ML102730398

Calculation C11116, Revision 0, Kewaunee Unit 1 Steam Generator Narrow Range Level Protection Channel Statistical Allowance (Csa) Calculation

ML102730398
Person / Time
Site:	Kewaunee
Issue date:	09/07/2010
From:	Baugus A Dominion Energy Kewaunee
To:	Office of Nuclear Reactor Regulation
References
10-527, TAC ME2139 C11116, Rev 0
Download: ML102730398 (49)

Text

{{#Wiki_filter:KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION USE DOCUMENT INFORMATION 6.2.1.1 Document Type Calculation / Evaluation 6.2.1.2 Document ID C11116 6.2.1.3 Document Title Kewaunee Unit 1 Steam Generator Narrow Range Level Protection Channel Statistical Allowance (CSA) Calculation. 6.2.1.4 KPS Revision 0 6.2.1.5 Addendum N/A 6.2.1.6 Document Date 10/14/2009 6.2.1.7 Topic Development of the Steam Generator Narrow Range Level High Level Turbine Trip and Feedwater Isolation, Low Level Coincidence with Steam Flow Feed Flow Mismatch Reactor Trip, and the Low Low Level Reactor Trip Channel Statistical Allowances (CSA) to support Kewaunee's conversion to Improved Technical Specifications (ITS) 6.2.1.8 Document Status Current 6.2.1.9 Superceded By N/A 6.2.1.10 Attachments Y 6.2.1.11 Safety Related Y AUTHOR INFORMATION 6.2.2.1 Author/Submitter AW Baugus 6.2.2.2 Vendor N/A 6.2.2.3 Vendor Author N/A 6.2.2.4 Discipline Instrument and Control DOCUMENT RELATIONSHIPS 6.2.3.1 System(s) 05A-975 6.2.3.2 DCR(s) N/A 6.2.3.3 Keyword(s) CALC INDEX 6.2.3.4 Inputs 6.2.3.5 Outputs ADMIN/RECORDS USE ONLY 6.2.4.1 Comments 6.2.4.2 Record Type 6.2.4.3 Retention Period 6.2.4.4 Software Application 6.2.4.5 Vault Location 6.2.4.6 Film Reel 6.2.4.7 Reel Odometer

Calculation Cover Sheet Station: Kewaunee - KPS Calculation Number: C11116 Unit(s): 1 Revision: 0 System Code(s): DSA (Feedwater) Addendum: N/A Calculation Quality Class:' Safety Related 0 Non-Safety Related Status: Current Installation Verification Required: ~ Yes 0 No Keyword(s): CSA, Steam Generator Narrow Range Level Supersedes: C11116-1, Rev. OJ C11116-2, Rev. 1, C11116-3JRev. 1, C11116-4, Rev. 0, C11116-1 0, Rev. 1. SUbject (Calculation Title): Kewaunee Unit 1 Steam Generator Narrow Range Level Protection Channel Statistical Allowance (CSA) Calculation. Initiating Document: Kewaunee Improved Technical Specifications (ITS) CM-AA-CLC-301, Revision: 1 Station: Unit: System: Equipment Location (Mark Number): Tag Number (If Applicable): KPS 1 D5A 24042 LT-461 KPS 1 05A 24043 LT-462 KPS 1 GSA 24044 LT-463 KPS 1 GSA 24046. LT-471 Objective: The objective of this calculation is to determine the Channel Statistical Allowance (CSA) value(s) associated with Kewaunee's Unit 1 Steam Generator Hi Level Turbine Trip and Feedwater Isolation J Low Level Coincidence with Steam Flow/Feed Flow Mismatch Reactor Trip, the Low-Low Reactor Trip functions and the AMSAC Low-Low Level Trip. This calculation supports Kewaunee's conversion to Improved Technical Specifications (ITS). Reviewer (Print): D.M.McGrath Originator (Print): A. W. Baugus

== Conclusion:== The Channel Statistical Allowance (GSA) values associated with the Steam Generator Narrow Range Level Trips are: CSA-NORMAL(Low Level Coincidence) CSA-NORMAL(LOw Low Level RX Trip) CSA-NORMAL(AMSAC Low Low Level TUrb/AX Trip) CSA-NORMAL Hi Level Turb Tri I FW Isol Owners Review (Print): Victor Myers Approval (Print): B. R. Morrison (1) This Is the revision of CM-AA..CLC-301 and CM..AA-CLC-301-1 001 in effect at the time the calculation was Initiated.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 2 of 23 Affected Components (Cont.): Station: KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS Unit: 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 System: 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 05A 047 05A 047 05A 047 05A 047 Equipment Location (Mark Number): 24047 24048 4848601 4848401 4845801 4848301 4848101 4848201 4848602 4848402 4845803 4848302 4848102 4848202 4848403 4845802 4848103 4848203 4848404 4809808 4845804 4809808 4848104 4809807 4848204 4809807 Tag Number (If Applicable): LT-472 LT-473 LQ-461 LQ-462 LQ-463 LQ-471 LQ-472 LQ-473 LC-461A/B LC-462A/B LC-463C/D LC-471A/B LC-472A/B LC-473C/D LC-462C LC-463E LC-472C LC-473E LM-462 LC-462G LM-463B LC-463G LM-472 LC-472G LM-473B LC-473G

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 3 of 23 TABLE OF CONTENTS SECTION DESCRIPTION PAGE Calculation Cover Sheet 1 Table of Contents 3 Attachments 3 Record of Revision 3 1.0 Purpose 4 2.0 Method of Analysis 4 3.0 Design Inputs 5 4.0 Assumptions 6 5.0 References 7 6.0 Computer Codes 9 7.0 Functional Block Diagram 10 8.0 Calculation 12 9.0 Conclusion 23 ATTACHMENTS SG Narrow Range Level, PMA Calculation 50.59 Applicability Review 50.59 Pre-Screening RECORD OF REVISION Rev. 0 Original Issue. This calculation replaces Calculations C11116-1, Rev. 0, C11116-2, Rev. 1, C11116-3, Rev. 1, C11116-4, Rev. 0, and C11116-10, Rev. 1. This calculation is written as a Channel Statistical Allowance (CSA) Calculation versus a Setpoint Calculation.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 4 of 23 1.0 PURPOSE The purpose of this calculation is to determine the Channel Statistical Allowance (CSA) values associated with the Steam Generator Narrow Range Level Loops. The functions addressed in this calculation are the Steam Generator Low Level Coincident Reactor Trip, Steam Generator Hi Level Turbine Trip and Feedwater (FW) isolation, Steam Generator Lo-Lo Level Reactor Trip and ESFAS Initiation, and the AMSAC Low-Low Level Trip. The applicable instrumentation loops are L-461, L-462, L-463, L-471, L-472, and L-473. The loops are similar; therefore the CSA values presented in this calculation will be applicable for all of the loops. 2.0 METHOD OF ANALYSIS This calculation uses the methodology presented in STD-EEN-0304, Revision 6, Calculating Instrumentation Uncertainties by the Square Root of the Sum of the Squares Method (Reference 5.1). The CSA determined in this calculation is a derivation of the following generic equation presented in STD-EEN-0304, Revision 6, Section 6.1: CSA = SE +/- [EA² + PMA² + PEA² + (SCA + SMTE)² + SD² + SPE² + STE² + SPSE2 + (M1 + M1MTE)² + (M2 + M2MTE)² +...+ (Mn + MnMTE)² + RD² + RTE² + RRA²] (Equation 1) The terms M1 through Mn refer to individual rack modules within the Steam Generator Narrow Range Level Loops. The term MnMTE refers to the Module Measuring and Test Equipment where n is the module number as shown on the Functional Block Diagram in Section 7.0. Finally, the EA term will be removed from the equation for normal conditions since there is no environmental allowance for non-harsh conditions. These changes result in the following equation. For normal conditions: CSA = SE +/- [PMA² + PEA² + (SCA + SMTE)² + SD² + SPE² + STE² + SPSE2 + (M1 + M1MTE)² + (M2 + M2MTE)² +...+ (Mn + MnMTE)² + RD² + RTE² + RRA²] (Equation 2) The error terms in the equations above are consistent with standard industry definitions and are described in Section 8.0 and in detail in Reference 5.1. 2.1 Process Measurement Accuracy (PMA) Terms The Process Measurement Accuracy Terms used in this calculation are extracted from Calculation C11116-5, Rev. 0, Attachment 4 (Ref 5.19). Because they are applied deterministically as process measurement bias to the Channel Statistical Allowance, no additional uncertainty is added to these biases. For conservatism, the PMA is ignored when evaluating low or low-low level trips when the resultant CSA is a net positive (i.e. Actual level is

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 5 of 23 higher than indicated level), correspondingly the PMA is ignored when evaluating high level trips when the resultant CSA is a net negative (i.e. Actual level is lower than indicated level). The PMA terms from Attachment 1 include downcomer affects, mid deck plate affects, and Fluid Velocity effects at the lower tap. The reference leg temperature effect was determined at 95°F and per Reference 5.18, page 17 the maximum temperature could be 120°F and the minimum temperature could be 40°F. The reference leg temperature variation for 120°F and 40°F was determined in Reference 5.21 to be +0.74% of span and - 0.83% of span. Table 2-1 Function MDP + TH (1) % span Reference Leg Temperature Error (2) % span Total PMA % span Low Level 25.5% Level Setpoint - 1.8291%(3) - 0.83% - 2.659 Low Low Level 17% Level Setpoint - 1.6875%(4) - 0.83% - 2.518 AMSAC Low Low Level 13% Level Setpoint -1.5781%(5) -0.83% -2.408 Hi Hi Level 66.5% Level Setpoint + 5.2050 %(6) + 0.74% + 5.945 (1) MDP + TH is the combination of the mid deck plate and thermal & hydraulic errors as shown on, SG Narrow Range Level, PMA Calculation. (2) Reference Leg Temperature Error is derived from Calculation CN-SSO-02-8, Rev. 1, page 17. The values above are for the two temperature extremes of 40°F and 120°F. (3) The value for the Low Level Setpoint @ 25.5% is the bounding value between the Hi Tave 0% TP, Lo Setpoint 25.5% value and the Low Tave, 10% TP Lo Setpoint 25.5% value (Ref. pg 17 of 23 of ). (4) The value for the Low Low Level Setpoint @ 17.0% is the bounding value between the Hi Tave 0% TP, Lo-Lo Setpoint 17.0% value and the Low Tave, 10% TP Lo-Lo Setpoint 17.0% value (Ref. pg 11 of 23 of Attachment 1). (5) The value for the AMSAC Low Low Level Setpoint @ 13.0% is the bounding value between the Hi Tave 0% TP, Lo-Lo Setpoint 13.0% value and the Low Tave, 10% TP Lo-Lo Setpoint 13.0% value (Ref. pg 11 of 23 of Attachment 1). (6) The value for the Hi Hi Level Setpoint @ 66.5% is the bounding value between the Hi Tave 0% TP, Hi-Hi Setpoint 66.5% value and the Low Tave, 10% TP Hi-Hi Setpoint 66.5% value (Ref. pg 7 of 23 of ). 3.0 DESIGN INPUTS The design inputs are manufacturer's published data sheets, active (current) calculations, station controlled drawings and other controlled documents as listed in Section 5.0, References.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 6 of 23 4.0 ASSUMPTIONS 4.1 The Environmental Allowance (EA) term is assumed to be zero for Normal (non-accident) conditions. This term includes the effects due to degradation of cable insulation (IR) and the effects of high temperatures and radiation during an accident. The Steam Pressure/Temperature Effect (SPTE) has also been assumed to exist only during exposure to the temperature pressure profile. 4.2 Based on Reference 5.15, all test data is referenced to the rack 10 Test Point Resistor (TPR), therefore the errors associated with the installed DB Box resistors used to convert the loop current to an applied input voltage to the Foxboro or NUS module under test is included in the overall error of the Foxboro or NUS module as referenced to the rack TPR. 4.3 According to References 5.14 and 5.15, a Fluke 45 Digital Multimeter (DMM) is used to perform the transmitter and rack module calibration. According to Reference 5.13, the DC Voltage accuracies for the ranges of interest are as follows: Range Desired Acceptance Range 300 mV 300 mV 299.92 to 300.08 mV 3 V 3 V 2.9992 to 3.0008 V 30 V 30 V 29.992 to 30.008 V Range Desired Acceptance Range 1000 mV 900 mV 899.76 to 900.24 10 V 9 V 8.9976 to 9.0024 At Kewaunee, there are six possible voltage spans that could be present in the Reactor Protection System; i.e., 40 to 200 mVDC, 100 to 500 mVDC, 1 to 5 VDC, 0.4 to 12.4 VDC, 2 to 10 VDC, and 0 to 10 VDC. The DC voltage accuracies converted to % of span are given below. 100 to 500 mVDC (1000 mV range) accuracy = (0.24 mVDC / 400 mVDC)

• 100% = 0.06% of span 0.4 to 12.4 VDC (30 V range) accuracy = (0.008 VDC / 12 VDC)
• 100% = 0.07% of span 2 to 10 VDC (30 V range) accuracy = (0.008 VDC / 8 VDC)
• 100% = 0.10% of span 0 to 10 VDC (30 V range) accuracy = (0.008 VDC / 10 VDC)
• 100% = 0.08% of span

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 7 of 23 40 to 200 mVDC (300 mVDC range) accuracy = (0.08 mVDC / 160 mVDC)

• 100% = 0.05% of span 1 to 5 VDC (10 V range) accuracy = (0.0024 VDC / 4 VDC)
• 100% = 0.06% of span This calculation will be bounded using an accuracy of + 0.1% of span for the Fluke 45 DMM for all possible conditions for ranges 30 VDC or less. It is acceptable for the calibration procedures to use a DMM with accuracy specifications equal to or better than the Fluke 45 DMM.

4.4 For this calculation, when terms are treated as a bias or the net CSA is made up of two values, then a net (+) means that the actual process is higher than the indicated value and a net (-) means that the actual process is lower than the indicated value.

5.0 REFERENCES

5.1 Dominion

Standard, STD-EEN-0304, Revision 6,

Calculating Instrumentation Uncertainties by the Square Root of the Sum of the Squares Method. 5.2 Kewaunee Updated Safety Analysis Report (USAR), Chapters 7, 10, and 14. 5.3 Kewaunee Technical Specifications, Section 2.3.a.5, Table TS 3.5-2, Table TS 3.5-3, and Table TS 3.5-4. 5.4 Kewaunee Vendor Technical Manual KW-VTM-000-FOXBO-0031 (100-1762-1), Revision 15, Nuclear Energy Systems - Instrumentation Reference Manual. 5.5 Kewaunee Vendor Technical Manual KW-VTM-000-FOXBO-0015 (100-1744-1), Revision 10, Instrumentation Documentation. 5.6 Kewaunee Vendor Technical Manual KW-VTM-000-NUSIN-0017 (240730), Revision 2, NUS Instruments Series SPS500 Power Supply. 5.7 Kewaunee Vendor Technical Manual KW-VTM-000-NUSIN-0022 (C-N-430-9), Revision 4, SAM504-3 Single & DAM504-3 Dual Alarm Module IOM. 5.8 Kewaunee Vendor Technical Manual KW-VTM-000-ROSEM-0006 (2566-1), Rosemount Instruction Manual, Rosemount 1154 Alphaline Nuclear Pressure Transmitter, Product Manual 00809-0100-4514, Rev. AA, June 1999. 5.9 Kewaunee Instrument and Control Procedure ICP-82B-137, Revision 6, ICE - Precision Test Resistor Calibration. 5.10 Kewaunee General Instrument Procedure GIP-007, Revision E, Protection Loop mV Data Collection.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 8 of 23 5.11 Kewaunee Instrument and Control Procedure ICP-82B-168, Revision 3, ICE - Heise PTE-1 Calibrator and HQS-2 Pressure Module Calibration. 5.12 Kewaunee Instrument and Control Procedure ICP-82B-06, Revision T, ICE - Pressure Gauge Calibration. 5.13 Kewaunee Instrument and Control Procedure ICP-82B-129, Revision 10, ICE - Fluke 45 Dual Display Multimeters Calibration. 5.14 Instrument Surveillance Procedure MA-KW-ISP-FW-028A, Rev. 0, Steam Generator Level Transmitters Calibration. 5.15 Instrument Surveillance Procedures: SP-05A-028B-1, Rev. B, Steam Generator Level Instrument Channel 461 (Red) Calibration. SP-05A-028B-2, Rev. B, Steam Generator Level Instrument Channel 462 (Blue) Calibration. SP-05A-028B-3, Rev. 3, Steam Generator Level Instrument Channel 463 (Yellow) Calibration. SP-05A-028B-5, Rev. B, Steam Generator Level Instrument Channel 472 (Red) Calibration. SP-05A-028B-6, Rev. B, Steam Generator Level Instrument Channel 473 (White) Calibration. SP-05A-028B-4, Rev. 3, Steam Generator Level Instrument Channel 471 (Yellow) Calibration. 5.16 Interconnecting Wiring Diagrams: XK-100-622, Rev. 2M XK-100-663, Rev. 2Q 5.17 Station Drawings:

• XK-100-554, Rev. 2B
• XK-100-149, Rev. 4K
• E-3602, Rev. H 5.18 Kewaunee Power Station Environmental Qualification Plan, Rev. 27.

5.19 Kewaunee Calculation C11116-5, Rev. 0, Steam Generator NR Level, Control Room Indication. 5.20 Kewaunee DCR 2939, Replace all Six Narrow Range Steam Generator Level Transmitters 24042 (LT-461), 24043 (LT-462), 24044 (LT-463), 24046 (LT-471), 24047 (LT-472), 24048 (LT-473).

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 9 of 23 5.21 Kewaunee Calculation CN-SSO-02-08, Rev. 1, Kewaunee Steam Generator Water Level Trip Setpoints Uncertainty Calculations for 7.4% Power Uprate, Replacement Steam Generators and WCAP-15821, Rev. 0. 5.22 Kewaunee Calculation C10746, Revision 0, Addendum A, Instrument Loop Calibration Resistor Check. 5.23 Instrument Surveillance Procedure SP-47-281, Rev. 14, AMSAC Quarterly Functional Test. 5.24 Kewaunee Vendor Technical Manual KW-VTM-000-NUSIN-0010, Revision 0, NUS Instruments Series 500 Analog Isolator Module Operations & Maintenance Manual. 6.0 COMPUTER CODES No computer codes were used to perform this calculation. All calculations were performed by hand using the method described in Section 2.0.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 10 of 23 7.0 Functional Block Diagram This drawing is representative of Loop A Channel 3. Loop A Channel 4 and Loop B Channels 1 and 2 are similar. Loop A Channel 1 and Loop B Channel 2 are similar to the other Channels with the exception of the Steam Generator Low Level Reactor Trip, and the AMSAC Low-Low Level Turbine Trip / Reactor trip. LM-462 FOXBORO LEAD/LAG M4 LC-462G FOXBORO OR NUS BISTABLE M5 LQ-462 FOXBORO OR NUS POWER SUPPLY M1 LC-462C FOXBORO OR NUS BISTABLE M2 LC-462A/B FOXBORO OR NUS BISTABLE M3 AMSAC Low - Low Level Logic S/G Level Low RX Trip S/G Low Low Level Rx Trip High Level FW Isolation LT-462 ROSEMOUNT TRANSMITTER 1154DP4 30 to 137 In-H20

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 11 of 23 The channels listed below (Table 7-1) develop the Steam Generator Low Level Coincidence Reactor Trip, Low Low Level Reactor Trip, the High Level Turbine Trip & Feedwater Isolation, and the AMSAC Low-Low Level Trip. This calculation is applicable for all four Steam Generator Level Channels. TABLE 7-1 Channel Tag/ Mark No. Tag/ Mark No. Tag/ Mark No. Tag/ Mark No. Tag/ Mark No. Tag/ Mark No. SG A Level Channel 1 (Red) LT-461 (24042) LQ-461 (4848601) LC-461A/B (4848602) SG A Level Channel 3 (Blue) LT-462 (24043) LQ-462 (4848401) LC-462A/B (4848402) LC-462C (4848403) LM-462 (4848404) LC-462G (4809808) SG A Level Channel 4 (Yellow) LT-463 (24044) LQ-463 (4845801) LC-463C/D (4845803) LC-463E (4845802) LM-463B (4845804) LC-463G (4809808) SG B Level Channel 1 (Red) LT-472 (24047) LQ-472 (4848101) LC-472A/B (4848102) LC-472C (4848103) LM-472 (4848104) LC-472G (4809807) SG B Level Channel 2 (White) LT-473 (24048) LQ-473 (4848201) LC-473C/D (4848202) LC-473E (4848203) LM-473B (4809807) LC-473G (4809807) SG B Level Channel 4 (Yellow) LT-471 (24046) LQ-471 (4848301) LC-471A/B (4848302)

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 12 of 23 8.0 CALCULATION SE = Systematic Error No Systematic Error has been identified for these loops. SE = 0.000% of span PMA = Process Measurement Accuracy The PMA terms from Section 2.1 are given below for the various loop functions considered in the calculation. PMA1 (Low Level Coincidence) Section 2.0, Table 2-1 shows a PMA value of - 1.8291 % of span for the Low Level Coincidence circuit. This PMA value is based on Low Tave, 10% tube plugging, Low Setpoint of 25.5% Level and 100% power. For conservatism, the above is the most bounding PMA value between the Hi Tave 0% tube plugging, low setpoint of 25.5% and the Low Tave 10% tube plugging, low setpoint of 25.5% level. This value will be added to the Reference Leg Temperature error (from Table 2-1) to determine the overall PMA to be applied to the Steam Generator Low Level Coincidence Trip Function. PMA2 (Low Low Level ESFAS Initiation) Section 2.0, Table 2-1 shows a PMA value of - 1.6875 % of span for the Low Low Level ESFAS Initiation circuit. This PMA value is based on Hi Tave, 0% tube plugging, Low Low Setpoint of 17.0% Level and 100% power. For conservatism, the above is the most bounding PMA value between the Hi Tave 0% tube plugging, Lo-Lo setpoint of 17.0% and the Low Tave 10% tube plugging, Lo-Lo setpoint of 17.0% level. This value will be added to the Reference Leg Temperature error (from Table 2-1) to determine the overall PMA to be applied to the Steam Generator Low Level Coincidence Trip Function. PMA3 (Hi Level Turbine Trip / Feedwater Isolation) Section 2.0, Table 2-1 shows a PMA value of + 5.2050 % of span for the Hi Hi Turbine Trip & Feedwater Isolation circuit. This PMA value is based on Hi Tave, 0% tube plugging, Hi Hi Setpoint of 66.5% Level and 100% power. For conservatism, the above is the most bounding PMA value between the Hi Tave 0% tube plugging, Hi Hi setpoint of 66.5% and the Low Tave 10% tube plugging, Hi Hi setpoint of 66.5% level. This value will be added to the Reference Leg Temperature error (from Table 2-1) to determine the overall PMA to be applied to the Steam Generator Low Level Coincidence Trip Function. PMA4 (AMSAC Low Low Level Turbine Trip / Reactor Trip) Section 2.0, Table 2-1 shows a PMA value of - 1.5781 % of span for the AMSAC Low Low Level Turbine Trip / Reactor Trip. This PMA value is based on Hi Tave, 0% tube plugging, Lo-Lo

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 13 of 23 Setpoint of 13.0% Level (AMSAC) and 100% power. For conservatism, the above is the most bounding PMA value between the Hi Tave 0% tube plugging, Lo-Lo setpoint of 13.0% and the Low Tave 10% tube plugging, Lo-Lo setpoint of 13.0% level. This value will be added to the Reference Leg Temperature error (from Table 2-1) to determine the overall PMA to be applied to the Steam Generator Low Level Coincidence Trip Function. PMA1 = - 2.659% of span PMA2 = - 2.518% of span PMA3 = + 5.945% of span PMA4 = -2.408% of span PEA = Primary Element Accuracy PEA is not applicable for this loop configuration. PEA = +/- 0.000% of span SCA = Sensor Calibration Accuracy Reference 5.14 provides a transmitter calibration accuracy of + 0.25% of span. SCA = + 0.250% of span (Reference 5.14) SMTE = Sensor Measuring and Test Equipment The following Measuring and Test Equipment or its equivalent is used for calibration of the Transmitters:

1) SMTE1 = DMM, Fluke Model 45 or equivalent SMTE1 = +/- 0.100% of span (Assumption 4.3)

2) SMTE2 = 10 Precision Test Resistor with an accuracy of +/- 0.01% of span SMTE2 = +/- 0.010% of span (Reference 5.9)

3) Reference 5.14 states that a pressure measuring device with an accuracy of + 0.2 in-H2O or better is used for the calibration of the Steam Generator Level transmitters.

SMTE3 = 100%

• 0.2 H2O / 107 H2O = 0.187% of span SMTE3 = +/- 0.187% of span

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 14 of 23 The Transmitter Measuring and Test Equipment (SMTE) accuracy is equal to: SMTE = [(SMTE1 + SMTE2)2 + SMTE3 2] 1/2 SMTE = [(0.1 + 0.01)2 + (0.187)2] 1/2 SMTE = +/- 0.217% of span SD = Sensor Drift The sensors are Rosemount Model 1154DP4 transmitters (Ref. 5.20). The calibration span of the instrument is 107 W.C. (Ref. 5.15). Based on Reference 5.8, the Rosemount Model 1154 transmitter has a drift value of +/- 0.2% of the upper range limit (URL) for a 30-month period following calibration. For a calibration cycle up to 30 months the drift value is: SD = +/- 0.2% of the URL per 30 Months, URL = 150 W.C. SD = +/- {[(0.2% / 100%)

• 150 W.C.] / 107 W.C.}
• 100 SD = +/- 0.280% of span SPE = Sensor Pressure Effect The Sensor Pressure effect (SPE) will have two components, Static Pressure Zero (SPZ) effect and Static Pressure Span (SPS) effect. SPE will have a random component derived from the Static Pressure Zero (SPZ) effect and the Static Pressure Span (SPS) effect uncertainty i.e. the generally accepted value of SPE is computed for a pressure max of 1020 psia (Attachment 1).

Per Reference 5.8, the URL for the Rosemount Series D transmitter (Range Code 4) is 150 W.C. Also per Reference 5.8, the Static Pressure Zero (SPZ) effect is + 0.2% of URL per 1000 psi for model 1154DP range code 4 transmitters. The Static Pressure Span uncertainty effect is + 0.5% of input per 1000 psi. The maximum operating pressure of the main steam header, as shown in Attachment 1 is 1020 psia. From Reference 5.14 the calibration span of the sensor is 107 W.C. SPZ = (([(0.2% / 100%)

• 150 W.C.] / 107 W.C.}
• 100%} * (1005.3 psig / 1000 psig)

SPZ = + 0.282% of span Per Reference 5.19 the Rosemount transmitters have been corrected for a static pressure of 785 psig. Per Reference 5.8 this correction has an uncertainty of + 0.5% of input per 1000 psi. SPS = + 0.5% of input per 1000 psi SPS = 0.5% * (1005.3 psig / 1000 psig) SPS = + 0.503% of span

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 15 of 23 The overall Transmitter Sensor Pressure Effect (SPE1) term is equal to: SPE= (SPZ2 + SPS2)1/2 SPE = (0.2822 + 0.5032)1/2 SPE = +/- 0.577% of span STE = Sensor Temperature Effect Rosemount Instruction Manual (Ref. 5.8) states the temperature effect for Range Code 4 is: +/- (0.75% of URL + 0.5% span) / 100°F (Reference 5.8) Upper Range Limit = 150 W.C. Transmitter Span = 107 W.C. Temperature Span = 80°F (Based on the EZD Zone L02 (Ref. 5.18) minimum temperature of 40°F and Maximum temperature of 120°F) STE = [(0.75%

• 150 W.C / 107 W.C.) + 0.5%] * (80°F / 100°F)

STE = +/- 1.241% of span SPSE = Sensor Power Supply Effect According to Reference 5.20, Rosemount Model 1154DP4 differential pressure transmitters are used for the Steam Generator Level Channels. According to Reference 5.8, the Sensor Power Supply Effect for this model is less than 0.005% of output span per volt. The nominal load resistance for the Steam Generator Level Channels is approximately 650 (Reference 5.15). Based on Figure 2-3 in Reference 5.8, the nominal power supply voltage at 650 at 20 mA is 25.4 VDC. From Figure 2-3, the high end qualified power supply voltage is 45 VDC and the low end voltage is 13.5 VDC. Based on References 5.14 and 5.15, the power supply output voltage is not checked during the performance of the Channel Calibration Procedure or the Steam Generator Level Transmitter Calibration Procedure, therefore to bound all possible conditions, a power supply output tolerance of + 11.9 VDC (i.e. 25.4 VDC - 13.5 VDC) will be used to determine the Sensor Power Supply Effect. SPSE = +/- [(0.005% / 100%) * (11.9 VDC / 1.0 VDC)]

• 100% = 0.060%

SPSE = + 0.060% of span

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 16 of 23 M1 = Foxboro / NUS Loop Power Supply Model 610AC-0/SPS500 According to References 5.15 and 5.16, the loop power supply is either a Foxboro H/610AC-0 or a NUS Instruments SPS500. Based on References 5.14 and 5.15, these power supplies are not used as a current to voltage converters. Therefore, the accuracy for M1 is + 0.0 % of span. M1 = + 0.000% of span M1MTE = Loop Power Supply Measuring and Test Equipment According to References 5.15 and 5.16, the loop power supply is either a Foxboro H/610AC-0 or a NUS Instruments SPS500. Based on References 5.14 and 5.15, these power supplies are not used as a current to voltage converters. Therefore, the accuracy for M1MTE is + 0.0 % of span. M1MTE = 0.000% of span M2 = Foxboro/NUS Bistable Module Model 63U-AC-OHBA/SAM504-3 Based on Reference 5.16, either a Foxboro Model M/63U-BC or NUS Instruments Model SAM504-3 may be installed as a Steam Generator Low Level bistable. The calibrated accuracy is +/- 0.500 % of span. (Reference 5.15) M2 = +/- 0.500% of span M2MTE = Foxboro/NUS Bistable Module Model 63U-AC-OHBA/SAM504-3 Measuring and Test Equipment Based on Reference 5.15, the following M&TE is used to calibrate the bistable: M2MTE = +/- (Fluke + TPR) Fluke Accuracy = +/- 0.100% of span (Assumption 4.3) Test Point Resistor Accuracy = +/- 0.100% of span (Reference 5.22) M2MTE = +/- (0.100 + 0.100) = +/- 0.200% of span M2MTE = +/- 0.200% of span M3 = Foxboro/NUS Bistable Module Model 63U-AC-OHBA/DAM504-3 Based on Reference 5.16, either a Foxboro Model M/63U-BC or NUS Instruments Model DAM504-3 may be installed for the Steam Generator Level Low-Low and Hi Level bistable. The calibrated accuracy is +/- 0.500 % of span. (Reference 5.15) M3 = +/- 0.500% of span

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 17 of 23 M3MTE = Foxboro/NUS Bistable Module Model 63U-AC-OHBA/DAM504-3 Measuring and Test Equipment Based on Reference 5.15, the following M&TE is used to calibrate the bistable: M3MTE = +/- (Fluke + TPR) Fluke Accuracy = +/- 0.100% of span (Assumption 4.3) Test Point Resistor Accuracy = +/- 0.100% of span (Reference 5.22) M3MTE = +/- (0.100 + 0.100) = +/- 0.200% of span M3MTE = +/- 0.200% of span M4 = Foxboro/NUS Signal Converter I/I Module Model M/66BC-0/ OCA504 Based on Reference 5.16 and 5.24, either a Foxboro Model M/63U-BC or NUS Instruments Model OCA504 may be installed for the Steam Generator Signal Converter Module. The calibrated accuracy is +/- 0.500 % of span. (Reference 5.23) M4 = +/- 0.500% of span M4MTE = Foxboro/NUS Signal Converter I/I Module Model M/66BC-0/OCA504 Measuring and Test Equipment Based on Reference 5.15, the following M&TE is used to calibrate the Signal Converter Module: M4MTE = +/- (Fluke + TPR)2 + (Fluke + TPR)2 Fluke Accuracy = +/- 0.100% of span (Assumption 4.3) Test Point Resistor Accuracy = +/- 0.100% of span (Reference 5.22) M4MTE = +/- (0.100 + 0.100)2 + (0.100 + 0.100)2 = +/- 0.283% of span M4MTE = +/- 0.283% of span M5 = Allen Bradley Processor Mini PLC-2 Based on Reference 5.17, an Allen Bradley Mini PLC-2 is installed for use as the Steam Generator AMSAC Low-Low Level trip function. The calibrated accuracy is +/- 0.500 % of span. (References 5.17 & 5.23) M5 = +/- 0.500% of span

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 18 of 23 M5MTE = Allen Bradley PLC Module Measuring and Test Equipment Based on Reference 5.15, the following M&TE is used to calibrate the Allen Bradley PLC AMSAC Low-Low Level trip function: M5MTE = +/- (Fluke + TPR) Fluke Accuracy = +/- 0.100% of span (Assumption 4.3) Test Point Resistor Accuracy = +/- 0.100% of span (Reference 5.22) M5MTE = +/- (0.100 + 0.100) = +/- 0.200% of span M5MTE = +/- 0.200% of span RD = Rack Drift The superseded calculations specified a drift value derived from previous testing. However, that data is not current and Kewaunee is replacing Foxboro rack modules with NUS Instruments equivalents where sufficient drift trends have not been established. Therefore, the standard and conservative value of + 1.0% of span as referenced in STD-EEN-0304, Revision 6 will be used in this calculation. RD = + 1.000% of span (Reference 5.1) RTE = Rack Temperature Effect For Kewaunee calculations the Rack Temperature Effect term was either assumed to be embedded in the Rack Drift term or set to zero percent of span. However, the effects of rack temperature changes have not been monitored or documented. Therefore, the standard and conservative value of + 0.5% of span as referenced in STD-EEN-0304, Revision 6 will be used for this calculation. RTE = + 0.500% of span (Reference 5.1) RRA = Rack Readability Allowance Rack Readability Allowance (RRA) is applicable for the indication portion of the loops. This calculation is determining the CSA value associated with the applicable trips and not the indication. Thus, RRA = + 0.000% of span (Reference 5.1)

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 19 of 23 Steam Generator Low Level Coincidence Reactor Trip Uncertainty (Normal Conditions) The Channel Uncertainty for the Steam Generator Low Level Coincident Reactor Trip based on NORMAL conditions is given by the following equation: CSA = SE + PMA1 + [PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M2 + M2MTE)2 + RD2 + RTE2]1/2 Where: SE = 0.000% of span PMA1 = - 2.659% of span PEA = 0.000% of span SCA = 0.250% of span SMTE = 0.217% of span SD = 0.280% of span SPE = 0.577% of span STE = 1.241% of span SPSE = 0.060% of span M1 = 0.000% of span M1MTE = 0.000% of span M2 = 0.500% of span M2MTE = 0.200% of span RD = 1.000% of span RTE = 0.500% of span CSA = 0.0 - 2.659 + [0.02 + (0.25 + 0.217)2 + 0.282 + 0.5772 + 1.2412 + 0.0602 + (0.0 + 0.0)2 + (0.50 + 0.20)2 + 1.002 + 0.502]1/2 CSA-NORMAL (SG Low Level Coincidence) = - 0.681% of span to - 4.637% of span = - 0.681% Level to - 4.637% Level Note: When the resultant CSA is a net negative (-) the actual level is lower than indicated level.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 20 of 23 Steam Generator Low Low Level Reactor Trip Uncertainty (Normal Conditions) The Channel Uncertainty for the Steam Generator Low Low Level Reactor Trip based on NORMAL conditions is given by the following equation: CSA = SE + PMA2 + [PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M3 + M3MTE)2 + RD2 + RTE2]1/2 Where: SE = 0.000% of span PMA2 = - 2.518% of span PEA = 0.000% of span SCA = 0.250% of span SMTE = 0.217% of span SD = 0.280% of span SPE = 0.577% of span STE = 1.241% of span SPSE = 0.060% of span M1 = 0.000% of span M1MTE = 0.000% of span M3 = 0.500% of span M3MTE = 0.200% of span RD = 1.000% of span RTE = 0.500% of span CSA = 0.0 - 2.518 + [0.02 + (0.25 + 0.217)2 + 0.282 + 0.5772 + 1.2412 + 0.0602 + (0.0 + 0.0)2 + (0.50 + 0.20)2 + 1.002 + 0.502]1/2 CSA-NORMAL (SG Lo-1 Level) = - 0.540% of span to - 4.496% of span = - 0.540% Level to

-4.496% Level Note: When the resultant CSA is a net negative (-) the actual level is lower than indicated level. 

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 21 of 23 Steam Generator Hi Level Turbine Trip & FW Isolation Uncertainty (Normal Conditions) The Channel Uncertainty for the Steam Generator Hi Level Turbine Trip / FW Isolation for NORMAL conditions is given by the following equation: CSA = SE + PMA3 + [PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M3 + M3MTE)2 + RD2 + RTE2]1/2 Where: SE = 0.000% of span PMA3 = +5.945% of span PEA = 0.000% of span SCA = 0.250% of span SMTE = 0.217% of span SD = 0.280% of span SPE = 0.577% of span STE = 1.241% of span SPSE = 0.060% of span M1 = 0.000% of span M1MTE = 0.000% of span M3 = 0.500% of span M3MTE = 0.200% of span RD = 1.000% of span RTE = 0.500% of span CSA = 0.0 + 5.945 + [0.02 + (0.25 + 0.217)2 + 0.282 + 0.5772 + 1.2412 + 0.0602 + (0.0 + 0.0)2 + (0.50 + 0.20)2 + 1.002 + 0.502]1/2 CSA-NORMAL (Hi Level Turb Trip/FW Isol) = + 3.967% of span to + 7.923% of span = + 3.967% Level to + 7.923% Level Note: When the resultant CSA is a net positive (+) the actual level is higher than indicated level.

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 22 of 23 Steam Generator AMSAC Low Low Level Turbine Trip / Reactor Trip Uncertainty (Normal Conditions) The Channel Uncertainty for the Steam Generator AMSAC Low Low Level Turbine Trip / Reactor Trip based on NORMAL conditions is given by the following equation: CSA = SE + PMA4 + [PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M4 + M4MTE)2 + (M5 + M5MTE)2 + RD2 + RTE2]1/2 Where: SE = 0.000% of span PMA4 = - 2.408% of span PEA = 0.000% of span SCA = 0.250% of span SMTE = 0.217% of span SD = 0.280% of span SPE = 0.577% of span STE = 1.241% of span SPSE = 0.060% of span M1 = 0.000% of span M1MTE = 0.000% of span M4 = 0.500% of span M4MTE = 0.283% of span M5 = 0.500% of span M5MTE = 0.200% of span RD = 1.000% of span RTE = 0.500% of span CSA = 0.0 - 2.408 + [0.02 + (0.25 + 0.217)2 + 0.282 + 0.5772 + 1.2412 + 0.0602 + (0.0 + 0.0)2 + (0.50 + 0.283)2 + (0.50 + 0.20)2 + 1.002 + 0.502]1/2 CSA-NORMAL (SG Lo-1 Level) = - 0.281% of span to - 4.535% of span = - 0.281% Level to

- 4.535% Level Note: When the resultant CSA is a net negative (-) the actual level is lower than indicated level. 

Engineering Work Sheet Calculation Number: C11116 Revision: 0 Addendum: N/A Page 23 of 23

9.0 CONCLUSION

S The results of this calculation are summarized below: Steam Generator Low Level Coincidence CSA-NORMAL (Low Level Coincidence) = - 0.681% Level to - 4.637% Level Steam Generator Low-Low Level Reactor Trip CSA-NORMAL (Low Low Level RX Trip) = - 0.540% Level to - 4.496% Level Steam Generator Hi Level Turbine Trip & FW Isolation CSA-NORMAL (Hi Level Turb Trip / FW Isol)

= + 3.967% Level to + 7.923% Level Steam Generator AMSAC Low-Low Level Reactor Trip CSA-NORMAL (AMSAC Low Low Level Turb/RX Trip) = - 0.281% Level to - 4.535% Level 

CALCULATION NO: C11116-5 ORIGINATOR: PDesotelte Calctrlation C11116, Rev. 0 Page 1 of 23 DATE: 5/6/2004 CALCULATION REV: 0 REVIEWER: JWerner DATE: 5/11/2004 Page 91 of 131Wednesday, May 12, 2004 SG Narrow Range Level, PMA Calculation Pages: 22 Page 75 of 115 Pages

GALeUUTION NO: C11116-5 ~~~~~~~~~~~~~~.-- ~alculation ~11116, ~ev. 0 Page 2 of 23 ORIGINATOR: PDesotelJe DATE." 5/6/2004 CALCULATION REV: 0 REVIEWER: JWerner DATE: 5/11/2004 Actual vs. Indicated S/G Level and PMA Calculation for KNPP 7.4% Power Uprate

Purpose:

Determine the Process Measurement Accuracy (PMA) for the Narrow Range Steam GeneratorLeveIsetpoints and indication The PMA will be used in Loop Accuracy Calculations to determine Total Loop Error.

References:

1 Westinghouse Calculation No. CN..OPES(99)-025 t Actual vs. Indicated S/G Level and PMA Input Calculations for Kewaunee RSG. 2. Westinghouse Nuclear Safety Advisory Letter NSAL-02-3. S/G Mid..deck Plate Pressure Loss Issue. 3. Westinghouse Nuclear Safety Advisory Letter NSAL..024, Maximum Reliable lndicated S/G Water Level. 4. Westinghouse NuclearSafety Advisory Letter NSAL-02-5, S/G Water Level Control SystemUncertainty Issue. 5. Westinghouse I&CEJPOED(02)-49 Maximum Reliable Indicated Level (MIRL) for Kewaunee 7.4% Uprating.. April 5, 2002 6. Westinghouse 1&CEIPOED(02)-32 Rev.-l Thennal and Hydrolic Parameters Input for Steam Generator Level Process Measurement Accuracy for Kewaunee Power Uprate and RTSR Program. July 11, 2002 7. Westinghouse CN...SSO-02-8 Rev~ 0 Kewaunee Steam Generator WaterLevel Trip Setpoints Uncertainty Calculations for 7.4% Power Uprate, Repacement Steam Generators, and WCAP-15821, Rev.O Background Notes: This calculation uses the same methodology as Reference 1. Combining ofthePMA uncertainties in an Excel spread sheet to detel1l1ine bounding PMA values for KNPP Steam generator level setpoint calcUlations. Reference 1 was accomplished for the Steam Generator Replacement(SGR) project and Reference 7 was accomplished for the KNPP 7a4% Power Uprate. This KNPP generated PMA calculation will use parameters from both Westinghouse generated calculations. This calculation will use a transmitter calibration curve detennined through an iterative process using the PMA calculation to evaluate a best fit and minimize errors. The (W) Power-uprate PMA calculation used High Tave. (573°F) with 0% Tube Plugging and Low Tave.. (556 3Op) with 10% tube plugging as bounding conditions and calculated the PMA for a HI...HI and LO-LO setpoint of 78% and 10% respectively.. This calculation will determine the PMA for 78%, 100/0. a programmed level of44%, the KNPP Tech. Spec. value of 15% and KNPP setpoints of 66.5%, 25.5%,20% and 19% for the bounding conditions. The 78% level is 6 inches above the mid deck plate and is the maximum recommended leveL Reference 5. Page. 92 of 13IWednesday, May 12, 2004 Page 76 of 115 Pages

CALCULATION NO: C11116-S ORIGINATOR: PDesotelle Calculation C11116, Rev. 0 Page 3 of 23 DATE: 5/6/2004 CALCULATION REV: 0 Method of Analysis: REVIEWER: JWerner DATE: 5/11/2004 The analysis will largelyuse an Excel spreadsheet to calculate the actual vs. indicated levels. Themethodology is similar to that used in Reference 1.. Computer Code used: The computer code used is Microsoft Excel 97 SR-2 for Windows 95 The steam table conditions were obtained from an Excel add-in called Winsteam from Techware Engineering . applications inc., desk top version 3.1. Inputs I calculations: Tap to tap height plus thermal expansion, Reference 1 Thennal and Hydraulic parameters, Reference 6 Maximum Reliable Indicated Level (MRIL), Reference 5 Nerative (w) error = actual level lower than indicated Positive (+) error = actual level higher than indicated Ltnear interpolation of the Downcommer temperature (IDC) parameter is used to determine those temperatures for speciflc levels not included in reference 6. The Following IS a column by column description of the spread sheet A. Power Level B~ Inches of water above the lower tap e.. Percent level in decimal form. D.. Steam flow (pPH xlOE6) from. Reference 6 E. Steam pressure (PSIA) at the tube bundle. Reference 6. F. Temperature G. Spectfic volume of saturated fluid at specified pressure (cot-E) from W1nsteam add in. H. SpeCIfic volume of saturated gas at speCIfied pressure (coL-E) from Winsteam add in. I. Specific volume of the downcommer water at pressure (col.-E) and temperature (col.-F) from Winstearn add in. J. DIfferentIal pressure (PSI) across Mid Deck Plate (MDP) Reference 6. K. Velocity Head Effect, flow past lower level tap. Reference 6, Square of flow interpolatlon. L. SpeCIfIc volume of the Reference Leg water at pressure (col-E) and temperature 9SoF from Winsteam add in M. Reference Leg Pressure (PSI) = 144.53/(Col-L*1728) N~ Sub-cooled region Process Leg Pressure (pL..I) = 30.27/(Col..I*1728) O. Saturated water region Process Leg Pressure (PL-2) =(Col...B..30.27)/(Col-G*1728) P. Saturated Steam regIon Process Leg Pressure (PL-3) = (144.53-Col-B)/(Col-H*1728) Q. PL-Total (PSI) Total Process Leg Pressure::: SUM(Col-N thru Col-P) Page 93 of 131Wedta,sda,Y, May 121 2004 Page 77 of 115 Pages

CALCULATION NO: C11116-5 ORIGINATOR: POesoteJle Calculation C11116, Rev. 0 Page 4 of 23 DATE: 5/6/2004 CALCULATION REV: 0 REVIEWER: JWerner DATE: 5/11/2004 R. Differential Pressure (DP) across the Xmtr at specified level (pSn = (Col-M)-(Col-Q) This is the DP due to the differences in Density and height of water between the RL and PL~ s. Xmtr DP minus the rvIDP effect Plus VelQcity effect (PSI)(DP) = (Col-R) - (Col-I) + (Col-K) The MDP has a negatIve effect and the velocity a positive effect. This is the combined or resultant DP across the Xmtr for the given conditions. T. The actual water level in the steam generator when the indicated level is at the specIfied level. The actual DPt Col-S is calculated for a specific height of water and SInce the actual DP will likely differ from the Xmtr calIbrated DP for the specIfic level. The error is calculated as follows. The Indicated level is calculated based on the cal1brated DP span uSIng the actual DP. [(Col:M,Row:38)-(CoJ:S)] I (Col:M~Row:39) the result is a % of cahbrated span. ThlS result is then subtracted from the specified % level, the resultant difference wlll be a posItive or negatlve value~ This difference or error is then algebrmcally added to the specified %level to obtain the actual level when the indicated level is equal to the specifiedlevel. IE for a specifled level of 78% (78%+(78%-(Col:M,Row:38...Col:S)/Col:M,Row:39)))*100 u. Xmtr calibrated DP for the specIfied Level. ($M$38)-{O.78*$M$39) Where ($M$38) = calibration 0% DP, spread sheet location ($M$39) = Calibration Span, Spread sheet location v. Thermal Hydraulic DP error. (Col:R-Col:U)

w. MOP +VelocIty DP error. (Col:S - Co):R) x~

MOP +Velocity + thermal Hydrolic errors combined. (Col:S -Col~U) y~ Thermal HydrollC % error. (Co]:V I $M$39) z. MDP + Velocity %error. (Col:W I $M$39) AA.1\\1DP + Velacity + Thermal Hydraulic Errors combined. (Col:X I $M$39) Page 94 of 131Wednesday, May 12, 2004 Page 78 of 115 Pages

~ '= I r t\\ M Q ~ Reference.,. ~ ~ ~ t--c Elevation of tower Tap from top of tube sheel(.nches) 44108 Reference 1 ~ ~ ~ ~ ~ ~: Elevallon of feednng J-Tube dIscharge from lop of tUbe !:h?et{1nches) 47124 Reference 1 ~ Elevation of upper Tap from top of tube shee\\{mches} ~ ~ too,. 56506 Reference 1 ~ ~ ~ ~ Reference leg Temporature (oF) 95 Reference 5 Assumption ~ ~ ~ ~ ~ ~ DP for Mld-Deck PJaie (ps.J worst case 100~o power 0164 Aefe"ence 2 lower Tap 10 J...Tube Olschatge (471 2411.441 08 tC)+ 11 lor thermal expansion 3027u Reference 1 0 0 ~ Programmed water Leve' 44°,{, (14453" 44) = 635932 5046748 Reference 1 ~ 0) Conversion Factor used to convert from denSity to pressure pSI 1728 Reference 1 ~en COnvers1on Factor to convert from pressure ps, to callbrallon "H20 @ 6S0 F (pst - 2:1729648) 27729648 Reference 1 SpeCifiC Volumes at specified pressures ~ 0 ~ 23 Pressure (psla) 200 300 4CtO 500 600 700 800 900 1020 S ~ 24 ~ 25 @ 95 QF Ref Leg 0016105 0016101 0016096 0016091 0016086 0016081 0016076 0016071 0016056 ~ ~ 26 VaF @sat 0018387 0018897 0019343 0019752 0020140 0020514 0020879 0021240 o02Hi72 ~ a 27 V*G @sat 2288035 1 543446 1 161596 0928152 0770162. 0655866 0559179 0501069 0436300 ~ 28 29 Reference leg (RL) and Process leg (PL) pressures II -0 52012 52027 52043 5206183 0 51933 51949 51964 51980 51996 <D 454B9 44261 43241 42344 41530 40773 40059 39379 3859409 (IJ 0r+ () 0366 00542 00720 00901 01086 01275 01469 01669 o 191703 ~ XMTR m Differential Pressure (DP) psi calibraUo OP

• Htgh 1OO~f, Lvi 06444 07687 08723 09636 10466 1123g 1l96S 12664 13468 1 0818745

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• HIgh 100% Lvi 178685 213163 24188B 267195 290229 311645 331865 351179 373456 30

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~ 66 10 1127334 078 0322-9769 53482 0021517 0457811 0021299 0014 00000072 0016068 520551 tlj ~ 67 0 1127334 078 0 10200 547 0021672 0436300 0021670 O{lOO 00000000 0016066 520618

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~ 51 HI Tave, 0% TP, MRIL. 78% Hi Tave, 0% TP, MRIL. 78% ~ ~ Minus ~ N PL-1 PL-2 PL-3 PL-Tolal OP-XMTR MDP OP Aatual XMTR TH MDP -I-V MOP T TH THonly MOP+V MDP+TH fg ~ ~ subcooled sal waler sat steam @78%LVL +Velocl!y Level CALlBDP DPError DP Error OP E:IOT ~

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PSI PSI PSI PSI PSI PSI @78%lnd @78%LVl PSI PSI PSI Error Error Error 0 (') 085883 228823 003205 317911 202353 186G57 7618026 193079 00927 -01630 -007022 24034% -42231% -18197% 085655 228172 003276 317104 203186 188568 7683115 01011 193079 -01462 -004510 2619~0 -37981% -11689% 085400 227503 003350 316253 204063 191227 77 52019 19307g 01098 -01284 .{l018S1 28467% -33265% -047980'" m 085109 226816 003427 315351 204992 193940 7822321 193079 01191 -01105 000861 30875%

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• 120646 494056 01164

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~ ~ t"'-t h n A I B I C 'F 1 G M ~ ~ ~ ~ ~ 203 loW T Ave, 10%TP, MRll, 78% ~ 0 204 205 Mid-Deck Ve\\octly RL ~ ~ 06 POWER SG LEVEL SG level STM Flow P-STM TOe V-F V-G V..DO D? Effect V=AL pressure ~ 207 WI above LT PPH x 10E6 PSlA OE(3IF @ P*STM @ P..STM PSI PS~ PSI 208 a 0 209 100 1127334 078 3867 6557 4824 0020349 0702361 0020045 0164 il 0010422 0016083 520047 210 90 1127334 07B 3447 6843 4863 0020456 0671682 0020124 0146 00008275 0016082 520092 211 80 1127334 078 303 7141 0020566 --L. 4905 0642232 0020212 0128 00006392 0016080 520139 0> 212 70 1121334 078 262 7449 4952 0020678 0614179 0020313 0111 00004177 0016079 520187 01 60 1127334 078 22.14 7769 5001 0020795 0587299 0020422 0094 00003407 0016077 520237 50 1127334 078 1815 8109 5055 0020918 0560974 0020546 0077 '00002290 0016076 520291 40 1127334 078 1418 8454 5110 0021043 0536343 0020676 0060 00001396 0016074 520345 30 1127334 07B 1 035 B821 5173 0021176 0512172 0020831 0044 00000743 0016072 520402 ~ ~ 20 1127334 078 0673. 9205 5247 0021314 o4888B1 a 021023 0029 (}{lOOO314 0016070 520463 S ~ 10 '127334 078 0322 9620 5330 0021463 0465676 0021250 0014 00000072 0016068 520528 ~ Q 0 1127334 o 7B 0 1020fl 5470 0021672 0436300 0021610 0000 00000000 0016066 520618 ~ ~ ~ ~ ~.. Mid-Deck VeroCily RL C- "'U SG LEVEL SG level STMFlow P-STM TDC V-F V..G V*DC DP Effect V=Al pressure ~ a (l) ~ If above LT 0/0 PPH x 10E6 PSIA DEGF @ P-STM @ P-8TM PSI pst PSI

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m ~ 100 961125 Oti65 3867 6557 4821 0020349 0702361 0020037 0164 00010422 0016083 520047 iii'" 90 961125 0665 3441 6843 4860 002.0456 0671682 '0020117 0146 00008215 0016082 520092 BO 961125 0665 303 7141 490 1 o{)20566 0642232 0020203 0128 00006392 0016080 520139 70 961125 0665 262 7449 4948 0020678 0614179 0020303 o 111 00004777 0016079 520187 '"'0>> 60 961125 0665 2214 1769 4997 0020795 0587299 0020412 0094' 00003401 0016077 5.20237 ID ~ CO tu

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~ ~ Q t ~ ~ ~ t ~ n ~ N AA ~ ~ ~ 202 203 Low T Ave, 10% TP, MRIL, 78% Low T Ave, 10%TPr MRll., 78%

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~ ~ ~ ~ 20 Minus ~ N 205 PL*1 PL*2 PL*3 PL-Totat OP..XMTR MOP OP Actual XMTR TH MOP + V MDP + TH TH only MOP+V MDP+TH ~ ~ ~ 20 subcooled sat water sat steam @ 78% lVL + Ve'ocllY level CALtBDP DP Error DP Error DP Error oM 1"1~~ t;""". PSI PSI PSI PSI PSI @78%1nd @ 780/0 LVL PSI PSI ~ PSI Error Error Error 087392 234513 002620 324525 1 95522 179226 7441006 -0 1630 0 0 1 93079 00244 -013852 063320/0

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~ &? Q ~ ~ r-.. <':l ~ n ~ ~ ~ § A M ~ 240 ~ ~ ~ 241 Low Tave. 10%TP, Programmed Leve144% C ~ ~ 242 '\\oIo~ ~ 243 Mld-Deck Velocity RL ~ ~ l::J, ~ 2 POWER SG LEVEL SG Lpvel STM Flow P-STM TOe V-F ,V-G V-DC OP Eneel V::Rl ~ pressure ~ 245 Ck H above LT 'Yo PPHx 10E6 PSIA DEGF @ P-STM @ P-STM PSI PSI PSI 246 0 (') 247 100 635932 044 3867 6557 4814 0..,20349 0702361 0020022 0164 00010422 0016083 520047 ~ 248 90 635932 044 3447 6843 4852 0020456 0671682 0020100 0146 00008275 0016082 520092 -..10 249 80 635932 () 44 303 7141 4694 00.20566 0642232 0020186 0128 00006392 0016080 520139 OJ 250 70 635932 044 .262 7449 4940 0020618 0614179 0020284 o 111 00004777 0016079 5 20~87 bt 251 60 635932 044 2214 7769 4989 0020795 0587299 0020392 0094 00003407 o(}16077 520237 252 50 635932 044 1815 8109 5042 G020918 0560974 0020512 oon 00002290 0016076 520291 253 40 635932 044 1418 8454 5097 0021043 0536343 0020641 0060 00001396 0016074 520345 ~ ~ 254 30 635932 044 1035 8a21 5159 0021176 0512172 0020793 0044 00000743 0016012 520402 255 20 635932 044 0673 9205 5233 0021314 0488861 0020983 0029 00000314 0016070 520463 ~ 256 10 635932 044 0322 962 0 5315 0021463 0465676 0021205 0014 {) 0000072 0016068 520528 t.2j ~ 257 0 635932 044 0 10200 5470 0021672 0436300 0021670 0000 00000000 0016066 520618

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~ 258 ~ es 259 ~ 260 Low T ave. 100/"TP, LO Selpolnt 25.5% 261 If "'tJ 262 Mld-Oeck Velocily Rl tJ 263 POWER SG LEVEL SG Level STM Flow P-STM TOC V-F V-G V-DC OP Effect V~RL pressure (I)en 264 01'

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294 057215 000000 014908 082122 438405 437006 1921512 428458 00995 -00140 008547 25778~ -03626°k 22151 % tl-j ~ 295 065616 000000 015911 081521 439091 439C91 1975546 428458 01063 00000 010632 275550;0 oOOOO~~ 27555% ~ ~ 296 >:I t-.3 297 ~ 298 Low TAve, 10%TPJ LQ..LO Setpolnt 13o/~(AMSAC) Li)W T Avet 10%TP. lO..LO Selpoint 13 % iAMSAC) 299 Mlnus 300 Pl-1 PL*2 PL-3 PL*Total Dp..XMTA MOP DP Actual XMTR TH MDP + V MOP+TH TH only MDP+V MOp -+ TH Ii ""1J 301 subcoolpd sat water sal steam @ 11°k LVL + Velocity level CAl'S OP DP Error DP Error DP Error 'o/G °10 0' 0 ~ CD 302 PSI PSI PSl PSI PSl PSI @13%rnd @ 13ifo LVL PSI PSI PSI Errol' Error Error CJ) 0 303 ~ 304 otJ4370 000000 010360 064730 455317 439021 11 73747 443893 01142 -0 1630 ..004872 29606% -42231%

• 12625%

<D 305 054172 000000 010834 (} 65006 455086 440569 1213860 443893 o1~19 -0 1452

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~ G: 317 Low T Ave, 10% TPl' Tech Spec Limit 5°" ~ 0 ~ 318 ~ N 319 Mid-Deck VelocIIV RL ~ ~ c:::. ~ 320 POWER SG lEVEL SG level STMFlow P..STM TOe V-F V-G V-DC OP Erfect V;:;AL ~ prassure ~ 321 0' II aboveLT PPH x 10E6 PSIA DEGF @ P-STM @ P*STM PS~ PSI PSI ItJ 322 0 0 323 100 72265 005 3867 6557 4800 0020349 0102361 0019991 0164 o00t0422 0016083 520047 324 90 005 72265 3447 6843 4836 0020456 0671882 0020Q64 0146 00008275 0016082 520092 325 80 12265 005 303 7141 4817 0020568 0642232 0020147 0128 00006392 0016080 520139 0> 326 70 72265 005 262 74~9 4922 0020678 0614179 0020242 o 111 0OOO4n7 0016079 520187 J01 327 60 72265 005 2214 7789 4970 0020795 0587299 0020347 0094 00003407 0016077 520237 328 50 72265 005 1 815 8109 5022 0020918 0560974 0020464 0077 00002290 0015076 520291 329 40 72265 nos 1418 6454 5076 0021043 0536343 0020588 0060 00001396 0016074 520345 330 30 7~265 005 1035 8821 5137 0021176 0512172 0020734 0044 00000743 0016072 520402 ~ C 331 20 72265 005 0673 9205 5209 0021314 0488861 0020917 0029 00000314 0016070 520463 ~ ~ =s ~ 332 10 72265 005 0322 9620 5287 o021&i63 0465676 0021124 0014 00000072 0016068 520528 ~ ~ 333 0 72265 005 0 1020 {) 5470 0021672 0436300 0021670 0000 00000000 0016066 520618 ~ ~ 334 >:i ~ 335 ~ 336 Low T Ave, 10%TP, Analytical Lim.t 0% 337 338 Mid-Deck Veloctly RL C'- "U 339 POWER 56 LEVEL SG level 8TM Flow P*STM TDC V-F V-G V-DC DP Effect V=RL ~ a pressure (D CD 340 0/0

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341 (I) ~ ~ ~ 342 1tlO 00000 0 3867 6557 4797 0020349 0702361 0019985 0'64 00010422 0016063 520047 ar 343 90 00000 0 3447 6843 4834 0020456 0671682 0020060 0146 00008275 0016082 520092 344 80 00000 0 3il3 7141 4874 0020566 0642232 0020142 0128 QOOOG392 0016080 520139 345 70 00000 0 262 7449 4919 0020678 0614179 0020237 0'11 00004777 0016079 520187 ""0>> 346 60 00000 () 2214 7769 4967 0020795 0587299 0020341 0094-00003407 0016077 520237

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~ ~ Q ~ t'-4 ~ ~ n E Q. ~ § N AA ~ ~ 316 ~ ~ ~ 317 LDW T Ave, 10%TP., Tech Spec limit 5% low T Ave, 10% TP, Tech Spec Llm,t 5% ~ ~ ~ 318 MInus ~w 319 PL-1 PL-2 PL-:) PL-Tolal DP-;<MTA MOP DP Actual XMTR TH MOP + V MDP + TH TH only MDP+V MDP+ TH ~ ~ <::=t ~ ~ 320 subcooled sal water sat steam @5%LVL +Velocity Level CALIB DP DP Error Of' Error DP Error ok 6. .t., ~ 321 PSI PSI psr PSI PSI PSI @ 5%lnd @ 5~~ LVL PSI PSI PS~ Error Error Error 322 0 0 323 020920 000000 011313 032233 487814 471519 415930 474763 01305 -0 1630 ..Q03244 3 =04824°~ -42231 % -{)8407% ...A. ...,A. 324 020843 000000 011830 032673 487419 472902 451174 474763 01266 -01452 -001961 32800% ..376220/0 -048230/0 .-L ~ 325 020757 000000 o 12372 033129 481009 474273 487322 474163 01225 -01274 ..000489 3 17380/0

• 33006%
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• 24272%

05250% 28 020436 000000 0141&4 034600 485891 476014 584254 474763 01093 -00768 003251 28321 q/G

• 1 98960/0 o 8425 Cl/a 329 020313 000000 014815 035128 485217 479231 615802 474763 01045

-00599 004468 27093"0

• 1 55130/0 1 1580(1/0 330 020170 000000 015514 035683 484719 480326 644t87 474763 00995
• 00439 005564 25802%

-1 1384°.{. 1 44194fo ~ C 331 019993 000000 016254 036247 4B4216 48'319 669906 474763 00945 -00290 006556 24498% -07507% 1 6991 % ~ ~ 332 019798 ?OOOOO 017063 o3SSG1 483667 482268 694495 474763 00890 -00140 007505 2 3076C}~ -0 3626°k 1 94490/0 ~ ~ 333 019299 000000 {) 18212 037511 4831(18 483108 716266 47478S 00835 00000 008345 2 1621~0 00000% 21627% ~ ~ 334 ~ 335 ~ ~ 336 Low T Ave, 10%TP, Analytical Limit 0% Low T Ave, 1{)%TP, Analytical limit 00/0 337 Minus 338 PL-1 PL-2 PL-3 PL-Total DP-XMTR MDP OP Actual XMTR TH MDP + V MOP + TH TH only MDP+V MOP+ TH II '"U 339 subcooled sat water sal steam @ O~'o lVL + Velocity Level CAUBDP DP Error DP Error DP Error Ok o,{. 01 a .0 <D 340 PSI PSI PSI PSI pst PSI @ 00/0' lnd @ COk lVL PSi PSI PSl Error Error Error en 0 341 ( ~ 342 000000 000000 011908 011908 508139 491843 -057356 494056 01408 -01630 -002213 36496%

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• 01105 001461 32428%

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• 00937' 002574 30943%

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~ 0 ~ ~ (1) 0 Page III of131 .-..-....---_..._--_...._---~-

~ ~ ~ ~ t:-t ~ ~ ~ CO") ~ ~ ~ ~ ~ M ~ ~ 35 C ~ ~ 355 Downcommer temperatures Ironl Reference 6 ~ w 356 00/0 10% 20% 30% 400k 50°4 60% 10% 80~o ~ ~ c::> ~ 357 Leva' Leve' level Level Level Level Level Leve' loveI ~ ~ 358 loTave loTave LoTav& Lo Tave La Tave loTave LoTave La lave LoTave 359

• F
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0 360 ~ 361 4797 480~ 4806 4809 4813 48~ 6 4619 4822 4825 -10 -.I. 62 4834 4838 4843 4847 4851 -4854 4858 4861 4864 m 363 4874 4879 4884 4888 4892 4898 4900 4902 4900 0'1 364 4919 4924 4929 4934 4938 4942 4946 4949 4953 365 4961 4972 4977 4982 4987 4991 4995 499 B 5002 366 501 9 5025 5031 5035 5040 5044 5048 5052 5056 367 5072 5079 5085 5090 5095 5099 5104 S108 511 1 ~ §i 368 5133 5140 5146 5152 5157 5162 5166 5170 5174 S 369 5205 5213 521 9 5225 5231 5236 5240 5244 5248 ~ ~ 370 5282 5292 5aO 0 5307 5313 531 8 5323 5327 5331 ~ ~ 371 547 5470 5470 5470 5470 5470 5470 5470 5470 ~ 372 ~ C 373 ~ 374 375 InterjJolation of downcommer temperature to various levels Co- "'U

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CJ 376 500/0 130% 170% 255% 440% 665% 780% (I) !tl 377 loTave lo lave LoTave en Lo Tave loTave loTave loTave J 0 m 4""+ 378 ~ ~ 379 479950 480320 480480 480765 ~C1 420 482095 482440 m 380 483600 483950 484150 484520 485220 485995 486340 381 487650 488050 488250 488620 4B9360 490130 490520 382 492150 492550 492750 493175 493960 494795 495220 -0>> 383 496950 497350 497550 497975 498860 499695 500120 Q) ~

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• F

-F -F Interpotation of downcommer temperature to vtldous levels 50% 13 O~1, 170% 255% 440°'" 665°kJ 780% HI Tave H& Tavo HI Tave HI Tavo Hi Tave HI Tave HI Tave N ~ ~ ~ ~ ~ ~ Va ~ ~ ~

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~ ~ Page 113 of 131

Calculation C11116, Rev. 0 Page 1 of 1 50.59 APPLICABILITY REVIEW (Is the activity excluded from 50.59 review?) Document/Activity number: _C_l_1_1_16~,_R_e_vi_sl_'0_0_0 Briefdescription of proposed activity (what is being changed and why): This calculation supercedes calculation C11116-1, Revision 0, C11116-2. Revision 1 and C11116-3, Revision l.Calculation Cl1116, Revision 0 dev-el-ops-t:he-..bhannel-Stat-i-stical-AUowanee-(CSA)-values-asseciated with Kewaunee~s Unit-l Steam'6ener-at-e>r Hi Level-'Furbine-Trip-and"Feedwater - Isolation, Low Level Coincidence with Steam FlowlFeed Flow Mismatch Reactor Trip, and the Low-Low Reactor Trip functions. This calculation supports Kewaunee's conversion to Improved Technical Specifications (ITS). Does the proposed activity involve or change any of the following documents or processes? Check YES or NO for EACH applicability review item. Explain in comments ifnecessary. [Ref. USA 50.59 Resource Manual] 3. 1. 2. NOTE: Ifyou are unsure if a document or process may be affected, contact the process owner. Yes No Docmnent or Applicable Contact!Action ../ ../ Process Regulation a D ~ Technical Specifications or Operating License 10CFR50.92 Process change per LI-AA-I01. Contact Licensing. Activity/change previously approved by NRC in Identify NRC letter in comments below. Process b 0 ~ 10CFR50.90 change: licenseamendment or NRC SBR Contact Licensing for assistance. c 0 ~ Activity/change covered by an existing approved 10CFR50 Appendix. B Identify screening or evaluation in comments below. 10CFRS0.59 reviewt screening, or evaluation. Process change. d 0 ~ Dominion Quality Assurance Program Description 10CFR50.54(a) ContactQA. (DOM-QA-l) Refer to NO-AA-I01. D ~ Emergency Plan 10CFR50.54(q) ContactEP. e Refer to FP-R-BP-02. f 0 ~ Security Plan 10CFR50.54(p) Contact Security. Refer to FP-S-SPE-OL g 0 t81 1ST Plan 1.0CFRS0.55a(t) Contact 1ST process owner. Refer to ER-AA-IST-IO. h 0 ~ lSI Plan 10CFR50.55a(g) Contact lSI process owner. Refer to BR-AA-NDB-122, NAD-ol.05, and NAD~05.1L i 0 ~ BeeS Acceptance Criteria 10CFRSO,46 Contact Licensing. USAR or any document incorporated by reference - Process USAR change per NEP-05.02. j 0 ~ Check YES only ifchange is editorial (see 10CFR50.71 Attachment A). Contact USAR process owner for assistance. Commitment - Commitment changes associated Contact Licensing. k 0 ~ with a response to Generic Letters and Bulletinst or 10CFR50 Appendix B if described in the USAR require a pre--screening. Refer to LI-AA-I10. Maintenance activity or new/revised maintenance Evaluate under Maintenance Rule. 1 0 ~ procedure - Check YES only ifclearly maintenance 10CFRSO.65 Refer to ER-AA-MRL-IO. ER-AA-MRL-IOO, and and equipment will. be restored to its as-designed NAD-08.21. condition within 90 days (see Attachment C). New/revised administrative or managerial directive/procedure (e.g., NAn, GNP, Fleet m 0 -121 Procedure) or a change to any procedure or other 10CFR50 Appendix B Process procedure/document revision. controlled document (e.g., plant drawing) which is clearlyeditoriaVadministrative. See Attachments A andB. n 0 ~ Fire Plan 10CFR50.48 Fire Protection Program Document Change Control, GNP-05.30.01. 0 0 ~ Independent Spent Fuel Storage Installation (ISFSI) 10CFR72.48 Implement DNAP-3004, starting with Applicability. Date: 10-11/-.0q Date: /0/1<//2 o~ 9 4. 5. Reviewed by: D. M. McGrath (print!sign). Conclusion. Check one of the following: [8J All documents/processes listed above are checked NO.10CFR50.59 applies to the proposed activity. A 50.59 pre-screening shall be performed. o One or more ofthe documents/processes listed above are checked YES, AND controls all aspects of the proposed activity. 10CFRSO.59 does NOT apply. Process the change under the applicable program/process/procedure. o One or more ofthe documents/processes listed above are checked YESt however, some portion ofthe proposed activity is not controlled by any ofthe above processes. 10CFR50.59 applies to that portion. A 50.59 pre-screening shall be performed. Comments: ET-CEE-09-0009, Rev. 0 will transmit the SO.59/72.48 Evaluation and program/document updates. 6. Print name followed by signature. Attach completed Conn doeumentJaCtiVi~ package. Prepared by: Andrew W~ Baugus . c>-- --.I ~ (print/sign) Form GNP..04..04.01-1 Rev. 12 Date: APR 08 2008 Page 15 of 16

Calculation C11116, Rev. 0 Page 1 of 1 1. 2. 3. 50.59 PRE-SCREENING (Is a 50.59 screenIng required?) Document/Activity number: _C_l_1_11_6...:.,,_R_ev_i_si..;,.o_n_O Brief description of proposed activity (what is being changed and why): This calculation supercedes calculation C11116-L Revision 0, C11116-2, Revision 1 and Clll16-3, Revision l.Calculation Cll116, Revision 0 develops the Channel Statistical Allowance (CSA) values associated with Kewaunee's Unit 1 Steam Generator Hi Level Turbine Trip and Feedwater Isolation, Low Level Coincidence with Steam FlowlFeed Flow Mismatch Reactor Trip, and the Low-Low Reactor Trip functions. This calculation supports .Kewaun.ee's ~~nyersion to I!J1proved Technical Sp~~ifi~ti0l!s (IT~). Does the proposed activity involve or change any ofthe following documents or processes? Explain in Comments ifnecessary. Check YES or NO for BACH pre-screening item. [Ref. USA 50.59 Resource Manual] NOTE: If you are unsure if a document or process may be affected, contact the process owner. NOTE: An asterisk (*) indicates that the document is incorporated by reference in the USAR or is implicitly considered part ofthe USAR. NOTE: Check NO if activity/change is considered editorial, administrative, or maintenance as defmed in Attachments A, B, and C. Explain in Comments if necessary. Yes t/ No./ DocumentlProcess Directive! Procedure a 0 ~ Updated Safety Analysis Report CUSAR) NEP-05.02 b 0 ~ Technical Specifications Bases or Technical Requirements Manual (TRM) U-AA-IOl, LI-AA-I01-l001 c 0 ~ Commitments made in response to NRC Generic Letters and Bulletins, and those described in the USAR LI-AA-I10 d D ~ Environmental QUalification (EQ) Plan NAD-QI.08 e D ~ Regulatory Guide 1.97 eRG 1.97) Accident Monitoring Instromentation Plan NAD-05.22 f 0 ~ Fire Plan NAD-Ol.02 g 0 ~ Appendix. R Design Description NAD-Ol.02 h 0 ~ Fire Protection Program Analysis (FPPA) NAD-Ol.02 i 0 ~ Offsite Dose Calculation Manual (ODCM) NAD-05.l3 j 0 ~ Radiological Environmental Monitoring Manual tREMM) NAD-05.l3 "k 0 ~ Station Blackout Design Description 1 0 ~ Control Room Habitability Study 0 ~ Plant Drawing ChangeslDiscrepancies-Check YES only if: 1) the change adds information to, deletes information m from, or alters the configuration ofa drawing that is incorporated in the USAR, or 2) configures an sse NAD..05.01 differently than described or credited in USAR text. n 0 ~ CalculationslEvaluationslAnalyses/Computer Software - Check YES only if: 1) It affects a method ofevaluation Various described in the USARt or 2) It independently (Le., not part of a modification) affects the licensing or design basis. 0 0 ~ Permanent Plant Physical Changes - All require a screening. NAD-04.03 p 0 ~ Temporary Plant Physical Changes (rCRs) - Check No only ifinstalled for maintenance AND in effect for less NAD-04.03 than 90 days at power conditions. q 0 ~ QA Typing Determinations ~ Check YES only ifreduction in classification, or affects design function as described NAn-OI.Ol in USAR. r 0 ~ Setpoint or Acceptance Criteria - Check YES only ifchange affects plant monitoring, performance) or operation. Various s 0 ~ PlantProcedureslRevisions - Check YES only ifthe change directly or indirectly involves operating, controlling NAD-03.01 or configuring an sse differently than described or credited in USAR. t D ~ Engineering Specifications - Check YES only if a design function or design requirement may be affected. NAn-OS.03 u 0 ~ Operations Night Orders or Operator Work Arounds - Check YES only ifSSCs are operated or configured GNP-03.30.01 differently than described in USAR. NAD-08.14, 0 ~ Temporary plant alterations (e.g., jumpers, scaffolding, shielding, barriers) - Check YES only ifinstalled (or in GMP-127, v effect) for m~ntenance for longer than 90 days at power conditions. GNP-01.23.04, FPP-08-09 w 0 ~ Temporary plant alterations - Check YES only if not associated with maintenance. x 0 ~ Corrective/Compensatory Actions - Check YES only if degraded/non-conforming plant condition accepted "as-is" OP-AA-I02 or compensatory action taken. Ib-ltI-tJ9 Date: Date: lD. Desrochers Andrew W. Baugus 4 Conclusion. Check one ofthe following: ~ All ofthe documents or processes listed above are checked NO. A 50.59 screening is NOT required. Process change in accordance with the applicable prograrnlprocesslprocedure~ o .One or more ofthe documents or processes listed above are checked YES. A 50.59 screening shall be performed. 5 Comments: ET-CEE-09-0009, Rev. 0 will transmit the 50.59/72.48 Evaluation and program/document updates. 6 Print name followed by signature. Either the preparer or reviewer shall be 50.59 screening qualified. Attach completed form to document/activity/change package. Prepared by: (print/sign) Reviewed by: (print/sign) I:nrnt ~NP_nl1 nl1 01.? RO\\f 1?}}