RS-03-229, Additional Information Regarding License Amendment Request for Main Steam Line Low Pressure Isolation Setpoint
| ML033510089 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 12/05/2003 |
| From: | Simpson P Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-03-229 | |
| Download: ML033510089 (61) | |
Text
Exeltknm Exelon Generation www.exeloncorp.corn Nuc ear 4300 Winfield Road Warrenville, IL 60555 RS-03-229 December 5, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Additional Information Regarding License Amendment Request for Main Steam Line Low Pressure Isolation Setpoint
Reference:
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S.
NRC, "Request for Amendment to Technical Specifications for Main Steam Line Low Pressure Isolation Function," dated March 28, 2003 In the referenced letter, Exelon Generation Company, LLC (EGC) requested a change to the Facility Operating Licenses listed above regarding the Technical Specifications (TS) for Main Steam Line (MSL) Low Pressure Isolation Function. The proposed change revises the allowable value for the MSL Pressure - Low Function of the Primary Containment Isolation System (PCIS) Instrumentation at Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2.
On December 4, 2003, the NRC requested additional information to support review of the referenced letter. The attachments to this letter provide the requested information.
Attachments 1 and 2 do not contain General Electric Company (GE) report GENE-0000-0010-4202-01, "Engineering Evaluation of Impact on Transient and Safety Analyses of Reducing the Low Pressure Isolation Setpoint Analytical Limit to 785 psig - Dresden Units 2 & 3 and Quad Cities Units 1 & 2." This document contains proprietary information and was provided to the NRC in the referenced letter.
EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously submitted to the NRC in Attachment 1 of the referenced letter. The bases for concluding that the proposed TS changes do not involve a significant hazards consideration are not affected by the supplemental information provided in Attachments 1 and 2 of this submittal.
A-0 01'
December 5, 2003 U. S. Nuclear Regulatory Commission Page 2 of 2 Should you have any questions concerning this letter, please contact Mr. Thomas G.
Roddey at (630) 657-2811.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 5t day of December 2003.
Respectfully, Patrick R. Simpson Manager - Licensing Attachments: Attachment 1: NED-I-EIC-0097, Revision 5, " Main Steam Line Low Pressure Setpoint Error Analysis, " Dresden Nuclear Power Station : NED-I-EIC-0033, Revision 4, "Main Steam Line Low Pressure Setpoint Error Analysis," Quad Cities Nuclear Power Station cc:
Regional Administrator-NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Illinois Emergency Management Agency -
Division of Nuclear Safety t..
ATTACHMENT I NED-I-EIC-0097, Revision 5 Main Steam Line Low Pressure Setpoint Error Analysis Dresden Nuclear Power Station
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- Ex6eknnM CC-AA-309-1 001 Revision 0 ATTACHMENT 1
. Design Analysis Cover Sheet Nuclear Last Page No. 28 Analysis No.
NED-I-EIC-0097.
Revision 5 EC/ECR No.
Revision
Title:
Main Steam Line Low Pressure Isolation Switch Setpoint Error Analysis Station(s)
Dresden
' Component(s)
Unit No.:
Units 2 & 3 PS 2-0261-30A PS 3-0261-30A Discipline I
PS 2-0261-30B PS 3-0261-30B Description Code/
103/ Setpoint PS 2-0261-30C PS 3-0261-30C Keyword Safety Class Safety Related PS 2-0261-30D PS 3-0261-30D System Code 0261 (MS)
Structure CONTROLLED DOCUMENT REFERENCES Document No.
From/To Document No.
From/To Is this Design Analysis Safeguards?
Yes Cl No 0 Does this Design Analysis Contain Unverified Assumptions?
Yes El No 0 ATI/AR#
Is a Supplemental Rev0ew Required?:
Yes Ri No 0 Testing Preparer Joseph R. Basak (c,,t#_:/~/3 Print Name
.Sign Name Date Reviewer Dale R. Earnan Ad
_ -el Z-ID:
~~Print Name Sign Name Date.
Method of Review i3Detailed Review i0 Alternate Calculations OTesting Review Notes:
Approver Stephen V. Tutich Print Name Sign Name Dhte (For Extemal Analys Only)
___I F ak=o-Raviewer.
ti 1i Print Name
-Sign Name Date Approver Print Name Sign Name Date Description of Revision (list affected pages for partials):
Revision 5 determines the calculated setpoint, field calibration setpoint, and allowable value for the Main Steam Line Low Pressure Isolation function based on a reduced Analytical Limit of 785 psig. This revision also incorporates format changes in accordance with CC-AA-309; however, the section headings and numbering from the previous revision are maintained. Changes are Identified by revision bar.
THIS DESIGN ANALYSIS SUPERCEDES: NED-I-EIC-0097 Revision 4 I
CC-AA-309 - ATTACHMENT 1 - Design Analysis Approval Page 2 of 5 DESIGN ANALYSIS NO.
NED-I-EIC-0097 REV-04 PAGE NO.
2 Revision Summary (including EC's incorporated): This revision completely re-formats the calculation per CC-AA-309, Rev.1, and NES-G-14, Rev. 1. Therefore, no revision bars were used. All attachments were deleted. In addition, it incorporates DCR 990359 (EC 13754), and makes changes to both analyzed M&TE and errornvalues to improve operating margin.
.ic o gn44 EC 3L 7535,t Per 0.W°e
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/02-Electronic Calculation Data Files:. W6CV975 62p<ZS 7rq4. o/oc. /
qq ay (Program Name, Version, File Name'extension/rize/date/hour/min)
-IV-OZ/'e:z3At Design Impact review completed?.
] Yes
[X] NIA, Per EC#:
337551 (If yes, attach impact review sheet)
Prepared by Z
Print Date Reviewed by: 'PL
,,Ag
/Ot-/'-jd' Print Sign Date Method of Review:
[X] Detailed
-This Design Analysis supersedes: _
[ ] Alternate
.[ ] Test
, In Its entirety.
w Approved by: S Iffy*'
Print Sign
' Date External Desiqn Analysis Review (Attachment 3 Attached) nfla.,ts..
,J k."
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Print Print
. Sign
- Date Approved by:
I
- Sign Date:
Do any ASSUMPTIONS/ENGINEERING JUDGEMENTS require later verification?
Tracked By: AT#. EC# etc.)
[ I Yes [X]No, Page2of5 (Printed: 06/14/02 10:23 AM)
E-Form CC-AA-309-1 v1.0 for use with CC-AA-309 Revision 1 and above.
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7 CC-AA-309 - ATTAC.HMENT 1 - Design Analysis Approval Page 3 of 5 DESIGN ANALYSIS NO.
NED-I-EIC-0097 REV:
3 PAGE NO. 3 Revision Summary (including EC's incorporated): This revision was made to analyze an increased calibration interval per extended AOT/STI submittal. Deleted Attachment A. Added Attachment C. Revision bars are shown only where content changes, not forre-formatting or re-numbering. Pages revised are: 3, 4, 6-10, 12-20,22.
Electronic Calculation Data Files:
(Program Name, Version, File Name extension/size/date/hour/min)
Design Impact review completed?
[*3Yes
[ ] N/A, Per EC#:-
(If yes, attach impact review sheet)
Prepared by:
J.D. Lee (S&L)
/
/
11/12/98 Print Sign Date Reviewed by:
A. C. Go (S&L)
/
I 11/12/98
. Print Sign Date Method of Review:
[X1 Detailed
[ ] Altemate
[ ] Test This Design Analysis supersedes: -
in Its entirety.
Approved by:
Prnnl Sign Date External Design Analysis Review (Attachment 3 Attached)
Reviewed by:
/
Print Sign Date Approved by:
I Print Sign Date Do anyASSUMPTIONS/ENGINEERING JUDGEMENTS require later verification?
[ ] Yes [X] No Tracked By-AT#, EC# etc.)
Page 3 of 5 (Printed: 06/14/02 10:23 AM)
E-Form CC-AA-309-1 v1.0 for use with CC-AA-309 Revision I and above.
CC-AA-309 - ATTACHMENT 1 - besign Analysis Approval.
Page4of 5 DESIGN ANALYSIS NO.
NED-I-EIC-0097 REV:
2 PAGE NO.
4 Revision Summary (including EC's incorporated): This revision determines a new setpoint value based on the new Tech Spec Upgrade LCO. Calculation also includes all errors associated with increasing the surveillance period to quarterly intervals and includes the addition of the Beta Model 320 to the approved M&TE equipment list.
e~
Electronic Calculation Data Files:
(Program Name, Version, File Name extension/size/date/hour/min)
Design impact review completed?
[
(If yes, attach impact review sheet)
Prepared by:
R. W. Ellen
/
Print Reviewed by:*
W. D. Crumpacker /
Print Method of Review:
[X] Detailed
[ 1 This Design Analysis supersedes:-
] Yes
[ ]NWA, Per EC#:_
/
1 1
9/15/95 Sign Date
/___ 9/15/95 5
Sign Date hdtemate
[ ] Test in its entirety.
. ~ ~~~~~~~~~~~~~~~~
MppluveU I
.y; Print.
Sign Date
- Z%1t3ara-ei-n*a isnve-,ALa-m ni4Aan Reviewed by
Print I.
I Sign Date*
Approved by:
Print Sign Date Do anyASSUMPTIONS/ENGINEERING JUDGEMENTS require later verification?.
[ ] Yes [X1 No Tracked By'. AT#, EC# et.)tc Page4of5 (Printed: 06/14/02 10:23 AM)
E-Form CC-AA-309-1 vi.0 for use with CC-AA-309 Revision 1 and above.
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- CC-AA-309 - ATTACHMENT 1 - Design Analysis Approval Page 5 of 5
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e, DESIGN ANALYSIS NO.
.NED-I-EIC-0097 REV:
~01 PAGE NO.5 Revision Summary (including EC's incorporated): This revision computes a new setpoint with a larger setting tolerance to decrease the necessity for frequent calibrations while ensuring a positive margin, per Dresden IMD request. Clarified Assumption 16.
Electronic Calculation Data Files:
(Program Name, Version, File Name extensionfsizeldate/hour/min)
Design impact review completed?
[ l Yes
[ ] N/A, Per EC#:
(If yes, attach impact review sheet)
Prepared by:
E. A. Kaczmarski
/
Print Reviewed by:
M. S. Banopon
/
Print Method of Review:
[X] Detailed
[ ] A This Design Analysis supersedes:
Sign
/__3/5/93 Date 1
3/8/93_
Date hltemate Sign
[ ] Test in its entirety.
,- -.. !, -
4 Appruvou r y;
_!I Print Sign Date I
a Reviewed by:
Print Sign I.
Date Approved by:
Print Sign Date Do any ASSUMPTIONS/ENGINEERING JUDGEMENTS require later verification?
[ ] Yes [XI No,.
Tracked By. AT#, EC# etc.)
Page 5 of 5 (Printed: 06/14/02 10:23 AM)
E-Form CC-AA-309-1 vi.0 for use with CC-AA-309 Revision 1 and above.
.~~~~~~~~~~~~~~~~I
'1. fl NEP-12-02.02 Effective Date:
01/07/00 REVISION
SUMMARY
CALCULATION NO.
h NED-I-EIC-0097 REV:. 0 PAGE NO. 6 REVISION
SUMMARY
Revision 0, Initial Issue.
Electronic Calculation Data Files:
(Program Name, Version, File Name extension/size/date/hour/min)
Prepared By:
E. A. Kacznarski-9/3/92 (Print/Sign/initial)
Date Reviewed By:.
M.S. Banogon 9/30/92 (Print/Sigrnhnitial)
Date Type of Review:
[X] Detailed
[ ] Alternate
[
Test
[ ] Repetitive Calculation DoanyASSUMPTIONSIENGINEERINGJUDGMENTSrequiredlaterverirication?
[ ] Yes [3 No Tracked By: (AT#, etc.)_
PEPP-E FORM
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Revision 0 Nuclear.
DESIGN ANALYSIS TABLE OF CONTENTS 0
ANALYSIS NO. NED-I-EIC-0097 REV. NO. 5 PAGE NO. 7 SECTION:
PAGE NO.
I SUB-PAGENO.
DESIGN ANALYSIS COVERSHEET 1
TABLE OF CONTENTS 7
1.0 Purpose / Objective 8
2.0 Methodology and Acceptance' Criteria 8
3.0 Assumptions / Engineering Judgements
.11 4.0 Design Input 12 5.0 References.
15 6.0 Calculation / Numerical Analysis 18 7.0 Summary and Conclusions 28 ATTACHMENTS A. GENE-000-0010-4202-01P RO, Class I11, January 2003, GE Al-A35 Nuclear Energy "Engineering Evaluation of Impact-on Transient and safety Analyses of Reducing the Low Pressure Isolation Setpoint Analytical Limit to 785 psig Dresden Units 2 & 3 and Quad Cities Units 1 & 2" a
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l CC-M-309-1 001 o nelts s,
Revision 0 Nuclear Analysis No. NED-I-EIC-0097 I
Revision 5 I
Page 8 of 28 l
1.0 Purpose / Objective The purpose of this calculation is to derive the total error and determine the calculated setpoint, field calibration setpoint, and Technical Specification Allowable Value (Table 3.3.6.1-1, Function 1.b) for the Units 2 and 3 instrumentation loops that perform the Main Steam Line Low Pressure Group I Isolation. The setpoint determination will be evaluated for a quarterly calibration interval and a reduction in the Analytical Limit following the implementation of Extended Power Uprate.
The analysis has evaluated the impact of the time of operation for this function and determined that the environment remains mild for the purposes of instrument accuracy for the period of operation.
Therefore, only normal operating environmental conditions are considered.
Finally, this calculation computes Expanded Tolerance (administrative internal as found limit) for the above switches as necessary to support surveillance activities.
This calculation applies to Dresden Instrument Surveillance (DIS) Procedures DIS 0250-02, Main Steam Line Low Pressure Isolation Switch Calibration (Reactor Mode Switch in Run Mode) and DIS 0250-12, Main Steam Line Low Pressure Isolation Switch Calibration (Reactor Mode Switch NOT in Run Mode) for each of the following instruments:
PS-2(3)-0261-30A PS-2(3)-0261-30B PS-2(3)-0261-30C PS-2(3)-0261-30D 2.0 Methodology and Acceptance Criteria 2.1 Basic Methodology The methodology used for this calculation is that presented in NES-EIG-20.04, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy", (Ref. 5.1.2). See also Section 3.0 for assumptions and engineering Judgement issues.
2.2 Classification Level Because this is a Tech Spec loop, the Total Error (Z) is evaluated in conformance with a Level 1 Setpoint as defined in Reference 5.1.2, Appendix D, Graded Approach to Determination of Instrument Channel Uncertainty. As a Level 1, this means that the random errors (a) to a 2a.value are combined via SRSS, and the non-random errors (Ye) are added. The total error is the sum of the random and non-random errors.
TE = 2a + Ye
Exei CC-AA-309-1 001 Revision 0 Nudlear Analysis No. NED-I-EIC-0097 Revision 5 Page 9 of 28 I~~~~~
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2.3 Clarifications to NES-EIC-20.04 2.3.1 Other Environmental. Effects Temperature, ambient pressure and humidity errors, when available from the manufacturer, were evaluated with respect to the conditions specified in the Dresden EQ.
zones. The EQ zone requirements for each instrument are obtained from the Exelon passport Component Data Sheet location data, Component Classification Binder, and the Dresden EQ Zone maps (Ref. 5.6.1, 5.4.1, & 5.4.3). if these errors are not provided, the EQ zone conditions are analyzed to determine if they are within the manufacturers specified operating conditions. If the environmental conditions are bounded, these error effects are considered to be included in the manufacturer's'reference accuracy specification.
2.3.2 Seismic Seismic effects associated with instrumentation at or below those classified as an OBE are considered negligible.. Where the seismic event, which itself is considered a single event from a Licensing viewpoint, is greater than an OBE, then the instrumentation shall be re-calibrated prior to Station operation and therefore are not required to be evaluated in this uncertainty calculation.
2.4 Calculated Setpoint A calculated setpoint will be determined utilizing the following equations based on Appendix C of Reference 5.1.2 where applicable:
=
[lower limit]
where SP:
is the calculated setpoint AL:
'is the Analytical Limit Z:
is the total error for the device including all estimated effects MAR:
is a selected margin used to provide additional conservatism
-Nt1-. ahe nameso fhele~rms nthu-gunedc q-Tnflin accordance with specific device designations.
CC-AA-309-1 001 Exek en.:Revision 0
Nuclear Analysis No. NED-I-EIC-0097
.l Revision 5 Page 10 of 28.
l 2.5 Allowable Value An allowable value will be determined utilizing the following equations based on Appendix C of Reference 5.1.2 as applicable-:
AV SPc - j Zav J
[lower limit]
AV SPc + Zav""I
[upper limit]
where AV:
is the allowable value SPc:
is the calculated setpoint Zav+, Zav-: is the total error (positive, negative) for the device during calibration Note 1: The names of the terms in the generic equations shown above may be modified in' accordance with specific loop designations.
Note 2: The errors that are, included for. the determination of the allowable values (Zav) are only those applicable during calibration. Thus, only errors during normal conditions are included.
Note 3: The Zav is equivalent to the DTI term. See discussion of DTI term below.
2.6 Calibration Tolerance (ST)
The calibration tolerance (or Setting Tolerance, ST) is assumed to describe the limits of the as-left component outputs..For a random error, this corresponds to 100%. of the population and can be statistically represented by a 36 value. Per Reference 5.1.2, the "Setting Toleranceu (ST) is defined as a random error that is due to procedural allowances given to the technician performing the calibration and can be expressed as a 1 a, 2a, or 30 value. :.ST, = calibration tolerance or setting tolerance.
2.7 Expanded Tolerances (ET)
Expanded tolerances are determined for the device as follows, in keeping with the intent of Reference 5.1.2,-Appendix C. See'also Reference 5.1.8.
- b. If any of the tolerances' determined using the equation above results'in an expanded tolerance (ET) value that is less than the setting tolerance (ST),jthen ET = ST is specified.
The expanded tolerance is specified as an acceptable tolerance",for as-found values. It is -
expected that the calibration s'etting tolerance still be utilized as the as-left tolerance.
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Analysis No. NED-I-El.:OO97 Revisloni Page 11 of 28 2.8 Drift Tolerance Interval (DTI)
The Drift Tolerance Interval based on vendor specifications (DTIv) isbased upon reference accuracy, calibration error (CAL), setting tolerance (ST) and drift (D)., For these switches, the reference accuracy consists only df the Repeatability (RPT) term: The' DTv is used in the determination of the Allowable Values and Extended Tolerances. A formal drift analysis has not been performed for this application of the Barksdale B2T-M12SS-TC pressure switch to derive DTIc. Therefore, DTIv will be used.
2.9 Decimal Precision Decimal precision is limited to three decimal places. The final results are rounded to the number of decimal places appropriate for the calibration procedure. Error standard deviations or sigma (a) values are noted in brackets []following the value.
2.10 Acceptance Criteria The acceptance criteria for this calculation is such that the calibration setpoints associated with the subject instrument loops are set such that they are bounded by the calculated setpoint.
There are no acceptance criteria for the allowable value determination. The allowable value is calculated in accordance with the methodology and the results are provided for use.
The expanded tolerances are determined in accordance with Section 2.6 and are acceptable if the result is greater than or equal to the applicable setting tolerance and do not result in a violation of an applicable limit.
3.0 Assumptions I Engineering Judgments 3.1 Published instrument vendor specifications are considered to be based on sufficiently large' samples so that the probability and confidence level meets the 2a criteria, unless stated, otherwise by the vendor.
__ 3.2 ornormaLerrmr-analysisnorm alvibrations-and-seismic-effects-ar-considered-negigible-r capable of being calibrated out In accordance with Appendix I of Reference 5.1.2.
3.3 Head corrections have been evaluated and incorporated in this calculation. Tap and mounting' elevationslwere obtained from separate walkdowns (Reference 5.1.3), or from station drawings (Reference 5.3.3). Head corrections obtained from drawings have not considered installation tolerances'. The head correction listed in the DIS procedure has been used for instruments that could not be verified by a walkdown, or where insufficient drawing information was available.'
Where DIS and walkdown head corrections are available, calculations used head corrections derived from walkdown data. Density corrections have been lncorporated into the specific instrument head correction using the minimum ambient temperature for instrument calibration.
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Revision 0 Nuclear Analysis No. NED-l-EIC:0097 l
Revision.5 Page 12 of 28 3.4 Evaluation of M&TE errors is based on the assumption that the test equipment listed in Section 4 is used. Use of test equipment less accurate than that listed in Section 4 will require evaluation of the effect on the calculation results.
3.5 Per the P&ID drawings (References 5.3.4.1 & 5.3.4.2) the pressure switches tap off of the main steam lines upstream of the Main Turbine Stop valves. The process is-saturated steam. The sample lines go up from the steam taps, run horizontally, and drop to the instrument location (References 5.3.3.1 through 5.3.3.4). In the portion of the sample line that drops to the instrument location, steam condenses to form a subcooled water column. As discussed in Section 3.3 above, allowance is made for this head of water. Process measurement errors for normal operating conditions are considered to be accounted for in the establishment of the existing setpoint. Therefore, Process Error Is considered to be zero.
4.0 Design Input 4.1 Instrument Channel Configuration - The instrument loop consists of a pressure switch.
4.2 The instrument loop is calibrated quarterly per Reference 5.6.3.
4.3 Loop Element Data - Barksdale Model B2T-M12SS-TC Pressure Switch (Ref 5.6.1)
From Reference 5.7.1 Adjustable Range:
77 psig to 1200 psig (Increasing) 50 psig to 1173 psig (Decreasing)
Reference Accuracy: t 0.5% Span Temperature Range: -65 to 1650F (Max. recommended range of pressure media &
ambient temperature) 4.4 Local Service Environments Per References 5.1.3, 5.1.4, 5.3.3, and 5.6.1, the pressure switches are located in panels 2252(3)-lA, in the Turbine Building. The operating conditions that are evaluated are summarized below aresbased on the above references and References 5.4.2 and 5;4.3.
Panel 2252-1A 2253-1A Elevation Between 535'-4 and 536'-8" EQ Zone EQ Zone 30 Normal Operating Conditions Accident Conditions Ambient Temperature..
650F-120OF N/A Ambient Pressure' 14.7 psia N/A Humidity 20 to 90% RH N/A Radiation
<1.0 x 1 RADS (40 years)
N/A 1'..,.
I Exekl rn.S CC-AA-309-1 001 Revision 0 Nuclear I -
Analysis No. NED-I-EIC-0097 Revision 5 I
Page 13 of 28 l
Switch Location: Turbine Bldg. Panel 2252(3)-lA, EQ. Zone 30 (Reference 5.1.3)
PS-2-261-30A PS-3-261-30A PS-2(3)-261-30B PS-2-261-30C PS-3-261-30C PS-2(3)-261-30D
- Mounting Elev.
Mounting Elev.
Mounting Elev.
- Mounting Elev.
Mounting Elev.
Mounting Elev.
536'8" 536'6" 536'6" 5367r*
535,4" 535,4" 4.5 Calibration Procedure Data Dresden Instrument Calibration Procedure DIS 0250-02 (Ref. 5.2.1) provides the historical information below.
Field Calibration Setpoint (SPf)
Sw. Opens @ 850 psig (Decr.) - includes 5 psig head I
Setting Tolerance (ST)
+/- 10 psig **
Surveillance Interval (SI) 3 months fRef. 5.6.3 & 5.6.41 Late Factor (LF) 25% of Calibration Frequency (Ref. 5.6.5]
- Revision 4 of this calculation (NED-I-EIC-0097) 4.6 Analytical Limit (AL)
From Reference 5.5.2, the Analytical Limit for this function is 785 psig.
4.7 M&TE Based on discussion with Instrument Maintenance department personnel, the normal M&TE used in the calibration of the subject pressure switches is the Honeywell Loveland 2020 System Calibrator with a Fluke 700 series pressure module.
References 5.2.1 and 5.2.2 include three options of M&TE for the calibration of the pressure switches, the Honeywell Loveland 2020 with a Fluke 70serjes ressure I
module (either 1000 or 1500 psig ranges) and the Beta 320.
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CC-AA-309-1 001 Revision 0 Nuclear Analysis No. NED-I-EIC-0097 Revision 5 Page 14 of 28 4.8 M&TE Accurracies Per reference 5.1.2 equation C.6, RAMTE is the M&TE referenice accuracy. Per reference 5.5.1:
Beta 320 (0 -1000 psig)
RAMTE = 1.004988 TEMTE = 0 REMTE = 0 (already included in RAMTE value).
Honeywell Loveland 2020 with Fluke pressure module (0-1500 psig)
Honeywell Loveland 2020 with Fluke pressure module (0-1000 psig)
RAMTE = 0.388104 TEMTE = 0 REMTE = 0 (already Included in RAMTE value)
RAMTE = 0.269258.
TEMTE = 0 REMTE = 0 (already included in RAMTE value)
The Beta 320 value will be used in calculations because it is the less accurate of the two instruments even though the Honeywell Loveland is the M&TE primarily used in this calibration; RAMTE = 1.005 (rounded up from 1.004988)
Calibration Standard Errors: In accordance with Reference 5.6.6, the standards used to calibrate the M&TE either meet the 4:1 ratio or the M&TE calibration acceptance tolerance is reduced enough to ensure.that the effect of STD is negligible.
STD (from reference 5.1.2) =0 4.9 Drift Specification Per Reference 5.1.2, Appendix A, drift is assigned as +/-1.0% of Span per refueling interval, up to 30 months. Per Reference 5.6.3, the trip unit calibration interval is 3 months and per Reference 5.1.6 the late factor is 25% of calibration interval.
4.10 Sting Toleran (ST)
As shown in step 4.5 the current setting tolerance is 1/
10 'sig..This existing setting tolerance (ST) will be retained.
4.11 Allowable Value (AV)
See Section 6.5.4.
4.12 Normal Operating Throttle Pressure From Reference 5.5.2, normal operating throttle pressure post EPU is approximately 912 psig.
ExeI X CC-AA-309-1001 axe, on >
Revision 0 Nuclear Analysis No. NED-I-EIC-0097 Revision 5l Page 15 of 28 5.0 References 5.1 METHODOLOGY 5.1.1 ANSI/ISA-S67.04-1994, Setpoints for Nuclear Safety-Related Instrumentation.
5.1.2 NES-EIC-20.04, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy", Revision 3.
5.1.3 Sargent & Lundy, Main Steam Line Low Pressure Switch Sensing Line Walkdown Drawings, Unit 3, page 1 of 4, dated 10/10/91 and Unit 2, page 1 of 3, dated 1/4/90.
5.1.4 ABB Impell Letter 0591-632-001, Dated July 8,1992; transmitting "Dresden Head.
Correction Data Collection Information".
5.1.5 Deleted.
5.1.6 Technical Specification Surveillance Requirement SR 3.0.2, Amendment # 194/188.
5.1.7 ASME Steam tables, 4* Edition.
5.1.8 ComEd document DG99-001245, Improved Technical Specifications (ITS) and 24 month Technical Specifications Project Technical Plan, Revision 2, April 28,2000 5.2 PROCEDURES 5.2.1 DIS 0250-02, Revision 17, Main Steam Line Low Pressure Isolation Switch Calibration (Reactor Mode Switch in Run Position) 5.2.2 DIS 0250-12, Revision 5, "Main Steam Line Low Pressure Isolation Switch Calibration (Reactor Mode Switch NOT in Run Position)."
5.2.3 CC-AA-309, "Control of Design Analyses", Rev. 003
.3
-DRAWWNGG-5.3.1 Dresden Schematic Drawings 5.3.1.1 12E-2501, Sheet 1, Revision AU 5.3.1.2 12E-2501, Sheet 2, Revision AU 5.3.1.3 12E-3501, Sheet 1, Revision AR.
5.3.1.4 12E-3501, Sheet 2, Revision AP
ExeI~n~.
CC-AA-309-1001 Revision 0 Nuclear Analysis No. NED-I-EIC-0097 Revision 5 Page 16 of 28 5.3.2 Dresden Wiring Diagram Drawings 5.3.2.1 12E-2747A, Revision BJ 12E-3747A, Revision BG 5.3.2.2 12E-2747C, Revision BE 12E-3747C, Revision BF 5.3.2.3 12E-2749A, Revision BP 12E-3749A, Revision BJ 5.3.2.4 12E-2749C, Revision BE 12E-3749C, Revision BA 5.3.3 Dresden Instrument Installation Drawings 5.3.3.1 M-31 0, Sheet 23, Revision B 5.3.3.2 M-310, Sheet230, Revision B 5.3.3.3 M-31 0, Sheet 232, Revision B 5.3.3.4 M-494, Sheet 23, Revision 000 5.3.4 Dresden P&lD Drawings 5.3.4.1 M-12, Sheet 2, Revision ABB 5.3.4.2 M-345, Sheet 2, Revision PV 5.4 ENVIRONMENTAL PARAMETERS 5.4.1 Component Classification Binder # CC-DR017 5.4.2 UFSAR, Section 9.4, Air conditioning, Heating, Cooling, AND Ventilation Systems, Revision 4 5.4.3 Calculation DRE01 -0041, Rev. 0, Updated EQ Zone Parameter Tables following Implementation of Extended Power Uprate.
5.5 OTHER EVALUATIONS / CALCULATIONS 5.5.1 DRE98-0047, Rev. 1, Dresden Station Measurement and Test Equipment (M&TE)
Accuracy Calculation 5.5.2 GE Nuclear Energy, GENE-0000-0010-4202-01P RO, Class l1l, January2003, uEngineering Evaluation of Impact on Transient and Safety Analyses of Reducing theLw Low Pressure Isolation Setpolnt Analytical Limit to 785 psig Dresden Units 2 & 3 and Quad Cities Units 1 & 2" 5.5.3 GE Nuclear Energy, SIL 130, March 31, 1975, "Main Steam Line Low Pressure Isolation Limit Change"
CC-AA-309-1 001 Ex e n.
Revision 0 Nuclear Analysis No. NED-E-EI.097 Revision 5
.Page 17 of 28 5.6 OTHER STATION DOCUMENTS 5.6.1 Exelon Passport Records PS 2-261-30A Rev 004 PS 3-261-30A.
Re 005 PS 2-261-30B Rev 004 PS 3-261-30B Rev 005 PS 2-261-30C Rev 004 PS 3-261-30C Rev 005 PS 2-261-30S Rev 004 PS 3-261-30D Rev 005 5.6.2 Dresden Technical Specification Upgrade, Table 3.2.A-1, Isolation Actuation Requirements, Item 3.c, page 3/4.2-3, Unit 2 - Amendment No. 175 dated 10/01/99 and Unit 3 - Amendment No. 171 dated 10/01/99. (Historical Record) 5.6.3 Dresden Technical Specification Table 3.3.6.1-1, Function 1.b, Amendment # 194/188.
- 5.6.4 Dresden Technical Specification Surveillance Requirement SR 3.3.6.1.4, Amendment #
194/188.
5.6.5 Dresden Technical Specification Surveillance Requirement SR 3.0.1 Amendment #
194/188.
5.6.6 CornEd Memorandum Doc. ID # 5795530, Calibration Standard Error (STD) analysis in the instrument setpoint and loop accuracy calculations.
5.7 VENDOR DOCUMENTS 5.7.1 Barksdale Bulletin No. 870420-C, 1990
....... 1- -.,-
.. I CC-AA-309-1001 Exe M
- n.
Revision 0 Nuclear Analysis No. NED-I-EIC-0097 Revision. 5.
, Page 18 of 28 6.0 Calculation / Numerical Analysis 6.1 RANDOM ERROR 6.1.1 Process Error (PE)
From Engineering Judgement 3.5, PE=0 6.1.2 Trip Point Repeatability (RPT)
Repeatability (+/-t0.5% of Span) and switch span (50 to 1173 psig) are given in Section 4.3 for this decreasing setpoint.. This is a.2a value. For a span of 1123 psig the accuracy Is:
RPT = (+/-0.5% of span) (span)
= (.005)(1173 psig - 50 psig)
= 5.615 psig
[2a]
Converting to la, RPT = (5.615/2)
= 2.8075 psig
- [1C]
Rounded to 2.808 psig 6.1.3 Drift Error (aD)
Per Section 4.9, drift is assigned as +/-1.0% of Span per refueling interval, up to 30 months. Per Section 4.9, the trip unit calibration interval is 3 months and the late factor is 25% of calibration frequency. Therefore, aD
= +/- 1.0%
- Span aD
= +/- 1.0% * (1173 psig -50 psig)
[4.3]
- D
=+/-11.23 psig
[2a]
Converting to la aUli 0
=(i11.23psi)Q2 aD1i
=+/-11.23/2 ODi
=+5.615 psi
[1a]
6.1.4 Calibration Error (CAL)
)2 2 +
2 1/2 CAL = + [(RAMTE + TEMTE) + REMTE
+ STD ]
(equation C6 from reference 5.1.2)
Where:
RAMTE = 1.005 psig (Section 4.8)
TEMTE = 0.000'psig (Section 4.8)
ExeInI CC-AA-309-1001 k I
~~~~~~~~~~~~~Reviisi 0
Nuclear Analysis No. NED-I-EIC-0097 l
Revision 5 l
Page 19 of28 REMTE = 0.000 psig (Section 4.8)
STD
= 0.000 psig (Section 4.8)
Therefore:
CAL =+1.005 psig
[1c]
6.1.5 Setting Tolerance (ST)
Per Section 4.5, the existing Setting Tolerance is, ST = +/-10 psig
[3aJ Per Reference 5.1.2, Appendix A, Setting Tolerance is considered to be a 3a Term. Converting to lo:
ST,0 = ST/3 ST,, = +/-lOpsig/3 ST1
= +/-3.333
[1 ]
6.1.6 Random Input Error (IN)
This is the first and only module.-Therefore, there Is no random input error.
IN=Opsig 6.1.7 Determination of Total Random Error (a)
Utilizing Equation C9 from Reference 5.1.2, total random error is, (PE)2 + (RPT)2 + (aD10j2 + (CAL)2 + (ST 0)2+ (IN)2 ]1/2
= i [ (Q)2 +(2.808 psig)2 +(5.615 psig)2 +(1.005 psig)2 +(3.333 psig)2 +(O)2 ]V2
+/-s
- i7.179psig
.[1CY]
6.2 NON RANDOM ERRORS 6.2.1 Humidity Error (eHn)
There are no humidity errors described in the Vendor's specification for the pressure switcn. i hese errors are included in instrument reference accuracy or are negligible.
Therefore, eHn = 0
.oxse.,.n.
I Revision 0 Nuclear Analysis No. NED-I-EIC-0097 Revision 5
. l Page 20 of 28 6.2.2 Temperature Error (eTn)
The Vendor's specification for the pressure switch gives the maximum recommended range of pressure media & ambient temperature as -65 to 1650F (Step 4.3). The normal operating ambient temperature at the switch location is 650F to 1200 F (Step 4.4), which is within the manufacturer's reference conditions for accuracy. Therefore, eTn =0 6.2.3 Radiation Error (eRn)
There are no radiation errors described in the Vendor's specification for the pressure switch. These errors are considered to be negligible (Appendix I of Reference 5.1.2).
Periodic calibration will compensate for any accumulated error. Therefore, eRn=0 6.2.4 Seismic Error (eSn)
Seismic events are not considered under normal operating conditions (Appendix I of Reference 5.1.2 and Section 2.3.2). Therefore,'
eSn =0 6.2.5 Static Pressure Offset (eSPn)
There are no static pressure offset errors described in the Vendor's specification for the pressure switch. Therefore, eSPn=0 6.2.6 Pressure Error (ePn)
There are no ambient pressure errors described in the Vendors specification for the pressureswitch.bhes'crs-are-considered-to-e-includedLin-instrument-reference accuracy. Note, however, that a head correction is applicable to the instrument's location and that head correction is addressed later in this calculation.
~~ePn=0 6.2.7 elRn Insulation resistance (elRn)
Current leakage through insulation is not applicable to these pressure switches, these are simply contacts and this error is not applicable.
elRn=0
' j '...... :. -F-_
-.. I_. %----- --
xekM Nuclear Analysis No. NED-I-EIC-0097 CC-AA-309-1001.
Revision 0 r-I Revision 5 I
Page21 of 28 6.2.8 Margin (MARn)
For this portion of the calculation, no additional margin is added for conservatism.
MARn=0 6.2.9 Power Supply Effects (eVn)
There is no power supply required to operate this instrument, Therefore, eVn - 0 6.2.10 Total Non-Random Error (Ee)
Utilizing Equation C9 from Reference 5.1.2, total non-random error is, Me = +/-[eHn +eTn + eRn+eSn+eSPn+ePn+elRn+ MARn + eVn]
se = +/-[0+0+0+0+0+0+0+0+0]
Me = +/-0 psig 6.3 TOTAL ERROR (TEn or Z)
From Section 2.2, total error for normal conditions is, TEn = Z = + 2a + Ye
[2.2]
Where:
a
= +/- 7. 179 psig Ze
= +/- O psig TEn = Z = +/- 2 ( 7.179 psig) + 0 psig TEn = Z = +/- 14.358 psig
[6.1.71
[6.2.10]
..., - I _.1_.1 1.1-
-l...
-I..,.=..
I
, 1. s-..-
- -.-.
.-.. . 1. 10 I -.. 1,
- . Exek r I
Exe onM Nuclear Analysis No. NED-I-EIC-0097 l
6.4 INSTRUMENT HEAD CORRECTION (hWD.)
CC-AA-309-1 001 Revision 0 Revision 5 l
Page 22of 28 6.4.1 Walkdown Head Correction Reference 5.1.3 provides the following data for determination of required head correction.
Instrument # PS-2-261-30A 30B 30C 30D Mounting Elevation:
536'8" 536'6" 536'7" 535'4" Penetration Elevation:
541'3" 541'3" 541'3" 541'3".
Process Tap Elevation:
544'6" 544'6" 544'6" 544'6" Instrument # PS-3-261-30A 30B 30C 30D Mounting Elevation:
536'6" 536'6" 535'4" 535'4" Penetration Elevation:
545'0" 5450WV 545'0" 545'0" Process Tap Elevation:
544'5%4" 544'51 4" 544'5W4" 544'5 6.4.2 Determination of Head Correction With process tap and instrument mounting in the same environmental location, Walkdown Head Correction (hwD) is determined as follows, hWD
= {(Process Elev-Mounting Elev)(p @ 650F; 1200 psig))
Per Reference 5.1.7, the density of water (p) at 65°F and 1200 psig is 62.5778#/ft3 Process Tap Elev -Mounting Elev Unit 2 PS-2-261-30A 7'8"
= 92n PS-2-261-30B 8'0"
= 96W PS-2-261-30C 7'11"
= 95" PS-2-261-30D 992"
= 110" Unit 3 PS-3-261-30A, B 7'111"
=95%"
PS-3-261-30C, D 9'1/4W
= 109%"4
^r3>s.
.X _ age A,
,,*,~~~~~~~~~~Mi T
7 1.. ;w__"
7.>; ~
~ ~ ~ ~ V -u
-t -
by.I%.
.,1.1 T i
i{- ; :, ]
ExeknO CC-AA-309-1 001 Revision 0 Nuclear Analysis No. NED-I-EIC0097.
Revislon 5 Page 23 of 28 The biggest worst-case distance between process tap location, and mounting elevation location occurs with Instrument # PS-2-261-30D, Therefore, for conservatism, worst-case distances will be used to determine walkdown Head Correction.
Instrument # PS-2-261-30D Process Elev - Mounting Elev = 544'6" - 535'4" = 1 O hwD
= {(1 1O")(62.5778 #/ft3)(ft3/1728 in3))
= 3.984 psig For conservatism, this is rounded up to 5 psig. Therefore, hWD
=eP = 5psig
-, :.,: -
.11-1--.1 I....
.,. -1
- I I.
- Exek~n.
xe 6-n.h K1I Hin -l r CC-AA-309-1001 Revision 0 I Vu~ Goi
-~
Analysis No. NED-I-EIC-0097 Revision.5 Page 24 of 28 1
~
I -4.
6.5 SETPOINT ANALYSIS 6.5.1 Analytical Limit (AL)
From Section 4.6, AL =785 psig 6.5.2 Analytical Limit with Head Correction (ALc)
Per Section 6.4.2 hwD - 5 psig, Therefore, using AL = 785 psig from Section 6.5.1; Instrument # PS-2(3)-261-30A, -30B, -30C, -30D ALc
= AL+ hwD
= 785 psig + 5 psig
= 790 psig 6.5.3 Setpoint Calculation, SPc (including Head Correction)
The calculated setpoint (SPp) is determined from the Analytical Limit (AL) and the total.
error as follows for a decreasing setpoint.
From Section 4.5, the exiting actual instrument (calibrated) setpoint (SPa) = 850 psig.
From Section 6.3, total error (TEn) =+/- 14.358 psig.
From Section 6.5.1, Analytical Limit (AL) = 785 psig From Section 2.4 and Reference 5.1.2, a margin is calculated as 0.5% of span for additional conservatism. The span, is 1123 psig (50 to 1173 psig) per Section 4.3.
- Thus, I
-I I
MAR =0.5%* 1123 psig =5.615 psig From Section 2.4 and Appendix C of Reference 5.1.2 provides the instructions for calculating an Allowable Value for a decreasing setpoint as:
SPc
= 785 psig + 14.358 psig + 5.615psig SPc
= 804.973 psig (w/o head correction)
I
CC-AA-309-1001 OXeI()flM Revision 0 Nuclear I -
Analysis No. NED-I-EIG-0097 I
Revision 5 l
Page 25 of 28 Adding the 5 psig Head Correction, hwD from Section 6.4.2, to SPc:
SPc
= 804.973 psig + 5 psig SPCHD
= 809.973 psig (wi head correction)
Based on the calculated setpoint, a conservative calibration setpoint (SPf and SPfHC) will be established as follows (The calibration setpoint SPfHc is conservative with respect to the calculated setpoint SPCHD, provides additional margin to the AV, but does not affect the Expanded Tolerance):
SPf
= 810 psig decreasing (without head correction)
SPfHc
= 815 psig decreasing (w/ head correction) 6.5.4 Determination of Allowable Value, AV (including Head Correction)
Appendix C of Reference 5.1.2 and Section 2.5 provides the instructions for calculating an Allowable Value for a decreasing setpoint as:
AV = SP - applicable uncertainty Where:
=
Allowable Value SP
=
Calculated Trip Setpoint (SPc) applicable uncertainty =
a value calculated from the errors and uncertainties that have been determined to affect the trip setpoint at the time of the as found measurement.
As described in Reference 5.1.8, the applicable uncertainty is referred to as the drift.
tolerance interval (DTIv). In addition, per Section 2.8,;the DTlv.is determined from the combination of Reference Accuracy or Repeatability (RPT), Drift (a1D), Setting Tolerance (ST) and Calibration Error (CAL). From Section 6.1 of this calculation, the values of these terms are as fIiows:
RPT(la)
= +/-2.808 psig
[6.1.2]
CAL(lo)
= +/-1.005 psig
[6.1.4]
aD(1a)
= +5.615 psig
[6.1.3]
ST(la)
= +/-3.333 psig
[6.1.5]
Per Section 6.1 of this calculation, all four terms used in determining the DTlv are considered as random terms. Thus, the DTIv is calculated as follows:
- - 0
-I.--
-xe onW Revision 0 Nuclear Analysis No. NED-I-EIC-0097 l
Revision 5 I
Page 26 Of 28 Units 2 and 3 DTIv (1 (a) = +/- [(RPT(1 a))2 + (CAL(l a))2 + (D(1 a))2 + (ST(1 a))2]"2 DTIv (1 a) = i [(2.808 psig)2 + (1.005 psig)2 + (5.615 psig)2+ (3.333 psig)2]1'2 DTIv (la) = +/-7.179 psig
[1a]
DTIv (2a)
= +/- 2(DTIv (la))
= +/- 2(7.179 psig)
=
14.358 psig
[2a]
Therefore, the AV is calculated as follows:
AV SPc - DTIv AV 2 804.973 psig - 14.358 psig AV 2 790.615 psig AV 2 791 psig (rounded for conservatism)
The terms included in the AV determinations above are treated in the same way as they are in the setpoint determination. Therefore, adequate margin exists between the Analytical Limit and the Allowable Value, and no check calculation is required.
Adding Head Correction:
AVW
=791 psig+5 psig.
[Section 6.4.2]
AVc
= 796 psig (w/ head correction) 6.5.5 Determination of Expanded Tolerance, ET [Administrative'As Found Limit](including Head Correction)
From Section 6.1 and 6.5.4:
ST(3a)
=+/-l 0psig
[6.1]
ST(2a)
= +/-2(ST(3a)/3)
_ =+/-2(10/3 psig)
= +/- 6.667 psig
[2a]
DTIv (2a)
= +/- 14.358 psig
[2a]
-m CC-AA-309-1001 Lxe^un..
XRevision 0
Nuclear L
Analysis No. NED-I-EIC-0097 f
Revision 5 l
Page 27 of 28 Per Reference 5.1.8, the Expanded Tolerance for these switches is determined as follows:
= +/- [0.7 x (DTIv(2q) - ST(2a))] + ST(2o)
= +/- [0.7 x (1 4.358 psig - 6.667 psig)] + 6.667 psig
=+/-12.051 psig
= +/-12 psig (rounded for conservatism)
In order to evaluate the computed ET value, two comparisons are made. First the expanded tolerance must exceed the 3a value of the setting tolerance.
[pass]
Secondly, the calculated setpoint; minus the expanded tolerance, must not be less than any.
applicable limit. The only limit of concern here is the Allowable Value.
(SPfHc - ET) > AVc where:
SPfHC = 815psig
[6.5.3]
= 12 psig AVc
= 796 psig
[6.5.4]
(815 psig - 12 psig) ? 796 psig.
803 psig > 796 psig
[pass]
Therefore, the computed expanded tolerance is acceptable with respect to the setting tolerance and the ET limit does exceed the Allowable Value. Therefore, ET
=+/- 2 psig (2a) 6.5.6 Margin to Normal Operating Throttle Pressure (NOTP)
A Comparison is made between SPf and the normal process pressure.. For conservatism, the
-terms-are-cided-atgebraicallinsteadif usirg-squareroot-sum-ofthesquares-Forn-4-12, normal operating throttle pressure (NOTP) post EPU is approximately 912 psig.
SPf + ST + TEn < NOTP 810 psig.+ 10 psi + 14.358 < 912 psig
[Sections 6.5.3, 6.1.5, 6.3, 4.12]
834.358 psig < 912 psig
[pass]
GE SIL 130 (Reference 5.5.3) recommends that the nominal setpoint (SPf) be approximately 100 psi less than the turbine inlet pressure and 25 psi above the AL.. The proposed setpoint (810 psig) still meets this generic guidance (approx. 100 psi less than 912 psig and 25 psi above 785 psig). Note, post EPU the other numeric values of SIL 130 are no longer applicable to Dresden.
Exen 1, lCC-AA-309-1 001
.x-e~s~nW Revision 0 Nuclear Analysis No. NED-I-EIC-0097.
Revision 5.
Page 28 of 28 7.0 Summary and Conclusions (FINA'Ll The results summarized below are determined based on a reduction in the Analytical Limit from 825 psig to 785 psig. A License Amendment is required prior to implementation of the-revised setpoint requirements.
The results summarized below are applicable for normal operating and anticipated transient conditions when calibrated with the M&TE specified in Sections 4.7 & 4.8.
Acceptance Criteria The acceptance criteria associated with the setpoint are met since the field calibration setpoints are set such that they are bounded by the calculated setpoint and provide margin to the normal operating throttle pressure.
There are no acceptance criteria for the Allowable Value determination. A License Amendment to incorporate the revised Allowable Value into the Technical Specifications is required prior to implementation of the revised field calibration setpoint.
The acceptance criteria associated with the expanded tolerance are met since the expanded tolerance is greater than or equal to the applicable setting tolerance and does not result in violation of an applicable limit.
Calibration Summary The calibration information used to support the results of this calculation is defined below. In addition, the calibration values and expanded tolerances are identified.'
EPN Parameter Process Units Head
,________ _______Corrected Units 2(3)-0261-30A 2(3)-0261-30B 2(3)-0261-30C 2(3)-0261-30D Analytical Limit (AL) 1 785 psig.
1 790 psig Calculated Allowable Value (AV) 2 791 psig.
Ž796 psig Calculated Setpoint (SPc)
> 804.973 psig
Ž809.973 psig Field Calibration Setpoint Value (SPf) 810 psig 815 psig
- 1.
0 Calibration Frequency and Tolerances Surveillance l
Setting Expanded Interval l
Tolerance Tolerance 3 months
+ 10 psig
+ 12 psig' Note: An amendment to Dresden Technical Specifications to incorporate the specified Allowable Value is required prior to implementation of the Field Calibration Setpoint.
ATTACHMENT 2 NED-I-EIC-0033, Revision 4 Main Steam Line Low Pressure Setpoint Error Analysis Quad Cities Nuclear Power Station
_q
Exelons.'
CC-AA-309-1001 Revision 0 ATTACHMENT 1 Design Analysis Cover Sheet M
Nuclear Il Last Page No. 24 Analysis No.
NED-I-EIC-0033 Revision 004 EC/ECR No.
NA Revision NA
Title:
Main Steam Line Low Pressure Setpoint Error Analysis Station(s)
Quad Cities Component(s)
Unit No.:
Units 1 & 2 PS 1-0261-30A PS 2-0261-30A Discipline I
PS 1-0261-30B PS 2-0261-30B Description Code/
103 Setpoint PS 1-0261-30C PS 2-0261-30C Keyword Safety Class Safety Related PS 1-0261-30D PS 2-0261-30D System Code 0261 Structure CONTROLLED DOCUMENT REFERENCES Document No.
FromlTo Document No.
From/To QDC-0261-1-0813 Is this Design Analysis Safeguards?
Yes No Does this Design Analysis Contain Unverified Assumptions?
Yes El No Z ATI/AR#
Is a Supplemental Review Required?
.Yes 0 No Z Preparer Joseph R. Basak-hi3 3 Print Name
/
ISignName Da Fe Reviewer Bran Edmark H
e V103 Print Name Sign Name Date Method of Review 3 Detailed Review D Alternate Calculations Q Testing Review Notes:
Approver E
6 i
)F_
_l Print Name Sig Date (For ExWMas klats OMA Exelon Reviewer Approver
- Joseph P. Taft Print Name Sign Name I -
Date Print Name Sign Name Date Description of Revision (list affected pages for partials):
Revision 4 determines the calculated setpoint, field calibration setpoint, and allowable value for the Main Steam Line Low Pressure Isolation function based on a reduced Analytical Limit of 785 psig. This revision also incorporates DCR 990502 and format changes in accordance with CC-AA-309; however, the section headings and numbering from the previous revision are maintained. Changes are identified by revision bar.
THIS DESIGN ANALYSIS SUPERCEDES: DCR # 990502 (EC # 30838) AND NED-I-EIC-0033 Revision 003
CC-AA-309 Revision 3 l Page 14 of 15.I ATTACHMENT I General Review Questions Page 1 of I.
DESIGN ANALYSIS NO.
W*1, -T mw-E/e-O.
J'REV:
4
- 1.
Does the design analysis conform to design requirements?
- 2.
Does the design analysis conform to applicable codes, standards, and regulatory requirements?
- 3.
Have applicable design and safety limits been identified?
- 4.
Is the analysis method appropriate?
- 5.
Are the methods used and recommendations given conservative relative to the design and safety limits?
- 6.
Are assumptions/Engineering Judgments explained and appropriate?
- 7.
Have appropriately verified Computer Program and versions been identified, when applicable?
- 8.
Does the Computer Program conform with the NRC SER or similar document when applicable?
- 9.
Has the input been correctly incorporated into the design analysis?
- 10.
Has the input been reviewed by all cognizant design authorities?
- 11.
Are the analysis outputs and conclusions reasonable compared to the inputs and assumptions?
- 12.
Are the recommendations/results/conclusions reasonable based on previous experience?
- 13.
Has a verification of the design analysis been performed by alternate methods?
- 14.
Has all input data been used correctly and is it traceable?
- 15.
Has the effect on plant drawings, procedures, databases, and/or plant simulator been addressed?
- 16.
Has the effect on other systems been addressed?
- 17.
Have any changes in other controlled documents (e.g. UFSAR, Technical Specifications, COLR, etc.) been identified and tracked?
- 18.
When applicable, are the analysis results consistent with the proposed license amendment?
- 19.
Have other documents that have used the calculation as input been reviewed and revised as appropriate?
Yes 0.
10
. N EC 0
RI No
'l 0
El El El El N/A
.0 El El El El El E~l El RI 0
El El 19 0
0.
El RI ElI
'El El El El El El RI1 El El El I
4/6~l //30/a3
CC-AA-309-1001 l~xeitbn.m.
Revision 0 Nuclear DESIGN ANALYSIS TABLE OF CONTENTS ANALYSIS NO.
NED-I-EIC-0033 REV. NO. 4 PAGE NO. 2 SECTION:
PAGE NO.
I SUB-PAGE NO.
DESIGN ANALYSIS COVERSHEET 1
TABLE OF CONTENTS 2
1.0 PURPOSE / OBJECTIVE 3
2.0 METHODOLOGY AND ACCEPTANCE CRITERIA 3
3.0 ASSUMPTIONS 5
4.0 DESIGN INPUTS 6
5.0 REFERENCES
7 6.0 INSTRUMENT CHANNEL CONFIGURATION 8
7.0 PROCESS PARAMETERS.
9 8.0 LOOP ELEMENT DATA 9
9.0 CALIBRATION INSTRUMENT DATA 10 10.0 CALIBRATION PROCEDURE DATA 10 11.0 CALCULATION 11 12.0 SETPOINT ERROR ANALYSIS 19 13.0 SETPOINT ERROR ANALYSIS CONCLUSIONS 24 ATTACHMENTS A. Record of Conversation, Peter Price (Terran Technologies, Inc.) and Al-A2 Carl Murphy (Barksdale, Inc.), dated 3/2/2000 B Druck letter, "DPI 601 Operating Temperature Range," from Steven W.
BI Johnson to Richard Sieprawski, dated 12/11/98 C. GENE-000-00104202-OIP RO, Class III, January 2003, GE Nuclear Cl-C35 Energy "Engineering Evaluation of Impact on Transient and safety Analyses of Reducing the Low Pressure Isolation Setpoint Analytical Limit to 785 psig Dresden Units 2 & 3 and Quad Cities Units I & 2" I
Exekon.
Nuclear CC-AA-309-1001
- Revision 0 Analysis No. NED-1-EIC-0033 I
Revision 4 l
Page 3 of 24 l
1.0*
PURPOSE/OBJECTIVE The purpose of this calculation is to determine the calIulated setpoint, Allowable Value, field calibration setpoint, and expanded tolerance for the in)trumentation loops.that perform the Main Steam Line Low Pressure Group I Isolation function. These instrument loops initiate a Group I Isolation (MSIV closure) in the event of low Main Steam Line (MSL) pressure with the Mode Switch in the RUN position. This is a MSLIBreak Detection function.
This calculation evaluates the instrument loops associated with pressure switches PS 1(2)-
0261-30A, B, C, & D. This evaluation will determine errors associated with normal operating environmental conditions and station selected measurement and test equipment, to ensure compliance with the Quad Cities Technical Specifications. Per Reference 5.19, the switches are required to mitigate the effects of a Main Steam Line Break (MSLB). Because this event does not create a harsh environment for these switches, this calculation evaluates normal plant operating conditions, only.
Determination of total error, calculated setpoint, field calibration setpoint, Allowable Value and Expanded Tolerances is in accordance with References 5.2 and 5.13. This evaluation utilizes a historical drift analysis provided by Reference 5.12.. The setpoint determination will.
be evaluated for a quarterly calibration interval and a reduction in the Analytical Limit following the implementation of Extended Power Uprate. The current Analytical Limit (AL) for the Main Steam Line Low Pressure Isolation is 825 psig (Reference 5.16); however, this calculation determines the setpoint requirements based on a reduced Analytical Limit of 785 psig (Reference 5.21).
2.0 METHODOLOGY AND ACCEPTANCE CRITERIA This calculation is to evaluate instrument loop errors, during normal operating environmental conditions, using specific maintenance and test equipment (M&TE) selected by Quad Cities Instrument Maintenance (TM) Department, to ensure Tech. Spec. compliance. This calculation applies to Quad Cities Instrument Surveillance (QCIS) Procedure No. 200-15, Main Steam Line Low Pressure Calibration and Functional Test, for each of the following instruments:
0 0
0 0
PS 1(2)-0261-30A PS 1(2)-0261-30B PS 1(2)-0261-30C PS 1(2)-0261-30D
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Page 4 of 24 2.1 As-Found and As-Left data were analyzed in Reference 5.12 to determine the drift tolerance interval in accordance with Reference 5.13 and Appendix J to Reference 5.2. Instrument drift is evaluated as follows:
l The vendor drift specification (DTIv) is based upon reference accuracy (RA), calibration error (CAL), setting tolerance (ST) and drift (D).
The calculated drift specification (DTIc) is the calculated drift based on historical As-Found/As-Left data.
The larger of the two values (DTIv.or DTIc) is used in determination of the difference between the Analytical Limit and the Nominal Trip Setpoint.
Historical drift data from Reference 5.12 will be used for the applicable terms included in the uncertainty analysis, in accordance with NES-EIC-20.04, Rev. 1, Appendix J, Section 2.7.
This is a Level 1 Graded Approach Method, and all terms will be expressed in terms of the final desired deviation level of 26.
2.2 The calibration tolerance is assumed to describe the limits of the as-left component outputs.
For a random error, this corresponds to 100% of the population and can be statistically represented by a 3 c value. Per Reference 5.2, the "Setting Tolerance" (ST) is defined as a random error that is due to procedural allowances given to the technician performing the calibration. For this calculation:
ST = (Calibration Tolerance)* 2/ 3 [2a]
2.3 The acceptance criteria for this calculation is such that the calibration setpoints associated with the subject instrument loops are bounded by the calculated setpoint.
There are no acceptance criteria for the Allowable Value determination. The Allowable Value is calculated in accordance with the methodology and the results are provided for use.
The expanded tolerances are determined in accordance with Reference 5.13 and are acceptable if the result is greater than or equal to the applicable setting tolerance and do not result in a violation of an applicable limit.
2.4 Derivation of setpoints and Allowable Values for use in the Improved Technical Specification Project was performed in accordance with the methodology of References 5.2 and 5.13, utilizing the drift tolerance intervals for nominal calibration intervals of 3 months. The current surveillance interval is 3 months (Reference 5.17).
2.5 Expanded tolerances will be computed for each switch, based on the methodology within Reference 5.13.
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I 3.0 ASSUMPTIONS/ENGINEERING JUDGEMENTS 3.1 Published instrument and M&TE vendor performanc specifications are considered to be 2a values unless specific information is available to indi ate otherwise. The least Significant Digit (LSD) for digital indications is assumed to be a 2ca v ue.
3.2 Temperature, humidity and pressure errors have bee incorporated when provided by the manufacturer. Otherwise, these errors are assumed to e included in the manufacturer's reference accuracy specification.
3.3 The only temperature induced M&TE errors that were evaluated were those specified by the manufacturer for a specific model number. This methodology used the most conservative error evaluation by considering the full range of ambient temperature change as specified for the applicable EQ zone.
.1I 3.4 Radiation induced errors associated with normal environments have been incorporated when provided by the manufacturer. Otherwise, these errors are assumed to be small and capable of being adjusted out each time the instrument is calibrated.
3.5 Instrument sensing lines are assumed to be cold and dead-ended. As such, process fluid temperature in contact with the instrument is assumed to be ambient temperature.
3.6 It is assumed that the M&TE listed in Section 9.0 is calibrated to required manufacturer's recommendations and within the manufacturer's required environmental conditions.
Temperature related errors are based on'the difference between the manufacturer's specific calibration temperature and the worst case temperature at the device is used.
3.7 Based on Assumption 3.6, it is assumed that the calibration standard accuracy error of primary calibration equipment is negligible with respect to other error terms.
3.8 Evaluation of M&TE errors is based on the assumption that the test equipment listed in Section 9.0 is used. Use of test equipment less accurate than that listed will require evaluation of the effect on calculation results.
3.9 Deleted 3.10 For events at or below an OBE, seismic effects on instrumentation are considered negligible, unless specific Equipment Qualification testing provides results to the contrary. Where the seismic event, which itself is considered the single event from a Licensing viewpoint, is greater than an OBE, then the instrument shall be recalibrated prior to Station operation. Therefore, seismic effects are not evaluated in this uncertainty calculation.
3.11 Deleted
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Analysis No. NED-I-EIC-0033 Revision 4l Page 6 of 24 4.0 DESIGN INPUTS 4.1 Reference 5.12 states that the bounding 1 15-day drift tolerance interval for the Barksdale Model B2T-A12SS/B2T-M12SS-TC pressure switch has been determined to be a random i1 6.8 psig, with no bias term. This drift was conservatively treated as time dependent and the random portion is conservatively treated as normally distributed. The random term is considered to be a 2a value.
4.2 Only normal environmental conditions have been considered unless specifically identified.
Temperature, radiation and humidity errors, when available from the manufacturer, were evaluated with respect to the normal conditions specified in the Quad Cities EQ zones.
Instrument location was obtained from the CECo Instrument Database (EWCS) (Reference
.5.6). Locations were then correlated to EQ zones and application environments were determined using the Quad Cities Enviornmental Zone Maps (Reference 5.1 0.a and 5.10.b).
Seismic Effects are not included in this evaluation, as discussed in-Section 3.10.
4.3 Head corrections have been evaluated and incorporated in this calculation. Elevations were obtained from separate walkdowns or station drawings. Head corrections obtained from drawings have not considered installation tolerances. Density corrections have been incorporated using the most limiting temperature for the area of concern.
4.4 Instrument reference accuracy is obtained from published manufacturer's specifications (Reference 5.4).
4.5 Deleted 4.6 Deleted 4.7 Calibration Tolerance was obtained from the associated QCIS calibration data sheet.
4.8 Deleted 4.9 The Analytical Limit (AL) for the Main Steam Line Low Pressure Isolation is 785 psig per Reference 5.21 (previously 825 psig per Reference 5.16). This is the process requirement and does not include calibration requirements, i.e., head correction.
4.10 The minimum temperature experienced by the switches and instrument tubing routed throughout the Turbine Building is 650F (Reference 5.15).
4.11 Per Reference 5.17, the switches are calibrated on a 3-month calibration cycle; 4.12 Per Attachment B, Druck Incorporated has indicated that the temperature effect of the Druck DPI 601 (+/-0.006% of reading/0F) applies up to a maximum temperature of 1227F.
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5.0 REFERENCES
5.1 ANSI/ISA-S67.04-1 988, Setpoints for Nuclear Safe Related Instrumentation.
5.2 NES EIC-20.04 Revision 3, Analysis of Instrument hannel Setpoint Error and Instrument Loop Accuracy 5.3 Quad Cities Instrument Surveillance Procedures for Iain Steam Line Low Pressure Calibration and Functional Test:
Unit I Division I QCIS 0200-15 evision 011 Unit 1 Division II QCIS 0200-59 Revision 001 Unit 2 Division I QCIS 0200-60, Revision 001 Unit 2 Division II QCIS 0200-61, Revision 001 5.4 Barksdale Bulletin No. S870420-N, 1997, (VETI Binder C0007, Barksdale Pressure Switches).
5.5 Deleted 5.6 Quad Cities Passport Data Records PS 1-0261-30A, Revision 003 PS 2-0261-30A, Revision 002 PS 1-0261-30B, Revision 003 PS 2-0261-30B, Revision 002 PS 1-0261-30C, Revision 002 PS 2-0261-30C, Revision 002 PS 1-0261-30D, Revision 002 PS 2-0261-30D, Revision 002 5.7 NED-I-EIC-0255, Measurement and Test Equipment (M&TE) Accuracy Calculation for.Use with Commonwealth Edison Company Boiling Water Reactors, Rev. 0, April 14, 1994 5.8 Deleted 5.9 ABB Impell Letter 0591-449-001, (Dated 3-20-91); Head Correction Determination 5.10 Quad Cities Environmental Zone Maps
- a. M-4A, Sheet 1, "Environmental Zone Map (Basement Floor Plan) Elevation 554'-0" Figure 1," Revision E
- b. M-4A, Sheet 3, "Environmental Zone Map (Mezzanine Floor Plan) Elevation 623'-0" Figure 3," Revision D 5.11 ABB Impell Letter 0059-80012-001; (Dated 06-23-93), Head Correction Determination 5.12 Quad Cities Calculation QDC-0261-I-0813, "Instrument Drift Analysis for Barksdale Model B2T-A12SS/B2T-M12SS-TC [PS-1(2)-0261-30A,B,C,D]," Rev. 0, dated 11/8/99
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iII CC-AA-309-1001 Revision 0 Analysis No. NED-I-EIC-0033 Revision 4 Page 8 of 24 5.13 ComEd Document No. DG99-001245, Improved Tec ical Specifications (ITS) and 24-Month Technical Specifications Project Technical Plan, Revi ion 2, April 28, 2000 5.14 Quad Cities Drawings
- a. M-100, "Main Steam Piping Plan and Sections,"
ev. N
- b. M-101, "Main Steam Piping Plan and Sections," ev.M
- c. 4E-1 503A, "Schematic Diagram PCI System Pan 1901-15 Trip Logic and Condenser,"
Rev. AM
- d. 4E-I503B, "Schematic Diagram PCI System Pan 1 901-17 Trip Logic and Condenser,"
Rev. AU
- f. 4E-2503A, Sheet 2, "Schematic Diagram PCI System Panel 902-15 Trip Logic and Condenser," Rev. AE
- g. 4E-2503B, Sheet 1, "Schematic Diagram PCI System Panel 902-17 Trip Logic," Rev. AE
- h. 4E-2503B, Sheet 2, "Schematic Diagram PCI System Panel 902-17 Trip Logic," Rev. AK 5.15 Quad Cities Station UFSAR, Section 9.4.4.1, Turbine Building Area Ventilation System, Design Basis, Rev. 5 5.16 NDIT NFMO000O26, Seq. 00, "Expanded List of Analytical Limits for Specified Instrument Functions," dated 1/31/00 (HISTORICAL REFERENCE) 5.17 Quad Cities 1 and 2 Technical Specifications through Amendment No. 210/204, Table 3.3.6.1-1 Primary Containment Isolation Instrumentation 5.18 Crane's Flow of Fluids Through Valves; Fittings and Pipe Technical Paper No. 410, 1988 5.19 Specification 13524-103-NOOI, "Environmental Qualification Specification for Electrical Equipment in Response to IE Bulletin 79-O0B/10CFR50.49 for Quad Cities Nuclear Power Station, Units 1 and 2," Rev. 0 5.20 CoinEd letter, Document Number DGOO-000175, "Use Of ComEd Default Drift Values For Instrument Drift Effects," from Thomas B. Thorsell, dated 2/15/2000.
5.21 GENE-000-0010-4202-01P RO, Class III, January 2003, GE Nuclear Energy "Engineering Evaluation of Impact on Transient and safety Analyses of Reducing the Low Pressure Isolation Setpoint Analytical Limit to 785 psig Dresden Units 2 & 3 and Quad Cities Units 1 & 2" 6.0 INSTRUMENT CHANNEL CONFIGURATION 6.1 There are four instrument channels per unit, each consisting of a single pressure switch.
Applicable EPN's include the following:
PS 1(2)-0261-30A PS 1(2)-0261-30B PS 1(2)-0261-30C PS 1(2)-0261-30D
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5.13 ComEd Document No. DG99-001245, Improved Technical Specifications (ITS) and 24-Month Technical Specifications Project Technical Plan, Revision 2, April 28,2000 5.14 Quad Cities Drawings a! M-100, "Main Steam Piping Plan and Sections," Rev. N
- b. M-101, "Main Steam Piping Plan and Sections," Rev. M
- c. 4E-1503A, "Schematic Diagram PCI System Panel 901-15 Trip Logic and Condenser,"
Rev. AM
- d. 4E-1503B, "Schematic Diagram PCI System Panel 901-17 Trip Logic and Condenser,"
Rev. AU
- f. 4E-2503A, Sheet 2, "Schematic Diagram PCI System Panel 902-15 Trip Logic and Condenser," Rev. AE
- g. 4E-2503B, Sheet 1, "Schematic Diagram PCI System Panel 902-17 Trip Logic," Rev. AE
- h. 4E-2503B, Sheet 2, "Schematic Diagram PCI System Panel 902-17 Trip Logic," Rev. AK 5.15 Quad Cities Station UFSAR, Section 9.4.4.1, Turbine Building Area Ventilation System, Design Basis, Rev. 5 5.16 NDIT NFM0000026, Seq. 00, "Expanded List of Analytical Limits for Specified Instrument Functions," dated 1/31/00 (HISTORICAL REFERENCE) 5.17 Quad Cities 1 and 2 Technical Specifications through Amendment No. 210/204, Table 3.3.6.1 -
I Primary Containment Isolation Instrumentation 5.18 Crane's Flow of Fluids Through Valves, Fittings and Pipe Technical PaperNo. 410, 1988 5.19 Specification 13524-103-NOOI, "Environmental Qualification Specification for Electrical Equipment in Response to IE Bulletin 79-OIB/IOCFR50.49 for Quad Cities Nuclear Power Station, Units I and 2," Rev. 0 5.20 ComEd letter, Document Number DGOO-000 175, "Use Of ComEd Default Drift Values For Instrument Drift Effects," from Thomas B. Thorsell, dated 2/15/2000 5.21 GENE-000-0010-4202-01 RO, GE Nuclear Energy "Engineering Evaluation of Impact on Transient and safety Analyses of Reducing the Low Pressure Isolation Setpoint Analytical Limit to 785 psig Dresden Units 2 & 3 and Quad Cities Units I & 2" 6.0 INSTRUMENT CHANNEL CONFIGURATION 6.1 There are four instrument channels per unit, each consisting of a single pressure switch.
Applicable EPN's include the following:
PS 1(2)-0261-30A PS 1(2)-0261-30B PS 1(2)-0261-30C PS 1(2)-0261-30D
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I CC-AA-309-1001 Revision 0 Analysis No. NED-I-EIC-0033 Revikion 4 Page 9 of 24 7.0 PROCESS PARAMETERS 7.1 The Instrument Loop provides a Group I Isolation u n sensing low MSL pressure while the Mode Switch is in the RUN position. The switches nse MSL pressure via instrument tubing, filled with water. Per References 5.6, 5.1O.b, 5.14.a d 5.14.b, tubing is routed from the process connection in the Steam Tunnel (EQ Zone 2 ) to instrument racks 2251-1 (Unit 1) and 2-2252-1 (Unit 2) (EQ Zone 26). Because the ins ent tubing is static, the fill water temperature is assumed to be at ambient temperatur (Section 3.5). The following process parameters exist:
Temperature 65 - 120'F (Section 4.10 and Reference 5.10.b)
Process Water Pressure 804 psig (low pressure setpoint form Section 13) to 912 psig (normnal MSL pressure per Reference 5.21) 8.0 LOOP ELEMENT DATA 8.1 PS 1-0261-30C and PS 1-0261-30D: Barksdale Model B2T-M12SS-TC (Reference 5.6)
PS 1(2)-0261-30A, PS 1(2)-0261-30B, PS 2-0261-30C and PS 2-0261-30D: Barksdale Model B2T-A12SS Pressure Switch (Reference 5.6)
From Reference 5.4 and Attachment A:
- Adjustable Range:
Reference Accuracy:
Temperature Range:
77-1200 psig (Inc.)
50-1173 psig (Dec.)
+/-0.5% of Adjustable Range
-65 to 165°F (Max. recommended range of pressure media & ambient temperature) 8.2 Environmental Data for Switch Location Switch Location Unit 1(2) Turbine Bldg., 61 1'6" Elev.
Panel 2251-1 (Unit I and 2-2252-1 (Unit 2) (Reference 5.6)
From Design Input 4.2, Environmental Zone 26, Normal Operating Conditions, and Sect. 5.10.
Temperature Pressure Radiation Relative Humidity 1200F 14.7 PSIA
<1.0 x1 Rads (40-Year TID) 20 - 90%
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Pagel1 of 24I 11.0 CALCULATION From Ref. 5.2, Equation C9, the Total Error (Z) is eqal to the sum of the Total Random and Total Non-Random Errors (Note: The switch has an alog input and a discrete output.
Therefore, it is classified as a bistable module.)
Equation 11.0:
Z =+/-[ap a
2+
2+<l,'+CAL2 +ST2 +cczN 2f2+/-[eSP+ P+eV+eT+eH+eR+eS+eIR+MAR]
Where all random errors are of the same confidence evel and:
Z
=
Accuracy Represented by the Total Uncertainty a
=
Random Error e
=
BiasError PE
=
Process Error RA
=
Reference Accuracy D
=
Drift CAL
=
Calibration Error ST
=
Setting Tolerance IN
=
Random Input Error(s) eSP
=
Static Pressure Error eP
=
Pressure Error eV
=
Power Supply Error eT Temperature Error eH
=
Humidity Error eR
=
Radiation Error eS
=
Seismic Error eIR
=
Error due to current leakage through Insulation Resistance MAR =
Margin (included only if applicable) 11.1 Process Error (COPE)
The switches sense Main Steam Line pressure via instrument tubing routed to the Instrument Racks. Tubing is routed in the Turbine Building (TB) from the process connection in the Steam Tunnel down to the switches, located in Instrument Racks 225 1-1 (Unit 1) and 2-2252-1 (Unit 2) (References 5.6, 5.14.a and 5.14.b). Per Section 3.5, instrument tubing is static and the fill water temperature is assumed to be at ambient temperature. The process error will be evaluated based on the following sections of the tubing route:
Section I - Steam Tunnel. This section includes the route from the process connection to the zone penetration. Per References 5.6, 5.10.b, 5.14.a and 5.14.b, this corresponds to EQ Zone 25, which has a maximum temperature of 1207F. Minimum temperature in the TB is 650F per Section 4.10. Elevation changes for each switch are summarized, based on references 5.9 and
- 5.11.
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Page 12 of 24 Section 2 - Instrument Racks 2251 -1 and 2-2252 This section includes the route from the zone penetration to the switch. Per References 5.6 and 5.1O.b, this corresponds to EQ Zone 26, which has a maximum temperature of 120'F. Minimum temperature in the TB is 650F per Section 4.10. Elevation changes for each switch are summarized, based on references 5.9 and 5.11.
Instrument No.
Penetration Elev.
Mounting Elev.
Delta h (ah)
PS 1-0261-30A 620'-8" 613'-10" 82" PS 1-0261-30B 620'-8" 613'-10" 82" PS 1-0261-30C 620'-8" 613'-10" 82" PS 1-0261-30D 620'-8" 613'-10" 82" PS 2-0261-30A 621'-5" 614"-4" 85" PS 2-0261-30B 621'-6" 613'-8" 94" PS 2-0261-30C 621'-6" 613'-8" 94" PS 2-0261-30D 621'-8" 613'-8" 96" Since both sections have the same temperature range, they are evaluated together. Based on the above, the maximum temperature range over which the instruments may be calibrated and operated is 65° to 1201F. Therefore, temperature may decrease or increase by as much as 550F between calibration and operation.
ATDEC = (TOP-MIN - TCA1,MAX)
= (65 0F - 120'F)
= -550 F ATINC = (TOP-MAX - TCAL.MIN)
= (120'F - 650F)
= 550F
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Page 13 of 24 The change in fill water density is evaluated over thee ranges to determine the worst-case magnitude of the process error.
Decreasing Temperature Per Reference 5.18, density of water at 120'F is appr ximately 61.7132 lb/f1. Density at 650F is not given directly, but can be approximated by int olation between 60'F (62.371 lb/fR3) and 70 'F (62.305 lb/ft')
p @ 650F
= (62.305 lb/ft3 + 62.3 1 lb/f 3)/2
= 62.338 lb/ft3 Process pressure (MSL pressure) has an impact on fluid density, but this affect is considered negligible for this evaluation. Based on the above tables, the maximum height through which this density change can be experienced is -166 inches (relative to the tap point). The effect of changes in water density on the process pressure at which the switch actuates (PE) is calculated for decreasing temperature (from 1200 to 650F) as follows:
PEDEC = (PFWAL - pImrL) x height
= (62.338 lb/ft3 - 61.7132 lb/ft3) x (1 ft3/1728 in3) x (-166 in)
= -0.060021 psig Increasing Temperature Similarly, the effect on the process pressure at which the switch actuates is calculated for increasing temperature (65° to 120'F) as follows:
PEaC = (PFiNAL - PmrML) X height
= (61.7132 lb/t 3-62.338 lb/ft3) x (1 ft3/1728 in3) x (-166 in)
= +0.060021 psig Even for the worst case, the magnitude of the bidirectional error (+/-0.060021 psig) is negligible compared to other error contributors. Therefore, CYPE
=0 11.2 Reference Accuracy (aRA) aRA
= Reference Accuracy Substituting values from Section 8.1 for a decreasing parameter:
CFRA
= +/-0.5% of Adjustable Range
= +/-0.5%(1173 - 50) psig
= +/-5.615 psig
[2cr]
NOTE: Reference Accuracy will be established per the results of Reference 5.12. Historical drift from the referenced calculation will include this term, thus aRA will be forced to zero in the final loop accuracy computation.
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Page 14 of 24 11.3 Drift (CD)
Per Reference 5.20, a drift value of 1 %/refueling cycle is assigned to this device. Since this is a default drift value, it is conservatively applied (ie., even though the drift value is given in terms of "% span/refueling cycle," it is not reduced for a quarterly calibration).
-1%span
- -++/-l% (1 173 psig - 50 psig)
-+1 1.23 psig
[2cr]
NOTE: Drift will be established per the results of Reference 5.12. Historical drift from the referenced calculation will include this term, thus CD will be forced to zero in the final loop accuracy computation.
11.4 Calibration Error (CAL)
The Calibration Error(CAL) is the sum of the Measurement & Test Equipment (MTE) and the Calibration Standard Error (STD). Hence, from NES-EIC-20.04, Eq. C8, (Ref. 5.2).
CAL = +/-[(RAMTEIN + TEMTEN)2 + REMTErN2 + STDI 2 + (RAMTEour + TEMTEour) 2 +
REMTEo r 2 + STDour2 ]1" Where:
RAMTE Reference Accuracy (MTE)
TEMTE Temperature Error (MTE)
REMTE Reading Error (Analog M&TE)
IAMTE Indication Accuracy (REMTE equivalent for Digital MTE)
STD Calibration Standard Error This instrument loop consists of a pressure switch only, with a process analog input, and a digital output. This means that each of the terms: RAMTEOuT, TEMTEOuT, REMTEour and STDour are equal to zero.
11.4.1 Measurement and Test Equipment Error (MTE)
The switches are calibrated by applying a test pressure to the switch while measuring the pressure with one of the pressure instruments listed in Section 9.0. The one with the greater uncertainty is used in the Calibration Error computation. A determination' of the worst-case M&TE error is performed below.
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Revision 4 Page 15 of 24 11.4.1.1 Measurement and Test Equipment Error for the Heise CMM (0-1000 psig range) -
MTEI:
Per Section 8.2, the maximum temperature e switches may experience is 1201F.
Per Section 4.10, the minimum temperatur experienced by the switches is 650F.
Therefore, the worst-case temperature chan e is ATi = 1200 - 730 - 470F. Per Reference 5., MTE error for a maximum zone temperature of 120'F with a AT of 470F is:
MTE`1(1 ) =+5.705480 psig
[lcr]
11.4.1.2 Measurement and Test Equipment Error fo the Druck DPI-601 (0-1000 psig range) -
MTE2:
Per Reference 5.7:
MTE(10) = +/-[(RA(1,) + IA(^0) + TE(I )2 + RES2]VZ Where RA
= Reference accuracy IA
= Indication accuracy TE
= Temperature effect RES
= Resolution From the data in Section 9.0, RAMTE 2
= +/-0.30% Range
= (+/-0.003 0)(1000- 0 psig)
= L3.0 psig
[2a]
IAMTE2
= +0.006% Range
= (+/-0.00006)(1000 - 0 psig)
= +/-0.060 psig
[2a]
Reference 5.7 evaluates the Druck temperature effect over a range of 320 to 1040F, referenced to 730F. Attachment B states that the temperature effect is actually valid for temperatures up to 1220F. Per Section 8.2, the maximum temperature the switches may experience is 1207F. Per Section 4.10, the minimum temperature experienced by the switches is 650F. Therefore, the worst-case temperature change is AT2= 120° - 73° = 470F.
Conservatively, evaluating the temperature effect at the upper limit of the current setpoint acceptance criteria (Section 10.0):
TEMTE2
= +/-(0.006% of reading/0F) x AT2
= +/-[(0.00006)(858 psig)/0F][470F]
= L2.419560psig
[2cr]
RESMTE2
= 0.1 psig
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Page 16 of 24 Converting to 1 a values:
RAMTE 2(1i)
= (+/-3.0 psig) x 0.5
= +1.5 psig
[a IAMTE2(k,)
(+0.060 psig) x 0.5
+I:0.030 psig
[lo]
TEMTEi( 0)
= (+/-2.419560 psig) x 0.5
= 41.209780 psig
[lo]
Substituting and solving for MTE2:
MTE 2(la)
= +[(RAMTE 2 ('Iq) + IAMTE2(1a) + TEMTE2(1I))
+ RESMTE22]
= +[((1.5) + (0.030) + (1.209780))2 + (0. 1)2]2n psig
= 2.741604 psig
[Ia]
11.4.1.3 Calibration Standard Error, STD The error due to calibration accuracy of calibration equipment standards is assumed to be negligible (Assumption 3.7). Therefore, STD
=0 psig 11.4.2 Selection of CAL term Examining MTEI and MTE2 above, CAL is calculated based on MTEI, the larger of the two MTE errors:
CAL.=
[(MTEh) 2 + (STD)2]'2
= [(5.705480 psig)2 + (0 )2]ln
=:+/-5.705480psig
[as]
Converting to a 2a value
(+/-5.705480 psig) x 2
=+/-1 1.410960 psig
[2cy]
NOTE: CAL will be established per the results of Reference 5.12. Historical drift from the referenced calculation will include this term, thus CAL will be forced to zero in the final loop accuracy computation.
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11.5 Setting Tolerance, ST Per Section 10.0, the Calibration Tolerance is +/-4 psig therefore:
ST.
4 *2 /3=
.666667 psig 11.6 Input Error (aON)
The pressure switches are single devices. They sense Main Steam Line pressure directly and provide contact output upon reaching their setpoint.
ere is no input error associated with these switches. Therefore:
aON 11.7 Static Pressure Offset (eSP)
Static pressure errors do not apply to a pressure switch. Therefore, eSP
==0 11.8 Pressure Error (eP)
The pressure switches sense Main Steam Line pressure directly. There is no error associated with changes in process pressure. Therefore:
eP 0
11.9 Power Supply Effects (eV)
There is no power supply which may affect the accuracy specification for the pressure switch.
Therefore, eV
=0 11.10 Temperature Error (eT)
The Vendor's specification for the pressure switch gives the maximum recommended range of pressure media & ambient temperature as -65 to 1650F (Section 8.1). The normal operating ambient temperature at the switch is 650F to 120'F (Sections 4.10 and 8.2). Therefore, per Assumption 3.5, eT
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Nuclear CC-AA-309-1001 Revision 0 I ___
Analysis -No. NED-I-EIC-0033 Revision 4 l
Page 18 of 24 11.11 Humidity Error (eH)
There are no humidity errors described in the Vendor's specification for the pressure switch.
These errors are assumed to be included in instrument reference accuracy or are negligible (Assumption 3.2). Therefore, eH.
=0 11.12 Radiation Error (eR)
There are no radiation errors described in the Vendor's specification for the pressure switch.
These errors are assumed to be included in instrument drift related errors or are negligible :
(Assumption 3.4). Therefore, eR
=0 11.13 Seismic Error (eS)
Seismic effects are not considered in this evaluation per Section 3.10. Therefore, eS
=0 11.14 Insulation Resistance (eIR)
There is no insulation resistance effect for a pressure switch.
11.15 Margin (MAR)
See Section 12.5.1
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Nuclear III I
II CC-AA-309-1001 Revision 0 Analysis No. NED-I-EIC-0033 Revi~ion 4 Page 19 of 24 l
12.0 SETPOINT ERROR ANALYSIS Using the results from Reference 5.12, Section 7.1, eHistorical Drift (D) is:
D = +/-16.8 psig (115 Days),
And Equation 11.0 (this calculation Section 11.0):
Z = +/-[GE 2 +v 2 +oD2 +CAL2 +ST 2 +aN2] i [e P +eP +eV +eT +eH +eR +eS +eIR +MAR]
We find from Section 11.0 that the value of the random terms crPE and cyN, all bias terms
("eX") and MAR are zero. Therefore, the above equation becomes I
Z = +/-[RA2 + oD2+ CAL2 + ST2]12 Since the historical drift (Reference 5.12, Section 7.1) is normally distributed and obtained from the measured results of a large numnber of surveillance tests, the 2s value of the historical drift (D) includes the terms in the above equation which normally affect a calibration, i.e.:
(1) aRA, (2) aD, (3) CAL, (4) ST We can therefore replace these terms with the historical drift term, D, as follows:.
Z
= +[D~~~2]1/2 z+/-D Since D = 16.8 psig (2a):
z
=+/-[16.82]" psig
= +/-16.8 psig
[2a]
Where +/-16.8 psig is the Total Random Error Note that Total Random error consists only of historical drift (aRA, aD, CAL. and ST). Per reference 5.13, these terms also define Drift Tolerance Interval (DTIc). Therefore, DTIc
= +/-16.8 psig
[2a]
12.1 QCIS Head Correction From Reference 5.3, Head Correction (hQas) = 6 psig 12.2 Walkdown Head Correction Reference 5.9 provides the following for determination of required head correction for Unit 1 switches:
X q
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CC-AA-309-1001 Revision 0 Nuclear I..
Analysis No. NED-I-EIC-0033 Revision 4 l
Page 20 of 24 Instrument PS 1-0261-30A PS 1-0261-30B PS 1-0261-30C PS 1-0261-30D Mounting Elev.
613'1 0" 613'1 0" 613'10" 613'10" Process Tap Elev.
627'06" 627'06" 627'06" 627'06" Delta 164" 164" 164" 164" Reference 5.11 provides the following for determination of required head correction for Unit 2 switches:
Instrument PS 2-0261-30A PS 2-0261-30B PS 2-0261-30C PS 2-0261-30D Mounting Elev.
614'04" 613'08" 613'08" 613'08" Process Tap Elev.
627'06" 627'06" 627'06" 627'06" Delta 158" 166" 166" 166" To determine the worst-case head correction, the minimum temperature in the area of the tube routing must be considered (lowest temperature, highest process density). Since both the process taps and switches are located in the Turbine Building, a minimum temperature of 65 0F is used per Section 4.10..
Walkdown head correction (hWD) is calculated as follows:
hWD
= (delta h) x (p @
65 0F)
Per reference 5.18, density of water at 65 0F is approximately 62.33 8 lb/f 3.
Unit I hwD
= (delta h) x (p @ 65 0F)
= (164 in) x (62.33 8 lb/fl3) x (1 ft3/1728 in3)
= 5.916338 psig Note that the QCIS head correction of 6 psig (Section 12.1) is slightly greater, which is conservative for a decreasing limit. Therefore, a head correction of 6 psig is used.
Unit 2 The worst case head correction for Unit 2 is calculated for PS 2-0261-30B, 30C and 30D:
hwD
= (delta h) x (p @ 65°F)
= (166 in) x (62.338 lb/lf3) x (1 ft/1728 in3)
= 5.988488 psig.
Note that the QCIS head correction of 6 psig (Section 12.1) is slightly greater, which is conservative for a decreasing limit. Therefore, a head correction of 6 psig is used.
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.1 CC-AA-309-1 001 Revision 0
______Analysis No..NED-1-EIC-0033 Revi ion 4 I
Page 21 of 24 l
12.3 Calculation of AL with Head Correction (ALc)
From Section 4.9, the Analytical Limit for Main Ste Line Low Pressure Isolation (not including head correction) is 785 psig.
ALc AL + Head Correction As determined previously, the walkdown head corre tion (hwD) equals the QCIS head correction (hQCls). Therefore, substituting the value or head* correction given in Section 12.1:
ALc
= 785 psig + 6 psig
= 791 psig 12.4 Drift Tolerance Interval Determined from Vendor Specifications and Normal Methods (DTIv)
Per Reference 5.13, Drift Tolerance Interval (DTIv) is determined by combining Reference Accuracy, Drift, Setting Tolerance and Calibration Error. Based on this, the following-random error values developed in Section 11.0 will be used in the development of DTIv (rounded to three decimal places):
Random Errors Reference Accuracy (aRA)
Calibration Error (CAL)
Setting Tolerance (ST)
Drift (CRD)
- i5.615 psig
+/-1 1.41 1 psig
+2.667 psig
+/-11.230 psig
[Section 11.2]
[Section 11.4]
[Section 11.5]
[Section 11.3]
[2c]
[2cr]
[2c]
[2a]
Per Reference 5.13, DTIv is calculated as:
DTIv
_+ [(a) 2 + (CAL)2 + (ST)2 + (aD)h]
=+/- [(5.615)2+ (11.411)2+ (2.667)2+ (11.230)21 /2
-+/- 17.175 psig.
[2cr]
12.5 Setpoint, Allowable Value, and Expanded Tolerance Determination for Improved Technical Specification /24 Month Cycle Extension Project 12.5.1 Setpoint Determination Since the DTIv developed in Section 12.4 is greater than DTIc, it is used in the determination of the Nominal Trip Setpoint as described in Section 2.1.
Per Reference 5.2, Calculated Setpoint (SPc) for a decreasing limit is calculated as follows:
SPc
=AL+(Z+MAR)
CC-AA-309-1001 xeI 6nI Revision 0.
Nudear J.'
Analysis No. NED-I-EIC-0033 I
Revision 4 l
Page 22 of 24 Total error (Z) is shown in Section 12.0 to consist of the same terms that define drift tolerance interval (DTI). Therefore, DTIv can be substituted directly for total error (Z).
As indicated in Section 11.15, additional margin is not required, since As Found and As Left data was analyzed in the determination of DTIc, which is enveloped by DTIv.
However, because DTIc and DTIv are relatively close (16.8 psig and 17.175 psig, respectively), an additional margin of 0.5% of span is added to ensure adequate margin.
The following are therefore used in the development of SPc:
= 791 psig (includes head correction)
[Section 12.4]
Z
= DTIv = 17.175 psig
[Section 12.4]
MAR = 0.5% span
= 0.005 x (1173 psig - 50 psig)
[Section 8.1]
= 5.615 psig Substituting:
SPc
=AL + (Z + MAR)
= 791 psig + (17.175 psig + 5.615 psig)
= 813.790 psig (includes head correction)
A field calibration setpoint (SPf) of 814 psig for this decreasing parameter is conservative and therefore acceptable.
12.5.2 Allowable Value (AV) Determination Per References 5.2 and 5.13, AV for a decreasing setpoint is calculated as follows:
=SPc - (DTIc)
Where SPc
= 813.790 psig (incl. head correction)
[Section 12.5.1]
DTIc = 16.8 psig
[Section 12.0]
Therefore, AV
= 813.790 psig - 16.8 psig
= 796.990 psig
= 797 psig (rounded conservatively)
The terms included in the AV determination were treated in the same way as they were in the setpoint determination. Therefore, adequate margin exists between the Analytical Limit and the Allowable Value, and no check calculation is required.
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III III CC-AA-309-1001 Revision 0 Nii1CIarI Analysis No. NED-I-EIC-0033 Revision 4 l
Page 23 of 24 it-jc r'
'r ~,---
A lr lptina (P Mh ThIptp...;nntmnn 1 IL.J.Y K,;AJpallUtU AUMl%,&
S "AA^%
.t a~^
Per Reference 5.13, ET is calculated as follow ET
= +/-[0.7 x (1 6.8 psig - 2.66666 psig)] + 2.666667 psig
= +/-12.560000 psig
= +/-12 psig (rounded conservatively)
[2c]
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CC-AA-309-1001 Revision 0 Nuclear I -,
Analysis No. NED-I-EIC-0033 l
Revision 4 l
Page 24 of 24 l
13.0 SETPOINT ERROR ANALYSIS CONCLUSIONS The results summarized below are determined based on a reduction in the Analytical Limit from 825 psig to.785 psig. A License Amendment is required prior to implementation of the revised setpoirit requirements.
The results summarized below are applicable for normal operating and anticipated transient conditions when calibrated with the M&TE specified in Sections 4.7 & 4.8.
The calibration information used to support the results of this calculation is defined below. In addition, the calibration values and expanded tolerances are identified.
Calibration Setpoint / Allowable Value:'
EPN Parameter Process Units Head Corrected Units PS 1(2)-0261-30A Analytical Limit 785 psig 791 psig PS 1(2)0261-3OBC Allowable Value 2791 psig
'797 psig PS 1(2)-0261-30C PS 1(2)-0261-30D Calculated Setpoint 807.790psig 813.790 psig (nominal)
Field Calibration 808 psig 814 psig Setpoint (nominal)
Calibration Frequency, Setting Tolerances and Expanded Tolerances:
Surveillance Setting Tolerance Expanded Interval-(3s)
Tolerance (2a)
Channel Calibration Quarterly
+/-4 psig
+/-12 psig and Functional Test Note that the Acceptance Criteria described in Section 2.0 of this calculation are satisfied:
New field calibration setpoint (814 psig) is bounded by the calculated setpoint (813.790 psig, minimum)
Expanded tolerance (+/-12 psig) is greater than the setting tolerance (+/-4 psig) and does not result in a violation of any limit (SPf - ET > AV)
Note: An amendment to Quad Cities Technical Specifications to incorporate the specified Allowable Value is required prior to implementation of the Field Calibration Setpoint.
- 5 STATION/UNIT: Quad Cities/1 and 2
~ ~ ~ ~ ~ ~ ~ ~ ~ o
.6 0,3 0
L CALCULATION NO: DGR99EO52 REV.-NM-Attachment A 9A 7t.
NEP-1 2-02.01 Effective Date: 11/4/99 Page Al of A2 April 21, 2000 Peter A. Price (Terran Technologies, Inc.)
for Rick Sieprawski Commonwealth Edison 22710 2 0 6th Ave. N.
Cordova, II 61242 Carl Murphy Barksdale, Inc.
P.O. Box 58843 Los Angeles, CA 90058
- Carl, Attached please find a Record of Conversation outlining our discussion of 3/2/2000. 1 am including this document in a calculation for the Quad Cities Nuclear Station' and need to have your concurrence that the information is correct. I would appreciate it if you could review the document for accuracy and return it to the above address, with your confirmation or corrections/annotations.
Thank you very much for your cooperation in this manner.
Peter A. Price IPEPP-E FORM
4.
STATION/UNIT: Quad Cities/i and 2 NEP-1 2-02.01
=ffanrthra r~n4f 1 1 A 1o
-Eb-
.- - ETC do33 oo 4 Page P CALCULATION NO: 4GR99G502 REV.NhyA Attachment A Record of Conversation Date:
March 2, 2000 From:
Peter Price, Terran Technologies, Inc.l To:
Carl Murphy, Barksdale Inc. (800-835-1060)
Subject:
Barksdale Pressure Switches, B2T I called Carl to clarify information on Barksdale B2T pressure switches. Specifically, the difference between model numbers B2T-A12SS and B2T-M12SS-TC. Carl stated the following:.
I IoIAi
\\2 of A2' Both are bourdon tube actuated switches (B2T).
The difference between the Al2SS and M12SS is the DC rating of the contacts. The Al 2SS is not rated for 125 and 250 VDC. The M12SS is.
The u-TC" suffix designates that the switches have been cycled at temperature. This is a process performed primarily for the nuclear industry to help stabilize the tube.
The Reference Accuracy, Adjustable Range and Temperature Ratings are the same for the two models.
APPROVED AS ISSUED Barksdale, Inc.
CarloMucph e It Product Sale Spec is I
960oc) i PEPP-E FORM
- a.. A STATION/UNIT: Quad Cities/1 and 2
!NEP-12-02.01 Effective Date: 11/4/99 fj E ET-St-X3 oo
- Page B1-of Bi CALCULATION NO
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