ML091410123: Difference between revisions

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| number = ML091410123
| number = ML091410123
| issue date = 05/06/2009
| issue date = 05/06/2009
| title = Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass
| title = Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass
| author name = Kolodziejczyk E
| author name = Kolodziejczyk E
| author affiliation = Northern States Power Co, Xcel Energy
| author affiliation = Northern States Power Co, Xcel Energy
Line 20: Line 20:
=Text=
=Text=
{{#Wiki_filter:QF-2116, Rev 3 (FP-G-RM-01)
{{#Wiki_filter:QF-2116, Rev 3 (FP-G-RM-01)
Page 1 of 2...... ......RECORD INFORMATION SHEET Doc Type/Sub Type: CALC Document Number: 96-054 R5 Title: Turbine Stop ValveClosurelGenerator Load Reject Scram Bypass F1 1. The following record has been identified as either illegible on microfilm or identified as uncertain whether it will be legible on microfilm.
Page 1 of 2 RECORD INFORMATION SHEET Doc Type/Sub Type:
A copy has been filmed for "reference only" and the originals are maintained in hard copy.F- 2. The following record has illegible or missing information that has been reviewed and deemed the "best available copy". A member of the originating organization has signed and dated below after commenting on the illegible or missing information.
CALC Document Number:
The record will not be retained in hardcopy.F] 3. The following record or item is stored in hard copy due to inability to transfer to microfilm.
96-054 R5
[ 4. The following calculation and attachments have been reviewed and deemed acceptable as legible as a QA record.Pages / Items Description I Comments Print/Sign:
 
Au CM. LF-x / A Date: 0S" 1 1Form retained in accordance with record rete n schedule identified in FP-G-RM-01.
==Title:==
QF-0549 (FP-E-CAL-01)
Turbine Stop ValveClosurelGenerator Load Reject Scram Bypass F1 1. The following record has been identified as either illegible on microfilm or identified as uncertain whether it will be legible on microfilm. A copy has been filmed for "reference only" and the originals are maintained in hard copy.
Rev. 3 Paae 1 of 6~XceEnergT Calculation Signature Sheet Document Information NSPM Calculation (Doc) No: TRevision:
F-2. The following record has illegible or missing information that has been reviewed and deemed the "best available copy". A member of the originating organization has signed and dated below after commenting on the illegible or missing information. The record will not be retained in hardcopy.
Title: Facility:
F] 3. The following record or item is stored in hard copy due to inability to transfer to microfilm.
0 MT E-I PI Unit: 0 1 El2 Safety Class: Z SR El Aug Q El Non SR Special Codes: E] Safeguards El Proprietary Type: Calc Sub-Type: I-NOTE: LPrint and sign name in signature blocks, as required.ajor.RevisionsZ6 EC I'.,2Z [] Vendor Cale Vendor Name or Code: Sargent & Lundy Vendor Doc No: De iDtion of in: Prepared by: RE M Date: Reviewed by: -(,. .) Date: 0_--o -0 7 Type of Review: E] Design Verification El Tech Review(f Vendor Acce Method Used (For DV only ) ReMR iew Alternate Calc Fl Test Approved by: ,Date:. 1 Minor Revisions EC No: 7E []Vendor Calc: Minor Rev. No: Description of Change: Pages Affected: Prepared by: Date: Reviewed by: j Date: Type of Review: El Design Verification El Tech Review El Vendor Acceptance Method Used (For DVbOnly):
[
El Review [l Alternate Calc E] Test Approved by: Date: (continued on next page)Record Retention:
: 4. The following calculation and attachments have been reviewed and deemed acceptable as legible as a QA record.
Retain this form with the associated calculation for the life of the plant.
Pages / Items Description I Comments Print/Sign: Au CM. LF-x  
QF-0549 (FP-E-CAL-01), Rev. 3 Page 2 of 6 XcelEnergy" Calculation Signature Sheet EC No: El [vendor Calc: Minor Rev. No: Description of Change: Pages Affected: Prepared by: Date: Reviewed by:/ Date: Type of Review: EI Design Verification Ei Tech Review -- Vendor Acceptance Method Used (For DV Only): E] Review L] Alternate Calc EL Test Approved by: Date: EC No: i [Vendor Caic: Minor Rev. No: Description of Change: Pages Affected: Prepared by: Date: Reviewed by: Pate: Type of Review: EL Design Verification Li Tech Review [] Vendor Acceptance Method Used (For DV Only): Li Review EL Alternate Calc Li Test Approved by: FDate:J EC No: il Vendor Calc:
/
Minor Rev. No: Description of Change: Pages Affected: Prepared by: Date: Reviewed by: Date, Type of Review: EL Design Verification L] Tech Review L] Vendor Acceptance Method Used (For DV Only): L] Review EL Alternate Calc Li Test Approved by: I Date: Record Retention:
A
Retain this form with the associated calculation for the life of the plant.
_,ý*
NOTE: This reference table is used for data entry into the PassPort Controlled Documents Module, reference tables (C012 Panel). It may also be used as the reference section of the calculation.
Date: 0S"1 1*
The input documents, output documents and other references should all be listed here. Add additional lines as needed.Reference Documents (PassPort C012 Panel from C020)# Controlled*
Form retained in accordance with record rete n schedule identified in FP-G-RM-01.
Document Name Document Number Doc Ref Type**Doc? + Type Rev (if known)I -General Electric Instrument Setpoint Methodology NEDC-31336P-A 1996 ]lnput L--]Output 2L-- GE-NE-901-021-  
 
;input El-Output Setpoint Calculation Guidelines for the Monticello 0492 Nuclear Generating Plant DRF A0001 932-1 3 F] Guidelines for Instrument Calibration TR-1 03335-Rl iinput l:]Output Extension/Reduction Programs -4 F-1 Task Report T0502, Nuclear Management Company i]nput Loutput Monticello Nuclear Generating Plant Extended Power T0502 Uprate 5 Monticello Updated Safety Analysis Report. Plant USAR-07.06 25P Zinput [:IOutput Instrumentation and Control Systems: Plant Protection System 6 Operations Manual B.05.06. Plant Protection System B.05.06 lnput Llutput 7 F- Generic Letter 91-04, Changes in Technical Zlnput E]OutputSpecification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle 8 [] Elnput D-loutput 10 Fl [:]input [:]output 11 F_ r--linput Doutput 12W r- _3lnput Woutput Record Retention:
QF-0549 (FP-E-CAL-01) Rev. 3 Paae 1 of 6
Retain this form with the associated calculation for the life of the plant.
~XceEnergT Calculation Signature Sheet Document Information NSPM Calculation (Doc) No:
13 Wl -]Input Eji]Output 14 WInput W-Output 15 WlInput [-]Output 16 I-E _]Input [:]Output 17 E--_ -]Ilnput -]Output*Controlled Doc checkmark means the reference can be entered on the C012 panel in black. Unchecked lines will be yellow. If checked, also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.)
TRevision:
**Corresponds to these PassPort "Ref Type" codes: Inputs/Both  
 
= ICALC, Outputs = OCALC, Other/Unknown  
==Title:==
= blank)Other PassPort Data Associated System (PassPort C011, first three columns) OR Equipment References (PassPort C025, all five columns): Facility Unit System Equipment Type Equipment Number PREASURE PS-5-14A/B/C/D SWITCHES Superseded Calculations (PassPort C01 9): Facility Calc Document Number Title MT CA-96-054 Rev. 4 TURBINE STOP VALVE CLOSURE/GENERATOR LOAD REJECT SCRAM BYPASS SETPOINT CALCULATION Record Retention: Retain this form with the associated calculation for the life of the plant.
Facility: 0 MT E-I PI Unit: 0 1 El2 Safety Class:
Monticello Specific Information IZ DBD Topic Code(s) (See MT Form 3805): RATE F-1 DBD Structural Code(s) (See MT Form 3805): Does the Calculation:
Z SR El Aug Q El Non SR Special Codes: E] Safeguards El Proprietary Type: Calc Sub-Type:
F1 YES Z No Affect the Fire Protection Program? (If Yes, Attach MT Form 3765)[I YES [9 No Affect piping or supports? (If Yes, Attach MT Form 3544)El YES .Z No Affect IST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation)
I-NOTE:
LPrint and sign name in signature blocks, as required.
ajor.RevisionsZ6 EC Number4*4 I'.,2Z
[] Vendor Cale Vendor Name or Code:
Sargent & Lundy Vendor Doc No:
De iDtion of in:
Prepared by: RE M Date:
Reviewed by:
(,.  
)
Date: 0_--o -0 7 Type of Review: E] Design Verification El Tech Review(f Vendor Acce Method Used (For DV only )
ReMR iew Alternate Calc Fl Test Approved by:  
,Date:.
6--*--
1 Minor Revisions EC No:
7E
[]Vendor Calc:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:
j Date:
Type of Review: El Design Verification El Tech Review El Vendor Acceptance Method Used (For DVbOnly): El Review [l Alternate Calc E] Test Approved by:
Date:
(continued on next page)
Record Retention: Retain this form with the associated calculation for the life of the plant.
 
QF-0549 (FP-E-CAL-01), Rev. 3 Page 2 of 6 XcelEnergy" Calculation Signature Sheet EC No:
El
[vendor Calc:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:/
Date:
Type of Review: EI Design Verification Ei Tech Review -- Vendor Acceptance Method Used (For DV Only): E] Review L] Alternate Calc EL Test Approved by:
Date:
EC No:
i [Vendor Caic:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:
Pate:
Type of Review: EL Design Verification Li Tech Review [] Vendor Acceptance Method Used (For DV Only): Li Review EL Alternate Calc Li Test Approved by:
FDate:J EC No:
il Vendor Calc:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:
: Date, Type of Review: EL Design Verification L] Tech Review L] Vendor Acceptance Method Used (For DV Only): L] Review EL Alternate Calc Li Test Approved by:
I Date:
Record Retention: Retain this form with the associated calculation for the life of the plant.
 
NOTE:
This reference table is used for data entry into the PassPort Controlled Documents Module, reference tables (C012 Panel). It may also be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed.
Reference Documents (PassPort C012 Panel from C020)
Controlled*
Document Name Document Number Doc Ref Type**
Doc? + Type Rev (if known)
I General Electric Instrument Setpoint Methodology NEDC-31336P-A 1996  
]lnput L--]Output 2L--
GE-NE-901-021-  
;input El-Output Setpoint Calculation Guidelines for the Monticello 0492 Nuclear Generating Plant DRF A0001 932-1 3
F]
Guidelines for Instrument Calibration TR-1 03335-Rl iinput l:]Output Extension/Reduction Programs -
4 F-1 Task Report T0502, Nuclear Management Company i]nput Loutput Monticello Nuclear Generating Plant Extended Power T0502 Uprate 5
Monticello Updated Safety Analysis Report. Plant USAR-07.06 25P Zinput [:IOutput Instrumentation and Control Systems: Plant Protection System 6
Operations Manual B.05.06. Plant Protection System B.05.06 lnput Llutput 7
F-Generic Letter 91-04, Changes in Technical Zlnput E]Output Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle 8
[]
Elnput D-loutput 10 Fl
[:]input [:]output 11 F_
r--linput Doutput 12W r-
_3lnput Woutput Record Retention: Retain this form with the associated calculation for the life of the plant.
 
13 Wl  
-]Input Eji]Output 14 WInput W-Output 15 WlInput [-]Output 16 I-E
_]Input
[:]Output 17 E--_  
-]Ilnput -]Output
*Controlled Doc checkmark means the reference can be entered on the C012 panel in black. Unchecked lines will be yellow. If checked, also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.)
**Corresponds to these PassPort "Ref Type" codes: Inputs/Both = ICALC, Outputs = OCALC, Other/Unknown = blank)
Other PassPort Data Associated System (PassPort C011, first three columns)
OR Equipment References (PassPort C025, all five columns):
Facility Unit System Equipment Type Equipment Number PREASURE PS-5-14A/B/C/D SWITCHES Superseded Calculations (PassPort C01 9):
Facility Calc Document Number Title MT CA-96-054 Rev. 4 TURBINE STOP VALVE CLOSURE/GENERATOR LOAD REJECT SCRAM BYPASS SETPOINT CALCULATION Record Retention: Retain this form with the associated calculation for the life of the plant.
 
Monticello Specific Information IZ DBD Topic Code(s) (See MT Form 3805):
RATE F-1 DBD Structural Code(s) (See MT Form 3805): #*j Does the Calculation:
F1 YES Z No Affect the Fire Protection Program? (If Yes, Attach MT Form 3765)
[I YES
[9 No Affect piping or supports? (If Yes, Attach MT Form 3544)
El YES. Z No Affect IST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation)
Record Retention: Retain this form with the associated calculation for the life of the plant.
Record Retention: Retain this form with the associated calculation for the life of the plant.
QF-0547 (FP-E-MOD-11)
 
Rev. 1[ _ XceIEnergy" External Design Document Suitability Review Checklist External Design Document Being Reviewed:
QF-0547 (FP-E-MOD-11) Rev. 1
Title: ..f.... I ...t e t c Number: &: I e. Rev: Date: ____/_L__This design document was received from: Organization Name: Sargent  
[ _ XceIEnergy" External Design Document Suitability Review Checklist External Design Document Being Reviewed:
& Lundy PO or DIA  
 
==Title:==
f....  
"a-e*sI I
t e t c
Number:
I e.
Rev:
* Date:
____/_L__
This design document was received from:
Organization Name:
Sargent & Lundy PO or DIA  


==Reference:==
==Reference:==
The purpose of the suitability review is to ensure that a calculation, analysis or other design document provided by an External Design Organization complies with the conditions of the purchase order and/or Design Interface Agreement (DIA) and is appropriate for its intended use. The suitability review does not serve as an independent verification. Independent verification of the design document supplied by the External Design Organization should be evident in the document, if required.
The reviewer should use the criteria below as a guide to assess the overall quality, completeness and usefulness of the design document. The reviewer is not required to check calculations in detail.
REVIEW Check
: 1.
Design inputs correspond to those that were transmitted to the External Design Organization.
: 2.
Assumptions are described and reasonable.
: 3.
Applicable codes, standards and regulations are identified and met.
: 4.
Applicable construction and operating experience is considered.
: 5.
Applicable structure(s), system(s), and component(s) are listed.
H;
: 6.
Formulae and equations are documented. Unusual symbols are defined.
EIr
: 7.
Acceptance criteria are identified, adequate and satisfied.
: 8.
Results are reasonable compared to inputs.
: 9.
Source documents are referenced.
: 10.
The document is appropriate for its intended use.
: 11.
The document complies with the terms of the Purchase Order and/or DIA.
: 12.
Inputs, assumptions, outputs, etc. which could affect plant operation are enforced
?
by adequate procedural controls. List any affected procedures. 0 *,*-d2
: 13.
Plant impact has been identified and either implemented or controlled. (e.g., For piping analyses, the piping and support database is updated or a tracking item has been initiated.)
Completed by:
_Date:
6---6I -o 2
Page 1 of 1


The purpose of the suitability review is to ensure that a calculation, analysis or other design document provided by an External Design Organization complies with the conditions of the purchase order and/or Design Interface Agreement (DIA) and is appropriate for its intended use. The suitability review does not serve as an independent verification.
Calculation no. 96-054 TABLE OF CONTENTS Item QF-0549 QF-0547 TOC SOP-0402-07 Calculation Attachment Attachment Attachment Attachment Attachment Description Calculation Signature Sheet External Design Document Suitability Review Checklist Table of Contents S & L Issue Summary Body Pages 6
Independent verification of the design document supplied by the External Design Organization shouldbe evident in the document, if required.The reviewer should use the criteria below as a guide to assess the overall quality, completeness and usefulness of the design document. The reviewer is not required to check calculations in detail.REVIEW Check 1. Design inputs correspond to those that were transmitted to the External Design Organization.
1 1
: 2. Assumptions are described and reasonable.
2 3
: 3. Applicable codes, standards and regulations are identified and met.4. Applicable construction and operating experience is considered.
4 5
: 5. Applicable structure(s), system(s), and component(s) are listed. H;6. Formulae and equations are documented. Unusual symbols are defined. EIr 7. Acceptance criteria are identified, adequate and satisfied.
1 16 222 3
: 8. Results are reasonable compared to inputs.9. Source documents are referenced.
1 1
: 10. The document is appropriate for its intended use.11. The document complies with the terms of the Purchase Order and/or DIA.12. Inputs, assumptions, outputs, etc. which could affect plant operation are enforced ?by adequate procedural controls.
Total pages 54 I1
List any affected procedures.
0 -13. Plant impact has been identified and either implemented or controlled. (e.g., For piping analyses, the piping and support database is updated or a tracking item has been initiated.)
Completed by: _ __________ _ _ _Date:
6---6I -o 2 Page 1 of 1 Calculation no. 96-054 TABLE OF CONTENTS Item QF-0549 QF-0547 TOC SOP-0402-07 Calculation Attachment Attachment Attachment


Attachment Attachment Description Calculation Signature Sheet External Design Document Suitability Review Checklist Table of Contents S & L Issue Summary Body Pages 6 1 1 2 3 4
ISSUE  
5 1 16 22 2 3 1 1 Total pages 54 I1 ISSUE  


==SUMMARY==
==SUMMARY==
Line 72: Line 218:


==SUMMARY==
==SUMMARY==
CLIENT: Northern States Power Company UNIT NO.: 1 Page No.: 1 PROJECT NAME: Monticello Nuclear Generating Plant PROJECT NO.: 12400-009 Z NUCLEAR SAFETY-RELATED CALC. NO.: CA-96-054, Revision 5 El NOT NUCLEAR SAFETY-RELATED TITLE: Turbine Stop Valve Closure/Generator Load Reject Scram Bypass EQUIPMENT NO.: PS-5-14A,B,C,D IDENTIFICATION OF PAGES ADDED/REVISED/SUPERSEDEDNOIDED & REVIEW METHODThis revision completely supersedes Revision 4INPUTS/ ASSUMPTIONS El VERIFIED M UNVERIFIED REVIEW METHOD: Detailed REV. 5 STATUS:' Approved DATE FOR REV.: 4/21)2009 PREPARER Eric Kolodziejczyk  
CLIENT:
.44 --DATE: 4/21/2009 REVIEWER John O'Hara / Greg Rainey " -/ -DATE: 4/21/2009 APPROVER Steven Malak DATE: 4/21/2009 IDENTIFICATION OF PAGES ADDED/REVISEOD/SUPERSEIDED/VOIDED &REVIEW METHOD INPUTS1 ASSUMPTIONS El VERIFIED Dl UNVERIFIED REVIEW METHOD; REV.STATUS: DATE FOR REV.: PREPARER DATE: REVIEWER DATE: APPROVER DATE: IDENTIFICATION OF PAGES ADDED/REVISED/SUPERSEDEDNVOIDED & REVIEW METHOD INPUTS/ ASSUMPTIONS El VERIFIED El UNVERIFIED REVIEW METHOD: REV.STATUS: .DATE FOR REV,: PREPARER DATE: REVIEWER DATE: APPROVER DATE:NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS SOP040207,DOC Page 1 of 1Rev. Date:
Northern States Power Company UNIT NO.:
11-12-2007 (I' MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 1 of 16 1. PURPOSE This calculation performs.
1 Page No.: 1 PROJECT NAME:
a setpoint calculation for the turbine stop valve closure and generator load reject scram bypass signal provided by pressure switches PS-5-14A/B/C/D.
Monticello Nuclear Generating Plant PROJECT NO.:
This calculation affects the Reactor, Protection System and ensures that above Pbypass (Input 4.7)reactor thermal power the scram bypass signal is deactivated.
12400-009 Z
Revision 5 of this calculation updates the analyzed drift values to reflect the current 24-month calibration interval.Revision 4 of this calculation reflects turbine replacement for both EPU (Extended Power Uprate) and CLTP (Current Licensed Thermal Power) and adjusts the operation setpoint to reflect the new turbine first stage pressure curve. Additionally, revisions are incorporated to meet the current setpoint control program standards with the guidance of ESM-03.02-APP-I (Input 4.1).Revision 3 of this calculation reflected the results of turbine testing during startup from the 1998 refueling outage and adjusts the setpoints for the higher steam flow/lst stage turbine pressure resulting from rerate.2. METHODOLOGY This calculation is performed using the GE Setpoint Methodology as a guide as described in Appendix I to Engineering Standards Manual Section ESM-03.02, Revision 4, Design Requirements, Practices, & Topics (Instrumentation and Controls) (Input 4.1). This methodology utilizes statistical estimates of the various instrument errors to achieve conservative, but reasonable, predictions of instrument channel uncertainties.
NUCLEAR SAFETY-RELATED CALC. NO.:
The objective of the statistical approach to setpoint calculations is to achieve a workable compromise between the need to ensure instrument trips when appropriate, and the need to avoid spurious trips that may unnecessarily challenge safety systems or disrupt plant operation.
CA-96-054, Revision 5 El NOT NUCLEAR SAFETY-RELATED TITLE:
The setpoint established in this calculation is considered a non-safety related setpoint.
Turbine Stop Valve Closure/Generator Load Reject Scram Bypass EQUIPMENT NO.:
An Analytical Limit and Allowable Value (Tech Spec value) are typically only associated with safety-related setpoints.
PS-5-14A,B,C,D IDENTIFICATION OF PAGES ADDED/REVISED/SUPERSEDEDNOIDED & REVIEW METHOD This revision completely supersedes Revision 4 INPUTS/ ASSUMPTIONS El VERIFIED M UNVERIFIED REVIEW METHOD:
The GE methodology does not clearly discuss the treatment of -non-safety-related setpoints; however, the MNGP methodology states that the Allowable'Value calculation does not apply to setpoints for which an AV is not documented in the Tech Spec.The previous revision of this calculation establishes an Analytical Limit and calculates.
Detailed REV.
an Allowable Value. Therefore, this calculation will retain the AL terminology and AVcalculatipn.
5 STATUS:'
Per Input 4.1, the Spurious Trip Avoidance Evaluation is satisfied using engineering judgment.See Section 6.5.8 for more details.M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Genbrator Load Reject Revision 5 ScrarnBypass Page 2 of 16 The determination of the pressure switch drift value used in this calculation is performed in accordance with ESM-03.02-APP-lIl (Input 4.2).3. ACCEPTANCE CRITERIA The Nominal Trip Setpoint (NTSP), Allowable Value (AV) and instrument settings should be established such that the Analytical Limit will not be exceeded when all applicable instrumentation uncertainties are considered.
Approved DATE FOR REV.:
The existing setpoints and As-found/As-left ranges will be verified to provide sufficient margin using the GE methodology as a guide. A setpoint value will be established with a 95%/95% tolerance interval as a criteria of uncertainties (Input 4.2). That is, there is a 95% probability that the constructed limits contain 95% of the population of interest for a 24-month +25% calibration interval (Reference 10.7) for the pressure switches.
4/21)2009 PREPARER Eric Kolodziejczyk  
If the existing setpoint and ranges do not provide sufficient margin, new setpoints or ranges will be specified by this calculation.
.44 DATE:
: 4. INPUTS 4.1 Engineering Standards Manual ESM-03.02-APP-I, Revision 4, GE Methodology (Instrumentation and Controls).
4/21/2009 REVIEWER John O'Hara / Greg Rainey "  
The ESM provides plantspecific guidance on the implementation of the General Electric methodology (Reference 10.1) and guidelines (Reference 10.2).4.2 Engineering Standards Manual ESM-03.02-APP-Ill, Revision 5, Drift Analysis (Instrumentation and Controls).
/
The. ESM provides .plant specific guidance on the implementation of the EPRI guidelines on drift analysis (Reference 10.3).95%/95% Tolerance Factor for 44 data points 2.445 (Table 9.1)99%/95% Tolerance Factor for 44 data points 2.677 (Table 9.1)4.3 Monticello Component Master List (CML). The CML contains information regarding-the pressure switches and calibration tools listed in this calculation.
DATE:
Device Calibration Interval PS-5-14A,B,C,D 24 months Calibration Device Description XPI-9021 Ashcroft 2089 XPS-95171 L Mansfield and Green TQ-50 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 3 of 16 4.4 Calculation CA-98-010, Revision 6, Environmental Qualification (DOR) of Barksdale Pressure Switches.
4/21/2009 APPROVER Steven Malak DATE:
EQ Calculation File 0910-106EQ-05.
4/21/2009 IDENTIFICATION OF PAGES ADDED/REVISEOD/SUPERSEIDED/VOIDED  
&REVIEW METHOD INPUTS1 ASSUMPTIONS El VERIFIED Dl UNVERIFIED REVIEW METHOD; REV.
STATUS:
DATE FOR REV.:
PREPARER DATE:
REVIEWER DATE:
APPROVER DATE:
IDENTIFICATION OF PAGES ADDED/REVISED/SUPERSEDEDNVOIDED & REVIEW METHOD INPUTS/ ASSUMPTIONS El VERIFIED El UNVERIFIED REVIEW METHOD:
REV.
STATUS:
DATE FOR REV,:
PREPARER DATE:
REVIEWER DATE:
APPROVER DATE:
NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS SOP040207,DOC Page 1 of 1 Rev. Date: 11-12-2007 (I'


===4.5 Calculation===
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 1 of 16
: 1.
PURPOSE This calculation performs. a setpoint calculation for the turbine stop valve closure and generator load reject scram bypass signal provided by pressure switches PS-5-14A/B/C/D. This calculation affects the Reactor, Protection System and ensures that above Pbypass (Input 4.7) reactor thermal power the scram bypass signal is deactivated.
Revision 5 of this calculation updates the analyzed drift values to reflect the current 24-month calibration interval.
Revision 4 of this calculation reflects turbine replacement for both EPU (Extended Power Uprate) and CLTP (Current Licensed Thermal Power) and adjusts the operation setpoint to reflect the new turbine first stage pressure curve. Additionally, revisions are incorporated to meet the current setpoint control program standards with the guidance of ESM-03.02-APP-I (Input 4.1).
Revision 3 of this calculation reflected the results of turbine testing during startup from the 1998 refueling outage and adjusts the setpoints for the higher steam flow/lst stage turbine pressure resulting from rerate.
: 2.
METHODOLOGY This calculation is performed using the GE Setpoint Methodology as a guide as described in Appendix I to Engineering Standards Manual Section ESM-03.02, Revision 4, Design Requirements, Practices, & Topics (Instrumentation and Controls) (Input 4.1). This methodology utilizes statistical estimates of the various instrument errors to achieve conservative, but reasonable, predictions of instrument channel uncertainties. The objective of the statistical approach to setpoint calculations is to achieve a workable compromise between the need to ensure instrument trips when appropriate, and the need to avoid spurious trips that may unnecessarily challenge safety systems or disrupt plant operation.
The setpoint established in this calculation is considered a non-safety related setpoint. An Analytical Limit and Allowable Value (Tech Spec value) are typically only associated with safety-related setpoints. The GE methodology does not clearly discuss the treatment of -non-safety-related setpoints; however, the MNGP methodology states that the Allowable'Value calculation does not apply to setpoints for which an AV is not documented in the Tech Spec.
The previous revision of this calculation establishes an Analytical Limit and calculates. an Allowable Value. Therefore, this calculation will retain the AL terminology and AVcalculatipn.
Per Input 4.1, the Spurious Trip Avoidance Evaluation is satisfied using engineering judgment.
See Section 6.5.8 for more details.
M/cah


CA-95-027, Revision 1, Determination of Instruments Service Conditions for Input Into Setpoint Calculations.
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
M04230-0065.
Turbine Stop Valve Closure/Genbrator Load Reject Revision 5 ScrarnBypass Page 2 of 16 The determination of the pressure switch drift value used in this calculation is performed in accordance with ESM-03.02-APP-lIl (Input 4.2).
Data .obtained from this input is listed in Section 6.2.2.4.6 MNGP EPU Task Report T0700: EC 12473, Letter GE-MNGP-AEP-196, 1 st Stage Shell Pressure curve, dated August 1, 2007 (Attachment 3).% Rated Thermal Power (Input 4.7)__ 1st Stage Shell Pressure 25% (EPU) 28.2% (CLTP) 140.0 psia (125.3 psig)4.7 MNGP EPU Task Report T0900: Transient Analysis EC11830. GE-NE-0000-0062-2932 OPL-3, Transient Protection Parameters Verification for Reload Licensing Analysis.Parameter CLTP EPU Rated Power 1775 MWt 2004 MWt Pbypass 45% RTP 40% RTP 4.8 Memo from John Hess (GE) to Jim Devine (MNGP) dated March 15, 1996 (Attachment 4).4.9 MNGP EPU Task Report T1004: Environmental Qualification EC11836, Rev. 0. March 2008. This Input demonstrates environmental conditions used in the evaluation of Inputs 4.4 and 4.5 will not change due to EPU.4.10 NX-63626, Ashcroft Digital Test Gauge Operating Instructions.
: 3.
4.11 Calibration Device Range Accuracy XPI-9021 (Ashcroft 2089) 0-500 psig 0.05% Full Scale NX-17448, Mansfield and Green Pneumatic Dead Weight Tester.Calibration Device Range Accuracy XPS-95171 (Mansfield and Green TQ-50) 100-5000 psig 0.025% Reading M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 4 of 16 5. ASSUMPTIONS Validated Assumptions:
ACCEPTANCE CRITERIA The Nominal Trip Setpoint (NTSP), Allowable Value (AV) and instrument settings should be established such that the Analytical Limit will not be exceeded when all applicable instrumentation uncertainties are considered. The existing setpoints and As-found/As-left ranges will be verified to provide sufficient margin using the GE methodology as a guide. A setpoint value will be established with a 95%/95% tolerance interval as a criteria of uncertainties (Input 4.2). That is, there is a 95% probability that the constructed limits contain 95% of the population of interest for a 24-month +25% calibration interval (Reference 10.7) for the pressure switches. If the existing setpoint and ranges do not provide sufficient margin, new setpoints or ranges will be specified by this calculation.
5.1 The GE memo from John Hess to Jim Devine of MNGP (Attachment  
: 4.
: 4) cites a 3%process measurement uncertainty based on unexpected changes in flow coefficients
INPUTS 4.1 Engineering Standards Manual ESM-03.02-APP-I, Revision 4, GE Methodology (Instrumentation and Controls). The ESM provides plantspecific guidance on the implementation of the General Electric methodology (Reference 10.1) and guidelines (Reference 10.2).
*and tolerances on machining.
4.2 Engineering Standards Manual ESM-03.02-APP-Ill, Revision 5, Drift Analysis (Instrumentation and Controls). The. ESM provides.plant specific guidance on the implementation of the EPRI guidelines on drift analysis (Reference 10.3).
The memo discusses tolerances prior to EPU. However, the tolerances on machining are not dependant on pressure or flow. Therefore, this process measurement uncertainty is assumed to remain applicable at EPU. conditions.
95%/95% Tolerance Factor for 44 data points 2.445 (Table 9.1) 99%/95% Tolerance Factor for 44 data points 2.677 (Table 9.1) 4.3 Monticello Component Master List (CML). The CML contains information regarding-the pressure switches and calibration tools listed in this calculation.
5.2 No seismic data is available for the Barksdale Switches.
Device Calibration Interval PS-5-14A,B,C,D 24 months Calibration Device Description XPI-9021 Ashcroft 2089 XPS-95171 L Mansfield and Green TQ-50 M/cah
Per Input 4.5, the Zero Period Acceleration at the switches is 0.26g. This value is low enough to consider normal vibration effects negligible.
 
Therefore, SE is taken to be 0.5.3 Error effects due to Static Pressure Effects (SPE), typically associated with differential pressure instruments, are assumed negligible for Gauge pressure instruments since ambient pressure is considered constant.5.4 No vendor specification is available for Accuracy Temperature Effect (ATE). ATE will be considered included in the vendor accuracy.
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Since normal temperature range is within the vendor specified temperature limits, effects due to normal temperature variations are considered to be included in the Analyzed Drift.5.5 The Readability Error associated with reading the impulse pressure curve in Attachment 3 is taken to be one quarter of one minor division.Unvalidated Assumptions:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 3 of 16 4.4 Calculation CA-98-010, Revision 6, Environmental Qualification (DOR) of Barksdale Pressure Switches. EQ Calculation File 0910-106EQ-05.
5.6 The first stage pressure and thermal power relationship according to Input 4.6 needs to be validated during start-up testing.Note: The percent power relationship given in Attachment 3 assumes that the reactor is providing steam to the turbine and that other auxiliary steam loads are not significantly affecting thermal power. This may require procedural changes to assure that auxiliary steam loads are secured during.start up testing....
4.5 Calculation CA-95-027, Revision 1, Determination of Instruments Service Conditions for Input Into Setpoint Calculations. M04230-0065. Data.obtained from this input is listed in Section 6.2.2.
M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 5 of 16 6. ANALYSIS 6.1 Instrument Channel Arrangement 6.1.1 Loop Information:
4.6 MNGP EPU Task Report T0700: EC 12473, Letter GE-MNGP-AEP-196, 1st Stage Shell Pressure curve, dated August 1, 2007 (Attachment 3).
Definition of Channel: Each instrument channel is comprised of a turbine first stage pressure switch and an associated relay. Each relay provides input to the Reactor Protection System (RPS)scram logic in order to bypass scrams initiated by turbine stop valve closure and control valve fast closure during low reactor power conditions.
% Rated Thermal Power (Input 4.7)__
At these low reactor power conditions, the turbine bypass valves have sufficient capacity to bypass the steam without increasing reactor vessel pressure to unsafe levels. The bypass signal logic is two out of two once. The reactor power level associated with the bypass signal is established at the same thermal power as prior to EPU (30% of 1775 MWt). This corresponds to an EPU reactor power of 26.6% at 2004 MWt. However, the Analytical Limit will be taken as a more conservative 25% reactor power (28.2%
1st Stage Shell Pressure 25% (EPU) 28.2% (CLTP) 140.0 psia (125.3 psig) 4.7 MNGP EPU Task Report T0900: Transient Analysis EC11830. GE-NE-0000-0062-2932 OPL-3, Transient Protection Parameters Verification for Reload Licensing Analysis.
CLTP) for the purposes of this calculation.
Parameter CLTP EPU Rated Power 1775 MWt 2004 MWt Pbypass 45% RTP 40% RTP 4.8 Memo from John Hess (GE) to Jim Devine (MNGP) dated March 15, 1996 (Attachment 4).
Once the switch pressure setpoint is exceeded, the scram bypass signal is deactivated.
4.9 MNGP EPU Task Report T1004: Environmental Qualification EC11836, Rev. 0. March 2008. This Input demonstrates environmental conditions used in the evaluation of Inputs 4.4 and 4.5 will not change due to EPU.
The scram bypass signal is reactivated on decreasing reactor power, once the switch reset limit has been reached.
4.10 NX-63626, Ashcroft Digital Test Gauge Operating Instructions.
4.11 Calibration Device Range Accuracy XPI-9021 (Ashcroft 2089) 0-500 psig 0.05% Full Scale NX-17448, Mansfield and Green Pneumatic Dead Weight Tester.
Calibration Device Range Accuracy XPS-95171 (Mansfield and Green TQ-50) 100-5000 psig 0.025% Reading M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 4 of 16
: 5.
ASSUMPTIONS Validated Assumptions:
5.1 The GE memo from John Hess to Jim Devine of MNGP (Attachment 4) cites a 3%
process measurement uncertainty based on unexpected changes in flow coefficients
*and tolerances on machining. The memo discusses tolerances prior to EPU. However, the tolerances on machining are not dependant on pressure or flow. Therefore, this process measurement uncertainty is assumed to remain applicable at EPU. conditions.
5.2 No seismic data is available for the Barksdale Switches. Per Input 4.5, the Zero Period Acceleration at the switches is 0.26g. This value is low enough to consider normal vibration effects negligible. Therefore, SE is taken to be 0.
5.3 Error effects due to Static Pressure Effects (SPE), typically associated with differential pressure instruments, are assumed negligible for Gauge pressure instruments since ambient pressure is considered constant.
5.4 No vendor specification is available for Accuracy Temperature Effect (ATE). ATE will be considered included in the vendor accuracy. Since normal temperature range is within the vendor specified temperature limits, effects due to normal temperature variations are considered to be included in the Analyzed Drift.
5.5 The Readability Error associated with reading the impulse pressure curve in Attachment 3 is taken to be one quarter of one minor division.
Unvalidated Assumptions:
5.6 The first stage pressure and thermal power relationship according to Input 4.6 needs to be validated during start-up testing.
Note: The percent power relationship given in Attachment 3 assumes that the reactor is providing steam to the turbine and that other auxiliary steam loads are not significantly affecting thermal power. This may require procedural changes to assure that auxiliary steam loads are secured during.start up testing....
M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 5 of 16
: 6.
ANALYSIS 6.1 Instrument Channel Arrangement 6.1.1 Loop Information:
Definition of Channel:
Each instrument channel is comprised of a turbine first stage pressure switch and an associated relay. Each relay provides input to the Reactor Protection System (RPS) scram logic in order to bypass scrams initiated by turbine stop valve closure and control valve fast closure during low reactor power conditions. At these low reactor power conditions, the turbine bypass valves have sufficient capacity to bypass the steam without increasing reactor vessel pressure to unsafe levels. The bypass signal logic is two out of two once. The reactor power level associated with the bypass signal is established at the same thermal power as prior to EPU (30% of 1775 MWt). This corresponds to an EPU reactor power of 26.6% at 2004 MWt. However, the Analytical Limit will be taken as a more conservative 25% reactor power (28.2% CLTP) for the purposes of this calculation. Once the switch pressure setpoint is exceeded, the scram bypass signal is deactivated. The scram bypass signal is reactivated on decreasing reactor power, once the switch reset limit has been reached.
6.1.2 Loop Diagram:
6.1.2 Loop Diagram:
Pressure Switch elay 6.2 Instrument Definition and Determination of Device Error Terms 6.2.1 Instrument Definition:
Pressure Switch elay 6.2 Instrument Definition and Determination of Device Error Terms 6.2.1 Instrument Definition:
I Reference Component ID: PS-5-14A,B,C,D Location:
I Reference Component ID:
PS-5-14A,B,C,D Location:
East Shield Wall[(TB-951)  
East Shield Wall[(TB-951)  


===4.3 Manufacturer===
===4.3 Manufacturer===
Barksdale 4.3 Model Number:
B2T-A1 2SS 4.3 Upper Range Limit (URL):
1200 psig 4.3 Adjustable Range 50-1200 psig 4.3 M/cah


Barksdale
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
 
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 6 of.16 6.2.2 Vendor Performance Specs  
===4.3 Model===
+/-0.5% of Adfustable Range Att. 2 PS-5-14A,B,C,D:
Number: B2T-A1 2SS 4.3 Upper Range Limit (URL): 1200 psig 4.3 Adjustable Range 50-1200 psig 4.3 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 6 of .16 6.2.2 Vendor Performance Specs +/-0.5% of Adfustable Range Att. 2 PS-5-14A,B,C,D:
Input Signal Output Signal First Stage Contact Closure 4.3 Turbine Pressure at setpoint Process and Physical Interfaces:
Input Signal Output Signal First Stage Contact Closure 4.3 Turbine Pressure at setpoint Process and Physical Interfaces:
Calibration Conditions:
Calibration Conditions:
Reference Calibration Temperature Range: 65 to 90OF 4.5, 4.9 Calibration/Surveillance Interval:
Reference Calibration Temperature Range:
24 months +/-25% 4.3 Normal Plant Conditions:
65 to 90OF 4.5, 4.9 Calibration/Surveillance Interval:
24 months +/-25%
4.3 Normal Plant Conditions:
Temperature:
Temperature:
60 to 104 0 F 4.5, 4.9 Radiation:
60 to 104 0F 4.5, 4.9 Radiation:
Negligible 4.5, 4.9 Pressure:
Negligible 4.5, 4.9 Pressure:
Ambient 4.5, 4.9 Humidity:
Ambient 4.5, 4.9 Humidity:
120-100% 4.5, 4.9 Trip Environment Conditions:
120-100%
4.5, 4.9 Trip Environment Conditions:
Temperature:
Temperature:
60-104OF 4.5, 4.9 Radiation:
60-104OF 4.5, 4.9 Radiation:
Negligible 4.5, 4.9 Pressure:
Negligible 4.5, 4.9 Pressure:
Ambient 4.5, 4.9 Humidity:
Ambient 4.5, 4.9 Humidity:
100% 4.5, 4.9 Seismic ZPA: PS-5-14A/B 0.26g 4.5 PS-5-14C/D 0.24g 4.5 Process Conditions; During Calibration:
100%
Not Applicable Worst Case: Not Applicable M/cah MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE: Turbine Stop Valve ClosurelGenerator Load-Reject R 5vision5 Scram Bypass Page 7 of 16 6.2.3 Device Accuracy: Sigma Reference Vendor Accuracy:
4.5, 4.9 Seismic ZPA:
VA +/-0.5% (Full Scale) 3 Att..2, Note 1 Accuracy Temperature Effect: ATE=0.0 5.4, Note 2 Over Pressure Effect: OPE=0.0 Note 3 Static Pressure Effect: SPE=Not applicable 5.3, Note 4 Seismic Effect: SE=0.0 _ _ 5.2, Note 5 Radiation Effect: RE=Not applicable Note 6 Humidity Effect: HE=Included in VA 4.4, Note 7 Power Supply Effect: PSE=Not applicable Note 8 Radio/EM Interference REE=Not applicable Note 8 Note 1: VA=Vendor Accuracy VA = 0.5% x Full Scale VA = 0.005 x 1200 = 6.0 psig Note 2: No vendor specification is available for ATE. Accuracy temperature effect will be considered included in the vendor accuracy.
PS-5-14A/B 0.26g 4.5 PS-5-14C/D 0.24g 4.5 Process Conditions; During Calibration:
Since this instrument is not subject to a harsh environment, most of the temperature effect is considered in the Analyzed Drift.Note 3: These switches have a proof pressure of 1800 psig which exceeds the pressure that they will be exposed to. As such, Over Pressure Effect is taken to be equal to 0.Note 4: Error effects due to Static Pressure Effects (SPE) are negligible for gauge pressure instruments.
Not Applicable Worst Case:
Note 5: No seismic data is available for the Barksdale Switches.
Not Applicable M/cah
Per Input 4.5, the Zero Period Acceleration is 0.26g. This value is low enough to consider normal vibration effects negligible.
 
Note 6: Per Input 4.5, radiation dose is considered negligible for the pressure switch location.
MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE:
Therefore, Radiation Effect is considered negligible.
Turbine Stop Valve ClosurelGenerator Load-Reject R
Note 7: Per input 4.4, the Barksdale switches are Enviironmentally Qualified for a relative humidity of 100%. Therefore, Humidity Effect is considered included in the VA.M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 8 of 16 Note 8: Error effects due to Power Supply Effects (PSE) and RFI/EMI Effects (REE) are not applicable for bi-stable electro-mechanical devices (Reference 10.2)6.2.4 Device Drift: Sigma Reference I Analyzed Drift I AD=+/-23.0 psig 2 1 Attachment 1A drift analysis using instrument calibration history is included in Attachment 1 for determining the 24 month plus 25% drift.Per Section A1.8 of Attachment 1, bias will not be considered for the pressure switches.ADbias = 0.0 The random portion of the Analyzed Drift is calculated by multiplying the Standard Deviation (s) of the final data set by the 95%/95% Tolerance Interval Factor (TIF95/95) and by the normality adjustment factor (NAF): ADrandom = s x TJF9,/95 x NAF ADradoi, =8.34 x 2.445 x 1 ,Drando,, =20.4psig(23.6 months)
5vision5 Scram Bypass Page 7 of 16 6.2.3 Device Accuracy:
Sigma Reference Vendor Accuracy:
VA +/-0.5% (Full Scale) 3 Att..2, Note 1 Accuracy Temperature Effect:
ATE=0.0 5.4, Note 2 Over Pressure Effect:
OPE=0.0 Note 3 Static Pressure Effect:
SPE=Not applicable 5.3, Note 4 Seismic Effect:
SE=0.0 5.2, Note 5 Radiation Effect:
RE=Not applicable Note 6 Humidity Effect:
HE=Included in VA 4.4, Note 7 Power Supply Effect:
PSE=Not applicable Note 8 Radio/EM Interference REE=Not applicable Note 8 Note 1:
VA=Vendor Accuracy VA = 0.5% x Full Scale VA = 0.005 x 1200 = 6.0 psig Note 2:
No vendor specification is available for ATE. Accuracy temperature effect will be considered included in the vendor accuracy. Since this instrument is not subject to a harsh environment, most of the temperature effect is considered in the Analyzed Drift.
Note 3:
These switches have a proof pressure of 1800 psig which exceeds the pressure that they will be exposed to. As such, Over Pressure Effect is taken to be equal to 0.
Note 4:
Error effects due to Static Pressure Effects (SPE) are negligible for gauge pressure instruments.
Note 5:
No seismic data is available for the Barksdale Switches. Per Input 4.5, the Zero Period Acceleration is 0.26g. This value is low enough to consider normal vibration effects negligible.
Note 6:
Per Input 4.5, radiation dose is considered negligible for the pressure switch location. Therefore, Radiation Effect is considered negligible.
Note 7:
Per input 4.4, the Barksdale switches are Enviironmentally Qualified for a relative humidity of 100%. Therefore, Humidity Effect is considered included in the VA.
M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 8 of 16 Note 8:
Error effects due to Power Supply Effects (PSE) and RFI/EMI Effects (REE) are not applicable for bi-stable electro-mechanical devices (Reference 10.2) 6.2.4 Device Drift:
Sigma Reference I Analyzed Drift I AD=+/-23.0 psig 2 1 Attachment 1 A drift analysis using instrument calibration history is included in Attachment 1 for determining the 24 month plus 25% drift.
Per Section A1.8 of Attachment 1, bias will not be considered for the pressure switches.
ADbias = 0.0 The random portion of the Analyzed Drift is calculated by multiplying the Standard Deviation (s) of the final data set by the 95%/95% Tolerance Interval Factor (TIF95/95) and by the normality adjustment factor (NAF):
ADrandom = s x TJF9,/95 x NAF ADradoi, =8.34 x 2.445 x 1
,Drando,, =20.4psig (23.6 months)
The extended calibration interval of 24 months plus 25% is calculated by multiplying the random portion of the Analyzed drift by a scaling factor to extrapolate the drift uncertainty.
The extended calibration interval of 24 months plus 25% is calculated by multiplying the random portion of the Analyzed drift by a scaling factor to extrapolate the drift uncertainty.
See Section A1.9 of Attachment 1 for more detail.a d ýCIo= 20.4x 23.6 , = 23.Opsig (30 months)Analyzed Drift AD = DL = +/- 23.0 psig M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 9 of 16 6.2.5 As Left Tolerance (ALT): The suggested limit on the magnitude of the ALT per Input 4.1 is given as: ALT 2 T J(VA) + (c)2 + (CST,)Y 3 ALT 2 V(6.0)2 + (0.25)2 + (0.125)2 4.0 3 (Calibration error terms are calculated in Section 6.2.6)An ALT of up to 4.0 psi is acceptable based on the methodology suggested in Input 4.1.However, previous instrument performance (Input 4.3) suggests that a smaller ALT value is routinely achievable.
See Section A1.9 of Attachment 1 for more detail.
The existing As-Left Tolerance specified on the calibration worksheet is +/- 2.0 psi. The ALT will remain at +/- 2.0 psi.6.2.6 Device Calibration Error:
a d  
_ Value Sigma Reference Calibration Tool Error Cj: 0.25 psi 3 4.10, Note I Tool Calibration Error CiSTD: 0. 125 psi 3 4.11, Note 2 As Left Tolerance ALT: 2.0 psi 2 6.2.5 Note 1: Per Input 4.3, the Barksdale pressure switches are calibrated with XPI-9021 (Ashcroft 2089). From Input 4.10, the vendor accuracy of the Ashcroft 2089 is 0.05% of full scale. Therefore, the XPI-9021 has an accuracy of 0.25 psi at 500 psi.Calibration Device Range Accuracy Reference XPI-9021 (Ashcroft 2089) 0-500 psig 0.05% Full Scale 4.10 Note 2: Per Input 4.3, the Ashcroft 2089 is calibrated using the XPS-95171 dead weight tester. From Input 4.11, the vendor accuracy of the Mansfield and Green dead weight tester is 0.025% of output pressure.
ýCIo ADEr,,*o,, = 20.4x 23.6
Therefore, the XPS-95171 has an accuracy of 0.125 psi at 500 psi.Calibration Device Range Accuracy Reference XPS-95171 (Mansfield and Green Deadweight tester) 100-5000 psig 0.025% Reading 4.11 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 10 of 16 Since calibration term values are controlled by 100% testing they are assumed to represent 3 sigma values. Individual calibration error terms are combined using the SRSS method and normalized to a 2 sigma confidence level: CL Device I Calibration Error CL -+ / c sT2 + C7STD 2 CL + .2,j0.252 0 L 0252+0.1252  
= 23.Opsig (30 months)
+22 3 CL = 1.35psi 6.3 Determination of Primary Element Accuracy (PEA) and Process Measurement Accuracy (PMA)Attachment 4 (Input 4.8)PMA = Tolerances on machining, +/-3% of point.= +/-3% X 125.3 psig+/- +/-3.8 psi (Per Input 4.6, 25% (Section 6.1) EPU power (28.2% CLTP) corresponds to 140 psia. The conversion to gauge pressure is calculated using a 14.7 psi atmospheric pressure.
Analyzed Drift AD = DL = +/- 23.0 psig M/cah
This value is conservative for the site.)6.4 Determination of Other Error Terms The Analytical Limit in this calculation is based on a theoretical first stage shell pressure curve. The curve in Attachment 3 is readable to one quarter of the smallest division (Assumption 5.5). Therefore, the following readability error must be considered:
 
Reference REA= +/- 5 psi 4.6, 5.5 M/cah MONTICELLO NUCLEAR GENERA TINGPLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page I tof 16 6.5 Calculation of Allowable Value and Operating Setpoint 6.5.1 Allowable Value (AV): Per Section 6.1.1, the Analytical Limit corresponds to 26.6% power (EPU) or 30% power (CLTP). However, the Allowable Value will be calculated using a conservative AL of 25%power (EPU) or 28.2% power (CLTP). Per Input 4.6, this AL corresponds to a first stage pressure of 140 psia (125.3 psig). The conversion to gauge pressure is calculated using a 14.7 psi atmospheric pressure.
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
This value is conservative for the site.AV!ýAL -1.645>VA 2 +C + PMA 2 + PEA 2 + R EA 2) + bias terms AY 12 5.3 -( 2 )yJ6.0+ 1.35 + 3.8 + 25. 0')AV 118.07 AV= 118 psig 6.5.2 Nominal Trip Setpoint Calculation:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 9 of 16 6.2.5 As Left Tolerance (ALT):
NTSP 1 = At, -)A2T + C + D2 +PMA 2 +PEA 2 + PREA 2 + bias terms NTS~=15.31.645)~60  
The suggested limit on the magnitude of the ALT per Input 4.1 is given as:
+132 +2.02 +.82 +02+5.02-NTS P, = 125.3-+1.5+2  
ALT 2
+35 NTSP 1 = 105.0 6.5.3 Licensee Event Report (LER) Avoidance Evaluation:
T J(VA) + (c)2 + (CST,)Y 3
The purpose of the LER Avoidance Evaluation is to ensure that there is sufficient margin provided between the AV and the NTSP to reasonably avoid violation of the AV. For a single instrument channel a Z value of greater than 1.29 provides sufficient margin between the NTSP and the AV. Although this is a multi channel loop, a Z of 1.29 will be used for conservatism.
ALT 2 V(6.0)2 + (0.25)2 + (0.125)2 4.0 3
Therefore, NTSP 2 is calculated to provide a lower bound for the NTSP based on LER avoidance criteria.M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5Scram Bypass Page 12 of 16 Sigma(LER)=l(-A2  
(Calibration error terms are calculated in Section 6.2.6)
.+C +D. )+bias Sigma(LER)=1(J6.02  
An ALT of up to 4.0 psi is acceptable based on the methodology suggested in Input 4.1.
+ 1.352 +23.02)Sigma(LER)  
However, previous instrument performance (Input 4.3) suggests that a smaller ALT value is routinely achievable. The existing As-Left Tolerance specified on the calibration worksheet is +/- 2.0 psi. The ALT will remain at +/- 2.0 psi.
= 11.90 NTSP 2 = AV -Zx Sigma(LER)
6.2.6 Device Calibration Error:
Value Sigma Reference Calibration Tool Error Cj:
0.25 psi 3
4.10, Note I Tool Calibration Error CiSTD:
: 0. 125 psi 3
4.11, Note 2 As Left Tolerance ALT:
2.0 psi 2
6.2.5 Note 1: Per Input 4.3, the Barksdale pressure switches are calibrated with XPI-9021 (Ashcroft 2089). From Input 4.10, the vendor accuracy of the Ashcroft 2089 is 0.05% of full scale. Therefore, the XPI-9021 has an accuracy of 0.25 psi at 500 psi.
Calibration Device Range Accuracy Reference XPI-9021 (Ashcroft 2089) 0-500 psig 0.05% Full Scale 4.10 Note 2:
Per Input 4.3, the Ashcroft 2089 is calibrated using the XPS-95171 dead weight tester. From Input 4.11, the vendor accuracy of the Mansfield and Green dead weight tester is 0.025% of output pressure. Therefore, the XPS-95171 has an accuracy of 0.125 psi at 500 psi.
Calibration Device Range Accuracy Reference XPS-95171 (Mansfield and Green Deadweight tester) 100-5000 psig 0.025% Reading 4.11 M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 10 of 16 Since calibration term values are controlled by 100% testing they are assumed to represent 3 sigma values. Individual calibration error terms are combined using the SRSS method and normalized to a 2 sigma confidence level:
CL Device I Calibration Error CL  
+  
/
c sT2  
+
C7STD 2
CL  
+.
2,j0.252 0
L 0252+0.1252 +22 3
CL = 1.35psi 6.3 Determination of Primary Element Accuracy (PEA) and Process Measurement Accuracy (PMA)
(Input 4.8)
PMA = Tolerances on machining, +/-3% of point.
= +/-3% X 125.3 psig
+/- +/-3.8 psi (Per Input 4.6, 25% (Section 6.1) EPU power (28.2% CLTP) corresponds to 140 psia. The conversion to gauge pressure is calculated using a 14.7 psi atmospheric pressure. This value is conservative for the site.)
6.4 Determination of Other Error Terms The Analytical Limit in this calculation is based on a theoretical first stage shell pressure curve. The curve in Attachment 3 is readable to one quarter of the smallest division (Assumption 5.5). Therefore, the following readability error must be considered:
Reference REA= +/- 5 psi 4.6, 5.5 M/cah
 
MONTICELLO NUCLEAR GENERA TINGPLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page I tof 16 6.5 Calculation of Allowable Value and Operating Setpoint 6.5.1 Allowable Value (AV):
Per Section 6.1.1, the Analytical Limit corresponds to 26.6% power (EPU) or 30% power (CLTP). However, the Allowable Value will be calculated using a conservative AL of 25%
power (EPU) or 28.2% power (CLTP). Per Input 4.6, this AL corresponds to a first stage pressure of 140 psia (125.3 psig). The conversion to gauge pressure is calculated using a 14.7 psi atmospheric pressure. This value is conservative for the site.
AV*!ýAL - 1.645>VA 2  
+C  
+ PMA 2 + PEA 2 + R EA 2) + bias terms AY 12 5.3 - ( 2 )yJ6.0+ 1.35 + 3.8  
+ 25. 0')
AV *118.07 AV= 118 psig 6.5.2 Nominal Trip Setpoint Calculation:
NTSP1 = At, -
)A2T  
+ C + D2 +PMA 2 +PEA 2 + PREA 2 + bias terms NTS~=15.31.645)~60  
+132 +2.02 +.82  
+02+5.02
-NTS P, = 125.3-+1.5+2  
+35 NTSP1 = 105.0 6.5.3 Licensee Event Report (LER) Avoidance Evaluation:
The purpose of the LER Avoidance Evaluation is to ensure that there is sufficient margin provided between the AV and the NTSP to reasonably avoid violation of the AV. For a single instrument channel a Z value of greater than 1.29 provides sufficient margin between the NTSP and the AV. Although this is a multi channel loop, a Z of 1.29 will be used for conservatism. Therefore, NTSP 2 is calculated to provide a lower bound for the NTSP based on LER avoidance criteria.
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MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 12 of 16 Sigma(LER)=l(-A2.+C  
+D. )+bias Sigma(LER)=1(J6.02 + 1.352 +23.02)
Sigma(LER) = 11.90 NTSP2 = AV - Zx Sigma(LER)
NTSP 2 = 118-(1.29x11.90)
NTSP 2 = 118-(1.29x11.90)
NTSP 2 = 102.6 Therefore, an NTSP < 102.6 psig will result in a Z greater than 1.29 and provide sufficient margin between the NTSP and the AV.6.5.4 Selection of Operating Setpoints:
NTSP 2 = 102.6 Therefore, an NTSP < 102.6 psig will result in a Z greater than 1.29 and provide sufficient margin between the NTSP and the AV.
NTSP < Controlling NTSP -ALT NTSP < NTSP 2 -ALT NTSP 1.02.6-2.0 NTSP < 100.6 An instrument setting of 95.0 psig will be used for the setpoint.
6.5.4 Selection of Operating Setpoints:
Since this is less than the calculated NTSP, the setpoint is acceptable.
NTSP < Controlling NTSP -ALT NTSP < NTSP2 - ALT NTSP
* 1.02.6-2.0 NTSP *< 100.6 An instrument setting of 95.0 psig will be used for the setpoint. Since this is less than the calculated NTSP, the setpoint is acceptable.
6.5.5 Leave Alone Zone:
Leave Alone Zones are not used at MNGP (Input 4.1).
6.5.6 Establishing As Found Tolerances (AFT):
The upper limit for the As-found tolerance is 118 psig, the Allowable Value. There is no lower limit specified for this setpoint.
An as-found tolerance is calculated to provide limits for use during the surveillance testing:
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MONTICELLO NUCLEAR GENERATING PLANT CA-96-054
: TITLE, Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 13 of 16 AFT =VALT 2 +AD 2 AFT=
2.02 + 23.02 AFT = 23.1 An as found tolerance + 22 psig is considered conservative and.will be used.
6.5.7 Required Limits Evaluation:
The required limits are considered to be adequate when the following equation is satisfied:
AV - NTSP >_ AFT 118 -95&#x17d; 22 The equation is satisfied and the setpoint and required limits are adequate.
6.5.8 Spurious Trip Avoidance Evaluation:
The typical methodology for Spurious Trip Avoidance Evaluations is not implemented because of the nature of the setpoint. The setpoint does not cause a scram directly but is rather one of the conditions which need to be satisfied in order for the Reactor Protection System to initiate a scram. Therefore, this section will discuss the spurious enabling of the scram logic during conditions less than the Analytical Limit.
This calculation uses an AL of 25% (EPU) or 28.2% (CLTP) reactor thermal power. Based on channel uncertainties, the setpoint is set lower than this value to ensure the scram bypass signal is deactivated above the AL. The scram bypass signal is deactivated once the setpoint is reached. Therefore, a spurious scram on increasing reactor thermal, power could only occur during the conditions between the switch activation and the AL.
As discussed in Section 6.1, the automatic scram bypass signal is reactivated on decreasing reactor power once the pressure switch reset is reached. Due to the deadband of the pressure switches, this bypass signal is always reactivated below the NTSP and AL.
Therefore, a spurious scram can occur on decreasing power between the AL and the switch reset. The maximum deadband of the switch is 27 psi (Attachment 2) but has historically been 14 - 16 psi (Input 4.3). As such, the range of pressures at which it is possible to spuriously scram is relatively small and, due to the nature of pressure switches, is impossible to eliminate completely.
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MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 14 of 16 The lower as found limit of the pressure switch setpoint is 73 psig. On decreasing reactor power, the lowest condition the bypass signal would remain not active is when the first stage pressure reaches 73 - 27 = 46 psig (since the maximum deadband of the switch is 27 psi). Therefore, below 46 psig the scram bypass signal is always activated.
The as found and as left tolerance limits for the switch reset should be revised to ensure the deadband is not greater than 27 psi. This allows for the setpoint to drift within the As-Found range and ensures the deadband is not more than 27 psi lower than the setpoint.
6.5.9 Elevation Correction:
None.
6.5.10 Determination of Actual Setpoint:
The new setpoint and instrument setting will therefore be as follows:
Setpoint:
As-Found -Range:
As-Left Range:
Reset:
Maximum Deadband:
95 psig 73 to 117 psig 93 to 97 psig 27 psig
: 7..
CONCLUSIONS The results of the calculations are as follows:
Term Value(psig)
Reference ALT 6.0 6.2.3 ALN 6.0 6.2.3 DL 23.0 6.2.4 ALT 2.0 6.2.5 CL 1.35 6.2.6 PEA 0.0 6.3 PMA 3.8 6.3 M/cah


====6.5.5 Leave====
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Alone Zone: Leave Alone Zones are not used at MNGP (Input 4.1).6.5.6 Establishing As Found Tolerances (AFT): The upper limit for the As-found tolerance is 118 psig, the Allowable Value. There is no lower limit specified for this setpoint.An as-found tolerance is calculated to provide limits for use during the surveillance testing: M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE, Turbine Stop Valve Closure/Generator Load Reject Revision 5Scram Bypass Page 13 of 16 AFT =VALT 2 +AD 2 AFT= 2.02 + 23.02 AFT = 23.1 An as found tolerance
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 15 of 16 Term Value(psig)
+ 22 psig is considered conservative and.will be used.6.5.7 Required Limits Evaluation:The required limits are considered to be adequate when the following equation is satisfied:
Reference REA  
AV -NTSP >_ AFT 118 -95 22 The equation is satisfied and the setpoint and required limits are adequate.6.5.8 Spurious Trip Avoidance Evaluation:
+5 6.4 NTSP 95.0 6.5.4 AV 118 6.5.1 AFT  
The typical methodology for Spurious Trip Avoidance Evaluations is not implemented because of the nature of the setpoint.
+/-22 6.5.6
The setpoint does not cause a scram directly but is rather one of the conditions which need to be satisfied in order for the Reactor Protection System to initiate a scram. Therefore, this section will discuss the spurious enabling of the scram logic during conditions less than the Analytical Limit.This calculation uses an AL of 25% (EPU) or 28.2% (CLTP) reactor thermal power. Based on channel uncertainties, the setpoint is set lower than this value to ensure the scram bypass signal is deactivated above the AL. The scram bypass signal is deactivated once the setpoint is reached. Therefore, a spurious scram on increasing reactor thermal, power could only occur during the conditions between the switch activation and the AL.As discussed in Section 6.1, the automatic scram bypass signal is reactivated on decreasing reactor power once the pressure switch reset is reached. Due to the deadband of the pressure switches, this bypass signal is always reactivated below the NTSP and AL.Therefore, a spurious scram can occur on decreasing power between the AL and the switch reset. The maximum deadband of the switch is 27 psi (Attachment
: 8.
: 2) but has historically been 14 -16 psi (Input 4.3). As such, the range of pressures at which it is possible to spuriously scram is relatively small and, due to the nature of pressure switches, is impossible to eliminate completely.
FUTURE NEEDS Testing should be completed during power ascension following the turbine replacement in order to verify the first stage pressure and reactor thermal power relationship. This document.
M/cah MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 14 of 16 The lower as found limit of the pressure switch setpoint is 73 psig. On decreasing reactor power, the lowest condition the bypass signal would remain not active is when the first stage pressure reaches 73 -27 = 46 psig (since the maximum deadband of the switch is 27 psi). Therefore, below 46 psig the scram bypass signal is always activated.
should be updated to reflect the testing results. The readability error in Section 6.4 would no longer be applicable. Plant procedures should be revised to reflect the new setpoint and associated as-found and as-left tolerances.
The as found and as left tolerance limits for the switch reset should be revised to ensure the deadband is not greater than 27 psi. This allows for the setpoint to drift within the As-Found range and ensures the deadband is not more than 27 psi lower than the setpoint.6.5.9 Elevation Correction:
: 9.
None.6.5.10 Determination of Actual Setpoint: The new setpoint and instrument setting will therefore be as follows: Setpoint: As-Found -Range: As-Left Range: Reset: Maximum Deadband: 95 psig 73 to 117 psig 93 to 97 psig 27 psig 7. .CONCLUSIONS The results of the calculations are as follows: Term Value(psig)
ATTACHMENTS 1 PS-5-14A, B, C and D drift data.
Reference ALT 6.0 6.2.3 ALN 6.0 6.2.3 DL 23.0 6.2.4 ALT 2.0 6.2.5 CL 1.35 6.2.6 PEA 0.0 6.3 PMA 3.8 6.3 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 15 of 16 Term Value(psig)
2 Barksdale Catalog Datasheets.
Reference REA +5 6.4 NTSP 95.0 6.5.4 AV 118 6.5.1 AFT +/-22 6.5.6 8. FUTURE NEEDS Testing should be completed during power ascension following the turbine replacement in order to verify the first stage pressure and reactor thermal power relationship.
3 GE-MNGP-AEP-196 1st Stage Shell Pressure curve. GE. 1LX0501-07 Rev. 1 4
This document.should be updated to reflect the testing results. The readability error in Section 6.4 would nolonger be applicable.
Memo from John Hess (GE) to Jim Devine (MNGP) dated March 15, 1996.
Plant procedures should be revised to reflect the new setpoint and associated as-found and as-left tolerances.
5 Setpoint Relationships
: 9. ATTACHMENTS 1 PS-5-14A, B, C and D drift data.2 Barksdale Catalog Datasheets.
: 10.
3 GE-MNGP-AEP-196 1 st Stage Shell Pressure curve. GE. 1LX0501-07 Rev. 1 4 Memo from John Hess (GE) to Jim Devine (MNGP) dated March 15, 1996.5 Setpoint Relationships
REFERENCES 10.1 NEDC-31336P-A, General Electric Instrument Setpoint Methodology, September 1996.
: 10. REFERENCES 10.1 NEDC-31336P-A, General Electric Instrument Setpoint Methodology, September 1996.10.2 GE-NE-901-021-0492, DRF A0001932-1, Setpoint Calculation Guidelines for the Monticello Nuclear Generating Plant, October 1992.10.3 EPRI Report TR-1 03335-R1, Guidelines for Instrument Calibration Extension/Reduction Programs, Revision 1, March, 1994.10.4 Task Report T0502, Nuclear Management Company Monticello Nuclear Generating Plant Extended Power Uprate: M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 16 of 16 10.5 USAR-07.06.
10.2 GE-NE-901-021-0492, DRF A0001932-1, Setpoint Calculation Guidelines for the Monticello Nuclear Generating Plant, October 1992.
Monticello Updated Safety Analysis Report. Plant Instrumentation and Control Systems: Plant Protection System. Revision 25P.10.6 Operations Manual B.05.06. Plant Protection System.10.7 Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle., M/cah I MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachm~rlt 1 Page 1 of 22 A1.1 Data Grouping The Barksdale model 2T-A12SS pressure switches presented below are included in this analysis.
10.3 EPRI Report TR-1 03335-R1, Guidelines for Instrument Calibration Extension/Reduction Programs, Revision 1, March, 1994.
The current setpoints are obtained from the MNGP Component Master List (CML) Database.Equipment ID Range Setpoint (desired)PS-5-14A 50- 1200 psig 125 psig PS-5-14B 50 -1200 psig 125 psig PS-5-14C 50 -1200 psig 125 psig PS-5-14D 50 -1200 psig 125 psig As shown in section 6.2.2, the trip units are exposed to similar environmental conditions with the same calibration frequency.
10.4 Task Report T0502, Nuclear Management Company Monticello Nuclear Generating Plant Extended Power Uprate:
Therefore, the individual drift data for the trip units can be grouped without further numerical testing, following the criteria set forth in step 5.4.8 of ESM-03.02-APP-lII.
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MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 16 of 16 10.5 USAR-07.06. Monticello Updated Safety Analysis Report. Plant Instrumentation and Control Systems: Plant Protection System. Revision 25P.
10.6 Operations Manual B.05.06. Plant Protection System.
10.7 Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle.,
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I MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachm~rlt 1 Page 1 of 22 A1.1 Data Grouping The Barksdale model 2T-A12SS pressure switches presented below are included in this analysis. The current setpoints are obtained from the MNGP Component Master List (CML) Database.
Equipment ID Range Setpoint (desired)
PS-5-14A 50- 1200 psig 125 psig PS-5-14B 50 - 1200 psig 125 psig PS-5-14C 50 - 1200 psig 125 psig PS-5-14D 50 - 1200 psig 125 psig As shown in section 6.2.2, the trip units are exposed to similar environmental conditions with the same calibration frequency. Therefore, the individual drift data for the trip units can be grouped without further numerical testing, following the criteria set forth in step 5.4.8 of ESM-03.02-APP-lII.
A1.2 Populating the Spreadsheet Calibration data for the pressure switches included the date of calibration, as well as the As-Found and As-Left setpoint values. This data was input into a Microsoft Excel spreadsheet, and included in this Attachment.
A1.2 Populating the Spreadsheet Calibration data for the pressure switches included the date of calibration, as well as the As-Found and As-Left setpoint values. This data was input into a Microsoft Excel spreadsheet, and included in this Attachment.
The calibration interval was determined by taking the difference between the current and previous calibration dates. Per step 5.3.9 of ESM-03.02-APP-III, the calibration interval was converted to months by dividing the number of days by 30.5 days per month.The Drift value was calculated by taking the difference between the current calibration As-Found value and the previous calibration As-Left value.Each of the pressure switches contained a discrepancy in its data set. On the calibration dates of 05/12/1996 and 06/1111996, only the As-Found setpoint value was reported.However, each data set contained a data point for the following day (05/13/1996 and 06/12/1996, respectively) which included the As-Left setpoint value. For the purposes of this drift analysis, each of the data pairs was combined into a single data point which included both the As-Found and. As-Left setpoints.
The calibration interval was determined by taking the difference between the current and previous calibration dates. Per step 5.3.9 of ESM-03.02-APP-III, the calibration interval was converted to months by dividing the number of days by 30.5 days per month.
This is considered reasonable, as a discrepancy of a single day is insignificant compared to the average calibration interval of approximately 15 months.It is noted that the calibration setpoint for the pressure switches was adjusted several times during the analysis time period. However, all the pressure switches in question were adjusted uniformly, and the overall difference in setpoints is small compared to the instrument setpoint.
The Drift value was calculated by taking the difference between the current calibration As-Found value and the previous calibration As-Left value.
range (approximately 5%). Since the analysis deals with drift values, and not the setpoints themselves, no special considerations were made for the varying setpoints:
Each of the pressure switches contained a discrepancy in its data set. On the calibration dates of 05/12/1996 and 06/1111996, only the As-Found setpoint value was reported.
M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 2 of 22 AU.3 Spreadsheet Performance of Basic Statistics The following information was determined for each instrument individually:
However, each data set contained a data point for the following day (05/13/1996 and 06/12/1996, respectively) which included the As-Left setpoint value. For the purposes of this drift analysis, each of the data pairs was combined into a single data point which included both the As-Found and. As-Left setpoints. This is considered reasonable, as a discrepancy of a single day is insignificant compared to the average calibration interval of approximately 15 months.
The average or mean value (x) of the drift data for each instrument was determined by using the "Average" function in Microsoft Excel. This function uses the following equation: n where x = average of data set xi = individual drift value n = total number of values The standard deviation of a data set returns the measure of how widely dispersed thevalues are in relation to the mean of the data. The standard deviation for each instrument was determined using the "STDEV" function.
It is noted that the calibration setpoint for the pressure switches was adjusted several times during the analysis time period. However, all the pressure switches in question were adjusted uniformly, and the overall difference in setpoints is small compared to the instrument setpoint. range (approximately 5%). Since the analysis deals with drift values, and not the setpoints themselves, no special considerations were made for the varying setpoints:
Microsoft Excel uses the following equation in the "STDEV" function: nZ x,~ x.n(n-1)where s = standard deviation of sample x= individual drift value n = total number of values The variance (S2) is another measure of data spread from the mean. The variance for each instrument was determined by using the "VAR" function in Microsoft Excel. The variance is calculated as follows: S 2 nEX2 -(EX)n(n-1)where s2 = variance of sample xi= individual drift value n = total number of values The largest positive drift value for each instrument was determined by using the "MAX" function.The largest negative drift value for each instrument was determined by using the "MIN" function.The number of data points (n) for each instrument was determined using the "COUNT" function.The psig values for average, standard deviation, and largest positive and negative drift were converted to a percent of instrument span using the following formula:/. span = psig value x100%psig span M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 3 of 22 A Drift Trend Plot was developed for each instrument by plotting the drift value versus calibration date. Bounds corresponding to + 2s (2 standard deviations) are shown on the plot.Page 11 presents the combined drift data statistics for the subject trip units. The combined statistics were determined using the preceding methods.A1.4 Outlier Detection and Expulsion Per step 5.5 of ESM-03.02-APP-ll, the t-Test is used to detect the presence of outliers in the final data set. The t-Test requires the use of the following equation: t.-x S where t = individual t-Test statistic s = standard deviation of sample xi= individual drift value x= individual drift value The t-Test involves calculating the individual t' statistics for each data point, and comparing them to a critical value. The critical value depends on the sample size, and is obtained from Table 9.2 of ESM-03.02-APP-Il1.The t-Test is shown on pages 12 and 13 of this Attachment.
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Based on a sample size of 44, the critical value utilized in the t-Test is 2.91. None of the calculated individual t-Test statistics exceeded the critical value and therefore, no outliers were identified or removed.A1.5 Normality Tests Most statistical analyses make the assumption that the values in question are normally distributed.
 
The criteria in ESM-03.02-APP-llI require that the data set be tested for normality.
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
It is recommended that for samples with less than 50 data points, the W Test be utilized.W Test The W Test calculates a test statistic value for the sample population and compares the calculated value to the critical values for W, which are tabulated in Table 9.6 of ESM-03.02-APP-Ill.
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 2 of 22 AU.3 Spreadsheet Performance of Basic Statistics The following information was determined for each instrument individually:
The W Test is a lower-tailed test. Thus if the calculated value of W is less than the critical value of W, the assumption of normality would be rejected at the stated significance level. If the calculated value of W is larger than the critical value of W, there is no evidence to reject the assumption of normality.To perform a W Test, the drift value data set is sorted and numbered in ascending order from smallest to largest.Micah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 4 of 22 Calculate the S 2.value for the group: S' (n- 1) x s'where S 2= sum of the squares about the mean S2= unbiased estimate of the sample population variance n total number of data points Calculate the quantity b of the sample group: b [a,,-,+, x (x,,,+, -x, where i= 1 tok, and k =nl2 if n is even or k = (n-1)/2 if n is odd n = total number of data points xi = individual sample data point an-i+1 = coefficient obtained from Table 9.5 of ESM-03.02-APP-III Calculate theW value for the sample group. The following equation is used: b2 S 2 Determine the critical W values based on the sample size using Table 9.6 in ESM-03.02-APP-Ill.See pages 14 and 15 for the W Test of the drift data. For a sample size of 44, the critical value of the W Test is 0.944. The calculated W value was 0.982. Based on this result, there is no evidence to reject the assumption of normality.
The average or mean value (x) of the drift data for each instrument was determined by using the "Average" function in Microsoft Excel. This function uses the following equation:
A1.6 Selection of Final Data Set The pressure switches in question have only one calibration setpoint.
n where x = average of data set xi = individual drift value n = total number of values The standard deviation of a data set returns the measure of how widely dispersed the values are in relation to the mean of the data. The standard deviation for each instrument was determined using the "STDEV" function. Microsoft Excel uses the following equation in the "STDEV" function:
Therefore, all data points will be part utilized and no further analysis is required in determining the final data set.A1.7 Time-Dependency Analysis Standard statistical analyses do not consider time-dependency.
nZ x,~
The following tests attempt to uncover any time-related performance and the impact of any time-dependency on the analysis.Drift Interval Plot A drift interval plot is an XY scatter plot that shows the data set plotted against the time interval between calibrations, It relies on visual inspection to discriminate the plot for any trend in the data to exhibit a time dependency.
x.
A prediction line can be added to this plot to aid in the analysis.
n(n-1) where s = standard deviation of sample x= individual drift value n = total number of values The variance (S2) is another measure of data spread from the mean. The variance for each instrument was determined by using the "VAR" function in Microsoft Excel. The variance is calculated as follows:
Page 16 shows the drift interval plot for this data set. The drift interval plot includes the tolerance interval (TI) described in section A1.9. The plot also includes a predicted line, Micah MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 1Drift Analysis Attachment 1 Page 5 of 22 which in this case passes through the x-axis. Based on section 4.8.4.D.4 of ESM-03.02-APP-Ill, cases where the drift function crosses zero are normally established assuming no time dependency.
S 2 nEX2  
Standard Deviations and Means at Different Calibration Intervals (Binningq Analysis)The binning analysis is the most recommended method of determining time dependent tendencies in a given sample pool. Following the instructions in step 4.8.3 of ESM-03.02-APP-Ill, the drift data was segregated into different groups (bins) corresponding to different ranges of calibration intervals.
-(EX) n(n-1) where s2 = variance of sample xi= individual drift value n = total number of values The largest positive drift value for each instrument was determined by using the "MAX" function.
In order for further analysis to be done, at least 2 valid bins must exist. In order to be considered valid, a bin must contain more than five data points and more than 10% of the total data count. The binning analysis (pages 17-18) includes 3 valid bins.The average drift, standard deviations and average time intervals were calculated for each bin. These parameters were plotted on page 18. This plot shows the variation of the bin averages and standard deviations versus time interval.
The largest negative drift value for each instrument was determined by using the "MIN" function.
The behavior of the plot indicates no time dependency, following the criteria of step 4.8.4.D.4 of ESM-03.02-APP-Ill.Regression Analysis A regression analysis was performed on the drift data, as well as the absolute value of the drift data. This analysis is shown on pages 19 through 22.The results of the regression analysis were compared to the criteria of step 4.8.4 from ESM-03.02-APP-III.
The number of data points (n) for each instrument was determined using the "COUNT" function.
The analytical results indicate no time dependency.
The psig values for average, standard deviation, and largest positive and negative drift were converted to a percent of instrument span using the following formula:
However, per the instruction of step 5.8.3.E, the data will be conservatively considered to be moderately time dependent.
/. span = psig value x100%
A1.8 Drift Bias Determination The absolute value of the average calculated drift for the trip pressure switches is 0.2 psig, which is approximately equal to 0.02% of the calibrated span. The criteria in ESM-03.02-APP-Ill state that if the absolute value of the mean drift is less than 0.1% of the calibrated span, the instrument drift does not appear to have a bias. Therefore, the drift bias terms will be taken as 0 in this analysis.A1.9 Analyzed Drift Value Bias Term'Based on the drift data as well as section A1.8, the instruments do not have a bias.Therefore, the bias term will be equal to 0.Random Term The random term of the analyzed drift value is calculated with the below equation: A Dd,.do,, s x TIF x NAF where ADrandom = random term for analyzed drift s = drift standard deviation TIF 95%/95% tolerance interval factor NAF = Normality Adjustment Factor M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TIT'LE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 6 of 22 The standard deviation of the drift data is equal to 8.34 psig. The TIF for a sample size of 44 is equal to 2.445 (Table 9.1 of ESM-03.02-APP-lII).
psig span M/cah
Since the W Test did not reject the hypothesis of normality, a Normality Adjustment Factor was not necessary and is therefore equal to 1. Thus, the random drift term is calculated to be 20.4 psig. The random term is equal to the tolerance interval (TI) plotted on the Drift Interval Plot on page 16.Extended Interval Predicted Drift (Random Term)Since the drift was determined to be moderately time dependent, the following equationwas used to extrapolate the drift uncertainty:
 
AD .random = AD,,,,od,,, x or where ADE.random  
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
= extended period drift term ADrandom = random termrfor analyzed drift CIE = extended calibration interval (surveillance interval +25%)CIO = average observed calibration time interval from bin with longest time interval The value of the random term for the analyzed drift was determined to be 20.4 psig. The extended calibration interval is equal to the surveillance calibration interval (24 months)plus an additional 25% (6 months). Therefore, CIE is equal to 30 months. CIo is determined from the bin of data that had the longest calibration interval.
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 3 of 22 A Drift Trend Plot was developed for each instrument by plotting the drift value versus calibration date. Bounds corresponding to + 2s (2 standard deviations) are shown on the plot.
In this case, it is the bin with a calibration interval range of 22.5 to 30 months. The average calibration interval within this bin is equal to 23.6 months. These values produce a 30-month predicted drift term of 23.0 psig from the above equation.The instruction in step 5.10.4.B states that the calculated extended interval predicted drift terms must be compared to the uncertainty calculated using the 99%/95% tolerance factor. The following equation is utilized to increase the TIF..A rnn -ai TIF99 / 95 AD E.ra,,do,, A AD rand,,o,, x 11E'95/95 where ADE.random  
Page 11 presents the combined drift data statistics for the subject trip units. The combined statistics were determined using the preceding methods.
= extended period drift term ADrandorn  
A1.4 Outlier Detection and Expulsion Per step 5.5 of ESM-03.02-APP-ll, the t-Test is used to detect the presence of outliers in the final data set. The t-Test requires the use of the following equation:
= random term for analyzed drift TIF95/9 5 = 95%/95% tolerance interval factor TIF991 9 5 d 99%/95% tolerance interval factor Using the random drift term of 20.4 psig, a 95%/95% TIF of 2.445 and a 99%/95% TIF of-2.677, the extended period drift term is calculated to be 22.3 psig. Therefore, 23.0 psig isthe larger of the two and should be used as the 30-month predicted drift term.M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass' Revision 5 Drift Analysis Attachment1 Page 7 of 22 Drift Data for PS-5-14A Calibration As- Drift Drift Date Interval t AsD-Leftr (Mnh) Found (psig) (%)(Months)4/22/2007 24.4 127.8 124.6 1.3 0.11 4/9/2005 22.8 126.5 126.5 0.0 --MO 5/14/2003 17.3 120.5 126.5  
t.-x S
-5.0 -0.43 12/2/2001 21.8 134.5 125.5 10.5 0.91 2/5/2000 16.1 114.0 124.0  
where t = individual t-Test statistic s = standard deviation of sample xi= individual drift value x= individual drift value The t-Test involves calculating the individual t' statistics for each data point, and comparing them to a critical value. The critical value depends on the sample size, and is obtained from Table 9.2 of ESM-03.02-APP-Il1.
-11.0 -.0.96 10/1/1998 4.4 120.0 125.0 5.5 0.48 5/21/1998 1.1 139.5 114.5 0.0 0.00 4/16/1998 22.1, 1,39.5 139.5 1.5 0.13 6/12/1996 1.0 137.0 138.0 7.0 0.61 5/13/1996 18.7 166.0 130.0 -9.0 -0.78 10/20/1994 19.9 191.0 175.0 16.5 1.43 2/20/1993 174.5 174.5 Basic Statistics for PS-5-14A Average x (psig) 1.6 Standard Deviation s (psig) 8.2 Variance s (psig) 66.5 Largest Positive Drift (psig) 16.5 Largest Negative Drift (psig) -11.0 Number of Samples n 11 Average x (%) 0.14 Standard Deviation s (%) 0.7094 Largest Positive Drift (%) 1.43 Largest Negative Drift (%) -0.96 Drift Trend Plot for PS-5.-14A20.0 10.0 0.0-20o 51711990 1/31/1993 10/28/1995 7/24/1998 4/19/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14A -+2s -.. 2s M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 8 of 22 Drift Data for PS-5-14B Calibration As- As-Left Date Interval As-Left Drift Drift (Months) Found (psig) (%)4/22/2007 24.4 128.5 126.3 2.5 0.22 4/9/2005 22.8 122.0 126U0 -2.0 -0.17 5/14/2003 17.3 -122.0 124.0  
The t-Test is shown on pages 12 and 13 of this Attachment. Based on a sample size of 44, the critical value utilized in the t-Test is 2.91. None of the calculated individual t-Test statistics exceeded the critical value and therefore, no outliers were identified or removed.
-4.0 -0.35 12/2/2001 21.8 129.5 126.0 4.5 0.39 2/5/2000 16.1 114.0 125.0 -11.0 -0.96 10/1/1998 4.4 118.0 125.0 2.0 0.17 5M21/1998 1.1 134.0 116.0 -2.5 -0.22 4/16/1998 22.1 136.5 136.5 -1.5 -0.13 6/12/1996 1.0 134.0 138.0 4.0 0.35 5/13/1996 18.7 160.5 130.0 -14.5 -1.26 10/20/1994 19.9 193.0 175.0 18.0 1.57 2/20/1993 171.0 175.0 Basic Statistics for PS-5-14B Average x (psig) -0.4 Standard Deviation s (psig) 8.5 Variance s 2  (psig) 72.8 Largest Positive Drift (psig) 18.0 Largest Negative Drift (psig) -14.5 Number of Samples n 11 Average x (%) -0.04 Standard Deviation s (%) 0.7421 Largest Positive Drift (%) 1.57 Largest Negative Drift (%) -1.26 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 9 of 22 Drift Data for PS-5-14C Calibration As- Drift Drift Date Interval As-Left (Months) Found (psig) A 4/22/2007 24.4 123.1 126.3 -2.4  
A1.5 Normality Tests Most statistical analyses make the assumption that the values in question are normally distributed. The criteria in ESM-03.02-APP-llI require that the data set be tested for normality. It is recommended that for samples with less than 50 data points, the W Test be utilized.
-0.21 4/9/2005 22.8 125.5 125.5 0.0 0.00 5/14/2003 17.3 119.0 125.5 -6.0 -0&#xfd;52 12/2/2001 21.8 134.0 125.0 10.0 0.87 2/5/2000 16.1 119.0 124.0 -7.0 -0.61 10/1/1998 4.4 119.0 126.0 4.0 0.35 5/21/1998 1.1 137.8 115.0 1.3 0.11 4/16/1998 22.1 136.5 136.5 -1.6 -0.14 6/12/1996 1.0 129.5 138.1 0.0 0.00 5/13/1996 18.7 167.5 129.5 -8.0 -0.70 10/20/1994 19.9 187.0 175.5 12.0 1.04 2/20/1993 166.0 175.0 Basic Statistics for PS-5-14C Average x (psig) 0.2 Standard Deviation s (psig) 6.5 Variance s 2 (psig) 41.9 Largest Positive Drift (psig) 12.0 Largest Negative Drift (psig) -8.0 Number of Samples n 11 Average x (%) 0.02 Standard Deviation s (%) 0.5626 Largest Positive Drift (%) 1.04 Largest Negative Drift (%) -0.70 Drift Trend Plot for PS-5-14C 0 20.0 10,0 ,, 10 -1 .0-2 0 .0 -5/7/1990 1731/1 993 10/28/1995 712411998 4119/2001 1/14/2004 10/10/2006 7/6/2009 Date---- PS-5-14C ---+2s -w...- -2s M/cah.
W Test The W Test calculates a test statistic value for the sample population and compares the calculated value to the critical values for W, which are tabulated in Table 9.6 of ESM-03.02-APP-Ill. The W Test is a lower-tailed test. Thus if the calculated value of W is less than the critical value of W, the assumption of normality would be rejected at the stated significance level. If the calculated value of W is larger than the critical value of W, there is no evidence to reject the assumption of normality.
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 10 of 22 Drift Data for PS-5-14D Calibration Clbain As- .Drift Drift Date Interval As- As-Left Drift D (Mnh) Found (psig) (%)(Months)4/2212007 24.4 122.3 124.8 -0.7. -0.06 4/9/2005 22.8 123.0 123.0 -2.5 -0.22 5/14/2003 17.3 119.5 125.5 -6.0 -0.52 12/2/2001 21.8 133.8 125.5 8.8 0.77 2/5/2000 16.1 110.0 125.0 -14.0 -1.22 10/1/1998 4.4 118.0 124.0 4.5 0.39 5/2111998 1.1 145.0 113.5 7.5 0.65 4/16/1998 22.1 127.0 137.5 -10.0 -0.87 6/12/1996 1.0 135.0 137.0 5.5 0.48 5/13/1996 18.7 156.0 129.5 -18.0 -1.57 10/20/1994 19.9 193.5 174.0 17.5 1.52 2/20/1993  
To perform a W Test, the drift value data set is sorted and numbered in ascending order from smallest to largest.
.169.0 176.0 Basic Statistics for PS-5-14D Average x (psig) -0.7 Standard Deviation s (psig) 10.7 Variance s2 (psig) 114;8 Largest Positive Drift (psig) 17.5 Largest Negative Drift (psig) -18.0 Number of Samples n 11 Average x (%). -0.06 Standard Deviation s (%) 0.9318 Largest Positive Drift (%) 1.52 Largest Negative Drift (%) -1.57 Drift Trend Plot for PS-5-14D 30.0 -T-S20.0 -AWLg 10.0 0.0>-10.0 e--20.0 S-30.0 5/711990 1/3111993 10/28/1995 7/24/1998 4/19/2001 1/14/2004 10/10/2006 7/6/2009 Date-.--- PS-5-14D -. --+2s -2s]M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 11 of 22 Basic Statistics for Combined Drift Data Average -(psig) 0.2 Standard Deviation s (psig) 8.34 Variance s 2  (psig) 69.6 Largest Positive Drift (psig) 18,0 Largest Negative Drift (psig) -18.0 Number of Samples 44 Average x (%) 0,02 Standard Deviation s (%) 0.7256 Largest Positive Drift (%) 1.57 Largest Negative Drift (%) -1.57 Micah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve ClosurelGenerator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 12 of 22 Outlier Test (t-Test) for Combined Data Set Equipment Calibration Drift Outlier?ID (Months) (psig) T YESINO PS-5-14A 24.4 1.3 0.13 NO 22.8 0.0 0.02 NO 17.3 .-5.0 0.62 NO 21.8 10.5 1.24 NO 16.1 -11.0 1.34 NO 4.4 5.5 .0.64 NO 1.1 0.0 0.02 NO 22.1 1.5 0.16 NO 1.0 7.0 0.82 NO 18.7 -9.0 1.10 NO 19.9 16.5 1.96 NO PS-5-14B 24.4 2.5 0.28 NO 22.8 -2.0 0.26 NO 17.3 -4.0 0.50 NO 21.8 4.5 0.52 NO 16.1 -11.0 1.34 NO 4.4 2.0 0.22 NO 1.1 -2.5 0.32 NO 22.1 -1.5 0.20 NO 1.0 4.0 0.46 NO 18.7 -14.5 1.76 NO 19.9 18.0 2.14 NO PS-5-14C 24.4 -2.4 0.31 NO 22.8 0.0 0.02 NO 17.3 -6.0 0.74 NO 21.8 10.0 1.18 NO 16.1 -7.0 0.86 NO 4.4 4.0 0.46 NO 1.1 1.3 0.13 NO 22.1 --1.6 0.21 NO 1.0 0.0 0.02 NO 18.7 -8.0 0.98 NO 19.9 12.0 1.42 NO PS-5-14D 24.4 -0.7 0.10 NO 22.8 -2.5 0.32 NO 17.3 -6.0 0.74 NO 21.8 8.8 1.03 NO 16.1 -14.0 1.70 NO4.4 4.5 0.52 NO 1.1 7.5 0.88 NO 22.1 -10.0 1.22 NO M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision..5 Drift Analysis Attachment 1 Page 13 of 22 I 1.0 5.5 0.64 NO 18.7 -18.0 2.18 NO 19.9 I 17.5 2.08 NO The outlier test shows that none of the individual T-statistics exceed the critical value of 2.91. The critical value was obtained from Table 9.2 of ESM-03.02-APP-lI1.
Micah
Therefore, the data set contains no outliers.M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass, Revisiorl.5 Drift Analysis Attachment'l Page 14 of 22 Normality Test -W Test X1 i an-i+1 Xn-i+l bi-18.0 1 0.3872 18.0 13.94-14.5 2 0.2667 17.5 8.53-14.0 3 0.2323 16.5 7.09-11.0 4 0.2072 12.0 4.77-11.0 5 0.1868 10.5 4.02-10.0 6 0.1695 10.0 3.39-9.0 7 0.1542 8.8 2.74-8.0 8 0.1405 7.5 2.18-7.0 9 0.1278 7.0 1.79-6.0 10 0.1160 5.5 1.33-6.0 11 0.1049 5.5 1.21-5.0 12 0.0943 4.5 0.90-4.0 13 0.0842 4.5 0.72-2.5 14 0.0745 4.0 0.48-2.5 15 0.0651 4.0
 
* 0.42-2.4 16 0.0560 2.5 0.27-2.0 17- 0.0471 2.0 0.19-1.6 18 0.0383 1.5 0.12-1.5 19 0.0296 1:3 0.08-0.7 20 0.0211 1.3 0.04 0.0 21 0.0126 0.0 0.00 0.0 22 0.0042 0.0 0.00 0.0 --- ---.....0.0 --- ---1.3 --- ---1.3 --- ---1.5 --- ---2.0 = ...2.5 --- ---4.0 --- ---4.0 --- ---4.5 --- ---....4.5 ---....5.5 --- ---....7 .5 ... .. ..8.8 ---.. .. .10.0 --- ---...10.5 ..........
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
12 .0 ............
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 4 of 22 Calculate the S2.value for the group:
M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96.054 TITLE:, Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 15 of 22-16.5 1 ---17.5 -- ----18.0 ... .W Test Analysis n 44 S2 2993.8 b, '(bi) 54.2 W 0.982 P 0.944 Since W > P, the results of the W Test, do not provide any evidence to reject the assumption of normality.
S' (n-1) x s' where S2 = sum of the squares about the mean S2= unbiased estimate of the sample population variance n
Drift Tolerance Interval (TI)TI=
total number of data points Calculate the quantity b of the sample group:
b
[a,,-,+, x (x,,,+, - x, where i= 1 tok, and k =nl2 if n is even or k = (n-1)/2 if n is odd n = total number of data points xi = individual sample data point an-i+1 = coefficient obtained from Table 9.5 of ESM-03.02-APP-III Calculate theW value for the sample group. The following equation is used:
b2 S2 Determine the critical W values based on the sample size using Table 9.6 in ESM-03.02-APP-Ill.
See pages 14 and 15 for the W Test of the drift data. For a sample size of 44, the critical value of the W Test is 0.944. The calculated W value was 0.982. Based on this result, there is no evidence to reject the assumption of normality.
A1.6 Selection of Final Data Set The pressure switches in question have only one calibration setpoint. Therefore, all data points will be part utilized and no further analysis is required in determining the final data set.
A1.7 Time-Dependency Analysis Standard statistical analyses do not consider time-dependency. The following tests attempt to uncover any time-related performance and the impact of any time-dependency on the analysis.
Drift Interval Plot A drift interval plot is an XY scatter plot that shows the data set plotted against the time interval between calibrations, It relies on visual inspection to discriminate the plot for any trend in the data to exhibit a time dependency. A prediction line can be added to this plot to aid in the analysis.
Page 16 shows the drift interval plot for this data set. The drift interval plot includes the tolerance interval (TI) described in section A1.9. The plot also includes a predicted line, Micah
 
MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 1Drift Analysis Page 5 of 22 which in this case passes through the x-axis. Based on section 4.8.4.D.4 of ESM-03.02-APP-Ill, cases where the drift function crosses zero are normally established assuming no time dependency.
Standard Deviations and Means at Different Calibration Intervals (Binningq Analysis)
The binning analysis is the most recommended method of determining time dependent tendencies in a given sample pool. Following the instructions in step 4.8.3 of ESM-03.02-APP-Ill, the drift data was segregated into different groups (bins) corresponding to different ranges of calibration intervals. In order for further analysis to be done, at least 2 valid bins must exist. In order to be considered valid, a bin must contain more than five data points and more than 10% of the total data count. The binning analysis (pages 17-
: 18) includes 3 valid bins.
The average drift, standard deviations and average time intervals were calculated for each bin. These parameters were plotted on page 18. This plot shows the variation of the bin averages and standard deviations versus time interval. The behavior of the plot indicates no time dependency, following the criteria of step 4.8.4.D.4 of ESM-03.02-APP-Ill.
Regression Analysis A regression analysis was performed on the drift data, as well as the absolute value of the drift data. This analysis is shown on pages 19 through 22.
The results of the regression analysis were compared to the criteria of step 4.8.4 from ESM-03.02-APP-III. The analytical results indicate no time dependency. However, per the instruction of step 5.8.3.E, the data will be conservatively considered to be moderately time dependent.
A1.8 Drift Bias Determination The absolute value of the average calculated drift for the trip pressure switches is 0.2 psig, which is approximately equal to 0.02% of the calibrated span. The criteria in ESM-03.02-APP-Ill state that if the absolute value of the mean drift is less than 0.1% of the calibrated span, the instrument drift does not appear to have a bias. Therefore, the drift bias terms will be taken as 0 in this analysis.
A1.9 Analyzed Drift Value Bias Term
'Based on the drift data as well as section A1.8, the instruments do not have a bias.
Therefore, the bias term will be equal to 0.
Random Term The random term of the analyzed drift value is calculated with the below equation:
A Dd,.do,,
s x TIF x NAF where ADrandom = random term for analyzed drift s = drift standard deviation TIF 95%/95% tolerance interval factor NAF = Normality Adjustment Factor M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TIT'LE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 6 of 22 The standard deviation of the drift data is equal to 8.34 psig. The TIF for a sample size of 44 is equal to 2.445 (Table 9.1 of ESM-03.02-APP-lII). Since the W Test did not reject the hypothesis of normality, a Normality Adjustment Factor was not necessary and is therefore equal to 1. Thus, the random drift term is calculated to be 20.4 psig. The random term is equal to the tolerance interval (TI) plotted on the Drift Interval Plot on page 16.
Extended Interval Predicted Drift (Random Term)
Since the drift was determined to be moderately time dependent, the following equation was used to extrapolate the drift uncertainty:
AD  
.random = AD,,,,od,,, x or where ADE.random = extended period drift term ADrandom = random termrfor analyzed drift CIE = extended calibration interval (surveillance interval +25%)
CIO =
average observed calibration time interval from bin with longest time interval The value of the random term for the analyzed drift was determined to be 20.4 psig. The extended calibration interval is equal to the surveillance calibration interval (24 months) plus an additional 25% (6 months). Therefore, CIE is equal to 30 months. CIo is determined from the bin of data that had the longest calibration interval. In this case, it is the bin with a calibration interval range of 22.5 to 30 months. The average calibration interval within this bin is equal to 23.6 months. These values produce a 30-month predicted drift term of 23.0 psig from the above equation.
The instruction in step 5.10.4.B states that the calculated extended interval predicted drift terms must be compared to the uncertainty calculated using the 99%/95% tolerance factor. The following equation is utilized to increase the TIF..
A rnn  
-ai TIF99 / 95 AD E.ra,,do,,
A AD rand,,o,,
x 11E'95/95 where ADE.random = extended period drift term ADrandorn = random term for analyzed drift TIF95/95 = 95%/95% tolerance interval factor TIF99195 d 99%/95% tolerance interval factor Using the random drift term of 20.4 psig, a 95%/95% TIF of 2.445 and a 99%/95% TIF of
-2.677, the extended period drift term is calculated to be 22.3 psig. Therefore, 23.0 psig is the larger of the two and should be used as the 30-month predicted drift term.
M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass' Revision 5 Drift Analysis Page 7 of 22 Drift Data for PS-5-14A Calibration As-Drift Drift Date Interval t
AsD-Leftr (Mnh)
Found (psig)
(%)
(Months) 4/22/2007 24.4 127.8 124.6 1.3 0.11 4/9/2005 22.8 126.5 126.5 0.0  
- -MO 5/14/2003 17.3 120.5 126.5  
-5.0  
-0.43 12/2/2001 21.8 134.5 125.5 10.5 0.91 2/5/2000 16.1 114.0 124.0  
-11.0  
-.0.96 10/1/1998 4.4 120.0 125.0 5.5 0.48 5/21/1998 1.1 139.5 114.5 0.0 0.00 4/16/1998 22.1, 1,39.5 139.5 1.5 0.13 6/12/1996 1.0 137.0 138.0 7.0 0.61 5/13/1996 18.7 166.0 130.0  
-9.0  
-0.78 10/20/1994 19.9 191.0 175.0 16.5 1.43 2/20/1993 174.5 174.5 Basic Statistics for PS-5-14A Average x
(psig) 1.6 Standard Deviation s
(psig) 8.2 Variance s
(psig) 66.5 Largest Positive Drift (psig) 16.5 Largest Negative Drift (psig)  
-11.0 Number of Samples n
11 Average x
(%)
0.14 Standard Deviation s
(%)
0.7094 Largest Positive Drift
(%)
1.43 Largest Negative Drift
(%)  
-0.96 Drift Trend Plot for PS-5.-14A
* 20.0 10.0 0.0
-20o 51711990 1/31/1993 10/28/1995 7/24/1998 4/19/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14A  
+2s 2s M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 8 of 22 Drift Data for PS-5-14B Calibration As-As-Left Date Interval As-Left Drift Drift (Months)
Found (psig)
(%)
4/22/2007 24.4 128.5 126.3 2.5 0.22 4/9/2005 22.8 122.0 126U0  
-2.0  
-0.17 5/14/2003 17.3 -
122.0 124.0  
-4.0  
-0.35 12/2/2001 21.8 129.5 126.0 4.5 0.39 2/5/2000 16.1 114.0 125.0  
-11.0  
-0.96 10/1/1998 4.4 118.0 125.0 2.0 0.17 5M21/1998 1.1 134.0 116.0  
-2.5  
-0.22 4/16/1998 22.1 136.5 136.5  
-1.5  
-0.13 6/12/1996 1.0 134.0 138.0 4.0 0.35 5/13/1996 18.7 160.5 130.0  
-14.5  
-1.26 10/20/1994 19.9 193.0 175.0 18.0 1.57 2/20/1993 171.0 175.0 Basic Statistics for PS-5-14B Average x
(psig)  
-0.4 Standard Deviation s
(psig) 8.5 Variance s2 (psig) 72.8 Largest Positive Drift (psig) 18.0 Largest Negative Drift (psig)  
-14.5 Number of Samples n
11 Average x
(%)  
-0.04 Standard Deviation s
(%)
0.7421 Largest Positive Drift
(%)
1.57 Largest Negative Drift
(%)  
-1.26 M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 9 of 22 Drift Data for PS-5-14C Calibration As-Drift Drift Date Interval As-Left (Months)
Found (psig)
A 4/22/2007 24.4 123.1 126.3  
-2.4  
-0.21 4/9/2005 22.8 125.5 125.5 0.0 0.00 5/14/2003 17.3 119.0 125.5  
-6.0  
-0&#xfd;52 12/2/2001 21.8 134.0 125.0 10.0 0.87 2/5/2000 16.1 119.0 124.0  
-7.0  
-0.61 10/1/1998 4.4 119.0 126.0 4.0 0.35 5/21/1998 1.1 137.8 115.0 1.3 0.11 4/16/1998 22.1 136.5 136.5  
-1.6  
-0.14 6/12/1996 1.0 129.5 138.1 0.0 0.00 5/13/1996 18.7 167.5 129.5  
-8.0  
-0.70 10/20/1994 19.9 187.0 175.5 12.0 1.04 2/20/1993 166.0 175.0 Basic Statistics for PS-5-14C Average x
(psig) 0.2 Standard Deviation s
(psig) 6.5 Variance s 2 (psig) 41.9 Largest Positive Drift (psig) 12.0 Largest Negative Drift (psig)  
-8.0 Number of Samples n
11 Average x
(%)
0.02 Standard Deviation s
(%)
0.5626 Largest Positive Drift
(%)
1.04 Largest Negative Drift
(%)  
-0.70 Drift Trend Plot for PS-5-14C 0
20.0 10,0 *,,
10 0**
-1.0
-2 0.0 5/7/1990 1731/1 993 10/28/1995 712411998 4119/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14C -
- - +2s -
w...- -2s M/cah.
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 10 of 22 Drift Data for PS-5-14D Calibration Clbain As-  
.Drift Drift Date Interval As-As-Left Drift D
(Mnh)
Found (psig)
(%)
(Months) 4/2212007 24.4 122.3 124.8  
-0.7.  
-0.06 4/9/2005 22.8 123.0 123.0  
-2.5  
-0.22 5/14/2003 17.3 119.5 125.5  
-6.0  
-0.52 12/2/2001 21.8 133.8 125.5 8.8 0.77 2/5/2000 16.1 110.0 125.0  
-14.0  
-1.22 10/1/1998 4.4 118.0 124.0 4.5 0.39 5/2111998 1.1 145.0 113.5 7.5 0.65 4/16/1998 22.1 127.0 137.5  
-10.0  
-0.87 6/12/1996 1.0 135.0 137.0 5.5 0.48 5/13/1996 18.7 156.0 129.5  
-18.0  
-1.57 10/20/1994 19.9 193.5 174.0 17.5 1.52 2/20/1993  
.169.0 176.0 Basic Statistics for PS-5-14D Average x
(psig)  
-0.7 Standard Deviation s
(psig) 10.7 Variance s2 (psig) 114;8 Largest Positive Drift (psig) 17.5 Largest Negative Drift (psig)  
-18.0 Number of Samples n
11 Average x
(%).  
-0.06 Standard Deviation s
(%)
0.9318 Largest Positive Drift
(%)
1.52 Largest Negative Drift
(%)  
-1.57 Drift Trend Plot for PS-5-14D 30.0 -T-S20.0 -
AWLg 10.0 0.0
>-10.0 e--20.0 S-30.0 5/711990 1/3111993 10/28/1995 7/24/1998 4/19/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14D -.  
- -+2s 2s]
M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 11 of 22 Basic Statistics for Combined Drift Data Average (psig) 0.2 Standard Deviation s
(psig) 8.34 Variance s2 (psig) 69.6 Largest Positive Drift (psig) 18,0 Largest Negative Drift (psig)  
-18.0 Number of Samples 44 Average x
(%)
0,02 Standard Deviation s
(%)
0.7256 Largest Positive Drift
(%)
1.57 Largest Negative Drift
(%)  
-1.57 Micah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve ClosurelGenerator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 12 of 22 Outlier Test (t-Test) for Combined Data Set Equipment Calibration Drift Outlier?
ID (Months)
(psig)
T YESINO PS-5-14A 24.4 1.3 0.13 NO 22.8 0.0 0.02 NO 17.3  
.-5.0 0.62 NO 21.8 10.5 1.24 NO 16.1  
-11.0 1.34 NO 4.4 5.5  
.0.64 NO 1.1 0.0 0.02 NO 22.1 1.5 0.16 NO 1.0 7.0 0.82 NO 18.7  
-9.0 1.10 NO 19.9 16.5 1.96 NO PS-5-14B 24.4 2.5 0.28 NO 22.8  
-2.0 0.26 NO 17.3  
-4.0 0.50 NO 21.8 4.5 0.52 NO 16.1  
-11.0 1.34 NO 4.4 2.0 0.22 NO 1.1  
-2.5 0.32 NO 22.1  
-1.5 0.20 NO 1.0 4.0 0.46 NO 18.7  
-14.5 1.76 NO 19.9 18.0 2.14 NO PS-5-14C 24.4  
-2.4 0.31 NO 22.8 0.0 0.02 NO 17.3  
-6.0 0.74 NO 21.8 10.0 1.18 NO 16.1  
-7.0 0.86 NO 4.4 4.0 0.46 NO 1.1 1.3 0.13 NO 22.1  
--1.6 0.21 NO 1.0 0.0 0.02 NO 18.7  
-8.0 0.98 NO 19.9 12.0 1.42 NO PS-5-14D 24.4  
-0.7 0.10 NO 22.8  
-2.5 0.32 NO 17.3  
-6.0 0.74 NO 21.8 8.8 1.03 NO 16.1  
-14.0 1.70 NO 4.4 4.5 0.52 NO 1.1 7.5 0.88 NO 22.1  
-10.0 1.22 NO M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision..5 Drift Analysis Page 13 of 22 I
1.0 5.5 0.64 NO 18.7  
-18.0 2.18 NO 19.9 I 17.5 2.08 NO The outlier test shows that none of the individual T-statistics exceed the critical value of 2.91. The critical value was obtained from Table 9.2 of ESM-03.02-APP-lI1. Therefore, the data set contains no outliers.
M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass, Revisiorl.5 Drift Analysis Attachment'l Page 14 of 22 Normality Test - W Test X1 i
an-i+1 Xn-i+l bi
-18.0 1
0.3872 18.0 13.94
-14.5 2
0.2667 17.5 8.53
-14.0 3
0.2323 16.5 7.09
-11.0 4
0.2072 12.0 4.77
-11.0 5
0.1868 10.5 4.02
-10.0 6
0.1695 10.0 3.39
-9.0 7
0.1542 8.8 2.74
-8.0 8
0.1405 7.5 2.18
-7.0 9
0.1278 7.0 1.79
-6.0 10 0.1160 5.5 1.33
-6.0 11 0.1049 5.5 1.21
-5.0 12 0.0943 4.5 0.90
-4.0 13 0.0842 4.5 0.72
-2.5 14 0.0745 4.0 0.48
-2.5 15 0.0651 4.0
* 0.42
-2.4 16 0.0560 2.5 0.27
-2.0 17-0.0471 2.0 0.19
-1.6 18 0.0383 1.5 0.12
-1.5 19 0.0296 1:3 0.08
-0.7 20 0.0211 1.3 0.04 0.0 21 0.0126 0.0 0.00 0.0 22 0.0042 0.0 0.00 0.0 0.0 1.3 1.3 1.5 2.0  
=...
2.5 4.0 4.0 4.5 4.5 5.5 7.5 8.8 10.0 10.5 12.0 M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96.054 TITLE:,
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 15 of 22
-16.5 1
17.5 18.0 W Test Analysis n
44 S2 2993.8 b, '(bi) 54.2 W
0.982 P
0.944 Since W > P, the results of the W Test, do not provide any evidence to reject the assumption of normality.
Drift Tolerance Interval (TI)
TI=
* TIF
* TIF
* NAF s = 8.344031 TIF = 2.445 NAF= 1 TI = 20.40 M/cah MONTICELLO NUCLEAR GENERATING PLANT' CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass. Revision 5 DriftAnalysis Attachment 1 Page 16 of 22 Time Dependency Testing -Drift Interval Plot 0-0 E2 r0 n .c2 c cD, L? c Lo (N N (N (N (Bisd) :4j(M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 DriftAnalysis Attachment 1 Page 17 of 22 Time Dependency Testing -Binning Analysis 1 2 3 4 5 6 0 to 1.25 months > 1.25 to 3.75 > 3.75 to 7.5 > 7.5 to 15.0 > 15 to 22.5 > 22.5 to 30months months months months months Cl Drift Cl Drift Cl Drift Cl Drift Cl Drift CI Drift (Months) (psig) (Months) (psig) (Months) (psig) (Months) (psig) (Months) (psig) (Months) (psig)1.1 ' 0.0 4.4 5.5 17.3 -5.0 24.4 1.3 1.0 7.0 4.4 2.0 21.8 10.5 22.8 0.0 1.1 -2.5 4.4 4.0 16.1 -11.0 24.4 2.5 1.0 4.0 4.4 4.5 22.1 1.5 22.8 -2.0 1.1 1.3 18.7 -9.0 24.4 -2.4 1.0 0.0 19.9 16.5 22.8 0.0 1.1 7.5 17.3 -4.0 24.4 -0.7 1.0 5.5 21.8 4.5 22.8 -2.5 16.1 -11.0 22.1 -1.5 18.7 -14.5 19.9 18.0 17.3 -6.0 21.8 10.0 16.1 -7.0 22.1 -1.6 18.7 -8.0 19.9 12.0 17.3 -6.0 21.8 8.8 16.1 -14.0.............................
* NAF s  
..................... .... .......
=
---... ..2 2 .1 .. -1 0 .0 .-18.7 -18.0 19.9 17.5% of Valid?Bin #.Bin Range Count Total YESINO Bin # (months) Data 1 0 to 1.25 8 18.2 YES 2 > 1.25 to 3.75 0 0.0 NO.3 > 3.75 to 7.5 4 9.1 NO 4 > 7.5to 15.0 0 0.0 NO 5 > 15 to 22.5 24 54.5 YES 6 > 22.5 to 30 8 18.2 YES M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054' TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 18 of 22 Time Dependency Testing -Binninig Analysis, continued Bin # Drift Drift Drift Average Data Bin # .v r g Standard C o n Average Deviation CI Count1 2.9 3.67 1.1 8 2 ---...---
8.344031 TIF  
0 3 4.0 1.47 4.4 4 4 --- 0 5 -1.1 10.85 19.3 24 6 -0.5 1.80. 23.6 8 Time Dependency Plot 4.0 15.00= 3.0 2.0 10.00 1.0o U S0.01 5.00o 1.-1.0 1 .6 0-2. 0 0.00 Average Calibration Interval (Months).-Drift Average o---- Drift Standard Deviation M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 19 of 22 Time Dependency Testing -Regression Analysis (Final Data Set)
=
2.445 NAF=
1 TI  
=
20.40 M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT' CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass.
Revision 5 DriftAnalysis Page 16 of 22 Time Dependency Testing - Drift Interval Plot 0-0 E2 r0 n
c2 c
cD, L?
c Lo (N
N (N
(N (Bisd) :4j(
M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 DriftAnalysis Page 17 of 22 Time Dependency Testing - Binning Analysis 1
2 3
4 5
6 0 to 1.25 months  
> 1.25 to 3.75  
> 3.75 to 7.5  
> 7.5 to 15.0  
> 15 to 22.5  
> 22.5 to 30 months months months months months Cl Drift Cl Drift Cl Drift Cl Drift Cl Drift CI Drift (Months) (psig) (Months)
(psig)
(Months) (psig)
(Months)
(psig)
(Months) (psig)
(Months) (psig) 1.1 '
0.0 4.4 5.5 17.3  
-5.0 24.4 1.3 1.0 7.0 4.4 2.0 21.8 10.5 22.8 0.0 1.1  
-2.5 4.4 4.0 16.1  
-11.0 24.4 2.5 1.0 4.0 4.4 4.5 22.1 1.5 22.8  
-2.0 1.1 1.3 18.7  
-9.0 24.4  
-2.4 1.0 0.0 19.9 16.5 22.8 0.0 1.1 7.5 17.3  
-4.0 24.4  
-0.7 1.0 5.5 21.8 4.5 22.8  
-2.5 16.1  
-11.0 22.1  
-1.5 18.7  
-14.5 19.9 18.0 17.3  
-6.0 21.8 10.0 16.1  
-7.0 22.1  
-1.6 18.7  
-8.0 19.9 12.0 17.3  
-6.0 21.8 8.8 16.1  
-14.0 2 2. 1..  
-1 0.0.-
18.7  
-18.0 19.9 17.5
% of Valid?
Bin #.Bin Range Count Total YESINO Bin #
(months)
Data 1
0 to 1.25 8
18.2 YES 2  
> 1.25 to 3.75 0
0.0 NO.
3  
> 3.75 to 7.5 4
9.1 NO 4  
> 7.5to 15.0 0
0.0 NO 5  
> 15 to 22.5 24 54.5 YES 6  
> 22.5 to 30 8
18.2 YES M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054' TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 18 of 22 Time Dependency Testing - Binninig Analysis, continued Bin # Drift Drift Drift Average Data Bin #.
v r g Standard C
o n Average Deviation CI Count 1
2.9 3.67 1.1 8
2 0
3 4.0 1.47 4.4 4
4 0
5  
-1.1 10.85 19.3 24 6  
-0.5 1.80.
23.6 8
Time Dependency Plot 4.0 15.00
=
3.0 2.0 10.00 1.0o U
S0.01 5.00o 1.-1.0 1  
.6 0
-2. 0 0.00 Average Calibration Interval (Months)
Drift Average o---- Drift Standard Deviation M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 19 of 22 Time Dependency Testing - Regression Analysis (Final Data Set)


==SUMMARY==
==SUMMARY==
OUTPUT Regression Statistics Multiple R 0.110327 R Square 0.012172 Adjusted R Square -0.01135 Standard Error .8.391239 Observations 44 ANOVA Significance df SS MS F F Fcrit Regression 1 36.44073 36.44073 0.517529 0.475882 3.417947 Residual 42 2957.342 70.4129 Total 43 2993.783 Standard Lower Upper Lower Upper Coefficients Error t Stat P-value 95% 95% 95.0% 95.0%Intercept 1.831605 2.627369 0.697125 0.489565 3.47064 7.13385 3.47064 7.13385 x Variable 1 -0.10742 0.14932  
OUTPUT Regression Statistics Multiple R 0.110327 R Square 0.012172 Adjusted R Square  
-0.7194 0.475882 0.40876 0.19392 0,40876 0.19392 RESIDUAL OUTPUT Observation 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 Predicted Y-0.78522-0.61968-0.02799-0.51402 0.098797 1.363183 1.708336-0.53868 1.725946-0.17944-0.30623-0.78522-0.61968-0.02799-0.51402 0.098797 1.363183 Residuals 2.085216 0.619684-4.97201 11.01402-1I1.0988 4.136817-1.70834 2.038678 5.274054-8.82056 16.80623 3.285216-1.38032-3.97201 5.014025-11.0988 0.636817 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve ClosurelGenerator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment I Page 20 of 22 18 1.708336 -4.20834 19 -0.53868 -0.96132 20 1.725946 2.274054 21 -0.17944 -14.3206 22 -0.30623 18.30623 23 -0.78522 -1.61478 24 -0.61968 0.619684 25 -0.02799 -5.97201 26 -0.51402 10.51402 27 0.098797 -7.0988 28 1.363183 2.636817 29 1.708336 -0.40834 30 -0.53868 -1.06132 31 1725946 -1.72595 32 -0.17944 -7.82056 33 -0.30623 12.30623 34 -0.78522 0.085216 35 -0.61968 -1.88032 36 -0.02799 -5.97201 37 -0.51402 9.314025 38 0.098797 -14.0988 39 1.363183 3.136817 40 1.708336 5.791664 41 -0.53868 -9.46132 42 -1.725946 3.774054 43 -0.17944 -17.8206.44 -0.30623 17.80623 Line Fit Plot 20.0 15.0 1.0.0 -.0 25.00 .0-300 15. 0-20. 0 Calibration Time Interval (Months)E Drift , Predicted Drift M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator LoadReject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 21 of 22 Time Dependency Testing -Regression Analysis (Absolute Values of Final Data Set)
-0.01135 Standard Error.
8.391239 Observations 44 ANOVA Significance df SS MS F
F Fcrit Regression 1 36.44073 36.44073 0.517529 0.475882 3.417947 Residual 42 2957.342 70.4129 Total 43 2993.783 Standard Lower Upper Lower Upper Coefficients Error t Stat P-value 95%
95%
95.0%
95.0%
Intercept 1.831605 2.627369 0.697125 0.489565 3.47064 7.13385 3.47064 7.13385 x
Variable 1  
-0.10742 0.14932  
-0.7194 0.475882 0.40876 0.19392 0,40876 0.19392 RESIDUAL OUTPUT Observation 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 Predicted Y
-0.78522
-0.61968
-0.02799
-0.51402 0.098797 1.363183 1.708336
-0.53868 1.725946
-0.17944
-0.30623
-0.78522
-0.61968
-0.02799
-0.51402 0.098797 1.363183 Residuals 2.085216 0.619684
-4.97201 11.01402
-1I1.0988 4.136817
-1.70834 2.038678 5.274054
-8.82056 16.80623 3.285216
-1.38032
-3.97201 5.014025
-11.0988 0.636817 M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve ClosurelGenerator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment I Page 20 of 22 18 1.708336  
-4.20834 19  
-0.53868  
-0.96132 20 1.725946 2.274054 21  
-0.17944  
-14.3206 22  
-0.30623 18.30623 23  
-0.78522  
-1.61478 24  
-0.61968 0.619684 25  
-0.02799  
-5.97201 26  
-0.51402 10.51402 27 0.098797  
-7.0988 28 1.363183 2.636817 29 1.708336  
-0.40834 30  
-0.53868  
-1.06132 31 1725946  
-1.72595 32  
-0.17944  
-7.82056 33  
-0.30623 12.30623 34  
-0.78522 0.085216 35  
-0.61968  
-1.88032 36  
-0.02799  
-5.97201 37  
-0.51402 9.314025 38 0.098797  
-14.0988 39 1.363183 3.136817 40 1.708336 5.791664 41  
-0.53868  
-9.46132 42 -1.725946 3.774054 43  
-0.17944  
-17.8206.
44  
-0.30623 17.80623 Line Fit Plot 20.0 15.0 1.0.0 -
0*.0 25.00  
.0-300
: 15. 0
-20. 0 Calibration Time Interval (Months)
E Drift, Predicted Drift M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator LoadReject SCRAM Bypass Revision 5 Drift Analysis Page 21 of 22 Time Dependency Testing - Regression Analysis (Absolute Values of Final Data Set)


==SUMMARY==
==SUMMARY==
OUTPUT Regression Statistics Multiple R 0.181127 R Square 0.032807 Adjusted R Square 0.009779 Standard Error 5.255246 Observations 44 ANOVA Significance df SS MS F F Fcrit Regression 1 39.34483 39.34483 1.424629 0.239342 3.417947 Residual 42 1159.939.
OUTPUT Regression Statistics Multiple R 0.181127 R Square 0.032807 Adjusted R Square 0.009779 Standard Error 5.255246 Observations 44 ANOVA Significance df SS MS F
27.61761 Total 43 1199.284 Standard Lower Upper Lower Upper Coefficients Error t Stat P-value 95%
F Fcrit Regression 1 39.34483 39.34483 1.424629 0.239342 3.417947 Residual 42 1159.939. 27.61761 Total 43 1199.284 Standard Lower Upper Lower Upper Coefficients Error t Stat P-value 95%
95% 95.0% 95.0%Intercept 4.667286 1,645462 2.836459 0.006991 1.346609 7.987963 1.346609 7.987963 x Variable 1 0.111618 0.093516 1.193578 0.239342 -0,0771 0.300341 -0.0771 0.300341 RESIDUAL OUTPUT Predicted Observation Y Residuals 1 7.386381 -6.08638 2 7.214379 -7.21438 3 6.599563 -1.59956 4 7.10459 3.39541 5- 6.467817 4.532183 6 5.154015 0.345985 7 4.795373 -4.79537 8 7.1302QB -5.63021 9 4.777075 2.222925 10 6.756927 2.243073 11 6,888673 9.611327 12 7.386381 -4.88638 13 7.214379 -5.21438 14 6.599563 -2.59956 15 7.10459 -2.60459 16 6.467817 4.532183 17 5.154015 -3.15401 18 4.795373 -2.29537 M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TtTLB: 4 Aflrine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 1 Page 22 of 22 19 7.130208 -5.63021 20 4.777075 -0.77707 21 6.756927 7.743073 22 6.888673 11.11133 23 7,386381 -4.98638 24 7.214379 -7.21438 25 6.599563 -0.59956 26 -7.10459 2.89541 27 6.467817 0.532183 28 5.154015 -1.15401 29 4.795373 -3.49537 30 7.130208 -5.53021 31 4.777075 -4.77707 32 6.756927 1.243073 33 6.888673 5.111327 34 7.386381 -6.68638 35 7.214379 -4.71438 36 6.599563 -0.59956 37 7.10459 1.69541 38 6.467817 7.532183 39 5.154015 -0.65401 40 4.795373 2.704627 41 7.130208 2.869792 42 4.777075 0.722925 43 6.756927 11.24307 44 6.888673 10.61133 Line Fit Plot 20.0 -16.0 .14.0-12.90 10.0 <8.0 6.0 4.0 -2.0 0.00.0 5.0 10.0 '15.0 20.0 25.0 30.0 Calibration Time Interval (Months)[ Drift @ Predicted Drift M/cah MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 2 Page 1of 2~25OI ~flPO!AQ SC .~W I-0 ii'H~2~O/-fR~SSURE ~Cr~T 1~4  
95%
~ / -AMJ~CO ECMALC  
95.0%
~N~O ( E~ C1~)~-! A2t All :th e s lons fr w.........................................
95.0%
V .h, G1 12 MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 I Drift Analysis Attachment 2 Page 2 of 2 Pressure Switch Products,~J Chlraetriserc At rnoees ircorpo reteU01rvrztrs L aireories.
Intercept 4.667286 1,645462 2.836459 0.006991 1.346609 7.987963 1.346609 7.987963 x
fac ~rd CFA List10 si&#xfd;,!P noee rreOsup-cnereeresu swenens. -Typo S POT Snap -"In: v Jrjl cc Rain 1mrp cc 125F250 VAc 3 AxD @4U VAC-,L O.A rrpCa24 VtC Temperature Raene Operating stcrage Atijuteina leu lioing Le. n d W &#xfd;iIiL , Awvacabe ufern requcs (c~uS&#xfd;.i tre,:Ceyl
Variable 1
-2yt -.IW5 ID ,,.I Gs-4~)uklm I Cir cuit 2rk'eInIne Sh- irpping Weight$tzpped Model-* ileHosoed Model-*Weted Parsra -Process Ffhtinq a Btourdon Tube -En~clsure Rating5 Stripped Model Iloused Model Nresure Connoctian NFAA4 pron~snreeUP i~fs600;i.n IM-N 1!4' iPT ujte. -Comsul Fnstnry tor ThQ-as Cltc NErdA4 -1 Tempeialutee5Aedowaxi Clat, odtseeYCgesSe&#xfd;&#xfd;ce  
0.111618 0.093516 1.193578 0.239342  
: rndisaO&#xfd;L r&#xfd;I'd(UL a5 CSA apvvl atne labbns or. ts i Sep-trinsl Connaeton Stipped HlinSed21' Free bea1&#xfd; ;In ler nal iernn-i s'jip v,3oia cern ( 0 rn c&#xfd;1In DIS ely <-err -COt4TIOOL.
-0,0771 0.300341  
PROISLiOrS
-0.0771 0.300341 RESIDUAL OUTPUT Predicted Observation Y
: 3.
Residuals 1
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass -Revision 5 Drift Analysis Attachment 4 Page 1 of 1 MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE: Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment 5 Page 1 of I For Illustration Only Not to Scale Pressure psig Analytical Limit Allowable Value NTSP 1 NTSP 2 Setpoint (NTSP)125.7 118.0 117 As-Found+22 psig 105.0 102.6 97 95 93 As-Left+/-2 psig As-Found-22 psig 73 Maximum Switch Deadband 27 psig 46 M/cah}}
7.386381  
-6.08638 2
7.214379  
-7.21438 3
6.599563  
-1.59956 4
7.10459 3.39541 5-6.467817 4.532183 6
5.154015 0.345985 7
4.795373  
-4.79537 8
7.1302QB  
-5.63021 9
4.777075 2.222925 10 6.756927 2.243073 11 6,888673 9.611327 12 7.386381  
-4.88638 13 7.214379  
-5.21438 14 6.599563  
-2.59956 15 7.10459  
-2.60459 16 6.467817 4.532183 17 5.154015  
-3.15401 18 4.795373  
-2.29537 M/cah
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TtTLB: 4 Aflrine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 22 of 22 19 7.130208  
-5.63021 20 4.777075  
-0.77707 21 6.756927 7.743073 22 6.888673 11.11133 23 7,386381  
-4.98638 24 7.214379  
-7.21438 25 6.599563  
-0.59956 26  
-7.10459 2.89541 27 6.467817 0.532183 28 5.154015  
-1.15401 29 4.795373  
-3.49537 30 7.130208  
-5.53021 31 4.777075  
-4.77707 32 6.756927 1.243073 33 6.888673 5.111327 34 7.386381  
-6.68638 35 7.214379  
-4.71438 36 6.599563  
-0.59956 37 7.10459 1.69541 38 6.467817 7.532183 39 5.154015  
-0.65401 40 4.795373 2.704627 41 7.130208 2.869792 42 4.777075 0.722925 43 6.756927 11.24307 44 6.888673 10.61133 Line Fit Plot 20.0 -
16.0 14.0-12.90 10.0 8.0 6.0 4.0 -
2.0 0.0 0.0 5.0 10.0  
'15.0 20.0 25.0 30.0 Calibration Time Interval (Months)
[ Drift @ Predicted Drift M/cah
 
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Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 1of 2
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Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 I
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MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass  
-Revision 5 Drift Analysis Page 1 of 1
 
MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:
Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 1 of I For Illustration Only Not to Scale Pressure psig Analytical Limit Allowable Value NTSP1 NTSP 2 Setpoint (NTSP) 125.7 118.0 117 As-Found
+22 psig 105.0 102.6 97 95 93 As-Left
+/-2 psig As-Found
-22 psig 73 Maximum Switch Deadband 27 psig 46 M/cah}}

Latest revision as of 11:44, 14 January 2025

Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass
ML091410123
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/06/2009
From: Kolodziejczyk E
Northern States Power Co, Xcel Energy
To:
Office of Nuclear Reactor Regulation
References
L-MT-09-026, TAC MD9990 96-054, Rev 5
Download: ML091410123 (51)
v • d • e


Text

QF-2116, Rev 3 (FP-G-RM-01)

Page 1 of 2 RECORD INFORMATION SHEET Doc Type/Sub Type:

CALC Document Number:

96-054 R5

Title:

Turbine Stop ValveClosurelGenerator Load Reject Scram Bypass F1 1. The following record has been identified as either illegible on microfilm or identified as uncertain whether it will be legible on microfilm. A copy has been filmed for "reference only" and the originals are maintained in hard copy.

F-2. The following record has illegible or missing information that has been reviewed and deemed the "best available copy". A member of the originating organization has signed and dated below after commenting on the illegible or missing information. The record will not be retained in hardcopy.

F] 3. The following record or item is stored in hard copy due to inability to transfer to microfilm.

[

4. The following calculation and attachments have been reviewed and deemed acceptable as legible as a QA record.

Pages / Items Description I Comments Print/Sign: Au CM. LF-x

/

A

_,ý*

Date: 0S"1 1*

Form retained in accordance with record rete n schedule identified in FP-G-RM-01.

QF-0549 (FP-E-CAL-01) Rev. 3 Paae 1 of 6

~XceEnergT Calculation Signature Sheet Document Information NSPM Calculation (Doc) No:

TRevision:

Title:

Facility: 0 MT E-I PI Unit: 0 1 El2 Safety Class:

Z SR El Aug Q El Non SR Special Codes: E] Safeguards El Proprietary Type: Calc Sub-Type:

I-NOTE:

LPrint and sign name in signature blocks, as required.

ajor.RevisionsZ6 EC Number4*4 I'.,2Z

[] Vendor Cale Vendor Name or Code:

Sargent & Lundy Vendor Doc No:

De iDtion of in:

Prepared by: RE M Date:

Reviewed by:

(,.

)

Date: 0_--o -0 7 Type of Review: E] Design Verification El Tech Review(f Vendor Acce Method Used (For DV only )

ReMR iew Alternate Calc Fl Test Approved by:

,Date:.

6--*--

1 Minor Revisions EC No:

7E

[]Vendor Calc:

Minor Rev. No:

Description of Change:

Pages Affected:

Prepared by:

Date:

Reviewed by:

j Date:

Type of Review: El Design Verification El Tech Review El Vendor Acceptance Method Used (For DVbOnly): El Review [l Alternate Calc E] Test Approved by:

Date:

(continued on next page)

Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0549 (FP-E-CAL-01), Rev. 3 Page 2 of 6 XcelEnergy" Calculation Signature Sheet EC No:

El

[vendor Calc:

Minor Rev. No:

Description of Change:

Pages Affected:

Prepared by:

Date:

Reviewed by:/

Date:

Type of Review: EI Design Verification Ei Tech Review -- Vendor Acceptance Method Used (For DV Only): E] Review L] Alternate Calc EL Test Approved by:

Date:

EC No:

i [Vendor Caic:

Minor Rev. No:

Description of Change:

Pages Affected:

Prepared by:

Date:

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Pate:

Type of Review: EL Design Verification Li Tech Review [] Vendor Acceptance Method Used (For DV Only): Li Review EL Alternate Calc Li Test Approved by:

FDate:J EC No:

il Vendor Calc:

Minor Rev. No:

Description of Change:

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Prepared by:

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I Date:

Record Retention: Retain this form with the associated calculation for the life of the plant.

NOTE:

This reference table is used for data entry into the PassPort Controlled Documents Module, reference tables (C012 Panel). It may also be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed.

Reference Documents (PassPort C012 Panel from C020)

Controlled*

Document Name Document Number Doc Ref Type**

Doc? + Type Rev (if known)

I General Electric Instrument Setpoint Methodology NEDC-31336P-A 1996

]lnput L--]Output 2L--

GE-NE-901-021-

input El-Output Setpoint Calculation Guidelines for the Monticello 0492 Nuclear Generating Plant DRF A0001 932-1 3

F]

Guidelines for Instrument Calibration TR-1 03335-Rl iinput l:]Output Extension/Reduction Programs -

4 F-1 Task Report T0502, Nuclear Management Company i]nput Loutput Monticello Nuclear Generating Plant Extended Power T0502 Uprate 5

Monticello Updated Safety Analysis Report. Plant USAR-07.06 25P Zinput [:IOutput Instrumentation and Control Systems: Plant Protection System 6

Operations Manual B.05.06. Plant Protection System B.05.06 lnput Llutput 7

F-Generic Letter 91-04, Changes in Technical Zlnput E]Output Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle 8

[]

Elnput D-loutput 10 Fl

[:]input [:]output 11 F_

r--linput Doutput 12W r-

_3lnput Woutput Record Retention: Retain this form with the associated calculation for the life of the plant.

13 Wl

-]Input Eji]Output 14 WInput W-Output 15 WlInput [-]Output 16 I-E

_]Input

[:]Output 17 E--_

-]Ilnput -]Output

  • Controlled Doc checkmark means the reference can be entered on the C012 panel in black. Unchecked lines will be yellow. If checked, also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.)
    • Corresponds to these PassPort "Ref Type" codes: Inputs/Both = ICALC, Outputs = OCALC, Other/Unknown = blank)

Other PassPort Data Associated System (PassPort C011, first three columns)

OR Equipment References (PassPort C025, all five columns):

Facility Unit System Equipment Type Equipment Number PREASURE PS-5-14A/B/C/D SWITCHES Superseded Calculations (PassPort C01 9):

Facility Calc Document Number Title MT CA-96-054 Rev. 4 TURBINE STOP VALVE CLOSURE/GENERATOR LOAD REJECT SCRAM BYPASS SETPOINT CALCULATION Record Retention: Retain this form with the associated calculation for the life of the plant.

Monticello Specific Information IZ DBD Topic Code(s) (See MT Form 3805):

RATE F-1 DBD Structural Code(s) (See MT Form 3805): #*j Does the Calculation:

F1 YES Z No Affect the Fire Protection Program? (If Yes, Attach MT Form 3765)

[I YES

[9 No Affect piping or supports? (If Yes, Attach MT Form 3544)

El YES. Z No Affect IST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation)

Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0547 (FP-E-MOD-11) Rev. 1

[ _ XceIEnergy" External Design Document Suitability Review Checklist External Design Document Being Reviewed:

Title:

f....

"a-e*sI I

t e t c

Number:

I e.

Rev:

  • Date:

____/_L__

This design document was received from:

Organization Name:

Sargent & Lundy PO or DIA

Reference:

The purpose of the suitability review is to ensure that a calculation, analysis or other design document provided by an External Design Organization complies with the conditions of the purchase order and/or Design Interface Agreement (DIA) and is appropriate for its intended use. The suitability review does not serve as an independent verification. Independent verification of the design document supplied by the External Design Organization should be evident in the document, if required.

The reviewer should use the criteria below as a guide to assess the overall quality, completeness and usefulness of the design document. The reviewer is not required to check calculations in detail.

REVIEW Check

1.

Design inputs correspond to those that were transmitted to the External Design Organization.

2.

Assumptions are described and reasonable.

3.

Applicable codes, standards and regulations are identified and met.

4.

Applicable construction and operating experience is considered.

5.

Applicable structure(s), system(s), and component(s) are listed.

H;

6.

Formulae and equations are documented. Unusual symbols are defined.

EIr

7.

Acceptance criteria are identified, adequate and satisfied.

8.

Results are reasonable compared to inputs.

9.

Source documents are referenced.

10.

The document is appropriate for its intended use.

11.

The document complies with the terms of the Purchase Order and/or DIA.

12.

Inputs, assumptions, outputs, etc. which could affect plant operation are enforced

?

by adequate procedural controls. List any affected procedures. 0 *,*-d2

13.

Plant impact has been identified and either implemented or controlled. (e.g., For piping analyses, the piping and support database is updated or a tracking item has been initiated.)

Completed by:

_Date:

6---6I -o 2

Page 1 of 1

Calculation no.96-054 TABLE OF CONTENTS Item QF-0549 QF-0547 TOC SOP-0402-07 Calculation Attachment Attachment Attachment Attachment Attachment Description Calculation Signature Sheet External Design Document Suitability Review Checklist Table of Contents S & L Issue Summary Body Pages 6

1 1

2 3

4 5

1 16 222 3

1 1

Total pages 54 I1

ISSUE

SUMMARY

Form SOP-0402-07, Revision 7B DESIGN CONTROL

SUMMARY

CLIENT:

Northern States Power Company UNIT NO.:

1 Page No.: 1 PROJECT NAME:

Monticello Nuclear Generating Plant PROJECT NO.:

12400-009 Z

NUCLEAR SAFETY-RELATED CALC. NO.:

CA-96-054, Revision 5 El NOT NUCLEAR SAFETY-RELATED TITLE:

Turbine Stop Valve Closure/Generator Load Reject Scram Bypass EQUIPMENT NO.:

PS-5-14A,B,C,D IDENTIFICATION OF PAGES ADDED/REVISED/SUPERSEDEDNOIDED & REVIEW METHOD This revision completely supersedes Revision 4 INPUTS/ ASSUMPTIONS El VERIFIED M UNVERIFIED REVIEW METHOD:

Detailed REV.

5 STATUS:'

Approved DATE FOR REV.:

4/21)2009 PREPARER Eric Kolodziejczyk

.44 DATE:

4/21/2009 REVIEWER John O'Hara / Greg Rainey "

/

DATE:

4/21/2009 APPROVER Steven Malak DATE:

4/21/2009 IDENTIFICATION OF PAGES ADDED/REVISEOD/SUPERSEIDED/VOIDED

&REVIEW METHOD INPUTS1 ASSUMPTIONS El VERIFIED Dl UNVERIFIED REVIEW METHOD; REV.

STATUS:

DATE FOR REV.:

PREPARER DATE:

REVIEWER DATE:

APPROVER DATE:

IDENTIFICATION OF PAGES ADDED/REVISED/SUPERSEDEDNVOIDED & REVIEW METHOD INPUTS/ ASSUMPTIONS El VERIFIED El UNVERIFIED REVIEW METHOD:

REV.

STATUS:

DATE FOR REV,:

PREPARER DATE:

REVIEWER DATE:

APPROVER DATE:

NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS SOP040207,DOC Page 1 of 1 Rev. Date: 11-12-2007 (I'

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 1 of 16

1.

PURPOSE This calculation performs. a setpoint calculation for the turbine stop valve closure and generator load reject scram bypass signal provided by pressure switches PS-5-14A/B/C/D. This calculation affects the Reactor, Protection System and ensures that above Pbypass (Input 4.7) reactor thermal power the scram bypass signal is deactivated.

Revision 5 of this calculation updates the analyzed drift values to reflect the current 24-month calibration interval.

Revision 4 of this calculation reflects turbine replacement for both EPU (Extended Power Uprate) and CLTP (Current Licensed Thermal Power) and adjusts the operation setpoint to reflect the new turbine first stage pressure curve. Additionally, revisions are incorporated to meet the current setpoint control program standards with the guidance of ESM-03.02-APP-I (Input 4.1).

Revision 3 of this calculation reflected the results of turbine testing during startup from the 1998 refueling outage and adjusts the setpoints for the higher steam flow/lst stage turbine pressure resulting from rerate.

2.

METHODOLOGY This calculation is performed using the GE Setpoint Methodology as a guide as described in Appendix I to Engineering Standards Manual Section ESM-03.02, Revision 4, Design Requirements, Practices, & Topics (Instrumentation and Controls) (Input 4.1). This methodology utilizes statistical estimates of the various instrument errors to achieve conservative, but reasonable, predictions of instrument channel uncertainties. The objective of the statistical approach to setpoint calculations is to achieve a workable compromise between the need to ensure instrument trips when appropriate, and the need to avoid spurious trips that may unnecessarily challenge safety systems or disrupt plant operation.

The setpoint established in this calculation is considered a non-safety related setpoint. An Analytical Limit and Allowable Value (Tech Spec value) are typically only associated with safety-related setpoints. The GE methodology does not clearly discuss the treatment of -non-safety-related setpoints; however, the MNGP methodology states that the Allowable'Value calculation does not apply to setpoints for which an AV is not documented in the Tech Spec.

The previous revision of this calculation establishes an Analytical Limit and calculates. an Allowable Value. Therefore, this calculation will retain the AL terminology and AVcalculatipn.

Per Input 4.1, the Spurious Trip Avoidance Evaluation is satisfied using engineering judgment.

See Section 6.5.8 for more details.

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Genbrator Load Reject Revision 5 ScrarnBypass Page 2 of 16 The determination of the pressure switch drift value used in this calculation is performed in accordance with ESM-03.02-APP-lIl (Input 4.2).

3.

ACCEPTANCE CRITERIA The Nominal Trip Setpoint (NTSP), Allowable Value (AV) and instrument settings should be established such that the Analytical Limit will not be exceeded when all applicable instrumentation uncertainties are considered. The existing setpoints and As-found/As-left ranges will be verified to provide sufficient margin using the GE methodology as a guide. A setpoint value will be established with a 95%/95% tolerance interval as a criteria of uncertainties (Input 4.2). That is, there is a 95% probability that the constructed limits contain 95% of the population of interest for a 24-month +25% calibration interval (Reference 10.7) for the pressure switches. If the existing setpoint and ranges do not provide sufficient margin, new setpoints or ranges will be specified by this calculation.

4.

INPUTS 4.1 Engineering Standards Manual ESM-03.02-APP-I, Revision 4, GE Methodology (Instrumentation and Controls). The ESM provides plantspecific guidance on the implementation of the General Electric methodology (Reference 10.1) and guidelines (Reference 10.2).

4.2 Engineering Standards Manual ESM-03.02-APP-Ill, Revision 5, Drift Analysis (Instrumentation and Controls). The. ESM provides.plant specific guidance on the implementation of the EPRI guidelines on drift analysis (Reference 10.3).

95%/95% Tolerance Factor for 44 data points 2.445 (Table 9.1) 99%/95% Tolerance Factor for 44 data points 2.677 (Table 9.1) 4.3 Monticello Component Master List (CML). The CML contains information regarding-the pressure switches and calibration tools listed in this calculation.

Device Calibration Interval PS-5-14A,B,C,D 24 months Calibration Device Description XPI-9021 Ashcroft 2089 XPS-95171 L Mansfield and Green TQ-50 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 3 of 16 4.4 Calculation CA-98-010, Revision 6, Environmental Qualification (DOR) of Barksdale Pressure Switches. EQ Calculation File 0910-106EQ-05.

4.5 Calculation CA-95-027, Revision 1, Determination of Instruments Service Conditions for Input Into Setpoint Calculations. M04230-0065. Data.obtained from this input is listed in Section 6.2.2.

4.6 MNGP EPU Task Report T0700: EC 12473, Letter GE-MNGP-AEP-196, 1st Stage Shell Pressure curve, dated August 1, 2007 (Attachment 3).

% Rated Thermal Power (Input 4.7)__

1st Stage Shell Pressure 25% (EPU) 28.2% (CLTP) 140.0 psia (125.3 psig) 4.7 MNGP EPU Task Report T0900: Transient Analysis EC11830. GE-NE-0000-0062-2932 OPL-3, Transient Protection Parameters Verification for Reload Licensing Analysis.

Parameter CLTP EPU Rated Power 1775 MWt 2004 MWt Pbypass 45% RTP 40% RTP 4.8 Memo from John Hess (GE) to Jim Devine (MNGP) dated March 15, 1996 (Attachment 4).

4.9 MNGP EPU Task Report T1004: Environmental Qualification EC11836, Rev. 0. March 2008. This Input demonstrates environmental conditions used in the evaluation of Inputs 4.4 and 4.5 will not change due to EPU.

4.10 NX-63626, Ashcroft Digital Test Gauge Operating Instructions.

4.11 Calibration Device Range Accuracy XPI-9021 (Ashcroft 2089) 0-500 psig 0.05% Full Scale NX-17448, Mansfield and Green Pneumatic Dead Weight Tester.

Calibration Device Range Accuracy XPS-95171 (Mansfield and Green TQ-50) 100-5000 psig 0.025% Reading M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 4 of 16

5.

ASSUMPTIONS Validated Assumptions:

5.1 The GE memo from John Hess to Jim Devine of MNGP (Attachment 4) cites a 3%

process measurement uncertainty based on unexpected changes in flow coefficients

  • and tolerances on machining. The memo discusses tolerances prior to EPU. However, the tolerances on machining are not dependant on pressure or flow. Therefore, this process measurement uncertainty is assumed to remain applicable at EPU. conditions.

5.2 No seismic data is available for the Barksdale Switches. Per Input 4.5, the Zero Period Acceleration at the switches is 0.26g. This value is low enough to consider normal vibration effects negligible. Therefore, SE is taken to be 0.

5.3 Error effects due to Static Pressure Effects (SPE), typically associated with differential pressure instruments, are assumed negligible for Gauge pressure instruments since ambient pressure is considered constant.

5.4 No vendor specification is available for Accuracy Temperature Effect (ATE). ATE will be considered included in the vendor accuracy. Since normal temperature range is within the vendor specified temperature limits, effects due to normal temperature variations are considered to be included in the Analyzed Drift.

5.5 The Readability Error associated with reading the impulse pressure curve in Attachment 3 is taken to be one quarter of one minor division.

Unvalidated Assumptions:

5.6 The first stage pressure and thermal power relationship according to Input 4.6 needs to be validated during start-up testing.

Note: The percent power relationship given in Attachment 3 assumes that the reactor is providing steam to the turbine and that other auxiliary steam loads are not significantly affecting thermal power. This may require procedural changes to assure that auxiliary steam loads are secured during.start up testing....

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 5 of 16

6.

ANALYSIS 6.1 Instrument Channel Arrangement 6.1.1 Loop Information:

Definition of Channel:

Each instrument channel is comprised of a turbine first stage pressure switch and an associated relay. Each relay provides input to the Reactor Protection System (RPS) scram logic in order to bypass scrams initiated by turbine stop valve closure and control valve fast closure during low reactor power conditions. At these low reactor power conditions, the turbine bypass valves have sufficient capacity to bypass the steam without increasing reactor vessel pressure to unsafe levels. The bypass signal logic is two out of two once. The reactor power level associated with the bypass signal is established at the same thermal power as prior to EPU (30% of 1775 MWt). This corresponds to an EPU reactor power of 26.6% at 2004 MWt. However, the Analytical Limit will be taken as a more conservative 25% reactor power (28.2% CLTP) for the purposes of this calculation. Once the switch pressure setpoint is exceeded, the scram bypass signal is deactivated. The scram bypass signal is reactivated on decreasing reactor power, once the switch reset limit has been reached.

6.1.2 Loop Diagram:

Pressure Switch elay 6.2 Instrument Definition and Determination of Device Error Terms 6.2.1 Instrument Definition:

I Reference Component ID:

PS-5-14A,B,C,D Location:

East Shield Wall[(TB-951)

4.3 Manufacturer

Barksdale 4.3 Model Number:

B2T-A1 2SS 4.3 Upper Range Limit (URL):

1200 psig 4.3 Adjustable Range 50-1200 psig 4.3 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 6 of.16 6.2.2 Vendor Performance Specs

+/-0.5% of Adfustable Range Att. 2 PS-5-14A,B,C,D:

Input Signal Output Signal First Stage Contact Closure 4.3 Turbine Pressure at setpoint Process and Physical Interfaces:

Calibration Conditions:

Reference Calibration Temperature Range:

65 to 90OF 4.5, 4.9 Calibration/Surveillance Interval:

24 months +/-25%

4.3 Normal Plant Conditions:

Temperature:

60 to 104 0F 4.5, 4.9 Radiation:

Negligible 4.5, 4.9 Pressure:

Ambient 4.5, 4.9 Humidity:

120-100%

4.5, 4.9 Trip Environment Conditions:

Temperature:

60-104OF 4.5, 4.9 Radiation:

Negligible 4.5, 4.9 Pressure:

Ambient 4.5, 4.9 Humidity:

100%

4.5, 4.9 Seismic ZPA:

PS-5-14A/B 0.26g 4.5 PS-5-14C/D 0.24g 4.5 Process Conditions; During Calibration:

Not Applicable Worst Case:

Not Applicable M/cah

MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE:

Turbine Stop Valve ClosurelGenerator Load-Reject R

5vision5 Scram Bypass Page 7 of 16 6.2.3 Device Accuracy:

Sigma Reference Vendor Accuracy:

VA +/-0.5% (Full Scale) 3 Att..2, Note 1 Accuracy Temperature Effect:

ATE=0.0 5.4, Note 2 Over Pressure Effect:

OPE=0.0 Note 3 Static Pressure Effect:

SPE=Not applicable 5.3, Note 4 Seismic Effect:

SE=0.0 5.2, Note 5 Radiation Effect:

RE=Not applicable Note 6 Humidity Effect:

HE=Included in VA 4.4, Note 7 Power Supply Effect:

PSE=Not applicable Note 8 Radio/EM Interference REE=Not applicable Note 8 Note 1:

VA=Vendor Accuracy VA = 0.5% x Full Scale VA = 0.005 x 1200 = 6.0 psig Note 2:

No vendor specification is available for ATE. Accuracy temperature effect will be considered included in the vendor accuracy. Since this instrument is not subject to a harsh environment, most of the temperature effect is considered in the Analyzed Drift.

Note 3:

These switches have a proof pressure of 1800 psig which exceeds the pressure that they will be exposed to. As such, Over Pressure Effect is taken to be equal to 0.

Note 4:

Error effects due to Static Pressure Effects (SPE) are negligible for gauge pressure instruments.

Note 5:

No seismic data is available for the Barksdale Switches. Per Input 4.5, the Zero Period Acceleration is 0.26g. This value is low enough to consider normal vibration effects negligible.

Note 6:

Per Input 4.5, radiation dose is considered negligible for the pressure switch location. Therefore, Radiation Effect is considered negligible.

Note 7:

Per input 4.4, the Barksdale switches are Enviironmentally Qualified for a relative humidity of 100%. Therefore, Humidity Effect is considered included in the VA.

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 8 of 16 Note 8:

Error effects due to Power Supply Effects (PSE) and RFI/EMI Effects (REE) are not applicable for bi-stable electro-mechanical devices (Reference 10.2) 6.2.4 Device Drift:

Sigma Reference I Analyzed Drift I AD=+/-23.0 psig 2 1 Attachment 1 A drift analysis using instrument calibration history is included in Attachment 1 for determining the 24 month plus 25% drift.

Per Section A1.8 of Attachment 1, bias will not be considered for the pressure switches.

ADbias = 0.0 The random portion of the Analyzed Drift is calculated by multiplying the Standard Deviation (s) of the final data set by the 95%/95% Tolerance Interval Factor (TIF95/95) and by the normality adjustment factor (NAF):

ADrandom = s x TJF9,/95 x NAF ADradoi, =8.34 x 2.445 x 1

,Drando,, =20.4psig (23.6 months)

The extended calibration interval of 24 months plus 25% is calculated by multiplying the random portion of the Analyzed drift by a scaling factor to extrapolate the drift uncertainty.

See Section A1.9 of Attachment 1 for more detail.

a d

ýCIo ADEr,,*o,, = 20.4x 23.6

= 23.Opsig (30 months)

Analyzed Drift AD = DL = +/- 23.0 psig M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 9 of 16 6.2.5 As Left Tolerance (ALT):

The suggested limit on the magnitude of the ALT per Input 4.1 is given as:

ALT 2

T J(VA) + (c)2 + (CST,)Y 3

ALT 2 V(6.0)2 + (0.25)2 + (0.125)2 4.0 3

(Calibration error terms are calculated in Section 6.2.6)

An ALT of up to 4.0 psi is acceptable based on the methodology suggested in Input 4.1.

However, previous instrument performance (Input 4.3) suggests that a smaller ALT value is routinely achievable. The existing As-Left Tolerance specified on the calibration worksheet is +/- 2.0 psi. The ALT will remain at +/- 2.0 psi.

6.2.6 Device Calibration Error:

Value Sigma Reference Calibration Tool Error Cj:

0.25 psi 3

4.10, Note I Tool Calibration Error CiSTD:

0. 125 psi 3

4.11, Note 2 As Left Tolerance ALT:

2.0 psi 2

6.2.5 Note 1: Per Input 4.3, the Barksdale pressure switches are calibrated with XPI-9021 (Ashcroft 2089). From Input 4.10, the vendor accuracy of the Ashcroft 2089 is 0.05% of full scale. Therefore, the XPI-9021 has an accuracy of 0.25 psi at 500 psi.

Calibration Device Range Accuracy Reference XPI-9021 (Ashcroft 2089) 0-500 psig 0.05% Full Scale 4.10 Note 2:

Per Input 4.3, the Ashcroft 2089 is calibrated using the XPS-95171 dead weight tester. From Input 4.11, the vendor accuracy of the Mansfield and Green dead weight tester is 0.025% of output pressure. Therefore, the XPS-95171 has an accuracy of 0.125 psi at 500 psi.

Calibration Device Range Accuracy Reference XPS-95171 (Mansfield and Green Deadweight tester) 100-5000 psig 0.025% Reading 4.11 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 10 of 16 Since calibration term values are controlled by 100% testing they are assumed to represent 3 sigma values. Individual calibration error terms are combined using the SRSS method and normalized to a 2 sigma confidence level:

CL Device I Calibration Error CL

+

/

c sT2

+

C7STD 2

CL

+.

2,j0.252 0

L 0252+0.1252 +22 3

CL = 1.35psi 6.3 Determination of Primary Element Accuracy (PEA) and Process Measurement Accuracy (PMA)

(Input 4.8)

PMA = Tolerances on machining, +/-3% of point.

= +/-3% X 125.3 psig

+/- +/-3.8 psi (Per Input 4.6, 25% (Section 6.1) EPU power (28.2% CLTP) corresponds to 140 psia. The conversion to gauge pressure is calculated using a 14.7 psi atmospheric pressure. This value is conservative for the site.)

6.4 Determination of Other Error Terms The Analytical Limit in this calculation is based on a theoretical first stage shell pressure curve. The curve in Attachment 3 is readable to one quarter of the smallest division (Assumption 5.5). Therefore, the following readability error must be considered:

Reference REA= +/- 5 psi 4.6, 5.5 M/cah

MONTICELLO NUCLEAR GENERA TINGPLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page I tof 16 6.5 Calculation of Allowable Value and Operating Setpoint 6.5.1 Allowable Value (AV):

Per Section 6.1.1, the Analytical Limit corresponds to 26.6% power (EPU) or 30% power (CLTP). However, the Allowable Value will be calculated using a conservative AL of 25%

power (EPU) or 28.2% power (CLTP). Per Input 4.6, this AL corresponds to a first stage pressure of 140 psia (125.3 psig). The conversion to gauge pressure is calculated using a 14.7 psi atmospheric pressure. This value is conservative for the site.

AV*!ýAL - 1.645>VA 2

+C

+ PMA 2 + PEA 2 + R EA 2) + bias terms AY 12 5.3 - ( 2 )yJ6.0+ 1.35 + 3.8

+ 25. 0')

AV *118.07 AV= 118 psig 6.5.2 Nominal Trip Setpoint Calculation:

NTSP1 = At, -

)A2T

+ C + D2 +PMA 2 +PEA 2 + PREA 2 + bias terms NTS~=15.31.645)~60

+132 +2.02 +.82

+02+5.02

-NTS P, = 125.3-+1.5+2

+35 NTSP1 = 105.0 6.5.3 Licensee Event Report (LER) Avoidance Evaluation:

The purpose of the LER Avoidance Evaluation is to ensure that there is sufficient margin provided between the AV and the NTSP to reasonably avoid violation of the AV. For a single instrument channel a Z value of greater than 1.29 provides sufficient margin between the NTSP and the AV. Although this is a multi channel loop, a Z of 1.29 will be used for conservatism. Therefore, NTSP 2 is calculated to provide a lower bound for the NTSP based on LER avoidance criteria.

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 12 of 16 Sigma(LER)=l(-A2.+C

+D. )+bias Sigma(LER)=1(J6.02 + 1.352 +23.02)

Sigma(LER) = 11.90 NTSP2 = AV - Zx Sigma(LER)

NTSP 2 = 118-(1.29x11.90)

NTSP 2 = 102.6 Therefore, an NTSP < 102.6 psig will result in a Z greater than 1.29 and provide sufficient margin between the NTSP and the AV.

6.5.4 Selection of Operating Setpoints:

NTSP < Controlling NTSP -ALT NTSP < NTSP2 - ALT NTSP

  • 1.02.6-2.0 NTSP *< 100.6 An instrument setting of 95.0 psig will be used for the setpoint. Since this is less than the calculated NTSP, the setpoint is acceptable.

6.5.5 Leave Alone Zone:

Leave Alone Zones are not used at MNGP (Input 4.1).

6.5.6 Establishing As Found Tolerances (AFT):

The upper limit for the As-found tolerance is 118 psig, the Allowable Value. There is no lower limit specified for this setpoint.

An as-found tolerance is calculated to provide limits for use during the surveillance testing:

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054

TITLE, Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 13 of 16 AFT =VALT 2 +AD 2 AFT=

2.02 + 23.02 AFT = 23.1 An as found tolerance + 22 psig is considered conservative and.will be used.

6.5.7 Required Limits Evaluation:

The required limits are considered to be adequate when the following equation is satisfied:

AV - NTSP >_ AFT 118 -95Ž 22 The equation is satisfied and the setpoint and required limits are adequate.

6.5.8 Spurious Trip Avoidance Evaluation:

The typical methodology for Spurious Trip Avoidance Evaluations is not implemented because of the nature of the setpoint. The setpoint does not cause a scram directly but is rather one of the conditions which need to be satisfied in order for the Reactor Protection System to initiate a scram. Therefore, this section will discuss the spurious enabling of the scram logic during conditions less than the Analytical Limit.

This calculation uses an AL of 25% (EPU) or 28.2% (CLTP) reactor thermal power. Based on channel uncertainties, the setpoint is set lower than this value to ensure the scram bypass signal is deactivated above the AL. The scram bypass signal is deactivated once the setpoint is reached. Therefore, a spurious scram on increasing reactor thermal, power could only occur during the conditions between the switch activation and the AL.

As discussed in Section 6.1, the automatic scram bypass signal is reactivated on decreasing reactor power once the pressure switch reset is reached. Due to the deadband of the pressure switches, this bypass signal is always reactivated below the NTSP and AL.

Therefore, a spurious scram can occur on decreasing power between the AL and the switch reset. The maximum deadband of the switch is 27 psi (Attachment 2) but has historically been 14 - 16 psi (Input 4.3). As such, the range of pressures at which it is possible to spuriously scram is relatively small and, due to the nature of pressure switches, is impossible to eliminate completely.

M/cah

MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 14 of 16 The lower as found limit of the pressure switch setpoint is 73 psig. On decreasing reactor power, the lowest condition the bypass signal would remain not active is when the first stage pressure reaches 73 - 27 = 46 psig (since the maximum deadband of the switch is 27 psi). Therefore, below 46 psig the scram bypass signal is always activated.

The as found and as left tolerance limits for the switch reset should be revised to ensure the deadband is not greater than 27 psi. This allows for the setpoint to drift within the As-Found range and ensures the deadband is not more than 27 psi lower than the setpoint.

6.5.9 Elevation Correction:

None.

6.5.10 Determination of Actual Setpoint:

The new setpoint and instrument setting will therefore be as follows:

Setpoint:

As-Found -Range:

As-Left Range:

Reset:

Maximum Deadband:

95 psig 73 to 117 psig 93 to 97 psig 27 psig

7..

CONCLUSIONS The results of the calculations are as follows:

Term Value(psig)

Reference ALT 6.0 6.2.3 ALN 6.0 6.2.3 DL 23.0 6.2.4 ALT 2.0 6.2.5 CL 1.35 6.2.6 PEA 0.0 6.3 PMA 3.8 6.3 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 15 of 16 Term Value(psig)

Reference REA

+5 6.4 NTSP 95.0 6.5.4 AV 118 6.5.1 AFT

+/-22 6.5.6

8.

FUTURE NEEDS Testing should be completed during power ascension following the turbine replacement in order to verify the first stage pressure and reactor thermal power relationship. This document.

should be updated to reflect the testing results. The readability error in Section 6.4 would no longer be applicable. Plant procedures should be revised to reflect the new setpoint and associated as-found and as-left tolerances.

9.

ATTACHMENTS 1 PS-5-14A, B, C and D drift data.

2 Barksdale Catalog Datasheets.

3 GE-MNGP-AEP-196 1st Stage Shell Pressure curve. GE. 1LX0501-07 Rev. 1 4

Memo from John Hess (GE) to Jim Devine (MNGP) dated March 15, 1996.

5 Setpoint Relationships

10.

REFERENCES 10.1 NEDC-31336P-A, General Electric Instrument Setpoint Methodology, September 1996.

10.2 GE-NE-901-021-0492, DRF A0001932-1, Setpoint Calculation Guidelines for the Monticello Nuclear Generating Plant, October 1992.

10.3 EPRI Report TR-1 03335-R1, Guidelines for Instrument Calibration Extension/Reduction Programs, Revision 1, March, 1994.

10.4 Task Report T0502, Nuclear Management Company Monticello Nuclear Generating Plant Extended Power Uprate:

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject Revision 5 Scram Bypass Page 16 of 16 10.5 USAR-07.06. Monticello Updated Safety Analysis Report. Plant Instrumentation and Control Systems: Plant Protection System. Revision 25P.

10.6 Operations Manual B.05.06. Plant Protection System.

10.7 Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle.,

M/cah

I MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachm~rlt 1 Page 1 of 22 A1.1 Data Grouping The Barksdale model 2T-A12SS pressure switches presented below are included in this analysis. The current setpoints are obtained from the MNGP Component Master List (CML) Database.

Equipment ID Range Setpoint (desired)

PS-5-14A 50- 1200 psig 125 psig PS-5-14B 50 - 1200 psig 125 psig PS-5-14C 50 - 1200 psig 125 psig PS-5-14D 50 - 1200 psig 125 psig As shown in section 6.2.2, the trip units are exposed to similar environmental conditions with the same calibration frequency. Therefore, the individual drift data for the trip units can be grouped without further numerical testing, following the criteria set forth in step 5.4.8 of ESM-03.02-APP-lII.

A1.2 Populating the Spreadsheet Calibration data for the pressure switches included the date of calibration, as well as the As-Found and As-Left setpoint values. This data was input into a Microsoft Excel spreadsheet, and included in this Attachment.

The calibration interval was determined by taking the difference between the current and previous calibration dates. Per step 5.3.9 of ESM-03.02-APP-III, the calibration interval was converted to months by dividing the number of days by 30.5 days per month.

The Drift value was calculated by taking the difference between the current calibration As-Found value and the previous calibration As-Left value.

Each of the pressure switches contained a discrepancy in its data set. On the calibration dates of 05/12/1996 and 06/1111996, only the As-Found setpoint value was reported.

However, each data set contained a data point for the following day (05/13/1996 and 06/12/1996, respectively) which included the As-Left setpoint value. For the purposes of this drift analysis, each of the data pairs was combined into a single data point which included both the As-Found and. As-Left setpoints. This is considered reasonable, as a discrepancy of a single day is insignificant compared to the average calibration interval of approximately 15 months.

It is noted that the calibration setpoint for the pressure switches was adjusted several times during the analysis time period. However, all the pressure switches in question were adjusted uniformly, and the overall difference in setpoints is small compared to the instrument setpoint. range (approximately 5%). Since the analysis deals with drift values, and not the setpoints themselves, no special considerations were made for the varying setpoints:

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 2 of 22 AU.3 Spreadsheet Performance of Basic Statistics The following information was determined for each instrument individually:

The average or mean value (x) of the drift data for each instrument was determined by using the "Average" function in Microsoft Excel. This function uses the following equation:

n where x = average of data set xi = individual drift value n = total number of values The standard deviation of a data set returns the measure of how widely dispersed the values are in relation to the mean of the data. The standard deviation for each instrument was determined using the "STDEV" function. Microsoft Excel uses the following equation in the "STDEV" function:

nZ x,~

x.

n(n-1) where s = standard deviation of sample x= individual drift value n = total number of values The variance (S2) is another measure of data spread from the mean. The variance for each instrument was determined by using the "VAR" function in Microsoft Excel. The variance is calculated as follows:

S 2 nEX2

-(EX) n(n-1) where s2 = variance of sample xi= individual drift value n = total number of values The largest positive drift value for each instrument was determined by using the "MAX" function.

The largest negative drift value for each instrument was determined by using the "MIN" function.

The number of data points (n) for each instrument was determined using the "COUNT" function.

The psig values for average, standard deviation, and largest positive and negative drift were converted to a percent of instrument span using the following formula:

/. span = psig value x100%

psig span M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 3 of 22 A Drift Trend Plot was developed for each instrument by plotting the drift value versus calibration date. Bounds corresponding to + 2s (2 standard deviations) are shown on the plot.

Page 11 presents the combined drift data statistics for the subject trip units. The combined statistics were determined using the preceding methods.

A1.4 Outlier Detection and Expulsion Per step 5.5 of ESM-03.02-APP-ll, the t-Test is used to detect the presence of outliers in the final data set. The t-Test requires the use of the following equation:

t.-x S

where t = individual t-Test statistic s = standard deviation of sample xi= individual drift value x= individual drift value The t-Test involves calculating the individual t' statistics for each data point, and comparing them to a critical value. The critical value depends on the sample size, and is obtained from Table 9.2 of ESM-03.02-APP-Il1.

The t-Test is shown on pages 12 and 13 of this Attachment. Based on a sample size of 44, the critical value utilized in the t-Test is 2.91. None of the calculated individual t-Test statistics exceeded the critical value and therefore, no outliers were identified or removed.

A1.5 Normality Tests Most statistical analyses make the assumption that the values in question are normally distributed. The criteria in ESM-03.02-APP-llI require that the data set be tested for normality. It is recommended that for samples with less than 50 data points, the W Test be utilized.

W Test The W Test calculates a test statistic value for the sample population and compares the calculated value to the critical values for W, which are tabulated in Table 9.6 of ESM-03.02-APP-Ill. The W Test is a lower-tailed test. Thus if the calculated value of W is less than the critical value of W, the assumption of normality would be rejected at the stated significance level. If the calculated value of W is larger than the critical value of W, there is no evidence to reject the assumption of normality.

To perform a W Test, the drift value data set is sorted and numbered in ascending order from smallest to largest.

Micah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 4 of 22 Calculate the S2.value for the group:

S' (n-1) x s' where S2 = sum of the squares about the mean S2= unbiased estimate of the sample population variance n

total number of data points Calculate the quantity b of the sample group:

b

[a,,-,+, x (x,,,+, - x, where i= 1 tok, and k =nl2 if n is even or k = (n-1)/2 if n is odd n = total number of data points xi = individual sample data point an-i+1 = coefficient obtained from Table 9.5 of ESM-03.02-APP-III Calculate theW value for the sample group. The following equation is used:

b2 S2 Determine the critical W values based on the sample size using Table 9.6 in ESM-03.02-APP-Ill.

See pages 14 and 15 for the W Test of the drift data. For a sample size of 44, the critical value of the W Test is 0.944. The calculated W value was 0.982. Based on this result, there is no evidence to reject the assumption of normality.

A1.6 Selection of Final Data Set The pressure switches in question have only one calibration setpoint. Therefore, all data points will be part utilized and no further analysis is required in determining the final data set.

A1.7 Time-Dependency Analysis Standard statistical analyses do not consider time-dependency. The following tests attempt to uncover any time-related performance and the impact of any time-dependency on the analysis.

Drift Interval Plot A drift interval plot is an XY scatter plot that shows the data set plotted against the time interval between calibrations, It relies on visual inspection to discriminate the plot for any trend in the data to exhibit a time dependency. A prediction line can be added to this plot to aid in the analysis.

Page 16 shows the drift interval plot for this data set. The drift interval plot includes the tolerance interval (TI) described in section A1.9. The plot also includes a predicted line, Micah

MONTICELLO NUCLEAR GENERA TING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 1Drift Analysis Page 5 of 22 which in this case passes through the x-axis. Based on section 4.8.4.D.4 of ESM-03.02-APP-Ill, cases where the drift function crosses zero are normally established assuming no time dependency.

Standard Deviations and Means at Different Calibration Intervals (Binningq Analysis)

The binning analysis is the most recommended method of determining time dependent tendencies in a given sample pool. Following the instructions in step 4.8.3 of ESM-03.02-APP-Ill, the drift data was segregated into different groups (bins) corresponding to different ranges of calibration intervals. In order for further analysis to be done, at least 2 valid bins must exist. In order to be considered valid, a bin must contain more than five data points and more than 10% of the total data count. The binning analysis (pages 17-

18) includes 3 valid bins.

The average drift, standard deviations and average time intervals were calculated for each bin. These parameters were plotted on page 18. This plot shows the variation of the bin averages and standard deviations versus time interval. The behavior of the plot indicates no time dependency, following the criteria of step 4.8.4.D.4 of ESM-03.02-APP-Ill.

Regression Analysis A regression analysis was performed on the drift data, as well as the absolute value of the drift data. This analysis is shown on pages 19 through 22.

The results of the regression analysis were compared to the criteria of step 4.8.4 from ESM-03.02-APP-III. The analytical results indicate no time dependency. However, per the instruction of step 5.8.3.E, the data will be conservatively considered to be moderately time dependent.

A1.8 Drift Bias Determination The absolute value of the average calculated drift for the trip pressure switches is 0.2 psig, which is approximately equal to 0.02% of the calibrated span. The criteria in ESM-03.02-APP-Ill state that if the absolute value of the mean drift is less than 0.1% of the calibrated span, the instrument drift does not appear to have a bias. Therefore, the drift bias terms will be taken as 0 in this analysis.

A1.9 Analyzed Drift Value Bias Term

'Based on the drift data as well as section A1.8, the instruments do not have a bias.

Therefore, the bias term will be equal to 0.

Random Term The random term of the analyzed drift value is calculated with the below equation:

A Dd,.do,,

s x TIF x NAF where ADrandom = random term for analyzed drift s = drift standard deviation TIF 95%/95% tolerance interval factor NAF = Normality Adjustment Factor M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TIT'LE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 6 of 22 The standard deviation of the drift data is equal to 8.34 psig. The TIF for a sample size of 44 is equal to 2.445 (Table 9.1 of ESM-03.02-APP-lII). Since the W Test did not reject the hypothesis of normality, a Normality Adjustment Factor was not necessary and is therefore equal to 1. Thus, the random drift term is calculated to be 20.4 psig. The random term is equal to the tolerance interval (TI) plotted on the Drift Interval Plot on page 16.

Extended Interval Predicted Drift (Random Term)

Since the drift was determined to be moderately time dependent, the following equation was used to extrapolate the drift uncertainty:

AD

.random = AD,,,,od,,, x or where ADE.random = extended period drift term ADrandom = random termrfor analyzed drift CIE = extended calibration interval (surveillance interval +25%)

CIO =

average observed calibration time interval from bin with longest time interval The value of the random term for the analyzed drift was determined to be 20.4 psig. The extended calibration interval is equal to the surveillance calibration interval (24 months) plus an additional 25% (6 months). Therefore, CIE is equal to 30 months. CIo is determined from the bin of data that had the longest calibration interval. In this case, it is the bin with a calibration interval range of 22.5 to 30 months. The average calibration interval within this bin is equal to 23.6 months. These values produce a 30-month predicted drift term of 23.0 psig from the above equation.

The instruction in step 5.10.4.B states that the calculated extended interval predicted drift terms must be compared to the uncertainty calculated using the 99%/95% tolerance factor. The following equation is utilized to increase the TIF..

A rnn

-ai TIF99 / 95 AD E.ra,,do,,

A AD rand,,o,,

x 11E'95/95 where ADE.random = extended period drift term ADrandorn = random term for analyzed drift TIF95/95 = 95%/95% tolerance interval factor TIF99195 d 99%/95% tolerance interval factor Using the random drift term of 20.4 psig, a 95%/95% TIF of 2.445 and a 99%/95% TIF of

-2.677, the extended period drift term is calculated to be 22.3 psig. Therefore, 23.0 psig is the larger of the two and should be used as the 30-month predicted drift term.

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass' Revision 5 Drift Analysis Page 7 of 22 Drift Data for PS-5-14A Calibration As-Drift Drift Date Interval t

AsD-Leftr (Mnh)

Found (psig)

(%)

(Months) 4/22/2007 24.4 127.8 124.6 1.3 0.11 4/9/2005 22.8 126.5 126.5 0.0

- -MO 5/14/2003 17.3 120.5 126.5

-5.0

-0.43 12/2/2001 21.8 134.5 125.5 10.5 0.91 2/5/2000 16.1 114.0 124.0

-11.0

-.0.96 10/1/1998 4.4 120.0 125.0 5.5 0.48 5/21/1998 1.1 139.5 114.5 0.0 0.00 4/16/1998 22.1, 1,39.5 139.5 1.5 0.13 6/12/1996 1.0 137.0 138.0 7.0 0.61 5/13/1996 18.7 166.0 130.0

-9.0

-0.78 10/20/1994 19.9 191.0 175.0 16.5 1.43 2/20/1993 174.5 174.5 Basic Statistics for PS-5-14A Average x

(psig) 1.6 Standard Deviation s

(psig) 8.2 Variance s

(psig) 66.5 Largest Positive Drift (psig) 16.5 Largest Negative Drift (psig)

-11.0 Number of Samples n

11 Average x

(%)

0.14 Standard Deviation s

(%)

0.7094 Largest Positive Drift

(%)

1.43 Largest Negative Drift

(%)

-0.96 Drift Trend Plot for PS-5.-14A

  • 20.0 10.0 0.0

-20o 51711990 1/31/1993 10/28/1995 7/24/1998 4/19/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14A

+2s 2s M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 8 of 22 Drift Data for PS-5-14B Calibration As-As-Left Date Interval As-Left Drift Drift (Months)

Found (psig)

(%)

4/22/2007 24.4 128.5 126.3 2.5 0.22 4/9/2005 22.8 122.0 126U0

-2.0

-0.17 5/14/2003 17.3 -

122.0 124.0

-4.0

-0.35 12/2/2001 21.8 129.5 126.0 4.5 0.39 2/5/2000 16.1 114.0 125.0

-11.0

-0.96 10/1/1998 4.4 118.0 125.0 2.0 0.17 5M21/1998 1.1 134.0 116.0

-2.5

-0.22 4/16/1998 22.1 136.5 136.5

-1.5

-0.13 6/12/1996 1.0 134.0 138.0 4.0 0.35 5/13/1996 18.7 160.5 130.0

-14.5

-1.26 10/20/1994 19.9 193.0 175.0 18.0 1.57 2/20/1993 171.0 175.0 Basic Statistics for PS-5-14B Average x

(psig)

-0.4 Standard Deviation s

(psig) 8.5 Variance s2 (psig) 72.8 Largest Positive Drift (psig) 18.0 Largest Negative Drift (psig)

-14.5 Number of Samples n

11 Average x

(%)

-0.04 Standard Deviation s

(%)

0.7421 Largest Positive Drift

(%)

1.57 Largest Negative Drift

(%)

-1.26 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 9 of 22 Drift Data for PS-5-14C Calibration As-Drift Drift Date Interval As-Left (Months)

Found (psig)

A 4/22/2007 24.4 123.1 126.3

-2.4

-0.21 4/9/2005 22.8 125.5 125.5 0.0 0.00 5/14/2003 17.3 119.0 125.5

-6.0

-0ý52 12/2/2001 21.8 134.0 125.0 10.0 0.87 2/5/2000 16.1 119.0 124.0

-7.0

-0.61 10/1/1998 4.4 119.0 126.0 4.0 0.35 5/21/1998 1.1 137.8 115.0 1.3 0.11 4/16/1998 22.1 136.5 136.5

-1.6

-0.14 6/12/1996 1.0 129.5 138.1 0.0 0.00 5/13/1996 18.7 167.5 129.5

-8.0

-0.70 10/20/1994 19.9 187.0 175.5 12.0 1.04 2/20/1993 166.0 175.0 Basic Statistics for PS-5-14C Average x

(psig) 0.2 Standard Deviation s

(psig) 6.5 Variance s 2 (psig) 41.9 Largest Positive Drift (psig) 12.0 Largest Negative Drift (psig)

-8.0 Number of Samples n

11 Average x

(%)

0.02 Standard Deviation s

(%)

0.5626 Largest Positive Drift

(%)

1.04 Largest Negative Drift

(%)

-0.70 Drift Trend Plot for PS-5-14C 0

20.0 10,0 *,,

10 0**

-1.0

-2 0.0 5/7/1990 1731/1 993 10/28/1995 712411998 4119/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14C -

- - +2s -

w...- -2s M/cah.

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 10 of 22 Drift Data for PS-5-14D Calibration Clbain As-

.Drift Drift Date Interval As-As-Left Drift D

(Mnh)

Found (psig)

(%)

(Months) 4/2212007 24.4 122.3 124.8

-0.7.

-0.06 4/9/2005 22.8 123.0 123.0

-2.5

-0.22 5/14/2003 17.3 119.5 125.5

-6.0

-0.52 12/2/2001 21.8 133.8 125.5 8.8 0.77 2/5/2000 16.1 110.0 125.0

-14.0

-1.22 10/1/1998 4.4 118.0 124.0 4.5 0.39 5/2111998 1.1 145.0 113.5 7.5 0.65 4/16/1998 22.1 127.0 137.5

-10.0

-0.87 6/12/1996 1.0 135.0 137.0 5.5 0.48 5/13/1996 18.7 156.0 129.5

-18.0

-1.57 10/20/1994 19.9 193.5 174.0 17.5 1.52 2/20/1993

.169.0 176.0 Basic Statistics for PS-5-14D Average x

(psig)

-0.7 Standard Deviation s

(psig) 10.7 Variance s2 (psig) 114;8 Largest Positive Drift (psig) 17.5 Largest Negative Drift (psig)

-18.0 Number of Samples n

11 Average x

(%).

-0.06 Standard Deviation s

(%)

0.9318 Largest Positive Drift

(%)

1.52 Largest Negative Drift

(%)

-1.57 Drift Trend Plot for PS-5-14D 30.0 -T-S20.0 -

AWLg 10.0 0.0

>-10.0 e--20.0 S-30.0 5/711990 1/3111993 10/28/1995 7/24/1998 4/19/2001 1/14/2004 10/10/2006 7/6/2009 Date PS-5-14D -.

- -+2s 2s]

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 11 of 22 Basic Statistics for Combined Drift Data Average (psig) 0.2 Standard Deviation s

(psig) 8.34 Variance s2 (psig) 69.6 Largest Positive Drift (psig) 18,0 Largest Negative Drift (psig)

-18.0 Number of Samples 44 Average x

(%)

0,02 Standard Deviation s

(%)

0.7256 Largest Positive Drift

(%)

1.57 Largest Negative Drift

(%)

-1.57 Micah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve ClosurelGenerator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 12 of 22 Outlier Test (t-Test) for Combined Data Set Equipment Calibration Drift Outlier?

ID (Months)

(psig)

T YESINO PS-5-14A 24.4 1.3 0.13 NO 22.8 0.0 0.02 NO 17.3

.-5.0 0.62 NO 21.8 10.5 1.24 NO 16.1

-11.0 1.34 NO 4.4 5.5

.0.64 NO 1.1 0.0 0.02 NO 22.1 1.5 0.16 NO 1.0 7.0 0.82 NO 18.7

-9.0 1.10 NO 19.9 16.5 1.96 NO PS-5-14B 24.4 2.5 0.28 NO 22.8

-2.0 0.26 NO 17.3

-4.0 0.50 NO 21.8 4.5 0.52 NO 16.1

-11.0 1.34 NO 4.4 2.0 0.22 NO 1.1

-2.5 0.32 NO 22.1

-1.5 0.20 NO 1.0 4.0 0.46 NO 18.7

-14.5 1.76 NO 19.9 18.0 2.14 NO PS-5-14C 24.4

-2.4 0.31 NO 22.8 0.0 0.02 NO 17.3

-6.0 0.74 NO 21.8 10.0 1.18 NO 16.1

-7.0 0.86 NO 4.4 4.0 0.46 NO 1.1 1.3 0.13 NO 22.1

--1.6 0.21 NO 1.0 0.0 0.02 NO 18.7

-8.0 0.98 NO 19.9 12.0 1.42 NO PS-5-14D 24.4

-0.7 0.10 NO 22.8

-2.5 0.32 NO 17.3

-6.0 0.74 NO 21.8 8.8 1.03 NO 16.1

-14.0 1.70 NO 4.4 4.5 0.52 NO 1.1 7.5 0.88 NO 22.1

-10.0 1.22 NO M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision..5 Drift Analysis Page 13 of 22 I

1.0 5.5 0.64 NO 18.7

-18.0 2.18 NO 19.9 I 17.5 2.08 NO The outlier test shows that none of the individual T-statistics exceed the critical value of 2.91. The critical value was obtained from Table 9.2 of ESM-03.02-APP-lI1. Therefore, the data set contains no outliers.

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass, Revisiorl.5 Drift Analysis Attachment'l Page 14 of 22 Normality Test - W Test X1 i

an-i+1 Xn-i+l bi

-18.0 1

0.3872 18.0 13.94

-14.5 2

0.2667 17.5 8.53

-14.0 3

0.2323 16.5 7.09

-11.0 4

0.2072 12.0 4.77

-11.0 5

0.1868 10.5 4.02

-10.0 6

0.1695 10.0 3.39

-9.0 7

0.1542 8.8 2.74

-8.0 8

0.1405 7.5 2.18

-7.0 9

0.1278 7.0 1.79

-6.0 10 0.1160 5.5 1.33

-6.0 11 0.1049 5.5 1.21

-5.0 12 0.0943 4.5 0.90

-4.0 13 0.0842 4.5 0.72

-2.5 14 0.0745 4.0 0.48

-2.5 15 0.0651 4.0

  • 0.42

-2.4 16 0.0560 2.5 0.27

-2.0 17-0.0471 2.0 0.19

-1.6 18 0.0383 1.5 0.12

-1.5 19 0.0296 1:3 0.08

-0.7 20 0.0211 1.3 0.04 0.0 21 0.0126 0.0 0.00 0.0 22 0.0042 0.0 0.00 0.0 0.0 1.3 1.3 1.5 2.0

=...

2.5 4.0 4.0 4.5 4.5 5.5 7.5 8.8 10.0 10.5 12.0 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96.054 TITLE:,

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 15 of 22

-16.5 1

17.5 18.0 W Test Analysis n

44 S2 2993.8 b, '(bi) 54.2 W

0.982 P

0.944 Since W > P, the results of the W Test, do not provide any evidence to reject the assumption of normality.

Drift Tolerance Interval (TI)

TI=

  • TIF
  • NAF s

=

8.344031 TIF

=

2.445 NAF=

1 TI

=

20.40 M/cah

MONTICELLO NUCLEAR GENERATING PLANT' CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass.

Revision 5 DriftAnalysis Page 16 of 22 Time Dependency Testing - Drift Interval Plot 0-0 E2 r0 n

c2 c

cD, L?

c Lo (N

N (N

(N (Bisd) :4j(

M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 DriftAnalysis Page 17 of 22 Time Dependency Testing - Binning Analysis 1

2 3

4 5

6 0 to 1.25 months

> 1.25 to 3.75

> 3.75 to 7.5

> 7.5 to 15.0

> 15 to 22.5

> 22.5 to 30 months months months months months Cl Drift Cl Drift Cl Drift Cl Drift Cl Drift CI Drift (Months) (psig) (Months)

(psig)

(Months) (psig)

(Months)

(psig)

(Months) (psig)

(Months) (psig) 1.1 '

0.0 4.4 5.5 17.3

-5.0 24.4 1.3 1.0 7.0 4.4 2.0 21.8 10.5 22.8 0.0 1.1

-2.5 4.4 4.0 16.1

-11.0 24.4 2.5 1.0 4.0 4.4 4.5 22.1 1.5 22.8

-2.0 1.1 1.3 18.7

-9.0 24.4

-2.4 1.0 0.0 19.9 16.5 22.8 0.0 1.1 7.5 17.3

-4.0 24.4

-0.7 1.0 5.5 21.8 4.5 22.8

-2.5 16.1

-11.0 22.1

-1.5 18.7

-14.5 19.9 18.0 17.3

-6.0 21.8 10.0 16.1

-7.0 22.1

-1.6 18.7

-8.0 19.9 12.0 17.3

-6.0 21.8 8.8 16.1

-14.0 2 2. 1..

-1 0.0.-

18.7

-18.0 19.9 17.5

% of Valid?

Bin #.Bin Range Count Total YESINO Bin #

(months)

Data 1

0 to 1.25 8

18.2 YES 2

> 1.25 to 3.75 0

0.0 NO.

3

> 3.75 to 7.5 4

9.1 NO 4

> 7.5to 15.0 0

0.0 NO 5

> 15 to 22.5 24 54.5 YES 6

> 22.5 to 30 8

18.2 YES M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054' TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 18 of 22 Time Dependency Testing - Binninig Analysis, continued Bin # Drift Drift Drift Average Data Bin #.

v r g Standard C

o n Average Deviation CI Count 1

2.9 3.67 1.1 8

2 0

3 4.0 1.47 4.4 4

4 0

5

-1.1 10.85 19.3 24 6

-0.5 1.80.

23.6 8

Time Dependency Plot 4.0 15.00

=

3.0 2.0 10.00 1.0o U

S0.01 5.00o 1.-1.0 1

.6 0

-2. 0 0.00 Average Calibration Interval (Months)

Drift Average o---- Drift Standard Deviation M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 19 of 22 Time Dependency Testing - Regression Analysis (Final Data Set)

SUMMARY

OUTPUT Regression Statistics Multiple R 0.110327 R Square 0.012172 Adjusted R Square

-0.01135 Standard Error.

8.391239 Observations 44 ANOVA Significance df SS MS F

F Fcrit Regression 1 36.44073 36.44073 0.517529 0.475882 3.417947 Residual 42 2957.342 70.4129 Total 43 2993.783 Standard Lower Upper Lower Upper Coefficients Error t Stat P-value 95%

95%

95.0%

95.0%

Intercept 1.831605 2.627369 0.697125 0.489565 3.47064 7.13385 3.47064 7.13385 x

Variable 1

-0.10742 0.14932

-0.7194 0.475882 0.40876 0.19392 0,40876 0.19392 RESIDUAL OUTPUT Observation 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 Predicted Y

-0.78522

-0.61968

-0.02799

-0.51402 0.098797 1.363183 1.708336

-0.53868 1.725946

-0.17944

-0.30623

-0.78522

-0.61968

-0.02799

-0.51402 0.098797 1.363183 Residuals 2.085216 0.619684

-4.97201 11.01402

-1I1.0988 4.136817

-1.70834 2.038678 5.274054

-8.82056 16.80623 3.285216

-1.38032

-3.97201 5.014025

-11.0988 0.636817 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve ClosurelGenerator Load Reject SCRAM Bypass Revision 5 Drift Analysis Attachment I Page 20 of 22 18 1.708336

-4.20834 19

-0.53868

-0.96132 20 1.725946 2.274054 21

-0.17944

-14.3206 22

-0.30623 18.30623 23

-0.78522

-1.61478 24

-0.61968 0.619684 25

-0.02799

-5.97201 26

-0.51402 10.51402 27 0.098797

-7.0988 28 1.363183 2.636817 29 1.708336

-0.40834 30

-0.53868

-1.06132 31 1725946

-1.72595 32

-0.17944

-7.82056 33

-0.30623 12.30623 34

-0.78522 0.085216 35

-0.61968

-1.88032 36

-0.02799

-5.97201 37

-0.51402 9.314025 38 0.098797

-14.0988 39 1.363183 3.136817 40 1.708336 5.791664 41

-0.53868

-9.46132 42 -1.725946 3.774054 43

-0.17944

-17.8206.

44

-0.30623 17.80623 Line Fit Plot 20.0 15.0 1.0.0 -

0*.0 25.00

.0-300

15. 0

-20. 0 Calibration Time Interval (Months)

E Drift, Predicted Drift M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator LoadReject SCRAM Bypass Revision 5 Drift Analysis Page 21 of 22 Time Dependency Testing - Regression Analysis (Absolute Values of Final Data Set)

SUMMARY

OUTPUT Regression Statistics Multiple R 0.181127 R Square 0.032807 Adjusted R Square 0.009779 Standard Error 5.255246 Observations 44 ANOVA Significance df SS MS F

F Fcrit Regression 1 39.34483 39.34483 1.424629 0.239342 3.417947 Residual 42 1159.939. 27.61761 Total 43 1199.284 Standard Lower Upper Lower Upper Coefficients Error t Stat P-value 95%

95%

95.0%

95.0%

Intercept 4.667286 1,645462 2.836459 0.006991 1.346609 7.987963 1.346609 7.987963 x

Variable 1

0.111618 0.093516 1.193578 0.239342

-0,0771 0.300341

-0.0771 0.300341 RESIDUAL OUTPUT Predicted Observation Y

Residuals 1

7.386381

-6.08638 2

7.214379

-7.21438 3

6.599563

-1.59956 4

7.10459 3.39541 5-6.467817 4.532183 6

5.154015 0.345985 7

4.795373

-4.79537 8

7.1302QB

-5.63021 9

4.777075 2.222925 10 6.756927 2.243073 11 6,888673 9.611327 12 7.386381

-4.88638 13 7.214379

-5.21438 14 6.599563

-2.59956 15 7.10459

-2.60459 16 6.467817 4.532183 17 5.154015

-3.15401 18 4.795373

-2.29537 M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TtTLB: 4 Aflrine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 22 of 22 19 7.130208

-5.63021 20 4.777075

-0.77707 21 6.756927 7.743073 22 6.888673 11.11133 23 7,386381

-4.98638 24 7.214379

-7.21438 25 6.599563

-0.59956 26

-7.10459 2.89541 27 6.467817 0.532183 28 5.154015

-1.15401 29 4.795373

-3.49537 30 7.130208

-5.53021 31 4.777075

-4.77707 32 6.756927 1.243073 33 6.888673 5.111327 34 7.386381

-6.68638 35 7.214379

-4.71438 36 6.599563

-0.59956 37 7.10459 1.69541 38 6.467817 7.532183 39 5.154015

-0.65401 40 4.795373 2.704627 41 7.130208 2.869792 42 4.777075 0.722925 43 6.756927 11.24307 44 6.888673 10.61133 Line Fit Plot 20.0 -

16.0 14.0-12.90 10.0 8.0 6.0 4.0 -

2.0 0.0 0.0 5.0 10.0

'15.0 20.0 25.0 30.0 Calibration Time Interval (Months)

[ Drift @ Predicted Drift M/cah

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 1of 2

~25OI

~

flPO!AQ SC.~W I

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/ -

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A2t All :th e s lons fr w

V.h, G1 12

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 I

Drift Analysis Page 2 of 2 Pressure Switch Products,

~J Chlraetriserc At rnoees ircorpo reteU01rvrztrs L aireories. fac ~rd CFA List10 siý,!P noee rreOsup-cnereeresu swenens.

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MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass

-Revision 5 Drift Analysis Page 1 of 1

MONTICELLO NUCLEAR GENERATING PLANT CA-96-054 TITLE:

Turbine Stop Valve Closure/Generator Load Reject SCRAM Bypass Revision 5 Drift Analysis Page 1 of I For Illustration Only Not to Scale Pressure psig Analytical Limit Allowable Value NTSP1 NTSP 2 Setpoint (NTSP) 125.7 118.0 117 As-Found

+22 psig 105.0 102.6 97 95 93 As-Left

+/-2 psig As-Found

-22 psig 73 Maximum Switch Deadband 27 psig 46 M/cah

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