINTY CLASSIFY EACH MODULE AND COMPONENT'S ENVIRONMENT (HARSH ENVIRONMENT?)
NO IDENTIFY OTHER NORMAL INSTRUMENT UNCERTAINTIES (drift, normal temp, eff ects, etc.) IDENTIFY NORMAL PROCESS MEASUREMENT EFFECTS (head effects, etc.) IDENTIFY CALIBRATION UNCERTAINTIES CLASSIFY EACH UNCERTAINTY AS RANDOM OR BIAS COMBINE PROPAGATED INPUT ERRORS, MODULE ERRORS AND OUTPUT ERRORS TO OBTAIN THE CALIBRATION BLOCK OUTPUT ERROR REPEAT FOR EACH CALIBRATION BLOCK TO OBTAIN TOTAL LOOP UNCERTAINTY DONE DETERMINE THE SETPOINT AND ALLOWABLE VALUE Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards YES Figure 2, Setpoint Calculation Flowchart Title MEASUREMENT EFFECTS (ref. lea heatup. etc.) IDENTIFY OTHER ACCIDENT INSTRUMENT UNCERTAINTIES temp. effects, radiation effects, etc. IDENTIFY OTHER ACCIDENT EFFECTS (IR, etc.) STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 16 of 22 Accuracy Revision 4 Revision 4 This process includes: " identifying individual components and modules contained within the instrument channel, and when appropriate identifying the calibration blocks within which the components or modules are calibrated, " propagating input errors and uncertainties through the calibration block, and " combining the propagated errors, the specific module errors and any output errors to determine a calibration block output uncertainty. If necessary, this calibration block uncertainty becomes one of the input uncertainties to the next calibration block. The definition of a calibration block is the basis for this methodology. A calibration block is identified by the calibration process associated with the instrument channel to be evaluated. A calibration block is contained between the point where a test input is applied and the point at which an output is observed. The calibration block output may be digital, i.e. a bistable output, or analog, as in a measured variable or an indicated variable. As shown in figure 3, a calibration block has: 1) input errors and uncertainties, including process errors, calibration errors, uncertainties associated with the input from previous modules, etc.. 2) calibration block errors and uncertainties, including: " environmental conditions that affect the modules or components within the calibration block, " reference accuracy of each internal module or component, " process conditions that affect an individual module or component, e.g. static pressure error, and " other uncertainties associated with the individual modules or components within the module 3) output errors and uncertainties, including calibration errors, setting tolerance, etc. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel '-'-Setpoint Error and Instrument Loop Sheet 17 of 22 Accuracy (Title NES-EIC-20
.04 Revision 4 Revision 4 The total calibration block accuracy is a combination of: input errors/uncertainties propagated across the calibration block, module errors/uncertainties, some of which may have to be propagated across components within the calibration block, and output errors/uncertainties. A Calibration Block Containing t or More Components or Modules CALIBRATION BLOCK ERRORS comp 0nenUmodule errors and uncertainties errors and uncertainties from environmental effects component, module or loop drift TERRORS " propagated input errors " component/module errors (these may require propagation) " output calibration errors Figure 3, Input, Calibration Block and Output Errors and Uncertainties See Appendices C and D for the equations used to combine individual errors and uncertainties when calculating total calibration block accuracy. Some considerations when identifying a calibration block are: NES-EIC-20
.04 l) A calibration block may contain 1 or more modules, or components based on the calibration methodology of the specific channel. Where a string calibration is performed as the final acceptance test, the entire string becomes the calibration block. 2) A calibration block can never contain just a resistor. Often a resistor is used for signal conversion. The interposing resistor may be part of the output errors of one calibration block, part of the input errors to the next calibration block or both. The calibration procedure must be carefully analyzed to ensure that the effect of these resistors are correctly incorporated into the channel or calibration block accuracy. Braidwood, Byron, Dresden, Title STANDARD LaSalle, and Quad Cities NE S-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 18 of 22 Nuclear Engineering Standards Accuracy Revision 4 " " INPUT ERRORS " " process errors " input measurement errors and uncertainties " input calibration errors Revision 4 ( NES-EIC-20
.04 5.3.2 Determine The Required Actuation Functions and Process/Environmental Conditions For Each Function Identify the purpose of the instrument channel and setpoint to be analyzed. Determine the conditions where the setpoint is required to function and the associated environment(s) when this function is required. 5.3.2.1 Design Basis Determine the design basis of the setpoint and the associated instrument channels. The design basis information should include: " the function of the instrument channel " the purpose of the setpoint " whether the existing setpoint represents an allowable value or limiting setpoint " what analyses are affected by the setpoint " what limiting criteria (acceptance criteria) and assumptions regarding the setpoint are included in these analyses 5.3.2.2 Environmental Conditions Determine the environment in which each component/module is located and the environmental conditions in which they must perform their function. Figure 4 shows a typical instrument channel layout, the point within the channel affected by various types of errors and uncertainties, and the environment for each module. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 19 of 22 Accuracy (Title Revision 4 Revision 4 1 NES-EIC-20
.04 ENVIRON MENT B f Control Room or Environmentally-Controlled Area ,are R o ot Conve r t er --= Co n verte r _ -- Bista ble ._ UNCERTAINTY ALLOWANCES DEVICE EXAMPLES t'~ Process Measurement Effects Tank, Tubing, Transmitter/Sensor, IN converter, Bistable, Indicator, etc. Equipment Uncertainties Calibration Uncertainties 4 4) Other Uncertainties (eIR, leadwire effects, etc.) Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title Figure 4, Typical Instrument Channel Layout I ISA- RP67.04-.02-2000, Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation, Approved January l, 2000. STANDARD NE S-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 20 of 22 Accuracy Revision 4 ENVIRONMENT A I Plant ! ' Flow dP Tr a n smitter Process Process H Measurement
' Tank, Piping Tubing, Primary Element, II Cables Systems, etc. etc. Sensor, Transmitter Signal Signal Actuation Conditioning H Conditioning H or Indication Signal Converter, Isolators, Signal Converter, Isolators, Bistable, Indicator Scaling, etc. Scaling, etc.
Revision 4 5.3.3 Identify Design Parameters and Sources of Uncertainty
 
====5.3.4 Classify====
Each Modules Environment NES-EIC-20
.04 Once the design basis for the instrument setpoint and environment is determined, identify the potential sources of errors and uncertainties that may affect the instrument channel accuracy. See Appendix A for a discussion of the minimum list of errors and uncertainties that must be included in accordance with this standard. This minimum list is not intended to limit the types and sources of error and uncertainty associated with an instrument setpoint. Each instrument channel, method of process measurement, calibration methodology, and environment may have unique errors and uncertainties. This standard requires that the station specific EQ Zones contained in the UFSAR and the station specific environmental conditions associated for each zone are to be used in evaluating all environmental effects. 5.3.5 Identify Normal/Accident Process Measurement Effects, Instrument Uncertainties, Calibration Uncertainties and Other Uncertainties, and Classify Each Uncertainty as Random, Bias, etc. See Appendix A and Reference 3.2 for applicable error effect equations and methods for determining values of uncertainty. 5.3.6 Combine Propagated Input Errors, Module Errors and Output Errors to Yield Total Calibration Block Output Error See Appendix B for error propagation and Appendix C for equations for the combination of errors and uncertainties. 5.3.7 Obtain Total Channel Uncertainty See appendix C for the methodology and equations used to combine individual errors and uncertainties. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards (Title STANDARD NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 21 of 22 Accuracy Revision 4 Revision_. ~ NES-EIC-20
.04 5.3.8 Determine the Setpoint and Allowable Value See appendix C for the methodology and equations used to determine an instrument setpoint and an associated allowable value. 5.3.9 Administrative Limits Refer to ER-AA-520, Instrument Performance Trending, when administrative limits are required as part of the instrument loop accuracy determination. Braidwood, Byron, Dresden, Fitle ' STANDARD LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel -' Setpoint Error and Instrument Loop Sheet 22 of 22 Nuclear Engineering Standards Accuracy Revision 4 Revision 41 1 NES-EIC-20
.04. APPENDIX A SOURCES OF ERROR AND UNCERTAINTY Latest Revision indicated by a bar in tight hand margin. Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet Al of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 NES-EIC-20
.04 This appendix discusses the sources of error that may affect instrument loop accuracy. In all cases, sound engineering judgment should be applied to account for errors not explicitly described below. Significant errors, whether or not they are described in this appendix shall also be included in the computation of setpoint error, or instrument loop accuracy. This appendix provides a minimum list of errors and uncertainties that shall be evaluated for each component and module when evaluating instrument channel accuracy in accordance with this standard. 1.0 PROCESS ERRORS Process errors result from changes in the process or sensing channel from the nominal, or calibration conditions. They may also result from conditions that cannot be readily measured, e.g. turbulence or other system complexities. To account for process errors in a setpoint error calculation, it is necessary to model the process, and the effects of sensing elements on the process. For example, intrusive flow sensing devices, such as venturis, directly effect the process that they measure. Process models should account for calibration conditions, normal operation, and accident conditions. For each of these conditions, the behavior of all applicable process variables, such as temperature, pressure, and density, must be understood well enough to predict the error. Changes in the process may result in either random or non-random errors. Non-random process errors are those which can predictably be correlated to process conditions, such as thermal expansion effects. Random errors result from uncertainties that are not predictable as to their direction, but exist as a range or limit of error around the process value. 1.1 DENSITY EFFECTS Measurements of fluid flow, pressure, and levels are effected by the process densities. Density changes in the process and in instrument sensing lines can result in measurement errors. An example of a process measurement that is affected by density changes is the measurement of fluid flow. Fluid flow is inversely proportional to the square root of fluid density. If a flow meter is calibrated for a specific fluid density, and the density changes, then a flow measurement error that is inversely proportional to the square root of the density change will result. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX A NES-EIC-20
.04 Analysis of Instrument Channel "" Setpoint Error and Instrument Loop Sheet A2 of A17 Accuracy Title Revision 4 Revision 4 ~_NES-EI_ C-20.04 1.2 FLOW ERRORS Flow measurements are based on nominal values for the dimensions of components such as nozzles, orifices, and venturis. These devices are subject to changes in dimension due to the erosion and/or corrosion effects of the material they contain. Changes in pipe diameter, or bore tolerance will cause flow measurement errors. and should be considered in the evaluation of instrument loop accuracy 1.3 TEMPERATURE ERRORS Changes in the process media temperature from the nominal or calibration values will cause process measurement errors. Pressure and differential pressure measurements are particularly susceptible to temperature induced errors. Pressure and level measurements are made by sensing the hydrostatic head pressure of a fluid. The hydrostatic head pressure of a fluid is directly proportional to the product of the fluid's height and specific weight. Since specific weight is a temperature dependent parameter, temperature changes in the process fluid will cause process measurement errors. Temperature induced process errors will affect pressure, level, and flow measurements and should be considered in the evaluation of instrument loop accuracy. 1.4 THERMAL EXPANSION ERRORS Changes in temperature cause dimensional changes in system structures, components and instrument sensing lines. Instrument calibration is often based on specific sensing line or component installed elevations. Component elevation changes due to temperature effects will cause process measurement errors and should be considered in the evaluation of instrument loop accuracy. An example of a thermal expansion effect on a process measurement is reactor pressure vessel growth. As the reactor is heated and pressurized to operating conditions, dimensional increases occur. Differential pressure level sensing instruments are calibrated for specific values of process tap and component elevations. These elevations may change from calibration values as the reactor is brought up to operating conditions as a result of thermal expansion. Thermal expansion errors should be accounted for in the evaluation of instrument loop accuracy. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX A NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A3 of A17 Accuracy Title Revision 4 Revision 4 1.5 PIPING CONFIGURATION
 
===2.0 REFERENCE===
 
ACCURACY (RA) NES-EIC-20
.04 Intrusive devices, i.e. nozzles, orifices, venturis and valves, as well as pipe bends, changes in pipe diameter and material cause turbulence in flow media. Flow turbulence is a source of flow measurement error. Inspection of piping and isometric drawings can provide information on the proximity of flow sensors to fittings and valves that cause turbulence. It may be possible to bound flow measurement error due to turbulence based on the upstream or downstream separation between the flow sensor and source of turbulence. Refer to References 3.2, 3.10 and 3.13 for additional information. The Reference Accuracy of an instrument loop component is never zero. This would infer that there is no difference between the true value of a process and the measured value of a process. Error free measurements are physically impossible. The error due to the Reference Accuracy of an instrument is usually given as a numerical expression, graph, or specification published by the instrument vendor. Where independent test labs rather than the manufacturers have evaluated an instrument's performance characteristics, the test methods should be reviewed to ensure that the test results are consistent with their intended use. The error due to instrument Reference Accuracy is classified as a normally distributed random variable. 3.0 OPERATIONAL ERRORS. 3.1 Drift (D) Instrument drift is a change in instrument performance that occurs over a period of time that is unrelated to input, environment or load. Drift independently effects all components of an instrument loop. Ambient conditions such as temperature, radiation, and humidity do not affect the magnitude of an instrument's drift. Specific instrument drift effect data is typically provided from: " The instrument manufacturer " The review of historical calibration data " Documentation industry experience " Environmental Test Reports Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A4 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 If specific values for this effect are not available from these sources, the following default values may be included when preparing the analysis for additional conservatism. The Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) default drift effect values that will be used in these cases are: Mechanical Components
: +/-1.0% of span per refueling cycle Electronic Components
: +/-0.5&deg;10 of span per refueling cycle The intent of these Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) default drift effect values is to establish consistent values for this type of error for inclusion into the calculations to achieve additional conservatism when this data is not available, applicable, or published. Selection of these default drift effect values is the result of engineering review and judgement of industry practices, typical Reference Accuracy for these device types, and industry experience. These default drift effect values shall not be used when instrument drift effect data is available from the sources listed above. Manufacturer's published "drift specifications" that are explicitly dependent on operational conditions, i.e. temperature, should not be misinterpreted as Drift in the instrument analysis. In these instances, the use of the word drift is inconsistent with the definition in this standard. An example of this is, "the instrument's zero drift is 10 mv/ C." The net effect of drift on the components of an actuating loop may shift the trip point in the conservative direction, the non-conservative direction, or not at all. Drift is probabilistic in nature. Therefore, the magnitude and direction of its effects are impossible to predict precisely. Drift is classified as a symmetric random error. This classification accurately models the uncertainty in the sign of the drift error and assumes that the maximum possible drift always occurs between successive instrument surveillances, However, if a instrument surveillance occurs either before or after the manufacturer's published drift interval, then the value for drift must be adjusted to account for the differing intervals (see Eq. A1 or A2). Where the error caused by drift is assumed to be a linear function of time, equation Al should be used. If the engineer preparing the calculation determines that the drift effect is not a linear function, i.e. "point drift", then the basis for the drift function shall be explained in the calculation. The following equation should be used to calculate instrument drift (D): D = (1 +LF/Sf)SIxfDE (Eq. A1) where: IDE = instrument drift effect that is specified by the instrument vendor, published by an independent test lab, or determined from plant historical data. Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A5 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 NES-EIC-20
.04 SI = instrument surveillance interval specified in the station technical specifications or other station document. LF where: = test interval late factor. This is the amount of time (grace period) by which a required instrument surveillance is administratively allowed to exceed the licensed surveillance period. Surveillance intervals, grace periods and Late Factor are found in the plant technical specifications. This method of drift error calculations should be used unless other data or vendor information is available. The drift term is considered a linear function of time unless other methods to evaluate drift are available. Where multiple time periods of IDE and/or SI are to be evaluated, and it can be shown or reasonably argued that the drift error during each drift period is random and independent, then the SRSS of the individual drift periods between calibrations may be used. D = [ IDE ) [(SI+LF)/VDP]"' (Eq. A2) VDP = vendor drift period that is specified by the instrument vendor or obtained from other testing (e.g. as-found/as-left analysis). Example: SI+LF = 22 1/2 months VDP = 12 months IDE = 1 % span per 12 month period 3.2 STATIC PRESSURE EFFECTS (eSP) in D=[1%1[22 1/2/121 = +/- 1.37% span Static pressure effects are instrument errors due to a change in process pressure from the value present at the time of calibration. These effects should be considered for those devices with sensing elements that are in direct contact with the process. This effect typically applies to differential pressure sensors. eSP = ISPE(ASP) (Eq. A3) where: ISPE = the instrument static pressure effect specified by the vendor, independent test lab or determined from plant historical data. ASP = the changes in static pressure conditions from calibration conditions. Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel '-" Setpoint Error and Instrument Loop Sheet A6 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 T NES-EIC-20
.04 3.3 PRESSURE EFFECTS (eP) Pressure changes can cause density changes in process media. Pressure induced density changes in process media from nominal or calibration values are sources of process measure-ment error. Pressure changes due to environmental or accident effects can cause measure-ments errors in process parameters. eP = IPE(AP) (Eq. A4) where: IPE = instrument pressure effect is determined from vendor specifications, pub-lished independent test lab data or plant historical data. AP = changes in pressure from calibration conditions. 3.4 POWER SUPPLY EFFECTS (eV) Variations in the output of an instrument loop's power supply may cause errors in process measurement. Instrument errors due to fluctuations in the loop power supply may be estimated by: eV = IPSE(AV) (Eq. AS) where: IPSE = Instrument power supply effect is determined from vendor specifications or published independent test lab data. AV = power supply stability as determined from plant data 4.0 ENVIRONMENTAL ERRORS Changes in environmental conditions from those present at the time of calibration can cause measurement errors. Errors due to environmental fluctuations can occur during calibration, during normal operation, or during an accident and should be included in the calculation of instrument loop accuracy. Environmental errors are classified as non-random. The following three methods may be used to specify environmental error effects. Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A7 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 NES-EIC-20
.04 1) A numerical constant that bounds the error is specified for a specific range of environ-mental conditions. This constant is specified by the instrument manufacturer, or an independent test lab. An example of this type of error specification is: 1 % of output span for ambient temperatures of 60 - 90&deg;F. 2) An instrument's environmental error is calculated by evaluating a model that describes the instruments sensitivity to specific environmental fluctuations. Environmental error models may be available from instrument manufacturers and published in the instrument specifications, or from independent test labs. An example of this type of error specification is: Temperature Error (eT) = 0.75% of the Upper Range Limit + 0.50% of the Calibrated Span 3) An instrument's environmental errors may be given as a graphical specification. Figure Al shows a graphical representation of instrument error based on empirical or calculated data gathered by the instrument manufacturer, or by an independent test lab. A graphical error specification shows instrument error as a function of environmental changes. c ?L N (d _&deg; W U .m 0 2.4-1 2,2-2.0 , -, 1.8-1 .6-1,4-1.2-1.0-1 0.8 0.6 - 0.4 - 0,2-0 0 1 4 30 50 70 90 110 Temperature
(&deg;F) 130 Figure Al, Graphical Specification of Device Error Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet AS of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 [ NES-EIC-20
.04 4.1 TEMPERATURE EFFECTS (eT) Temperature errors result from deviations in ambient temperature at the instrument location from the temperature at which the instrument was previously calibrated. Where a mathematical model (ITE) is available for temperature error, then the model should be evaluated for the anticipated temperature change. eT = ITE(AT) (Eq. A6) where: ITE = the instrument temperature effect that models the measurement error as a function of the temperature changes (AT). 4.2 HUMIDITY EFFECTS (eff) Humidity errors are due to changes in humidity at an instrument location from calibration or nominal values. If a model is available for humidity error, then the model should be evaluated for the anticipated humidity change. eH = IHE(AH) (Eq. A7) where: 4.3 RADIATION EFFECTS (eR) Radiation errors are caused by instrument exposure to ionizing radiation. If a model is available for radiation error, then the model should be evaluated for the anticipated radiation dose. eR = IRE(TID) (Eq. A8) where: = the instrument humidity effect that models the measurement error as a function of humidity changes (OH). = the instrument radiation effect that models the measurement error as a function of radiation dose, expressed as total integrated dose (TID). Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel -'-' Setpoint Error and Instrument Loop Sheet A9 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision NES-EIC-20
.04 4.4 SEISMIC EFFECTS (eS) Seismic errors result from subjecting an instrument to high energy vibrations and accelera-tions. If a model is available for seismic error, then that model should be evaluated for the anticipated acceleration at the instrument location. eS = ISE(ZPA) (Eq. A9) where: ISE = the instrument seismic effect that models the measurement error as a function of Zero Period Acceleration (ZPA) anticipated at the instrument location. Seismic error models must take into account the instrument response due to location, mounting, orientation, and flexibility of the instrument, etc. Data for required response spectra and the associated error due to seismic effects should be obtained from the plant UFSAR, seismic test reports, and seismic structure analysis reports. The published instru-ment error (and its associated ZPA due to seismic effects should be compared with the required response spectrum specified for the instrument location to ensure that they are consistent. IEEE Recommended Practice For Seismic Qualification of Class lE Equipment For Nuclear Power Generating Stations (reference 3.18) defines Required Response Spectrum (RRS) as, "The response spectrum issued by the user or his agent as part o&#xac; his specifications for qualifications or artificially created to cover future applications. The RRS constitutes a requirement to be met". 5.0 CALIBRATION ERRORS Errors that occur in the adjustment and measurement of loop element signals due to measure-ment and test equipment (M&TE) are called calibration errors. Calibration errors are classified as random and include: " M&TE reference accuracy, " M&TE reading error, " M&TE environmental errors, " calibration standard reference accuracy (STD), " calibration standard reading error, and " setting tolerance (ST). Braidwood, Byron, Dresden, itle APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel '-' [Setpoint Error and Instrument Loop Sheet A10 of All Nuclear Engineering Standards Accuracy Revision 4 Revision 4 ( NES-EIC-20
.04 5.1 MEASUREMENT AND TEST EQUIPMENT (M&TE). 5.1.1 M&TE Error (RAMTE) All calibration procedures require measurement and test equipment to monitor instrument adjustments using a specified set of conditions. Some calibration procedures require additional test components whose accuracy must be included in the determination of calibra-tion error. M&TE error includes the reference accuracy of each device, the uncertainties resulting from the environment in which the M&TE was calibrated or used, and the uncertainty added by any component used in a calibration procedure. M&TE accuracy should be obtained from the manufacturer's published specifications unless the device has been calibrated or maintained to a different set of criteria. At Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad), the calibration facility may be directed to maintain the M&TE to a accuracy different from the manufacturer's specification. This difference should be documented in the basis for the M&TE accuracy used in the instrument channel or setpoint accuracy calculation. When assumptions are required regarding which particular M&TE device may be utilized in a test or calibration procedure, the assumed accuracy of the test equipment data should be equal to that of the least accurate instrument in the group of possible candidates. Measurement and test equipment used during calibration procedures may be sensitive to environmental fluctuations. M&TE errors should use the largest expected change between the instrument calibration conditions and the normal environment. These extremes typically are obtained from EQ documents, e.g. the station EQ zone maps. This provides a bounding or conservative estimate of M&TE environmental error. Restricting or assuming that the calibration environment deviates less than the associated EQ zone is not desirable since it places added requirements on the IM's to document the assumed environmental condition during each calibration. 5.1.2 Reading Error (REMTE) Since it is unlikely that an analog gauge reading will always coincide with a graduation tick mark, the readability of the gauge scale is !/2 of the smallest division. The uncertainty in this readability, or reading error (RE), is t '/a of the smallest graduation interval. For devices that have non-linear scales, the division used to determine the reading error is consistent with the desired reading. For digital output devices, the reading error is considered to be the least significant digit (LSD) or least significant increment of the display. Braidwood, Byron, Dresden, itle APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet All of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 ( NES-EIC-20
.04 5.1.3 Input M&TE Temperature Error (TEMTE) M&TE temperature errors are determined from the vendor's expression for temperature effects (ITE) and the range of temperature fluctuations (AT). The temperature extremes at which the M&TE equipment was calibrated and the ambient temperature extremes in which the M&TE device is going to be used should be evaluated. 5.1.4 Calibration Standard Error (STD). Calibration standards are used to perform periodic calibrations on M&TE. If the calibration standard is at least 4 times more accurate than the M&TE, then its error represents at most 6.25% of the M&TE error, and may be assumed to be negligible. If the calibration standard is not 4 times more accurate than the measurement and test equipment, then its error should be factored into the calculation of calibration error. Refer to NES-EIC-20
.01, Standard for Evaluation of M&TE Accuracy When Calibrating Instrument Components and Channels, for additional guidance. 5.1.5 Surveillance Interval (SI). The surveillance interval is the period between successive instrument surveillances or calibrations. Surveillance intervals are specified in the plant technical specifications, imple-mented in the plant calibration procedures, or identified by station instrument calibration scheduling programs. Station Technical Specifications may allow a grace period beyond the specified calibration frequency. The surveillance frequency is typically limited to 125% of the required SI. The grace period should be included in the determination of instrument loop accuracy. The grace period should not be included in the calculation of the Allowable Value since it results in the potential for non-conservative evaluation of operability. 5.2 SETTING TOLERANCE (ST) Setting tolerance is the uncertainty associated with the calibration procedure allowances used by technicians in the calibration process. Programs exist at each station to ensure that instrument channels and calibrated setpoints will not be left outside of a specified setting tolerance. As a result, it is expected that 100% of the population is left within the required setting tolerance. For pre-existing instrument channels that have established calibration procedures, the setting tolerance should be incorporated into the setpoint calculation as a 36 error estimate. For new channels, the setting tolerance should be conservatively determined to justify a 3o confidence value. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX A NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A12 of A17 Accuracy Title Revision 4 Revision 4 6.0 CALCULATIONAL ERRORS 6.1 NUMERICAL PRECISION AND ROUNDING NES-EIC-20
.04 The precision of a number is determined by the significant digits in the number. Conclusions based on a calculation or measurement depend on the number of significant digits in the result of the calculation, or measurement. Calculated results can be no more precise than the calculation input data. To prevent the propagation of rounding and truncation errors in a calculation, round only the final result. The final result should be rounded to the number of significant digits found in the least precise input data but no less than the number of significant digits utilized in presenting the calibration setpoint or the calibration endpoints for loops that do not have setpoints. If the output is read on a DVM that displays 3 digits after the decimal point, the calculations conclusions must be rounded to no less than 3 digits after the decimal point. This standard recommends the following method for rounding. The left-most non-zero digit in a number is the most significant digit. The right-most non-zero digit is the least significant digit if there is no decimal point. If there is a decimal point, the right most digit is the least significant digit. The number of digits between the most significant and least significant digits are counted as the number of significant digits associated with a calculation, or measurement. The following numbers all have 4 significant digits: 1234, 1.234, 10.10, 0.0001010, 1.000e4. Round the final results of calculations to a level of precision that is consistent with the data input to the calculation. The rules for rounding are: 1. If the next digit less than the desired degree of precision is greater than 5, round up the least significant digit. Example: 1.2347 =::> 1.235 2. If the next digit less than the desired degree of precision is less than 5, do not change the least significant digit. Example: 7.8932 =::> 7.893 3. If the next digit less than the desire degree of precision is equal to 5, increment the least significant digit only if it is an odd number. Examples: 3.4325 =:> 3.432, 3.4335 =:> 3.434 Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel "- Setpoint Error and Instrument Loop Sheet A13 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision T NES-EIC-20
.04 6.2 A-D AND D-A ERRORS Analog-to-Digital or Digital-to-Analog conversions (A/D or D/A) errors occur whenever a continuous process is represented digitally with a fixed number of bits. The resolution of the A/D or D/A converter is a primary consideration when evaluating A/D or D/A errors. Resolution is given by: n Resolution = (1/2 )(signal span) where `n' is the number of bits in the A/D or D/A converter and signal span is the signal range present at the input of the A/D or D/A converter. There are several types of A/D or D/A converters, each of which has different sources of conversion error. Therefore, other A/D or D/A conversion errors must be determined on a case-by-case basis. 7.0 INSULATION RESISTANCE ERROR (eIR) The eIR error shall be evaluated for all instrument components and instrument modules where the actuation function is expected to operate in an abnormal or harsh environment. Sources of data for insulation resistance should include values typical for the instrument loop under consideration, such as maximum supply voltage, nominal supply voltage, maximum loop resistance, minimum loop resistance, nominal insulation resistance (which should include conductor-to-conductor and conductor-to-ground values), and splice and terminal block insulation resistance. It may be necessary to arrive at these values through performance of generic calculations typical of several types of instrument loops. For a further effects of process measurement errors due to accident related insulation resistance degradation see Reference 3.2. 8.0 Setpoint Margin (MAR) Margin may be included in the determination of instrument loop accuracy when an additional level of confidence is desired. For example, a particular vendor's testing methodology is not considered sufficiently rigorous to justify a 2a confidence value for one of the published performance criteria. This determination may be based on engineering judgment, evaluation of the vendor's test plan or station/industry experience with the component. For the component in this example, it is determined that no other information exists to identify an alternate confidence level. This standard recommends that the vendor data should be incorporated at the 26 confidence level. Then an additional margin value is included in the instrument loop accuracy equation to provide additional conservatism. Braidwood, Byron, Dresden, Title APPENDIX A LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel ~'- Setpoint Error and Instrument Loop Sheet A14 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 T NES-EIC-20
.04 NOTE: where as foimdlas-left analysis or special test data is available, the component performance data should be utilized at the confidence level obtained from the statistical evaluation of the data. For new instrument channels, an additional margin of 0.5% of the instrument measurement span, in instrument units, shall be included in order to account for unanticipated, or unknown loop component uncertainties. This margin may be deleted after sufficient calibration history exists to justify the instrument channel accuracy based on all other errors and uncertainties. 9.0 CLASSIFICATION OF ERROR TERMS All errors and uncertainties shown in Table A 1 shall be evaluated as part of the determination of instrument loop accuracy. Where an individual error or uncertainty is 0, negligible or not applicable, the calculation shall describe why this condition is appropriate. Table 1 indicates the default classification for each type of error or uncertainty. These classifications may be changed as a result of published vendor information, other monitoring programs (e.g. as-found/as-left drift analysis), or engineering judgment. The basis for any changes to the classification of an error term shall be fully documented in the associated instrument channel or setpoint accuracy calculation. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX A NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A15 of A17 Accuracy Title Revision 4 Revision 4 NES-EIC-20
.04 Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX A NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A16 of All Accuracy Title Revision 4 Table A1, Classification of Error Terms Error T Symbol Error Classification Process Errors PE Density Error non-random, bias Process Error (non-instrument related, e.g. temperature stratification) random (NOTE: temperature streaming uncertainty may also include an associated bias error) Flow Element Error random (when calculated in accordance with reference 3.10) except for errors resulting from fouling which are bias errors Temperature Error eT non-random, bias Thermal Expansion Error non-random, bias Configuration or Installation Error random (e.g. installation tolerances) or bias (e.g. as measured installation deviation)
Reference Accuracy RA random Operational Errors Drift Error D random Static Pressure Error eSP non-random, bias Pressure Error eP non-random, bias or symmetric Power Supply Error ev non-random, bias or symmetric Environmental Errors Temperature Error eT non-random, bias or symmetric Humidity Error eH non-random, bias or symmetric Radiation Error eR non-random, bias or symmetric Seismic Error eS non-random, bias or symmetric Revision 4 NES-EIC-20
.04 Table Al (cont.), Classification of Error Terms Error T Symbol Error Classification Calibration Errors M&TE Reference Accuracy RAMTE random M&TE Reading Error REMTE random M&TE Temperature Error TEMTE random Calibration Standard Reference Accuracy RASTD random Calibration Standard Reading Error RESTD random Setting Tolerance ST random (3o) Calculational Errors Numerical Precision and Rounding random A-D and D-A Error random Other Errors Insulation Resistance eIR non-random, bias or symmetric Margin MAR non-random, bias or symmetric Braidwood, Byron, Dresden, LaSalle, and Quad Cities Title APPENDIX A NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet A17 of A17 Nuclear Engineering Standards Accuracy Revision 4 Revision - -1 NES-EIC-20
.04 APPENDIX B PROPAGATION OF ERROR AND UNCERTAINTIES Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Revision indicated by a bar in right hand margin. le Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy APPENDIX B NES-EIC-20
.04 Sheet BI of B7 Revision 4 Revision 4 I NES-EIC-20
.04 1.0 PROPAGATION OF UNCERTAINTIES THROUGH FUNCTIONAL MODULES This purpose of this appendix is to provide the methodology and functional relations to propagate errors and uncertainties through a calibration block. This appendix provides common linear and non-linear propagation equations for both random and bias errors and uncertainties. The equations provided in this appendix may be used in engineering calculations without further derivation. For module functions not identified in this appendix, the equivalent error function should be derived. See references 3.2 and 3.11 for further information. 2.0 SYMBOLS Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Table B1, Uncertainty Symbols For simplification, the following examples only show the positive input and output bias error terms. Where the bias is symmetrical or assumed symmetrical (as in protection and reactor Title APPENDIX B NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet B2 of B7 Accuracy Revision 4 Symbol T Description X, Y input signals Units must be consistent, e.g. % of span, mA, V, etc. a random error a x , a y ... a n represent random errors associated with inputs X and Y. UOUT is the resulting composite random output error. Units must be consistent with the associated input signals, e.g. +/-% full span, tmA, +/-V, etc. For linear functions (e.g. fixed linear gain amp), GOUT is a normally distributed, random error since the transfer function (gain) is linear. GOUT may be combined with other normally distributed error terms using the SRSS method. For non-linear functions (e.g. logarithmic amplification or square root extraction), GOUT assumes sufficiently small input errors so that GOUT is a nearly normal distribution. GOUT may then be combined with other normally distributed error terms using the SRSS method. e bias error e x , e y ...e N represent bias errors associated with inputs X and Y and e represents the composite bias error. OUT Units must be consistent with the associated input signals e.g. % full span, +/-mA, +/-V, etc.
Revision 4 trip setpoints, and graded methodology level 1 applications), the negative output error would be identical in magnitude and opposite in sign. Bias errors at the module output are combined by algebraically adding all of the positive biases and separately algebraically adding all of the negative biases. See appendix C for discussion of error combination. 3.0 FUNCTIONAL MODULES 3.1 LINEAR FIXED GAIN AMPLIFIER INPUT: X+/-(y X+e x Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards gain = k APPENDIX B NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet B3 of B7 Accuracy Title NES-EIC-20
.04 Note: this category also applies to modules that convert process units at the input into different output process units, e.g. a transmitter where the gain might equal mA/psi), or an isolator where the gain might be mA/mA, V/V or mA/V, etc. where: Q OUT e OUT OUTPUT: kX +/- cs o , it + eout = kax = ke x Revision 4 Revision 4 I NES-EIC-20
.04 3.2 SUMMING AMPLIFIER X INPUT: X+/-F x+e x Y INPUT: Y +/- F Y +ey 3.3 MULTIPLIER X INPUT: X+/-F x+e x Y INPUT: Y + F Y +e, Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title X gain =kl Y gain = k2 where: where: G OUT B OUT 6 0UT B OUT OUTPUT: (k 1 *X) + (k2
* Y) +/- FoUT +BOUT 2 1r_ = [(kl
* 6x) + (k2* (; Y)~ = (kl *e x) + (k2
* ey) OUTPUT: ~~ (k 1 *X) * (k2
* Y) f F oUT +BOUT 2 2 u2 (kl*k2)[(X*(Yy)
+(Y*a x) l (kl *k2)[(X*eY)
+ (Y*e x)1 (Y Our is an approximation since it is assumed that the individual input errors are small and their cross product is negligible. See reference 3.2 for the complete equation. APPENDIX B NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet B4 of B7 Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04 3.4 DIVIDER X INPUT: X +/- F x +e x Y INPUT: Y +/- FY +e y 3.5 MULTIPLIER DIVIDER X INPUT: X +/-F x+e x j Y INPUT: Y+/-F y+e y Z INPUT: Z t F Z +e z Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards where: module gain = k _k1[((Yx(yX)2+(Xx(yy)2)1/
2 i 6 OUT = k2 Y 2 where: (k I *X)/(k2
* Y) +/- FOUT +B OUT ki[(Yxe x)~z (Xxe y)1 J OUTPUT: (k *X
* Y)/ Z t FOUT +BOUT ~ Y l2 X 2 XY 2 CZ xQ'X I +] CZ x 6 r J +( Z x6Z~ eotrr 'kj(YxexI+CXxey Z Z OUTPUT: ZY xez) Title APPENDIX B NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet B5 of B7 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 3.6 SQUARE ROOT EXTRACTOR X INPUT: X+/-F,+e x X INPUT: X+/-F,+e x Y INPUT: Y+/-Fy+ey Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards OUT = 2(X) 112 eOUT = k[(X+ex)va
_ (X)1/2 ke x eouT 2(X)vz 3.7 SQUARE ROOT EXTRACTOR WITH MULTIPLIER where: OUTPUT: k(X)ltz+/- Four +BOUT for for ex 1 X eX < 1 X OUTPUT: k(X*Y)"-'t Four +eovr k[(Y x6 x)2 +(Xx u y)2 V 12 a Our 2(XY) 112 k[(Y x e x) + (X x e,, )] -our 2(XY) 1/2 i itle APPENDIX B NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet B6 of B7 Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 3.8 LOGARITHMIC AMPLIFICATION where: Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards where: C OLT eovr = 4.0 MODULES WITH INPUT AND/OR OUTPUT SIGNAL OFFSETS ROUT replaced with (x - x o) and x o represents the output offset. Example (square root extractor with input and output offsets) k(T x (TOUT - v2 2(x- x0) OUTPUT: k, + (k2
* log X) +/- F our +e OuT k 2 log e l )X k 2 log e~ X The functions provided in Appendix B, section 3 use normalized input and output signal values and do not explicitly indicate that either the input signal(s) or the output signal(s), or both, are offset from 0, e.g. 4-20 mA, 1-5 V. The above functions can be modified to include an offset where absolute signal values are desired. This is done by substituting (x - 9 for input X where the input offset is x,. The output is modified in a similar manner with INPUT: Xt6 x+e x => (x-x,) ta x+e x OUTPUT: k(X)r1- CY OUT +eOUT k(x - x 0) f 60UT + e OUT eouT-k((x-xo)
+ex)u2-(x_xo)Ill ke x eouT = u2 2(x-x 0) title APPENDIX B NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet B7 of B7 Accuracy Revision 4 Revision 4 NE S S-EIC-20.04 APPENDIX C EQUATIONS FOR INSTRUMENT CHANNEL UNCERTAINTIES, SETPOINTS AND ALLOWABLE VALUES Latest Revision indicated by a bar in right hand margin, Braidwood, Byron, Dresden, itle APPENDIX C LaSalle, and Quad Cities I NES-EIC-20
.04 Analysis of Instrument Channel I Setpoint Error and Instrument Loop Sheet C1 of C8 Nuclear Engineering Standards Accuracy Revision 4 I Revision 4 S-EIC-20.04 1.0 UNCERTAINTY EQUATION In order to provide a level of confidence that a setpoint actuation will occur prior to exceeding a performance or design basis criteria, the instrument loop accuracy must be determined. This level of confidence is dependent on determining the individual process and component errors and uncertainties, and then combining them in a consistent manner. The combination of errors is based on statistical and algebraic methods. Errors and uncertainties are combined based on the type of error or uncertainty represented. These types are defined as: " random, independent errors and uncertainties, which are combined using the square-root-sum-of square (SRSS) methodology. " random, dependent or not sufficiently independent errors and uncertainties, which are combined by first algebraically adding them to form a pseudo-random composite uncertainty, then combining this uncertainty using SRSS with the other random uncertainties. " dependent and/or non-randomly distributed errors and uncertainties, which are combined algebraically. Accuracy, represented by the combination of errors and uncertainties, is calculated using the following equation. 2 2 Z B+ C) + (D+E)]V, t (BFI) + (L)- (M) (Eq. C 1) random and independent terms. The terms are zero-centered, approximately normally distributed, and indicated by a t sign. random, dependent uncertainty terms that are independent of terms A, B and C 1) non-normally (abnormally) distributed uncertainties, or 2) biases with unknown sign. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards accuracy represented by the total uncertainty itle APPENDIX C NE S-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet C2 of CS Accuracy Revision 4 Z = Where: Z +/-[(A+ A, B, C = D, E = F =
Revision 4 NES-El C-20.04 This term is used to indicate limits of error associated with uncertainties that are not normally distributed and do not have known direction. The magnitude of this term (absolute value) is assumed to contribute to the total uncertainty in a worst-case direction and is also indicated by a +/- sign. L, M = biases with known sign. These terms can impact an uncertainty in a specific direction and therefore, have a specific + or - contribution to the total uncertainty. L represents positive biases and M rep-resents negative biases. When the maximum and minimum total uncertainty is desired, equation Cl can be rewritten to combine all positive biases and all negative biases in separate terms. Z+ = +[(A Z + B Z + C y) + (D+E)2]"' + G (Eq. CZ) Z-  Z + B z + C Z) + (D+E)2]h - H (Eq. C3) Where: Z, A, B, C, D, E, F, L and M are defined for equation C1, and G = (EIF+I) + (F.L), where F+ is the positive bias term sum (Eq. C4) H = (ELF-1) + (E1MI), where F" is the negative bias term sum (Eq. CS) The categorization of errors and uncertainties is shown in Appendix C, Figure 1. Random errors and uncertainties are provided using a value and a level of confidence. The combination of these errors and uncertainties MUST be evaluated at the same confidence level, e.g. 2Q, la, etc. NOTE: Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) PWR protection setpoints are calculated using the Westinghouse methodology. See the applicable Westinghouse WCAP and the individual protection setpoint calculations for a discussion of this methodology. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX C NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet C3 of C8 Accuracy Revision 4 Revision 4 ( NES-EIC-20
.04 1d CNCERTAINTY
' I RANDOM i APPROXIM,ATELYI i NONRANDOM TERMS NORMALLY i BIAS, DISTRIBUTED SYSTEMATK.) F t J ~- F7 -- INDEPENDENT DEPENDENT CORRECTION BIAS BIAS NON-NORMALL Y IKNOWNSIGN)
I (UNKNOWNSIGNI DISTRIBUTED ATTRIBUTES I i VARIABLE MAGNITUDE, RANDOM SIGN iFIXED, KNOWN 7VARIABLEORFIXED VARIABLE OR FIXED VARIABLE SIGN AND i MAGNITUDE AND MAGNITUDE AND MAGNITUDE MAGNITUDE KNOWN SIGN KNOWN SIGN RANDOM SIGN i UT4ERNAMES STATISTICAL, OFFSET SYSTEMATIC NONE NONE ACCIDENTAL, CORRELATED PRECISION COMBINATIONAL SRSS SRSS AFTER NOT I;SED TO COMBINE LIKE ABSOLUTE VALUE TO PRODUCE A RESTRICTIONS LINEAR SUMMING CALCULATE S~NSLINEARILY CONSERVATIVERFSULT
' CHANNEL UNCERTAINTY QUANTIFICATION TWOSIG,AAA(4S%)
PROBABILITY LEVEL 'CONSTANTS ESTVAATEDLIMITSOFERROR EQUATION TERMS ./-D, +;-E ~~NONE +L,-M +/-F Figure Cl, Uncertainty Model Braidwood, Byron, Dresden, Title APPENDIX C LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet C4 of CS Nuclear Engineering Standards Accuracy Revision 4 Revision 4 J NES-EIC-20
.04 2.0 UNCERTAINTY EQUATIONS USING EXELON (BRAIDWOOD, BYRON, DRESDEN, LASALLE, AND QUAD) SYMBOLOGY
 
===2.1 CALIBRATION===
 
ERROR The equation for calibration error (CAL) is defined using Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) symbology: CAL = +/-[(RAMTE + TEMTE)2 + REMTE 2 + STD 2] "2 (Eq. C6) where: RAMTE = M&TE Reference Accuracy TEMTE = M&TE Temperature Error REMTE = M&TE Reading Error STD = Calibration Standard Error and is determined from the following equation: STD = f[(RASTD + TESTD)2 + RESTD 2] 1n (Eq. C7) RASTD = Calibration Standard Reference Accuracy TESTD = Calibration Standard Temperature Error RESTD = Calibration Standard Reading Error Where both input M&TE and output M&TE are used in the calibration of a calibration block, Eq. C6 is rewritten as follows: CAL = +/-[(RAMTE, N + TEMTE, N)2 + REMTE, N Z + STD I N 2 + (RAMTE ouT + 2.2 TOTAL ERROR TEMTE ouT)2 + REMTE ouT + STDouT2] 1/2 (Eq. CS) The symbols shown in Appendix A, Table 1 can be substituted into equation C1 using the applicable default error classifications. Use of this equation should be consistent with the error classifications specific to each instrument loop. For example, if the vendor supplied drift error has been determined to be a bias error, an eD term would be added to the bias errors and the a o term would be removed. Z = t[6PE2 + aRA2 + a p e + CAL2 + ST 2 + 6IN2 ]''" t [eSP + eP + eV + Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards eT + eH + eR + eS + eIR + MAR] (Eq. C9) APPENDIX C NES-EIC-20
.04 Analysis of Instrument Channel "-'-'-Setpoint Error and Instrument Loop Sheet C5 of C8 Accuracy Title Revision 4 Revision 4 NES-EIC-20
.04 where: all random errors are at the same confidence level and, 3.0 TRIP SETPOINT The Trip Setpoint (SP) is calculated to provide a level of confidence that the setpoint function will occur prior an acceptance limit. For protection setpoints, this level of confidence is a 2a value for random errors and the analytical limit is the associated acceptance limit. Increasing_
Protection Setpoint SP = AL - (Z+MAR) (Eq. C 10) Decreasing Protection Setpoint SP = AL + (Z+MAR) (Eq. Cl 1) Other Increasing Setpoints SP = acceptance limit - (Z+MAR) (Eq. C 12) Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX C NES-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet C6 of CS Accuracy Revision 4 PE = Process Error RA = Reference Accuracy D Drift CAL Calibration Error ST Setting Tolerance IN Random input Error(s) esp Static Pressure Error eP - Pressure Error eV - Power Supply Error eT - Temperature Error eH - Humidity Error eR - Radiation Error eS - Seismic Error eIR - Error due to current leakage through insulation resistance MAR Margin (included only if applicable)
Revision 4 1 Other Decreasing Setpoints SP = acceptance limit + (Z+MAR) (Eq. C 13) where: SP = calculated trip setpoint AL = analytical limit Z = total uncertainty as defined in equation C9 or its equivalent MAR = margin, if applicable for an additional level of conservatism acceptance limit: any other limit chosen to ensure that a condition is not exceeded. Examples are: plant protection limits , personnel safety limits, equipment protection limits, radiation dose limits, EOP setpoints, etc. 4.0 ALLOWABLE VALUE NES-EIC-20
.04 The Allowable Value is calculated to provide acceptance criteria for evaluation of operability. It is a value, that if exceeded, may mean that the instrument loop, module or component is no longer performing within the assumptions of the setpoint calculation, the design basis or the Technical Specifications. The Allowable Value is typically used to evaluate the "as-found" trip setpoint with respect to a condition of operability. The Allowable Value is typically included in the station Technical Specifications. The Allowable Value is calculated by combining ONLY those errors that effect the "as-found' setpoint value and then adding or subtracting the combined error from the trip setpoint. Increasing Setpoint AV = SP + applicable uncertainty (Eq. C14) Decreasing Setpoint AV = SP-applicable uncertainty (Eq. C15) where: AV = Allowable Value SP = Calculated Trip Setpoint applicable uncertainty
= a value calculated from the errors and uncertainties that have been determined to effect the trip setpoint From all of the errors and uncertainties that have been determined to effect the trip setpoint, ONLY those that effect the as-found measurement are combined using equation C9 or its equivalent. For example, for an instrument channel where the as-found trip value is determined during a quarterly functional check, a test signal is applied to the instrument rack and the bistable is observed to change state. The total uncertainty consists of the input M&TE uncertainties, the instrument channel uncertainties, any environmental effects during the functional check and the setting tolerance. None of the sensor errors effect the Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX C NES-EIC-20
.04 Analysis of Instrument Channel '-`-Setpoint Error and Instrument Loop Sheet C7 of CS Accuracy Title Revision 4 Revision 4 I NES-EIC-20
.04 "as-found" setpoint value in this example, and would not be included in the applicable uncertainty for this setpoint when calculating an Allowable Value for the quarterly function check. 5.0 EXPANDED TOLERANCES An Expanded Tolerance is a value calculated from available instrument uncertainties that is used to evaluate an instrument's performance and it's potential degradation. Refer to ER-AA-520 for calculation of Expanded Tolerances. Braidwood, Byron, Dresden, Title APPENDIX C LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet C8 of C8 Nuclear Engineering Standards Accuracy Revision 4 A NES-EIC-20
.0 Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX D GRADED APPROACH TO DETERMINATION OF INSTRUMENT CHANNEL ACCURACY Revision indicated by a bar in right hand margin. fle Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy APPENDIX D ES-EIC-20.04 Sheet DI of D8 Revision 4 Revision 4
 
==1.0 INTRODUCTION==
 
The Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) setpoint methodology was developed and is defined by this standard to provide the basis, consistent with ANSI/ISA-67.04.01-2000, for the determination of instrument setpoints, allowable values and instrument loop accuracy. This ISA standard defines the requirements for establishing and maintaining setpoints for nuclear safety-related instrumentation. In addition, ISA-RP67.04.02-2000 provides guidance for implementing ANSUISA-67
.04.01-2000 and imposes rigorous requirements for instrument uncertainty calculations and setpoint determination for safety-related instrument setpoints in nuclear power plants. ISA- RP67.04.02-2000 recognizes that the historical focus of ANSUISA-67
.04.01-2000 was the class of setpoints associated with the analytical limits as determined in the accident analysis. These setpoints have typically been interpreted as the reactor protection (RP) and emergency safety features (ESF) setpoints The RP and ESF setpoints are those critical to ensuring that the integrity of the multiple barriers to the release of fission products are maintained. The Recommended Practice also states that setpoints that are not part of the safety analysis and are not required to maintain the integrity of the fission product barriers may not require the same level of rigor or detail as described by the Recommended Practice. For these non-RP and non-ESF setpoints, a graduated or "graded" approach is appropriate for setpoints that: " provide anticipatory inputs to the RP or ESF functions, but are not credited in the accident analysis or, " support operation of, but not the initiation of, the ESF setpoints. T NES-EIC-20
.04 ISA draft Technical Report, ISA-dTR67.04.09, "Graded Approaches to Setpoint Determination", is being prepared to provide further guidance in establishing classification schemes for setpoints and recommending an approach to translate these classification schemes into a methodology for determination of instrument loop accuracies and setpoints. The technical report requires that a "graded methodology" provide a consistent hierarchy of both rigor and conservatism for classifying, determining and subsequently maintaining setpoints. This appendix provides a classification scheme and the associated graded methodology for the determination of instrument loop accuracy at Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) nuclear stations. The instrument loop accuracy may then be used to determine the associated instrument setpoints The Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) "graded methodology" is summarized in Table D1. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX D NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D2 of D8 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 2.0 CLASSIFICATION The Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) graded methodology classifies instrument setpoints into four levels. These correspond to a "level of confidence" that the setpoint will perform its function with respect to a limit or other limiting criteria. These levels range from Level 1, which provides the highest confidence, to Level 4, which may only document engineering judgment. The following sections identify instrument channel functions and the minimum level of confidence used when determining instrument loop accuracy. Those individuals preparing and reviewing instrument loop accuracy calculations may choose to perform a particular instrument loop accuracy calculation using a higher level of confidence. This basis for this decision shall be fully documented in the instrument loop accuracy calculation. It is not the intent of this standard to identify every instrument function encountered in a nuclear station. The following sections should provide sufficient guidance for selecting the appropriate level of confidence for those instrument functions not explicitly identified. Care should be taken to ensure that the function of the setpoint is clearly identified and that the instrument loop accuracy is determined consistent with the following levels. 2.1 LEVEL 1 This level is consistent with the definition of nuclear safety-related instrumentation in ANSUISA-67
.04.01-2000. These instruments provide setpoints that: 1) Provide emergency reactor shutdown 2) Provide containment isolation
: 3) Provide reactor core cooling 4) Provide for containment or reactor heat removal 5) Prevent or mitigate a significant release of radioactive material to the environment or is otherwise essential to provide reasonable assurance that a nuclear power plant can be operated without undue risk to the health and safety of the public For Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) nuclear stations, this specifically includes all reactor protection system (RPS), emergency safety features (ESF), emergency core cooling system (ECCS), primary containment isolation system (PCIS) and secondary containment (SCIS) setpoints. Braidwood, Byron, Dresden, itle APPENDIX D LaSalle, and Quad Cities NES-EI C-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D3 of DS Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04 2.2 LEVEL 2 This level will include those setpoints that: 2.3 LEVEL 3 1) Ensure compliance with Technical Specification but are not level 1 setpoints. 2) Provide setpoints or limits associated with RG 1.97, category A variables. 3) Provide setpoints or limits associated with station emergency operating procedure (EOP) requirements. The RG 1.97 category A variables are included in Level 2 since they provide the primary information required to permit the control room operator to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events. Level 2 instrument loops are typically associated with those setpoints that provide the station operator with specific action values or limits used to verify plant status. This includes instrument loops that provide an indication of acceptable performance for structures, systems and components in the Technical Specifications. Setpoints or limits contained in station EOP's that are RG 1.97 category A variables, or setpoints that provide specific action values are included in Level 2. Other EOP setpoints may be either Level 2 or 3 depending on their function. This level will include those setpoints that: 1) Provide setpoints or limits associated with RG 1.97, category B, C or D variables. 2) Provide setpoints or limits associated with other regulatory requirements or operating commitments, e.g. OSHA, EPA, etc. 3) Provide setpoints or limits that are clearly associated with personnel safety or equipment protection. The RG 1.97, category B, C and D variables are associated with contingency actions and may be included in EOP's or other written procedures. Classification of EOP setpoints as a Level 3 setpoint shall be approved by the station EOP coordinator or other individual designated by the station operations department. Braidwood, Byron, Dresden, Title APPENDIX D LaSalle, and Quad Cities NES-EIC-2 0.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D4 of D8 Nuclear Engineering Standards Accuracy Revision 4 Revision 41 1 NES-EIC-20
.04 2.4 LEVEL 4 This level will include those setpoints that: 1) Provide setpoints or limits not identified with the requirements in levels l, 2 or 3 above. 2) Require documentation of engineering judgment, industry or station experience, or other methods have been used to set or identify an operating limit. Level 4 shall provide documentation of all non-Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) methodologies used to establish instrument loop accuracies or instrument setpoints. 3.0 DETERMINATION OF INSTRUMENT LOOP ACCURACY 3.1 LEVELS OF CONFIDENCE The level of confidence associated with the calculation enforces a gradation in rigor and conservatism to the instrument loop accuracy evaluation. Level 1, the highest level of conservatism, is typically associated with a 95% level of confidence that the setpoint will provide its intended function prior to limit or limiting condition. Levels 2, 3 and 4 provide decreasing levels of confidence by allowing various additions to the methodology used to calculate and combine errors and uncertainties. At Level 4, the instrument loop accuracy may not be associated with any clearly identified level of confidence other than experience. The methodology associated with each level is shown in Table D1. 3.2 LEVEL 1 Calculation of instrument loop accuracy, instrument setpoints and allowable values in Level 1 shall use the equations in App. C. These equations use a 2a level of confidence and require that determination of instrument loop accuracy always err on the side of conservatism. Level 1 setpoints are consistent with ISA 67.04.01-2000 and ISA RP67.04.02-2000. in order to ensure that protective actions occur 95% of the time with a high degree of confidence before the analytical limits are reached. 3.3 LEVEL 2 Level 2 instrument loop accuracy is calculated using the equations in Appendix C with the following exceptions
: Braidwood, Byron, Dresden, Title APPENDIX D LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D5 of D8 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 ( NES-EIC-20
.04 3.4 LEVEL 3 3.5 LEVEL 4 1) Random errors are evaluated at a la level of confidence
: 2) Bias errors may be combined using SRSS in accordance with Reference 3.11 3) Where it can be determined that a setpoint function is only evaluated in a single direction, either increasing or decreasing, single side o&#xac; interest confidence levels may be utilized (reference 3.2, section 8.1 ). Level 3 instrument loop accuracy is calculated using the equations in Appendix C, the exceptions in Level 2 and the following additional exceptions
: 1) Uncertainties applicable to the entire instrument channel are used wherever available, e.g. channel drift and channel temperature uncertainty vs. module-/component drift and module/component temperature uncertainty. 2) Where all terms are expected to be approximately normally distributed and the number of terms is >_4, the sum is assumed to be approximately distributed. Therefore, all terms can be combined using SRSS. 3) For bistables, the RA term does not require inclusion of the hysteresis/linearity components. Only the RA uncertainty OR the ST uncertainty, whichever is larger shall be used Level 4 instrument loop accuracy may be calculated using the equations in Appendix C and include the exceptions in Level 2 and 3. For calculations associated with Level 4 instrument loops, the basis for determining the instrument loop accuracy shall be documented. Braidwood, Byron, Dresden, Title APPENDIX D LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D6 of D8 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 NES-EIC-20
.04 Table D1, Graded Methodology Braidwood, Byron, Dresden, Title APPENDIX D NES-EIC-20
.04 LaSalle, and Quad Cities Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D7 of D8 Nuclear Engineering Standards Accuracy Revision 4 LEVEL TYPICAL APPLICATION METHO- DOLOGY APPLICABLE UNCERTAINTY METHODS 1 " Protection setpoints 2a + Ee; " Consistent with ISA 67.04.01-2000 " ESF/RPS/ECCS and ISA RP67.04.02-2000. " PCIS/SCIS " Ensures protective actions occur 95% of the time with a high degree of confidence before the analytical limits are reached. " Random and bias error combination
: Z=+/-[A 2+B 2+ C 2+ (E+ F)2]t/i t qFj) + (L) - (M) Z = resultant uncertainty, combination of random and bias uncertainties A,B,C = random, independent terms D,E = random dependent terms (independent of A,B and C) F = abnormally distributed uncertainties and/or bias (unknown sign) L,M = biases with known sign 2 " EOP operator action setpoints a + Ee; " Bias errors combined using SRSS in " RG 1.97 Type A variables accordance with ASME PTC 19.1: e i = +/-[F2 + L 2 + M2]''/z where F, L and M are bias errors as shown above " Single side of interest confidence interval evaluation where the evaluated setpoint is in a single direction: Z = 0.4686 + Eei Revision 4 1. NES-EIC-20
.04 Table D1(cont.), Graded Methodology Braidwood, Byron, Dresden, Title APPENDIX D LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet D8 of D8 Nuclear Engineering Standards Accuracy Revision 4 LEVEL TYPICAL APPLICATION METHO- DOLOGY APPLICABLE UNCERTAINTY METHODS 3 " RG 1.97 Type B, C & D a + Le; " Uncertainties applicable to the entire variables instrument channel are used wherever available, e.g. channel drift and channel temperature uncertainty vs. module/component drift and module/- component temperature uncertainty. " Single side of interest confidence interval evaluation where the evaluated setpoint is in a single direction: Z=0.4686+Lei " Where all terms are expected to be approximately normally distributed, the sum is assumed to be approx- imately distributed for n?4: Z = (a n t + e n 2]'/z " For bistables, the RA term does not require inclusion of the hysteresis/linearity components, therefore use the RA uncertainty OR the ST uncertainty, whichever is larger. 4 " Documentation of setpoint as appropriate " Engineering Judgment shall be accuracy (e.g. non-safety, non- documented tech spec compliance) " Other regulatory related " Engineering evaluation/conclusions setpoints (consequences of non- shall be documented compliance are deemed acceptable) " Vendor, Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad), or other methodologies may be utilized where appropriate Revision NES-EIGM04 APPENDIX E REACTOR WATER LEVEL TO SENSOR dP CONVERSION Latest Revision indicated by a bar in right hand margin. Braidwood, Byron, Dresden, Tide APPENDIX E LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet El of E8 Nuclear Engineering Standards a Accuracy Revision 4 j Revisioln 4 NES-EIC-20
.04 (.0 PURPOSE Differential pressure transmitters are used to monitor reactor vessel water level in a l3WR. Reactor vessel level is typically described by elevation from a reference level with units of "inches Reactor Water Level" or "in. RWL", while sensor dP is measured in units of pressure such as "inches water column" or "in.WC". For example; 380.87 in. WC may correspond to a range of -340 in. RWL to +60 in. RWL. When converting between vessel level and sensor V, changes in process conditions inside the reactor vessel and changes in environmental conditions must be accounted for. As shown in Figure E1, the sensing lines that connect the dP sensor and the reactor vessel are effected by at least 2 different environmental zones; the drywell and the reactor building. Each of these environmental zones has its own normal temperature deviations. During accident conditions, such as recirculation line break, each of these zones may experience significant temperature increases at the transmitter location or within the drywell. This appendix will provide: 1) a conversion factor between "in. RAU' and the equivalent dP at the sensor as measured in "in.WC" 2) an equation to calculate changes in sensor dP that result from changes in the drywell and/or reactor building temperature. 3) a scaling conversion factor for changes to sensor dP that result from changes in process conditions. 2.0 CONVERSION OF "in. RWL" TO SENSOR dP IN "in.WC" The differential pressure between the high and low inputs of a differential pressure transmitter is: dP = P H - P L . E I ) where: P H = the sum of the hydrostatic head pressures at the high sensor input P L = the sum of the hydrostatic head pressures at the low sensor input Braidwood, Byron, Dresden, Title APPENDIX E LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E2 of E8 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 NES-EIC-20
.04 Hydrostatic pressure head is given by: P = Pgz (Eq. E2) where: P P g z Using the definition of specific weight, 7= pg, the equation for dP is: dP = 7(z2 -z1) (Eq. E3) Using Figure E l, we can define a conversion constant (K) as the change in reactor water level (L) for a change in sensor dP. Referring to Figure El for the associated elevations, the dP resulting from a level, L, is: dl? = 72(Ec -EPH -ENL +EPL) + 73(EPH -EPL) - 74(EC - L) - 71(L -ENL) (Eq. ES) An incremental change in dP, given by dP + 6dP, is a result of a corresponding incremental change in level, L + SL: dP + SdP Solving for the change in dP by subtracting equation ES from equation E6: SdP= (dP + W) - (R) = f- 74(Ec - (L + SL)) - 71((L + 6L) -ENL)] - f- 74(Ec - L) - 71(L - ENL)I Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards pressure density of the fluid (lbm/ft 3) gravitational constant height of the column of fluid =72(E4 - EPH - ENL + EPL) + 73(EPH - EPL) - 74(Ec - (L + (5L)) - 71((L + SL) - ENO (Eq. E6) 8L(74-71) (Eq. E7) APPENDIX E NES-E IC-20.0 4 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E3 of E8 Accuracy Title Revision 4 Revision 4 NES-EIC-20
.04 For the change in sensor dl? corresponding to a I inch change in reactor vessel water level: SL = I in. RWL From equation E4: &iP in. WC K= 6L =(Y4-Y1)in.RWL 3.0 CHANGES IN SENSING LINE AND SENSOR ENVIRONMENT Changes in sensor dP will result from changes in the drywell environment and/or changes in the reactor building environment due to changes in density of the sensing line fluid. For example: " changes from calibrated environmental conditions to the maximum or minimum normal environmental conditions. " changes from maximum normal environmental conditions to maximum accident conditions. Using Figure E 1, we can define the sensor dl? for 2 different environments. Environment 1 dPLI &deg; [y2-1(Ec - EPH ) + y3-1(EPH - E x)] - IYI-1(Ec - L l) + y41(L l - ENO where: Ll = 72-1 = 73 + 72-1(ENL - EPL) + 73-1 (EPL - Ex) (Eq. E8) 72-1(Ec - EPH - ENL + EPL) + y3- I (EPH - EPL) - 741(Ec - L 1) - y-1 (L l - ENL) (Eq. E9) reactor vessel water level (in. RWL) at condition 1 spec. wgt. of saturated fluid in the reactor vessel at condition 1 spec. wgt. of fluid in that portion of the sensing lines in the drywell at drywell temperature 1 spec. wgt. of fluid in that portion of the sensing lines in the reactor building at reactor building temperature 1 spec. wgt. of saturated vapor in the reactor vessel at condition 1 Braidwood, Byron, Dresden, Title APPENDIX E LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E4 of E8 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 - - ( NES-EIC-20
.04 Environment 2 where: L2 = Y,-2 = Y2-2 = Y3-2 = Ya-2 = If we assume all changes between environment 1 and environment 2 are limited to changes in the drywell and reactor building environments
: Ll = L2 = YI-2 Ya-1 = Ya-2 The change in sensor dP from condition 1 to condition 2 is: 3.1 EXAMPLE AdP = dP L2 - dPL1 = RY2 Y2_i)(EC - EPH - ENL + EPL)l + L(Y3 Y3-l)(EPH - EPL)J To calculate the process error due to a LOCA, we need to determine the change in sensor dP between maximum normal environmental conditions and the maximum accident environmental conditions in the drywell and reactor building. This is typically calculated at a specific reactor vessel level, e.g. one of the vessel level protection setpoints. In addition, in order to calculate a bounding change, the following assumptions apply: 1) Transient effects are ignored. It is assumed that the sensing lines are at thermal equilibrium with their environment. 2) Reactor vessel process conditions do not change, only the sensing line environments are effected by the LOCA. Obviously the reactor vessel saturation conditions will change if a scram occurs, but in this example we are looking only for the process error at the protection level setpoint. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards
= (2-2(Ec - EPH - ENL + EPL) + Y3-2(EPH - Ep) 2(Ec - L2) - Y,_2 (L2 - ENO (Eq. E 10) reactor vessel water level (in. RWL) at condition 2 spec. wgt. of saturated fluid in the reactor vessel at condition 2 spec. wgt. of fluid in that portion of the sensing lines in the drywell at drywell temperature 2 spec. wgt. of fluid in that portion of the sensing lines in the reactor building at reactor building temperature 2 spec. wgt. of saturated vapor in the reactor vessel at condition 2 (Eq. E 11) Title APPENDIX E NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E5 of E8 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 From equation E 11: OdP = where: Yen = 72a = Yin Yea = 4.0 REACTOR WATER LEVEL SCALING [(y2a - 72n)(Ec - EPH - ENL + EPA + [(7-1.- 73n)(EPH - EPL)] (Eq. E12) spec. wgt. of the fluid in that portion of the sensing lines in the drywell at the maximum normal environment. spec. wgt. of the fluid in that portion of the sensing lines in the drywell at the maximum accident environment. spec. wgt. of the fluid in that portion of the sensing lines in the reactor building at the maximum normal environment spec, wgt. of the fluid in that portion of the sensing lines in the reactor building at the maximum accident environment. Using equation E8 and equation E 12, we can calculate the equivalent change in reactor vessel water level: ORWL = A dP (74-70 ARWL= ((72a -72n)(E c -E PH -E NL +EPL)l+1(73a -73n)(E PH -E PA (74-71) (Eq. E 13) Reactor vessel level is typically provided in inches above or below some reference, e.g. top of active fuel (TAF). In order to determine the correct dP transmitter scaling we use equation E5 to determine the dP at normal process conditions and normal drywell and reactor building environments. This dP must then be converted to the equivalent dP at calibration conditions. Transmitter calibration is typically performed at cold shut-down conditions where the reactor vessel vapor space contains air and it is assumed that the vessel fluid, drywell and reactor building are at the same temperature. From equation E8, we see that the conversion from sensor dl? to in. RWL is a function of the process conditions and is not effected by the sensing line environmental conditions. Braidwood, Byron, Dresden, Title APPENDIX E NES-EIC-20
.04 LaSalle, and Quad Cities Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E6 of E8 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 At normal process conditions
: dP P - Y4 -YI dL P At calibration conditions
: Therefore: dP c dL c =PAIR-YCF For scaling dP values, we define a conversion factor that provides the equivalent change in reactor vessel level for a given sensor dP when we change from calibration conditions to the normal process conditions. From equations E14 and E15, this is equivalent to dP c = dPP dLc(7AIR - yc ) = dL P (, y 4 - Yi) (Eq. E 16) dL P = T AIR -7C Ks _ dLc Y4 -71 When using standard steam tables, it is convenient to rewrite equation E 17 as a ratio of specific volumes. Neglecting the specific weight of air, conversion factor K s is: K s = `' ' (Eq. E18) vc(v4 - vi) Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards vessel level at process conditions K - SW&deg;`&deg;"ST" NT vessel level at calibration conditions Title NES-EIC-20
.04 (Eq. E 14) (Eq. E15) (Eq. E 17) APPENDIX E NES-E IC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E7 of E8 Accuracy Revision 4 Revision 4 4 NES-EIC-20
.04 Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards yi - specific weight of the saturated fluid in the reactor vessel y, - specific weight of the fluid in the sensing lines located in the drywell 7 3 specific weight of the fluid in the sensing lines located in the reactor building 7 4 - specific weight for the saturated vapor in the reactor vessel E NL - elevation of the lower nozzle E NH - elevation of the upper nozzle Ec - elevation of the condensate pot EP,, - elevation of the lower penetration EPu - elevation of the upper penetration E X elevation of the sensor L - Water Level (in. RWL) Figure El, Reactor Vessel Water Level and Sensor dP Title APPENDIX E NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet E8 of E8 Accuracy Revision 4 Revision 41 1 NESTIC-20A4 APPENDIX F TEMPERATURE EFFECTS ON LEVEL MEASUREMENT Latest Revision indicated by a bar in right hand margin. Braidwood, Byron, Dresden, Title APPENDIX F LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet Fl. of F14 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 - T NE S-EIC-20.04
 
==1.0 INTRODUCTION==
 
Differential pressure level measurement systems are typically calibrated for a specific set of operating conditions, i.e. processes pressure and reference leg temperature. If either of these conditions change, an error will be introduced between the actual level and the indicated level. This is due to changes in the dP at the sensor and results from changes in fluid density and not from changes in actual level. Since this error is of known magnitude and known direction (based on the difference between the calibrated condition and the new process and/or environmental condition), it is treated as a bias error. This appendix provides simplified formulas for estimating the effects of: " process pressure changes (assuming that the vessel is at saturation conditions), " environmental changes (assuming that the reference leg fluid temperature is at equilibrium with the environment), and " both process changes and reference leg temperature changes acting simultaneously to produce a worst case bias under specified conditions. 2.0 ERROR FRACTION When evaluating the effects of process and environmental changes on level measurement accuracy, it is convenient to consider these effects as changes from the known (or calibrated) condition. Using this concept, the level error is a function of how much the indicated level differs from the actual level. The indicated level (IND LVL) corresponds to the transmitter scaling relationship where transmitter output is a function of the dP applied to the transmitter. The scaling relationship should be based on specific process conditions and specific environmental conditions. The actual level (ACT LVL) will then deviate from the indicated level (IND LVL) as a function of the deviation of the process and environmental conditions from the calibrated conditions. This difference between indicated level and actual level is defined as the "error fraction" (E)`: E = % IND LVL - % ACT LVL This appendix will use units of % level which is consistent with typical level measurement scales where indicated level ranges from 0% to 100% level. While units of level, and consequently E could be in other units, the derivations are simplified if % level is chosen. Z The term "error fraction" and the equation E = % IND LVL - % ACT LVL, is consistent with the steam generator level protection and EOP setpoint accuracy evaluation originally provided by Westinghouse and currently incorporated in Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) setpoint accuracy calculations for Byron and Braidwood stations. itle APPENDIX F Braidwood, Byron, Dresden, LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F2 of F14 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 If E is calculated (regardless of the units of level measurement), the effects of temperature related errors on bistable or EOP setpoints can be evaluated. Table F1 can be used to determine if level bias error must be included in the instrument loop accuracy or may be ignored. These equations assume: Table Fl, Error Fraction Effect on Instrument Setpoints. 3.0 PROCESS FLUID DENSITY CHANGES The following equations may be used to calculate indicated level and the error fraction resulting from process fluid density changes. 1) saturated conditions inside the vessel The occurrence of subcooling in the downcomer region of PWR steam generators, which becomes significant above 70% RTP is typically included in instrument loop accuracy calculations, but is calculated through other mechanisms. 2) an actual steam generator level There is no actual level in the steam generator while generating steam. A transition zone exists between the saturated fluid and saturated vapor. The following equations calculate the actual level L as the collapsed level. 3) steady state process conditions Transient effects, such as rapid depressurization, are not included and would require a much more complicated analysis. 4) thermal equilibrium The reference leg fluid temperature is considered to be in equilibrium with the environment. Typical condensing pot installations are located close to the vessel. This results in the H L/H term in the following equations being sufficiently close to t for this term to be ignored. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards (Title APPENDIX F NES-EIC-20
.04 Analysis of Instrument Channel - Setpoint Error and Instrument Loop Sheet F3 of F14 Accuracy Revision 4 sign of E is positive (IND LVL > ACT LVL) sign of E is negative (ACT LVL > IND LVL) Increasing setpoint bias error will be conservative and bias error is non-conservative may be ignored and must be included in the instrument loo accuracy Decreasing setpoint bias error is non-conservative and bias error will be conservative must be included in the instrument and may be ignored loo accuracy Revision 4 ( NES-EIC-20
.04 3.1 FORMULAS For an actual level L, the indicated level will be: The error fraction for process fluid density changes is: E=%INDLVL-%ACTLVL
_E _ HL 100 H Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards
% INDLVL=~HLC PL'-Piz-Pgt
+Pg?+LC Prz-Pg''~lx100 PfI -P~i ) H PFi -P g where: all terms are defined in Figure Fl, and L, H and H L are in consistent units of length (e.g. inches) C PL -PLa-Pgi +Pg2J Pfi -P g I _L +H C Pf2 -P g r _ l1 Pf, -P g JI Title APPENDIX F NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F4 of F14 Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04 dl? 0% IVI Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards PLIgHL - (pf,gH + PgIg(HL- H)) gHL(PLI - Pgl) - gH(pfl - Pgl ) pLIg H L - PgIgHL gHL(PLI - Pgl) L - distance from lower tap to fluid level H - distance from lower tap to upper tap H~ -distance from lower tap to center line of condensing pot D, -fluid density D, - vapor density D, reference leg fluid density T I , P I temperature and pressure inside the vessel at calibrated conditions Pfl , P g , - density of saturated liquid and steam at calibration conditions T I and P I T 2 , P 2 temperature and pressure inside the vessel at some new condition Pa , Pat - density of saturated liquid and steam at the new conditions T 2 and P 2 T REF LEG - temperature of the environment and reference leg fluid PLI - density of reference leg liquid at T REF LEG and P t (compressed liquid) PL - density of reference leg liquid at T REF LEG and P 2 (compressed liquid) Figure Fl: Level Bias Error Due to Process Fluid Density Changes 3.2 DERIVATION Calculate the transmitter 0% and 100% level for the dP at TI and PI conditions
: f itle APPENDIX F NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F5 of F14 Accuracy Revision 4 Revision 4 j NES-EIC-20
.04 Calculate the transmitter dP at L% level for the dP at T2 and P2 conditions
: L% _ (L/H)x100%
lvl CIP L% IvI - Calculate the indicated level at the known dl? for L% level with respect to the calibrated transmitter dP: % IND LVL = dPL&deg;/` lvl - dP a% Iv, x 100 0 100% Iv, - dP 0% Iv, ~[gHL(PL2
-P g 2)-gL(Pf2 -P g 2)l-[gHL(PLI -P g I)] l.fgHL(PLI
-PgI)-gH(Pf, -Pgt)]-[gHL(PLI -P a gI)] (HL I PLI -PL2 -PgI +Pg2 1 + L ~Pf2 -Pg2 1 1 The error fraction is: H E=%IND LVL-%aACT LVL PLZgHL - (PIgL + Pg2g(HL - L)) P L2 gH L - p,gL - pg2gHL + Pg2gL g H L(PLZ - P g2) - gL(p Q - Pg2) (PLI -PLZ -PgI +Pg2 + L C Pf2 -P g 2~j Pf1-P g I ) H Pfl -P g I E _H L ( PLI -PL2 -P g I +Pg2 I + L (Pfa -Pg2 _ 11 100 H ~ Pf,-Pgl H ~ Pf, -P g I H~Pf, -PgI )) x loo- H) x 100 x 100 x 100 x 100 Braidwood, Byron, Dresden, Title APPENDIX F LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F6 of F14 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 4.0 REFERENCE LEG HEATUP Changes in ambient temperature will effect the density of the fluid in the reference leg. The following equation may be used to calculate the error fraction for reference leg heatup. These equations assume: 1) saturated conditions inside the vessel The occurrence of subcooling in the downcomer region of PWR steam generators, which becomes significant above 70% RTP is typically included in instrument loop accuracy calculations, but is calculated through other mechanisms. 2) an actual steam generator level There is no actual level in the steam generator while generating steam. A transition zone exists between the saturated fluid and saturated vapor. The following equations calculate the actual level L as the collapsed level. 3) steady state process conditions Transient effects, such as rapid depressurization, are not included and would require a much more complicated analysis. 4) thermal equilibrium The reference leg fluid temperature is considered to be in equilibrium with the environment. Typical condensing pot installations are located close to the vessel. This results in the H i/H term in the following equations being sufficiently close to 1 for this term to be ignored. 4.1 ERROR FRACTION The error fraction for changes in reference leg temperature is: E=%INDLVL-%ACTLVL v _E ___HL P1 _P2 100 H Pf -p g) where: - all terms are defined in figure F2, and - L, H and H L are in consistent units of length (e.g. inches) Braidwood, Byron, Dresden, Title APPENDIX F LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F7 of F14 Nuclear Engineering Standards Accuracy Revision 4 Revision 41 NES-EIC-20
.04 Pf, Pg T1 Pl T2 P2 Figure F2: Level Bias Error Due to Reference Leg Heatup 4.2 DERIVATION Calculate the transmitter dP at 0%, 100% and L% level for the calibrated (T I) conditions
: Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards density of saturated liquid and vapor in the vessel environment and reference leg temperature at the calibrated condition density of liquid in the reference leg at calibration conditions environment and reference leg temperature at the new condition density of liquid in the reference leg at a new environmental temperature Pig H L - PggHL gH L (P l - P ) Title p i gH L- ( p t gH + p 9 g(H L - H)) g H L(PI - pg) - gH(P F- p 9) L - distance from lower tap to fluid level H - distance from tower tap to upper tap H, - distance from lower tap to center line of condensing pot D, - fluid density D, - vapor density q. - reference leg fluid density APPENDIX F NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F8 of F14 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 Calculate the transmitter dP at 0% and 100% level for the T2 conditions
: P,gH L - PggHL = gH L (P, - P) p,gHL - (p t gH + P g g(H L - H)) gHL(P, - Ps) - gH(p r- P g) (L/100)(dPI 100% IVI - dPlo%, IVi) +dPlo1k IVI (L/100)(gH L (P, - P g) - gH(P f - P g) - gH L (P, - Pg)) + gH L (P I - Pg) gH L (p, - P Q) - (LgH/100)(p f- p g) This derivation uses a different, but more realistic concept. Starting with the indicated level that we observe, the actual level is calculated by including the effect of changes in reference leg density. Since level vs. dP is a linear relationship, a ratio is used to determine the actual level. Figure F3 will help in visualizing the required ratio. actual IevelO level 100 dP dP2 0% dPL dP2 f00% Figure F3, % Level vs. dP ACT LVL- 0&deg;k 100% - 0% dP 2 100170 - dP2 ACT LVL= dPL -dP2&deg;% X 100 W 2 100/0 - 0090 The indicated level is equal to the calibrated M, therefore: Braidwood, Byron, Dresden, itle APPENDIX F LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel [Setpoint Error and Instrument Loop Sheet F9 of F14 Nuclear Engineering Standards I Accuracy Revision 4 Revisiot><
4 NES-EIC-20
.04 ACT LVL = dP L = dPlL ` LgH 1 gHL(P,-P,)-( IOOJ(Pf-Pg)-gH,(P2-Pg)~
The error fraction is: _E 100 gHL(P2-P g) -gH(Pf -P g) -gHI(P2-P,) -H L H Pg-P2+Pg)
LH LH (Pf 100 P1 -P2 ~Pf -P g) -H(Pf -Pg) HL P1 -P2 H (p f -P g 1 _L 100) HL I P1 -P2 _ H x 100 E = % IND LVL - % ACT LVL Pg ) l~ =L-~-HL C PS -Pz 1 + x 100 H Pf -Ps 100 r w x100-L x 100 x 100 5.0 SIMULTANEOUS EFFECTS OF REFERENCE LEG HEATUP AND PROCESS FLUID DENSITY CHANGES When process changes and environmental changes interact, e.g. LOCA or steam breaks inside containment, or where a bounding error term is desired, the following equation can be used to calculate the error fraction. Braidwood, Byron, Dresden, Title APPENDIX F LaSalle, and Quad Cities N ES-EIC-20.0 4 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F10 of F14 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 NES-EIC-20
.04 These equations assume: 1) saturated conditions inside the vessel The occurrence of subcooling in the downcomer region of PWR steam generators, which becomes significant above 70% RTP is typically included in instrument loop accuracy calculations, but is calculated through other mechanisms. 2) an actual steam generator level There is no actual level in the steam generator while generating steam. A transition zone exists between the saturated fluid and saturated vapor. The following equations calculate the actual level L as the collapsed level. 3) steady state process conditions Transient effects, such as rapid depressurization, are not included and would require a much more complicated analysis. 4) thermal equilibrium The reference leg fluid temperature is considered to be in equilibrium with the environment. Typical condensing pot installations are located close to the vessel. This results in the H L/H term in the following equations being sufficiently close to I for this term to be ignored. 5.1 ERROR FRACTION E = % IND LVL- % ACT LVL E = - H L (PLI - PL2 -P g l +Pg2 + L Pf2 -Pg2 11 Pf I - P g 1 -) H ( p f , -p gl where: - all terms are defined in figure F4, and L, H and H L are in consistent units of length (e.g. inches) Braidwood, Byron, Dresden, Title APPENDIX F LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel _ Setpoint Error and Instrument Loop Sheet F11 of F14 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04 T REE LEG I T I , P I temperature and pressure inside the vessel at calibrated conditions pfI' pgl - density of saturated liquid and steam at calibration conditions T I and P t T I , P I temperature and pressure inside the vessel at some new condition pf2, Pg2 - density of saturated liquid and steam at the new conditions T I and P Z T REFLEGI - temperature of environment and the liquid in the reference leg PLI - density of reference leg liquid at T REFLEGI and P I (compressed liquid) T REFLEGI - temperature of environment and the liquid in the reference leg pLI - density of reference leg liquid at TREFLEGI and P, (compressed liquid) Figure F4, Level Bias Error Due to Both Process Fluid Density Changes and Reference Leg Heatup 5.2 DERIVATION Calculate the transmitter dP at 0% and 100% level for the calibrated conditions T I , P I and dP l I OU% IVI Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards PLIgHL - (prIgH + p g lg(H L - H) gHL(PLI - p gt) - gH(P fl - Pgl) PLIg H L - PgIgHL gHL(PLI - Pgt) L - distance from lower tap to fluid level H - distance from lower tap to upper tap H, - distance from lower tap to center line of condensing pot D, -fluid density D -vapordensity
: g. -reference leg fluid density title APPENDIX F NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F12 of F14 Accuracy Revision 4 Revision 4 l NES-EIC-20
.04 Calculate the transmitter dl? at L% level for the new conditions T2, P2 and TREE LEG2: dP2 % IND LVL= dPLT KI - dPO,r IV[ x 100 dPI00% IV , - dP Q% IV , Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards PL2gHL - (P, z gL + P g2 g(H L - L)) PLzgHL - PezgL - Pg2gHL + Pg2gL g H L (P,.2 - P g 2) - g L (P,z - Pg2) Calculate the indicated level (in % indicated level) for a dP = dP2 at the calibrated Ly~ tvi conditions T I , P I , and TREFLEGI'
[gHL(PL2 -Pg2)-gL(Pf2 -Pg2)l-[gHL(PL1 -Pg,)l x 100 fgHL(PLI -P g i)-gH(Pf, -P g i)l-LgHL(PLI -P g i)l HL(PL2 -P g 2 -PLC +P g t)-L(Pfz -Pg2) x 100 -H(Pf, -P g ,) ~HL ~PLI -P-2 -Pgi +Pg2 1 L (Pf2 -Pgz 1) H ~ PfI -P g t H~Pf, -P g j )) The error fraction is: E = % IND LVL - % ACT LVL Pfl-P g l ) HIPf,-P g I )) _E H L PLI -PL2 -P g l +P g 2 + L Pf2 -P g 2 1 100 Pfl H -Pgt ) HCPft -P g i -~ x 100 r HL ~PLI -PL2 -Pii +Pg2 1 L + ~Pfz -Pgz lI x 100- (L H) x 100 Title APPENDIX F NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F13 of F14 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 6.0 REFERENCE LEG BOILING In addition to process and reference leg density changes, boiling could conceivable occur in the reference leg due to rapid depressurization. Boiling or other gases coming out of solution in the reference leg would result in a large level error for a short period of time. For PWR plants, both pressurizer level and steam generator level could be effected by reference leg boiling. Analysis of chapter 15 events and containment analysis for Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) PWR stations indicate that no reference leg boiling is expected that would effect a protection setpoint. For pressurizer level setpoints, the RCS pressure is not expected to decrease below 1400 psig during a transient which prevents reference leg boiling. The accidents that rely on steam generator low level setpoints are not expected to experience depressurization at a rate that would result in reference leg boiling. NOTE: transients that could result in hydrogen coming out of solution in the pressurizer reference leg are not currently addressed in the setpoint analyses. For BWR plants, the possibility of reference leg boiling and reactor vessel level errors due to dissolved gasses coming out of solution has been addressed. The RVLIS/Backfill modifications have been installed in accordance with Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWR's Pursuant to l OCFR50.54(f). Setpoint accuracy calculations and reactor vessel level scaling calculations incorporate the effects of this modification on the associated reactor protection setpoints.
 
==7.0 REFERENCES==
 
7.1 CAE-92-189/CCE-92-201/CWE-92-214, Commonwealth Edison Company, Zion/Byron/Braidwood Stations, SIG Water Level PMA Term Inaccuracies, dated 6/18/92 7.2 CWE-79-26, Commonwealth Edison Company, Zion Station, NRC IE Bulletin 79-21, dated 8/29/79 7.3 NRC IE Bulletin 79-21, Temperature Effects on Level Measurements 7.4 "Delta-P Level Measurement Systems", Lang, Glenn E. And Cunnigham, James P., Instrumentation, Controls and Automation in the Power Industry, vol. 34, Proceeding of the 34th Power Instrument Symposium, June 1991 7.5 Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWR's Pursuant to IOCFR50.54(f) Braidwood, Byron, Dresden, Title APPENDIX F LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet F14 of F14 Nuclear Engineering Standards I Accuracy Revision 4 evision 41 1 NES-EIC-20
.04 uclear Engineering Standards APPENDIX G DELTA-P MEASUREMENTS EXPRESSED IN FLOW UNITS Braidwood, Byron, Dresden, LaSalle, and Quad Cities t Revision indicated by a bar in right hand margin. ifle Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy DIX G NES-EIC-20
.04 Sheet G1 of G9 Revision 4 Revision 4 I NES-EIC-20
.04
 
==1.0 INTRODUCTION==
 
Propagation of errors and uncertainties through a non-linear device results in output errors and uncertainties that are a function of the input value. In the case of the typical flow vs. dP relationship, an approximation can be derived for the square root/square function. This appendix provides an equation that can be used to convert between errors in % dP and errors in % full scale. Orifices, nozzles and venturies are typically provided with their flow uncertainty expressed as a % of full scale dP. This uncertainty is the same anywhere within the measured span. As an example, an orifice that has a full span of 100 in.WC and is specified to be accurate to +/-1% full span, will have an uncertainty of +/-I inch of water anywhere in the measured span. Since dP is a function of flow squared, this cannot be said for errors expressed in terms of flow, % flow or % flow span. The flow error will depend on the corresponding value of flow. 2.0 DERIVATION Since dP is proportional to flow squared: (FN )z = dPN (Eq. G1) where N = Nominal Flow Taking the partial derivative and solving for aF N: 2F N aF N = adPN aF N = (adPN)/(2 FN) Similarly, the error at a point (not in %) is: LaSalle, and Quad Cities aF N adP N adP N Braidwood, Byron, Dresden, F N 2(F N )` 2dPN Nuclear Engineering Standards and from equation G l : dPN = (FN)2 (Eq. G3) dPMAx (F MAX ) z where: MAX = maximum flow (Eq. G2) Title APPENDIX G NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet G2 of G9 Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04 The transmitter dP error is defined by: Therefore: dP MAX The error in flow units is obtained by solving for W N: F N (% FS dP)C FMAX af N = (2)(100) FN (Eq. G6) This can be rearranged to represent the error in % nominal flow: From equation G7, the error in % full span can be derived: i Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards adP N = % error in full scale dP (% FS dP) (Eq. G4) % FS dP~ _aF N _ adPN = dPMAX 100 J F N 2dP N %FS dp(FMAX 2 FN ) (2)(100) aF N FS dP) FMAX x 100 )_ 2 F F .7) DF N F N x 100 = F MAX (F MAX )(2)(100) APPENDIX G NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet G3 of G9 Accuracy Title 2dP MAX `FMAX ) \2 2 F F N (%FS dP) MAX _ (% FS dP)~ FM AX 2 A F N x 100 (Eq. G5) (Eq. G7) (Eq. G8) Revision 4 Revision 4 NES-EIC-20
.04 Replacing equation GS with variables equivalent to those typically used in accuracy analysis: Flow Error in % Full Scale Flow V Error in % Full Scale dP FMA= 2 A FIX) (Eq. G9) Flow Error in % Nominal Flow= 3.0 APPLICABILITY
 
===4.0 EXAMPLES===
4.1 EXAMPLE 1: Full Flow vs. Full Span Error Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title NOTE: full scale is equivalent to full span Error in % nominal flow at any flow level can be obtained in the same manner from equation G7. dP Error in % Full Scale dP) ( FMAx The following flow loop parameters are assumed for this example. (Eq. G 10) Equations G9 and G10 are used to convert between flow error and dP error. These equations are an approximation and assume that any sufficiently small portion of a curve can be replaced with a straight line. These equations show that the slope of a line segment at any point on a square root curve is: F MAx / 2F N . For a square root curve, this approximation provides a conservative estimate of error. Equation 9 is particularly useful when calculating instrument loop accuracy where all errors are converted to % of "full" span for consistency. Caution should be used when using equations G9 and G10 to determine flow channel setpoints. It is important to differentiate between "full flow" and "full span". For example, full span is typically 110% to 120% of full flow to ensure that the transmitter output signal is not limited at full flow. Equation G9 is used when 100% span error is desired and the error term is to be expressed in % full span. Equation G10 is used when the equivalent error at any other flow value, e.g. 100% flow, is desired. Full Scale Flow = 20% flow Nominal flow = 100% flow dP span = 0-500 in. WC Error = +/-1% span Transmitter scaling: 0-500 in WC is equivalent to 4-20 mA NOTE: typical orifice and nozzle span errors are provided as an error in dP span which is constant over the entire dP span. APPENDIX G NES-EIC-20
.04 Analysis of Instrument Channel -' Setpoint Error and Instrument Loop Sheet G4 of G9 Accuracy Revision 4 Revision 4 4.1.1 Find the error in % flow at 100% flow From section 4.1: F = 120% MAX F = 100% N error in % full scale dP = 1 % dP span Use equation G10 for nominal flow error determination. Error Nominal Flow = 4.1.2 Find the error at full span (120% flow). r dP Error in % Full Scale dl?l F = 120% MAX F = 100% N error in % full scale dP = +/-1% R span Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards F MAX =(I2% l (L120 100) ` _ +/-0.72% flow at 100% flow Use equation G9 for full span error determination. = ( dP Error in % Full Scale dP)C F MAX Error% Full Scale Flow 2 F N C 1o A 100) 2 = t0.6%a flow span (Title NES-EIC-20
.04 APPENDIX G NES-EIC-2 0.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet GS of G9 Accuracy Revision 4 Revision 4 - NES-EIC-20
.04 4.2 EXAMPLE 2: Calculation of flow error using dP The following flow loop parameters are assumed for this example. Low flow: Full span = 120% flow Nominal flow = 100% flow dP span = 0-500 in. WC Error = +/-1% span Transmitter scaling: 0-500 in WC is equivalent to 4-20 mA NOTE: typical orifice and nozzle span errors are provided as an error in dP span which is constant over the entire dP span. 4.2.1 Find the error in % flow at 100% flow Flow 2 a dP (Flow MAX %)2 __ (Flow N %)2 dPMAX dP N (120%O )2 _ (100%)2 500 in. WC dPN dP N = 347.22 in. WC The dP error is 1 % of 500 in. WC = +/-5 in. WC. Therefore, at full flow (equivalent to nominal or 100% flow) the dP should be 347.22+/-5 in. WC. Calculating the flow error: (F1ow mAx %)2 - (FloW N %)2 Hi flow: dP MAX dP N +/- 5 in. WC (120%) 2 _ (Flow N %)2 500 in. WC 352.22 in. WC Flow N. = 100.72 % flow (120%)2 (FloW N%)2 500 in. WC 342.22 in. WC Flow N- = 99.28 % flow Braidwood, Byron, Dresden, Title APPENDIX G LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet G6 of G9 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 - I NES-EIC-20
.04 Therefore the flow error is +/--0.72% flow at full flow. This is consistent (to 2 decimal places) with the error calculated using the approximation formula in step 4.1.1. 4.2.2 Find the error in % full span at 100% flow When using % full span to combine errors, the error at 100% flow must also be expressed in terms of % full span. Full flow = (100% flow)(100%
span/ 120% flow) = 83.33% of full span From 4.2.1, the flow error is +/-0.72% flow at full flow, which is equivalent to 10010.72% flow. Converting this to % of span: (100+0.72)(100%
span/ 120% flow) = 83.93 %full span (t00-0.72)(100%
span/ 120% flow) = 82.73% full span The deviation from full flow as a % of span is: 83.93% span - 83.33% span = 0.6% span and 83.33% span - 82.73% span = 0.6% span. Therefore, the nominal or 100% flow in terms of % full span is equivalent to 83.33+/-0.6% full span, which is consistent with step 4.1.2. 4.3 FLOW ERROR AT LOW FLOWS As shown in step 4.2, the approximation and the actual flow errors are expected to be relatively close when the nominal flow is close to full flow. Since errors as a % of span increase as flow decreases, the approximation becomes increasingly conservative at lower flows. Therefore, at low flows or when the exact flow error is desired, the dP method should be used to calculate flow error. 4.4 EXAMPLE 3: Error at Low flows The flow error associated with a low flow trip at 30% flow is required. Using the same values in steps 4.1 and 4.2: Braidwood, Byron, Dresden, itle APPENDIX G LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet G7 of G9 Nuclear Engineering Standards Accuracy F Revision 4 Revision 4 Approximation
: Actual error: Hi flow: Error, Nominal Flow -`:: Error% Full Scale Flow Using a t % span error = t5 in. WC: dP Error in % Full Scale dP) (FMAX C 1120 2 o)( 30) _ +/-8.0% flow at 30% flow r dP Error in % Full Scale dP) (FMAX ) C 1 2%)C 30/ -- +/-2.0% flow span Flow' a dP (Flow mAx %)` _ (FIow N %)2 dP MAX O N (120%)' _ (30_ %)2 500 in. WC dP N dP N = 31.25 in. WC (Flo w MAX %&deg;)2 _ (FIow N %)2 dP mAX O N (120%)Z _ (Flow N %)2 500 in. WC 36.25 in. WC Flow N' = 32.31 % flow NES-EIC-20
.04 Braidwood, Byron, Dresden, Title APPENDIX G LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet G8 of G9 Nuclear Engineering Standards Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 (120% )2 (Flow, %)2 Low flow: Nuclear Engineering Standards 500 in. WC 26.25 in. WC Flow N_ = 2750 %. flow For a low flow trip setpoint, we use the error in the conservative, decreasing direction. Therefore 30.0% flow - 27.50% flow = 2.5% flow. This is considered a random error or +/-2.50% flow when used in a loop accuracy calculation. Braidwood, Byron, Dresden, LaSalle, and Quad Cities NOTE: when considering accuracy requirements, it is good engineering practice to ensure flow setpoints are never less than 25% span.. In example 3, the 30% flow setpoint is equivalent to 25% flow span. The equivalent error in % span is: (30 + 2.50)(100%
span / 120% flow) = 27.08% flow span (30 - 2.50)(100%
span / 120% flow) = 22.92% flow span The conservative error for a decreasing setpoint is: 25% span - 22.92% span = +/-2.08% flow span. Step 4.4 shows that when errors are calculated as a "% of flow span", the approximate and actual error (+/-2.0% flow span vs. +/-2.08% flow span) are relatively close even at the minimum recommended flow setpoint. The flow error as a "% flow" indicates that the approximation is conservative
(}8% flow vs. +/-2.5% flow). Care should be taken to ensure that the method chosen to determine flow error is sufficiently conservative with respect to the function of the flow setpoint. CAUTION: When it is necessary to evaluate performance in terms of % flow (or gpm or mpph, etc), as in Technical Specification acceptance criteria or ISI test criteria, the use of the approximation method to calculate flow error may be excessively conservative with respect to the real accuracy of the measurement. Using the approximation to calculate flow error could result in overly conservative performance or test requirement. The result being a component, e.g. a pump, considered inoperable due to conservative acceptance criteria rather than excessively degraded performance. Title APPENDIX G NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet G9 of G9 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 APPENDIX H CALCULATION OF EQUIVALENT POINTS ON NON-LINEAR SCALES Latest Revision indicated by a bar in right hand margin. Braidwood, Byron, Dresden, Title APPENDIX H LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet HI of H6 Nuclear Engineering Standards Accuracy Revision 4 Revisi on 4 NES-EIC-20
.04
 
==1.0 INTRODUCTION==
 
Conversion of linear information to equivalent non-linear data points can be performed using ratios. This technique can be used for all non-linear continuous functions; e.g. square root, logarithmic, etc. For logarithmic scales, those of you who remember slide rules will quickly recognize the technique of ratioing distances. This method can be easily extended to any two scales that are equivalent. Typical instrument setpoint accuracy and instrument scaling examples include: mA to GPM, volts to source range counts, mA to DPM (decades per minute), etc. Equivalent scales are any two ranges that have a 1:1 analog relationship. 2.0 SCALE CONVERSION The following discussion uses a logarithmic indicator scale as an example. The indicator has a 1 to 5 volt input and a 10 to 10 7 CPM scale. First, the equivalent ranges are 1 to 5 volts and 10 to 10 7 CPM. The graphical representation below can often aid in visualizing this concept. Next, determine the equivalent CPM to 2.7993 volts using the technique of ratios. From the above graphic, it is obvious the distances represented on the linear and logarithmic scales are identical. Most of us are familiar with analog ratios, where the ratio (2.7993 to 1)/ (5 to 1) will give us the voltage ratio. For the logarithmic ratio, one must recognize that the equivalent distances are logarithms. We use this fact to write an equation for the unknown CPM: An alternate method to solve for log x: Braidwood, Byron, Dresden, LaSalle, and Quad Cities 5 volts 10 7 CPM (2.7993 volts -1 volt) ( log X -log 10 ) 5 volts -1 volt log 10 7 -log 10) 1.7993 volts log X-1 4 volts ) ~ 7 -1 log x = 3.69895 x = 4999.77 = 5000 CPM itle APPENDIX H NES-EIC-2 0.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet H2 of H6 Nuclear Engineering Standards I Accuracy Revision 4 1 2.7993 10 ?
Revi sion 4 NES-EIC-20
.04 log x = 3.69895 x = 103.69895 = 10&deg;.69895 x 10 3 = 4.998 x 10 3 = 5000 CPM For this discussion, assume that the linear uncertainty is 2% of span. This is equivalent to: 2.7993 volts +/- (2%(5 volts - I volt)) = 2.7993 +/- 0.08 volts Using the ratioing technique, it becomes a simple matter to find the equivalent CPM values for 2.8793 volts and 2.7919 volts. The +/-2% tolerance equations are provided below, followed by the completed graphic. 2.7993 volts - 0.8 volts _ log X -log 10 5 volts-1 volt ) (log 10 7 _log 10 g g 1.8793 volts _ log x -1 4 volts 7 - l log x = 3.81895 x = 6590.98 = 6591 CPM 1 2.7993 5 volts -2% +2% 2.8793 volts 6591 CPM 10 5"10 3  7 CPM Thus, for a linear input of 1 to 5 volts with an error of t2% of span, the equivalent uncertainty range at 5000 CPM is 3793 to 6591 CPM. As with all non-linear relationships, it is important to note that the uncertainty range is dependent on the point on the non-linear scale around which the uncertainty is calculated. In other words the +1591, -1207 CPM uncertainty range is only valid at 5000 CPM. Braidwood, Byron, Dresden, Title APPENDIX H NES-EIC-20
.04 LaSalle, and Quad Cities Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet H3 of H6 Nuclear Engineering Standards I Accuracy Revision 4 1 2.7193 1 I I 3793 I __
Revision 4 I NES-EIC-20
.04 3.0 EXAMPLES The following examples demonstrate some of the typical problems that can quickly be solved using this technique. A graphical representation is used to visualize the problem. One advantage of quickly sketching the problem is that incorrect relationships can be easily identified. 3.1 EXAMPLE 1 For an input range of 1 to 5 volts (0 to 100% span) and an output range of 10 to 10 7 CPM, find the setpoint in CPM at 65% input span. NOTE: Since 0 to 100% span is linear, there is no need to convert anything to volts. 3.2 EXAMPLE 2 65%-O%)_( log x -log 10 100% - 0%) J log 10' - log 10 (0.65(7 -1)) + 1= log x x = 79,432 = 7.9 x 10 4 CPM 100 % input 10 7 CPM For an input range of 1 to 5 volts (0 - 100% span) and an output range of 10-10 to 10-1 % power, find the setpoint (in percent power) at 3.6 volts. This example is typical of nuclear instrumentation where the source and intermediate range need to be displayed in percent power. First, calculate
% power, so that we don't have to do any conversion in our ratio equation. 3.6-1 volt 100% power _ x100% span x 65% power 5-1 volt ) ( 100% span ) Braidwood, Byron, Dresden, Title APPENDIX H LaSalle, and Quad Cities Analysis of Instrument Channel NES-EIC-20
.04 Setpoint Error and Instrument Loop Sheet H4 of H6 Nuclear Engineering Standards I Accuracy Revision 4 0% 65% 10 ?
Revision 4 NES-EIC-20
.04 3.3 EXAMPLE 3 10 First find the equivalent setpoint: Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards 0% 65% 100 % input ? 10-1 % power 65% - 0% ) ( log x - log 10-" ~ 100% - 0%) Uog 10-' -log 10-`&deg;) 0.65 J= (log x+10 1 -1+ 10 log x=-4.15 X=10.15=10.85 x10-5 = 7.08 x 10-5% power Using the ranges in Example 2, find the +/-2% of span tolerance for a setpoint of 7x 10-5 % power, where 2% of span represents the input error. NOTE: Once again there is no need to convert to other input units. 0% x % 100 % input 10-10 10-1 % power (log(7 x 10-5) - log 10-`0) ( x - 0% ) log 10-t - log 10-10 ) 1 100% - 0%) -4.151902 0+ 10} _ (100% - 0% x = 64.94553% input span Use the following ratio to solve for the upper limit (U). Title APPENDIX H NES-EI C-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet H5 of H6 Accuracy Revision 4 Revision 4 Solve for the lower limit (L). Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards (64.94553+2)-0%)
_ log U -log 10-`0 -) 100% -o% tog 10-` -lo g 10" i&deg; 0.6694533 = log U + 10 1 9 U = I0-3.97490'" = 1.06X 10-4% L power NES-EIC-20
.04 U = 10-3.974902 = 1.06 x 10-4% power As expected, non-linear scales result in non-symmetrical upper and lower values for an equivalent symmetrical input error. When evaluating the accuracy of a single point (e.g. bistable setpoint or EOP required actuation point), you can use the limit associated with the direction of the process change. Thus an increasing setpoint would use U and a decreasing setpoint would use L for calculating accuracy. When calculating accuracy for a point on an indicator scale, the accuracy values are used in 2 different ways. When calibrating the indicator the calibration limits can use the specific L and U values for each cardinal point. When providing accuracy values to a plant operator or other individual that is using the indicator to monitor a plant process condition, it is usually inconvenient to list asymmetric limits. In this case it is conservative to describe accuracy as tU or +/-L, whichever is larger. In order to use the ratio technique for other non-linear functions, compare (ratio) the equivalent scalar distances of each range. Thus with square root/square relationships, such as flow (GPM, CM etc.) or percent of flow, the ratio is obtained by taking the square root or square of the corresponding linear value. Title APPENDIX H NES-EIC-2 0.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet H6 of H6 Accuracy Revision 4 Revision 4 ( NES-EIC-20
.04 APPENDIX I NEGLIGIBLE UNCERTAINTIES Latest Revision indicated by a bar in right hand margin. Braidwoad, Byron, Dresden, itle APPENDIX I LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet Il of Ib Nuclear Engineering Standards Accuracy Revision 4 Revision 4 [ NES-EIC-20
.04
 
==1.0 INTRODUCTION==
 
The errors and uncertainties listed in this appendix have historically been found to be negligible under normal operating conditions. If the individual preparing an instrument loop accuracy calculation determines that the specific conditions apply, then these errors and uncertainties do not have to be evaluated in the calculation. 2.0 NEGLIGIBLE UNCERTAINTIES
 
===2.1 Radiation===
 
Effects The effects of normal radiation are small and accounted for in the periodic calibration process. Outside of containment there is not a creditable increase in radiation during normal operation. The uncertainty introduced by radiation effects on components is considered to be negligible. If an as-found/as-left analysis has been performed based on historical calibration data, then normal radiation effects are considered to be included in the drift analysis results. 2.2 Humidity Effects The uncertainty introduced by humidity effects during normal conditions is not typically addressed in vendor literature. Therefore humidity effects are considered to be negligible unless the manufacturer specifically mentions humidity effects in the applicable technical manual. The effects of changes in humidity on the components is considered to be calibrated out on a periodic basis. A condensing environment is regarded as an abnormal event which will require maintenance to the equipment. Humidity's below 10% are expected to occur very infrequently and are not considered. If an as-found/as-left analysis has been performed based on historical calibration data, the humidity effect is assumed to be included in the drift analysis results. 2.3 Power Supply Effects It is expected that regulated instrument power supplies have been designed to function within manufacturer's required voltage limits. The variations of voltage and frequency are expected to be small and the power supply voltage and frequency uncertainties are considered to be negligible with respect to other error terms. If an as-found/as-left analysis has been performed based on historical calibration data, the power supply voltage and frequency effects are assumed to be included in the drift analysis results. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX I NES-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 12 of 16 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 2.4 Calibration Standard Error (STD) The calibration standards used by the station to maintain and calibrate station M&TE are expected to be maintained to manufacturer's specifications. These calibration standards are more accurate than the station M&TE by a ratio greater than 4:1. Therefore, the effects of the calibration standard error are considered to be negligible with respect to other error terms. 2.5 Seismic/Vibration Effects The impact of Seismic Effects in the setpoint calculation should be consistent with the Licensing Design Basis of the specific station (e.g. assuming a design Seismic Event coincident with a Design Basis Accident). For normal errors, seismic events less than or equal to an OBE are considered to cause no permanent shift in the input/output relationship of the device. For seismic events greater than an OBE, it should be verified that the affected instrumentation is recalibrated prior to any subsequent accident to negate any permanent shift which may be resulted from a post seismic shift. Unlike Seismic effects, Vibration effects may not always be calibrated out or included in the statistical drift. Consideration must be made of the "normal operating" versus "calibration" conditions. If the relative vibration conditions of these two states is not the same, then the vibration effect must be considered. This effect is not calibrated out or included in the historical calibrations data. If an as-found/as-left analysis has been performed based on historical calibration data, the vibration effect is considered to be included in the drift analysis results, if the normal operation conditions and the calibration conditions are similar. 2.6 Lead Wire Effects Since the resistance of a wire is equal to the resistivity times the length divided by the cross sectional area, the very small differences in the length of wires between components does not contribute any significant resistance differences between wires. Therefore, the effect of lead wire resistance differences is considered negligible, except for RTD's and thermocouples. If a system design requires that lead wire effects be considered as a component of uncertainty, that requirement must be included in the design basis. It is assumed that the general design standard is to eliminate lead wire effects as a concern in both equipment design and installation. Failure to do so is a design fault that should be corrected. The lead wire effects for RTD's and thermocouples must be considered separately and must be evaluated for each specific application. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX I NES-EIC-20
.04 Analysis of Instrument Channel '-""--' Setpoint Error and Instrument Loop Sheet 13 of 16 Accuracy Title Revision 4 Revision 4 TNES-EIC-20
.04 3.0 NEGLIGIBLE UNCERTAINTIES FOR RELAYS, TIMERS, LIMIT AND MECHANICAL DISPLACER-TYPE SWITCHES 3.1 Relays and Timers Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX I NES-EIC-20
.04 Analysis of Instrument Channel '-" Setpoint Error and Instrument Loop Sheet 14 of 16 Accuracy Revision 4 Table Il Negligible Errors and Uncertainties for Relays and Timers Error T Symbol Justification Process Errors PE Density Error These particular devices are not in direct contact Process Error with the process and are not subject to these types Flow Element Error of errors or uncertainties. Temperature Error eT Thermal Expansion Error Configuration or Installation Error Operational Errors Drift Error D Unless specifically prescribed by the Vendor, drift is assumed to be accounted for in the ublished Reference Accuracy for the device. Static Pressure Error eSP These particular devices are not in direct contact with the process and are not subject to these types of errors or uncertainties. Pressure Error eP There are no Pressure Errors associated with the function of these devices as the ambient pressure at the device location remains constant at normal atmos heric pressure. Power Supply Error eV There are no Power Supply Errors associated with the function of these particular devices. Environmental Errors Unless specifically prescribed by the Vendor, Temperature Error eT environmental errors are assumed to be accounted Humidity Error eH for in the published Reference Accuracy for the Seismic Error eS device. Additionally, as these types of devices Radiation Error eR are typically installed in controlled environments and expected to perform their functions under normal operating conditions, the effects of these errors is considered negligible. Other Errors Insulation Resistance eIR There are no Insulation Resistance Errors associated with the function of these particular devices Random Input Errors These devices function as separate modules and have no random input errors.
Revision 4 [NESS IC-20.04 3.2 Limit Switches Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX I NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet 15 of 16 Accuracy Title Revision 4 Table 12, Ne ti 'ble Errors and Uncertainties for Limit Switches Error T Symbol justification Process Errors PE These particular devices are not in direct Density Error contact with the process and are not subject Process Error to these types of errors or uncertainties. Flow Element Error Temperature Error eT Thermal Expansion Error Configuration or Installation Error Operational Errors Drift Error D Unless specifically prescribed by the Vendor, drift is not applicable for these type of devices. Static Pressure Error eSP These particular devices are not in direct contact with the process and are not subject to these types of errors or uncertainties. Pressure Error eP There are no Pressure Errors associated with the function of these devices as the ambient pressure at the device location remains constant at normal atmospheric pressure. Power Supply Error eV There are no Power Supply Errors associated with the function of these particular devices. Environmental Errors Unless specifically prescribed by the Temperature Error eT Vendor, environmental errors are assumed to Humidity Error eH be accounted for in the published Reference Seismic Error eS Accuracy for the device. Radiation Error eR Other Errors Insulation Resistance eIR There are no Insulation Resistance Errors associated with the function of these particular devices Random Input Errors These devices function as separate modules and have no random input errors.
Revision 4 3.3 Mechanical Displacer-Type Switches (Float Switches)
Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX I NES-EIC-20
.04 Analysis of Instrument Channel ---Setpoint Error and Instrument Loop Sheet 16 of 16 Accuracy Title NES-EIC-20
.04 Revision 4 Table 13, Negligible Errors and Uncertainties for Mechanical Dis lacer-T Switches Error T Symbol Justification Operational Errors Drift Error D Unless specifically prescribed by the Vendor, drift is not applicable for these type of devices. Pressure Error eP There are no Pressure Errors associated with the function of these devices as the ambient pressure at the device location remains constant at normal atmospheric pressure. Power Supply Error eV There are no Power Supply Errors associated with the function of these particular devices. Environmental Errors Unless specifically prescribed by the Temperature Error eT Vendor, environmental errors are assumed to Humidity Error eH he accounted for in the published Reference Seismic Error eS Accuracy for the device. Radiation Error eR Other Errors Insulation Resistance eIR There are no Insulation Resistance Errors associated with the function of these articular devices Random Input Errors These devices function as separate modules and have no random input errors.
Revision NES- IQ= APPENDIX J GUIDELINE FOR THE ANALYSIS AND USE OF AS-FOUND/AS-LEFT DATA Latest Revision indicated by a bar in right hand margin. Braidwood, Byron, Dresden, Title APPENDIX J LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J1 of J24 Nuclear Engineering Standards I Accuracy I Revision 4 j Revision 4 I NES-EIC-20
.04
 
==1.0 INTRODUCTION==
 
The analysis of the data from calibration of installed instrumentation can provide the station with several pieces of information that will allow for better prediction of instrument behavior and will provide more "accurate" data for computation of loop uncertainties. This attachment defines a process that will be used at Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) to ensure consistency and compliance with regulatory position GL-91-04. This process will specifies certain requirements, but does not provide a step-by-step methodology. Each site should develop specific methodologies, utilizing these guidelines to support their specific needs. There are several approaches to the analysis of data and it's subsequent use. Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) has adopted a general methodology similar to that presented in EPRI TR-103335, Guidelines for Instrument Calibration Extension/Reduction Programs, Revision 1. Refer to this document for a complete understanding of the guidelines developed in this Appendix. This Appendix is divided into the following sections: 2.1 DATA COLLECTION AND POOLING 2.2 INITIAL ANALYSIS PROCESS 2.3 OUTLIER AND POOLING VERIFICATION REQUIREMENTS
 
===2.4 NORMALITY===
 
2.5 TIME DEPENDENCE
 
===2.6 RESULTS===
2.7 USING RESULTS 2.8 CONTINUING EVALUATION Each of these sections contains a general discussion of the expected actions that will conform to TR-103335 and the guidelines to be followed for analysis at Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) sites. 2.0 ANALYSIS METHODOLOGY 2.1 DATA COLLECTION AND POOLING 2.1.1 To evaluate the performance of an instrument or group of instruments the data that is collected should consist of a sufficient number of independent samples to allow for statistical analysis of the data that could indicate drift changes. The sample should also represent a good distribution of the instruments used. In most cases, this will be the whole population. For instruments that are used extensively in the plant, a sample can be used. When collecting data, the application of each instrument must be identified to avoid application specific errors that will cause pooling of data to be an incorrect decision. Because the evaluation includes the important element of time dependency determination, the data collected should have data from different calibration intervals. If data is not from different calibration Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX J NES-E IC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J2 of J24 Accuracy Revision 4 Revision 4 [ NES-EIC-20
.04 periods then the evaluation should be reviewed and/or revised when additional calibrations are available, The evaluation must include all of the times that the instrument has been calibrated, or checked for accuracy (i.e. surveillance testing without adjustment). 2.1.2 Selection of the Instruments to be Evaluated (Pooled) for a Given Drift Study 2.1.2.1 All instruments evaluated shall be from the same manufacturer and shall perform in an identical manner for the critical parameters that are to be analyzed. Determining which instruments meet this criterion is eschewed by the fact that many manufacturers' have different model numbers based on mounting, enclosure, etc. The differences typically have no effect on the method that the instrument uses to monitor the parameter of concern. In addition, the range of the instrument may vary without having any significant change in the measurement method. If multiple model numbers are used, the evaluations must include a discussion of the reason why the instruments are assumed identical, specifically in the critical areas of concern. 2.1.2.2 Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) has specified that the minimum targeted number of valid data points that are required to make a drift study statistically significant shall be 30 data points. The sample value of 30 is generally accepted as a minimum valid sample size. An analysis using less than this number can be performed if justification is provided in the study results. If the analysis is performed with less than thirty data points the results of the analysis should be verified after a sufficient number of points are available
(>30). In most circumstances, this number should be > 30 data points. If there are more than approximately 150 data points, there is no significant improvement in the statistical rigor of the analysis. 2.1.2.3 In order to obtain the necessary number of data points required to ensure that there is variance in the calibration interval for the make/model of concern, the calibration data from multiple instruments will be needed. The following criteria for the selection of which instruments and calibration data points shall be used: a. All instruments that are directly associated with RPS/ESF/ECCS automatic trips and actuations shall include at least one channel's instruments. b. To ensure that there is a historical perspective to the data evaluated, at least four calibration intervals of data shall be collected. The four intervals provide for historical data while ensuring that the more recent calibration data is used to detect current problems. If the instrument has not been installed for that period, then the available data will be used. There may be some problems in the evaluation of the instrument over a given calibration interval. c. If more than 150 data points can be developed for a given analysis, then a sample of instruments can be used instead of the whole population. The selection of which instruments to include wilt be done on a random basis, provided Section 2.1.2.3.a Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel -"-' Setpoint Error and Instrument Loop Sheet J3 of J24 Accuracy Title Revision 4 Revision 4 1 NES-EIC-20
.04 requirements are maintained. The method of selection will be prepared and included in the calculation. 2.1.3 Data Collection is the transfer of data from the calibration records to the final analysis tool. This very sensitive process will require independent verification and validation of data transferred. 2.1.3.1 A search of all preventive and corrective maintenance records shall be conducted on each instrument selected for inclusion in the study. This search shall identify every calibration and every corrective maintenance activity for the period of concern for the study. The search should go back at least four calibration intervals (i.e. at least five sets of calibration data). If there are less than eight instruments included in the study then additional historical data will need to be collected to achieve the minimum number of data points specified by Section 2.1.2.2. The data collected should ensure that the results are not from overlapping calibration intervals. 2.1.3.2 The data from the calibrations will be entered into a spreadsheet or data base program using a format similar to Figure J 1. For instruments that have multiple calibration points (transmitters, function generators, etc.) each calibration point will be entered in the spreadsheet using the percent of span as the column title. If there are discrepancies in the exact percent of span then calibration points that are within 5% of each other can be used together (e.g. 0% FS, 1 % FS and 5% FS can be considered the same calibration point). For switches, relays or other equipment where there is a single point that is calibrated the data can be entered in percent of instrument span or in process units. Due to the diversity of software that can be used to compute this spreadsheet statistics, there may be some variation in format. The specific project or calculation shall identify the software used and justify that the data entry is in agreement with the intent of Section 4.0 of TR-103335. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX J NES-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J4 of J24 Accuracy Revision 4 Revision 4 - - _ 1 NES-EIC-20
.04 Figure J1, Example Spreadsheet Data Entry The following information is particularly valuable for the analysis: " The date of calibration is documented. The time interval since the previous calibration is calculated in months in the Interval column. Depending on the data, the time interval might be calculated in days, weeks, or months. " The as-found and as-left data are entered into the spreadsheet exactly as recorded on the instrument data sheet. The values are in milliamperes (in this case) corresponding to a range of 0% to 100% of calibrated span. " Note that all calibration data points have been recorded. In general, it is preferable to consider and evaluate all available data. By this approach, a better understanding of instrument drift can be obtained. For calibrations that check calibration points during ascending and descending calibration, the ascending and descending point will be kept separately for the initial evaluation. 2.1.3.3 All Data transfer will require 100% independent verification. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet JS of J24 Accuracy Title Revision 4 Initial Data Anal sis Date Mo. Yr. Data Status Interval Months Tag Number Calibration Data (mA) 0% 25% 50% 75% 100% 5 93 As- Found 12 LT-459 4.00 8.00 11.94 15.96 20.01 As-Left LT-459 4.00 8.00 11.94 15.96 20.01 5 92 As- Found 14 LT-459 4.20 8.04 12.05 16.05 20.04 As-Left LT-459 4,00 8.00 11.98 15.98 20.00 3 91 As- Found II LT-459 4.09 8.04 12.02 16.05 20.04 As-Left LT-459 4.09 8.04 12.02 16.05 20.04 4 90 As- Found t0 LT-459 4.06 7.92 11.95 15.98 19.95 As-Left LT-459 4.06 7.92 11.95 15.98 19.95 6 89 As- Found 13 LT-459 4.00 8.00 12.02 16.07 20.02 As-Left LT-459 4,00 8.00 12.02 16.07 _ 20.02 5 88 As- Found 12 LT-459 4.24 8.20 12.16 16.12 20.15 As-Left LT-459 4.00 7.97 11.98 15.98 20.00 5 87 As- Found LT-459 NEW NEW NEW NEW NEW As-Left LT-459 4.02 7.99 11.99 16.07 20.01 Revision 4 NES-EIC-20
.04 2.1.3.4 Due to legibility problems, even if it is obvious that the data recorded in original records is incorrect, verbatim transcription of the data is required. If the information cannot be determined from the original record (due to legibility problems) then the data point will be left blank. Record of this omission shall be included in the analysis. 2.1.3.5 In addition to the calibration point as-found and as-left values, the calibrated span of the instrument, date of the calibration and any significant calibration anomalies are to be recorded in the spreadsheet. 2.2 INITIAL ANALYSIS PROCESS 2.2.1 From the original data, certain manipulations may be required to get the data in a form that can be evaluated across various instruments. 2.2.1.1 If the instrument loop is not a linear loop and the data has not been converted, then the raw calibration data should be converted to Linear Equivalent Full Scale (LEFS) to ensure that drift information is not masked. 2.2.1.2 If the instrument has a known span, the data should be normally converted into percent of calibrated span by dividing the raw data by the span. If the instrument does not have a known span, the data should be left in process units or converted to percent of the setpoint. 2.2.1.3 For each calibration interval where there is an as-left value from the older calibration and an as-found value from the younger calibration, a raw drift value should be determined by subtracting the as-left value from the as-found value. The calibration interval, in days, should also be determined. 2.2.2 Once the data is in the correct format, the number of data points, the average and the sample standard deviation should be determined for each column, (reference Section 4.0 of TR-103335). Due to the diversity of software that can be used to compute this spreadsheet statistics, there may be some variation in format. The specific project or calculation should identify the software used and justify that the data entry is in agreement with this Standard. Braidwood, Byron, Dresden, Title APPENDIX J LaSalle, and Quad Cities NES-EIC-2.-Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J6 of J24 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 NES-EIC-20
.04 2.3. OUTLIER AND POOLING VERIFICATION REQUIREMENTS
 
====2.3.1 After====
the initial computation of the average and the sample standard deviation, identification of any potential outliers and the cause of these outliers will provide important information as to the behavior of the data that was evaluated. 2.3.1.1 Using a T-Test, A statistical check of the raw data against the average and the sample standard deviation shall be conducted. Outlier Detection by the Critical values for T-Test ASTM Standard E 178-80 provides several methods for determining the presence of outliers. The recommended method for detection of an outlier is by the T-Test. This test compares an individual measurement to the sample statistics and calculates a parameter, T, known as the extreme studentized deviate. a s follows: Where, T= s T - Calculated value of extreme studentized deviate that is compared to the critical value of T for the sample size .z - Sample mean x;_ Individual data point s - Sample standard deviation Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX J NES-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J7 of J24 Accuracy Title Revision 4 Revision 4 l NES-EIC-20
.04 If the calculated value of T exceeds the critical value for the sample size and desired significance level, then the evaluated data point is identified as an outlier. The critical values of T for the upper 1%, 2.5%, and 5% levels are shown in Table J 1. Example, Instrument Draft Sample Braidwood, Byron, Dresden, LaSalle, and Quad Cities Table J1, Critical Values for T Note that the critical value of T increases as the sample size increases. The significance of this is that as the sample size grows, it is more likely that the sample is truly representative of the population. In this case, it is less likely that an extreme observation is truly an outlier. Thus, the T-Test makes it progressively more difficult to identify a point as an outlier as the sample size grows larger. This intuitively makes sense. As the sample size approaches infinity, there should be no outliers since all the data truly is a part of the total population. For this reason, it is relatively easy to identify a larger than average data point as an outlier if the sample size is small; however, it is (and should be) harder to call a given data point an outlier if the sample size is large. Table J1 provides outlier criteria up to a sample of 150 data points. Beyond this size, it should be even more difficult to declare an observation as an outlier. For greater than 150 data points, an outlier factor of 4 (or 4 standard deviations) is recommended in order to assure that outliers are not easily rejected from the sample. The T-Test inherently assumes that the data is normally distributed. The significance levels in Table JI represent the probability that a data point will be chance exceed the stated critical value. Referring to Table J 1 for a sample size of 40, we would expect to have a calculated value of T greater than 2.87 about 5% of the time and a calculated value of T greater than 3.24 about I % of the time. For safety-related calculations, testing outliers at the 2.5% significance level is required. Refer to ASTM Standard E 178-80 for further information regarding the interpretation of the T-Test. Title APPENDIX J NES-EI C-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet JS of J24 Nuclear Engineering Standards ( Accuracy Revision 4 Outlier Analysis Sample Size Upper 5 % Significance Level Upper 2.5% Significance Level Upper 1 % Significant Level 10 2.18 2.29 2.41 20 2.56 2.71 2.88 30 2.75 2.91 3.10 40 2.87 3.04 3.24 50 2.96 3.13 3.34 75 3.10 3.28 3.50 t00 3.21 3.38 3.60 125 3.28 3.46 3.68 150 3.33 3.51 3.73 Revision 4 NES-EIC-20
.04 Consider the 20 instrument drift data points shown in Table J2. The data appears to be within a +/-2.5% range with the exception of a single large data point, 5.20%. Would the T-Test identify this point as an outlier? The T-Test method requires the calculation of the sample mean and standard deviation before the calculated value of T can be obtained. For the above data, the sample mean and standard deviation are: Sample mean: 0.23% Sample Standard deviation: 1.24% Now, evaluate the 5.20% data point to determine if it might be an outlier. The calculation of T is as follows: As shown, the calculated value of T is 4.01. Compare this result to the critical values of T for this sample size is 2.56 at the 5% significant level and 2.88 at the 1% significant level (see Table J 1). In either case, the calculated value of T exceeds the critical value of T and the 5.20% data point is identified as an outlier. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Table J2, Instrument Draft Sample Data T- 15.20 - 0.231 = 4.01 1.24 APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J9 of J24 Accuracy Title Revision 4 Instrument Drift Sample Data 0.47% 5.20% -0.27% 0.21% 0.03% -0.12% -0.28% 0.42% 0.60% 0.69% -0.30% -0.78% -0.82% 0.30% -0.28% -0.08% 0.27% 0.03% 0.00% -0.45%
Revision 4 NES-EIC-20
.04 If the 5.205 data point is rejected from the sample, the sample statistics would be recomputed for the 19 remaining data points with the following results: Sample mean: -0.03% Sample standard deviation: 0.42% Notice that the single outlying observation was the only reason for an apparent bias of 0.23%. The standard deviation was reduced by approximately 65% (from 1.24% to 0.42%) by elimination of this single extreme value. 2.3.1.2 For any raw drift value that exceeds the critical T-Test, an evaluation shall be performed to determine if the data point should be excluded from the final data set. In no case can more than 5% of the original data be removed. Removal of outliers from the data set should be minimized as the process is to predict actual instrument performance. Since the data is all that we have to depict that performance, whether we like it or not, we need to accept the data unless underlying information can be inferred. The outlier process can not be repeated after an outlier or outliers have been removed within the constraints of this section. 2.3.1.3 Identification of a potential outlier in Section 2.3.1.2 does not mean that the value will be automatically excluded. Examples of when outliers should be removed include: a. Review of the calibration indicates that a data entry error was likely. This will normally be seen as a random value that is significantly outside the rest of the data with no explanation. This type of outlier is a rare event and should not be done routinely. b. Review of the data indicates that a bad calibration was performed. This will normally be seen by multiple outliers from the same calibration and a reverse drift of similar magnitude in the next calibration. In these cases, both sets of raw data should be removed. 2.3.1.4 The pattern of outliers should also be evaluated to determine if there is a bad instrument or application that is contaminating the data set. It is permissible for this evaluation to rerun the T-Test with a smaller critical T value to force outliers. If this is done, these outliers should not be removed from the final data set. This process will provide a number of data points that were at the extremes of the data set. If these extremes were primarily in one instruments' data or in one application area then additional evaluations need to be performed to determine if this data can be used with the rest of the data. 2.3.1.5 Bad instruments or bad applications will be detectable from the outliers that are identified. The best indication will be that the outliers will be bunched in the instrument or instruments Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J10 of J24 Accuracy Title Revision 4 Revision 4 NES-EIC-20
.04 used for a specific application. Other potential causes that could be identified by this process are: a. Variations in range or span b. Variations in age of calibration or equipment. 2.3.1.6 If the result of the outlier analysis indicates the potential for an application, range, age, etc. type of problem, then an analysis of the selection at that particular instrument should be conducted. Inclusion of data from any instrument can be checked by comparing this mean and variance of the instrument data to the mean and variance to the remainder of the data as explained in TR-103335 Section B.9. 2.4 NORMALITY 2.4.1 For this analysis, the assumption of normality is an integral assumption. To ensure that the data is a normal distribution or that a normal distribution is a conservative assumption, a test for normality of the data will be performed for all as-found/as-left data analysis after any outliers have been removed. 2.4.2 There are several tests for the normality of a data set. (See Appendix C of TR-103335). Exelon (Braidwood, Byron, Dresden, LaSalle, and Quad) requires at least one of the following numerical approaches be conducted before the qualitative evaluations are performed. " Chi-Squared, Y z , Goodness of Fit Test. This well known test is stated as a method for assessing normality in ISA-RP67.04, Recommended Practice, Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation. " WTest. This test is recommended by ANSI N15.15-1974, Assessment of the Assumption of Normality (Employing Individual Observed Values), for sample sizes less than 50. D-Prime Test. This test is recommended by ANSI N15.15-1974, Assessment of the Assumption of Normality (Employing Individual Observed Values), for moderate to large sample sizes. 2.4.3 If normality cannot be determined from a standard test then the data should be evaluated to determine if the assumption of normality is a conservative assumption. This can be done by one of the following techniques
: " Probability Plots. Probability plots (See Figure J2) provide a graphical presentation of the data that can reveal possible reasons for why the data is or is not normal. Use of a probability plot and qualitative evaluation demonstrates how close the tails of the curve approach a diagonal. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Title APPENDIX J NES-EIC-20.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J 1 1 of J24 Accuracy Revision 4 Revision 4 a m O m v c 3.0 2.51 2.01 1.5-' 1.0-0.5-! 0.0 -0.5t -1.0 -1.5--2.0 -2.5 -3.0 -1.0 -0.5 0.0 0.5 Actual Data Point Value NES-EIC-20
.04 Figure J2, Typical Probability Plot for Approximately Normally Distributed Data " Coverage Analysis. A coverage analysis (See figure J3) is used for cases in which the data fails a test for normality, but the assumption of normality can still be a conservative representation of the data. This is performed by a visual evaluation of a histogram of the data with a normal curve for the data overlaid. In most cases instrument data will tend to have a high kurtosis (center peaked data). Since the area of concern for uncertainty analysis is in the tails of the normal curve beyond at least two standard deviations, a high kurtosis will not invalidate the conservative assumption of normality if there are not multiple data points outside the two standard deviation points. Braidwood, Byron, Dresden, Title APPENDIX LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J12 of J24 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 1 NES-EIC-20
.04 300 250 200 c 150 a 100 50 0 2.5 TIME DEPENDENCE Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Figure J3, Coverage Analysis Histogram 2.4.4 If normality or a bounding condition of normality cannot be assumed for the data set, then depending on the distribution
: a. A distribution free tolerance value must be determined. b. The size of the standard deviation will be expanded to bound the distribution. As this is a seldom used case, this will not be discussed in this Standard. Refer to standard statistics texts for binomial and distribution free statistical method. To determine the amount of increase needed from the tabular 95/95 value for the histogram evaluation, use the count in each bar of the histogram and ensure that greater than 95% of the data is captured. Increase the standard deviation as necessary to capture at least 95% of the data. 2.5.1 The way the resultant drift value from this as-found/as-left analysis is used is very sensitive to the determination of the time dependency. This is particularly important for the extension of operating cycles via the NRC Generic Letter 91-04. This drift analysis requires that some decision be made on how the drift at thirty months can be determined from data that is taken over an eighteen month period. Title APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel --Setpoint Error and Instrument Loop Sheet J13 of J24 Accuracy Revision 4 Revision 4 i NES-EIC-20
.04 2.5.2 The basic and most conservative assumption that drift is linear time dependant will be used for the initial evaluation of the computed drift. However, during the development of the EPRI TR-103335, significant data was collected that indicates that drift does not follow a linear time dependent pattern and challenges this basic assumption. To determine the existence or lack of time dependency requires evaluation of the mean of the data over the calibration interval and the variation in uncertainty over the calibration interval. The evaluation of the mean of the data over the calibration interval will identify any bias component of the instrument drift that is time dependent. The evaluation of the variation in the data over the calibration interval will identify any change in the random component of drift that is time dependent. The following methodology is to be used to determine time dependence. Evaluation of the drift mean and its changes over time will use any combination of the following tools. a. Qualitative methods, which will include visual evaluation of the data on scatter plots, regression predication plots and bin mean plots. b. Quantitative methods, which will include regression of the significant data and the regression of the means of the bins (if there is sufficient data). Evaluation of drift variability and its changes over time will use any combination of the following tools: Qualitative methods, which will include visual evaluation of the data on scatter plots, regression predication plots and bin standard deviation plots. b. Quantitative methods, which will include regression of the Absolute Value of the significant data and the regression of the standard deviation of the bins (if there is sufficient data). 2.5.2.1 First, the data will be evaluated to determine if any of the data will generate significant leverage during regression. To do this the data collected shall be placed in interval bins. The interval bins that will normally be used are: a. 0 to 45 days (covers most weekly and monthly calibrations)
: b. 46 to 135 days (covers most quarterly calibrations)
: c. 136 to 225 days (covers most semi-annual calibrations)
: d. 226 to 445 days (covers most annual calibrations)
: e. 446 to 650 days (covers most old refuel cycle calibrations)
: f. 651 to 800 days (covers most extended refuel cycle calibrations)
: 9. 801 to 999 days h. > 1000 days Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel --Setpoint Error and Instrument Loop Sheet J14 of J24 Accuracy Title Revision 4 Revision 4 V NES-EIC-20
.04 2.5.2.2 For each internal bin, the average (x), sample standard deviation (a) and data count (Tl) shall be computed. In addition, the average calibration interval of the data points in each bin will be computed. 2.5.2.3 To determine the existence of time dependency, ideally the data needs to be "equally" distributed across the multiple bins. However, equal distribution in all bins would not normally occur. The minimum expected distribution that would allow this evaluation is: a. A bin will be considered in the final analysis if it holds more than five data points and more than ten percent of the total data count. The minimum number of data points in a bin was selected to ensure that one calibration at a point would not adversely affect evaluation of a significant amount of data at other intervals. The choice of five data points is engineering judgement and may be changed for a specific case with appropriate documentation in the specific calculation. b. For those bins that are to be considered the difference between bins will be less than twenty percent of the total data count. If there is a bin with significant data that does not meet this requirement, the evaluation should be done and the bin included if it can be shown to be from the same data set (a pooling test). c. At least two bins including the bin with the most data must be left for evaluation to occur. The following example demonstrates the process described above. Braidwood, Byron, Dresden, Title APPENDIX J NES-EIC-20
.04 LaSalle, and Quad Cities Analysis of Instrument Channel '-'-' Setpoint Error and Instrument Loop Sheet J15 of J24 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 For a given make and model of transmitter there were twelve EPN's that were looked at with historical calibrations for five calibration periods. Including corrective actions there were a total of 66 data points. The distribution of the data by bins was: The 46 to 135 day and 651 to 800 day bins are thrown out due to less than five data points and the 226 to 445 day bin is thrown out do to having less than ten percent of the data. Of the remaining three bins the 446 to 650 day bin is within twenty percent of the other two bins so there will be three bins used for evaluation. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Example Time Dependence Ev aluation NES-EIC-20
.04 Now the 0 to 45 day bin is greater than twenty percent from the next bin and thus only the 136 to 225 day and 446 to 650 day bins can be used for analysis. The majority of the data is in the 136 to 225 day bin and that bin is greater than twenty percent from the next most populous bin. In this case the normal analysis cannot be used. Engineering evaluation of the other bins with greater than ten percent of the data should be done to determine if they can be grouped with the data from the large bin. This could be done, by the pooling techniques listed above Title APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J16 of J24 Accuracy Revision 4 With a slight variation in the data: Bin Data Count % of Total Count 0 to 45 days 7 11 46 to 135 days 4 6 136 to 225 days 29 44 226 to 445 days 3 5 446 to 650 days 21 32 651 to 800 days 2 3 Bin Data Count % of Total Count 0 to 45 days 7 11 46 to 135 days 4 6 136 to 225 days 29 44 226 to 445 days 6 9 446 to 650 days 18 27 651 to 800 days 2 3 With another slight variation: Bin Data Count % of Total Count 0 to 45 days 7 1I 46 to 135 days 3 5 136 to 225 days 33 50 226 to 445 days 6 9 446 to 650 days 15 23 651 to 800 days 2 3 Revision 4 NES-EIC-20
.04 2.5.2.4 Once the bins have been selected, data from selected bins and all bins between them will be entered into a regression analysis program. The initial regression is for the data that populates all of the significant bins and the data that is between them. By eliminating the data that is in low populated bins and at the extremes of the calibration interval, leverage is minimized. This regression is to determine if the mean of the data changes over calibration interval. A regression analysis will be performed using calibration interval as the independent variable and drift as the dependant variable. Output of the regression analysis shall be in a standard ANOVA table similar to that shown in Table J3. Table J3, Sample ANOVA Table If the value for R Z is greater than 0.3, then the bias component of the drift should be considered to be linearly time dependent over the range of the calibration intervals included in the analysis. The constant and slope of the drift line will be used for bias values in uncertainty analysis for this instrument make and model. The appropriate tolerance interval for the 95/95 case should also be determined for this regression. [Note: This case will only occur rarely] If the value of R a is less than 0.3 but greater than 0.1 then there still can be a time dependency. To continue the evaluation use terms from the ANOVA table generated by the regression program (partial printout below) or an equivalent ANOVA table. Braidwood, Byron, Dresden, Title APPENDIX J LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel `-'- Setpoint Error and Instrument Loop Sheet J 1 7 of J24 Nuclear Engineering Standards I Accuracy Revision 4 DEP VAR: DOT2 N: 31 MULTIPLE R: 0.178 SQUARED MULTIPLE R: 0.032 ADJUSTED SQUARED MULTIPLE R: .000 STANDARD ERROR OF ESTIMATE: 1.304 VARIABLE COEFFICIENT STD ERROR STD COEF TOLERANCE T P (2 TAIL CONSTANT 0.848 0.740 0.000 1.146 0.266 PERIOD -0.001 0.002 -0.178 1.000 -0.787 0.441 ANALYSIS OF VARIANCE SOURCE SUM-OF- SQUARES DF MEAN. SQUARE F-RATIO P REGRESSION 1.054 1 1.054 0.620 0.441 RESIDUAL 32.319 29 1.701 ~ - '
Revision 411 Example, ANOVA Table Evaluation for Time Dependency Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards Table J4, Time Dependence Evaluation ANOVA Table From this table, the following values will give an indication of the potential for linear time dependency
: 1. X Variable 1 P-value, if less than 0.05, would indicate a time dependency NES-EIC-20
.04 2. ANOVA table F value, if it is greater than the F-table value for a 0.25% probability, the number of data points for the regression, and two degrees of freedom for the numerator, would indicate a time dependency. 2.5.2.5 After the initial regression test the same regression test is applied to the absolute value of the same data. This test detects the increasing variability with calibration interval but will not provide a correct mean. The same decision criteria as the first regression apply but the variable that is being evaluated is the random component of the drift. The slope of the regression will represent the variation in the standard deviation as calibration interval increases if a time dependency is determined. This variation will NOT provide a numerical value for the increase, but will indicate the trend. 2.5.2.6 If neither of the regression tests show an R Z value greater than 0.3, then a review of the mean and standard deviation data for each bin of significance and an evaluation of qualitative plots will assist the engineer in determining time dependence. 2.5.2.7 If the R-Square value is less than 0.1, then the bias component of the drift should be considered to be time independent over the range of the calibration intervals included in the analysis. For those cases with no apparent time dependency, one additional check should be performed to identify any potential problems resulting from increasing uncertainty. The evaluation of the mean and standard deviation of each bin of significance will provide visual trending of the mean and standard deviation with calibration interval. title APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel --Setpoint Error and Instrument Loop Sheet Jl8 of J24 Accuracy Revision 4 ANOVA d SS MS F Regression 001 0.606767762 0.6067678 2.7507691 Residual 119 26.24915424 0.2205811 Total 120 26.855922 Coefficients Standard Error t Stat P - value Intercept 0.1594012 0.087925043 1.8129 13 0.0723646 X Variable 1 -0.0003408 0.000205483
-1.6586443 0.0998413 Revision 4 NES-EIC-20
.04 For each bin that was evaluated, plot the mean and sample standard deviation against the average calibration interval for that bin. These plots will provide visual indication of the stability of the mean and sample standard deviation for the data available. Indications of increased magnitude of the mean and/or the standard deviation with increasing or decreasing calibration interval can be qualitatively assessed. A linear extrapolation of the expected increase in sample standard deviation and mean to the next bin outside the analyzed interval can be determined through the regression of the plotted values for the mean and standard deviation. This will provide a value for the mean and sample standard deviation, in Units/Day, for projection into the next bin. If there are more than three bins with significant data then a regression of the mean and standard deviation values that were plotted can be used for evaluation of the linear fit of the data. 2.5.2.8 Determination of time dependency will be in two parts. One for the bias section and one for the random section of the drift term. These decisions will be based on the following decision process: a. Bias Component If the bias is showing a time dependency it will be deviating from its calibration as-left value of near zero drift as the calibration interval is increased. This deviation will be repeatable in only one direction (positive or negative). 1) If the regression of the data has an R-Square value greater than 0.3 then it is assumed that the data is time dependent. 2) If the R-Square is less than 0.3 but greater than 0.1 then the X Variable I P-value and the F-Value tests should be completed. If either test indicates that the regression is significant then assume time dependency unless there is a reason to disregard the tests. 3) If the R-Square value is less than 0.1 then there is an expectation that the bias is time independent. This will be checked against the qualitative visual information to make a final determination. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards One result that would be a reason for disregarding the regression test is that the result could not represent the real instrument behavior. This has shown up in several cases where the regression line has a large intercept value and then trends toward or crosses the zero drift term. This implies that the maximum drift will occur at time zero which is not the expectation of the instrument calibration process. Title APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J19 of J24 Accuracy Revision 4 Revision 4 Review: 4) The value of the bias will be either the linear extrapolated value of the time dependent regression for a time dependent bias component or the mean of the final data set for a time independent bias component. 5) If the value of bias is determined to be less than 0.1% FS, it will be considered negligible whether it is time independent or time dependent (computed to the maximum surveillance interval). b. Random Component The variation of the data about the mean is normally the larger uncertainty in drift evaluations and this value is the random component of drift. If the magnitude of this variation is a function of calibration interval then this variation can be said to be time dependent. 2) If the R-Square is less than 0.3 but greater than 0.1 then the X Variable 1 P-value and the F-Value tests should be completed. If either test indicates that the regression is significant then assume time dependency unless there is a reason to disregard the tests. 3) If the R-Square value is less than 0.1 then there is an expectation that the random uncertainty is time independent. This will be checked against the qualitative visual information to make a final determination. Review: Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards The scatter plot of all data - Include linear approximation line The plot of the data that was regressed - Include linear approximation line NES-EIC-20
.04 The plot of the means of each significant bin - Include linear approximation line If the review of these plots indicates a clear trend toward an increasing value in the magnitude of the mean versus calibration interval, then engineering judgement should be used to conservatively treat the mean as a linearly time dependent bias. 1) If the regression of the Absolute Value of the data has an R-Square value greater than 0.3 then it is assumed that the data is time dependent. Title APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J20 of J24 Accuracy Revision 4 Revision 4 NES-EIC-20
.04 The scatter plot of all data - Include linear approximation line The plot of the Absolute Value of the data that was regressed - Include linear approximation line The plot of the standard deviation of each significant bin - Include linear approximation line If the review of these plots indicates a clear trend toward a linear variation in the standard deviation with calibration interval, then engineering judgement should be used to assume time dependency for the random component of the uncertainty. 4) The value of the random component of the drift will be either: The linear extrapolated value of the standard deviation of the bins plot for a time dependent random uncertainty or The standard deviation of the data for a time independent random component The interval for which this is valid is only the interval of the bins that were analyzed. 2.5.3 If two or more bins were not identified for analysis then the value of drift from this evaluation must determined from the data from the most populated bin. For this case the process utilized is: 2.5.3.1 Compute the mean and sample standard deviation for the most populated bin. In addition, compute the average calibration interval for the data in that bin. 2.5.3.2 The bias and random components of the drift are then determined by: a. The bias component will be then mean of the data in the single bin. This bias will be considered time independent unless a qualitative evaluation of the data would visually indicate that it is time dependent. Braidwood, Byron, Dresden, Title APPENDIX J LaSalle, and Quad Cities NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J21 of J24 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 NES-EIC-20
.04 2.6 RESULTS Extrapolation of the bias value from this bin to other bins will be by assuming it is a constant value throughout the range of concern for a time independent bias. b. The random component will be the 95/95 tolerance value of the data. This will be assumed to be time independent. Extrapolation to the bin either side of the single bin will require the use of the 99/95 tolerance value for additional conservatism. For extrapolation to larger calibration interval the random value will be expanded using the A2 Equation method of Appendix A Section 3.1. 2.6.1 The results of these as-found/as-left analyses determine a value of derived drift for the instrument make/model. This value will require the following minimum elements: 2.6.1.1 Bias -Will normally be either the mean of the final data set for time independent drift or the intercept (constant) and slope for linear time dependent drift. For time dependent drift, this cannot be from the regression of the absolute value data set but from the final data set. A mean that is less than 0.1% FS will be assumed to be zero. This is a standard value. Bias below this value has no significant effect on the loop uncertainty. 2.6.1.2 Time Dependent Drift Value - For drift that was classified as time dependent, the slope of the regression curve (Units/Day) is the dependent drift value. If this number was determined from the absolute value regression, it still should be specified. 2.6.1.3 Tolerance Value - This value will come from the regression study for time dependent drift. For time independent drift, it will be the sample standard deviation times a multiplier based on the sample size. The selection of the multiplier will be based on the required expectations. Some specific requirements are: Braidwood, Byron, Dresden, Title APPENDIX J LaSalle, and Quad Cities N ES-EIC-20.0 4 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J22 of J24 Nuclear Engineering Standards I Accuracy Revision 4 Revision 4 I NES-EIC-20
.04 99/95 - For cases where only one bin has sufficient data for analysis use this tolerance if the intent is to still assume time independent drift. 95/95 - For RPS and ECCS automatic actuations. If any instruments of the make/model are used for this then the result must be this confidence and tolerance interval. 95/75 - For other safety related instrumentation. If no instruments of this make/model are used for automatic actuations but they are used in safety related indication and alarm circuits then the tolerance value can be reduced to 75%. 75/75 - If the make/model is only used for non-safety related activities. 2.6.1.4 Valid Interval -The bounds of the calibration interval that were included in the analysis. For the above example, the first case would be 0 to 650 days and the second case would be 136 to 650 days. As extrapolation of statistical evaluations are not normally done this provides the data over the range where it should be valid. Some evaluation of the data within the bounding bins may be necessary to ensure that all of the data is not bunched at one interval. If there is bunching of data, the valid interval should be adjusted to account for this effect. 2.6.1.5 Extrapolation Margin - If the data from the analysis is to be extrapolated to either of the adjacent bins from the Valid Interval, then an additional margin will be added to the results of the evaluation. 2.6.2 The analysis should clearly indicate the make/model that it was performed for, and any functions excluded. 2.7 USING THE RESULTS 2.7.1 The data reduction has generated a "drift" value, but that number includes several uncertainties in addition to the classical drift. If the determined drift value is used in uncertainty calculations, the following uncertainties can normally be eliminated. To replace these values state that they are included in the calculated drift value and set their individual values to zero. 2.7.1.1 Reference Accuracy -The reference accuracy of the instrument is included in the calibration data and can be removed from the uncertainty calculation. 2.7.1.2 M&TE - As long as the calibration process uses the same, or more accurate, test equipment then this uncertainty is included in the calibration data and can be removed from the uncertainty calculation. Braidwood, Byron, Dresden, LaSalle, and Quad Cities Nuclear Engineering Standards APPENDIX J NES-EIC-20
.04 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J23 of J24 Accuracy Title Revision 4 Revision 4 NES-EIC-20
.04 2.7.1.3 Drift - The true drift is included in the determined drift and is included in the calibration data and can be removed from the uncertainty calculation. 2.7.1.4 Normal Environmental Effects - For the instruments that are included in the calibration, the effects of variations in radiation, humidity, temperature, vibration, etc. experienced during the calibration are included in the calibration data and can be removed from the uncertainty calculation. These terms cannot be removed from the uncertainty calculations if these components see different conditions or magnitudes of the parameter, such as vibration or temperature, while operating then during calibration. 2.7.1.5 Power Supply Effects - If the instruments are attached to the same power supply during calibration that is used during operation, then the affects are included in the calibration data and can be removed from the uncertainty calculation. 2.7.1.6 Setting Tolerance - If the setting tolerance is such that it is less than the determined drift then this tolerance will show up in that determined drift and can be removed from the uncertainty calculation. If the ST is much larger than the determined drift it will not normally be used in the calibration process and will not be seen in the determined drift. In this case the ST can be combined with the determined drift using SRSS. 2.7.2 For cases were there are time dependent drifts, the time frame used for determining the drift should be the normal surveillance interval plus twenty-five percent. Time dependent drift that is random is assumed to be normally distributed and can be combined using the Square Root Sum of the Squares method for intervals beyond the given interval for the drift as explained in Appendix A and C to this procedure. 2.7.3 Time independent drift can be assumed constant over the Valid Interval. It can also be assumed constant over the interval in the next bin if the Extrapolation Margin is applied. 2.8 CONTINUING EVALUATION 2.8.1 To maintain these evaluations current and to detect increasing drift, the process stipulated in CC-AA-520 "Instrument Performance Trending" shall be followed. Braidwood, Byron, Dresden, Title APPENDIX J LaSalle, and Quad Cities NES-EIC 4 Analysis of Instrument Channel Setpoint Error and Instrument Loop Sheet J 2 4 of J24 Nuclear Engineering Standards I Accuracy Revision 4 ATTACHMENT 2d Exelon Nuclear Procedure ER-AA-520, Revision 3 "Instrument Performance Trending" Exeltba. Nuclear 1. PURPOSE INSTRUMENT PERFORMANCE TRENDING ER-AA-520 Revision 3 Page 1 of 13 Level 3 - Information Use 1.1. This procedure provides the administrative process to implement an instrument trending program. An instrument trending program is a good engineering practice to monitor the behavior of instrumentation to provide early warning of failure. 1.2. This program monitors the results of calibrations of applicable instrumentation in the plant and generates periodic reviews of the data collected during these calibrations to determine what instruments are not performing to expectations. 1.3. This procedure identifies poor performance, which can occur in three basic ways: 1.3.1. An individual instrument could begin to show signs of failure by not meeting Setting Tolerance or exceeding the Leave Alone Zone (LAZ) for repeated calibrations. This is indicative of potential failure of the instrument at some future time. 1.3.2. Most or all of the instruments monitoring a specific plant parameter could begin to show signs of failure by not meeting Setting Tolerance or LAZ for repeated calibrations. This is indicative of the instrument being assigned a Setting Tolerance that is too constrictive for the make/model used. If the Setting Tolerance can not be expanded to prevent repetitive failures, then the instrument may not be the correct one for the parameter of concern. 1.3.3. Most or all of the instruments of a given make/model could begin to show signs of failure by not meeting Setting Tolerance or LAZ for repeated calibrations. This is indicative of the instrument being assigned a Setting Tolerance that is too constrictive for the make/model used. If the Setting Tolerance can not be expanded to prevent repetitive failures, then the instrument may not be the correct one for use. If this occurs after calibrations were successful, then the potential for a common mode failure exists. 1.4. This procedure provides control of the As-Found/As-Left data analysis. This program maintains the analysis conducted as part of the 24-month cycle extension project as required by Generic Letter 91-04 for applicable stations. 1.5. This procedure is applicable to all Exelon Operating Nuclear Stations. All instruments within the stations calibration program that are safety related, tech spec related, Reg. Guide 1.97, or Maintenance Rule instruments shall be included in this program. Those instruments that do not fall into one of the categories listed in the applicability statement are not required to be entered into the out of tolerance and trending program. The stations may choose to include other items in the trending program as they feel appropriate. 
: 2. TERMS AND DEFINITIONS ER-AA-520 Revision 3 Page 2 of 13 1.6. This procedure allows the sites to choose from several methods of trend data recording. Trending may be accomplished by the use of any of the methods outlined within this procedure. This includes the coded CR method, or by use of the as found condition codes within Passport, or the PIMS as found condition codes, or a suitable instrument "As-Found
/ As-left" data trending tool. 2.1. Allowable Value (AV): The limiting value that the trip setpoint may have when tested periodically, beyond which appropriate action shall be taken. The allowable value provides operability criteria for those setpoints or channels that have a limiting operating condition. This limiting condition is typically imposed by the Technical Specifications, but may also result from regulatory requirements, vendor requirements, design basis criteria or other operational limits. 2.2. Leave Alone Zone (LAZ) -Applicable to MAROG: The LAZ is a range of acceptable values around a nominal value established by adding or subtracting the required accuracy from the nominal value. When an instrument reading (cardinal point of calibration or trip setpoint) is found within this band during Surveillance Testing or calibration check, no calibration adjustment is required. In special cases, the LAZ can be established as a non-uniform band around a nominal value. 2.3. Reference Accuracy (RA): A number or quantity that defines a limit that errors will not exceed, when a device is used under specified operating conditions. Includes the combined effects of linearity, hysteresis, deadband, and repeatability. 2.4. Setting Tolerance (ST)/As Left Tolerance (ALT): Inaccuracy or offset introduced into the calibration process due to procedural allowances given to technicians performing the calibration. Proper selection of ST/ALT should take into account the effects of reading error and ease of instrument adjustment. The limits allowed for the "As-left" value of a setpoint or cardinal point during calibration (see Attachment 1). 2.5. Expanded Tolerance (ET)/As Found Tolerance (AFT) -Applicable to MWROG: The tolerance established for trending instruments that are found beyond the ST/ALT. This is a generic term that encompasses other terms presently used for an "As-Found" acceptance criteria including Administrative Limit, Reportable Limit, Performance Limit etc. It is the value established by applying the process described in Attachment
: 1. Trends will be evaluated against this value rather than the Setting Tolerance. 2.6. Out of Tolerance (OOT): The condition that exists when the As Found values for an instrument calibration exceed some pre-established limit or tolerance value (ET or LAZ). 
: 3. RESPONSIBILITIES 3.1. The Site Engineering Director is responsible for: 3.1.1. Implementing the site Instrument Trending Program. 3.1.2. Developing calculations of tolerances pertaining to instruments covered in this procedure with the exception of the "Quick Expanded Tolerance (ET)/As Found Tolerance (AFT)", which is provided for the maintenance supervisors determination and use. 3.2. The Site Maintenance Director , is responsible for: 3.2.1. Implementing the site Instrument Calibration Program. 3.2.2. Coding of calibration work order activity cause and repair codes. 3.3. The Senior Manager, Design Engineering is responsible for: ER-AA-520 Revision 3 Page 3 of 13 3.3.1. Updating the drift analysis for the instrumentation at those sites committed to a Drift Monitoring program using the supplied data once each operating cycle. 3.3.2. Evaluating the Trend Report for indication of common mode failures once per operating cycle. 3.4. The Senior Manager, Plant Engineering is responsible for: 3.4.1. Reviewing the trend report and evaluating instruments associated with a system within a month of receipt of the report. 3.5. The Surveillance Test Coordinator (MAROG only) is responsible for: 3.5.1. Coding of Surveillance Testing work order activity ST Grade codes. 
: 4. MAIN BODY ER-AA-520 Revision 3 Page 4 of 13 4.1. Exceptions - The CR trend codes used in this procedure are a station option. The CR trend codes simply provide the engineer with a way to "bin" all instrument out of tolerances. Therefore, the stations may use the trend codes at their own discretion. Trend Codes are defined in section 4.2.2.1.D 4.2. Requirement s NOTE A: The calibration program is defined within station specific procedures and shall be incorporated into the station work control process to ensure compliance with technical specifications and station commitments. NOTE B: This procedure requires that any instrument covered under the applicability stated in section 1.5 of this procedure, that is out of tolerance, is entered into an appropriate trending process and the trends evaluated as described in this procedure
 
====4.2.1. Reporting====
 
Out of Tolerances of instruments or control devices covered by the station Calibration Program for Stations using Passport and CR Trending method. 1. If an instrument can not be reset to within Setting Tolerance/As Left Tolerance during calibration, then INITIATE a CR to document the information and the instrument will be repaired/replaced. For plants required to collect as-found information, RECORD the information unless the instrument has failed. 2. A. If any as-found data is greater than the AV, WRITE a CR (Subject line to read: Inst. OOT, Equipment ID, and "Trend Code 131"). B. If all as-found data is less than the AV, then WRITE a CR (Subject line to read: Inst. OOT, Equipment ID, and "Trend Code B3"). If the calibration of the instrument/loop had at least one calibration point found outside the Setting Tolerance/As Left Tolerance (i.e. requiring adjustment of the instrument/loop) but the loop is left within the Setting Tolerance/As Left Tolerance, then the following actions are required by maintenance during review of the calibration procedure data: A. If an ET/AFT exists (in the controlled Plant Equipment Database or in the calibration procedure data), COMPARE the as-found data to that data and: 
: 2. If any as-found data is outside the ET/AFT, then proceed to 4.2.1.2. D. B. If an ET/AFT does not exist (in the controlled Plant Equipment Database or in calibration procedure data), then: ER-AA-520 Revision 3 Page 5 of 13 1. If all as-found data is within the ET/AFT, then document this evaluation on the procedure and close the WR without additional required action. 1. If the instrument loop provides a Technical Specification automatic initiation function, initiate an ER or AR/AR Eval. t o obtain a calculation, ET/AFT, and Allowable Value as required. 2. If the instrument loop does not provide a Technical Specification automatic initiation function, then proceed to Section 4.2.1.2.C. C. DETERMINE a Quick ET/AFT using Attachment 1 and EVALUATE the data against the Quick ET/AFT using the following criteria: 1. If all of the calibration data are within the Quick ET/AFT, close the WR without further action. If it is desired to incorporate the ET into the controlled Plant Equipment Database or the calibration procedure, INITIATE an ER or AR / AR Eval. t o do so. 2. If any calibration data is outside the ET/AFT, then proceed to 4.2.1.2. D. D. If any data point exceeds the ET/AFT, DETERMINE if any data point exceeds the Allowable Value (AV) for the instrument/
loop using the following process: 1. If an AV exists for the instrument/loop and a data point exceeds the AV, then WRITE a CR (Subject line to read: Inst. OOT, Equipment ID, and "Trend Code B2", if desired) and notify the shift manager that that instrument loop is potentially inoperable. If an appropriate instrument data trending tool is used, enter the as found and as left information in addition to writing the CR. 2. If no AV exists for the instrument loop, then write a CR (Subject line to read: Inst. OOT, Equipment ID, and "Trend Code B4", if desired) indicating that the instrument/loop was outside its ET/AFT OR record the as found and as left data in an appropriate instrument data trending tool. 3. If data point exceeds the ET/AFT but is inside AV, then write a CR (Subject line to read: Inst. OOT, Equipment ID, and "Trend 
 
====4.2.2. Trend====
Reporting Using The CR Code B4", if desired) OR record the as found and as left data in an appropriate instrument data trending tool. E. The threshold for generating an OOT CR for relays, time delay relays, and level switches calibrated by the Electrical Maintenance Department, Operational Analysis Department, or other department performing maintenance and calibration on these devices should continue to be based on the "TOLERANCE" currently stated in calibration procedures. WRITE a CR (Subject line to read: Inst. OOT, Equipment ID, and "Trend Code B4") if the stated tolerance is exceeded. Note: The following section, 4.2.2.1 does not apply to stations using PIMS for action tracking and an appropriate instrument data trending tool. ER-AA-520 Revision 3 Page 6 of 13 1. To provide for a simple trending process, the CR will be used as the documentation process. CR's written to solely document the trend code of an instrument's calibration should be able to be "closed to trending" (or an equivalent of this) since ER-AA-520 requires periodic reporting. CR's that document inoperability or exceeding tech spec's shall not be closed to trending only. To ensure that the CR will document the necessary information, the following are the minimum requirements that must be included in addition to that normally put in the CR: A. As a minimum, ENSURE that the subject field includes: "Instrument Out of Tolerance (OOT)" B. On the Originator Screen, ENSURE that the Equipment ID is included and that the Equipment ID represents the loop or instrument that is out of tolerance. Also include reference to applicable procedure, WR or surveillance number. C. On the Originator Screen, in the Action Request Description section, ENTER one of the following that most correctly states the degree of Out of Tolerance: 1. "Calibration Data exceeded the ET/AFT (Quick ET/AFT) but did not exceed the AV. Instrument/loop recalibrated to within ST/ALT." If no ET/AFT previously established and a computed ET/AFT is used, document here. 2. "Calibration Data exceeded an AV. Instrument/loop recalibrated to within ST/ALT." 
: 3. "Instrument has failed or can not be recalibrated to within ST/ALT." In addition, PROVIDE the following information
: ER-AA-520 Revision 3 Page 7 of 13 The magnitude and direction of the as-found value and the ET/AFT/ST/AFT
; that is, whatever tolerances were exceeded. The Trend Code, as applicable, in both Action Request Description and Subject sections. D. On the Originator Screen in the Subject section, one of the following statements should be made (trend codes may be omitted at site discretion)
: 1. "Trend Code 131" - At least one as-found data point exceeded the AV for the instrument or loop and the instrument can not be reset to within ST. Notify shift manager that the instrument loop is potentially inoperable. Repair or replace as appropriate. 2. "Trend Code 132" - At least one as-found data point exceeded the AV for the instrument or loop and the instrument can be reset to within ST. Notify shift manager that the instrument loop was potentially inoperable. Recalibrate, repair or replace as appropriate. 3. "Trend Code B3" - No as-found data point exceeded the AV for the instrument or loop and the instrument can not be reset to within ST. Repair or replace as appropriate. 4. "Trend Code B4" - No as-found data exceeded the AV but at least one data point exceeded the ET for the instrument or loop and the instrument can be reset to within the ST. Close CR to trend data point. 4.2.3. Reporting Out of Tolerances of instruments or control devices covered by the station Calibration Program for Stations using PIMS for trending. IF an instrument is Out of Tolerance (beyond LAZ), then: 1. TAKE the appropriate corrective actions in accordance with the applicable site procedures. 2. For Surveillance Testing, DOCUMENT the Test Grade in the PIMS Work Order per the site governing procedure (Ref.6.7) 3. For PIMS corrective
/ preventive Work Order activities, DOCUMENT the cause and repair codes per the site governing procedure.
If an instrument is Out of Tolerance ( beyond its setting tolerance
), then: 4.3. As-Found/As-Left Program 1. Instruments that are required to be trended, will be designated in the appropriate section of the controlled Plant Equipment Database . ER-AA-520 Revision 3 Page 8 of 13 A. DOCUMENT the As-Found and As-Left conditions in the work order Completion Remarks in accordance with MA-MA-716-010-1008, Section 8.5. B. DOCUMENT the appropriate Cause and Repair codes on all Work Order activities in accordance with MA-MA-716-010-1008, Exhibits 8.4.1 and 8.5.1. 4. If already existing, RECORD the As-Found and As-Left data in the instrument calibration program record. 4.2.4. Reporting Out of Tolerances of instruments or control devices covered by the station Calibration Program for Stations using PASSPORT for trending. 1. In Passport document the as found condition in the work order by selecting the appropriate As-Found condition code (summary listing of available codes are in MA-AA-716-011 attachment 2.). 2. Take appropriate actions per site procedures in generating a CR and notifying station management of potential inoperability. 4.3.1. An As-Found / As-Left Program is required only if the plant has committed to it as part of extending it operating cycle to 24 months. It may be implemented for other instrumentation at the discretion of the specific plant. The purpose of this program is to maintain a continuing evaluation of instrument drift based on calibration data and to incorporate any increase in observed drift into the appropriate calculations. 2. The Site Design Engineering group will UPDATE the drift analysis for the instrumentation in the Drift Monitoring program using the supplied data once each operating cycle. 4.4. Trending P rogram 4.4.1. The trending program will provide the plant with the analysis of the data provided by the above Sections. 4.4.2. For Plants using the CR trending approach: Approximately once per operating cycle, Engineering will RUN a Trend Report on the CR database. The trend report should be created by searching on the Subject field for "instrument out of tolerance", &deg;OOT", "Tol" or something similar that will encapsulate all the out of tolerance CR's that 4.4.4. For Plants using the Passport trending approach: Once per Operating Cycle, Engineering will RUN a Trend Report on the Passport Work Order database As Found condition codes. ER-AA-520 Revision 3 Page 9 of 13 were generated during the applicable period of time. This report can be sorted by System, Equipment ID, and, as applicable, trend code. 4.4.3. For Plants using the PIMS trending approach: Once per Operating Cycle, Engineering will RUN a Trend Report on the PIMS Work Order database. Engineering will REVIEW, at a minimum, Surveillance Test Work Orders with grades of "R", "A", and "U", and Work Orders with Cause Codes equal to "C4" and Repair Codes equal to "AA", "AG", "AH", and "AK". 4.4.5. Cognizant System Managers shall REVIEW the report and EVALUATE instruments associated with their systems. If a potential problem with the instrumentation on a system is determined, the System Manager should INITIATE a Trending CR to document the specific adverse trend and to evaluate the instrumentation of concern for appropriate corrective action. Instruments to be considered for evaluation are defined as 2 or more CR's over the last 5 calibration periods for a given instrument, OR 2 or more adverse trend codes (Passport or PIMS conditions reports) over the last 5 calibration periods for a given instrument. 4.4.6. Site Design Engineering will EVALUATE the Trend Report for indication of common mode failures once per operating cycle. If an adverse trend is identified, Design Engineering will INITIATE a Trending CR to evaluate the instrumentation of concern. 1. Adverse Trend CR's should contain the following: A. A description of "instrument out of tolerance trending report". B. A listing of what system / instruments were reviewed. C. A brief description of the resolution. Possible resolutions include: 1. Revise calibration acceptance criteria (i.e. ST, AV, ET, LAZ) 2. Increase surveillance
/ calibration frequency
: 3. Replace the instrument
: 4. Evaluation of correct instrument application
: 2. At least once per operating cycle, Site Design Engineering will PERFORM the following for drift analysis as required per site commitment
: A. For those instruments in the As-Found/As-Left program, Site Design Engineering will UPDATE the drift analysis for the make/model groups. 
: 5. DOCUMENTATION
 
===5.1. Trend===
reports per Section 4.4 6. REFERENCES B. For any updated drift value that either is a larger magnitude or changes from time independent to time dependent, a CR will be WRITTEN to require all associated setpoint calculations to be updated. C. The required ER's or AR / AR eval. will be WRITTEN for any changes in setpoints or tolerances in accordance with CC-AA-103. 6.1. Nuclear Engineering Standard NES -EIC-20.04 (includes Industry Standards)
 
===6.2. Exelon===
Procedure CC-AA-103, Configuration Change Control 6.3. Nuclear Design Informational Transmittal, DIT-BRW-2000-004, PIF Threshold for "Out-Of-Tolerance" Reporting for instruments or Channels Which Have Only an Instrument Calibration Setting Tolerance, 1-18-2000. 6.4. Exelon Procedure LS-AA-105, Operability Determinations
 
===6.5. Exelon===
Procedure LS-AA-125, Corrective Action Program 6.6. Exelon Procedure MA-MA-716-010-1008, Work Order (W/O) Work Performance 6.7. Site Specific Procedure for Surveillance Testing 6.8. Exelon Procedure MA-AA-716-011, Work Execution and Closeout. 7. ATTACHMENTS ER-AA-520 Revision 3 Page 1 0 of 13 6.9. ComEd Licensing submittal to NRC dated March 3, 2000 for technical specification changes for Dresden, Quad Cities, and LaSalle Stations to convert to Improved Standard Technical Specifications. 7.1. Attachment 1: Establishing Setting and Expanded Tolerances/As Found Tolerances (Applicable to MWROG Only)
ATTACHMENT 1 Establishing Setting (As Left) and Expanded (As Found) Tolerances (Applicable to MWROG only) Page 1 of 3 SETTING (As Left) TOLERANCE: Establishing a New Setting Tolerance: ER-AA-520 Revision 3 Page 1 1 of 13 The setting tolerance is selected to allow the technician a band in which an instrument can be left after calibration. This will minimize the amount of adjustment that the technician performs in attempting to set the instrument. This setting tolerance should be included in the evaluation of the uncertainty of the instrument/loop to indicate the monitored process parameter. Allowing too large of a ST can allow too much uncertainty in the loop calibration and/or not allow for detection of potential instrument failure. In some cases new instruments are added to the plant's equipment, or old instruments have not had a setting tolerance established. The following guidance will be used to select the initial setting tolerance of the instrument
: 1. If the instrument has a Reference Accuracy defined, then that value should be selected as the Setting Tolerance. Some adjustment to this value can be accommodated to provide the technician with easy to read values. This value can be adjusted based on system operability requirements. 2. If the ability of the Measurement
& Test Equipment (M&TE) to meet the above ST is not possible then select the ST at the value of the M&TE accuracy. As before, some adjustment to this value can be accommodated to provide the technician with easy to read values. This value can be adjusted based on system operability requirements. 3. To determine STs for loops or partial loops the Square Root Sum of the Squares (SRSS) of the individual instrument STs can be taken. As before, some adjustment to this value can be accommodated to provide the technician with easy to read values.
ATTACHMENT 1 Establishing Setting (As Left) and Expanded (As Found) Tolerances Page 2 of 3 EXPANDED (As Found) TOLERA NCE: (MWROG only) Note: For some stations, the ET is similar to the LAZ and need not be calculated as directed in this attachment. The expanded tolerance is a value that incorporates some of the additional uncertainty that can occur between calibrations. This expanded tolerance is very close to an Allowable Value as defined and explained in ISA S67.04 - 1994 Part I and II. The principle involved is that the instrument will show some drift from calibration to calibration and there are intrinsic uncertainties in calibration itself. If the instrument is in an As-Found state that is within this amount of uncertainty then the instrument is performing as expected in the loop uncertainty calculation. To select an ET perform the following: CALCULATED ET (BY ENGINEERING)
: ER-AA-520 Revision 3 Page 1 2 of 13 1. If there is a formal loop uncertainty calculation that has an Allowable Value calculated for the loop and/or any individual instruments, the ET should be the AV or some percentage of the AV. 2. If the calculation does not compute an AV, then the assumed STs for each instrument can be combined with the Drift and Reference Accuracy of the instrument in a SRSS to determine the ET. The ET for the loop will then be the individual ETs in the loop combined in the same manner as the channel uncertainty was determined. 3. If there is no formal loop uncertainty calculation, then the ET can be computed by conducting a SRSS of the ST, RA and drift of the instrument of concern. If drift is not known then the value of RA or the specified values in NES-EIC-20
.04 can be used. The ET for the loop will then be the SRSS of the individual ETs in the loop. 4. Other processes have been used in ComEd to compute ETs. These values are still valid and the process, if documented in site procedures, can still be used. QUICK ETs (AFTs): The Maintenance Supervisor may need a value to determine the failure code during calibrations when no THE CONTROLLED PLANT EQUIPMENT DATABASE value exists. The following is the acceptable way to compute a quick ET to use for close out of the work package: 1. If the ST is set at the RA of the instrument, multiply the ST by 1.5 and use this as the ET. 2. If the ST is larger than the RA, then use the ST as the ET. 3. If no RA is available, then multiply the ST by 1.5 and use this product as the ET.
WHERE: STPT A.L. S.T. A.F. E.T. A.V. x, Y, z ATTACHMENT 1 Establishing Setting (As Left) and Expanded (As Found) Tolerances Page 3 of 3 Typical Instrument With Setpoint (Example of Decreasing Trip With Allowable Value) A.V. Station Setpoints Value "As Left" Value. Setting Tolerance Value. "As Found" Value. Expanded Tolerance Value. Allowable Value. Tolerances and Uncertainty Values (Illustration Purposes Only) ER-AA-520 Revision 3 Page 13 of 13 +(x+Y)% ET/AFT +x% S.T./ALT STPT NOTE: The arrow indicates the A.L. change made by the technician during calibration. -x% S.T./ALT AF -(x+Y)% E.T./AFT ATTACHMENT 2e LaSalle County Station Instrument Maintenance Surveillance Procedure LIS-RI-103A, Revision 10 "Unit 1 RCIC Equipment Room/Steam Line Tunnel High Ambient and Differential Temperature Outboard Isolation (DIV 1) Calibration" UNIT 1 RCIC EQUIPMENT ROOM/STEAM LINE TUNNEL HIGH AMBIENT AND DIFFERENTIAL TEMPERATURE OUTBOARD ISOLATION (DIV 1) CALIBRATION LIS-RI-103A Revision 10 March 19, 2006 Level of Use Continuous LaSalle Station UNIT I INSTRUMENT MAINTENAN CE SURVEILLANCE I of 57 TABLE OF CONTENTS ATTACHMENTS A Equipment And Materials List...............................................................................53 B Yokogawa (Model DX102) Recorder Figure ........................................................55 C Surveillance/Plant Interface Information
...............................................................56 A. PURPOSE ............................................................................................................................3 B. PREREQUIS ITES ...............................................................................................................4 C. PRECAUTIONS
..................................................................................................................4 D. LIMITATIONS
....................................................................................................................5
 
==E. PROCEDURE==
 
E.1 General Preparations
................................................................................................7 E.2 RCIC Equipment Room High Ambient Temperature (1 E31-ROO I C, Channel 5) Calibration
..................................................................10 E.3 RCIC Equipment Room High Differential Temperature (1 E31-ROOI C, Channels 6 and 7) Calibration
.......................................................19 E.4 RCIC Steam Line Tunnel High Ambient Temperature (1E31-ROOK, Channel 9) Calibration
..................................................................31 E.5 RCIC Steam Line Tunnel High Differential Temperature (1E31-ROOIC, Channels 10 and 11) Calibration
...................................................38 E.6 Test Close Out........................................................................................................50 F. REVIEW AND SIGNOFF.................................................................................................51 G. REFERENCES
..................................................................................................................52 UNIT 1 RCIC EQUIPMENT ROOM/STEAM LINE TUNNEL HIGH AMBIENT AND DIFFERENTIAL TEMPERATURE OUTBOARD ISOLATION (DIV 1) CALIBRATION A. PURPOSE A.1 Obj ective A.2 Discussion Level of Use Continuous This surveillance provides instructions for test and calibration of RCIC Equipment Room/Steam Line High Ambient and Differential Temperature trips in Outboard Isolation (DIV 1) Logic. This surveillance will verify calibration and operability of following equipment: Coil of relay 1E31A-KO02A This surveillance satisfies Channel Calibration and Functional Test requirements of Tech Spec SR 3.3.6.1.2 and SR 3.3.6.1.4 (Table 3.3.6.1-1, Function 3.e, 3.f, 3.g and 31) for instrument channel tested. This surveillance partially satisfies Logic System Functional Test (LSFT) requirements of Tech Spec 3.3.6.1.5 for instrument channels tested that contribute to combined logic. For Sections E.2 and E.4: Burnout protection for recorder channel is verified. Thermocouple resistance values measured and compared with previous resistance values. Calibrator is used to simulate temperature input to recorder. Setpoint, reset point, and indication are measured and documented. All related channel alarm and trip functions are verified. Recorder channel being tested, including trips and alarms, is reset and returned to service prior to reperforming this process for next recorder channel. For Sections E.3 and E.5: Inlet temperature burnout protection for recorder Differential channel temperature is verified. Inlet thermocouple resistance values measured and compared with previous resistance values. Calibrator is used to simulate temperature input to recorder and indication is measured and documented. Calibrator is set to simulate Inlet (reference) temperature. Outlet temperature burnout protection for recorder Differential channel temperature is verified. Outlet thermocouple 3 of 57 LIS-RI-103A Revision 10 March 19, 2006 1E31-NO04A 1E31-ROOK, Channel 5 1 E31-NO05A 1 E31-NO06A 1 E31-ROO I C, Channels 6 and 7 1 E31-N024A 1 E31-ROO I C, Channe Is 9 IE31-NO25A 1E31-NO26A 1E31-ROOIC, Channels 10 and 11 A.3 Applicability PREREQUISITES C. PRECAUTIONS Level of Use Continuous resistance values measured and compared with previous resistance values. Calibrator is used to simulate Outlet temperature inputs to recorder Differential temperature channel. Setpoint, reset point, and indication are measured and documented. All related channel alarm and trip functions are verified. Recorder Differential channel being tested, including trips and alarms, is reset and returned to service prior to reperforming this process for next recorder channels. This surveillance may be performed in any Mode. B.1 Equipment and materials listed on Attachment A available. B.2 Plant conditions are such that keylock switch "DIV I RCIC LD ISOL BYPASS" (1E31A-S2A) on panel 1H13-P632 can be placed in "TEST" position. B.3 For Section E.2, plant conditions are such that keylock switch "DIV I RCIC LD ISOL BYPASS" (1E31A-S2A) on panel 1H13-P632 can be placed in "NORMAL" position. C.1 Due to thermocouple burnout protection, " When Ambient thermocouples are disconnected, recorder channel being tested will go upscale. " When Inlet thermocouples are disconnected, recorder Inlet temperature channel being tested will go downscale, causing corresponding Differential temperature channel to go upscale. " When Outlet thermocouples are disconnected, recorder Differential temperature channel being tested will go upscale. C.2 Recorder 1 E31-R001 C channels initiate both RCIC and MSIV isolation logic, if thermocouple lead is inadvertently lifted on a channel not being tested, an undesired half MSIV Isolation may occur. 4 of 57 LIS-RI-103A Revision 10 March 19, 2006 D. LIMITATIONS D.1 Acceptance Criteria NOTES Letters TS and LSFT are used to designate steps and data related to Technical Specification requirements. If recalibration is required, then acceptance criteria applies to As Left data. Otherwise acceptance criteria applies to As Found data. D.1.1 Instrument calibration data marked with letters TS shall be within stated Calibration Limits. (Tech Spec SR 3.3.6.1.4, Table 3.3.6.1-1, Function 3.e, 3.f, 3.g and 3.h) D.1.2 Trip, alarm and indication functions marked with letters TS or LSFT shall perform as stated. (Tech Spec SR 3.3.6.1.2 and SR 3.3.6.1.5) D.2 Generic D.2.1 Surveillance steps which cannot be completed as stated shall be brought to immediate attention of IM Supervisor and documented on cover sheet. D.2.2 Attachment C information is intended as an aid to Operations and Maintenance personnel and should NOT solely be used to direct or evaluate the use of this surveillance. D.2.3 If, after consultation with IM Supervisor, it is determined that acceptance criteria cannot be met, then these items shall be brought to the immediate attention of Shift Manager or Unit Supervisor. D.2.4 If work (Section E only) is to be stopped for more than 2 hours, then approval of Shift Manager is required per LIP-GM-902. D.2.5 Unit NSO shall be notified when work is stopped or restarted. D.2.6 Direct communications between test locations shall be maintained during active portions of this test. Level of Use Continuous 5 of 57 LIS-RI-103A Revision 10 March 19, 2006 D.3 Specific D.3.1 This surveillance's instructions take precedence. However, they may be supplemented by manufacturer's instructions at discretion of IM Supervisor to provide clarification as needed. D.3.2 Revisions to this surveillance may result in possible required changes to associated LSFT(s) since testing goes beyond end of channels. Level of Use Continuous 6 of 57 LIS-RI-103A Revision 10 March 19, 2006 
 
==E. PROCEDURE==
 
E.1 General Preparations NOTE Previous thermocouple resistance readings may not be available for the referenced procedure. In this case, readings from equivalent procedure(s) should be used. E.1.1 From most recent copy of test results from LIS-RI-103A or equivalent procedure, OBTAIN "As Found Thermocouple Resistance" for following thermocouples and RECORD as "Previous Thermocouple Resistance" where indicated: Level of Use Continuous 7 of 57 LIS-RI-103A Revision 10 March 19, 2006 [ ] " For IE3I-N004A, in Data Table 1 in Section E.2. [ ] For IE31-N005A and IE31-N006A, in Data Tables 3 and 5 respectively in Section E.3. [ ] " For 1E31-N024A, in Data Table 7 in Section E.4. [ ] " For IE31-N025A and 1E31-N026A, in Data Tables 9 and 11 respectively in Section E.5. NOTES Step E.1.4 may be performed in parallel with Steps E.1.2 and E.1.3. Reviews may be expedited by having copies of Attachment C available for distribution to Operations personnel. If desired, Attachment C may be removed from this surveillance and given to Operations personnel. E.1.2 REQUEST Unit Supervisor to PERFORM following: [ ] E.1.2.1 REVIEW details of surveillance's interface with plant provided on Attachment C. [ ] E.1.2.2 VERIFY that performance of this surveillance is compatible with current plant conditions, including other tests and maintenance in progress.
Level of Use Continuous 8 of 57 LIS-RI-103A Revision 10 March 19, 2006 [ ] E.1.2.3 VERIFY timeclock is recorded on cover sheet, or N/A as appropriate, for performance of this surveillance. E.1.2.4 AUTHORIZE start of surveillance. Time Unit Supervisor
/ E.1.3 REQUEST Unit NSO to PERFORM following: [ ] E.1.3.1 REVIEW details of surveillance's interface with plant provided on Attachment C and timeclock recorded on cover sheet. E.1.3.2 AUTHORIZE start of surveillance. Time NSO / [ ] E.1.4 OBTAIN equipment and materials listed on Attachment A and RECORD test equipment calibration data where required. NOTE Sound powered phone communications as follows: 1H13-P601
... SP13 1H13-P632
... SP11 [ ] E.1.5 VERIFY direct communications are available between test locations. [ ] E.1.6 REVIEW timeclock limits recorded on cover sheet and precautions listed in Section C.
NOTE The following step will ensure the associated functions maintain isolation capability as required by Tech Spec 3.3.6.1 Surveillance Requirements Note 2. E.1.7 VERIFY, by checking with Unit Supervisor, that the following Div 2 instrument channels are operable or are NOT required to be operable: Level of Use Continuous " RCIC Equipment Area High Ambient Temperature Isolation " RCIC Equipment Area High Differential Temperature Isolation " RCIC Pipe Tunnel High Ambient Temperature Isolation " RCIC Pipe Tunnel High Differential Temperature Isolation E.1.8 At panel IH13-P601, CHECK following annunciators are reset: "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.1.9 Have any timeclocks been specified (circle Yes or No below)? Yes - NOTIFY Unit NSO that any applicable timeclocks for following RCIC Isolations must be started for Div 1: " RCIC Equipment Room Temperature - High " RCIC Equipment Room Differential Temperature - High " RCIC Steam Line Tunnel Temperature - High " RCIC Steam Line Tunnel Differential Temperature - High No - PROCEED with following steps. 9 of 57 LIS-RI-103A Revision 10 March 19, 2006 [ ] E.1.10 REQUEST Unit NSO to VERIFY "DIV I RCIC LD ISOL BYPASS" switch (1E31A-S2A) on panel IH13-P632 in "TEST" position. [ ] E.1.11 At panel IH13-P601, CHECK annunciator "DIV 1 LD LOGIC PWR FAILURE/IN TEST" (C309) is initiated.
Level of Use Continuous 10 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.2 RCIC Equipment Room High Ambient Temperature (IE31-ROOK, Channel 5) C alibration
[ ] E.2.1 NOTIFY Unit NSO that testing of RCIC Equipment Room High Ambient Temperature is starting. B3 T3 M3 R3 R1 MI T1 131 j&j&j&j@j&j@j8 RELAY BASE PLUG-IN RELAY G & T& N & &I B4 T4 M4 R4 R2 M2 T2 B2 FIGURE 1 Agastat Relay Base E.2.2 At panel 1H13-P632, PERFORM following: [ ] E.2.2.1 CONNECT VOM #1, set to measure 125 Vdc, to terminal BB-75 (+) and terminal T1 (-) of relay 1E31A-KO02A (device CH). (refer to Figure 1) (IE-1-4226AD, 1E-1-4625AA, IE-1-4625AC)
[ ] E.2.2.2 CONNECT VOM #2, set to measure 125 Vdc, to terminal TI (+) of relay IE3IA-KO02A (device CH) and terminal BB-76 (-). (refer to Figure 1) (1E-1-4226AD, 1E-1-4625AA, 1E-1-4625AC)
[ ] E.2.2.3 REQUEST Unit NSO to VERIFY keylock switch "DIV I RCIC LD ISOL BYPASS" (l E3 IA-S2A) in "NORMAL" position. " CHECK VOM #I indicates approximately 0 Vdc. LSFT " CHECK VOM #2 indicates approximately 125 Vdc. LSFT [ ] " CHECK annunciator "DIV 1 LD LOGIC PWR FAILURE/IN TEST" (C309) is reset on panel 1H13-P601. 
[ ] E.2.2.4 REQUEST Unit NSO to VERIFY keylock switch "DIV I RCIC LD ISOL BYPASS" (IE31A-S2A) in "TEST" position. LSFT LSFT " CHECK VOM #1 indicates approximately 65 Vdc. CHECK VOM #2 indicates approximately 65 Vdc. [ ] " CHECK annunciator "DIV 1 LD LOGIC PWR FAILURE/IN TEST" (C309) is initiated on panel IH13-P601. NOTE Recorder IE3I-ROOIC, "DIV 1 LD-RCIC/MSL TEMP RCDR", is located on panel IH13-P632. [ ] E.2.3 At 1E31-ROOK, VERIFY Channel 5 (RCIC AMBIENT TMP - RCIC EQP ROOM) is displayed. [ ] E.2.4 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Ambient thermocouple, causing indication to "peg" upscale. E.2.5 Level of Use Continuous 1 I of 57 LIS-RI-103A Revision 10 March 19, 2006 At 1E31-ROOIC, LIFT following leads: (refer to Attachment (IE-1-4224AG, 1E-1-4625AE)
B) " Purple wire (+) from Channel 5 terminal +/A. LL Tag/Label
/ Red wire (-) from Channel 5 terminal -/B. LL Tag/Label
/
E.2.8.5 Is "Thermocouple Resistance Difference" in Data Table 1 less than 20 ohms (circle Yes or No below)? [ ] E.2.8.6 At panel 1H13-P632, MOVE DMM lead from lifted red (-) thermocouple wire to terminal GG-16 (ground). (1E-1-4625AB)
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. 12 of 57 LIS-R I-103A Revision 10 March 19, 2006 DATA TABLE 1 THERMOCOUPLE 1E31-NO04A RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Performed by Verified by E.2.6 At 1E31-ROOK, CHECK Channel 5 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). E.2.7 At panel IH13-P601, CHECK following annunciators are initiated: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.2.8 PERFORM Thermocouple 1E31-NO04A resistance check as follows: [ ] E.2.8.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 5 of 1E31-ROOK. [ ] E.2.8.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 1. [ ] E.2.8.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 1 and RECORD value for "Thermocouple Resistance Difference" in Data Table 1, then INITIAL for "Performed by" in Data Table 1. [ ] E.2.8.4 REQUEST Verifier to CHECK calculations in Data Table 1, then INITIAL for "Verified by" in Data Table 1.
E.2.8.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 13 of 57 LIS-RI-103A Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.2.8.8 DISCONNECT DMM. E.2.9 OBTAIN As Found data for Channel 5 of 1E31-ROOK as follows: E.2.9.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.2.9.2 SETUP Calibrator
#1 as follows: [ ] E.2.9.2.1 SELECT "SOURCE" mode: [ ] E.2.9.2.2 SELECT Function "TC" [ ] E.2.9.2.3 SELECT TC Type "E", then ENTER. E.2.9.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.2.9.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.2.9.3 At 1E31-ROOIC, CONNECT Calibrator
#1 (with Type E thermocouple wire) to Channel 5 terminals
+/A (purple lead) and -/B (red lead). [ ] E.2.9.4 VERIFY input terminal cover is installed on back of recorder. E.2.9.5 At 1 E31-R001 C, CHECK all Alarm marks for Channel 5 are green. E.2.9.6 At panel 1H13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411)
NOTE Steps E.2.9.8 through E.2.9.11 must be performed in conjunction with Step E.2.9.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.2.9.7 APPLY test inputs listed in Data Table 2 and RECORD As Found values. Level of Use Continuous 14 of 57 LIS-RI-103A Revision 10 March 19, 2006 Level of Use Continuous 15 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 2 1E31-ROOK, CHANNEL 5 (RCIC EQP ROOM) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (OF) 50.0 1 E31-ROO1 C of N/A 50.0 48.0 to 52.0 Channe15 100.0 IE31-ROOIC of N/A 100.0 98.0 to 102.0 Channe15 ALARM Calibrator
#1 &deg;F N/A 120.0 118.0 to 122.0 Setp oin t 150.0 lE31-ROOK of N/A 150.0 148.0 to 152.0 Channel 5 TRIP Calibrator
#1 &deg;F < 291.0 192.0 190.0 to 194.0 Setpoint 200.0 1E31-ROOK o f N/A 200.0 198.0 to 202.0 Channel 5 250.0 IE31-ROOK of N/A 250.0 248.0 to 252.0 Channe15 200.0 IE31-ROOK of N/A 200.0 198.0 to 202.0 Channel 5 TRIP Calibrator
#1 &deg;F N/A N/A N/A Reset Point 150.0 1E31-ROOK of N/A 150.0 148.0 to 152.0 Channel s ALARM Calibrator
#1 &deg;F N/A N/A N/A Reset Point 100.0 1E31-ROOK of N/A 100.0 98.0 to 102.0 Channe15 50.0 1E31-ROOK of N/A 50.0 48.0 to 52.0 Channe15 Performed by (Initials)
: As Found As Left Level of Use Continuous 16 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.2.9.10 When Alarm 1 and 2 marks for Channel 5 turn green on decreasing test signal, then: [I " RECORD Calibrator
#1 reading in As Found Trip Reset Point block of Data Table 2. " At panel 1H13-P632, CHECK VOM #1 indicates approximately LSFT 65 Vdc. " At panel 1H13-P632, CHECK VOM #2 indicates approximately LSFT 65 Vdc. [ " At panel 1H13-P601, CHECK annunciator "DIV 1 RCIC EQUIP AREA DIFF/AMB TEMP HI" (D411) is reset. E.2.9.11 When Alarm 3 mark for Channel 5 turns green on decreasing test signal, then: [ " RECORD Calibrator
#1 reading in As Found Alarm Reset Point block of Data Table 2. [ " At panel 1H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP Hl" (D507) is reset. E.2.9.8 When Alarm 3 mark for Channel 5 turns red on increasing test signal, then: [ ] " RECORD Calibrator
#1 reading in As Found Alarm Setpoint block of Data Table 2. " At panel 1 H 13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is initiated. E.2.9.9 When Alarm 1 and 2 marks for Channel 5 turn red on increasing test signal, then: [ ] " RECORD Calibrator
#1 reading in As Found Trip Setpoint block of Data Table 2. " At panel 1H13-P632, CHECK VOM #1 indicates approximately LSFT 125 Vdc. " At panel 1H13-P632, CHECK VOM #2 indicates approximately LSFT 0 Vdc. " At panel 1H13-P601, CHECK annunciator "DIV 1 RCIC EQUIP Ts AREA DIFF/AMB TEMP HI" (D411) is initiated.
E.2.10 Is As Found data in Data Table 2 within Calibration Limits (circle Yes or No below)? Level of Use Continuous 17 of 57 LIS-RI-103A Revision 10 March 19, 2006 Yes - GO TO Step E.2.11. No - PROCEED with following steps. [ ] E.2.10.1 CIRCLE As Found data in Data Table 2 which is outside Calibration Limits. [ ] E.2.10.2 CONTACT IM Supervisor for further instructions. [ ] E.2.10.3 RECORD As Left data on Data Table 2. E.2.11 At panel 1H13-P632, RESTORE Channel 5 of lE31-ROOK as follows: [ ] E.2.11.1 VERIFY input terminal cover is removed on back of recorder. E.2.11.2 DISCONNECT following test equipment: [ ] " VOM #1 and VOM #2. [ ] " Calibrator
#1. E.2.11.3 At 1E31-ROOK, LAND following leads: " Red wire (-) to Channel 5 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 5 terminal +/A. LL Tag/Label
/ [ ] E.2.11.4 At 1E31-ROOK, CHECK Channel 5 digital display indication is restored and all Alarm marks for Channel 5 are green. E.2.12 At panel 1H13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411)
E.2.13 Is Channel 5 indication on 1E31-ROOK at panel 1H13-P632 within _+ 5.5 &deg;F of Channel 5 indication on 1E31-RO02C at panel 1H13-P642 (circle Yes or No below)? E.2.14 Has Acceptance Criteria, specified in Section D. l, been met (circle Yes or No below)? Level of Use Continuous No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. Yes - PROCEED with following steps. No - CONTACT IM Supervisor for further instructions. Yes - NOTIFY Unit NSO that testing of RCIC Equipment Room High Ambient Temperature is completed. 18 of 57 LIS-RI-103A Revision 10 March 19, 2006 NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Inlet thermocouple, causing indication to "peg" downscale. E.3.4 At IE31-ROOK, LIFT following leads: (refer to Attachment B) (1E-1-4224AG, 1E-1-4625AE)
Level of Use Continuous " Purple wire (+) from Channel 6 terminal +/A. LL Tag/Label " Red wire (-) from Channel 6 terminal -/B. LL Tag/Label / E.3.5 At 1E31-ROOK, CHECK Channel 6 indication is driven downscale and digital display indicates
-* * * * * (burnout protection). 19 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.3 RCIC Equipment Room High Differential Temperature (1E31-ROOIC, Channels 6 and 7) Calibration
[ ] E.3.1 NOTIFY Unit NSO that testing of RCIC Equipment Room High Differential Temperature is starting. NOTE Recorder 1 E31-R001 C, "DIV 1 LD-RCIC/MSL TEMP RCDR", is located on panel 1H13-P632. [ ] E.3.2 At 1 E31-R001 C, VERIFY Channel 6 (RCIC AMBIENT TMP - RCIC EQP RM IN) is displayed. [ ] E.3.3 VERIFY input terminal cover is removed on back of recorder.
E.3.7.5 Is "Thermocouple Resistance Difference" in Data Table 3 less than 20 ohms (circle Yes or No below)? [ ] E.3.7.6 At panel 1H13-P632, MOVE DMM lead from lifted red (-) thermocouple wire to terminal GG-16 (ground). (1E-1-4625AB)
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. 20 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 3 THERMOCOUPLE 1E31-NO05A RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Pe rf o rmed by Verified by E.3.6 At panel 1H13-P601, CHECK following annunciators are initiated: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.3.7 PERFORM Thermocouple 1E31-NO05A resistance check as follows: [ ] E.3.7.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 6 of 1E31-ROOIC. [ ] E.3.7.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 3. [ ] E.3.7.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 3 and RECORD value for "Thermocouple Resistance Difference" in Data Table 3, then INITIAL for "Performed by" in Data Table 3. [ ] E.3.7.4 REQUEST Verifier to CHECK calculations in Data Table 3, then INITIAL for "Verified by" in Data Table 3.
E.3.7.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 21 of 57 LIS-RI-103A Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.7.8 DISCONNECT DMM. E.3.8 OBTAIN As Found data for Channel 6 of 1E31-ROOK as follows: E.3.8.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. Junc. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.3.8.2 SETUP Calibrator
# 1 as follows: [ ] E.3.8.2.1 SELECT "SOURCE" mode: [ ] E.3.8.2.2 SELECT Function "TC" [ ] E.3.8.2.3 SELECT TC Type "E", then ENTER. [ ] E.3.8.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.3.8.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.3.8.3 At 1E31-ROOK, CONNECT Calibrator
#1 (with Type E thermocouple wire) to Channel 6 terminals
+/A (purple lead) and -/B (red lead). [ ] E.3.8.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.3.8.5 APPLY test inputs listed in Data Table 4 and RECORD As Found values.
E.3.9 Is As Found data in Data Table 4 within Calibration Limits (circle Yes or No below)? Level of Use Continuous 22 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 4 1E31-ROOK, CHANNEL 6 (RCIC EQP RM IN) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) 50.0 IE31-ROOK of N/A 50.0 48.0 to 52.0 Channel 6 100.0 1 E3 I-ROO i C of N/A 100.0 98.0 to 102.0 Channel 6 150.0 1E31-ROOK of N/A 150.0 148.0 to 152.0 Channe16 200.0 1E31-ROOK of N/A 200.0 198.0 to 202.0 Channel 6 250.0 1E31-ROOK of N/A 250.0 248.0 to 252.0 Channe16 200.0 1E31-ROOK of N/A 200.0 198.0 to 202.0 Channel 6 150.0 1E31-ROOK of N/A 150.0 148.0 to 152.0 Channe16 100.0 IE31-ROOIC of N/A 100.0 98.0 to 102.0 Channe16 50.0 1E31-ROOK O F N/A 50.0 48.0 to 52.0 Channel 6 Performed by (Initials)
: As Found As Left Yes - GO TO Step E.3.10. No - PROCEED with following steps. [ ] E.3.9.1 CIRCLE As Found data in Data Table 4 which is outside Calibration Limits. [ ] E.3.9.2 CONTACT IM Supervisor for further instructions. [ ] E.3.9.3 RECORD As Left data on Data Table 4. 
[ ] E.3.10 At IE31-ROOK, SET Calibrator
#I to apply test input of 100 &deg;F for Channel 6 Inlet (reference) temperature. E.3.11 At panel IH13-P601, CHECK following annunciators are reset: [ " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) [ ] E.3.12 At 1 E31-ROO I C, VERIFY Channel 7 (RCIC DIFF TEMP - RCIC EQP RM dT) is displayed. [ ] E.3.13 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Outlet thermocouple, causing indication to "peg" upscale. E.3.14 At 1E31-ROOIC, LIFT following leads: (refer to Attachment B) (1E-1-4224AG, IE-1-4625AE)
Level of Use Continuous " If necessary, RAISE Calibrator
#I test input setting until annunciators (D507) and (D411) are reset on panel 1H13-P601. " Purple wire (+) from Channel 7 terminal +/A. LL Tag/Label " Red wire (-) from Channel 7 terminal -B. LL Tag/Label / E.3.15 At 1E31-ROOK, CHECK Channel 7 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). 23 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.3.17.5 Is "Thermocouple Resistance Difference" in Data Table 5 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.17.6 At panel 1H13-P632, MOVE DMM lead from lifted red (-) thermocouple wire to terminal GG-16 (ground). (1E-1-4625AB)
Level of Use Continuous 24 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 5 THERMOCOUPLE 1E31-NO06A RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Performed by Verified by E.3.16 At panel 1H13-P601, CHECK following annunciators are initiated: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ J " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.3.17 PERFORM Thermocouple IE31-NO06A resistance check as follows: [ J E.3.17.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 7 of 1E31-ROOK. [ ] E.3.17.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 5. [ J E.3.17.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 5 and RECORD value for "Thermocouple Resistance Difference" in Data Table 5, then INITIAL for "Performed by" in Data Table 5. [ ] E.3.17.4 REQUEST Verifier to CHECK calculations in Data Table 5, then INITIAL for "Verified by" in Data Table 5.
E.3.17.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 25 of 57 LIS-RI-103A Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.17.8 DISCONNECT DMM. [ ] E.3.18 At 1E31-ROOIC, VERIFY Calibrator
#1 set to apply test input of 100 &deg;F for Channel 6 Inlet (reference) temperature. " MONITOR and MAINTAIN Channel 6 inlet (reference) temperature at 100 &deg;F during calibration of Channel 7. E.3.19 OBTAIN As Found data for Channel 7 of 1 E31-ROO I C as follows: E.3.19.1 VERIFY following in Calibrator
#2 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.3.19.2 SETUP Calibrator
#2 as follows: [ ] E.3.19.2.1 SELECT "SOURCE" mode: [ ] E.3.19.2.2 SELECT Function "TC" [ ] E.3.19.2.3 SELECT TC Type "E", then ENTER. [ ] E.3.19.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.3.19.2.5 SET Calibrator
#2 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.3.19.3 At 1 E31-ROO I C, CONNECT Calibrator
#2 (with Type E thermocouple wire) to Channel 7 terminals
+/A (purple lead) and -/B (red lead). [ ] E.3.19.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.3.19.5 At IE31-ROOK, CHECK all Alarm marks for Channel 7 are green.
At panel IH13-P601, CHECK following annunciators are reset: " "RCIC PIPE RTE EQUIP AREA TEMP HI" (13507) " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (13411) NOTE Steps E.3.19.8 through E.3.19.11 must be performed in conjunction with Step E.3.19.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. APPLY test inputs listed in Data Table 6 and RECORD As Found values. Level of Use Continuous 26 of 57 LIS-RI-103A Revision 10 March 19, 2006 [ ] [ ] E.3.19.6 [ ] E.3.19.7 Level of Use Continuous 27 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 6 1E31-ROOIC, CHANNEL 7 (RCIC EQP RM dT) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) (a) 50.0 1E3I-ROOK of N/A -50.0 -52.0 to -48.0 Channe17 100.0 1E31-ROOIC of N/A 0.0 -2.0 to +2.0 Channel 7 ALARM Calibrator
#2 &deg;F N/A 130.0 128.0 to 132.0 Setpoint (d) (d) 150.0 IE31-ROOK of N/A 50.0 48.0 to 52.0 Channe17 200.0 I E31-ROOI C of N/A 100.0 98.0 to 102.0 Channe17 TRIP Calibrator
#2 &deg;F _< 289.0 208.5 206.5 to 210.5 Setpoint (b) (c) (c) 250.0 1E31-ROOIC of N/A 150.0 148.0 to 152.0 Channel 7 TRIP Calibrator
#2 &deg;F N/A N/A N/A Reset Point 200.0 IE31-ROOIC OF N/A 100.0 98.0 to 102.0 Channe17 150.0 1E31-ROOK of N/A 50.0 48.0 to 52.0 Channe17 ALARM Calibrator
#2 &deg;F N/A N/A N/A Reset Point 100.0 I E31-ROOK Channe17 of N/A 0.0 -2.0 to +2.0 50.0 1E31-ROOIC of N/A -50.0 -52.0 to -48.0 E I Channe17 (a) Test Inputs based upon Inlet (reference) temperature of 100 &deg;F. (b) Allowable Value (LCO): < 289.0 &deg;F equals _< 189.0 &deg;F + 100 &deg;F (reference) (c) Based on nominal trip setpoint of 208.5 &deg;F = 108.5 &deg;F + 100 &deg;F (reference) (d) Based on nominal alarm setpoint of 130.0 &deg;F = 30.0 &deg;F + 100 &deg;F (reference)
Performed by (Initials)
: As Found As Left Level of Use Continuous 28 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.3.19.8 When Alarm 3 mark for Channel 7 turns red on increasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Alarm Setpoint block of Data Table 6. " At panel 1H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is initiated. E.3.19.9 When Alarm 1 and 2 marks for Channel 7 turn red on increasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Trip Setpoint block of Data Table 6. " At panel 1H13-P601, CHECK annunciator "DIV I RCIC EQUIP Ts AREA DIFF/AMB TEMP HI" (D411) is initiated. E.3.19.10 When Alarm 1 and 2 marks for Channel 7 turn green on decreasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Trip Reset Point block of Data Table 6. " At panel 1H13-P601, CHECK annunciator "DIV 1 RCIC EQUIP AREA DIFF/AMB TEMP HI" (D411) is reset. E.3.19.11 When Alarm 3 mark for Channel 7 turns green on decreasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Alarm Reset Point block of Data Table 6. " At panel 1H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is reset. E.3.20 Is As Found data in Data Table 6 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.3.21. No - PROCEED with following steps. [ ] E.3.20.1 CIRCLE As Found data in Data Table 6 which is outside Calibration Limits. [ ] E.3.20.2 CONTACT IM Supervisor for further instructions. [ ] E.3.20.3 RECORD As Left data on Data Table 6.
Level of Use Continuous 29 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.3.21 At panel 1H13-P632, RESTORE Channels 6 and 7 of IE31-ROOIC as follows: [ ] E.3.21.1 VERIFY input terminal cover is removed on back of recorder. [ ] E.3.21.2 DISCONNECT Calibrator
#I and Calibrator
#2. E.3.21.3 At 1E31-ROOIC, LAND following leads: " Red wire (-) to Channel 6 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 6 terminal +/A. LL Tag/Label
/ [ ] E.3.21.4 At 1 E31-ROO I C, VERIFY Channel 6 digital display indication is restored. E.3.21.5 At IE31-ROOK, LAND following leads: " Red wire (-) to Channel 7 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 7 terminal +/A. LL Tag/Label
/ [ ] E.3.21.6 At 1E31-ROO1C, VERIFY Channel 7 digital display indication is restored and all Alarm marks for Channel 7 are green. E.3.22 At panel IH13-P601, CHECK following annunciators are reset: [ ] "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411)
E.3.23 Is Channel 7 indication on 1 E31-R001 Cat panel 1 H13-P632 within +/- 7.5 &deg;F of Channel 7 indication on 1E31-R002C at panel 1H13-P642 (circle Yes or No below)? E.3.24 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)? Level of Use Continuous No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. Yes - PROCEED with following steps. No - CONTACT IM Supervisor for further instructions. Yes - NOTIFY Unit NSO that testing of RCIC Equipment Room High Differential Temperature is completed. 30 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.4 RCIC Steam Line Tunnel High Ambient Temperature (IE31-ROOIC, Channel 9) Calibration
[ ] E.4.1 NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Ambient Temperature is starting. NOTE Recorder I E3I-ROO K, "DIV 1 LD-RCIC/MSL TEMP RCDR", is located on panel 1H13-P632. [ ] E.4.2 At 1 E31-R001 C, VERIFY Channel 9 (RCIC AMBIENT TMP - RCIC STM LN TNL) is displayed. [ ] E.4.3 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Ambient thermocouple, causing indication to "peg" upscale. E.4.4 At 1E31-ROOIC, LIFT following leads: (terminals located on left side, refer to Attachment B) (IE-I-4224AE, IE-I-4625AE)
Level of Use Continuous " Purple wire (+) from Channel 9 terminal +/A. LL Tag/Label " Red wire (-) from Channel 9 terminal -/B. LL Tag/Label / E.4.5 At 1 E31-ROOI C, CHECK Channel 9 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). 31 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.4.7.5 Is "Thermocouple Resistance Difference" in Data Table 7 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.4.7.6 At panel 1H13-P632, MOVE DMM lead from lifted red (-) thermocouple wire to terminal GG-16 (ground). (1E-1-4625AB)
Level of Use Continuous 32 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 7 THERMOCOUPLE 1E31-N024A RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Performed by Verified by E.4.6 At panel 1H13-P601, CHECK following annunciators are initiated: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.4.7 PERFORM Thermocouple 1E31-N024A resistance check as follows: [ ] E.4.7.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 9 of 1E31-ROOK. [ ] E.4.7.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 7. [ ] E.4.7.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 7 and RECORD value for "Thermocouple Resistance Difference" in Data Table 7, then INITIAL for "Performed by" in Data Table 7. [ ] E.4.7.4 REQUEST Verifier to CHECK calculations in Data Table 7, then INITIAL for "Verified by" in Data Table 7.
E.4.7.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 33 of 57 LIS-RI-103A Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.4.7.8 DISCONNECT DMM. E.4.8 OBTAIN As Found data for Channel 9 of 1E31-ROOIC as follows: E.4.8.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. Junc. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.4.8.2 SETUP Calibrator
#1 as follows: [ ] E.4.8.2.1 SELECT "SOURCE" mode: [ ] E.4.8.2.2 SELECT Function "TC" [ ] E.4.8.2.3 SELECT TC Type "E", then ENTER. [ ] E.4.8.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.4.8.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.4.8.3 At I E31-R001 C, CONNECT Calibrator
# 1 (with Type E thermocouple wire) to Channel 9 terminals
+/A (purple lead) and -/B (red lead). [ ] E.4.8.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.4.8.5 At 1 E31-R001 C, CHECK all Alarm marks for Channel 9 are green. E.4.8.6 At panel 1H13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411)
NOTE Steps E.4.8.8 through E.4.8.11 must be performed in conjunction with Step E.4.8.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.4.8.7 APPLY test inputs listed in Data Table 8 and RECORD As Found values. Level of Use Continuous 34 of 57 LIS-RI-103A Revision 10 March 19, 2006 Level of Use Continuous 35 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 8 1E31-ROOK, CHANNEL 9 (RCIC STM LN TNL) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) 50.0 1E31-ROOIC
&deg; F N/A 50.0 48.0 to 52.0 Channel 9 100.0 1E31-ROOIC
&deg;F N/A 100.0 98.0 to 102.0 Channel 9 150.0 1E31-ROOK
&deg;F N/A 150.0 148.0 to 152.0 Channel 9 ALARM Calibrator
#I &deg;F N/A 186.5 184.5 to 188.5 Setpoint TRIP Calibrator
#1 &deg;F _< 267.0 192.0 190.0 to 194.0 Setpoint (a) 200.0 IE31-ROOK
&deg;F N/A 200.0 198.0 to 202.0 Channe19 250.0 1E31-ROOK
&deg;F N/A 250.0 248.0 to 252.0 Channel 9 200.0 IE31-ROOK
&deg;F N/A 200.0 198.0 to 202.0 Channel 9 TRIP Calibrator
#1 &deg;F N/A N/A N/A Reset Point ALARM Calibrator
#1 &deg;F N/A N/A N/A Reset Point 1E31-ROOK N/A 150.0 148.0 to 152.0 150.0 Channel 9 &deg;F 100.0 IE31-ROOK
&deg;F N/A 100.0 98.0 to 102.0 Channe19 50.0 1E31-ROOK
&deg;F N/A 50.0 48.0 to 52.0 Channel 9 (a) Allowable Value per Operability Evaluation OE 05-003 Performed by (Initials)
: As Found As Left Level of Use Continuous 36 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.4.8.8 When Alarm 3 mark for Channel 9 turns red on increasing test signal, then: [ ] " RECORD Calibrator
#1 reading in As Found Alarm Setpoint block of Data Table 8. " At panel 1H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is initiated. E.4.8.9 When Alarm 1 and 2 marks for Channel 9 turn red on increasing test signal, then: [ ] " RECORD Calibrator
#I reading in As Found Trip Setpoint block of Data Table 8. " At panel 1H13-P601, CHECK annunciator "DIV 1 RCIC EQUIP Ts AREA DIFF/AMB TEMP HI" (D411) is initiated. E.4.8.10 When Alarm 1 and 2 marks for Channel 9 turn green on decreasing test signal, then: [ ] " RECORD Calibrator
#1 reading in As Found Trip Reset Point block of Data Table 8. [ ] " At panel 1H13-P601, CHECK annunciator "DIV 1 RCIC EQUIP AREA DIFF/AMB TEMP HI" (D411) is reset. E.4.8.11 When Alarm 3 mark for Channel 9 turns green on decreasing test signal, then: [ ] " RECORD Calibrator
#1 reading in As Found Alarm Reset Point block of Data Table 8. [ ] " At panel 1 H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is reset. E.4.9 Is As Found data in Data Table 8 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step EA. 10. No - PROCEED with following steps. [ ] E.4.9.1 CIRCLE As Found data in Data Table 8 which is outside Calibration Limits. [ ] E.4.9.2 CONTACT IM Supervisor for further instructions. [ ] E.4.9.3 RECORD As Left data on Data Table 8.
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. Yes - NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Ambient Temperature is completed. 37 of 57 LIS-RI-103A Revision 10 March 19, 2006 EA. 10 At panel 1H13-P632, RESTORE Channel 9 of 1E31-ROOK as follows: [ ] EA. 10.1 VERIFY input terminal cover is removed on back of recorder. [ ] E.4.10.2 DISCONNECT Calibrator
#1. E.4.10.3 At 1 E31-ROO I C, LAND following leads: " Red wire (-) to Channel 9 terminal -/B. 1 LL Tag/Label " Purple wire (+) to Channel 9 terminal +/A. LL Tag/Label
/ [ ] E.4.10.4 At IE3I-ROOK, CHECK Channel 9 digital display indication is restored and all Alarm marks for Channel 9 are green. E.4.11 At panel 1H13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.4.12 Is Channel 9 indication on I E31-R001 C at panel 1H13-P632 minus 10.0 &deg;F within _+ 5.5 &deg;F of Channel 9 indication on 1E31-RO02C at panel 1H13-P642 (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. Yes - PROCEED with following steps. E.4.13 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)?
NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Inlet thermocouple, causing indication to "peg" downscale. E.5.4 At IE3I-ROOIC, LIFT following leads: (terminals located on left side, refer to Attachment B) (IE-I-4224AE, lE-I-4625AE)
Level of Use Continuous Purple wire (+) from Channel 10 terminal +/A. LL Tag/Label " Red wire (-) from Channel 10 terminal -B. LL Tag/Label / E.5.5 At IE31-ROOIC, CHECK Channel 10 indication is driven downscale and digital display indicates
-* * * * * (burnout protection). 38 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.5 RCIC Steam Line Tunnel Huh Differential Temperature (1E31-ROOIC, Channels 10 and 11) C alibration
[ ] E.5.1 NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Differential Temperature is starting. NOTE Recorder IE31-ROOK, "DIV I LD-RCIC/MSL TEMP RCDR", is located on panel 1H13-P632. [ ] E.5.2 At 1 E31-ROO I C, VERIFY Channel 10 (RCIC AMBIENT TMP - RCIC STM TNL IN) is displayed. [ ] E.5.3 VERIFY input terminal cover is removed on back of recorder.
E.5.7.5 Is "Thermocouple Resistance Difference" in Data Table 9 less than 20 ohms (circle Yes or No below)? [ ] E.5.7.6 At panel IH13-P632, MOVE DMM lead from lifted red (-) thermocouple wire to terminal GG-16 (ground). (1E-1-4625AB)
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. 39 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 9 THERMOCOUPLE IE31-N025A RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Pe rf o rmed by Verified by E.5.6 At panel 1 H 13-P601, CHECK following annunciators are initiated: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.5.7 PERFORM Thermocouple 1E31-N025A resistance check as follows: [ ] E.5.7.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 10 of IE3I-ROOIC. [ ] E.5.7.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 9. [ ] E.5.7.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 9 and RECORD value for "Thermocouple Resistance Difference" in Data Table 9, then INITIAL for "Performed by" in Data Table 9. [ ] E.5.7.4 REQUEST Verifier to CHECK calculations in Data Table 9, then INITIAL for "Verified by" in Data Table 9.
E.5.7.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 40 of 57 LIS-RI-103A Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.5.7.8 DISCONNECT DMM. E.5.8 OBTAIN As Found data for Channel 10 of 1E31-ROOIC as follows: E.5.8.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.5.8.2 SETUP Calibrator
#1 as follows: [ ] E.5.8.2.1 SELECT "SOURCE" mode: [ ] E.5.8.2.2 SELECT Function "TC" [ ] E.5.8.2.3 SELECT TC Type "E", then ENTER. [ ] E.5.8.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.5.8.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.5.8.3 At 1E31-ROOK, CONNECT Calibrator
#1 (with Type E thermocouple wire) to Channel 10 terminals
+/A (purple lead) and -/B (red lead). [ ] E.5.8.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.5.8.5 APPLY test inputs listed in Data Table 10 and RECORD As Found values.
Level of Use Continuous 41 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 10 IE31-ROOIC, CHANNEL 10 (RCIC STM TNL IN) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) 50.0 1E31-ROOIC of N/A 50.0 48.0 to 52.0 Channel 10 100.0 IE31-ROOK of N/A 100.0 98.0 to 102.0 Channel 10 150.0 IE31-ROOK of N/A 150.0 148.0 to 152.0 Channel 10 200.0 1E31-ROOK of N/A 200.0 198.0 to 202.0 Channel 10 250.0 1E31-ROOK of N/A 250.0 248.0 to 252.0 Channe110 200.0 IE31-ROOIC o f N/A 200.0 198.0 to 202.0 Channel 10 150.0 1E31-ROOIC of N/A 150.0 148.0 to 152.0 Channel 10 100.0 IE31-ROOIC o f N/A 100.0 98.0 to 102.0 Channel 10 50.0 IE31-ROOK of N/A 50.0 48.0 to 52.0 Channel 10 Performed by (Initials)
: As Found As Left E.5.9 Is As Found data in Data Table 10 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.5.10. No - PROCEED with following steps. [ ] E.5.9.1 CIRCLE As Found data in Data Table 10 which is outside Calibration Limits. [ ] E.5.9.2 CONTACT IM Supervisor for further instructions. [ ] E.5.9.3 RECORD As Left data on Data Table 10.
NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Outlet thermocouple, causing indication to "peg" upscale. E.5.14 At 1E31-ROOIC, LIFT following leads: (terminals located on left side, refer to Attachment B) (1E-1-4224AE, lE-I-4625AE)
Level of Use Continuous " Purple wire (+) from Channel I I terminal +/A. LL Tag/Label " Red wire (-) from Channel I 1 terminal -/B. LL Tag/Label / E.5.15 At 1E31-ROOIC, CHECK Channel l I indication is driven upscale and digital display indicates
+* * * * * (burnout protection). 42 of 57 LIS-RI-103A Revision 10 March 19, 2006 [ ] E.5.10 At IE31-ROOIC, SET Calibrator
#I to apply test input of 100 &deg;F for Channel 10 Inlet (reference) temperature. " If necessary, RAISE Calibrator
#1 test input setting until annunciators (D507) and (D411) are reset on panel 1 H13-P601. E.5.11 At panel 1H13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.5.12 At 1 E31-ROO I C, VERIFY Channel 1 I (RCIC DIFF TEMP - RCIC STM TNL dT) is displayed. [ ] E.5.13 VERIFY input terminal cover is removed on back of recorder.
E.5.17.5 Is "Thermocouple Resistance Difference" in Data Table 11 less than 20 ohms (circle Yes or No below)? [ ] E.5.17.6 At panel 1H13-P632, MOVE DMM lead from lifted red (-) thermocouple wire to terminal GG-16 (ground). (1E-1-4625AB)
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. 43 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 11 THERMOCOUPLE 1E31-N026A RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Performed by Verified by E.5.16 At panel 1H13-P601, CHECK following annunciators are initiated: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV 1 RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) E.5.17 PERFORM Thermocouple 1E31-N026A resistance check as follows: [ ] E.5.17.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 11 of 1 E31-R001 C. [ ] E.5.17.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 11. [ ] E.5.17.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 11 and RECORD value for "Thermocouple Resistance Difference" in Data Table 11, then INITIAL for "Performed by" in Data Table 11. [ ] E.5.17.4 REQUEST Verifier to CHECK calculations in Data Table 11, then INITIAL for "Verified by" in Data Table 11.
E.5.17.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 44 of 57 LIS-RI-103A Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.5.17.8 DISCONNECT DMM. [ ] E.5.18 At 1E31-ROOIC, VERIFY Calibrator
#1 set to apply test input of 100 &deg;F for Channel 10 Inlet (reference) temperature. " MONITOR and MAINTAIN Channel 10 inlet (reference) temperature at 100 &deg;F during calibration of Channel 11. E.5.19 OBTAIN As Found data for Channel 11 of 1E31-ROOIC as follows: E.5.19.1 VERIFY following in Calibrator
#2 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.5.19.2 SETUP Calibrator
#2 as follows: [ ] E.5.19.2.1 SELECT "SOURCE" mode: [ ] E.5.19.2.2 SELECT Function "TC" [ ] E.5.19.2.3 SELECT TC Type "E", then ENTER. [ ] E.5.19.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.5.19.2.5 SET Calibrator
#2 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.5.19.3 At 1E31-ROOK, CONNECT Calibrator
#2 (with Type E thermocouple wire) to Channel 1 I terminals
+/A (purple lead) and -/B (red lead). [ ] E.5.19.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.5.19.5 At 1 E31-ROO I C, CHECK all Alarm marks for Channel I 1 are green.
E.5.19.6 At panel 1H13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV I RCIC EQUIP AREA DIFF AMB TEMP HI" (D411) NOTE Steps E.5.19.8 through E.5.19.11 must be performed in conjunction with Step E.5.19.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.5.19.7 APPLY test inputs listed in Data Table 12 and RECORD As Found values. Level of Use Continuous 45 of 57 LIS-RI-103A Revision 10 March 19, 2006 Level of Use Continuous 46 of 57 LIS-RI-103A Revision 10 March 19, 2006 DATA TABLE 12 1E31-ROOIC, CHANNEL 11 (RCIC STM TNL dT) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) (a) 50.0 1E31-ROOK of N/A -50.0 -52.0 to -48.0 Channel 1 l 100.0 1E31-ROOK of N/A 0.0 -2.0 to +2.0 Channel 11 150.0 1E31-ROOK of N/A 50.0 48.0 to 52.0 Channel 11 200.0 IE31-ROOK of N/A 100.0 98.0 to 102.0 Channel 11 ALARM Calibrator
#2 &deg;F N/A 202.0 200.0 to 204.0 Setpoint (d) (d) TRIP Calibrator
#2 &deg;F _< 255.0 208.5 206.5 to 210.5 Setpoint (b) (c) (c) 250.0 1E31-ROOK of N/A L 150.0 148.0 to 152.0 Channel 11 I I L I L TRIP Calibrator
#2 F &deg;F N/A N/A N/A Reset Point ALARM Calibrator
#2 ~ &deg;F N/A N/A N/A Reset Point ( I ( 200.0 IE31-ROOK 0F N/A 100.0 98.0 to 102.0 Channel l l 150.0 IE31-ROOK of N/A 50.0 48.0 to 52.0 Channel l l 100.0 1E31-ROOK o f N/A 0.0 -2.0 to +2.0 Channel l l 50.0 IE31-ROOK of N/A -50.0 -52.0 to -48.0 Channel l l (a) Test Inputs based upon Inlet (reference) temperature of 100 &deg;F. (b) Allowable value (LCO): < 255.0 &deg;F equals < 155.0 &deg;F + 100 &deg;F (reference) (c) Based on nominal trip setpoint of 208.5 &deg;F = 108.5 &deg;F + 100 &deg;F (reference) (d) Based on nominal alarm setpoint of 202.0 &deg;F = 102.0 &deg;F + 100 &deg;F (reference)
Performed by (Initials)
: As Found As Left  . .
E.5.19.8 When Alarm 3 mark for Channel 11 turns red on increasing test signal, then: Level of Use Continuous " RECORD Calibrator
#2 reading in As Found Alarm Setpoint block of Data Table 12. " At panel 1H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is initiated. E.5.19.9 When Alarm 1 and 2 marks for Channel 11 turn red on increasing test signal, then: 47 of 57 LIS-RI-103A Revision 10 March 19, 2006 [] Ts " RECORD Calibrator
#2 reading in As Found Trip Setpoint block of Data Table 12. " At panel 1H13-P601, CHECK annunciator "DIV I RCIC EQUIP AREA DIFF/AMB TEMP HI" (D411) is initiated. E.5.19.10 When Alarm 1 and 2 marks for Channel 11 turn green on decreasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Trip Reset Point block of Data Table 12. [ ] " At panel 1H13-P601, CHECK annunciator "DIV 1 RCIC EQUIP AREA DIFF/AMB TEMP HI" (D411) is reset. E.5.19.11 When Alarm 3 mark for Channel 11 turns green on decreasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Alarm Reset Point block of Data Table 12. [ ] " At panel 1 H13-P601, CHECK annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) is reset. E.5.20 Is As Found data in Data Table 12 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.5.21. No - PROCEED with following steps. [ ] E.5.20.1 CIRCLE As Found data in Data Table 12 which is outside Calibration Limits. [ ] E.5.20.2 CONTACT IM Supervisor for further instructions. [ ] E.5.20.3 RECORD As Left data on Data Table 12.
Level of Use Continuous 48 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.5.21 At panel I H13-P632, RESTORE Channels 10 and 11 of 1 E31-ROO I C as follows: E.5.21.1 VERIFY input terminal cover is removed on back of recorder. [ ] E.5.21.2 DISCONNECT Calibrator
#I and Calibrator
#2. E.5.21.3 At IE31-ROOK, LAND following leads: " Red wire (-) to Channel 10 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 10 terminal +/A. LL Tag/Label
/ [ ] E.5.21.4 At IE3I-ROOIC, VERIFY Channel 10 digital display indication is restored. E.5.21.5 At I E31-ROO I C, LAND following leads: " Red wire (-) to Channel I 1 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 11 terminal +/A. LL Tag/Label
/ [ ] E.5.21.6 At IE31-ROOIC, VERIFY Channel 1 I digital display indication is restored and all Alarm marks for Channel I 1 are green. E.5.22 At panel IH13-P601, CHECK following annunciators are reset: [ ] " "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) [ ] " "DIV I RCIC EQUIP AREA DIFF AMB TEMP HI" (D411)
E.5.23 Is Channel 11 indication on 1E31-ROOICat panel 1H13-P632 within +7.5 &deg;F of Channel 11 indication on 1E31-RO02C at panel 1H13-P642 (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. E.5.24 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)? Level of Use Continuous Yes - PROCEED with following steps. No - CONTACT IM Supervisor for further instructions. Yes - NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Differential Temperature is completed. 49 of 57 LIS-R1-103A Revision 10 March 19, 2006 Level of Use Continuous 50 of 57 LIS-RI-103A Revision 10 March 19, 2006 E.6 Test Close Out [ ] E.6.1 At panel 1H13-P632, VERIFY input terminal cover is installed on back of recorder 1 E31-R001 C. E.6.2 Does Unit Supervisor require panel 1H13-P632 switch "DIV I RCIC LD ISOL BYPASS" (1E31A-S2A) to remain in "TEST position (circle Yes or No below)? No - REQUEST Unit NSO to VERIFY panel 1H13-P632 switch "DIV I RCIC LD ISOL BYPASS" (IE31A-S2A) is in "NORMAL" position. Yes - Unit Supervisor DOCUMENT reason for switch remaining in "TEST" position in Comments section of cover sheet. E.6.3 Is panel 1H13-P632 switch "DIV I RCIC LD ISOL BYPASS" (1E31A-S2A) in "NORMAL" position (circle Yes or No below)? Yes - CHECK panel 1H13-P601 annunciator "DIV 1 LD LOGIC PWR FAILURE/IN TEST" (C309) is reset or N/A, if keylock switch "DIV I RWCU LD ISOL BYPASS" (1E31A-SIA) on panel 1H13-P632 is in "TEST" position. No - PROCEED with following steps. E.6.4 NOTIFY Unit NSO that: [ ] E.6.4.1 Surveillance has been completed. [ ] E.6.4.2 Any timeclock that may be in affect for performance of this surveillance may be stopped. [ ] E.6.5 NOTIFY Unit Supervisor that surveillance has been completed. [ ] E.6.6 VERIFY all personnel whose initials appear in this surveillance have completed Section F. [ ] E.6.7 DELIVER completed surveillance to IM Supervisor for final review and processing.
F. REVIEW AND SIGNOFF Performed by: (When indirect signoff used, signature indicates concurrence with use of initials)
Name (Print) Initials Signature Comments: Level of Use Continuous (Attach additional pages if necessary) 51 of 57 LIS-RI-103A Revision 10 March 19, 2006 G. REFERENCES Level of Use Continuous " 3.3.6.1, Primary Containment Isolation Instrumentation " Table 3.3.6.1-1 " SR 3.3.6.1.2, SR 3.3.6.1.4 and SR 3.3.1.5 52 of 57 LIS-RI-103A Revision 10 March 19, 2006 G.1 Schematic Diagrams: " 1 E- I -4224AA, AC, AE, AG, and AM " lE-I-4226AD 1E-1-4232AH G.2 Wiring Diagrams: " 1E-1-4625AA, AB, AC, AD, and AE G.3 Vendor Manual No. J-0949.000, "Yokogawa DAQStation DX100 Series and DX 200 Series" G.4 LIP-GM-902, General Requirements for Performance of Instrument Maintenance Department Procedures G.5 DCP 9700532, Unit I RWCU Leak Detection Modification G.6 SEAG 00-000444, ITS/24 Month Procedure Setpoint Data G.7 EC 51553, Replace Riley Temperature Switches G.8 EC 348527, Determination of Bias in Channel Checks for Leak Detection Temperature System - Unit 1 G.9 EC 356974, Leak Detection Recorder Temperature Alarms G.10 Calculation NED-I-EIC-0213, RCIC Equipment Area/Pipe Tunnel High Ambient & Differential Temperature Outboard & Inboard Isolation Error Analysis G.11 Operability Evaluation OE 05-003, RCIC Steam Line Tunnel Ambient Temperature - High G.12 Technical Specification references
:
Test Equipment Following equipment is required for normal performance of surveillance
: 1. DMM (HP 34401A) ID Number Cal. Due 2. Honeywell 2020 System Calibrator
#1 with Type E thermocouple wire ID Number Cal. Due 3. Honeywell 2020 System Calibrator
#2 with Type E thermocouple wire NOTE VOMs may not be substituted by equivalent equipment and must be of the same model/manufacturer. 3. VOMs - 2 required (not used for analytical measurements)
: 4. Test leads: Level of Use Continuous ATTACHMENT A EQUIPMENT AND MATERIALS LIST ID Number Cal. Due " Banana to alligator - 2 required " Banana to banana - 4 required. (stackable)
: 5. Lifted Lead Tags Labels - 4 required (N/A, if labeling is used) 6. Key #2, "DIV I RCIC LD ISOL BYPASS" (1E31A-S2A) on panel 1H13-P632
* Equivalent equipment (i.e., performing same function and covering similar range with equal or better accuracy) may be used in place of equipment listed. 53 of 57 LIS-RI-103A Revision 10 March 19, 2006 Consumables Tools None ATTACHMENT A (continued)
Following is a recommended tool list. Additions, deletion, and substitutions may be made at discretion of IM Technician. 1. Screwdriver - Phillips 2. Screwdriver - Holding (Phillips or Flat Blade) 3. Screwdriver - 6" Flat Blade Level of Use Continuous 54 of 57 LIS-RI-103A Revision 10 March 19, 2006 Level of Use Continuous ATTACHMENT B YOKOGAWA (MODEL DX102) RECORDER FIGURE (rear view) 0-10 55 of 57 NCI I glarmiRelay C II Terminal -Input Terminal LIS-RI-103A Revision 10 March 19, 2006 EQU IPMENT FUNCTION ATTACHMENT C SURVEILLANCE/PLANT INTERFACE INFORMATION Recorder channels calibrated and functionally tested by this surveillance provide isolation signal to 1E51-F008 for RCIC Equipment Room and Steam Line High Ambient and Differential Temperature on Division 1. Channels 5 and 9 of temperature recorder 1E31-ROOK monitor ambient temperature of RCIC Equipment Room and Steam Line respectively. Channels 6 and 10 of temperature recorder 1E31-ROOK monitor inlet (reference) temperature of RCIC Equipment Room and Steam Line respectively. Channels 7 and 11 of temperature recorder 1E31-ROOIC monitor differential between outlet and inlet (reference) temperature of RCIC Equipment Room and Steam Line respectively. Channels are calibrated to actual alarm setpoints of 120.0 &deg;F (Channel 5), 30.0 &deg;F (Channel 7), 186.5 &deg;F (Channel 9), 102.0 &deg;F (Channel 11) and trip setpoints of 192.0 &deg;F (Channels 5 and 9), 108.5 &deg;F (Channels 7 and 11) to allow for instrument and test equipment inaccuracies. 1. Channels 5, 7, 9 and 1 I will initiate following, if thermocouple is disconnected or monitored differential temperature rises above alarm setpoint: Level of Use Continuous " Panel 1H13-P601 annunciator "RCIC PIPE RTE EQUIP AREA TEMP HI" (D507) 2. Channels 5, 7, 9 and 1 I will initiate following, if thermocouple is disconnected or monitored differential temperature rises above trip setpoint: " Isolation signal to 1E51-F008, RCIC STEAM SUPPLY OUTBOARD ISOLATION VALVE " Panel 1H13-P601 annunciator "DIV 1 RCIC EQUIP AREA DIFF/AMB TEMP HI" (D411) PLANT E QUIPMENT/FUNCTIONS AFFECTED BY TEST 1. Trip/Initiations None. "DIV I RCIC LD ISOL BYPASS" switch (1E31A-S2A) on panel IH13-P632 will be in "TEST" position throughout testing. 56 of 57 LIS-RI-103A Revision 10 March 19, 2006 
: 2. Loss of Operability ATTACHMENT C (Continued)
 
===2.1 Following===
 
Division 1 instrumentation will be inoperable during performance of surveillance section specified: Level of Use Continuous " RCIC Equipment Room High Ambient Temperature (1E31-ROOK, Channel 5) during Section E.2. " RCIC Equipment Room High Differential Temperature (1E31-ROOIC, Channels 6 and 7) during Section E.3. " RCIC Steam Line Tunnel High Ambient Temperature (I E31-ROO I C, Channel 9) during Section E.4. " RCIC Steam Line Tunnel High Differential Temperature (1E31-ROOIC, Channels 10 and 11) during Section E.5. 2.2 Following Division 1 RCIC isolations will be bypassed throughout procedure because "DIV I RCIC LD ISOL BYPASS" switch (1E31A-S2A) on panel IH13-P632 will be in "TEST" position: " RCIC Equipment Room Temperature - High " RCIC Equipment Room Differential Temperature - High " RCIC Steam Line Tunnel Temperature - High " RCIC Steam Line Tunnel Differential Temperature - High 2.3 Refer to Tech Spec 3.3.6.1 for Timeclock/Operability requirements in current Mode. 3. Control Room Annunciators Actuated 3.1 At panel 1 H 13-P601: " C309, "DIV 1 LD LOGIC PWR FAILURE/IN TEST" " D411, "DIV 1 RCIC EQUIP AREA DIFF/AMB TEMP HI" " D507, "RCIC PIPE RTE EQUIP AREA TEMP HI" 4. Control Room Indicatin g Lights Actuated None 5. Process Computer Alarms Actuated None 57 of 57 LIS-RI-103A Revision 10 March 19, 2006 ATTACHMENT 2f LaSalle County Station Instrument Maintenance Surveillance Procedure LIS-RI-10313, Revision 10 "Unit 1 RCIC Equipment Room/Steam Line Tunnel High Ambient and Differential Temperature Inboard Isolation (DIV 2) Calibration" UNIT 1 RCIC EQUIPMENT ROOM/STEAM LINE TUNNEL HIGH AMBIENT AND DIFFERENTIAL TEMPERATURE INBOARD ISOLATION (DIV 2) CALIBRATION LIS-RI-103B Revision 10 March 19, 2006 Level of Use Continuous LaSalle Station UNIT I INSTRUMENT MAINTENANCE SURVEILL ANCE I of 54 TABLE OF CONTENTS ATTACHMENTS A Equipment And Materials List...............................................................................50 B Yokogawa (Model DX102) Recorder Figure ........................................................52 C Surveillance/Plant Interface Information
...............................................................53 A. PURPOSE............................................................................................................................3 B. PRERE QUISITES ...............................................................................................................4 C. PRECAUTIONS
..................................................................................................................4 D. LIMITATIONS
....................................................................................................................5
 
==E. PROCEDURE==
 
E. l General Preparations
................................................................................................7 E.2 RCIC Equipment Room High Ambient Temperature (1E31-R002C, Channel 5) Calibration
..................................................................10 E.3 RCIC Equipment Room High Differential Temperature (l E3I-R002C, Channels 6 and 7) Calibration
.......................................................17 E.4 RCIC Steam Line Tunnel High Ambient Temperature (1E31-R002C, Channel 9) Calibration
..................................................................29 E.5 RCIC Steam Line Tunnel High Differential Temperature (1E31-R002C, Channels 10 and 11) Calibration
...................................................35 E.6 Test Close Out........................................................................................................47 F. REVIEW AND SIGNOFF.................................................................................................48 G. REFERENCES
..................................................................................................................49 UNIT 1 RCIC EQUIPMENT ROOM/STEAM LINE TUNNEL HIGH AMBIENT AND DIFFERENTIAL TEMPERATURE INBOARD ISOLATION (DIV 2) CALIBRATION A. PURPOSE A.1 Objective A.2 Discussion Level of Use Continuous This surveillance provides instructions for test and calibration of RCIC Equipment Room/Steam Line High Ambient and Differential Temperature trips in Inboard Isolation (DIV 2) Logic. This surveillance will verify calibration and operability of following equipment: Coil of relay 1 E31 A-KO02B This surveillance satisfies Channel Calibration and Functional Test requirements of Tech Spec SR 3.3.6.1.2 and SR 3.3.6.1.4 (Table 3.3.6.1-1, Function 3.e, 31, 3.g and 3.h) for instrument channel tested. This surveillance partially satisfies Logic System Functional Test (LSFT) requirements of Tech Spec 3.3.6.1.5 for instrument channels tested that contribute to combined logic. For Sections E.2 and E.4: Burnout protection for recorder channel is verified. Thermocouple resistance values measured and compared with previous resistance values. Calibrator is used to simulate temperature input to recorder. Setpoint, reset point, and indication are measured and documented. All related channel alarm and trip functions are verified. Recorder channel being tested, including trips and alarms, is reset and returned to service prior to reperforming this process for next recorder channel. For Sections E.3 and E.5: Inlet temperature burnout protection for recorder Differential channel temperature is verified. Inlet thermocouple resistance values measured and compared with previous resistance values. Calibrator is used to simulate temperature input to recorder and indication is measured and documented. Calibrator is set to simulate Inlet (reference) temperature. Outlet temperature burnout protection for recorder Differential channel temperature is verified. Outlet thermocouple 3 of 54 LIS-RI-103B Revision 10 March 19, 2006 1E31-N004B 1E31-R002C, Channel 5 IE31-NO05B 1E31-NO06B 1E31-R002C, Channels 6 and 7 1E31-NO24B 1E31-R002C, Channel 9 1E31-NO25B IE31-NO26B IE31-R002C, Channels 10 and I I A.3 Applicability C. PRECAUTIONS Level of Use Continuous resistance values measured and compared with previous resistance values. Calibrator is used to simulate Outlet temperature inputs to recorder Differential temperature channel. Setpoint, reset point, and indication are measured and documented. All related channel alarm and trip functions are verified. Recorder Differential channel being tested, including trips and alarms, is reset and returned to service prior to reperforming this process for next recorder channels. This surveillance may be performed in any Mode. PREREQUISITES B.1 Equipment and materials listed on Attachment A available. B.2 Plant conditions are such that keylock switch "DIV II RCIC LD ISOL BYPASS" (1E31A-S2B) on panel 1H13-P642 can be placed in "TEST" position. B.3 For Section E.2, plant conditions are such that keylock switch "DIV 11 RCIC LD ISOL BYPASS" (1E31A-S2B) on panel 1H13-P642 can be placed in "NORM" position. C.1 Due to thermocouple burnout protection, When Ambient thermocouples are disconnected, recorder channel being tested will go upscale. " When Inlet thermocouples are disconnected, recorder Inlet temperature channel being tested will go downscale, causing corresponding Differential temperature channel to go upscale. When Outlet thermocouples are disconnected, recorder Differential temperature channel being tested will go upscale. C.2 Recorder 1E31-R002C channels initiate both RCIC and MSIV isolation logic, if thermocouple lead is inadvertently lifted on a channel not being tested, an undesired half MSIV Isolation may occur. 4 of 54 LIS-RI-103B Revision 10 March 19, 2006 LIMITATIONS D.1 Acceptance Criteria NOTES Letters TS and LSFT are used to designate steps and data related to Technical Specification requirements. If recalibration is required, then acceptance criteria applies to As Left data. Otherwise acceptance criteria applies to As Found data. D.1.1 Instrument calibration data marked with letters TS shall be within stated Calibration Limits. (Tech Spec SR 3.3.6.1.4, Table 3.3.6.1-1, Function 3.e, 3.f, 3.g and 3.h) D.1.2 Trip, alarm and indication functions marked with letters TS or LSFT shall perform as stated. (Tech Spec SR 3.3.6.1.2 and SR 3.3.6.1.5) D.2 Generic D.2.1 Surveillance steps which cannot be completed as stated shall be brought to immediate attention of IM Supervisor and documented on cover sheet. D.2.2 Attachment C information is intended as an aid to Operations and Maintenance personnel and should NOT solely be used to direct or evaluate the use of this surveillance. D.2.3 If, after consultation with IM Supervisor, it is determined that acceptance criteria cannot be met, then these items shall be brought to the immediate attention of Shift Manager or Unit Supervisor. D.2.4 If work (Section E only) is to be stopped for more than 2 hours, then approval of Shift Manager is required per LIP-GM-902. D.2.5 Unit NSO shall be notified when work is stopped or restarted. D.2.6 Direct communications between test locations shall be maintained during active portions of this test. Level of Use Continuous 5 of 54 LIS-RI-103B Revision 10 March 19, 2006 D.3 Specific D.3.1 This surveillance's instructions take precedence. However, they may be supplemented by manufacturer's instructions at discretion of IM Supervisor to provide clarification as needed. D.3.2 Revisions to this surveillance may result in possible required changes to associated LSFT(s) since testing goes beyond end of channels. Level of Use Continuous 6 of 54 LIS-RI-103B Revision 10 March 19, 2006 
 
==E. PROCEDURE==
 
E. I General Preparations NOTE Previous thermocouple resistance readings may not be available for the referenced procedure. In this case, readings from equivalent procedure(s) should be used. E.1.1 From most recent copy of test results from LIS-RI-10313 or equivalent procedure, OBTAIN "As Found Thermocouple Resistance" for following thermocouples and RECORD as "Previous Thermocouple Resistance" where indicated: Level of Use Continuous 7 of 54 LIS-RI-10313 Revision 10 March 19, 2006 [ ] " For 1E31-N004B, in Data Table 1 in Section E.2. [ ] " For 1E31-NO05B and IE3I-N006B, in Data Tables 3 and 5 respectively in Section E.3. [ ] " For IE31-N024B, in Data Table 7 in Section E.4. [ ] " For 1E31-NO25B and 1E31-N026B, in Data Tables 9 and 11 respectively in Section E.5. NOTES Step E.1.4 may be performed in parallel with Steps E.1.2 and E.1.3. Reviews may be expedited by having copies of Attachment C available for distribution to Operations personnel. If desired, Attachment C may be removed from this surveillance and given to Operations personnel. E.1.2 REQUEST Unit Supervisor to PERFORM following: [ ] E.1.2.1 REVIEW details of surveillance's interface with plant provided on Attachment C. [ ] E.1.2.2 VERIFY that performance of this surveillance is compatible with current plant conditions, including other tests and maintenance in progress.
Level of Use Continuous 8 of 54 LIS-RI-103B Revision 10 March 19, 2006 [ ] E.1.2.3 VERIFY timeclock is recorded on cover sheet, or N/A as appropriate, for performance of this surveillance. E.1.2.4 AUTHORIZE start of surveillance. Time Unit Supervisor
/ E.1.3 REQUEST Unit NSO to PERFORM following: [ ] E.1.3.1 REVIEW details of surveillance's interface with plant provided on Attachment C and timeclock recorded on cover sheet. E.1.3.2 AUTHORIZE start of surveillance. Time NSO / [ ] E.1.4 OBTAIN equipment and materials listed on Attachment A and RECORD test equipment calibration data where required. NOTE Sound powered phone communications as follows: 1H13-P601
... SP13 1H13-P642
... SP11 [ ] E.1.5 VERIFY direct communications are available between test locations. [ ] E.1.6 REVIEW timeclock limits recorded on cover sheet and precautions listed in Section C.
NOTE The following step will ensure the associated functions maintain isolation capability as required by Tech Spec 3.3.6.1 Surveillance Requirements Note 2. Level of Use Continuous 9 of 54 LIS-RI-10313 Revision 10 March 19, 2006 E.1.7 VERIFY, by checking with Unit Supervisor, that the following Div 1 instrument channels are operable or are NOT required to be operable: [ ] " RCIC Equipment Area High Ambient Temperature Isolation
[ ] " RCIC Equipment Area High Differential Temperature Isolation
[ ] " RCIC Pipe Tunnel High Ambient Temperature Isolation
[ ] " RCIC Pipe Tunnel High Differential Temperature Isolation At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. E.1.9 Have any timeclocks been specified (circle Yes or No below)? Yes - NOTIFY Unit NSO that any applicable timeclocks for following RCIC Isolations must be started for Div 2: RCIC Equipment Room Temperature - High " RCIC Equipment Room Differential Temperature - High " RCIC Steam Line Tunnel Temperature - High " RCIC Steam Line Tunnel Differential Temperature - High No - PROCEED with following steps. [ ] E.1.10 REQUEST Unit NSO to VERIFY "DIV II RCIC LD ISOL BYPASS" switch (1E31A-S2B) on panel IH13-P642 in "TEST" position. [ ] E.1.11 At panel 1H13-P601, CHECK annunciator "DIV 2 LD LOGIC PWR FAILURE/IN TEST" (13504) is initiated.
Level of Use Continuous 10 of 54 LIS-RI-103 B Revision 10 March 19, 2006 E.2 RCIC Equipment Room High Ambient Temperature (1E31-R002C Channel 5) Calibration
[ ] E.2.1 NOTIFY Unit NSO that testing of RCIC Equipment Room High Ambient Temperature is starting. B3 T3 M3 R3 R1 M1 T1 B1 Y---RELAY BASE PLUG-IN RELAY B4 T4 M4 R4 R2 M2 T2 B2 FIGURE I Agastat Relay Base E.2.2 At panel 1 H 13-P642, PERFORM following: [ ] E.2.2.1 CONNECT VOM #1, set to measure 125 Vdc, to terminal AA-78 (+) and terminal T1 (-) of relay 1E31A-KO02B (device CS). (refer to Figure 1) (1 E-1-4226AF, 1 E-1-4629AC)
[ ] E.2.2.2 CONNECT VOM #2, set to measure 125 Vdc, to terminal Tl (+) of relay 1E31A-KO02B (device CS) and terminal AA-79 (-). (refer to Figure 1) (1E-1-4226AF, 1E-1-4629AC)
[ ] E.2.2.3 REQUEST Unit NSO to VERIFY keylock switch "DIV II RCIC LD ISOL BYPASS" (1E31A-S213) in "NORM" position. " CHECK VOM #1 indicates approximately 0 Vdc. LSFT " CHECK VOM #2 indicates approximately 125 Vdc. LSFT [ ] " CHECK annunciator "DIV 2 LD LOGIC PWR FAILURE/IN TEST" (13504) is reset on panel 1H13-P601. 
[ ] E.2.2.4 REQUEST Unit NSO to VERIFY keylock switch "DIV II RCIC LD ISOL BYPASS" (IE31A-S2B) in "TEST" position. LEFT LSFT Level of Use Continuous " CHECK VOM #1 indicates approximately 65 Vdc. " CHECK VOM #2 indicates approximately 65 Vdc. " CHECK annunciator "DIV 2 LD LOGIC PWR FAILURE/IN TEST" (B504) is initiated on panel IH13-P601. NOTE Recorder 1E31-R002C, "DIV 2 LD-RCIC/MSL TEMP RCDR", is located on panel IH13-P642. [ ] E.2.3 At 1E31-R002C, VERIFY Channel 5 (RCIC AMBIENT TMP - RCIC EQP ROOM) is displayed. [ ] E.2.4 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Ambient thermocouple, causing indication to "peg" upscale. E.2.5 At IE31-R002C, LIFT following leads: (refer to Attachment B) (IE-1-4224AG, 1E-1-4629AB) 11 of 54 LIS-RI-103B Revision 10 March 19, 2006 " Purple wire (+) from Channel 5 terminal +/A. LL Tag/Label
/ " Red wire (-) from Channel 5 terminal -/B. LL Tag/Label
/
E.2.8.5 Is "Thermocouple Resistance Difference" in Data Table 1 less than 20 ohms (circle Yes or No below)? [ ] E.2.8.6 At panel 1H13-P642, MOVE DMM lead from lifted red (-) thermocouple wire to terminal CC-17 (ground). (1E-1-4629AC)
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. 12 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 1 THERMOCOUPLE 1 E31-N004B RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Init ials: Performed by Verified by E.2.6 At 1E31-R002C, CHECK Channel 5 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). [ ] E.2.7 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is initiated. E.2.8 PERFORM Thermocouple 1E31-N004B resistance check as follows: [ ] E.2.8.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 5 of 1E31-R002C. [ ] E.2.8.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 1. [ ] E.2.8.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 1 and RECORD value for "Thermocouple Resistance Difference" in Data Table 1, then INITIAL for "Performed by" in Data Table 1. [ ] E.2.8.4 REQUEST Verifier to CHECK calculations in Data Table 1, then INITIAL for "Verified by" in Data Table 1.
E.2.8.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Level of Use Continuous 13 of 54 LIS-RI-103B Revision 10 March 19, 2006 No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.2.8.8 DISCONNECT DMM. E.2.9 OBTAIN As Found data for Channel 5 of 1E31-R002C as follows: E.2.9.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.2.9.2 SETUP Calibrator
#1 as follows: [ ] E.2.9.2.1 SELECT "SOURCE" mode: [ ] E.2.9.2.2 SELECT Function "TC" [ ] E.2.9.2.3 SELECT TC Type "E", then ENTER. [ ] E.2.9.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.2.9.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.2.9.3 At IE3I-R002C, CONNECT Calibrator
#1 (with Type E thermocouple wire) to Channel 5 terminals
+/A (purple lead) and -/B (red lead). [ ] E.2.9.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.2.9.5 At IE31-R002C, CHECK all Alarm marks for Channel 5 are green. [ ] E.2.9.6 At panel I H 13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset.
NOTE Steps E.2.9.8 and E.2.9.9 must be performed in conjunction with Step E.2.9.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.2.9.7 APPLY test inputs listed in Data Table 2 and RECORD As Found values. Level of Use Continuous 14 of 54 LIS-RI-103 B Revision 10 March 19, 2006 DATA TABLE 2 1E31-R002C, CHANNEL 5 (RCIC EQP ROOM) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) 50.0 1E31-RO02C of N/A 50.0 48.0 to 52.0 Channel 5 100.0 IE31-RO02C of N/A 100.0 98.0 to 102.0 Channe15 150.0 IE31-R002C of N/A 150.0 148.0 to 152.0 Channel 5 TRIP Calibrator
#1 &deg;F _< 291.0 192.0 190.0 to 194.0 Setpoint 200.0 1 E31-RO02C N/A 198.0 202.0 Channel 5 of 200.0 to 250.0 IE31-RO02C o f N/A 250.0 248.0 to 252.0 Channel 5 200.0 1E31-RO02C of N/A 200.0 198.0 to 202.0 Channel 5 TRIP Calibrator
#1 &deg;F N/A N/A N/A Reset Point I 150.0 1E31-RO02C of N/A 150.0 148.0 to 152.0 Channel 5 100.0 IE31-RO02C of N/A 100.0 98.0 to 102.0 Channel 5 50.0 IE31-RO02C of N/A 50.0 48.0 to 52.0 Channel 5 Performed by (Initials)
: As Foun d As Left Level of Use Continuous 15 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.2.9.8 When Alarm 1 and 2 marks for Channel 5 turn red on increasing test signal, then: [] " RECORD Calibrator
#1 reading in As Found Trip Setpoint block of Data Table 2. " At panel 1H13-P642, CHECK VOM #1 indicates approximately LSFT 125 Vdc. " At panel IH13-P642, CHECK VOM #2 indicates approximately LSFT 0 Vdc. " At panel IH13-P601, CHECK annunciator "DIV 2 RCIC EQUIP TS AREA DIFF AMB TEMP HI" (E401) is initiated. E.2.9.9 When Alarm 1 and 2 marks for Channel 5 turn green on decreasing test signal, then: [ ] RECORD Calibrator
#1 reading in As Found Trip Reset Point block of Data Table 2. At panel 1 H 13-P642, CHECK VOM # 1 indicates approximately LSFT 65 Vdc. " At panel 1H13-P642, CHECK VOM #2 indicates approximately LSFT 65 Vdc. [ ] " At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. E.2.10 Is As Found data in Data Table 2 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.2.11. No - PROCEED with following steps. [ ] E.2.10.1 CIRCLE As Found data in Data Table 2 which is outside Calibration Limits. [ ] E.2.10.2 CONTACT IM Supervisor for further instructions. [ ] E.2.10.3 RECORD As Left data on Data Table 2.
Level of Use Continuous No - CONTACT IM Supervisor for further instructions. 16 of 54 Yes - NOTIFY Unit NSO that testing of RCIC Equipment Room High Ambient Temperature is completed. LIS-RI-103B Revision 10 March 19, 2006 E.2.11 At panel 1H13-P642, RESTORE Channel 5 of 1E31-RO02C as follows: [ ] E.2.11.1 VERIFY input terminal cover is removed on back of recorder. E.2.11.2 DISCONNECT following test equipment: [ ] " VOM #1 and VOM #2. [ ] " Calibrator
#1. E.2.11.3 At 1E31-RO02C, LAND following leads: " Red wire (-) to Channel 5 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 5 terminal +/A. LL Tag/Label
/ [ ] E.2.11.4 At 1E31-RO02C, CHECK Channel 5 digital display indication is restored and all Alarm marks for Channel 5 are green. [ ] E.2.12 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. E.2.13 Is Channel 5 indication on 1E31-RO02C at panel 1H13-P642 within _+ 5.5 &deg;F of Channel 5 indication on 1E31-ROOIC at panel 1H13-P632 (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. Yes - PROCEED with following steps. E.2.14 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)?
E.3 RCIC Equipment Room High Differential Temperature (1E31-R002C, Channels 6 and 7) Calibration
[ ] E.3.1 NOTIFY Unit NSO that testing of RCIC Equipment Room High Differential Temperature is starting. NOTE Recorder 1E31-R002C, "DIV 2 LD-RCIC/MSL TEMP RCDR", is located on panel 1H13-P642. [ ] E.3.2 At 1E31-R002C, VERIFY Channel 6 (RCIC AMBIENT TMP - RCIC EQP RM IN) is displayed. [ ] E.3.3 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Inlet thermocouple, causing indication to "peg" downscale. E.3.4 At 1E31-R002C, LIFT following leads: (refer to Attachment B) (1E-1-4224AG, 1E-1-4629AB)
E.3.5 At 1E31-R002C, CHECK Channel 6 indication is driven downscale and digital display indicates
-* * * * * (burnout protection). [ ] E.3.6 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is initiated. Level of Use Continuous " Purple wire (+) from Channel 6 terminal +/A. LL Tag/Label " Red wire (-) from Channel 6 terminal -/B. LL Tag/Label / 17 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.3.7.5 Is "Thermocouple Resistance Difference" in Data Table 3 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.7.6 At panel 1H13-P642, MOVE DMM lead from lifted red (-) thermocouple wire to terminal CC-17 (ground). (IE-1-4629AC)
E.3.7.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.7.8 DISCONNECT DMM. Level of Use Continuous 18 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 3 THERMOCOUPLE IE31-N005B RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Performed by Verified by E.3.7 PERFORM Thermocouple 1E31-NO05B resistance check as follows: [ ] E.3.7.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 6 of IE3I-R002C. [ ] E.3.7.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 3. [ ] E.3.7.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 3 and RECORD value for "Thermocouple Resistance Difference" in Data Table 3, then INITIAL for "Performed by" in Data Table 3. [ ] E.3.7.4 REQUEST Verifier to CHECK calculations in Data Table 3, then INITIAL for "Verified by" in Data Table 3.
Level of Use Continuous 19 of 54 LIS-RI-103 B Revision 10 March 19, 2006 E.3.8 OBTAIN As Found data for Channel 6 of 1E31-R002C as follows: E.3.8.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.3.8.2 SETUP Calibrator
#1 as follows: [ ] E.3.8.2.1 SELECT "SOURCE" mode: [ ] E.3.8.2.2 SELECT Function "TC" [ ] E.3.8.2.3 SELECT TC Type "E", then ENTER. [ ] E.3.8.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.3.8.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.3.8.3 At 1E31-R002C, CONNECT Calibrator
#1 (with Type E thermocouple wire) to Channel 6 terminals
+/A (purple lead) and -/B (red lead). [ ] E.3.8.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.3.8.5 APPLY test inputs listed in Data Table 4 and RECORD As Found values.
E.3.9 Is As Found data in Data Table 4 within Calibration Limits (circle Yes or No below)? Level of Use Continuous 20 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 4 1E31-R002C, CHANNEL 6 (RCIC EQP RM IN) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) 50.0 IE31-RO02C of N/A 50.0 48.0 to 52.0 Channel 6 100.0 I E31-RO02C of N/A 100.0 98.0 to 102.0 Channel 6 150.0 1E31-RO02C OF N/A 150.0 148.0 to 152.0 Channel 6 200.0 IE31-RO02C of N/A 200.0 198.0 to 202.0 Channel6 250.0 1E31-RO02C of N/A 250.0 248.0 to 252.0 Channel 6 200.0 1E31-RO02C of N/A 200.0 198.0 to 202.0 Channel 6 150.0 1E31-RO02C of N/A 150.0 148.0 to 152.0 Channel 6 100.0 IE31-RO02C o f N/A 100.0 98.0 to 102.0 Channel 6 50.0 IE31-RO02C of N/A 50.0 48.0 to 52.0 Channel 6 Performed by (Initials)
: As Found As Left Yes - GO TO Step E.3.10. No - PROCEED with following steps. [ ] E.3.9.1 CIRCLE As Found data in Data Table 4 which is outside Calibration Limits. [ ] E.3.9.2 CONTACT IM Supervisor for further instructions. [ ] E.3.9.3 RECORD As Left data on Data Table 4. 
[ ] E.3.10 At IE31-R002C, SET Calibrator
#1 to apply test input of 100 &deg;F for Channel 6 Inlet (reference) temperature. " If necessary, RAISE Calibrator
#1 test input setting until annunciator (E401) is reset on panel 1HI3-P601. [ ] E.3.11 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. [ ] E.3.12 At 1E31-R002C, VERIFY Channel 7 (RCIC DIFF TEMP - RCIC EQP RM dT) is displayed. [ ] E.3.13 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Outlet thermocouple, causing indication to "peg" upscale. E.3.14 At IE31-R002C, LIFT following leads: (refer to Attachment B) (1E-1-4224AG, 1E-1-4629AB)
Level of Use Continuous " Purple wire (+) from Channel 7 terminal +/A. LL Tag/Label " Red wire (-) from Channel 7 terminal -/B. LL Tag/Label / E.3.15 At IE3I-R002C, CHECK Channel 7 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). [ ] E.3.16 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is initiated. 21 of 54 LIS-RI-103B Revision 10 March 19, 2006 Calculations
: Initials: Level of Use Continuous DATA TABLE 5 THERMOCOUPLE IE31-NO06B RESISTANCE CHECK Performed by Verified by E.3.17.5 Is "Thermocouple Resistance Difference" in Data Table 5 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.17.6 At panel 1H13-P642, MOVE DMM lead from lifted red (-) thermocouple wire to terminal CC-17 (ground). (1 E-1-4629AC)
E.3.17.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.3.17.8 DISCONNECT DMM. 22 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.3.17 PERFORM Thermocouple 1E31-N006B resistance check as follows: [ ] E.3.17.1 CONNECT DMM, set to measure ohms, to purple (f) and red (-) leads lifted from Channel 7 of 1E31-R002C. [ ] E.3.17.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 5. [ ] E.3.17.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 5 and RECORD value for "Thermocouple Resistance Difference" in Data Table 5, then INITIAL for "Performed by" in Data Table 5. [ ] E.3.17.4 REQUEST Verifier to CHECK calculations in Data Table 5, then INITIAL for "Verified by" in Data Table 5. AS FOUND THERMOCOUPLE RESISTANCE I OHMS PREVIOUS THERMOCOUPLE RESISTANCE ( OHMS THERMOCOUPLE RESISTANCE DIFFERENCE I OHMS Level of Use Continuous 23 of 54 LIS-RI-103B Revision 10 March 19, 2006 [ ] E.3.18 At 1E31-R002C, VERIFY Calibrator
#1 set to apply test input of 100 &deg;F for Channel 6 Inlet (reference) temperature. " MONITOR and MAINTAIN Channel 6 inlet (reference) temperature at 100 &deg;F during calibration of Channel 7. E.3.19 OBTAIN As Found data for Channel 7 of 1E31-R002C as follows: E.3.19.1 VERIFY following in Calibrator
#2 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.3.19.2 SETUP Calibrator
#2 as follows: [ ] E.3.19.2.1 SELECT "SOURCE" mode: [ ] E.3.19.2.2 SELECT Function "TC" [ ] E.3.19.2.3 SELECT TC Type "E", then ENTER. [ ] E.3.19.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.3.19.2.5 SET Calibrator
#2 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.3.19.3 At 1E31-R002C, CONNECT Calibrator
#2 (with Type E thermocouple wire) to Channel 7 terminals
+/A (purple lead) and -/B (red lead). [ ] E.3.19.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.3.19.5 At 1E31-R002C, CHECK all Alarm marks for Channel 7 are green. [ ] E.3.19.6 At panel 1 H 13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset.
NOTE Steps E.3.19.8 and E.3.19.9 must be performed in conjunction with Step E.3.19.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.3.19.7 APPLY test inputs listed in Data Table 6 and RECORD As Found values. Level of Use Continuous 24 of 54 LIS-RI-103B Revision 10 March 19, 2006 Level of Use Continuous 25 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 6 1E31-R002C, CHANNEL 7 (RCIC EQP RM dT) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) (a) 50.0 IE31-R002C of N/A -50.0 -52.0 to -48.0 Channel 7 100.0 IE31-RO02C of N/A 0.0 -2.0 to +2.0 Channel 7 150.0 1 E31-RO02C OF N/A 50.0 48.0 to 52.0 Channe17 200.0 I E31-RO02C of N/A 100.0 98.0 to 102.0 Channel 7 TRIP Calibrator
#2 &deg;F <_ 289.0 I 208.5 I 206.5 to 210.5 Setpoint (b) (e) (&deg;) 250.0 1E31-RO02C of N/A 150.0 148.0 to 152.0 Channel 7 TRIP Calibrator
#2 &deg;F N/A N/A N/A Reset Point 200.0 IE31-RO02C of N/A 100.0 98.0 to 102.0 Channe17 150.0 IE31-RO02C of N/A 50.0 48.0 to 52.0 Channe17 100.0 1E31-RO02C of N/A 0.0 -2.0 to +2.0 Channel 7 50.0 I E31-RO02C of N/A -50.0 -52.0 to -48.0 Channel 7 (a) Test Inputs based upon Inlet (Reference) temperature of 100 &deg;F. (b) Based on LCO allowable value <+ Ref. <_ 289.0 &deg;F _ 189.0 &deg;F 100 &deg;F temp. (Calibrator
#1) (c) Based on nominal trip setpoint of 108.5 &deg;F + 100 &deg;F Ref. temp. (Calibrator
#1) = 208.5 &deg;F Performed by (Initials)
: As Found As Left Ts E.3.19.8 When Alarm 1 and 2 marks for Channel 7 turn red on increasing test signal, then: Level of Use Continuous 26 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.3.19.9 When Alarm 1 and 2 marks for Channel 7 turn green on decreasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Trip Reset Point block of Data Table 6. [ ] " At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) is reset. E.3.20 Is As Found data in Data Table 6 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.3.21. No - PROCEED with following steps. [ ] E.3.20.1 CIRCLE As Found data in Data Table 6 which is outside Calibration Limits. [ ] E.3.20.2 CONTACT IM Supervisor for further instructions. [ ] E.3.20.3 RECORD As Left data on Data Table 6. E.3.21 At panel 1H13-P642, RESTORE Channels 6 and 7 of 1E31-R002C as follows: [ ] E.3.21.1 VERIFY input terminal cover is removed on back of recorder. [ ] E.3.21.2 DISCONNECT Calibrator
#1 and Calibrator
#2. ] " RECORD Calibrator
#2 reading in As Found Trip Setpoint block of Data Table 6. " At panel 1 H 13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) is initiated.
Level of Use Continuous 27 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.3.21.3 At 1E31-R002C, LAND following leads: " Red wire (-) to Channel 6 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 6 terminal +/A. LL Tag/Label
/ [ J E.3.21.4 At IE31-R002C, VERIFY Channel 6 digital display indication is restored. E.3.21.5 At 1E31-R002C, LAND following leads: " Red wire (-) to Channel 7 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 7 terminal +/A. LL Tag/Label
/ [ ] E.3.21.6 At 1E31-R002C, VERIFY Channel 7 digital display indication is restored and all Alarm marks for Channel 7 are green. [ ] E.3.22 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset.
E.3.23 Is Channel 7 indication on 1 E31-RO02C at panel 1 H 13-P642 within _+ 7.5 &deg;F of Channel 7 indication on 1E31-ROOK at panel 1H13-P632 (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. E.3.24 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)? Level of Use Continuous Yes - PROCEED with following steps. No - CONTACT IM Supervisor for further instructions. Yes - NOTIFY Unit NSO that testing of RCIC Equipment Room High Differential Temperature is completed. 28 of 54 LIS-RI-103 B Revision 10 March 19, 2006 E.4 RCIC Steam Line Tunnel High Ambient Temperature (1E31-R002C, Channel 9) Calibration
[ ] E.4.1 NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Ambient Temperature is starting. NOTE Recorder 1 E31-R002C, "DIV 2 LD-RCIC/MSL TEMP RCDR", is located on panel 1H 13-P642. [ ] E.4.2 At 1E31-R002C, VERIFY Channel 9 (RCIC AMBIENT TMP - RCIC STM LN TNL) is displayed. [ ] E.4.3 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Ambient thermocouple, causing indication to "peg" upscale. E.4.4 At 1E31-R002C, LIFT following leads: (terminals located on left side, refer to Attachment B) (1 E-1-4224AF, 1 E- I -4629AB) E.4.5 At 1E31-R002C, CHECK Channel 9 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). [ ] E.4.6 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is initiated. Level of Use Continuous 29 of 54 LIS-RI-103B Revision 10 March 19, 2006 Purple wire (+) from Channel 9 terminal +/A. LL Tag/Label
/ Red wire (-) from Channel 9 terminal -B. LL Tag/Label
/
E.4.7.5 Is "Thermocouple Resistance Difference" in Data Table 7 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.4.7.6 At panel 1H13-P642, MOVE DMM lead from lifted red (-) thermocouple wire to terminal CC-17 (ground). (1E-1-4629AC)
E.4.7.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.4.7.8 DISCONNECT DMM. Level of Use Continuous 30 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 7 THERMOCOUPLE lE31-N024B RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Calculations
: Initials: Performed by Verified by E.4.7 PERFORM Thermocouple 1E31-N024B resistance check as follows: [ ] E.4.7.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 9 of 1E31-R002C. [ ] E.4.7.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 7. [ ] E.4.7.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 7 and RECORD value for "Thermocouple Resistance Difference" in Data Table 7, then INITIAL for "Performed by" in Data Table 7. [ ] E.4.7.4 REQUEST Verifier to CHECK calculations in Data Table 7, then INITIAL for "Verified by" in Data Table 7.
E.4.8 OBTAIN As Found data for Channel 9 of 1E31-R002C as follows: E.4.8.1 VERIFY following in Calibrator
#1 "SETUP" mode: " Ref. June. Compensat.: Internal Temperature Units: &deg;F " Temperature Scale: ITS-90 E.4.8.2 SETUP Calibrator
#1 as follows: E.4.8.2.1 SELECT "SOURCE" mode: E.4.8.2.2 SELECT Function "TC" E.4.8.2.3 SELECT TC Type "E", then ENTER. E.4.8.2.4 SELECT TC Source Mode "Linear T" then ENTER. E.4.8.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.4.8.3 At 1E31-R002C, CONNECT Calibrator
#1 (with Type E thermocouple wire) to Channel 9 terminals
+/A (purple lead) and -/B (red lead). E.4.8.4 VERIFY input terminal cover is installed on back of recorder. E.4.8.5 At 1E31-R002C, CHECK all Alarm marks for Channel 9 are green. E.4.8.6 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. NOTE Steps E.4.8.8 and E.4.8.9 must be performed in conjunction with Step E.4.8.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.4.8.7 APPLY test inputs listed in Data Table 8 and RECORD As Found values. Level of Use Continuous 31 of 54 LIS-RI-103B Revision 10 March 19, 2006 Level of Use Continuous 32 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 8 1 E3 I-R002C, CHANNEL 9 (RCIC STM LN TNL) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT &deg;F) 50.0 1 E31-RO02C o f N/A 50.0 48.0 to 52.0 Channel 9 100.0 1E31-RO02C of N/A 100.0 98.0 to 102.0 Channel 9 150.0 1 E31-RO02C o f N/A 150.0 148.0 to 152.0 Channel 9 TRIP Calibrator
#1 &deg;F < 267.0 192.0 190.0 to 194.0 Setpoint (a) 200.0 I E31-RO02C of N/A 200.0 198.0 to 202.0 Channe 1 9 250.0 1E31-RO02C of N/A 250.0 248.0 to 252.0 Channel 9 200.0 1 E31-RO02C of N/A 200.0 198.0 to 202.0 Channel 9 TRIP Calibrator
#1 &deg;F N/A N/A N/A Reset Point 150.0 IE31-RO02C of N/A 150.0 148.0 to 152.0 Channel 9 100.0 1E31-RO02C of N/A 100.0 98.0 to 102.0 Channel 9 50.0 IE31-RO02C of N/A 50.0 48.0 to 52.0 Channel 9 (a) Allowable Value per Operability Evaluation OE 05-003 Performed by (Initials)
: As Found As Left E.4.8.8 When Alarm 1 and 2 marks for Channel 9 turn red on increasing test signal, then: Level of Use Continuous RECORD Calibrator
#1 reading in As Found Trip Setpoint block of Data Table 8. 33 of 54 LIS-RI-103B Revision 10 March 19, 2006 Ts E.4.8.9 " At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) is initiated. When Alarm 1 and 2 marks for Channel 9 turn green on decreasing test signal, then: [ ] " RECORD Calibrator
# 1 reading in As Found Trip Reset Point block of Data Table 8. [ ] " At panel 1 H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) is reset. E.4.9 Is As Found data in Data Table 8 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.4.10. No - PROCEED with following steps. [ ] E.4.9.1 CIRCLE As Found data in Data Table 8 which is outside Calibration Limits. [ ] E.4.9.2 CONTACT IM Supervisor for further instructions. [ ] E.4.9.3 RECORD As Left data on Data Table 8. E.4.10 At panel 1H13-P642, RESTORE Channel 9 of 1E31-R002C as follows: [ ] E.4.10.1 VERIFY input terminal cover is removed on back of recorder. [ ] E.4.10.2 DISCONNECT Calibrator
#1.
E.4.10.3 At 1 E31-R002C, LAND following leads: " Red wire (-) to Channel 9 terminal -/B. Level of Use Continuous LL Tag/Label " Purple wire (+) to Channel 9 terminal +/A. Yes - PROCEED with following steps. E.4.13 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. 34 of 54 LL Tag/Label / [ ] E.4.10.4 At IE31-R002C, CHECK Channel 9 digital display indication is restored and all Alarm marks for Channel 9 are green. [ ] E.4.11 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. E.4.12 Is Channel 9 indication on 1E31-R002C at panel 1H13-P642 plus 10.0 &deg;F within _+ 5.5 &deg;F of Channel 9 indication on 1 E31-R001 C at panel 1H13-P632 (circle Yes or No below)? - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. Yes - NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Ambient Temperature is completed. LIS-RI-103B Revision 10 March 19, 2006 E.5 RCIC Steam Line Tunnel High Differential Temperature (1E31-R002C, Channels 10 and 11) Calibration
[ ] E.5.1 NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Differential Temperature is starting. NOTE Recorder 1E31-R002C, "DIV 2 LD-RCIC/MSL TEMP RCDR", is located on panel 1 H13-P642. [ ] E.5.2 At 1E31-R002C, VERIFY Channel 10 (RCIC AMBIENT TMP - RCIC STM TNL IN) is displayed. [ ] E.5.3 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Inlet thermocouple, causing indication to "peg" downscale. E.5.4 At 1E31-R002C, LIFT following leads: (terminals located on left side, refer to Attachment B) (1E-1-4224AF, 1E-1-4629AB)
E.5.5 At 1E31-R002C, CHECK Channel 10 indication is driven downscale and digital display indicates
-* * * * * (burnout protection). [ ] E.5.6 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is initiated. Level of Use Continuous " Purple wire (+) from Channel 10 terminal +/A. LL Tag/Label " Red wire (-) from Channel 10 terminal -/B. LL Tag/Label / 35 of 54 LIS-RI-10313 Revision 10 March 19, 2006 DATA TABLE 9 THERMOCOUPLE 1E31-NO25B RESISTANCE CHECK Calculations
: Initials: Performed by Verified by E.5.7.5 Is "Thermocouple Resistance Difference" in Data Table 9 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.5.7.6 At panel 1H13-P642, MOVE DMM lead from lifted red (-) thermocouple wire to terminal CC-17 (ground). (1 E-1-4629AC)
E.5.7.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.5.7.8 DISCONNECT DMM. Level of Use Continuous 36 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.5.7 PERFORM Thermocouple 1E31-N025B resistance check as follows: [ ] E.5.7.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 10 of 1E31-R002C. [ ] E.5.7.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 9. [ ] E.5.7.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table 9 and RECORD value for "Thermocouple Resistance Difference" in Data Table 9, then INITIAL for "Performed by" in Data Table 9. [ ] E.5.7.4 REQUEST Verifier to CHECK calculations in Data Table 9, then INITIAL for "Verified by" in Data Table 9. AS FOUND THERMOCOUPLE RESISTANCE I OHMS PREVIOUS THERMOCOUPLE RESISTANCE OHMS THERMOCOUPLE RESISTANCE DIFFERENCE OHMS Level of Use Continuous 37 of 54 LIS-RI- 103B Revision 10 March 19, 2006 E.5.8 OBTAIN As Found data for Channel 10 of IE31-R002C as follows: E.5.8.1 VERIFY following in Calibrator
#1 "SETUP" mode: [ ] " Ref. Junc. Compensat.: Internal " Temperature Units: &deg;F [ ] " Temperature Scale: ITS-90 E.5.8.2 SETUP Calibrator
#1 as follows: [ ] E.5.8.2.1 SELECT "SOURCE" mode: [ ] E.5.8.2.2 SELECT Function "TC" [ ] E.5.8.2.3 SELECT TC Type "E", then ENTER. [ ] E.5.8.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.5.8.2.5 SET Calibrator
#1 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.5.8.3 At IE3I-R002C, CONNECT Calibrator
#I (with Type E thermocouple wire) to Channel 10 terminals
+/A (purple lead) and -/B (red lead). [ ] E.5.8.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.5.8.5 APPLY test inputs listed in Data Table 10 and RECORD As Found values.
E.5.9 Is As Found data in Data Table 10 within Calibration Limits (circle Yes or No below)? Level of Use Continuous 38 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 10 1E31-R002C, CHANNEL 10 (RCIC STM TNL IN) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (OF) 50.0 IE31-RO02C of N/A 50.0 48.0 to 52.0 Channel 10 100.0 1E31-RO02C of N/A 100.0 98.0 to 102.0 Channel 10 150.0 1E31-RO02C of N/A 150.0 148.0 to 152.0 Channel 10 200.0 I E31-RO02C of N/A 200.0 198.0 to 202.0 Channel 10 250.0 IE31-RO02C of N/A 250.0 248.0 to 252.0 Channel 10 200.0 1E31-RO02C of N/A 200.0 198.0 to 202.0 Channel 10 150.0 1E31-R002C o f N/A 150.0 148.0 to 152.0 Channel 10 100.0 1E31-RO02C o f N/A 100.0 98.0 to 102.0 Channel 10 50.0 I E31-RO02C o f N/A 50.0 48.0 to 52.0 Channel 10 Performed by (Initials)
: As Found As Left Yes - GO TO Step E.5.10. No - PROCEED with following steps. [ ] E.5.9.1 CIRCLE As Found data in Data Table 10 which is outside Calibration Limits. [ ] E.5.9.2 CONTACT IM Supervisor for further instructions. [ ] E.5.9.3 RECORD As Left data on Data Table 10. 
[ ] E.5.10 At IE3I-R002C, SET Calibrator
#1 to apply test input of 100 &deg;F for Channel 10 Inlet (reference) temperature. [ ] E.5.11 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. [ ] E.5.12 At 1E31-R002C, VERIFY Channel I1 (RCIC DIFF TEMP - RCIC STM TNL dT) is displayed. [ ] E.5.13 VERIFY input terminal cover is removed on back of recorder. NOTES Channel Input Terminals on back of recorder are numbered from Right to Left. Lifted leads will disconnect Outlet thermocouple, causing indication to "peg" upscale. E.5.14 At 1E31-R002C, LIFT following leads: (terminals located on left side, refer to Attachment B) (IE-1-4224AF, lE-I-4629AB)
Level of Use Continuous " If necessary, RAISE Calibrator
#1 test input setting until annunciator (E401) is reset on panel 1 H 13-P601. 39 of 54 E.5.15 At 1E31-R002C, CHECK Channel 11 indication is driven upscale and digital display indicates
+* * * * * (burnout protection). [ ] E.5.16 At panel IH13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is initiated. LIS-RI-103B Revision 10 March 19, 2006 Purple wire (+) from Channel 11 terminal +/A. LL Tag/Label
/ Red wire (-) from Channel 11 terminal -/B. LL Tag/Label
/
DATA TABLE 11 THERMOCOUPLE 1E31-N026B RESISTANCE CHECK AS FOUND THERMOCOUPLE RESISTANCE E.5.17.5 Is "Thermocouple Resistance Difference" in Data Table 11 less than 20 ohms (circle Yes or No below)? No - CONTACT IM Supervisor for further instructions. Yes - PROCEED with following steps. [ ] E.5.17.6 At panel 1H13-P642, MOVE DMM lead from lifted red (-) thermocouple wire to terminal CC-17 (ground). (1E-1-4629AC)
E.5.17.7 Is thermocouple to ground resistance reading approximately infinite ohms (circle Yes or No below)? Yes - PROCEED with following steps. [ ] E.5.17.8 DISCONNECT DMM. Level of Use Continuous No - CONTACT IM Supervisor for further instructions. 40 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.5.17 PERFORM Thermocouple 1E31-N026B resistance check as follows: [ ] E.5.17.1 CONNECT DMM, set to measure ohms, to purple (+) and red (-) leads lifted from Channel 11 of 1 E31-R002C. [ ] E.5.17.2 RECORD DMM indication for "As Found Thermocouple Resistance" in Data Table 11. [ ] E.5.17.3 CALCULATE difference between As Found and Previous Thermocouple Resistances in Data Table I 1 and RECORD value for "Thermocouple Resistance Difference" in Data Table 11, then INITIAL for "Performed by" in Data Table 11. [ ] E.5.17.4 REQUEST Verifier to CHECK calculations in Data Table 11, then INITIAL for "Verified by" in Data Table 11.
Level of Use Continuous 41 of 54 LIS-RI-103B Revision 10 March 19, 2006 [ ] E.5.18 At 1E31-R002C, VERIFY Calibrator
#1 set to apply test input of 100 &deg;F for Channel 10 Inlet (reference) temperature. " MONITOR and MAINTAIN Channel 10 inlet (reference) temperature at 100 &deg;F during calibration of Channel 11. E.5.19 OBTAIN As Found data for Channel 11 of 1E31-R002C as follows: E.5.19.1 VERIFY following in Calibrator
#2 "SETUP" mode: [ ] " Ref. June. Compensat.: Internal [ ] " Temperature Units: &deg;F [] " Temperature Scale: ITS-90 E.5.19.2 SETUP Calibrator
#2 as follows: [ ] E.5.19.2.1 SELECT "SOURCE" mode: [ ] E.5.19.2.2 SELECT Function "TC" [ ] E.5.19.2.3 SELECT TC Type "E", then ENTER. [ ] E.5.19.2.4 SELECT TC Source Mode "Linear T" then ENTER. [ ] E.5.19.2.5 SET Calibrator
#2 to test input of 50 &deg;F, by depressing "5" and "0", then ENTER. [ ] E.5.19.3 At 1E31-R002C, CONNECT Calibrator
#2 (with Type E thermocouple wire) to Channel 11 terminals
+/A (purple lead) and -/B (red lead). [ ] E.5.19.4 VERIFY input terminal cover is installed on back of recorder. [ ] E.5.19.5 At 1E31-R002C, CHECK all Alarm marks for Channel 11 are green. [ ] E.5.19.6 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset.
NOTE Steps E.5.19.8 and E.5.19.9 must be performed in conjunction with Step E.5.19.7. Channe l digital indication is recorded on increasing inputs until Alarm mark turns red, then setpoint data is recorded. Reset point data similarly recorded when Alarm mark turns green on decreasing inputs. [ ] E.5.19.7 APPLY test inputs listed in Data Table 12 and RECORD As Found values. Level of Use Continuous 42 of 54 LIS-RI-103B Revision 10 March 19, 2006 Level of Use Continuous 43 of 54 LIS-RI-103B Revision 10 March 19, 2006 DATA TABLE 12 1E31-R002C, CHANNEL 11 (RCIC STM TNL dT) CALIBRATION DATA TEST READING UNITS ALLOWABLE DESIRED CALIBRATION AS AS INPUT FROM VALUE (LCO) VALUE LIMITS FOUND LEFT (&deg;F) (a) 50.0 1E31-ROO2C of N/A -50.0 -52.0 to -48.0 Channel 11 100.0 IE31-RO02C of N/A 0.0 -2.0 to +2.0 Channel 11 150.0 1E31-RO02C of N/A 50.0 48.0 to 52.0 Channel l l 200.0 IE31-RO02C of N/A 100.0 98.0 to 102.0 Channel l l TRIP Calibrator
#2 &deg;F _< 255.0 208.5 206.5 to 210.5 Setpoint (b) (c) (c) m 250.0 1E31-ROO2C of N/A 150.0 148.0 to 152.0 Channel 11 TRIP Calibrator
#2 &deg;F I N/A I N/A N/A Rese t Point 200.0 1 E31-ROO2C o f N/A 100.0 98.0 to 102.0 Channel 11 150.0 1E31-RO02C of N/A 50.0 48.0 to 52.0 Channel l l 100.0 IE31-RO02C of N/A 0.0 -2.0 to +2.0 Channel I 1 50.0 OO2C of N/A -50.0 -52.0 to -48.0 Chann Channel 11 (a) Test Inputs based upon Inlet (Reference) temperature of 100 &deg;F. (b) Based on LCO allowable value <_ 155.0 &deg;F + 100 &deg;F Ref. temp. (Calibrator
#1) < 255.0 &deg;F (c) Based on nominal trip setpoint of 108.5 &deg;F + 100 &deg;F Ref. temp. (Calibrator
#1) = 208.5 &deg;F Performed by (Initials)
: As Found As Left Ts E.5.19.8 When Alarm I and 2 marks for Channel 11 turn red on increasing test Level of Use Continuous signal, then: 44 of 54 LIS-RI-103B Revision 10 March 19, 2006 E.5.19.9 When Alarm 1 and 2 marks for Channel 11 turn green on decreasing test signal, then: [ ] " RECORD Calibrator
#2 reading in As Found Trip Reset Point block of Data Table 12. [ ] " At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) is reset. E.5.20 Is As Found data in Data Table 12 within Calibration Limits (circle Yes or No below)? Yes - GO TO Step E.5.21. No - PROCEED with following steps. [ ] E.5.20.1 CIRCLE As Found data in Data Table 12 which is outside Calibration Limits. [ ] E.5.20.2 CONTACT IM Supervisor for further instructions. [ ] E.5.20.3 RECORD As Left data on Data Table 12. E.5.21 At panel 1H13-P642, RESTORE Channels 10 and 11 of 1E31-R002C as follows: [ ] E.5.21.1 VERIFY input terminal cover is removed on back of recorder. [ ] E.5.21.2 DISCONNECT Calibrator
#1 and Calibrator
#2. ] " RECORD Calibrator
#2 reading in As Found Trip Setpoint block of Data Table 12. " At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) is initiated.
E.5.21.3 At 1E31-R002C, LAND following leads: " Red wire (-) to Channel 10 terminal -/B. LL Tag/Label / [ ] E.5.21.4 At IE31-R002C, VERIFY Channel 10 digital display indication is restored. E.5.21.5 At 1E31-R002C, LAND following leads: Level of Use Continuous LL Tag/Label " Purple wire (+) to Channel 10 terminal +/A. Red wire (-) to Channel 11 terminal -/B. LL Tag/Label " Purple wire (+) to Channel 11 terminal +/A. [ ] E.5.21.6 At 1E31-R002C, VERIFY Channel 11 digital display indication is restored and all Alarm marks for Channel 11 are green. 45 of 54 LL Tag/Label / [ ] E.5.22 At panel 1H13-P601, CHECK annunciator "DIV 2 RCIC EQUIP AREA DIFF AMB TEMP HI" (E401) is reset. LIS-RI-103B Revision 10 March 19, 2006 E.5.23 Is Channel 11 indication on 1 E31-RO02C at panel 1 H13-P642 within _+ 7.5 &deg;F of Channel 11 indication on IE31-ROOK at panel 1H13-P632 (circle Yes or No below)? E.5.24 Has Acceptance Criteria, specified in Section D.1, been met (circle Yes or No below)? Level of Use Continuous No - CONTACT IM Supervisor for further instructions or N/A, if not within specified limits due to plant conditions. Yes - PROCEED with following steps. No - CONTACT IM Supervisor for further instructions. Yes - NOTIFY Unit NSO that testing of RCIC Steam Line Tunnel High Differential Temperature is completed. 46 of 54 LIS-RI-103B Revision 10 March 19, 2006 Level of Use Continuous 47 of 54 LIS-RI-10313 Revision 10 March 19, 2006 E.6 Test Close Out [ ] E.6.1 At panel 1H13-P642, VERIFY input terminal cover is installed on back of recorder IE31-R002C. E.6.2 Does Unit Supervisor require panel 1H13-P642 switch "DIV II RCIC LD ISOL BYPASS" (1E31A-S2B) to remain in "TEST position (circle Yes or No below)? No - REQUEST Unit NSO to VERIFY panel 1H13-P642 switch "DIV II RCIC LD ISOL BYPASS" (1E31A-S2B) is in "NORM" position. Yes - Unit Supervisor DOCUMENT reason for switch remaining in "TEST" position in Comments section of cover sheet. E.6.3 Is panel 1H13-P642 switch "DIV II RCIC LD ISOL BYPASS" (1E31A-S2B) in "NORM" position (circle Yes or No below)? Yes - CHECK panel 1H13-P601 annunciator "DIV 2 LD LOGIC PWR FAILURE/1N TEST" (13504) is reset or N/A, if keylock switch "DIV II RWCU LD ISOL BYPASS" (1E31A-SIB) on panel 1H13-P642 is in "TEST" position. PROCEED with following steps. E.6.4 NOTIFY Unit NSO that: [ ] E.6.4.1 Surveillance has been completed. [ ] E.6.4.2 Any timeclock that may be in affect for performance of this surveillance may be stopped. [ ] E.6.5 NOTIFY Unit Supervisor that surveillance has been completed. [ ] E.6.6 VERIFY all personnel whose initials appear in this surveillance have completed Section F. [ ] E.6.7 DELIVER completed surveillance to IM Supervisor for final review and processing.
F. REVIEW AND SIGNOFF Performed by: (When indirect signoff used, signature indicates concurrence with use of initials)
Name (Print) Initials I Signature Comments: Level of Use Continuous (Attach additional pages if necessary) 48 of 54 LIS-RI-1035 Revision 10 March 19, 2006 G. REFERENCES Level of Use Continuous " 3.3.6.1, Primary Containment Isolation Instrumentation " Table 3.3.6.1-1 " SR 3.3.6.1.2, SR 3.3.6.1.4 and SR 3.3.1.5 49 of 54 LIS-RI-103B Revision 10 March 19, 2006 G. I Schematic Diagrams: " 1E-1-4224AA, AD, AF, AG, and AM 9 IE-1-4226AF 0 1E-1-4232AH G.2 Wiring Diagrams: " lE-I-4629AA, AB, AC, and AD G.3 Vendor Manual No. J-0949.000, "Yokogawa DAQStation DX100 Series and DX 200 Series" G.4 LIP-GM-902, General Requirements for Performance of Instrument Maintenance Department Procedures G.5 DCP 9700532, Unit 1 RWCU Leak Detection Modification G.6 SEAG 00-000444, ITS/24 Month Procedure Setpoint Data G.7 EC 51553, Replace Riley Temperature Switches G.8 EC 348527, Determination of Bias in Channel Checks for Leak Detection Temperature System - Unit 1 G.9 Calculation NED-I-EIC-0213, RCIC Equipment Area/Pipe Tunnel High Ambient & Differential Temperature Outboard & Inboard Isolation Error Analysis G.10 Operability Evaluation OE 05-003, RCIC Steam Line Tunnel Ambient Temperature - High G. I 1 Technical Specification references
:
Test Equipment Following equipment is required for normal performance of surveillance
: 1. DMM (HP 34401 A) ID Number Cal. Due 2. Honeywell 2020 System Calibrator
#1 with Type E thermocouple wire ID Number Cal. Due 3. Honeywell 2020 System Calibrator
#2 with Type E thermocouple wire NOTE VOMs may not be substituted by equivalent equipment and must be of the same model/manufacturer. 3. VOMs - 2 required (not used for analytical measurements)
: 4. Test leads: Level of Use Continuous ATTACHMENT A EQUIPMENT AND MATERIALS LIST ID Number Cal. Due " Banana to alligator - 2 required " Banana to banana - 4 required. (stackable)
: 5. Lifted Lead Tags Labels - 4 required (N/A, if labeling is used) 6. Key #5, "DIV II RCIC LD ISOL BYPASS" (IE31A-S2B) on panel IH13-P642
* Equivalent equipment (i.e., performing same function and covering similar range with equal or better accuracy) may be used in place of equipment listed. 50 of 54 LIS-RI-103B Revision 10 March 19, 2006 Consumables Tools None ATTACHMENT A (continued)
Following is a recommended tool list. Additions, deletion, and substitutions may be made at discretion of IM Technician. 1. Screwdriver - Phillips 2. Screwdriver - Holding (Phillips or Flat Blade) 3. Screwdriver - 6" Flat Blade 4. Sound Powered Phones - 2 required Level of Use Continuous 51 of 54 LIS-RI-103B Revision 10 March 19, 2006 Level of Use Continuous ATTACHMENT B YOKOGAWA (MODEL DX102) RECORDER FIGURE (rear view) 52 of 54 _ Alarm/Relay Terminal -Input Terminal LIS-RI-103B Revision 10 March 19, 2006 EQUIP MENT FUNCTION Recorder channels calibrated and functionally tested by this surveillance provide isolation signal to 1E51-17063 and 1E51-17076 for RCIC Equipment Room and Steam Line High Ambient and Differential Temperature on Division 2. Channels 5 and 9 of temperature recorder 1E31-R002C monitor ambient temperature of RCIC Equipment Room and Steam Line respectively. Channels 6 and 10 of temperature recorder 1E31-R002C monitor inlet (reference) temperature of RCIC Equipment Room and Steam Line respectively. Channels 7 and 11 of temperature recorder 1E31-R002C monitor differential between outlet and inlet (reference) temperature of RCIC Equipment Room and Steam Line respectively. Channels are calibrated to actual trip setpoints of 192.0 &deg;F (Channels 5 and 9) and 108.5 &deg;F (Channels 7 and 11) to allow for instrument and test equipment inaccuracies. 1. Channels 5, 7, 9 and 11 will initiate following, if thermocouple is disconnected or monitored differential temperature rises above trip setpoint: PLA NT EQUIPMENT/FUNCTIONS AFFECTED BY TEST 1. Trip/Initiations Level of Use Continuous ATTACHMENT C SURVEILLANCE/PLANT INTERFACE INFORMATION " Isolation signal to 1E51-17063, RCIC STEAM SUPPLY INBOARD ISOLATION VALVE " Isolation signal to 1E51-17076, RCIC STEAM SUPPLY INBOARD ISOLATION VALVE WARM UP BYPASS VALVE " Panel 1H13-P601 annunciator "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" (E401) None. "DIV II RCIC LD ISOL BYPASS" switch (1E31A-S2B) on panel 1H13-P642 will be in "TEST" position throughout testing. 53 of 54 LIS-RI-103 B Revision 10 March 19, 2006 
: 2. Loss of Operability ATTACHMENT C (continued)
 
===2.1 Following===
 
Division 2 instrumentation will be inoperable during performance of surveillance section specified: Level of Use Continuous " RCIC Equipment Room High Ambient Temperature (1E31-R002C, Channel 5) during Section E.2. " RCIC Equipment Room High Differential Temperature (1E31-R002C, Channels 6 and 7) during Section E.3. " RCIC Steam Line Tunnel High Ambient Temperature (IE31-R002C, Channel 9) during Section E.4. " RCIC Steam Line Tunnel High Differential Temperature (1E31-R002C, Channels 10 and 11) during Section E.5. 2.2 Following Division 2 RCIC isolations will be bypassed throughout procedure because "DIV II RCIC LD ISOL BYPASS" switch (1E31A-S2B) on panel 1H13-P642 will be in "TEST" position: " RCIC Equipment Room Temperature - High " RCIC Equipment Room Differential Temperature - High " RCIC Steam Line Tunnel Temperature - High " RCIC Steam Line Tunnel Differential Temperature - High 2.3 Refer to Tech Spec 3.3.6.1 for Timeclock/Operability requirements in current Mode. 3. Control Room Annunciators Actuated 3.1 At panel IH13-P601: " B504, "DIV 2 LD LOGIC PWR FAILURE/IN TEST" " E401, "DIV 2 RCIC EQUIP AREA DIFF/AMB TEMP HI" 4. Control Room Indicatin g Lijzhts Actuated None 5. Process Computer Alarms Actuated None 54 of 54 LIS-RI-103 B Revision 10 March 19, 2006}}

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