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ENCLOSURE 14a to Attachment 14

Peach Bottom Atomic Power Station Units 2 and 3

NRC Docket Nos. 50-277 and 50-278

Setpoint Calculation For

Average Power Range Monitor Simulated Thermal Power - High

PE-0251

Calc # PE-0251 Rev. 2Page 1

CC-AA-309-1001Revision 6

ATTACHMENT IDesign Analysis Major Revision Cover Sheet

Page I of 5Design Analysis (Major Revision) Last Page No. Attachment 4, page 2

Analysis No.: I PE-0251 Revision: 2 002

Title: Provide Allowable Values (AV) and Nominal Trip Setpoints (NTSP) for Various SetpointFunctions of the NUMAC PRNM System

ECIECR No.: 10-00478 Revision: 1 0

Station(s): Peach Bottom Component(s): "

Unit No.: 2,3 Various (see calculation)

Discipline: PEDE

Descrip. CodelKeyword: 10 N/A

Safety/QA Class: " SR

System Code: 12 60A, 60B, 60F

Structure: 13 N/A

CONTROLLED DOCUMENT REFERENCES Is

Document No.: From/To Document No.: From/To

Tech Spec Sections 3.3.1.1 & 3.3.2.1 To Various (see calculation section 6.0) From

UFSAR Sections 7.2, 7.3, 7.5, 7.7 To

Is this Design Analysis Safeguards Information? 16 Yes RI No Z If yes, see SY-AA-101-106

Does this Design Analysis contain Unverified Assumptions? " Yes E] No 0 If yes, ATI/AR#:

This Design Analysis SUPERCEDES: 11 in its entirety.

Description of Revision (list changed pages when all pages of original analysis were not changed): '9 This revisionsupersedes Minor Revision 1 A entirely and incorporates Minor Revisions 1B, and 1C, as well as:

1) Determines the Allowable Values (AVs) and Nominal Trip Setpoints (NTSPs) for the Average Power RangeMonitor (APRM) Simulated Thermal Power (STP) Flow Biased Scram (Two Loop Operation (TLO) and SingleLoop Operation (SLO)) and APRM STP Flow Biased Rod block (TLO and SLO), in support of Extended PowerUprate (EPU). This includes both reactor recirculation drive flow dependent functions (APRM STP Flow BiasedScram and Rod Block) and "Clamp" functions (APRM STP Flow Biased Clamp Scram and Rod Block).

2) Determines As Left Tolerances (ALT) and As Found Tolerances (AFT) associated with the above-listed APRMSTP Flow Biased functions for use in instrument performance trending.

(Continued on Page I A)

Preparer: 10D.J. Cujko (S&L)

Print Name Sian Name Date

Method of Review: 21 Detailed Review 0 Alternate Calculations (attached) LI Testing ElReviewer: 12 A.S. Luthra (S&L) 1tfL, IFc. .A .S. LAar. 7'r(

Print Name Sign Name ae

Review Notes: 23 Independent review Z Peer review L]

(For Extrnal Anlyses Only) O

External Approver: 24 W.A. Barasa (S&L)__, ____.,__ - 5--Print Name Sign Name Date

Exelon Reviewer: 5 1 c..e C',k r( i C-v- 9_-I_11Print Name Sign Name Date

Independent 3rd Party Review Reqd?26 Yes L NoA. ,,

Exelon Approver: 11 'A e 4. txa'0_ __"_

Print Name Sign Nmete

Calc # PE-0251 Rev. 2Page lA

(Continued from Page 1)

The calculation Excel file for the base revision was not available for incorporating the changes for thisrevision. Therefore, the values determined by this revision have been performed by hand-calculations. R2

This analysis was originally performed via spreadsheet calculations, and computation of resulting valueswere not shown. To provide additional clarity, the computations for the entire calculation are shown inthis revision.

The LER and spurious trip avoidance sections were not previously applied to the determination of NTSP.Therefore, these sections are being deleted. However, LER Avoidance Criteria was applied by GEH forfunctions impacted due to EPU. In order to maintain consistency with the results of this calculation andReference 6.5.6, the LER Avoidance Criteria was applied in this calculation with steps shown in theapplicable section where the NTSP is calculated.

This revision also addresses the revised Analytical Limit for the "Neutron Flux Upscale Trip-Setdown"function as provided by GE. This change has no impact on the calculated NTSP and AV values.

The following affected pages have been replaced/added: 1, lA, lB, IC, ID, IE, 2, 3, 3A, 4, 4A, 5, 5A, 7,8, 8A, 9, 10, 11, 12, 12A, 13, 14, 14A, 14B, 14C, 15-44, Attachment 3, Attachment 4. In addition, theRev. 1 cover sheet was deleted.

Clarifications and Exceptions:

The slope of the Flow Control Line (recirculation flow verse power relationship) during EPU operation ischanging to 0.55, and the existing calculation revision (Rev. 1) is based on a Flow Control Line with aslope of 0.66. This calculation revision will apply the EPU slope value of 0.55. This will reduce thecalculated uncertainty values (i.e., accuracy, drift calibration, PMA, and PEA uncertainties) associatedwith the APRM channel STP flow biased scram and rod block functions only.

The existing Rev 1 of this calculation is performed by Excel software, and actual computations of resultingvalues are not shown. In order to implement the EPU changes and revise the appropriate existing values,the existing calculated values were back-calculated to verify the computations used by Excel. Allcomputations impacted by the EPU changes were verified except for the determination of the 0.80 % ratedP overall flow drift (RFM) value and the 0.91 % rated P channel instrument drift (LD) value which areboth shown on page 18 of Rev 1. It is suspected that the values for these terms should be computed asfollows, which results in values that bounds the existing values:

overall flow drift (RFM) = [(0.57 % rated P)2 + (0.70 % rated P)2]0 5

= 0.90 % rated P (not 0.80 % rated P)

channel instrument drift (LD)(APRM, RFM) (fb) = [(0.90 % rated P)2 + (0.42 % rated p)2]0.5

= 0.99 % rated P (not 0.91 % rated P)

Additionally, the computation for the determination of the 1.22 % rated Q channel instrument drift (LD)value, shown on page 18 of Rev 1, could not be verified. However, this value was not applied in any othersubsequent computations. It is suspected that the value for this term should be computed as follows, whichresults in a value that bounds the existing value:

Calc # PE-0251 Rev. 2Page IB

channel instrument drift (LD)

(RFM) (flow) = [(0.86 % rated Q)2 + (1.05 % rated Q)2 ]o5

= 1.36 % rated Q (not 1.22 % rated Q) R2

As such, the EPU related uncertainties for these terms are determined using the same method as shownabove.

SLO operation uses a GE proprietary method for calculating certain error terms (LA, CA, and LD). Thespecific error terms were provided as input from GE and are not derived in this calculation. The errorterms are referred to within this calculation revision as LA', CA', and LD'. Note that these error terms arelarger and thus more conservative than the error terms used in TLO operation.

Calc # PE-0251 Rev. 2Page IC

ATTACHMENT 2Owner's Acceptance Review Checklist for External Design Analyses

Page 1 of 2R2

No Question Instructions and Guidance Yes I No I N/AI Do assumptions have All Assumptions should be stated in clear terms with enough [

sufficient documented justification to confirm that the assumption is conservative.rationale?

For example, 1) the exact value of a particular parameter maynot be known or that parameter may be known to vary overthe range of conditions covered by the Calculation. It isappropriate to represent or bound the parameter with anassumed value. 2) The predicted performance of a specificpiece of equipment in lieu of actual test data. It is appropriateto use the documented opinion/position of a recognizedexpert on that equipment to represent predicted equipmentperformance.Consideration should also be given as to any qualificationtesting that may be needed to validate the Assumptions. Askyourself, would you provide more justification if you wereperforming this analysis? If yes, the rationale is likelyincomplete.

2 Are assumptions Ensure the documentation for source and rationale for the 5 El [Ecompatible with the assumption supports the way the plant is currently or will beway the plant is operated post change and they are not in conflict with anyoperated and with the design parameters. If the Analysis purpose is to establish alicensing basis? new licensing basis, this question can be answered yes, if the

assumption supports that new basis.3 Do all unverified If there are unverified assumptions without a tracking 11 El Od

assumptions have a mechanism indicated, then create the tracking item eithertracking and closure through an ATI or a work order attached to the implementingmechanism in place? WO. Due dates for these actions need to support verification

prior to the analysis becoming operational or the resultantplant change being op authorized.

4 Do the design inputs The origin of the input, or the source should be identified and 10 El Elhave sufficient be readily retrievable within Exelon's documentation system.rationale? If not, then the source should be attached to the analysis. Ask

yourself, would you provide more justification if you wereperforming this analysis? If yes, the rationale is likelyincomplete.

5 Are design inputs The expectation is that an Exelon Engineer should be able to [] Elcorrect and reasonable clearly understand which input parameters are critical to thewith critical parameters outcome of the analysis. That is, what is the impact of aidentified, if change in the parameter to the results of the analysis? If theappropriate? impact is large, then that parameter is critical.

6 Aredesign inputs Ensure the documentation for source and rationale for thecompatible with the inputs supports the way the plant is currently or will beway the plant is operated post change and they are not in conflict with anyoperated and with the design parameters.,licensing basis?

7 Are Engineering See Section 2.13 in CC-AA-309 for the attributes that are O E] ElJudgments clearly sufficient to justify Engineering Judgment. Ask yourself,documented and would you provide more justification if you were performingjustified? this analysis? If yes, the rationale is likely incomplete.

Calc # PE-0251 Rev. 2Page ID

ATTACHMENT 2Owner's Acceptance Review Checklist for External Design Analyses

Paae 2 of 2No Question Instructions and Guidance Yes I No I NIA8 Are Engineering Ensure the justification for the engineering judgment M 0 0

Judgments compatible supports the way the plant is currently or will be operatedwith the way the plant is post change and is not in conflict with any designoperated and with the parameters. If the Analysis purpose is to establish a newlicensing basis? licensing basis, then this question can be answered yes, if

the judgment supports that new basis.9 Do the results and Why was the analysis being performed? Does the stated 0f Efl

conclusions satisfy the purpose match the expectation from Exelon on thepurpose and objective of proposed application of the results? If yes, then thethe Design Analysis? analysis meets the needs of the contract

10 Are the results and Make sure that the results support the UFSAR defined 1:1 0conclusions compatible system design and operating conditions, or they support a

with the way the plant is proposed change to those conditions. If the analysis

operated and with thne supports a change, are all of the other changing

licening wbasis? documents included on the cover sheet as impactedlicensing bdocuments?

11 Have any limitations on Does the analysis support a temporary, condition or U 0 F1the use of the results procedure change? Make sure that any other documentsbeen identified and needing to be updated are included and clearly delineatedtransmitted to the in the design analysis. Make sure that the cover sheetappropriate includes the other documents where the results of thisorganizations? analysis provide the input.

12 Have margin impacts Make sure that the impacts to margin are clearly shown 0 Elbeen identified and within the body of the analysis. If the analysis results indocumented reduced margins ensure that this has been appropriatelyappropriately for any dispositioned in the EC being used to issue the analysis.negative impacts(Reference ER-AA-2007)?

13 Does the Design Are there sufficient documents included to support the M E]Analysis include the sources of input, and other reference material that is notapplicable design basis readily retrievable in Exelon controlled Documents?documentation?

14 Have all affected design Determine if sufficient searches have been performed to 51 0 Elanalyses been identify any related analyses that need to be revised alongdocumented on the with the base analysis. It may be necessary to performAffected Documents List some basic searches to validate this.(ADL) for the associatedConfiguration Change?

15 Do the sources of inputs Compare any referenced codes and standards to the E 0and analysis current design basis and ensure that any differences aremethodology used meet reconciled. If the input sources or analysis methodologycommitted technical and are based on an out-of-date methodology or code,regulatory additional reconciliation may be required if the site hasrequirements? since committed to a more recent code

16 Have vendor supporting Based on the risk assessment performed during the pre-job S1 E]technical documents brief for the analysis (per H U-AA-1212), ensure thatand references sufficient reviews of any supporting documents not(including GE DRFs) provided with the final analysis are performed.been reviewed whennecessary?

R2

Calc. # PE-0251 Rev. 2Page IE

I R2

Revision Summary

Rev. Description of Revision Names (with DatesNo. Preparer Reviewer ApproverI ECR PB 99-00012, Rev 0 Revises the maximum RBM LTSP, ITSP, and ME Driscoll D.W. Reigel -Not Known-

HTSP NTSP values. Adds RBM LTSP, ITSP, and HTSP values for RBM 02/25/00 02/25/00 10/3/00fitter time constants <0.1 see. Revises the RBM downscale NTSP.Provides clarification of assumptions for calc. D.L. Tyson K.E. Cutler

10/3/00 10/3/002 This revision supersedes Minor Revision IA entirely and incorporates D.J. Cujko A.S. Luthra W.A. Barasa

Minor Revisions 1 B, and 1C, as well as 1) determines the AllowableValues (AVs) and Nominal Trip Setpoints (NTSPs) for the AveragePower Range Monitor (APRM) Simulated Thermal Power (STP) FlowBiased Scram (Two Loop Operation (TLO) and Single Loop Operation(SLO)) and STP flow Biased Rod block (TL0 and SLO), in support ofExtended Power Uprate (EPU); 2) determines As Left Tolerances (ALT)and As Found Tolerances (AFT) for non-clamped APRM STP FlowBiased Scram and Rod Block related functions for use in instrumentperformance tr'ending. This revision also addresses the revised AnalyticalLimit for the "Neutron Flux Upscale Trip-Setdown" function as providedby GE. To provide additional clarity, the computations for the entirecalculation are shown in this revision.

R2

iCalc # PE-0251 Rev 2

PBAPS 2 & 3NUMAC PRNM Setpoint Study

TABLE OF CONTENTS

Section Page Sub-Page

Cover SheetR2

Owner's Acceptance Review Checklist I C

Revision Summary IE

TABLE OF CONTENTS 2

1.0 PURPOSE / OBJECTIVE 3

2.0 SUMMARY OF RESULTS 4

3.0 DESIGN INPUT / CRITERIA 6

4.0 COMPUTERCALCULATIONS 9

5.0 ASSUMPTIONS 9

6.0 REFERENCES 12

7.0 CALCULATIONS 14

7.1 Methods 14

7.2 Computations 14C

7.3 APRM Channel AFT/ALT: RFM Instrument Loop Check 41 R2

8.0 Attachments 44

2

Calc # PE-0251 Rev 2 jR2


1.0 PURPOSE / OBJECTIVE

The purpose of this setpoint design calculation is to provide Allowable Values (AV) and Nominal TripSetpoints (NTSP) for various setpoint functions of NUMAC Power Range Neutron Monitoring(PRNM) System { ARTS [APRM (including LPRM, RFM, LTS Option mI OPRM) / RBM]} for PeachBottom Atomic Power Station Units 2 & 3. Therefore, this calculation utilizes methodologies ofReferences 6.1 and 6.2.1 and updates References 6.3.1 and 6.3.2 [Ref 6.3.2 is a supplement tocalculation #6 of Reference 6.3.1 ].

The methods used in this calculation would be consistent with the requirements of NRC RG 1.105 thatthe methodologies comply with. The results would be validated for adequacy against the appropriatecriteria. jR2

NUMAC PRNM channels addressed herein are as follows (names of functions are given; names maybe slightly different elsewhere, e.g., in specifications):1) APRM setpoints: Neutron Flux Fixed High Trip (Scram), STP Flow-Biased Trip (Scram), STP

Flow-Biased Alarm (Rod Block), STP Clamp Trip (Scram), STP Clamp Alarm (Rod Block),Neutron Flux Upscale Setdown Trip (Scram), STP Upscale Setdown Alarm (Rod Block), NeutronFlux Downscale Alarm (Rod Block), and (Recirculation) Flow Upscale Level Alarm (Rod Block);

2) RBM setpoints: Neutron Flux Downscale, Low, Intermediate, and High Power and Trip, and(Recirculation) Flow Compare Level Alarm (Rod Block).

The objective will be accomplished by:

1. Using the Analytical Limit (ANL)/Design Basis (DB) defined by assorted References 6.3.2, 6.3.6, R6.5.4 and 6.5.6, and using the error terms (LA, CA, LD, PEA and PMA) generated herein to calculate new IAV and NTSP.

2. Comparing the calculated AV/NTSP with the current or expected Technical Specification (TS)values to validate that the current or expected TS values are acceptable, or to determine the new TSvalues to be used.

3. Calculating the adequacy of the selected NTSP against the appropriate criteria (e.g., ANL/DB).

A LER avoidance test is performed to assure that the probability of a setpoint exceeding the Tech Specallowable value during surveillance testing is acceptably low. This evaluation is done by first determining theerrors that may be present during surveillance testing, and then assuring that the margin between NTSPI and R2AV is large enough (in terms of the expected variability due to these errors) to prevent (within acceptableprobability) the setpoint exceeding AV. If the margin is not sufficient, the nominal trip setpoint (NTSP) isadjusted to provide added margin. This adjusted nominal trip setpoint is designated NTSP2. This is a GEproprietary methodology that is further explained in Reference 6.1.

In addition to the above, assorted NUMAC PRNM channels which are not addressed herein utilizegeneric default values defined in various specifications of Reference 6.5.1, or values established by Rother procedures or methodologies (e.g., bypasses, time constants). R2

3

Calc # PE-0251 Rev 2PBAPS 2 & 3

NUMAC PRNM Setpoint Study

Additionally, As Found Tolerances (AFT) and As Left Tolerances (ALT) are computed for the APRM STPflow biased scram and APRM STP flow biased rod block functions using the error terms (loop referenceaccuracy, loop calibration equipment errors, loop calibration equipment reading errors, and loop instrumentdrift) generated herein. These tolerances are determined for use in trending instrument performance. Themethodology utilized is in accordance with Reference 6.2.1.3 and is described in detail in Sections 7.1.11 and7.1.12.

R2

3A



2.0 SUMMARY OF RESULTS

The following AV/TRM and NTSP/IS are calculated in Section 7 by using ANL/DB from assortedReferences 6.3.2, 6.3.6, 6.5.4 and 6.5.6. The NTSP/IS values are determined by allowing adequate marginsto their ANL/DB.

I R2

IR2

2.1 APRMChannel [all % P, exceptitem i, which is%91

TRIP ANL/DB AV/TRM NTSP/IS

a-1. STP Flow BiasedScram (TLO)

a-2. STP Flow BiasedScram (SLO)

b-1. STP Flow BiasedRod Block (TLO)

b-2. STP Flow BiasedScram (SLO)

c. STP Flow BiasedClamp Scram(TLO & SLO)

d. STP Flow BiasedClamp Rod Block(TLO & SLO)

e. Neutron Flux UpscaleTrip -- Setdown

f, STP Upscale RodBlock - Setdown

g. Neutron FluxDownscale Alarm

h. Fixed HighNeutron Flux Scram

Flow Upscale(See assumption5.1 .14)

0.55 W+65.5(Ref 6.5.6)

0.55W+62.2(Ref 6.5.6)

0.55W+55.9(Ref 6.5.6)

0.55W+52.6(Ref 6.5.6)

120.0(Ref. 6.5.6)

110.4(Ref. 6.5.6)

17.3(Ref. 6.5.10)

14.0(Ref. 6.3.2)

0.5(Ref. 6.3.2)

122.0(Ref. 6.5.4)

N/A

0.55W+63.3(Sect. 2.1.1)

0.55W+58.2(Sect. 2.1.1)

0.55W+53.7(Sect. 2.1.1)

0.55W+48.6(Sect. 2.1.1)

118.0(Sect. 2.1.1)

108.4(Sect. 2.1.1)

15.0(Sect 2.1.2)

0.55W+61.3(Sect. 2.1.1)

0.55W+55.4(Sect. 2.1.1)

0.55W+51.7(Sect. 2.1.1)

0.55W+45.8(Sect. 2.1.1)

116.0(Sect. 2.1.1)

106.4(Sect. 2.1.1)

14.6(Sect. 2.1.2)

R2

12.0

2.8

11.6

3.2

119.7

N/A

119.3

120.0(Ref.j6.3.4,6.3.5

W = percent of rated recirculation drive flow

4



2.1.1 APRM Channel: STP Flow Biased Scram and Rod Block

The calculated NTSP and AV values for the APRM STP flow biased scram and APRM STP flowbiased rod block functions determined in Section 7.2 of this calculation are compared to the valuesprovided in Reference 6.5.6 in the following comparison table (Table 2-1). In all cases, the calculatedNTSP and AV values are the same as the values provided by Reference 6.5.6. To achieve this, thecalculated NTSP and AV values are determined by application of GE LER avoidance methodologydocumented in Section 7.1.10 and by application of a ±2% power AGAF tolerance limit from Section5.1.12. Furthermore, the calculated drive flow dependent (or non-clamped) NTSP and AV values forSLO are determined as described above, but with an additional application of GE loop uncertaintyvalues as documented in Reference 6.10.

Table 2-1: Comparison Table

APRM Allowable Value (%o Power) NTSP (% PowerFunction GE Task PE-0251 Comparison GE Task PE-0251 Comparison

Report Value Report ValueValue Value(Ref. 6.5.6) (Ref. 6.5.6)

STP F-B 0.55W+63.3 0.55W+63.3 same 0.55W+61.3 0.55W+61.3 sameScram(TLO)STP F-B 0.55W+58.2 0.55W+58.2 same 0.55W+55.4 0.55W+55.4 sameScram(SLO)STP F-B 0.55W+53.7 0.55W+53.7 same 0.55W+51.7 0.55W+51.7 sameRod Block

STP F-B O.55W+48.6 0.55W+48.6 same 0.55W+45.8 0.55W+45.8 sameRod Block(SLO)STP F-B 118.0 118.0 same 116.0 116.0 sameScram(Clamp)(TLO&SLO)STP F-B 108.4 108.4 same 106.4 106.4 sameRod Block(Clamp)(TLO&SLO)

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2.1.2 APRM Channel: Neutron Flux Upscale Trip - Setdown

The Analytical Limit (ANL) for this setpoint function is changed from 17.0% (per Reference 6.3..2and as noted in Rev. 1 of this analysis) to 17.3% (Reference 6.5.10). However, this ANL change hasno impact on the calculated values for NTSP (14.6%) and AV (15.0%) as determined in Section 7.2.

4A

Calc # PE-0251 Rev 2 IR2PBAPS 2 & 3


2.2 RBM Channel fail % P, exceptitem h, which is%_QJ

TRIP MCPR* ANL/DB AVfTRM NTSP/IS

a. Low Power Setpoint(LPSP)

b. Intermediate PowerSetpoint (IPSP)

c. High Power Setpoint(HPSP)

d. Low Trip Setpoint **(LTSP)(Ref. 6.3.6)

e. Intermediate Trip **Setpoint (ITSP)(Ref. 6.3.6)

f. High Trip Setpoint**(HTSP)(Ref. 6.3.6)

g. Downscale TripSetpoint (DTSP)

30.0 (Ref. 6.3.2)

65.0 (Ref. 6.3.2)

85.0 (Ref. 6.3.2)

27.3

63.4

83.4

27.0

63.1

83.1

1.201.251.301.35

1.201.251.301.35

1.201.251.301.35

118.0/117.0121.0/120.0124.0/ 123.0127.0/125.8

112.0/111.2116.0/115.2119.0/118.0122.0/121.0

108.0/ 107.4111.0/110.2114.0/113.2117.0/116.0N/A

116.2/115.2119.2/118.2122.2/121.212512/124.0

110.2/109.4114.2/113.4117.2/116.2120.2/119.2

106.2/105.6109.2/ 108.4112.2/111.4115.2/114.2N/A

116.2/115.2119.2/118.2122.2/121.2123.0/ 123.0

110.2/ 109.4114.2/113.4117.0/ 116.2117.0/117.0

106.2/ 105.6109.2/108.4111.0/111.0111.0/111.0

5.0(Assumption5.1.15)

10.0(Assumption5.1.14)

h. Flow Compare N/A N/A

*These MCPR limits are based upon a 1.07 Safety Limit MCPR as documented in Reference 6.3.6. If thecycle specific SLMCPR is greater than 1.07, the MCPR values should be adjusted by multiplying the value bythe cycle specific SLMCPR/1.07. See the current Core Operating Limits Report (COLR) for cycle-specificMCPR limits.

**For the LTSP, ITSP, and HTSP AV and NTSP values, the first entry (larger value "w/o filter")

applies for filter time constant (tr1 ) settings of _< 0.1 second while the second entry (smaller'value"w/ filter") applies for settings of 0.1 < T,1 < 0.55 seconds. See Assumption 5.1.17 related to NTSPlimits.

IR2

5



2.3 APRM Channel AFT/AL T: STP Flow Biased Scram and Rod Block

2.3.1 Per Section 7. 1.11, AFT/ALT associated with APRM STP flow biased scram and rod-blockcalibration checks, in accordance with References 6.2.3.2.9 through 6.2.32.16, are provided in thebelow listing.

APRM Channel AFT/ALT for the STP Flow Biased Scram:ALTF.B SCR = N/AAFTF.B SCRAM = N/AAFTF.B CLAMp = N/A

APRM Channel AFT/ALT for the STP Flow Biased Rod Block:ALTF-B ROD BLOCK = N/AAFTF.B ROD BLOCK = N/AAFTF.B ROD CLAMP = N/A

This analysis does not provide an acceptance criteria for the calculated AFT/ALT values. Results aremerely summarized as determined in Section 7.3.

2.3.2 Per Section 7.3, calculated AFT/ALT associate with the combined flow transmitter / recirculationflow monitor (FT/RFM) loop calibration check, in accordance with References 6.2.3.2.1 through6.2.3.2.8, are provided in the below listing.

AFT/ALT for the RFM Loop Calibration Check

RFM ALTLOop =+1.1 %rated QRFM AFTLooP =±1.6 % rated Q

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5A

Calc # PE-0251 Rev. I

PBAPS 2 & 3NUMAC PRNM Semoint Study

3.0 DESIGN INPUT I CRITERIA r

3.1 The purposes ofthe instruments in the PRNM Channels of this Design Calculation are to:

1. provide a warning to the reactor operators via Annunciation in the Control Room2. provide scram trip signals to the Reactor Protection System, and3. provide trip signals to the Rod Withdrawal Block Circuitry indicating that the reactor power orrecirculation flow is exceeding its operational limits.

The calculations in this report are consistent with the following channel diagram, which is based onReference 6.5.1:

PRNM

LPRM LpRh& (to both TripDetectors APRM and APRM sig

FlowElement (2)

RBM Trip

FlowTransmitter (2) SI R .M Trip

I Siga,

6.%PBAI'S PRN'M Setpohit Calcjfinal.doc

Calc # PE-0251 Rev 2 I R2PBAPS 2 & 3


3.2 APRM Channel

3.2.1 Process Design Parameters

Process Variable: Neutron FluxNormal Operating Value: 0 - 100% PowerAnalytical Limit (ANL)/Design Basis (DB): (see above)Allowable Value (AV): (see above)Nominal Trip Setpoint (NTSP): (see above)

Ref6.5.26.5.2

6.3.2, 6.5.4, 6.5.6, 6.5.10Section 7, 6.5.6Section 7, 6.5.6

R2

3.3 RBM Channel


Process Variable: Neutron FluxNormal Operating Value: 0 - 100% PowerAnalytical Limit (ANL)/Design Basis (DB): (see above)Allowable Value (AV): (see above)Nominal Trip Setpoint (NTSP): (see above)

Ref.6.5.26.5.26.3.2, 6.3.6Section 7Section 7

3.4 RFM Channel


Process Variable: Recirculation FlowNormal Operating Value: 0 - 100% Flow

Ref.6.5.26.5.2

7

I R2Calc # PE-0251 Rev 2


3.5 Instrument Data

3.5.1 NUMACRef.

Manufacturer GE-NUMAC 6.5.1

Model No. PRNM 6.5.1

Location Main Control Room 6.5.1

Temp. Range 4.44-50- C (40-122 F) 6.5.1

Instrument Range * 6.5.1

Calibration Span (SP) (%) 0-125 6.5.1, Sect 3.5.3 R2

Electrical Output (Vdc) 0-1.0"* 6.5.1(mAdc) 0-I.0**

* It may vary from 0 to greater than 125% depending on the signals: applies to both flux (power) and

flow.For use by remote **recorders/***meters.

3.5.2 Recirculation Flow Transmitter

Manufacturer Rosemount

Model No. 1153DB6RBN0037

Location Reactor Building

Calibration Temp. 65-900 F

Normal Temperature 65-1020 F

Instrument Range (in WC) 0-2772.9(psid) 0-100

Calibration Span (SP) (in WC) 0-951.8(psid) 0-34.32

Electrical Output (mAdc) 4-20

Ref.

Asm 5.1.6

6.3.1

6.1

6.8.1, Sect. 3.5.4 1R2

6.3.1

6.3.2, Sect. 3.5.3 1R2

6.6.1

8



3.5.3 EPU Impact on Calibrated Instrument Spans

Per References 6.5.6 and 6.5.7, EPU conditions have no impact on calibrated instrument spans.

3.5.4 EPU Impact on Normal Ambient Environmental Conditions

Environmental conditions for EPU are provided in References 6.5.8 (temperature) and 6.5.9(radiation). Reference 6.5.8 identifies no change in normal area temperatures due to EPU for theareas in which the recirculation flow transmitters and NUMAC equipment are installed. Reference6.5.9 identifies an increase in the normal radiation environment due to EPU. However, Reference 6.1implies that normal radiation effects on the NUMAC equipment located in the control room (Section3.5.1) are not applicable to this analysis. Furthermore, per Section 2.6 of Reference 6.1, there are notransmitter radiation effects below 0.1 Mrad gamma TID; and the normal EPU radiation dose in theareas, in which the transmitters are located, are within this limit. Per the above discussion; 1) there isno EPU impact on normal ambient temperature, and 2) there is an increase in normal ambientradiation due to EPU, however, the increase has no impact on instrument performance.

R2

8A

1R2Calc # PE-0251 Rev 2


4.0 COMPUTER CALCULATION

N/A. R2

5.0 ASSUMPTIONS

5.1 Assumptions related to the configuration to which this calculation applies are confirmed to bevalid as part of the Exelon modification process. The remainder have been confirmed to be reasonable R2and appropriate as part of the technical reviews of this calculation.

5.1.1 The currently installed analog NMS (APRM, RBM, and Flow Unit) is replaced by the digitalNUMAC-PRNM arrangement of Reference 6.5.1.

5.1.2 For the APRM, both the flux (neutron) noise error and the flow noise error are 1.25% at 2-sigmavalues from LGS data (Ref 6.3.3); for the RBM, flux noise is 1.0% at 2-sigma; all per Reference 6.3.1.(Regarding flow noise, PBAPS reports that the actual recirculation flow noise measured at PBAPS isapproximately 1/3 to 1/2 of that at LGS (due to plant differences), so this assumption is conservativefor PBAPS).

5.1.3 All individual uncertainty expressions apply to the overall component [LPRM, FT. PRNM(chassis, electronics, signal conditioning, digitizing, etc.)] and are at 2-sigma unless otherwise stated inSection 7. Ultimately, channel uncertainty is normalized to 2-sigma and process units of % power forsubsequent AV, NTSP calculation. For the FT, uncertainties defined in Ref. 6.6.1 are considered 3-sigma, based on Ref. 6.1 and 6.2.1. This calculation uses the original drift specification forRosemount 1153 transmitters of +1/- 0.25% for 6 months (3 sigma value). This specification is moreconservative than the current Rosemount Specification of+l/- 0.20% for 30 months (2 sigma value) andis therefore acceptable. Sigma, called s, is given in the right-hand column of Section 7 for each term.

1R2

5.1.4 The calibration intervals maximum boundary values (and therefore the bases for VDexpressions) are as follows: for flow channel FT and PRNM RFM, 30-months; for PRNM APRM,700-hrs (approximately 1-month); for PRNM RBM, 4-hrs [insignificant time-interval for drift in RBMtrip functions since RBM re-initializes (nulls) after each usage]. These intervals are expected to coveroperational requirements (intervals less than these are therefore covered by this calculation).

5.1.5 PRNM uncertainty specifications include the environmental effect on the equipment.

5.1.6 The FT is assumed to be a Rosemount 1153DB6RBN0037 based on PIMS.

9

Calc # PE-0251 Rev 2 PBAPS 2 & 3 R2


5.1.7 Calibration temperature interval is 65-90 F, based on Reference 6.1

5.1.8 Since overall channel uncertainties are relatively minimal for digital equipment, and settings aredigitally entered into equipment, additional margin is considered negligible and ATSP = NTSP.Hence, STOL/LAZ (setting tolerances and leave-alone-zones) does not apply for PRNM (i.e.,STOL/LAZ is assumed to = 0). STOLs for FT-related calibration are as follows: 0.04 mAdc (based onRef. 6.1 - see assumption 5.1.18), 0.01 Vdc, 2.5 ohms (both based on Ref. 6.5.3). For the DMM usedto calibrate the FT, CEi = 0.026 mAdc (tool-specific treatment based on Ref. 6.2.1 - see assumption5.1.18).

5.1.9 All calibration uncertainty expressions are 3-sigma due to NIST traceability.

5.1.10 Flow element uncertainty (PEA) is 1% of rated loop flow at 2-sigma.R2

5.1.11 Not Used

5.1.12 Per Ref. 6.3.2, AGAF limits are +1- 2% power.

5.1.13 Not Used R2

5.1.14 There is no safety credit taken for the recirculation flow upscale or recirculation flowcomparison alarms. The purpose of the functions is to detect failed or abnormal conditions in the flowinput functions. The replacement system performs the same functions, but now integrates theprocessing equipment into the APRM and RBM hardware. Therefore, except for the transmitterinputs, all flow processing equipment is covered by the APRM and RBM self-test functions. With thisconfiguration, the same trip setpoints as used previously will provide equal or better detectioncapability for abnormal conditions provided the replacement PRNM equipment has equal or better R2performance characteristics compared to the equipment being replaced.

The original equipment was replaced in PECO Mod P000479 with a PLC controller (Reference 6.3.4),but the setpoints from the original equipment were maintained. Therefore, PRNM which eliminates allseparate flow processing hardware except for the transmitter and the initial flow input analog-to-digitalconversion (all calculations are performed digitally), provides substantial improvement in theinaccuracies and drifts compared to the original equipment. Therefore, the current setpoints areadequate and will be retained, except where setpoint changes are required per Reference 6.5.6 forAPRM STP flow biased scram and rod block functions:

The current setpoints are 120% of rated recirculation flow for the flow upscale alarm, and 10% flowdifference for the comparison alarm (8% of span with a span of, 125% = 10%) (Reference 6.3.5).

10

Calc # PE-0251 Rev 2 I PR2PBAPS 2 & 3


These setpoints will be used as nominal setpoints. These functions are not included in the Tech Specor the TRM, so no separate calculation of allowable value or DB will be performed.

5.1.15 Per Ref 6.5.5, there is no safety credit taken for the RBM Downscale Trip. The purpose of thefunction is to provide diagnostic information to assist trouble shooting the system under certainabnormal conditions that may occur. The NTSP is identified in Ref. 6.5.5 as 1.0%. However, percustomer request, 5.0% is utilized as the NTSP. The RBM Downscale Trip is deleted from the TechSpec by PECO ECR #PB 98-01802, so no separate calculation of an allowable value or DB will beperformed.

5.1.16 To compensate for a deadband of 1.0% in the RBM Low Power Setpoint ("auto-bypass")downscale trip setpoint and to convert it to an "upscale trip", subtract 1.1% from the calculated NTSP.The input parameter is carried at a resolution of 0. 1%, so 1.1 % is the smallest value that exceeds thedeadband.

5.1.17 The setpoint analyses justify a NTSP/IS equal to the AV/TRM for the RBM LTSP, ITSP andHTSP trip functions. RBM LTSP, ITSP and HTSP NTSP/IS are limited to 123.0%, 117.0% andI 11.0% respectively due to section A.2.8.2. 1.1 of MELLL/ARTS Topical Report NEDC-32162P (Ref.

6.3.6). Thus, NTSP/IS values shown in Section 2 can not exceed these limits.

5.1.18 Ref. 6.2.1 defines a standard practice, unless an exception is identified, of setting A(FT) equalto twice vendor accuracy for the FT. Ref. 6.2.1 further defines a standard practice to set STOLs andCEs for an FT = A (which would be twice vendor accuracy for the FT). The standard practices in Ref.6.2.1 conservatively provide margin to cover possible variations in the tools and methods used for thecalibration. For this analysis, the A(FT) has been set equal to twice vendor accuracy per Ref. 6.2. 1.However, setting the FT STOL and CE equal to twice vendor accuracy has been judged to beunnecessarily conservative, particularly since the only function affected are the flow biased rod blockand scram functions, neither of which is credited in any safety analyses. For this analysis, the FTSTOL has been set equal to vendor accuracy (consistent with Ref. 6.1) and FT CE has been selected toreflect commonly available DVMs, Fluke Model 8050 or equivalent (Ref. 6.2.1). Ref. 6.2.3 is affectedin the sense that PRNM calibration procedures will have to reflect this assumption of the DVM type.

5.1.19 The RFM performs two square root conversion algorithms that converts the 4 to 20 mA signalsfrom the flow transmitters to a 0 to I Vde output that corresponds to 0 to 125% rated loop flow. Sincethe square root conversion algorithm is non-linear, uncertainty terms appearing at the input of thesquare root conversion must be converted to equivalent output values by use of Equations in Section7.1.13. These equations indicate that the conversion is a function of an operating point at which theinput uncertainty is propagated through the square root algorithm. Therefore, an operating point must R2

be chosen at which the conversion will take place. For this calculation, the operating point isconsidered to be approximately 75% rated loop flow (or 0.6 V = 1 V * 75% /125%). Choosing thisvalue is a compromise in that the error term is then conservative at flows greater than 75%, but non-conservative at flows less than 75%. This is considered acceptable, since in general, plant operatingmargins become larger at low power and low flow conditions.

I1



6.0 REFERENCES

6.1 GE Report NEDC-31336P-A, GE Proprietary Information, September 1996, GE Instrument Setpoint R2

Methodology

6.2 PECO/Exelon Procedures6.2.1 Exelon design analysis related procedures6.2.1.1 Exelon Procedures CC-AA-309, Rev 10, Control of Design Analysis6.2.1.2 CC-AA-309-1001, Rev. 6, Guidelines for Preparation and Processing Design Analyses6.2.1.3 CC-MA-103-2001, Rev. 1, Setpoint Methodology for Peach Bottom Atomic Power Station and

Limerick Generating Station(The above procedures supersede PECO Nuclear Procedure NE-C-420 Rev 3, Design Calculation[including exhibits, mainly -4 ("dash-4")]) R2

6.2.2 Exelon configuration control related procedures6.2.2.1 Exelon Procedure CC-AA-102, Rev. 20, Design Input and Configuration Change Impact Screening6.2.2.2 CC-AA-103, Rev. 21, Configuration Change Control for Permanent Physical Plant Changes6.2.2.3 CC-AA-103-2001, Rev. 3, Setpoint Change Control

(The above procedures supersede PECO Modifications Procedure MOD-C-08 Rev 1, SetpointChanges (no exhibits))

6.2.3 PECO Plant Procedures and Practices covering Surveillance Test and Calibration6.2.3.1 Procedures and Practices for Recirculation Drive Flow Equipment6.2.3.2 Procedures and Practices for NUMAC PRNM Equipment6.2.3.2.1 S12N-60A-1 10-AEC2, Rev. 4, Calibration Check of APRM "1" Flow Bias Signal6.2.3.2.2 S12N-60A-1 10-BFC2, Rev. 4, Calibration Check of APRM "2" Flow Bias Signal6.2.3.2.3 S12N-60A-1 10-CGC2, Rev. 4, Calibration Check of APRM "3" Flow Bias Signal6.2.3.2.4 S12N-60A-1 10-DHC2, Rev. 4, Calibration Check of APRM "4" Flow Bias Signal6.2.3.2.5 SI3N-60A-1 10-AEC2, Rev. 5, Calibration Check of APRM "1" Flow Bias Signal6.2.3.2.6 S13N-60A-1 10-BFC2, Rev. 6, Calibration Check of APRM "2" Flow Bias Signal6.2.3.2.7 SI3N-60A-1 10-CGC2, Rev. 5, Calibration Check of APRM "3" Flow Bias Signal6.2.3.2.8 S13N-60A-1 10-DHC2, Rev. 5, Calibration Check of APRM "4" Flow Bias Signal6.2.3.2.9 SI2N-60A-APRM-I I C2, Rev. 6, Calibration/Functional Check of Average Power Range Monitor R2

(APRM) "I"6.2.3.2.10 S12N-60A-APRM-21 C2, Rev. 6, Calibration/Functional Check of Average Power Range Monitor

(APRM) "2"6.2.3.2.11 SI2N-60A-APRM-31 C2, Rev. 6, Calibration/Functional Check of Average Power Range Monitor

(APRM) "3"6.2.3.2.12 S12N-60A-APRM-4 I C2, Rev. 7, Calibration/Functional Check of Average Power Range Monitor

(APRM) "4"6.2.3.2.13 S13N-60A-APRM- 11C2, Rev. 8, Calibration/Functional Check of Average PowerRange Monitor

(APRM) "I"6.2.3.2.14 SI3N-60A-APRM-21 C2, Rev. 9, Calibration/Functional Check of Average Power Range Monitor

(APRM) "2"6.2.3.2.15 S13N-60A-APRM-31 C2, Rev. 10, Calibration/Functional Check of Average Power Range

Monitor (APRM) "3"

12



6.2.3.2.16 S13N-60A-APRM-41C2, Rev. 9, Calibration/Functional Check of Average Power Range Monitor(APRM) "4"

6.2.3.2.17 IC-1 1-50027, Rev. 3, Calibration, Alignment, Test and Related Functions for NUMAC Power R2

Range Neutron Monitor

6.3 Pre-Existing Calculations/Bases6.3.1 GE Report GE-NE-901-045-1293-1, Power Re-Rate Setpoint Calculations for PBAPS-2, 3

(calculation #6), dated January 19946.3.2 PECO Calculation No. PM-0875 Rev. 10, including ECR PB 97-03269 rev 0, AIR A1057656

"APRM Setpoint Analysis Implementation", dated 11/25/97 (a supplement to Ref. 6.3.1)6.3.3 GE Report GE-NE-208-20-0993-2, Power Re-Rate Setpoint Calculations for LGS-1, 2

(calculation #7), dated August 19946.3.4 PECO ECR PB 95-00382 rev 0, pages 1, 6, 7, 78, "Upgrade APRM Flow Bias Instruments per

Mod P000479", dated 03/23/956.3.5 PECO ECR PB 95-02159 rev 0, page 656.3.6 GE Report NEDC-32162P, Rev. 2, Maximum Extended Load Line Limit and ARTS

Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3, datedMarch 1995

6.4 PBAPS-2&3 Technical Specifications

6.5 Design Specifications R26.5.1 NUMAC Documents6.5.1.1 24A5221 rev 7, NUMAC PRNM System Generic RS6.5.1.2 24A5221HE0 rev 1, NUMAC PRNM System Specific RSDS, PBAPS-2&36.5.1.3 25A5916 rev 3, NUMAC APRM Generic PS6.5.1.4 25A5916ER0 rev 1, NUMAC APRM Specific PSDS6.5.1.5 25A5917 rev 2, NUMAC RBM Generic PS6.5.1.6 25A5917ER0 rev 1, NUMAC RBM Specific PSDS6.5.1.7 25A5041 rev 1, NUMAC OPRM Genetic PS6.5.1.8 25A5041AA rev 1, NUMAC OPRM Generic DSDS6.5.2 22A1372AB rev 3, NMS DSDS, PBAPS-2&36.5.3 GE DRF C51-00136 (4.42)6.5.4 PRNM System Bases for Neutron Flux and STP AL/AV/DB, PBAPS-2,3, Rev. 0, dated

12/15/98 (GE DRF C51-00214-00 (5.6))

12A



6.5.5 PRNM System Bases for RBM Downscale Trip Tech Spec Deletion and Reduced Setpoint, Rev. 0,dated 1/8/99 (GE DRF C51-00214-00 (5.7))

6.5.6 Exelon Generating Company LLC, Peach Bottom Units 2 and 3 Extended Power Uprate Task Report-Task T0506: TS Instrument Setpoints, Rev. 0, dated March 2011 (GE DRF 0000-0108-6952,Exelon Doc. PEAIC-EPU-7)

6.5.7 Exelon Generating Company LLC, Peach Bottom Units 2 and 3 Extended Power Uprate Task Report R2- Task T0307: Reactor Recirculation System, Rev. 0, dated September 2010 (GE DRF 0000-0108-0105, Exelon Doc. PEAM-EPU-14)

6.5.8 Exelon Nuclear, Peach Bottom Atomic Power Station Units 2 & 3, Evaluation 2009-10708, Rev. 0,Final Task Report 24 -HVAC (Exelon Doc. PEAM-EPU- 104)

6.5.9 Final Task Report, Exelon Nuclear Peach Bottom Atomic Power Station Extended Power Uprate,Task T0806, Equipment Qualification - Radiation, Revision 1 (Exelon Doc. PEAE-EPU-8)

6.5.10 Exelon Generating Company LLC, Peach Bottom Units 2 and 3 Extended Power Uprate Task Report- Task T0500: Neutron Monitoring System, Rev. 1, dated March 2011 (GE DRF 0000-0109-1933,Exelon Doc. PEAIC-EPU-2)

6.6 Vendor Documents6.6.1 Rosemount Model 1153DB6RBN0037

6.7 Licensing Documents6.7.1 PECO COLR for PBAPS-3 Reload I1, Cycle 12 Revision 2, dated 3/10/98

6.8 Exelon Documents R2

6.8.1 PB Mod P00507, Design Input Document, Rev. I

6.9 ISA-RP67.04.02-2000 Methodologies for the Determination of Setpoints for Nuclear Safety- R2Related Instrumentation

6.10 Exelon Transmittal of Design Information, Tracking No. PU-2011-020, Rev. 0 (Attachment 4)

13



7.0 CALCULATION

7.1 Methods

7.1.1 The accuracy due to noise is calculated from the LGS data in Reference 6.3.1.

7.1.2 The conversion of the flow error to power is modified by the 0.55 factor (see Section 3.3.1 of R2

Reference 6.5.6 for the slope of the function that defines the analytical limit).

7.1.3 The calibration instrument accuracies used in this calculation are based on a generically-

expected calibration for the NUMAC-PRNM. Accuracy Ratio is considered to be unity (1).

7.1.4 Unless otherwise noted, the unit used in this document is in percent of the rated thermal power.

7.1.5 Unless otherwise noted, the uncertainty values used in calculations in Section 7 are two (2)sigma and ± values.

7.1.6 DELETED R2

7.1.7 Final calculated values (e.g., AV, NTSP) are rounded: 1) in the direction of conservatism (i.e.,away from the ANL/DB), and 2) to one decimal place. Intermediate calculated values (uncertaintyterms, etc.) are not rounded.

various and sundry traditional and ongoing approaches that have evolved over the course of time(essentially Ref. 6.5.3).

7.1.9 LER Avoidance and STA criteria in accordance with the GE methodology (Reference 6.1) are notrequired per the Station methodology (Reference 6.2.1.3), and are therefore not required to be considered inthis calculation revision. However, the Reference 6.1 LER Avoidance Criteria is applied for the APRMSTP Flow Biased trip functions in order to maintain consistency with NTSP and AV values provided bySection 3.3.1 of Reference 6.5.6.

.7.1.10 The methodology used for determining the NTSP listed in Section 2.1 (functions a, b, c, & d only), R2APRM STP Flow Biased Scram and Rod Block (Single Loop and Two Loop Operation), is based on a GEHmethodology referred to as "LER Avoidance" (Reference 6.1). This involves a methodical approach toevaluate the calculated NTSP and determine whether additional margin is needed to ensure the allowablevalue is not exceeded. While this methodology is not addressed in Reference 6.2.1.3 for widespread use, itdoesprovide a more conservative result to the NTSP. In addition, applying this methodology will lead to aresult that is consistent with the values provided by GEH (Reference 6.5.6). Since Reference 6.5.6 onlyapplies to the functions impacted as a result of EPU, this methodology will be applied only for Section 2.1 forfunctions a, b, c, and d only.

14



7.1.11. APRM Channel AFT/ALT: STP Flow Biased Scram and Rod Block Check:

Per Section 5.13 of Reference 6.2.3.2.17 (IC procedure), the APRM STP flow biased scram and rod block(non-clamped) actuation points are checked by applying a simulated total recirculation flow input along with asimulated power input. The simulated flow input is kept constant while the simulated power input is adjustedwhile monitoring the point of actuation. These simulated flow and power inputs are applied digitally with akey-pad. (Note that the SI procedures, References 6.2.3.2.9 through 6.2.3.2.16, do not perform a similarcalibration check of these actuation points.) The NUMAC PRNM system is a digital system with digitalprocessing. As such, setpoints are not affected by instrument accuracy, drift, and calibration equipmenterrors. Settings are entered digitally with a key-pad, and therefore, an ALT does not apply (per Section 5.1.8,STOL/LAZ = 0). Also, since the calibration checks are performed digitally with a key-pad, an AFT also doesnot apply. This is because there is no drift in the digital portions of the system. There will be drift in theanalog-to-digital portions of the system, but not in the digital portions. (Note that per References 6.2.3.9through 6.2.3.17, the analog portions of the system are aligned with external standards such as anoscilloscope, volt meter, and ohm meter). The clamped APRM STP flow biased scram and rod blockactuations are checked similar to the method described above with the exception of applying a simulatedpower input without a corresponding simulated total recirculation flow input. Therefore, the APRM ChannelAFT/ALT for the STP flow biased scram and rod block (both clamped and non-clamped) functions are:

APRM Channel AFT/ALT for the STP Flow Biased Scram:ALT = N/AAFT =N/A

APRM Channel AFT/ALT for the STP Flow Biased Rod Block:ALT = N/AAFT = N/A

Per Reference 6.2.1.3, ALT equals LAZ.

7.1.12. APRM Channel AFT/ALT: Recirculation Flow Monitor (RFM) Loop Check: R2

Per References 6.2.3.2.1 through 6.2.3.2.8, the calibration of the RFM instrument loop is checked by applyingvariable test pressure inputs at the inputs of the recirculation flow transmitters while monitoring totalrecirculation flow rates on the flow rate display. As such, this calculation will determine AFT/ALT associatedwith the RFM loop calibration check from the input of the flow transmitters to the output indication of totalrecirculation flow. The ALT for the RFM loop calibration check is determined by the SRSS of the loopreference accuracy, loop calibration equipment errors, and the loop calibration equipment reading errors. TheAFT is determined by the SRSS of the loop reference accuracy, loop instrument drift, loop calibrationequipment errors, and the loop calibration equipment reading errors. This methodology is in accordance withReference 6.2.1.3. The equations utilized are as follows:

RFM ALTLooP = ±[(RFM ALOOp) 2 + (RFM CELoOP)2 + (RFM CERDG.LOOp)2]0"

RFM AFTLooP = +[(RFM ALOOP) 2 + (RUM VDLoop)2 + (RFM CELooP) 2 + (RFM CERnG.Loop) 2]0S'

14A

Calc 4 PE-0251 Rev 2 IR2PBAPS 2 & 3


where

RFM ALOOP

RFM VDLoopRFM CELooP

RFM CERt.-LOOP

= RFM loop reference accuracy specifications= RFM loop vendor drift specifications= RFM loop calibration equipment uncertainty= RFM loop calibration equipment readability

All uncertainties used in the AFT/ALT determination are considered to be 2-sigma (2a) values.

7.1.13 Uncertainty Propagation through Square Root Conversion Algorithms:

The RFM performs two square root conversion algorithms that converts the 4 to 20 mA signals from theflow transmitters to a 0 to 1 Vdc output. From these values, the transfer equation for converting squareroot conversion input signals to output signals is determined to be,

(V - 0) / (1 Vdc - 0) = (I - 4 mA)°5 / (20 mA - 4 mA)0 5

solving for output voltage "V",

V = (0.25 mA-O5) *(I -..4 mAf)0 5 Equation 7.1-1

where V is the output voltage in Vdc and I is the input current from the transmitters in milliamps. Sincethis is a non-linear function, the uncertainty transfer from input to output depends on the operating point.The transfer of the input error at any point can be determined by the derivative of this transfer function(Ref. 6.9). The result is,

dV = 0.5 * (0.25 mA"°-5 ) *(I - 4 mA)-°'5 * dl

R2

dV = (0.125 me.') * (I - 4 mA)"0' * dl Equation 7.1-2

where dV is the output uncertainty (in units of Vdc) caused by an input uncertainty of dl (in units of mA)at a value of I current (or operating point in units of mA).

When the operating point is know as a function of the output voltage rather than input current, anequation can be developed by solving Equation 7.1-1 for I and substituting into Equation 7.1-2.

solving Equation 7.1-1 for I,

I = (V / 0.25 mA0 5)2 + 4 mA

substituting I into Equation 7.1-2,

dV = (0.125 mA°-) * dI / [(V / 0.25 mA° 5)2 + 4 mA- 4 mA]°-= (01.5 mAni-5)*(0. 125 mA45-') * dl / V

dV = (0.03125 mAn') * dI / V

An operating point must be chosen at which the input uncertainty (dl in terms of mA) is propagatedthrough the square root algorithm. For this calculation, the operating point (V) is considered to be

14B

Calc # PE-025 1 Rev 2PBAPS 2 & 3


approximately 75% rated loop flow (or 0.6 V) per assumption 5.1.19. Therefore,

dV = (0.03125 mA-) * dI / (0.6 V)

where dI is in units of mA and dV is in units of Vdc,

or, converting from units of mA to units of amps,

dV =(0.03125 mAN) *(100l mA /I A) * dl/(0.6V)

dV = (31.25 At) *dI / (0.6 V) Equation 7.1-3

where dI is in units of amps and dV is in units of Vdc

7.1.14 Uncertainty Propagation through Summing Algorithms:

Uncertainties associated with inputs (either LPRM detectors or recirculation drive flow) to the PRNMutilize the algorithm of 1/(N 0 ') to establish the overall uncertainty on a percent rated basis, where N is thenumber of inputs to the PRNM [e.g., LPRMs to either APRM (20 minimum) or RBM (2 minimum), withminimum used for conservatism and to account for sensor failure; or recirculation drive flow loops toRFM (2 loops)]. The basis for this approach is illustrated by the following example utilizing recirculationdrive flow:

Example: let hypothetical individual rated loop flow = 1000 gpm, hence for a two-loop system, ratedtotal flow = 2000 gpm; if rated loop uncertainty = -10% rated loop flow = +100 gpm (10% of 1000 gpm),then rated total flow uncertainty is as follows (per Ref. 6.9):

R2

rated total flow uncertainty = +[(I00 gpm) 2 + (100 gpm) 2]°0 5

= -[2*(100 gpm)]°']= 205"*(l 00 gpm)= -141.42 gpm

or, [(141.42 gpm) / (2000 gpm)]* 100 % rated total flow * -7.07% rated total flow which equals thefollowing (per Ref. 6.9):

*7.07% rated total flow

Therefore,

% rated total flow

7.2 Computations

[begins on next page]

= 4-[(0.5*10 % rated loop flow)2 + (0.5* 10% rated loop flow)2 ]0-= ±[2*(0.5*10 % rated loop flow)2]10S= ±[2*0.25*(10 % rated loop flow)2]0'5

= ±[0.5 ( 10 % rated loop flow) 2]0'.= -(10 % rated loop flow) / (20,5)

= (% rated loop flow) / (2°'5)

14C

IR2Calc # PE-0251 Rev 2PBAPS 2 & 3


CHANNEL INSTRUMENT ERRORS (LA, LD)

FT DEVICE UNCERTAINTY CALCULATION

model range code output code URLFT 1153DB 6 R 100

TERM EXPRESSION

A(FI)

A] = 0.5%*SP= 0.5%*(34.32)

ATEI = (0.75%*URL + 0.5%SP )*(ATA /1 00°F)

min. normal temp = 65OFmax. calibration temp = 90°Fmax. normal/trip (n/t) temp = 1020FATAn = ATAt = 1020F - 90 OF = 120FATEIn = (0.75%*100 + 0.5%*34.32)*(12 0F/ 100TF) =

ATEIt = (0.75%* 100 + 0.5%*34.32 )*(12OF / 100TF)

SPNE1 N/A (systematic span effect is calibrated out) =

zero (random) span (random)SPEI = 0.5%*URL*(P/1000 psig) =0.5%*reading*(P/1000 psig)

Static Line Pressure (P) = 1200 psig

SPE1 = [(0.5%*100)2 + (0.5%*34.32)21]5*(1200 / 1000) =

OPEl = N/Aeval at 1200 psig line pressure

PSE1 - 0.005 %*SP per 1 Vdc(change in 24 Vdc regulated power supply output voltage) negligibleevaluate at 0 dVdc

PSEI = 0.005 %*(34.32)*(0 / 1) =

HTE1 = N/ARE1 = N/ASEISI = N/A

A(FT)norm 2/3*[(A1) 2 + (ATEln)2 + (SPNEI) 2 + (SPE1) 2 + (OPEl)2

+ (PSEI)2 + (HTEI)2 + (REI)2 + (SEIS1) 2]0.5

Ref6.1, 6.2.1, 6.6.1, 6.8.1

SP units34.32 psid

Results s

0.172 psid

0.111 psid0.111 psid

0.000

0.634 psig

0.000

R2

jR2

0.000 3

0.000 20.000 20.000 2

overall normalization

15

IR2Calc # PE-0251 Rev 2


A(FT)norm = 2/3*[(0.172)2 + (0.111)2+ (0)2 + (0.634)2 + (0)2+ (0)2 + (0)2 + (0)2 + (0)2°.5 0.444 psid 2

A(FT)trip = 2/3*[(A1)x + (ATE1t)2 + (SPNE1) 2 + (SPE1) 2 + (OPEl)2+ (PSEl) + (ITE1) 2 + (RE1) 2 + (SEIS1)21]-5

A(FT)trip = 2/3 *[(0.172)2 + (0.111)2 + (0)2 + (0.634)2 + (0)2+ (0) + (0)2 + (0)W + (0)2.05 0.444 psid 2

D(FI))

DI = 0.25%*URL per 6 months

Tech. Spec Calibration Interval (M) = 24 months; evaluatedover 30 months with 25% grace period

D1 = 0.25%*URL*(M /6 month)° 5

= 0.25%*100*(30 / 6)V5 0.559 psid 3

DTE1 = (0.75%*URL + 0.5%SP )*(ATD / 100-F) R2

min. normal tempmax. calibration tempmax. normal/trip (n/t) tempATD

= 65*F= 90*F= 102 0F= 90OF - 65 0F = 250F

DTE1 = (0.75%* 100 + 0.5%*34.32 )*(250F / 100IF) = 0.230 psid 3

overall normalizationD(FT)

D(FT)

= 2/3 *[(D 1) 2 + (DTEI1)2]0-5

= 2/3*[(0.559)2 + (0.230)2]05 0.403 psid 2

PRNMPRNM Channel (Figure 1) [% flux (power) at 2-sigma unless otherwise noted]

a) channel instrument accuracy (LA)APRM ch 1,2,3,4 RBM ch A.B

1) PRNM (LPRMs, APRM/RBM, and TU)gen VA = 0.00 % FS, where

FS =0 to 125gen VA 0.00 % FS, where

Ref6.5.1, 6.5.3

sindiv effect

(fixed) 3APRM% rated PRBM% rated PAPRMRBMAPRMRBM

gen L=gen L=

FS = 0 to0.00 % FS, where0.00 % FS, where

genA = 0.00%ratedPgenA = 0.00%ratedP

125

16

Cale # PE-0251 Rev 2 IR2

trip VA

trip VA

trip Htrip H


0.00 % FS, whereFS = 0 to 125

0.00% FS, whereFS = 0 to 125

0.00 % FS, where0.00 % FS, where

trip A = 0.00 % rated Ptrip A = 0.00 % rated P

APRM% rated PRBM% rated PAPRMRBMAPRMRBM

LPRMgen VA

gen L=

0.80 % FS, overFS =0 to 125

0.80 % FS, overFS = 0 to 125

% rated P

% rated P

% rated Pgen VA = gen L = 2/3"0.80 % *125 = 0.67

gen VA and gen L are combined and propagated through the summing algorithms as follows (Section7.1.14):

R2

gen A = LPRM(APRM)

gen A = LPRM(RBM)

2) RFM (FE, FT, and FU - for APRFT: span 34.32 psi =A(FT) 0.444 psi =sq rt cnv 0.600 Vdc aRFM flow inputs:

[1/(20)°s]*[(gen VA)2 + (gen L)2]0.5

[1/(20)0-5]*[(0.67)2 + (0.67)2]0.50.21 % rated P 20 LPRMs minimum

[1/(2)°S]*[(gen VA)2 + (gen L)2]°'[1/(2)°'s]*[(0.67)2 + (0.67)21050.67 % rated P 2 LPRMs minimum

IR2(fb)

16 mAdc(0.444 / 34.32)*100% = 1.29 % SP (e.g75 % rated loop Q (Sect. 5.1.19)2 (for standard TLO)

3

.,FT-(X-02-110 A-H)

Per Sections 7.1.13 and 7.1.14, A(FT) is propagated through the square root conversion and summingalgorithms as follows:

dV= (1 /sqrt2)*(31.25*dI/0.6)where,

dI = A(FT) = 1.29 % SP= 1.29 %*16 mA*(1 A)/(1000 mA)= 1.29 %*0.016 A

therefore,

dV =(1/sqrt2)*(31.25*1.290%0*0.016/0.6)= 0.0076 Vdc, or converting to units of% rated Q per scaling information in Section 3.5.1,

dV = 0.0076 Vdc *(125%.rated Q)/(1 Vdc) = 0:95 % rated Q

R2

17



As determined below under Item 3 [3) RFM (FE, FT, FU, and TU)] for 2 loop recirc:

gen A = 0.67 % rated Q

by combining dV and gen A as shown below,

overall flow accuracy (RFM) = [(dV)2 + (gen A)2]0,5

= [(0.95)2 + (0.67)2]0.5 = 1.16 % rated Q

hence, flow error = dP = coeff*dWFCTR slope = 0.55 (W coefficient)

therefore, converting overall flow accuracy (RFM) from units of % rated Q to units of% rated P is,

overall flow accuracy (RFM): = 0.55*1.16% rated Q = 0.64 % rated P

RFM3) RFM (FE, FT, FU, and TU) (flow)

R2

3gen VA = 0.80 % FS, over

FS= 0 to 125 %loopQgen L = 0.80 % FS, over

FS= 0 to 125 % loop Q

gen VA = gen L = 2/3*0.80 %*125 0.67 % loop Q

gen VA and gen L are combined and propagated through the summing algorithms as follows (Section7.1.14):

gen A = [1/(2)O']*[(gen VA)2 + (gen L)210 5

= [1/(2)0-5]*[(0.67)2 + (0.67)2V]-= 0.67 % rated Q 2 loop recirc (for standard TLO)

trip VA 0.00 % FS, whereFS = 0 to 125 % rated Q

trip H 0.00 % FS, whereFS= 0 to 125 % rated Q

trip A= 0.00 % rated Q

FT: span 34.32 psi 16 mAdcA(FT) 0.444 psi (0A44 / 34.32)*100% = 1.29 % SP (e.g., FT-(X)-02-11 A-H)sq rt cnv 0.600 Vdc at 75 % rated loop Q (Sect. 5.1.19)RFM flow inputs: 2 (for standard TLO)

Per Sections 7.1.13 and 7.1.14, A(FT) is propagated through the square root conversion and summingalgorithms as determined above under Item 2 [RFM (FE, FT, and FU -- for APRM)].

dV = 0.0076 Vdc, or converting to units of% rated Q per scaling information in Section 3.5.1,

dV = 0.0076 Vdc *(1 25% rated Q) / (1 Vdc) = 0.95 % rated Q

18

R2

R2

Calc #PE-0251 Rey 2PBAPS 2 & 3


R2

1R2

1R2

a) channel instrument accuracy (LA) (as determined from above results, except as noted)(APRM) [ 0.21 % rated P (fixed)(APRM, RFM) (0.64A2+ 0.21^2)^0.5 0.67 %(ratedP (fb)MRM) 0 0.21 % rated P (RBM power)

(RBM) [ 0.67 % rated P (RBM trip)(RFM) [ 1.16 % rated (flow)

b) channel instrument drift (LD)

1) PRNM (LPRMs, APRM/RBM, and TU)

gen VD = 0.5 % FS, whereFS = 0 to 125 % rated Pgen D = 2/3*0.5 % *125 = 0.42 % rated P

Ref6.5.1,6.5.3

APRM

gen VD 0.0 % FS, whereFS = 0 to 125 % rated PgenD = 2/3*0%*125 = 0.00 %ratedP

0.8 % FS, overFS = 0 to 125 % rated Pgen VD = 2/3*0.8 % *125 = 0.67 % rated P

RBM

LPRMgen VD

LPRM gen VD (0.67% rated P) is propagated through the summing algorithms as follows(Section 7.1.14):

gen D = LPRM(APRM) = [1/(20) 05]*(gen VD)= [1/(20)0"5]*(0.67)= 0.15 % rated P

R2

20 LPRMs minimum

gen D = LPRM(RBM) = [1/(2)0-5]*(gen VD)= [1/(2)o5]*(0.67)= 0.47 % rated P 2 LPRMs minimum

(note that the above values for LPRM gen D (0.15 & 0.47 % rated P) are not utilized inthis calculation)

2) RFM (FE, FT, and FU - for APRM)FT: span 34.32 psi =D(FT) 0.403 psi =

sq rt cnv 0.600 Vdc atRFM flow inputs:

16 mAde'0.403 / 34.32)*100%= 1.17 %SP75 % rated loop Q (Sect. 5.1.19)Z (for standard TLO)

19



Per Sections 7.1.13 and 7.1.14, D(FT) is propagated through the square root conversion and summingalgorithms as follows:

dV= (1 / sqrt 2) * (31.2S* dI / 0.6)where

dI = D(FT) = 1.17 % SP= 1.17 %*16 rnA*(1 A)/(1000 mA)= 1.17 %*0.016 A

therefore,

dV = (I / sqrt2) * (31.25 * 1.17 % * 0.016/0.6)= 0.0069 Vdc, or converting to units of % rated Q per scaling information in Section 3.5.1,

dV = 0.0069 Vdc *(125% rated Q) / (1 Vdc) = 0.86 % rated Q

As determined below under Item 3 [3) RFM (FE, FT, FU, and TU)] for 2 loop recirc:

gen D ='1.05 % rated Q

hence, flow error = dP = coeff*dWFCTR slope 0.55 (W coefficient)

therefore, converting dV and genD from units of % rated Q to units of % rated P is,

dV = 0.55*0.86 % rated Q = 0.47 % rated P

genD= 0.55*1.05 % rated Q = 0.58 % rated P

overall flow drift (RFM): = [(dV)2 + (gen D)2]0''= [(0.47)2 + (0.58)2]05 = 0.75 % rated P

I R2

R.2

P-2

RFM3) RFM (FE, FT, FU, and TU)

gen VD 1.79 % FS, whereFS= 0 to 125 % loop Q

gen D 2/3*1.79 %*125 = 1.49 %loop Q

gen D is propagated through the summing algorithms as follows (Section 7.1.14):

gen D [1/(2)0.5]*(gen D)= [I/(2)0.51*(I .49)= 1.05 % rated Q 2 loop recirc (for standard TLO)

FT: spanD(FT)sq rt cnvRFM flow inputs:

34.32 psi0.403 psi0.600 Vdc at

16 mAdc(0.403/34.32)*100%= 1.17 %SP75 % rated loop Q2 (for standard TLO)

20



Per Sections 7.1.13 and 7.1.14, D(FT) is propagated through the square root conversion and summingalgorithms as determined above under Item 2 [RFM (FE, FT, and FU - for APRM)].

dV = 0.0069 Vdc, or converting to units of % rated Q per scaling information in Section 3.5.1,

dV = 0.0069 Vdc *(125% rated Q) / (1 Vdc) = 0.86 % rated Q

b) channel instrument drift (LD) (as determined from above results, except as noted)(APRM) F--- .0.42 % rated P (fixed)(APRM, RFM) [(0.75A2+ 0.42A2)^0.5 = 0.86 % rated P (fb)

(RBM) [ 0.42 % rated P] (RBM power)(RBM) [ 0.00 % rated P[ (RBM trip)(RFM) [(0.86^2+ 1.05A2)AO.5 = 1.36 % rated (flow)

R2

IR2

1R2

SUMMARY OF CHANNEL INSTRUMENT ERRORSa) channel instrument accuracy (LA)

APRMfunctions

REMpowerfunctionsRBM trip functionsRFMfunctions

b) channel instrument drift (LD)

0.2 %rateIj02.67 raed P

0.21% rted P0.67 % ated P

L1.16 %ratedP

0.86 %rated P0.42 %rated P0.00 %rated P1.3 % atedP

(fixed)(fl)(RBM power)(RBM trip)(flow)

I R2

APRMufunctions

REM power functionsRBMtrip functionsRFMfunctions

(fixed)(fb)(RBM power)(RBM trip)(flow)

R2

1R2

CHANNEL CALIBRATION ERRORS (CA) Ref6.1,6.2,6.3,6.5

all calib errors are sindiv effect

3channel 1: APRM Channels

parameter / analog summary:

LPRM inmAdc

0.03.0

APRM outVdc0.0001.000

RBM outVdc0.0001.000

21

R2Calc # PE-0251 Rev 2


INOP-CAL mode, essentially no uncertainty

LPRMs cal uncertaintyAPRM cal uncertainty

0.0 % rated P0.0 % rated P

CE=let CEstd = CE

STOLi:

STOLI =

STOL2 =

STOL3 =

STOL3 =

STOL3 =

STOL3 =

STOL3 =

STOL4 =

00 % rated P0.010J % rated P

%ratedP0.0000.0000.0000.0000.0000.0000.0002.000

FS = 0 to 125 % rated P

(LGAF)INOP-CALAPRM downscale neutAPRM setdown neut/stpAPRM fixed hi-hi neutAPRM fb stp clmpAPRM fb stp scram/rb(AGAF)

6.5.3

6.3.2

STOL = sqrt (STOLi^2) =

STOL = sqrt (2^2) = 2

% rated P2.002.00[2.002.oo0L~ 2.00

APRM downscale neutAPRM setdown neut/stpAPRM fixed hi-hi neutAPRM fb stp cImpAPRM fb stp scram/rb

CA = (2/3)*sqrt (STOL^2+CE^2+CEstdi-2) =

CA = (2/3)*sqrt (2A2+0A2+0A2) = 1.33

incl CA from Q ch I a (P) below>>>>>CA = (2/3)*sqrt (STOLA2+CEA2+CEstdA2+PA2)CA = (2/3)*sqrt (2A2+0A2+0A2+0.596A2) = 1.39

1.33 % rated P1.33 % rated P1.33 % rated P

1.33 % rated P139 % rated P

APRM downscale neutAPRM setdown neut/stpAPRM fixed hi-hi neutAPRM ib stp clmpAPRM fb stp scram/rb

R2

R2

R2

22



channel 2: RBM Channels

APRM inputAPRM fb stp cimp to 3s

% rated P

1 0.001(RBM power)(RBM trip)

STOLi:

STOLI =STOL2 =STOL3 =STOL3 =STOL3 =

STOL3 =STOL3 =STOL3 =STOL3 =STOL4 =

N/A

N/A

FS% rated P

0.00.00.00.0

0.00.00.00.0

0 to 125 % rated P

INOP-CALRBM lowRBM interRBM high

RBM lowRBM interRBM highRBM downscl

STOL = sqrt (STOLi^2) =

CA = (2/3)*sqrt (STOLA2 + APRMA2) =

CA = (2/3)*sqrt (0A2 + 2A2) = 1.33

% rated P0 RBM low0.0 RBM inter0.0J REM high

0.0 RBM low0,0j REM inter

0.0 RBM high0.0. RBM downscl

1.33 % rated P RBM low1.33 % rated P RBM inter1.33 % rated P RBM high

0.00 % rated P RBM low0.00 % rated P REM inter0.00 % rated P RBM high0.00 % rated P RBM downscl

(RBM power)(RBM power)(RBM power)

(RBM trip)(RBM trip)(RBM trip)(RBM trip)





I R2

CA = (2/3)*sqrt (STOL^2) -

23



channel la: APRM Channels RFM Flow Reference Channel

parameter / analog summary:

FE out FT in FT out RFM in RFM outatm psid mAdc mAdc Vdc mAdc

0 0.00 4.0 0.4 0.000 0.00070000 33.89 20.0 2.0 1.000 1.000

calVdc0.010.0

ohms0.01620.0

recirc FEs -> flTs .> PRNM/ /

number: / /2 / /

boundary / /temp (F): / /

90 CE1A,B CE2A,BCE1A,Bstd CE2A,Bstd(Heise 710A) (Fluke 8050)

high precision resistor/ // // // // /

CE3 CE4CE3std CE4std

(Fluke 8050) (Fluke 8050)

For DPIlPG:CE1A,B

For DMM:CE2A,B

0.00 % input+ 0.10 % FS of0.10%*100 = 0.100 psid over span of

let DPI/PG=A 1? no(0.100/33.89)*.100% = 0.295 % FS of0.295%*125 =

20.000 mAdc 125 % loop Q0.00 % input + 0.13 % range of0.13%*20 = 0.026 mAdc over span of

let DMM=A I? no(0.026/16.00)*100% = 0.1625 % FS of0.1625%* 125 =

10.000 Vde 125 % loop Q0.00 % input+ 0.13 % range of0.13%*20 = 0.026 Vdc over span of(0.026/10.000)* 100%-= 0.260 % FS of0.260%*125-

1620.0 ohms 125 % loop Q0.00 % input + 0.13 % range of0.13%*2000 = 2.6 ohms over span of(2.6/1620)*100%= 0.1605 % FS of0.1605%*125 =

100 psid33.89 psid

125 % loop Q0.369 % loop Q

20 mAde16.00 mAdc

125 % loop Q0.203 % loop Q

6.2.1 CE spec

' R2

6.2.1 CE sp=e

R2

For DMM:CE3 =

6.2.1 CE spec

2010.0001250.325

VdcmAdc% loop Q% loop Q I R2

For DMM:CE4 =

6.2.1 CE spec

2000 ohms1620 ohms125 % loop Q0201 %loopQ

R2

24



CE = sqrt(O.369^2 + 0.203^2 + 0.325^2 + 0.201A2) = 0.569 % loop Q

From Section 7.1.14, CE is propagated through the summing algorithm as follows: R2

CE = [1/(2)0'5]*0.569 = 0.402 % rated Q

let CEstd = CE = 0.402 % rated Q

STOLi: 6.5.3

analog % FS % loopSTOLI = N/ASTOL2= 0.04 (0.04/16)*100% = 0.250 0.250%*125 = 0.313STOL3 0.010 (0.010/1)*100% = 1.000 1.000%*125 = 1.250STOL4= 2.5 (2.5/1620)*100% =0.154 1.54%*125 = 0.193

STOL = sqrt (STOLi^2)

= sqrt (0.313A2 + 1.250^2 + 0.193A2) = 1.303 % loop Q

From Section 7.1.14, STOL is propagated through the summing algorithm as follows:

STOL = [1/(2)°.]*1.303 - 0.921 % rated Q R2

CA = (2/3) * sqrt (STOLA2 + CE`A2 + CEstdA2) =CA = (2/3) * sqrt (0.92 1A2 + 0.402",2 + 0.402A2) = 0.722 % rated Q

converting to a 3-sigma value,

CA = 3/2*0.722 = 1.083 % rated Q [3 s]

converting from units of % rated Q to % rated P,

CA = 0.55*1.083 = 0.596 % rated P [3 s]

25



PROCESS MEASUREMENTACCURACY (PMA) VALIDATION

channel 1: APRM Channels

The PMA is a combination of the APRM tracking error and the uncertainty due toflow noise and neutron noise.

Ref6.1,6.5.3

Sindiv effect

2

For the loss of feedwater heating event, the APRM system is designed to have a tracking errorof not more than 1.11 % power in response to a 20% flow control maneuverwith a limiting control rod pattern. This shall hold true for all cases including that the LPRMsensors are failed or bypassed to the minimum number required in each APRM. The neutronnoise impact to the setpoint calculation is not included for scram functions due to filtering.Per below, flow noise contribution is 0.69 % power (as determined under "channel la: APRMChannels RFM Flow Reference Channel" below).Hence,

for heat flux PMA = 1 1.111 (1.1IA2 +0.69A2YAO.5 = 1.31

% rated PI (fixed)PSrated P (fb)

For the MSIV closure event, the APRM tracking error is 1.11% power, theneutron noise is 1.25 % power based on actual plant data, and the flow noiseis 1.25 %flow (0.69 % power, as determined under "channel la: APRMChannels RFM Flow Reference Channel" below) based on actual plant data.

IR21R2

R2

JR2

Combining by SRSS yieldsfor neutron flux PMA = (1.11A2+ l.25A2)0.5 = 1.67 %ratedP (fixed)P

(1.11^2+1.25A2+0.6912)^0.5= 1.81% ratedP (fb)


tracking:neutron noise same as above:

neutron noise estimated:LPRM readings

PMA=

0 % rated P at 2 s (RBM power)1.25 % rated P at 2 s (RBM power)

F(0"2 + 1.25^2)"0.5 = 1.25 % rated P J (RBM power)

1.0 % rated P at 2 s (RBM trip)1.0 % rated P at 3 s (RBM trip)(1.0A2 + (2/3*1.0)^2)A0.5 = 1.20 % ratedP (RBM trip)

I R2channel 1 a: APRM Channels RFM Flow Reference Channel

The .flow noise, based on actual plant data, is:PMA = 1 1.25 % ratedQ

converting PMA from units of % rated Q to % rated P is:PMA= 0.55*l.25=0.69%ratedP

PRIMARY ELEMENTACCURACY (PEA) VALIDATION

channel 1: APRM Channels [NA200/NA300 LPRMS]

I R2

Ref6.1, 6.5.3

indiv effect2

26



PEA is a combination of the LPRM sensor sensitivity and sensor non-linearity uncertainties.

bias randomThey are 10.33 +/- 0.20 % and sen-sen dpea

10.49 +/- 1.00 %, respectively sen-non-lin apea

Also, since N1 = minimum number of LPRM to one

APRM channel = 20

Therefore, overall PEA = (0.33 + 0.49) +/- (1/sqrt N 1) * sqrt (0.202 + 12)

bias random

PEA = 0.82 {= 0.33 + 0.49) +/- 0.228 (1/20A0.5)*(0.20A2 + 1.OO2)AO.5) N % rated P (fixed)I 0.503 = (0.228A2 + 0.389A2 + 0.224A2)AO.5 Note I % rated P (fb)

Note 1: RFM flow element random PEA uncertainty (0.389 % rated P) and random apea uncertainty(0.244) values are both determined as shown below.

or, separated into drift and accuracy components:

dpea = 0.33 +/- 0.045 {= (l/20"0.5)*(0.20} % rated Papea = 0.49 +/- 0.224 {= (1/20A0.5)*(1.00) % rated P (fixed)

0.449 {= (0.224A2 + 0.389A2yO.5 Note2 % rated P (fb)Note 2: RFM flow element random PEA uncertainty (0.389 % rated P) is determined as shownbelow.


PEA is a combination of the LPRM sensor sensitivity and sensor non-linearity uncertainties.(RBM power)

They are 0.33 +/- 0.20 % and sen-sen dpea0.00 +/- 1.00 %, respectively sen-non-I apea

bias random

PEA = 10.33 +/- 0.228 (=(1/2MAO.5)*(0.20^2 + 1.00"A2)0.5) % rated P (RBM power)


dpea = 0.33 +1- 0.045 (=(1/20^0.5)*(0.20) % rated P (RBM power)apea = 0.00 +/- 0.224 {=(1/20AO.5)*(l.00) % rated P (RBM power)

(RBM trip)

They are 0.00 +/- 0.00 f % and sen-sen dpea

R2

R2

1R2

jR2

0.49 +/- 1.00 I%, respectively sen-non-I apea

27



Also,. since N2 = minimum number of LPRM to one

RBM channel = 2bias random

PEA= ] 0.49 +/- 0.707 t=(I/20o.5)*(m.ofl % rated P (RBM trip) I R2


dpea = 0.00 +/- 0.000 % rated P (RBM trip)apea = 0.49 +/- 0.707 {=(i/2fo.5)*(i.oo) % rated P (RBM trip)

channel Ia: APRM Channels RFM Flow Reference Channel

PEA is the FE:FE error = 1% loop Q each venturi

IR2

)

converting to units of% rated Q,

FE error = [1/(2)0.51*1 % loop Q = 0.707 % rated Q

converting to units of % rated P,

FE error = 0.55*0.707 % rated Q 0.389 % rated P

2 loop recirc

2 loop recirc

R2

NOMINAL TRIP SETPOINT (IVTSP) AND ALLOWABLE VALUE (A V) Ref6.1, 6.2, 6.3, 6.5, 6.7

channel 1. APRM Channels

a-i) APRM STP Flow-Biased (TLO) - Upscale (flow-biased) (scram)

ANL 0.55 W + 65.5 % rated P

NTSP = A - [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+PEArandomA2+L.ID2))+PEAbiasI= 0.55W + 65.5 - [(1.645/2)*(SQRT(0.67A2+1.39^2+1.31A2+0.503A2+0.86A2))+0.82]= 0.55 W + 62.824

let NTSPI = 0.55 W + 62.8 % rated P

AV = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]= 0.55W + 65.5 - [(I .645/2)*(SQRT(0.67A2+1.39A2+1.3 1A2+0.449^2))+0.49]= 0.55 W+ 63.305

letAV 10.55 W+ 63.3 %ratedP P

6.5.6 I R2

jR2

1R2

28

Calc # PE-0251 Rev 2 PBAPS 2 & 3 R2


The following steps determine whether NTSPI satisfies the GEH LER Avoidance Criteria per Section 7.1.10.

Acceptance Criteria: Required Z(LER) ?: 0.81 (multiple channel) in accordance with Revision 1 of thisanalysis and Reference 6. 1. The Required Z(LER) > 0.81 (multiple channel) corresponds to a probability of90% (one-sided normal distribution) for multiple channels as noted in Revision 1 of this analysis.

Sigma(LER) = (1/2) * (LA2 + CA2 + LD2)'12

= (1/2) * (0.672 + 1.392 + 0.862)1,7

= 0.883

Z(LER) = (AV - NTSP,) / Sigma(LER)= (63.3 - 62.8) / 0.883= 0.566 implies NTSPI does not pass acceptance criteria

NTSP2 is calculated by using above equation, inserting the required minimum Z(LER) and solving for NTSP 2.

Required Z(LER) = (AV -NTSP 2) / Sigma(LER). Therefore, solve for NTSP20.81 = (63.3 - NTSP2) / 0.883; implies NTSP2 = 62.58

After conservative rounding:

let NTSP2 0.55 W + 62.5 % rated P

With consideration of the AGAF limits (±2% Power) given in Section 5.1.12, the 2 % Power value is added toNTSP 2. This will determine if the AV is exceeded.

NTSP 2 + AGAF limit = 62.5% + 2% = 64.5%; This value exceeds the AV of 63.3%. Therefore, NTSPAoj isdetermined below by subtracting the AGAF limit from the AV. R2

NTSPAoj = AV - AGAF limit = 63.3% - 2% = 61.3%

It is determined below whether NTSPArj satisfies the Z(LER) criteria:

Z(LER) = (AV - NTSPAw) / Sigma(LER)= (63.3 - 61.3) / 0.883= 2.265 implies NTSPAw passes acceptance criteria.

Therefore,

let NTSP = 10.55 W + 61.3 %rated P

a-2) APRM STP Flow-Biased (SLO) - Upscale (flow-biased) (scram)

ANL= 0.55 W + 62.2 % rated P 6.5.6

NOTE: SLO operation uses a -GEH proprietary method for calculating certain error terms (LA, CA, and LD).While the same equations are used as the TLO operation, the specific error terms were provided as input fromGEH and are not derived in this calculation. The error terms are being referred to below as (LA', CA', andLD') and are provided in Reference 6.10.

29

Calc # PE-0251 Rev 2


AV = ANL - [(I .645/2)*(SQRT(LA'^2+CA'A2+PMAA2+APEArandomA2))+APEAbias]

Where, per Reference 6.10,

LA' = 3.414% PowerCA' = 2.139% Power

0.55W + 62.2 - [(1.645/2)*(SQRT(3.414A2+2.139.A2+1.31A2+0.449A2))+0.49]- 0.55 W+ 58.21

let AV= 0.55 W + 58.2 % rated P

NTSP = ANL - [(1.645/2)*(SQRT(LA'A2+CA'A2+PMA^2+PEArandomA2+LD'A2))+PEAbias]


LD' = 5.42 % Power

0.55W + 62.2 - [(1.645/2)*(SQRT(3.414A2+2. 39^2+1.31 A2+0.503A2+5.42A2))+0.82]- 0.55 W + 55.707

let NTSP, 0.55 W + 55.7 % rated P


Acceptance Criteria: Required Z(LER)> 0.81 (multiple channel) in accordance with Revision 1 of thisanalysis and Reference 6.1. The Required Z(LER) > 0.81 (multiple channel) corresponds to a probability of90% (one-sided normal distribution) for multiple channels as noted in Revision 1 of this analysis. R2

Sigma(LER) = (1/2) * (LA2 + CA2 + LD)1a

= (1/2) * (3.4142 + 2.1392 + 5 .4 2 2)"2= 3.377

Z(LER) = (AV - NTSP,) / Sigma(LER)= (58.2 - 55.7) / 3.377= 0.740 implieg NTSPI does not pass acceptance criteria


Required Z(LER) = (AV - NTSP2) Sigma(LER). Therefore, solve for NTSP 20.81 = (58.2 - NTSP2) / 3.377; implies NTSP2 = 55.46%


let NTSP 2 0.55 W + 55.4 % rated P

With consideration of the AGAF limits (±2% Power) given in Section 5.1.12, the 2 % Power value is added toNTSP2 . This will determine if the AV is exceeded.

30



NTSP 2 + AGAF limit = 55.4% + 2% = 57.4%; This value does not exceed the AV of 58.2%. Therefore, R2

NTSP 2 passes acceptance criteria.

Therefore,

let NTSP = 10.55 W + 55.4 %rated P It J

b-i) APRM STP Flow-Biased (TLO) - Upscale (flow-biased) (rod block)

DB = 0.55 W + 55.9 % rated P 6.5.6

NTSP = DB - [(1.645t2)*(SQRT(LA^2+CA^2+PMA^2+PEArandomA2+LDA2))+PEAbias]= 0.55W + 55.9 - [(1.645/2)*(SQRT(0.67A2+ 1.39A2+1.3 1A2+0.503^2+0.86A2))+0.82]= 0.55 W + 53.224 R2

let NTSP1 = 0.55 W + 53.2 % rated P

AV = DB - [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+APEArandomA2))+APEAbias]= 0.55W + 55.9 - [(1.645/2)*(SQRT(0.67A2+1.39A2+1.3 lA2+0.449A2))+0.49]- 0.55 W+ 53.705

letAV 10.55 W + 53.7 % rated P


Acceptance Criteria: Required Z(LER) > 0.81 (multiple channel) in accordance with Revision 1 of thisanalysis and Reference 6.1. The Required Z(LER) > 0.81 (multiple channel) corresponds to a probability of90% (one-sided normal distribution) for multiple channels as noted in Revision I of this analysis.

Sigma(LER) = (1/2) * (LA2 + CA'+ LD2) += (1/2) * (0.672 + 1.392 + 0.862)1a

= 0.883

Z(LER) = (AV - NTSPI) I Sigma(LER) R2

= (53.7 - 53.2) / 0.883= 0.566 implies NTSPI does not pass acceptance criteria


Required Z(LER) = (AV - NTSP2) / Sigma(LER). Therefore, solve for NTSP20.81 = (53.7 - NTSP2) / 0.883; implies NTSP2 = 52.98


let NTSP2 = 0.55 W + 52.9 % rated P

With consideration of the AGAF limits (4-2% Power) given in Section 5.1.12, the 2 % Power value is added toNTSP2. This will determine if the AV is exceeded.

31

R,2Calc # PE-0251 Rev 2


NTSP2 + AGAF limit = 52.9% + 2% = 54.9%; This value exceeds the AV of 53.7%. Therefore, NTSPADj is

determined below by subtracting the AGAF limit from the AV.

NTSPADI = AV - AGAF limit = 53.7% - 2% = 51.7%

It is determined below whether NTSPADj satisfies the Z(LER) criteria:

Z(LER) = (AV - NTSPAm) / Sigma(LER)= (53.7 - 51.7) / 0.883= 2.265 implies NTSPADj passes acceptance criteria.

Therefore,R2

let NTSP= 0.55 W + 51.7 % ratedP P

b-2) APRM STP Flow-Biased (SLO) - Upscale (flow-biased) (rod block)

ANL= 0.55 W + 52.6 % rated P 6.5.6

NOTE: SLO operation uses a GEH proprietary method for calculating certain error terms (LA, CA, and LD).While the same equations are used as the TLO operation, the specific error terms were provided as input fromGEH and are not derived in this calculation. The error terms are being referred to below as (LA', CA', andLD') and are provided in Reference 6.10.

AV = ANL - [(1 .645/2)*(SQRT(LA'^2+CA'A2+PMAA2+APEArandom^2))+APEAbias]


LA' = 3.414% PowerCA' = 2.139% Power

0.55W + 52.6- [(1.645/2)*(SQRT(3.414A2+2.139^2+1.31A2+0.449^2))+0.49]- 0.55 W+ 48.61

let AV 10.55 W + 48.6 % rated P

NTSP = ANL - [(1.645/2)*(SQRT(LA'A2+CA'A2+PMA^2+PEArandomA2+LD'A2))+PEAbias]


LD' = 5.42 % Power

= 0.55W + 52.6 - [(1 .645/2)*(SQRT(3.414^2+2.139A2+1.31 A2+0.503^2+5.42A2))+0.82]- 0.55 W + 46.107

let NTSPI = 0.55 W + 46.1% rated P

The following steps determine whether NTSPI satisfies the GEH LER Avoidance Criteria per Section 7.1. 10.

32



Acceptance Criteria: Required Z(LER)_> 0.81 (multiple channel) in accordance with Revision I of thisanalysis and Reference 6.1. The Required Z(LER) > 0.81 (multiple channel) corresponds to a probability of90% (one-sided normal distribution) for multiple channels as noted in Revision I of this analysis.

Sigma(LER) = (112) * (LA2 + CA 2 + LD 2)1 2

= (1/2) * (3.4142 + 2.1392 + 5.422)In= 3.377

Z(LER) = (AV - NTSP1) / Sigma(LER)= (48.6 -46.1) / 3.377= 0.740 implies NTSPI does not pass acceptance criteria

NTSP 2 is calculated by using above equation, inserting the required minimum Z(LER) and solving for NTSP 2.R2

Required Z(LER) = (AV - NTSP 2) / Sigma(LER). Therefore, solve for NTSP20.81 = (48.6 - NTSP2) / 3.377; implies NTSP 2 = 45.86%


let NTSP 2 = 0.55 W + 45.8 % rated P

With consideration of the AGAF limits (:E2% Power) given in Section 5.1.12, the 2 % Power value is added toNTSP2. This will determine if the AV is exceeded.

NTSP 2 + AGAF limit = 45.8% + 2% = 47.8%; This value does not exceed the AV of 48.6%. Therefore,NTSP2 passes acceptance criteria.

Therefore,

let NTSP = 10.55 W + 45.8 % rated P -

c) APRM STP Flow-Biased - Upscale (flow-biased clamp) (scram)

ANL= 120.0 % rated P 6.5.6 jNTSP = ANL - [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+PEAranidomA2±LDA^2))+PEAbiasI

= 120.0- [(1.645/2)*(SQRT(0.2 ^2+1.33A2+1.11A2+0.228A2+0.42A2))+0.82]117.69 R2

let NTSP] = 117.6 % rated P

AV = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]= 120.0 - [(1.645/2)*(SQRT(0.2 ^2+1.33A2+1.11 ^2+0.224A2))+0.49] R2

-- __118.06 Ilet AV" 118.0 % rated P

The following steps determine whether NTSPI satisfies the GEH LER Avoidance Criteria per Section 7.1.10. I R2

33

I1R2Calc # PE-0251 Rev 2PBAPS 2 & 3


Acceptance Criteria: Required Z(LER) > 0.81 (multiple channel) in accordance with Revision I of thisanalysis and Reference 6.1. The Required Z(LER) > 0.81 (multiple channel) corresponds to a probability of90% (one-sided normal distribution) for multiple channels as noted in Revision 1 of this analysis.

Sigma(LER)

Z(LER)

= (1/2) * (LA2 + CA2 + LD2)V2(1/2) * (0.2 12 + 1.332 + 0.422)1/2

= 0.705

= (AV -NTSP, / Sigma(LER)= (118.0 - 117.6)/0.705= 0.567 implies NTSPI does not pass acceptance criteria


Required Z(LER) = (AV - NTSP 2) / Sigma(LER). Therefore, solve for NTSP 20.81 = (118.0 - NTSP2) / 0.70; implies NTSP 2 = 117.43


let NTSP2 = 0.55 W + 117.4 % rated P R2

With consideration of the AGAF limits (±2% Power) given in Section 5.1.12, the 2 % Power value is added toNTSP2. This will determine if the AV is exceeded.

NTSP2 + AGAF limit = 117.4% + 2% = 119.4%; This value exceeds the AV of 118.0%. Therefore, NTSPADJis determined below by subtracting the AGAF limit from the AV.

NTSPADI = AV - AGAF limit = 118.0% -2% = 116.0%


Z(LER) = (AV -NTSPA 1 ) / Sigma(LER)= (118.0- 116.0) / 0.705= 2.837 implies NTSPADj passes acceptance criteria.

Therefore,

let NTSP = 1 116.0 % rated P I

d) APRM STP Flow-Biased - Upscale (flow-biased clamp) (rod block)

DB--= 110.4 % rated P 6.5.6

NTSP DB - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LIDA2))+PEAbiasI= 110.4 - [(1.645i2)*(SQRT(0.21 ^2+1.33A2+1.11 .2+0.228A2+0.42^2))+0.82]

108.09

1R2

SR2

let NTSPI = 108.0 % rated P

34



AV = DB - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]110.4 - [(1.645/2)*(SQRT(0.21A2+1.33A2+1.1 lA2+0.224A2))+0.49]

108.46let AV= 108.4 % rated P


Acceptance Criteria: Required Z(LER) > 0.81 (multiple channel) in accordance with Revision I of thisanalysis and Reference 6.1. The Required Z(LER) > 0.81 (multiple channel) corresponds to a probability of90% (one-sided normal distribution) for multiple channels as noted in Revision 1 of this analysis.

Sigma(LER) = (1/2) * (LA2 + CA 2 + LD2)"'=(1/2) * (0.212+ 1.3 3 2+ 0 .4 2 2)1n

= 0.705

Z(LER) = (AV - NTSPI) / Sigma(LER)= (108.4 - 108.0) /0.705= 0.567 implies NTSPI does not pass acceptance criteria

NTSP2. is calculated by using above equation, inserting the required minimum Z(LER) and solving for NTSP2.

Required Z(LER) = (AV - NTSP 2) / Sigma(LER). Therefore, solve for NTSP20.81 = (108.4 - NTSP 2) / 0.705; implies NTSP2 = 107.83 R2


let NTSP2 = 0.55 W + 107.8 % rated P

With consideration of the AGAF limits (±2% Power) given in Section 5.1.12, the 2 % Power value is added toNTSP2. This will determine if the AV is exceeded.

NTSP2 + AGAF limit = 107.8% + 2% = 109.8%; This value exceeds the AV of 108.4%. Therefore, NTSPADJis determined below by subtracting the AGAF limit from the AV.

NTSPADj = AV - AGAF limit = 108.4% - 2% = 106.4%


Z(LER) = (AV -- NTSPAw) I Sigma(LER)= (108.4- 106.4) / 0.705= 2.837 implies NTSPADj passes acceptance criteria.

Therefore,

let NTSP = 106.4% rated P

35

R2Calc # PE-0251 Rev 2PBAPS 2 & 3


e) APRM Neutron Flux Upscale Trip - setdown (scram)

ANL = 17.3 % rated P

NTSP ANL - [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+PEArandom^2+LDA2))+PEAbias]= 17.3 - ((1.645/2)*(SQRT(0.2 ^A2+1.33A2+1.67A2+0.228A2+0.42A2))+0.82]

14.67

6.5.10 1R2

1R2let NTSP = 1 ~~14.6 %rated P =

AV = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]17.3 - [(1.645/2)*(SQRT(0.21A2+ 1.33A2+1.67A2+0.224A2))+0.49]

15.04 I R2let AV = 1 15.0 % rated P I

f) APRM STP Upscale Alarm - setdown

DB = 14.0 % rated P

(rod block)

6.3.2

NTSP DB - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]= 14.0 - [(1.645/2)*(SQRT(O.21A2+1.33A2+1.11A2+0.228A2+0.42A2))+0.82]

11.69

let NTSP = 1 11.6 % rated P =

1R2AV = DB - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]

= 14.0 - [(1 .645/2)*(SQRT(0.21^2+1.33A2+1.11 A2+0.224A2))+0.49]12.06

let AV= 12.0 % rated P

g) APRM Neutron Flux Downscale Alarm (rod block)

DB = 0.5 % rated P 6.3.2

NTSP = DB + [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]- 0.5 + [(1.645/2)*(SQRT(0.21A2+l .33A2+I .67^2+0.228^2+0.42^2))+0.82]

3.13I R2

let NTSP = 3.2 % rated7P I

36 I R2



AV = DB + [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+APEArandomA2))+APEAbias]= 0.5 + [(1.645/2)*(SQRT(0.21A2+133A2+1.67A2+0.224^2))+0.49] R2

2.76 = 2.77let AV 2.8 % ratedP

h) APRM Neutron Flux Fixed High (scram)

ANL = 122.0 % rated P 6.5.4

NTSP = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]= 122.0 - [(1.645/2)*(SQRT(0.21^2+l.33A2+1.67A2+0.228A2+0.42A2))+0.82] R2

119.37


AV = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]122.0 - [(1.645/2)*(SQRT(0.21A2+ 1.33A2+1.67A2+0.224^2))+0.49] R2

119.74 = 119.73let AV 119.7 % rated P


a) RBM Low Power Setpoint

ANL = 30.0 % rated P 6.3.2

NTSP = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]- (deadband + miin STP resolution)

30.0 - [(1.645/2)*(SQRT(0.21 2+1.33A2+1.25A2+0.228A2+0.42A2))+0.33] R2- (deadband + min STP resolution)

= 28.11 - (deadband + min STP resolution)

let D = 1.0 %rated Plet Res = 0.1 %rated Pfor overall effect of: 1.1 %rated PNTSP = 28.11 - 1.1 = 27.01 R2let NTSP = ~Iz 27.0 % rated P Asm 5

AV = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMA^2+APEArandomA2))+APEAbias]- (deadband + min STP resolution)

= 30.0 - [(1.645/2)*(SQRT(O.21A2+1.33A2+1.25A2+0.224A2))+0] - 1.1= 28.48 - 1.1

AV = 27.38let AV = I 27.3 % ratedP I

Ii I

b) RBM Intermediate Power Setpoint

ANL= 65.0 % rated P 6

.1.16

.R2

1R237



NTSP = ANL - [(1.645/2)*(SQRT(LA^2+CA^2+PMAA2+PEArandomA2+LDA2))+PEAbias]65.0 - [(1.645/2)*(SQRT(0.21A2+1.33A2+1.25A2+0.228A2+0.42^2))+0.33]

63.11

let NTSP = 1 63.1% rated P

IR2jR2

AV = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]65.0 - [(1.645/2)*(SQRT(0.21A2+1.33A2+1.25A2+0.224A2))+0]

63.48let AV 63.4 % rated P

c) RBM High Power Setpoint

ANL = 85.0 % rated P 6.3.2

NTSP ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]= 85.0 - [(1.645/2)*(SQRT(0.2A2+ 1.33A2+1.25A2+0.228A2+0.42^2))+0.33]

83.11 I R2

let NTSP = 1 83.1% rated P I

AV = ANL - [(I .645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]85.0 - [(1.645/2)*(SQRT(0.21A2+1.33^2+1.25A2+0.224A2))+o]

83.48let AV 83.4 % rated P

Note: RBM Trip NTSP & AV values are determined by applying the AL values corresponding to theassociated MCPR values. Computations using a 1.20 MCPR value are shown below as examples.NTSP & AV margins to the AL are equal for all evaluated MCPR values.d) RBM Low Trip Setpoint

]R2

R2

ANL = 117.0 %ratedPNTSP = ANL - [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]

= 117.0 - [(1.645/2)*(SQRT(0.67A2+0A2+1.20^2+0.707^2+0^2))+0.49]= 115.24

6.3.2

I R2

let NTSP = I 115.2 % rated P ]

AV = ANL - [(1 .645/2)*(SQRT(LA^2+CAA2+PMAA2+APEArandomA2))+APEAbias]= 117.0 - [(1.645/2)*(SQRT(0.67A2+0A2+1 .20A2+0.707^2))+0.49] I R

115.24115.2%ratedPlet AV =

d) RBM Low Trip SetpointMCPR AL AV

1.20 117.0 115.2118.0 116.2

1.25 120.0 118.2121.0 119.2

1.30 123.0 121.2124.0 122.2

1.35 125.8 124.01270 125.2

NTSP115.2116.2118.2119.2121.2122.2

124.0125.2

wfilter, 0. I<tau cI <- 0.55 secw/o filter, tau cI<= 0.1 sec

w/filter, 0.] <tau cI <= 0.55 sec

w/o filter, tau el< = 0. 1 sec

w/filter, 0.1<tau c1= 0.55 sec

wlofilter, tau cl< = 0.1 sec

w/filter, 0.1 <tauc I<= 0.55 secwlo filter, iau cJ< = 0. ) sec

38 I R2

I R2Calc # PE-0251 Rev 2PBAPS 2 & 3


e) RBM Intermediate Trip Setpoint

ANL = 111.2 %ratedP 6.3.2

NTSP = ANL - [(1.645/2)*(SQRT(LAA2+CAA2+PMAA2+PEArandomA2+LDA2))+PEAbias]= 111.2 - [(1.645/2)*(SQRT(O.67^2+0^2+1.2OA2+0.707A2+OA2))+0.49]

109.44


IR21R2

AV = AN_ - [(1.645/2)*(SQRT(LAA2+CAA2+PMA^2+APEArandomA2))+APEAbias]111.2 - [(1.645/2)*(SQRT(0.67^2+0A2+1.20A2+0.707A2))+0.49]

109.44let AV= [ 109.4 % ratedP P

e) RBM Intermediate Trip SetpointMCPR AL AV

1.20 111.2 109.4112.0 110.2

1.25 115.2 113.4116.0 114.2

1.30 118.0 116.2119.0 11Z2

1.35 121.0 119.2122.0 120.2

NTSP109.4110.2113.4114.2116.2117.2119.2120.2

w/filter, 0. I<tau cl<= 0.55 sec

wio filter, tau cl<= 0.1 secw/filter, 0.1<tau cl<= 0.55 sec

w/o filter, tau cl<= 0.1 secw/filter, 0.1<tau cl<= 0.55 seew/o filter, tau cl< = 0.1 secw/filter, 0.1<tau cl--- 0.55 see

w/o filter, tau ci<= 0.1 sec

f) RBM High Trip Setpoint

ANL = 107.4 % rated P 6.3.2

NTSP ANL - [(1.645/2)*(SQRT(LA^2+CA2'2+PMA^2+PEArandomA2+LD^2))+PEAbiasI107.4 - [(1.645/2)*(SQRT(0.67A2+0A2+1.20A2+0.707A2+0A2))+0.49]

105.64

let NTSP = 1 ~105.6 %rated P

R2

1R2AV = ANL - [(1.645/2)*(SQRT(LA^2+CAA2+PMAA2+APEArandomA2))+APEAbias]

107.4 - [(1.645/2)*(SQRT(0.67A2+0A2+1.20A2+0.707^2))+0.49]105.64

let AV = 1 ~~105.6 %rated P I

f) RBM High Trip SetpointMCPR AL

1.20 107.4

1.25

1.30

1.35

108.0110.2111.0113.2114.0116.0117.0

AV105.6106.2108.4109.2111.4112.2114.2115.2

NTSP105.6106.2108.4109.2111.4112.2114.2115.2

w/filter, 0.1<tau cl<- 0.55 seew/o filter, tau c I< = 0.1 sec

w/filter, 0. l<tau cl<= 0.55 sec

w/o filter, tau cl<= 0.1 sec

wffilter, 0. I<tau cl<= 0.55 see

w/o filter, tau c1<= 0.1 secw/filter, 0.1'<tau cl< 0.55 see

w/o filter, tau cl<= 0.1 sec

39 I R2



g) RBM Downscale Trip Setpoint

DB= -0.77 % rated P

IS = DB + [(1.645/2)*(SQRT(LAA2+CA^2+PMA^2+PEArandom^2+LDA2))+PEAbias]= -0.77 + [(1.645/2)*(SQRT(O.67A2+0A2+1 .20^2+0.707^2+0A2))+0.49] R2

0.99

let NTSP = I 1.0 % rated P I

TS = DB + [(I.645/2)*(SQRT(LAA2+CAA2+PMAA2+APEArandomA2))+APEAbias]= -0.77 + [(1.645I2)*(SQRT(0.67A2+0/A2+l.20^2+0.707A2))+0.49)

0.99let AV 1.0 % rated P]

6.5.5

jR2

40I R2



7.3 APRM Channel AFT/ALT: RFM Instrument Loop CheckThe AFT/ALT for the RFM Instrument loop check is determined per methodology provided in section

7.1.12.

7.3.1 RFM Loop Reference Accuracy (RFM Awop)

Per Ref. 6.6.1, recirculation flow transmitter reference accuracy is ±0.25% span. Per section 7.2,accuracy specifications associated with the RFM instrument loop includes "genA". Therefore,

FT A = 0.25% spanRFM A = genA = 0.67 % rated Q, where rated Q = 125%

In addition to RFM A, accuracy of the flow rate display is also included when determining total RFMloop reference accuracy. Per section 5.10 of Reference 6.2.3.2.17, the accuracy of each of the twoflow channel displays (recirculation flow loops A and B) is 1.0 % loop Q. Therefore,

RFM ADISPLAY = 1.0 % loop Q

Propagating FT A through the square root and summing algorithms per methodology provided onpage 17 is,

FT ApRop - [(1/2o 5)*(31.25*0.016*0.25%)/(0.6*100%)]*(125 % rated Q)= 0.184 % rated Q R2

Propagating the two flow channel display accuracies through the summing algorithm permethodology provided on page 17 is,

RFM ADISPLAY-PROP = (1/2 0'S)*(RFM ADISPLAY)= (1/20')*( 1.0 % loop Q)= 0.707 % rated Q

Combining terms via the SRSS method,

RFM ALoop = [(FT Apaop) 2 + (RFM A)2 + (R•M ADrSPYPROP 2 0.

=[(0.184% rated Q)2 + (0.67% rated Q) + (0.707 % rated Q)2]0-5

=0.991% rated Q

7.3.2 RFM Loop Vendor Drift Specification (RFM VDLooP)

Per Ref. 6.6.1 and Section 5.1.3, recirculation flow transmitter vendor drift specification is ±0.2%URL. Per page 15, the URL is 100 psi and calibrated span is 34.32 psid. Therefore,

FT VD = 0.2%*(URL)*(100%) / 34.32 psi= 0.2%*(100 psi)*(l00%) / 34.32 psi= 0.583 % span

Per page 18, vendor drift specifications associated with the RFM instrument loop includes "genD".

Therefore,

RFM VD = genD = 1.05 % rated Q, where rated Q = 125%

41



The drift associated with the flow rate displays are considered to be included in the RFM VD

specification.

RFM VDDisPLAy= 0

Propagating FT VD through the square root and summing algorithms per methodology provided onpage 17 is,

FT VDpRoP = [(1/20'5)*(31.25*0.016*0.583%)/(0.6*100%)']*(125 % rated Q)= ±0.429 % rated Q

Combining terms via the SRSS method,

RFM VDLoop = [(FT VDpRop)2 + (RFM Vl)) 2 + (RFM VDDISPLAY)2]°= [(0.429 % rated Q)2 + (1.05 % rated Q)2 + (0)= 1.134 % rated Q

7.3.3 RFM Loop Calibration Equipment Uncertainty (RFM CELooP)

Per References 6.2.3.2.1 through 6.2.3.2.8, the calibration of the RFM instrument loop is checked byapplying variable test pressure inputs at the inputs of the recirculation flow transmitters whilemonitoring total recirculation flow rates the at the flow rate display. As such, CE error will consistsof errors associated with the pressure gauges used to measure the applied test pressures at the R2

transmitter inputs.

Per References 6.2.3.2.1 through 6.2.3.2.8, the accuracy of the test gauges used to measure the appliedpressures is required to be equal to or better than -0..16 psig. Per page 15, the calibrated span is 34.32psid. Therefore,

CE = (0.16 psig/34.32 psig)*100% span= 0.466 % span

Propagating CE through the square root and summing algorithms per methodology provided on page17 is,

RFM CELooP [(1/20's)*(31.25*0.016*0.466 %)/(0.6*100%)]*(125 % rated Q)

= 0.343 % rated Q

7.3.4 RFM Loop Calibration Equipment Readability (RFM CEMG-Loop)

Readability associated with reading the test gauges is considered to be included in the CE term.Reading error associated with reading the flow rate display (total recirculation flow) is equal to theresolution of the display. Per References 6.2.3.2.1 through 6.2.3.2.8, the readings are in a resolutionof 0.1% rated Q. Therefore,

RFM CERDW-LOOP 0.1 % rated Q

42

Calc 4 PE-0251 Rev 2PBAPS 2 & 3


7.3.5 Determination of AFT/ALT for the RFM loop calibration check

Utilizing methodology in section 7.1.12,

RFM ALTLoop - [(RFM ALOOP) 2 + (RFM CELoop)2 + (RFM CERnG.LOOp)2 ] ' 0 I±- [(0.991% mted Q)2 + (0.343% rated Q)2 + (0.1% rated Q)2]

=-1.053 % rated Q+ 1 .1 % rated Q (rounded upward to nearest 0.1%, which is consistent with indicator

readability)

REM AFTLoop = 1[(RFM ALOOP) 2 + (RFM VDLooP) 2 + (RFM CE LooP) 2 + (R.FM CEirDG.LOOP) 2]- 5

=-+[(0.991% rated Q) + (1.134% rated Q)2 + (0.343% rated Q)2 + (0.1% rated Q)2]05

=±1.548 % rated Q= -1 .6 % rated Q (rounded upward to nearest 0.1%, which is consistent with indicator

readability)

R2

43



Attachments

Universal Glossary

Bases Documents (Ref. 6.5.4 and 6.5.5)

Attachments Pertinent to OPRM

Exelon Transmittal of Design Information, Tracking No. PU-2011-020, Rev. 0

8.0

1.

2.

3.

4.IR2

I R244 (Final)



ATrACUTMENT 1 I

UNIVERSAL GLOSSARY

A ampere; Accuracy;, vessel "A0 sideAAV Allowable Allowable Value (this Is not a redundancy)A• Individual Device AccuracyABA Amplitude-Based (core instability detection) Algorithm (a portion of OPRM ODA)a-c alternating-currentACRS Advisory Committee on Reactor SafeguardsA/D Analog-to-DigitalADS Automatic Depressurization SystemAFT As-Found ToleranceAGAF APRM Gain Adjustment FactorAL Analytical UmitAL Loop/Channel AccuracyALT As-Left ToleranceA/M ARTSJMELLLamb ambientAN Loop Accuracy During Normal ConditionsANL Analytical LimitANSI American National Standards InstituteAOO Anticipated Operational OccurrencesAOT Anticipated Operational TransientsAPEA Accuracy (random) portion of PEAAPED Atomic Power Equipment DepartmentAppx AppendixAPRE Accuracy of Pre-AmpAPRM Average Power Range MonitorAPT Acceptable Performance Tolerance (synonymous with LAT)AR Accuracy Ratio (used in calibration to denote ratio between C and Cs)ARE Aging Rate ErrorAR! Alternate Rod InsertionARM Area Radiation MonitorARTS APRMIRBMITechnical SpecificationAsm AssumptionASME American Society of Mechanical EngineersASP Allowable Setpoint; Analog Signal Processor; Automatic Signal ProcessorAT Loop Accuracy During Trip ConditionsATE Accuracy Temperature Effectatm standard atmosphere (14.696 psia)ATR Accuracy of (Flow) Transmitter (including Flow Element)ATSP Actual Trip SetpointATU Accuracy of Trip UnitATWS Anticipated Transient Without Scramaux auxiliary

Caic 4 PE-0251 Rev. I

PBAPS 2 & 3NIMAC PRNM Setpoint Study

ATTACHMENT 1UNIVERSAL GLOSSARY

AV Allowable Value (Tech Spec Limit)B vessel 4B* sidebar bar (unit of pressure (14.504 psia)]BE Battery ErrorBldg BuildingBPWS Banked Position Withdrawal SequenceBOS bottom-of-scaleBS Bias Span EffectBtu British Thermal UnitBV Bounding ValueBWR Boiling Water ReactorBWROG Boiling Water Reactor Owners' Groupbyp bypassc vessel coefficient of linear thermal expansionC Calibration Tool Error, Degrees Celsius; Conformity;, Closure; Discharge CoefficientCA Calibration AccuracyCAL Calibration Tolerancecalib calibrationC, Individual Device Calibrationcb control buildingcc cubic centimeter (synonymous with ml)CC Condensing ChamberCDB Component Data BaseCDCI Common Data and Control InterfaceCE Channel Error; Calibration EquipmentCF (static pressure span shift) correction factorCFR Code of Federal Regulationsch (instrument) channelCHC Constant Head Chamberchk checkCi CurieCIM Computer Interface ModuleCJ cold junctionCL Loop/Channel Calibration Accuracy; center linecm centimetersC/M Calibration and Monitoringcntr counterCOL Channel Operability LimitCOLR Core Operating Limits ReportCOU component of uncertaintycps counts per secondCPU Central Processing Unit

2



ATTACJHMNT 1UNIVERSAL GLOSSARY

Cr CrosstalkCR Current-RatedCRB Control Rod BlockCRD Control Rod Drive (System)CRDA Control Rod Drop AccidentCRPC Control Rod Program ControlsCRSS Control Rod Selection SignalsCRWB Control Rod Withdrawal BlockCS Core Spray (System); Calibrated SpanCSCS Core Standby Cooling SystemsCsm Calibration Standard Error (Tool Calibration Error)CTP Core Thermal Powercu cubicCU Channel Uncertainty (at a designated point in the channel)d drywell; throat diameterD Deadband; pipe diameter.D1 Individual Device DriftDIA Digital-to-AnalogDAS Data Acquisition SystemdB decibel (ratio of two parameters using logarithms to base 10)DB Design BasesDBA Design Bases AccidentDBD Design Bases DocumentDBE Design Bases Eventd-c direct-currentDC Design CalculationDCA d-c (current) alarmDCD Design Change.Document [identified by Volume No. (Roman numeral)]DE Display ExponentDFCS Digital Feedwater Control SystemDFS Divisions of Full ScaleDG Design Guidedh instrument line elevation differentialdiff differentialD, LooplChannel DriftDL Design UmitDMM Digital Multi-Meterdp differential pressureDPEA Drift (bias) portion of PEAdpmin minimum measurable differential pressure (across FE) judgment]DPRE Drift of Pre-AmplifierOPS Design & Performance Spec

3

.%%• *t•t-.%• =• ........ ,%,==*.***,..



ATTACHqENT IUNIVERSAL GLOSSARY

DR Drift; Decay RatioDRF Design Record FileDS Design SpecificationDSDS Design Specification Data SheetDSP Digital Signal ProcessorDTA delta T (accuracy)DTD delta T (drift)DTE Drift Temperature EffectDTR Drift of (Flow) TransmitterDTUI Drift of Trip UnitdV delta volt (change within the specified power supply voltage requirements)DVM Digital Volt-MeterdW delta recirculation drive flowdw drywellEAROM Electrically-Alterable Read-Only MemoryECC Elevation Correlation ChartECCS Emergency Core Cooling SystemsED Elementary DiagramEDC Engineering Design ChangeEDDL Elementary Diagram Device ListEDBS Equipment Data Base SystemEDF Equipment Data FileEER Engineering Evaluation Reportelev elevationELFS Equivalent Linear Full ScaleELLLA Extended Load Line Limit AnalysesELTR Extended Licensing Topical ReportEOC End-Of-(fuel) CycleEOP Emergency Operating ProcedureEp (Calibration) Procedural EffectEPRI Electric Power Research InstituteEPROM Electrically-Programmable Read-Only MemoryEPU Extended Power UprateEQ Equipment QualificationEQAB Engineering Quality Achievement BoardEqn equationEQEDC Equipment Qualification Environmental Design CriteriaERF Emergency Response FacilityERFIS ERF Information SystemERIS Emergency Response Information SystemESF Engineered Safety FeatureEUT Equipment Under Test

4

Calc # PE-0251 Roy. I



eV electron-volteval evaluationE1A Enhanced 1A [reactor stability option (long-term solution)]F Degrees Fahrenheit; Fluke (calibration tool)F, area thermal-expansion factorFB; f-b Flow-Biasedfc comer frequency (of noise filter, PBA)FC Fast ClosureFCD Functional Control Diagram; Flow Control DiagramFCS Feedwater Control SystemFCTR Flow Control Trip ReferenceFD Functional Diagram; Row DeviceFDDI Fiber Direct Data InterfaceFDDR Field Deviation Disposition RequestFE Flow ElementFFWTR Final Feedwater Temperature ReductionFL finalFM Full MeterFMdp Full Meter dpFO Fiber OpticFPS Final Product Spec; Functional Performance Specfreq frequencyFS Full ScaleFSAR Final Safety Analysis Reportft feetFT Flow TransmitterFTC Flow Trip CardFU Flow UnitFW, fw FeedwaterFWHOS Feedwater Heater Out-of ServiceFZR Fuel-Zone Rangeg local acceleration ofgravity; grams; gaingo standard acceleration of gravity (32.1740 ft/sec&, by international agreement)g= Newtonian dimensional constant (32.1740 Ibm-ft/lbrsec2)G GainGA Gain AccuracyGAF Gain Adjustment FactorGAFT Gain Adjustment Factor (Total); Group As-Found ToleranceGBA Growth-Based (core instability detection) Algorithm (a portion of OPRM ODA)GEASC GE Advanced Setpoint CalculationGEITAS GE Instrument Trending Analysis SystemGESET GE Setpoint Evaluation Tool

5

..... . ................................


PBAPS 2 & 3NUMAC PNM fStroint Study

ATTACHMENT IUNIVERSAL GLOSSARY

GETAB GE Thermal Analysis BasisGETARS GE Transient Analysis Recording System.GNWS Group Notch Wfthdrawal Sequencegpm gallons per minuteGRBA Growth Rate-Based (core instability detection) Algorithm (a portion of OPRM ODA)GS Gain Stabilityh heightH Hysteresis; Heise (calibration toot); overall elevation differentialHE Humidity Effect;, Harsh Environment (for EQ)HELB High Energy Line BreakHHM hand-held monitorhp high pressure (e.g., turbine)HPCI High Pressure Coolant Injection (System)HPCS High Pressure Core Spray (System)HPSP High Power SetpointHTE Harsh Temperature EffectHTSP High Trip SetpointHVAC Heating, Ventilating, and Air-ConditioningHVPS High-Voltage Power Supplyhr hours

effective differential pressure (in WC)Hz hertzH20 watert&C Instrumentation and ControlICD Ion Chamber Detector, Interface Control DrawingICF Increased Core FlowICPS Ion Chamber Power SupplyICS Integrated Computer SystemID inside diameterIDCCSIP inside diameter of the condensing chamber steam inlet pipeIDS Instrument Data SheetIEEE Institute of Electrical and Electronic EngineersIEC International Electro-technical CommissionlED Instrument Engineering DiagramIIR Infinite Impulse Response (filter for STP)in (or ") inchesind indicatorin HgA inches of mercury (absolute)INPO Institute of Nuclear Power Operationsin WC inches of water column110 Input/OutputIPM Integrated Plant Model

6

............ __

Calc # PE-025 i Rev. I



IPSP Intermediate Power SetpointIRA Insulation Resistance Accuracy ErrorIRM Intermediate Range MonitorIS Instrument SettingISA Instrument Society of AmericaISO International Standards Organizationisol isolationISP Instrument Surveillance ProcedureITS Improved Tech-SpecITSP Intermediate Trip SetpointIN Current-to-Voltage ConvertorI&TU indicator & trip unitIWD Interconnection Wiring Diagram10 instrument zeroJP Jet Pumpk kilo (E+03;10); isentropic exponentK Flow Coefficientkg kilogramsI literL Level; LinearityLA Loop AccuracyLACT level actualLAFT Loop As-Found ToleranceLAL Lower Analytical LimitLALT Loop As-Left ToleranceLAT Leave-Alone ToleranceLAZ Leave-Alone ZoneIb, pound-forceIbm pound-massLCD lowest common denominatorLCO Limiting Condition for OperationLCR Loop Calibration Report; Logarithmic-Count RateLD Level Device; Loop DriftLDM Leak Detection Monitor (NUMAC)LDS Leak Detection SystemLDT Line Designation TableLE Load EffectLER Licensee Event ReportLFMG Low-Frequency Motor-GeneratorLGAF LPRM Gain Adjustment FactorLI level indication (e.g., water level)LIMAX level indication maximum (e.g., water level, synonymous with TOS)

7

... . ......... ..' ...........


PBAPS 2 & 3NUMAC PRNM Semoitn Study

ATTACEMENT 1UNIVERSAL GLOSSARY

LIMIN level indication minimum (e.g., water level, synonymous with BOS)LISPAN level indication spanLIO level instrument zeroLLLA Load Une Limit AnalysesLLS Low-Low Set (S/RV)LMG .Level Meter GroupLMR Liquid Metal ReactorLMRL Lower Meter Reading LimitLOCA Loss-of-Coolant Accidentlp low pressure (e.g., turbine)LPAP Low Power Alarm PointLPCI Low Pressure Coolant Injection (mode of RHR)LPCS Low Pressure Core Spray (System)LPRM Local Power Range MonitorLPSP Low Power SetpointLRDRM Uquid Radwaste Discharge Radiation MonitorLRES Liquid Radwaste Effluent SystemLRM Logarithmic Radiation MonitorLSB Least-Significant BitLSD Least-Significant DigitLSL Licensing Safety Limit (Tech-Spec channel, bounds AL)LSSS Limiting Safety System SettingLT Level TransmitterLTR Licensing Topical ReportLTS Long-Term StabilityLTSP Low Trip SetpointLU Loop UncertaintyLVE Line Voltage ErrorLVPS Low-Voltage Power Supplym mass flow rate; meters; milli (E-03; 10-3); months (surveillance interval); overall

component (sigma) Of statistical adjustmentM Metrology Lab; mega (E+06;10); months (surveillance interval); marginM ratio (WtVVd) - 1mA milliamps d-cmax maximumMAZE maximum-acceptable zero errormbar millibarMCPR Minimum Critical Power RatioMCR Main Control RoomMELLLA Maximum Extended Load Line Limit AnalysesMEOD Maximum Extended Operating Domainmin minimum; minutes

8

Ca•c # PE-0251 Rev. I

PBAPS 2 & 3


ATTACIHMET 1UNIVERSAL GLOSSARY

ml milliliter (synonymous with cc)mm millimetersMM muli-meterMPL Master Parts ListMrad megarads gamma (E+06 rads;106 rads)MSIV Main Steam Isolation ValveMSL Main SteamlineMSLB Main Steamline BreakMSLRM Main Steamline Radiation MonitorMSR Moisture Separator ReheaterMST Main Steam Tunnel; Maintenance Surveillance TestMSV Mean Square VoltageMTBF Mean Time Between FailureMTE Maintenance & Test EquipmentMTT-R Mean Time to RepairmV millivolts d-cMVD Multi-Vendor DASMVP Mechanical Vacuum PumpsMW, Megawatts-electricalMW, Megawatts-thermaln the number of standard deviations (sigma) used (individual component); sample sizeN population size; System NoiseN/A, n/a not applicable; not availableNBR Nuclear Boiler RatedNBS Nuclear Boiler System; National Bureau of Standards (archaic)NC normally dosedNED Nuclear Engineering Departmentnegi negligibleNEMA National Electrical Manufacturers AssociationNF Neutron FluxNIST National Institute of Standards and Technology (formerly NBS)NL No LimitationNMS Neutron Monitoring SystemNO normally openNOP not-on-pegnorm normalNPS nominal pipe sizeNR Narrow RangeNRC Nuclear Regulatory CommissionNSSI Nuclear Steam Supply InterfaceNSSS Nuclear Steam Supply SystemNS 4S Nuclear Steam Supply Shutoff System

9N


PBAPS 2 & 3NUMAC PRNM Setpoit Study

ATrACHMENT IUNIVERSAL GLOSSARY

NTSP Nominal Trip SetpointNUMAC Nuclear Measurement Analysis and ControlNUREG Nuclear Regulationnv Neutron Velocity (flux)NVRAM non-volatile RAMnvt lime-Integrated Neutron FluxNWL Normal Water LevelO OffsetOCF Overlap Correction FactorODA Operator Display Assembly; Oscillation Detection Algorithm (synonymous with SA)OE Other ErrorOL Operational LimitOLM Operating License ManualOLMCPR Operating Limit MCPRO&MI Operation and Maintenance InstructionsOOS out-of-serviceOPE Overpressure EffectOPIC Overall Procedure for Instrument CalibrationOPL Operating Parameters for LicensingOPL-3 OPL covering Transient Protection Parameters VerificationOPL-4 OPL covering ECCS Parameters VerificationOPL-4A OPL covering Containment Analyses Input Parameters VerificationOPL-5 OPL covering Single Failure EvaluationOPRM (thermal-hydraulic) Oscillation Power Range Monitor (reactor core instability)ORE Observer Readability Error [accounts for parallax; typically half the minor division on

the linear (e.g., indicator/recorder) scale, other than e.g., meniscus, tape measure]OTS On-The-Spot (change)p pressure; pica (E-12;10")P powerP0 Plant ZeroPBA Period-Based (core instability detection) Algorithm (a portion of OPRM ODA)PC Process ComputerPCI PRNM Communication InterfacePCIS Primary Containment Isolation SystemPCT Peak Clad TemperaturePD Process DiagramPDIS Pressure Differential Indicating SwitchPDS Product Data Sheet.POT Pressure Differential TransmitterPE Position Effect; Primary Element (can also mean PE Error)PEA Primary Element AccuracyP/FM Powerl(Core) Flow Map

10

Calc #~ PE-0251 Rev. I

PBAPS 2 & 3NUMAC PRNM Setoint Study

ATTACHMOENT IUNIVERSAL GLOSSARY

PG Pressure GaugePHD Pulse Height DiscriminatorPIC portable indicating controllerP&ID Piping and Instrumentation DiagramPIMS Project Information Management SystemPIS Pressure Indicating SwitchPLA Point Log and AlarmPLC Programmable Logic ControllerPME Process Measurement ErrorPMI Plant Monitoring InstrumentationPMP Preventive Maintenance ProcedurePOP Percent of PointPPC Plant Process ComputerPPD Purchase Part DrawingPRM Process Radiation Monitor, Power Range MonitorPRMS Process Radiation Monitoring SystemPRNM Power Range Neutron MonitorPROM Programmable Read-Only MemoryPS Pressure SwitchPSA Proabilistic Safety AssessmentPSE Power Supply EffectPSH Pressure Switch (High)psia pounds per square inch (absolute)psid pounds per square inch (differential)psig pounds per square inch (gauge)PSL Pressure Switch (Low); Process Safety Limit (non-Tech-Spec channel)pt pointPT Pressure TransmitterPTDR Pneumatic Time-Delay RelayPU Power-Uprateq flow rate (generally volumetric, although sometimes mass)Q Quantizing Error; RL marginQLVPS Quad Low-Voltage Power SupplyR rem; Repeatability;, Rosemount (transmitter)RA Reference AccuracyRAD rads gammaRAM Random-Access Memoryrb reactor buildingRB Rod Block; Reactor BuildingRBM Rod Block MonitorRBVRM Reactor Building Vent Radiation Monitorrc range code

11

Calc N PE-0251 Rev. I

PBAPS 2 & 3NU-MAC PRNM Sgtioint Study


RCE Readability and Calibration Equipment (Effect)RCIC Reactor Core Isolation Cooling (System)RCIP Reactor Capacity Improvement Program (i.e., power uprate)RC&IS Rod Control & Information SystemRCP Rod Control ProgramRCPB Reactor Coolant Pressure BoundaryRCS Reactivity Control Systems; Reactor Coolant SystemRCTP Rated Core Thermal PowerRd Readability Error (half the minor scale division)RD Reset DifferentialRDA Rod Drop AccidentRDD Rod and Detector Displayrdg readingRed Reynolds number based on dReo Reynolds number based on DRE Radiation Effect; Readability Errorrec. recorderREE RFIIEMI Effectref pertaining to reference leg; referenceRef Referencerem roentgen equivalent manREP Reactor Engineering ProcedureRepro ReproducibilityRes Resolutionrev revisionRFIIEMI Radio Frequency/Electro-Magnetic InterferenceRFM Recirculation Flow MonitorRG Regulatory Guide.RHR Residual Heat Removal (System)RI Readability (of the) Indicator (synonymous with ORE)RIC remote indicating controlRIPDs Reactor Internal Pressure DifferentialsRL Required LimitRLA Reload Licensing AnalysesRLP Reference Leg PenetrationRM Relief Mode (S/RV)RMCS Reactor Manual Control SystemRMS Root Mean SquareR/O (Rosemount trip unit calibration) Read-Out Assembly (calibration tool)ROM Read-Only MemoryROU Relay Output UnitRPCS Rod Pattern Control System

12

I .... ...... -

Caic # PE-0251 Rev. 1

PBAPS 2 & 3hR&MAC PRNM Set;oint Study


RPIS Rod Position Information SystemRPS Reactor Protection SystemRPT Recirculation Pump TripRPV Reactor Pressure VesselRPVO Reactor Pressure Vessel Zero (Vessel Invert)RRCS Redundant Reactivity Control SystemRRS Reactor Recirculation SystemRs ResolutionRS Random Span EffectRSCS Rod Sequence Control SystemRSD Reactor Steam DomeRSDP Remote Shutdown PanelRTI Referred-To-InputRTO Referred-To-OutputRWCU Reactor Water Cleanup (System)RWE Rod Withdrawal ErrorRWL Rod Withdrawal Umiter, Rx Water Level (process condition)RWM Rod Worth MinimizerRx ReactorRZ Random Zero Effects seconds; sigma (standard deviation); steamS SensitivitySA Setpoint Accuracy (a term found in some calibration procedures); Stability Algorithm

(either ABA, GRBA, or PBA of OPRM; synonymous with ODA)SAR Safety Analyses Reportsat saturatedSBO Station BlackoutS&C sensor & converterSCIS Secondary Containment Isolation SystemSCS Significant Change Summary (ERIS)SDDF Supplier's Document Data FormSE Seismic EffectSEHR Special Emergency Heat RemovalSEIS Seismic EffectSER Safety Evaluation Report; System Evaluation Reportsec secondsSGTS Standby Gas Treatment SystemSIL Services Information LetterSL Safety LimitSLMCPR Safety Limit MCPRSLO Single-Loop OperationSM Setpoint Margin; Safety Mode (S/RV)

13

CaNc# PE-0251 Rv. 1

PBAPS 2 & 3NUJMAC PRNM Setnoint Study


S/N Serial NumberSP Calibrated Span; Surveillance Procedure; Setpoint Special Publication (of NBS)SPDS Safety Parameters Display System; Setpoint Data SheetSPE Static Pressure EffectSPNE Span EffectSR Shutdown RangeSRI Select Rod InsertSRM Source Range MonitorSRSS Square Root of the Sum of the SquaresSRU Signal Resistor UnitSlRV (main steam) Safety/Relief ValveSSA Safe Shutdown AnalysesSt StabilityST Startup TestSTA Spurious Trip AvoidanceSTOL Setting ToleranceSTP Surveillance Test Procedure; Simulated Thermal Power (avg NF with 6-sec IIR);

standard temperature and pressure (68 F and 1 atm)sub subcooledT Temperaturet timeTAF Top-of-Active-FuelTa Temperature Change applied to AccuracyTd Temperature Change applied to Drifttb turbine buildingTBD to be determinedTC thermocouple; Temperature Coefficientto time constantTCIU Thermocouple Input UnitTCV (Main) Turbine Control Valvetd time delayTDR Time-Delay RelayTDU Total Device Uncertainty

•TE Temperature Effect; Temperature Element; Trip EnvironmentTEC Temperature Equalizing ColumnTEF Temperature Effect FactorTFSP Turbine First-Stage PressureTHP Time History Plot (ERIS)TID Total Integrated Dose (gamma equivalent)TIP Traversing In-core ProbeTLD Test-Loop DiagramTLO Two-Loop Operation

14

. ..... - --.-----

Caic # PE-0251 Rev. I

PBAPS 2 & 3NUMAC PRNM Set-point Study


TLU Total Loop UncertaintyTOPPS Tracking Overpower Protection SystemTOS top-of-scaleTRA Transient Recording and AnalysesTRAPP Transient Protection ParametersTrE Trigger ErrorTRF Trip Reference FunctionTRK Uncertainty due to APRM TrackingTRM Technical Requirements ManualTS Technical Specification (Tech-Spec)TSV (Main) Turbine Stop ValveTT Temperature TransmitterTTA Tabular Trend Analysis (ERIS)turb turbineu micro (E-06; 100)UAL Upper Analytical LimitUMRL Upper Meter Reading UmitUFN Uncertainty due to Flow NoiseUNL Uncertainty due to Sensor NonlinearityUNN Uncertainty due to Neutron NoiseUR Upper Range-Limit; Upset RangeURL Upper Range-LimitUSNRC United States Nuclear Regulatory CommissionUSS Uncertainty due to Sensor Sensitivityv specific volume [e.g., superheated steam, compressed (subcooled) water]Vf specific volume of saturated waterv• specific volume of evaporationv9 specific volume of saturated steamVA Vendor Accuracyvac vacuumVac volts a-cvar pertaining to variable legVD Vendor DriftVdc volts d-cVE Vibration EffectV/I Voltage-to-Current ConvertorVLN Variable Leg Nozzle (tap)VLP Variable Leg PenetrationVM voltmeterVOM volt-ohm meterVWO (Main Turbine) Valves Wide Openw water;, with

15

........... . ...........

Catc # PE-0251 Rev. 1

PBAPS 2 & 3NUIMAC PRNM Seooint Study

ATTACEMENT 1UNIVERSAL GLOSSARY

W,Wd recirculation drive flowWt coolant core floww/o withoutWC water column [instrument reference condition (at 68 F and 1 atm)]WR Wide RangeWRM Wide Range MonitorWRNM Wide Range Neutron MonitorW&T Wallace & Tieman (calibration tool)WTE Warmup lme EffectX (Setpoint - Instrument Zero)/Calibrated Span (term in xmtr radiation effect algorithm)xmtr transmitterXPU Extended Power UprateXRL RL drift margin (synonymous with Q)Y c-fftirated SpaniUpper Range-Limit (term in xmtr temperature effect algorithm)Y, frictionless adiabatic isentropic expansion factor, inlet to throat (ratio of compressible

fluid flow to incompressible fluid flow)Z Measure of Margin in units of Standard DeviationsZPA Zero-Period AccelerationZS Zero Stability

end English, begin Greekratio of diameters (d/D)

A delta; differentialF. period tolerance (of PBA)y isentropic exponent; specific weight [(weight) density]R micro (E-06;:10"); absolute (dynamic) viscosityv kinematic viscosityp (mass) densitya sigma; standard deviation'1 square root extractor (also called square root converter)

summerQ ohms

END

16

DRF C5 1-00214-00 (5.6)

GE Proprietary Information

Power Range Neutron Monitoring (PRNM) SystemBases for Neutron Flux and STP Analytical Limits/Allowable Values/Desipn Bases

L

Peach Bottom Atomic Power Station (PBAPS) Units 2&3

Revision 0

December 15, 1998

Prepared by: -' t -9' qD. W. Reigel

Reviewed by: E[(E.C.Eckert

CG~(O ?•- QYZ-•l 'P~.Lv. O~1

Rage I of 4 Page 0r4basesSTPsetptO.doc

15 December 1998 DRF C51-00214-00 (4)

1. Background and PurposePeach Bottom 2 and 3 are replacing their original Power Range Monitoring (PM) systems withNUMAC Power Range Neutron Monitoring (PRNM) systems. As part of'that modification, theexisting APRM high neutron flux flow biased scram and scram clamp functions will be replacedby a neutron flux- high scram and a simulated thermal.power (STP) flow biased scram withclamp. Similarly, the current APRM high neutron flux flow biased rod block and clamp will bereplaced with a simulated thermal power (STP) flow biased rod block with clamp. Reference (c),reviewed and approved by the NRC, provided justification functionally for this action but providedno guidance on the bases for establishing analytical Emits for the new functions (allowable valuesand setpoits are established by the standard setpount methodology based on the analytical limit).Therefore, it is necessary to establish the analytical limit or design bases for the replacementfunctions.

Reference (a) established Analytical Limits/Design Bases for the current APRM neutron fluxbased flow biased and clamp functions. The intent of this document is to establish a bases for thereplacement functions without nev analysis.

2. Evaluation/approach

2.1 Previous Analysis

Refence (a) identifies the following key points.,

"The scram clamp is the only trip credited in any current PBAPS safety analysis. Nocredit is taken for the flow biased trip.

" The "AL- for the flow biased scram trip is established so that the value is clamped at81% of rated drive flmv (which gives a maximum high neutron flux trip setpoint of121.5% [81-0.66+681).

" -Of the limiting transients which are identified in Reference (a). maximum licensed lossof feedwater heating, a "slow" transient, does not result in neutron flux reaching thescram trip limit.

* The analysis for a slow recirculation flow increase transient is used to establish theflow-dependent core operating limits. During this postulated event, power would alsoexceed rated power, but no credit is taken in the analysis for the high pover'scramfunction (flow ref:renced value or clamped value).

" The limiting values for the rod block fimction are "design bases" values establishedbased on historical values and engineering judgment not any specific analysis. Nocredit is taken for the APRM rod block inpany safety analysis.

Reference (a) established the following values:

Function AIJDB AV " NTSPHigh Neutron Flux 0.66W+08.0% (DB) 0.66W+63.9% 0.66W+62.7%Scram. Flow BiasedHigh Neutron Flux 12210% (AL) 118.0% 117.0%Scram. ClampRod Block. Flow Biased 0.66W+59% (13B) 0,66W+56% 0.66W+54%Rod Block. Clamp 112.5% (DB) 110.0% 108.0%

Page 2 of 4

. .......................

15 December 1998 DRF CSI-00214-00 (4)

2.2 Comparison of functionsFor the replacement PRNM the replacement functions can be considered as follows:

0 The Neutron Flux - High lfmction, based on neutron flux. is an added function. It is not a funnion ofrecircato flow, and for protection purposes it replaces the e.dsting scram clamp for fast transientsor events.

* The STP flow biased scram and rod block fiuctions replace the existing flow biased functionsincluding the clamps, but operate froin a filtered neutron flux. They respond more slowly than thecurrent fctions, filtering out the higher frequency "noise characteristics from the direct APRMsignal, thereby allowing the setpoints to be set cloe to reactor operating power with less operationalimerfere (especially the rod block).

2.3 Bases for new valuesThe Neutron Flux - High setpoint function in the PRNM will perform identically to the high neutron fluxscram setpoint clamp in the current system. Therefore. the AL for scram clamp in the cuumet system willbe retained as the AL for the Neutron Flux- High function in the replacement system. This will meet theassumrptions upon which safety analysis were previously performed. thus requiring no new analysis. Theanalytical limit for this selpoint value is reconfirmned with the utility during transient analysis for eachreload co•.

Since Neutron Flux - High function is the only function which is credited in plant safety analysis, theremainder of the values are established based on historical results, trip avoidance margin, and engineeringjudgmet

One factor to be considered is that since die APRM neutron flux has essentially continuous "neutronnoise", for mrnsients that result in slowly changing neutron flux an actual rod block (or trip) would occurwhen the avrage neutron flux reached a level below the actual trip setting (because noise "peaks" wouldcae a tip when the average value nears the trip setting). Rod block initiation below the actual averagepower setpoint due to 'noise" can be a nuisance to the operators during plant poner ascensions.

Historically, for plants with STP based flow biased trips, typical values for the ST7 scram clamp AL/DBvalues have been somewhat lower (about 2-5%) than the AL value fbr the neutron flux high trips.Therefoe, for Peach Bottom 2 & 3. even though there is no specific safety analysis that requires such. theDB value for the STP flow biased trip clamp will be set at 2% less than the AL for the Neutron Flux-High trip. This recognizes that the SrP setpoint can be closer to reactor operation without introducinggreatcr risk of inadvertent trip. With the maximum neutron flux setpoint (AL) currently at 122% of ratedpower, this places the maximum clamped seApoint (DB) for the STP scram setpoint at 120% ofratedpower. This MT? setpoint is consistent with the original P3 2&3 transient design analysis in Reference(d) which studied the possibility of implementing the STP function into the design (plots for Sections 5.14and 5.15 show the upper limit of the STP setpoint at 120% of uprated power).

The flow-referenced portion of the setpoints for the STP scram and rod block are also not essential for anysafety analysis. Their historical purpose is to provide backup assurance that the plant is not operatedgrossly above the planned operating range (defined in the power/flow operating map. Figure 2-1 of thePower Rerate Licensing report, as amended. Reference (e)). The scipoints should be high enough thatthey do not prevent plant operation within the entire analyzed operating range.

Full power operation is planned oyver a range of core flow down to 81% (Table 2-1 and Figure2-1 ofReference (e)). in order to maintain margin between the sctpoints and the planned operating range, the"comer" of the flow-referenced setpoints needs to be maintained near this operating snap -comner". Coreflow and drive loop flow are nearly proportional in the high flow range (-80% drive flow should provide-81% core flmv). Therefore t[ie flow-referenced sctpoint DB has been scle.ccd to reach the DB clamped

Pag"3 of4

15 December 1998 DRF CS 1-00214-00 (4)

value at about 80% drive loop flow. The slope of the setpoint variation has been assumed to remain thesame since it approximates the slope of the flow control lines on the power/flow map.

The equation for the DB flow-referenced portion of the scram setpoint that reaches the 120% DB upperlimit for the scram setpoint at 80% drive flow is 0.66*W+67.2 % RTP.

Them is no safty-credht taken for the clamped or flow biased rod block ftctnon. The primary criteria forthese values is to provide rod blocks early enough in any rod maneuvering to avoid the risk of a scramtrip. Therere, the selection of these values is based on enkineeringjudganent and historical experience.The Nominal value for the APRM rod block clamped setpoint function for other plants with SM rodblocks has hisorically been set at 10%. equal to the current design APRM neutron flux trip setpoint forPBAPS. This value will be selected fbr the Nominal value for PBAP& The equation selected for theNominal flow-rcef ced portion of the rod block setpoint is 0.66*W+5.2S% so that the Nominal 108%upper lintbfor the rod block setpoint is reached at 80% drive flow. With the improved performancespecifications for the PRNM included In the analysis, these Nominal values will yield equal or greatermargin between the rod block nominal setting and the trip nominal setting for the PRNM systemcompared to currently installed equipment. so the scram avoidance objective of the rod block function ismet.

2.4 Analytical Umits/Design Bases Values for PRNMBased on the rationale in section 2.3. the selected values for the PRNM trips are as follows.

Function ALJDB AV NTSPNeutron Flux -- Ugh 122.0% (AL) (1) (1)ScramSTP- High Clamp 120.0% (DB) (1) (1)STPP-Ulgh (flow 0.66W+67.2% (DB) (I) (I)biased)__________

STP Rod Bock. Clamp (1 (1) 108% (Nom)STP Rod Block, Flow (1) (1) 0.66W+55.2% (Nora)Biased _t__ _ _ _66_ _

(1) To be determined in the PRNM setpoint analysis.

3. References:a) Peach Bottom EM Number PB 97-03269-000b) Peach Bottom 3 Technical Specification (including Amendhnent No. 224)c) NEDC-324 10P-A. Licensing Topical Report, NUMAC PR Retroflt Plus Option IXI Stability Trip

Function, October 1995.d). NEDC-10996, Peach Bottom Units 2 and 3 Transient Analysis Design Report. October 1973.e) NEDC-32183P. Power Rerate SafeiyAnahsis Reportfor Peach Bonom 2&3. May 1993 (as

amended).

Page 4 of 4

DRF C51-00214-00 (5.7)

GE Proprietary Information

Power Range Neutron Monitoring (PBNM) SystemBases for REM Downscale Trig Tech Spee deletion and reduced setpoint

Peach Bottom Atomic Power Station (PBAPS) Units 2&3

Revision 0

January 8, 1999

Prepared by: 'D. W. Reigel

Reviewed by-E. M Chu

0r

Page I of 5 bases-downmscaledselpt_revOa.doc

8 January 1999 DRF C51-00214-00 (5.7)

1. Introduction and PurposePeach Bottom 2 and 3 are replacing their original Power Range Monitoring (PRM) systems with NUMACPower Range Neutron Monitoring (PRNM) systems. Included in the modification is the ARTS based RodBlock Monitor (ARTS RBM).

The present design for the ARTS RBM and the PBAPS Tdch Specs include a downscale trip. The seipointfor the ARTS RBM downscale trip was originally established at nominally 94%. This value results in fairlyfiequent "nuisance" rod block alarms when rods are driven in for rod swapping or other maneuvers. Theserod block alarms cause distinctions for the operators without any apparent operational benefit.

In 1994, GE provided to PECO justificaton for reducing the setpoint to nominally 1% (Refirnce (d))provided administrative actions were implemented to assure that the RBM had "nulled" shortly before anyrod motion (a rod dc-select/re-select within the 10 minutes prior to withdrawing a rod). Subsequentdiscussion apparently lead to the conclusion that a 5% nominal setpoint provided some additional benefitsand was easier to administer, leading to a formal PECO change of the RBM downscale trip setpoint(eeece e)). /

Recent reviews associated with the PRNM retrofit project at PBAPS have revealed that the earlierjustifications didn't address the potential Technical Specification issues (the associated -allowable value" forthe downscale trip setpoint is in the PBAPS COLR. so a Tech Spec change was not required to implementthe revised setpoint). In addition, recent reviews have identified some ambiguity between the dis.cusion inRefren (d) and the discussions in Reference (c).

The purpose of this document is to provide justification, for the NUMAC PRNM system, for deletion of the

RBM downscale .from Technical Specifications and clarify the bases for the setpoint (at nominally 1%).

2. Evaluation/justification

2.1 HistoryThe original RBM designs for PBAPS and most other GE BWVRs included flow biased trips for the RBM,with functions implemented in analog electronics. For this design. the RBM flux and related setpoint valuescould vary over a wide range of values, potentially down to 30% power or less. That original designincluded a downscale trip setpoint of nominally 5% which was intended. at least in part. to.detect failedhardware which could result in an unusually low value of-the RBM flu-.

When the ARTS design is implemented, some of the basic logic is changcd. Specifically, the RBM localpower level is always normalized to 100 and all upscale setpoints are greater than 100. Therefore, When theARTS RBM program first evolved, an engineering judgment was made that the RBM downscale tripsetpoint could be increased (over that used in the non-ARTS RBM system) without problem. The hardwarein which the ARTS RBM functions wcre first implemented was the same analog clectronics used in theoriginal non-ARTS REM, and still had at least the potential for hardware failures that could result in areduced R3M flux signal that could be detected by the downscale trip. although no specific failures of thatkind have been documented. On the other hand. experience has shown that the incrcased do-wnscale'tripsetpoint in fact leads to nuisance rod block alarms under normal rod maneuvering conditions.

Page 2 of 5

8 January 1999 Slauay 199DRF C51-00214-O00(5.7)

2.2 Review and Evaluation of Previous Analysis

2.2.1 Original ARTS RBM AnalysisRefenc (q) docnuents the original analysis and bases for the ARTS improvement program, including the revisedREM logic. That report established the technical bases for the change, and in particular provided the technical basesfor the upscale trip analytical limits. The report established thi'initial dowscale trip Setpoint (94%) and idemifiesthat the there is no technical bases for the value (the "analyil limit" and "allowable value" aIe shown as "nea).

Review of the report and*thc rationale and factors considered for the upscale trip points confirms that no credit istaken ft the downscale trip setpoinL Futher there is nodiscussion of the rationale for selecting 94%. It appearsthat an engineeringjudgment was made that 94% was a reasonable value since in opeation the actual R1M valuewould always be greater than 100% fhr rod withdrawal action. Discussioa with GE experts indicam that selectionof this value was intended to allow 1br certain calibration errors and likely the small "pre-withdrawal" insertion of arod (to unlatch the collett) prior to withdrawal (so that inadvertent downscale trips would not occur). However, thereis no specific discussion in the Reference of expected behavior of the trips when rods are inserted, and it appears thatextended insertion, such as will occur during rod swapping, and the likelihood of"withdraw blockds due to trippingthe downscale trip during such insertions, was not considered in the selection of the nominal scipoint of 94V0/

Review of rence (c) also shows that the RBM system operation is based on the assumption that a newrod selection has been made within a short period of time before rod withdrawal (10 minutes is used as atypical value). Further, it is clear that the analysis are based on changes from the RBM flux value at thetime of the last selection with no specific provision for a reduction in RBM flux prior to witdlrawing the rod(which might be limited by the original downscale trip setpoin).

22.2 Peach Bottom Setpoint AnalysisReference (a) is the Peach Bottom setpoint calculation. updated after uprating the power for the station. The portionapplicable to the RBM setpoints is essentially a insertion of the GE prepared analysis. That analysis, reflecting themost recent analysis prepared, shows the RBM dowuscale setpont at 94%. with a "design bases" value of 99%.There is no oscusion in that document o the basis for the 88% or 94% values. It appears that a "design bases"value was "backfit" to correspond to the 94% nominal trip setpoint for the purpose of establishing an "allowablevalue" (which, based on Reference (b) is fisted in PBAPS' COLR).

Review of the analysis further co-nirms that the error and drift terms included in the setpoint ralculations for theRBM upscale power trips do not include any error terms related to the RBM dosriscale trip. i.e.. it confirms that nocredit is taken for the downscale trip.

2.2.3 Peach Bottom Analysis to Reduce RBM Downscale Setpoint

Reference (d) was prepared at PBAPS' request to justify reducing the RBM downscale trip. setpoint toeliminate spurious RBM rod block alarms that were occurring during normal rod maneuvering (e.g., rodinsertions during rod swaps at power). That reference states that at least part of the purpose of thedownscale trip is to "prevent the input signal from drifting too far away from the reference signal such that itwill impactthe setpoint margins determined in the RBM upscale trip setpoint'" However, review ofReference (e) and Reference (a) shows that no such credit has been taken for the downscale trip in thecalculation-of the upscale trip setpoints. In fact, the only "drift- considered in the upscale trip setpoints isthat in the actual hardware with values on the order of 0.5%, significantly less than the 6% that would beallowed by the original nominal 94% downecale trip setpoint. Reference (d) concluded that it was acceptableto reduce the setpoint to nominally 1%.

The conclusion that the RBM upscale power setpoints are based on the assumption that the RBM local fluxstarts at the initial "nulled" value (with no provision for "drif" domn toward the downscale trip supoint) isfurther supported by the recommendation in Reference (d) that PBAPS implcment a procedural action to

. Page 3 of 5

8 January 1999 DRF C51-00214-00 (5.7)

require that the operator assure that a nv selection (or deselectionreselection) has occurred within 10minutes prior to rod withdrawal to assure that the RBM has properly "nulled".

2.2-4 PBAPS RBM Downscale Trip Setpoint ReductionReference(a), the PBAPS ECIL that imlc ncted the reduced RBM downscale trip setpoint cites Referince(d), but also incldes discussion lea&ig to the conclusion that 5% is the preferred nominal trip sezpointSpecifically, the ECR states: "Per GE's recommendation, the downscale trip seepoint should be set 2a5percent rather than the 2.5 percent specified under revision 0. This will allow frs of rcpcatabilty ofcalibrations and will bring the trip above the LPRM dropout setting." It appears that earlier discussion hadalready lead to the conclusion that a 2.5% setting was preferred over the 1% value discussed in Reference(d). AlU of these points are reasonable bases for the value selected, but do not relat in any way to the RBMupscale power trip operAtio

2.2.5 SummaryIt is clear from review ofthe previous analysis that there is no actual analytical basis for the ARTS RBMdownscale trip seopoint. Therefbre, the conclusion is that the primary value of the downscale trip is to detectactual equipment failures so thatý for functional purposes, it actually forms an "extension" of the RBM inoptrip function.

2.3 NUMAC RBM Evaluation

2.3.1 NUMAC Digital ARTS RBM vs. Current Analog ARTS RBMThe NUMAC implementation of the ARTS RBM perfmons all of the calculations digitally, so thae is no analoghardware to "drift' of "fail low". In addition, the equipment includes self-test functions that cause most hardwareand many of the "system logic" failures to result directly in an Iop trip. Thercfore. theme are no identified orcredible falb thatwill be detected by the downasale trip with one possible exception. There are a few conditionsthat result in the REM logic setting the RBM flu, to zero. While all of these are intentional and rettu'normally"to the normal value or result in an Inop trip or alarm. it is possible that some unanticipated failure or failurecombination could leave the RBM flux value at the zero setting. While these will most likely be detected by theautomatic self-tes• logic or other "abnormal condition detetion" logic (e.g., no unbypassed LPRMs available wouldresult in both a "ze RBM flux value and a "too few LPRMs" alarm), a downscale alarm could be ofhdp indiagnosing the situation and identifying the source of the alarm.

23.2 Bases for the NUMAC RBM Downscale Trip SetpointBased on the above evaluation. the conclusion is that the dowttscale trip could be eliminated with virtually no impacton the RBM operability. However, since the fbnction is available and has the possibility of detecting supporting thediagnosis of sone falure conditions, it is concluded that the NUMAC RBM Downscale Trip setpoint for the ARTSREM at PBAPS (and for other plants with the same function) should be 1% as the nominal trip setpoint. with norelated analytical limit/design bases value or allowable value. The 1% value is selected only because it is aconvenient value, and with the digital processing in the NUMAC REM will always result in a downscale trip if theREM flux remains "set" to zero due to some failure (for the type of failure hypothesized, the RBM will not beprocessing a normal signal, so noise or error terms in the LPRM values need not be considered is establishing the1% value).

3. Removal of RBM Downscale Trip from Technical SpecificationsBased on the above evaluation, it is concluded that the only potential benefit of the RBM downscale trip function forthe NUIMAC ARTS RBM is to provide diagnostic information in the event offailures. but that those same failuresare also going to result in an RBM inop alarm. Consequently, the RBM downscale trip function in the NUMACARTS RBM providct no significant operability or failure detection benefit beyond that already provided by the RBM

Page 4 or 5

g$1== 1999 DRF C51-00214-00 (5.7)

Inop function, and should, therefom be deleted from the Technical Specifications for PBAPS and other plant whichutilize the NUMAC ARTS RBM

3.1 Justification for Deletion of the RBM Downscale Tdp from Tech SpecsThe REM downscale trip fnmcdton will detect substantial reductions in the RBM local flux after a "nW Is completed(a"nulr' occurs after a new rod selection). This function. in combination with the RBM inop finction, is intended todect problems with or abnormal conditions In the RBM equipment and system. However, no credit is talen for theR•M dmwnscale trip function in the establishment of the RBM upscale trip analytical limits or setpoint'values.

In the original analog RBE the inclusion of a "downscale function in addition to the inop function had some meritin that the analog equipment had some failure modes that could result in a reduction of signal, but not afull failure.Unlilk other nauun mosnitoring sysmem downscate functions (eg, the APRM downscale), there are no normaloperating conditions which am intended to be dected by the downscale function. Therefore, the RBM downscalefunction was in fact part of the overall RBM "mop" function.

The replacement of the original analog RBM with the NUMAC digital RBM results in all of the original analogpwcessing being replaced by digital processing. One effect of this is to eliminate the types of failures that canreasonably be detected by the downscale trip function. In addition, the inop" finction is enhanced in the NUMACRBM by the use of automatic self-est and internal logic to increase the detectability of abnormal conditions and todirectly included these in the RBM Inmp function.

Therefore, in the NUMAC ARTS RBM, there is no incremental value or benefit provided by the REM downscaletrip function. Cossten vdth the overall thrust of the Improved Tech Specs to eliminate "no value" requirements,the RUM downscale trip function. and its related discussion in the Bases, should be removed from the TechnicalSpecifications. The RBM loop function should be retained.

4. References:a) Peach Bottom Calculation OPM-0875b) Peach Bottom 3 Technical Specification (including Amendment No. 224)c) NEDE-30908P. GE Generic ARTS Descriptiond) GE Letter G94-PEPR-IIS, May 23, 1994, GVKumar (GENE) to HJ Ryan (PECO)e) PBAPS MCR No. PB 94-07707-001.

Page 5 of 5

Atta(* Page

175 Cuw,4ye=4w San Jawj CA 951 25

# PE-0251 Rev. 002hrment 31 of 14

N&SA 00412DRF A13-00381-02

January 2, 2001

Sujit Chakzaborty,PRŽIIM Project Manager

Subject: Minimum Number of Operable OPRM Cells for Option lf Stability atPeach Bottom 2 and 3

References:

1. Licensing Basis Hot Bundle Oscillation Magnitude for Peach Bottom 2 and 3, GE-NE-C51-00214-01, Revision I, January 1999.

2. NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and SuppressSolutions Licensing Basis Methodology And Reload Applications," August 1996.

Stability Option M operational requirements include (1) the minimum number ofoperable LPRMs per OPRM cell for a cell to be operable, (2) the minimum number of operableOPRM cells for an OPRM channel to be operable, and (3) the minimum number of operableOPRM channels for the OPRM function to be operable. Peach Bottom 2 and 3 has selected 2 asthe minimum number of operable LPRMs for an OPRM cell to be operable. The Peach Bottom2 and 3 Technical Specification for the OPRM function requires that a minimum of 3 OPRMchannels be operable for the OPRM function to be operable without a LCO. The purpose of thisletter is to document an evaluation of the minimum number of operable OPRM cells for anOPRM channel to be operable.

The licensing basis Peach Bottom 2 and 3 analysis performed with zero LPRM failurerate was shown in Reference 1. This letter documents the LPRM failure sensitivity on the hotbundle oscillation magnitude (HBOM) for the plant-specific configuration for the Peach Bottom2 and 3 4P design. The LPRM failure rate is varied from 44% to 46% to provide a licensing basisfor Peach Bottom 2 and 3 Option Ill stability. These results are shown in Table 1.

ill" -- W4 %a Q

2 Januury 2001Pge 2

Calc # PE-0251 Rev. 002Attachment 3Page 2 of 14

Table 1. Results Summary for Peach Bottom 2 and 3 HBOM(2 LPRMs Minimum)

Setpoint Licensing Basis 44% Failure 45% Failure 46% Failure(Reference 1) Rate Rate Rae

1.05 0.172 0.171 0.172 0.1731.10 0.337 0.333 0.334 0.3411.15 1 0.495 0.490 0.493 0.498

It is noted that 45% LPRM failure rate is the maximum LPRM failure rate allowablewithout having the HBOM greatly exceeding the licensing basis IBOM.

For a LPRM failure rate, GE has also performed a Monte Carlo simulation to determinethe corresponding operable OPRNM cells. This results is shown in Figure 1

Figure 1. Operating OPRMav. Failed LPRMs forPeach Bottom 2 and 3.

0

Qa.C

a

I

35

30

25

0 5 10 15 20 25 30 35 40 45 50

Number of Failed LPR9l

Cale # PE-0251 Rev. 002

2 January 2001 Attachment 3Page 3 Page 3 of 14

This study shows that a setting of 25 operable cells required per OPRM channel areconsistent with Reference I and the licensing methodology in Reference 2. Hence for the PeachBottom 2 and 3 OPRM confguration, a minimurr number of operable OPRM cells per OPRMchannel setting of 25 (out of 33) is adequate to meet the licensing bases for the OPRM function.This minimum value assures, based on the same acceptance criteria and statistical methodologydiscussed in Reference 2 that, for random LPRM failures up to at least 45.0% of the totalLPRMs, the results of Reference I still apply. The analyses performed addressed OPRMpeak/average setpoint values up to 1.15 and total LPRM failures equal to 45.0% of the totalLPRMs in the core. Based on the trends in the data, the OPRM minimum cells per channelsetpoint of 25 may also be valid for setpoints higher than 1.15 and numbers of LPRM failures notexceeding 45.0%. Additional analyses were judged unnecessary since setpoints above 1.15 arenot likely and LPRM failures even approaching 45.0% as a practical matter will never occur.

A minimum number of operable OPRM cells per OPRM channel setting of 25 may alsobe used in combination with a minimum number of LPRMs per OPRM cell setting of 1.However, in that case It is likely that more than one of the APRM channels, which at PeachBottom 2 and 3 share hardware with the OPRM channels, will reach its limit on minimumnumber of operable LPRMs per APRM channel before more than one OPRM channel reaches itslimit on minimum number of operable OPRM cells per OPRM channel.

Please let me know if there are any further questions regarding this analysis.

Sincerely,

Alan Chung(408) 925-2876.

cc: Jason PostClark CanhamNader SadeghiMargaret Harding

Kevin P. Oonawon. QChormw

BWAOWNERS' GROUP F ()0

do enm rgd * P"my Nuclea r P Plan - MoM Code F1210 * 10 Cemer Rad a Perlu, OH 44081NRC ProJect No. 691

bWROG 98113 K Calc # PE-0251 Rev. 002September"17, 1996 Attachment 3

Page 4 of 14

Docmue Contmo OskUnited Statn Nuclear Regulatory CommissionWhShmgton, DC 20555Atentirtn Mr. LE Phaps

Reactor Systems Branch

SUBJECT: Guidejwins for SiabiUgy Optlon i "-Enabled Regiorn- (TAC M92882)

Refemnce 1) Letter, RC Jones to RA Pinsilu, Acceptance for Referencing ofTbpicai Report NEDO-32465, "BWR Owners' Group ReactorStability Detect and Suppress Solutions Ucensing BasisMethodology and Reload Appfctmonsim , Marc 4,1996

Atahed. for you Information, is guidance the BWROG is providing to the stabilityOpetin Ill par•iciputing utlitles regarding the powermfw conditions for which the OptionItl protection feature wll be enabled (Le., operational bypass removed). This guidanceis Consistent with the methodology described in NEDO-32465 'BWR Owner' GroupReactor Stabibty Dot and Suppress Licensing Basis Metodology and ReloadAppI~cadonsW.

The Opton I1 rMethOWc9gy requires that te tip functon be enabled in W1e region of theoDWersflow map in which instabiliies ar expected. This region has been canseratlvelydeined i NEDO-32465 Section 2.2 as pow level greter than 30%. and core flow lessthan GO%. 1ypassing t trip funcmtion outside this region minkrionz the potental forspurous tIP due to random signal whifch mig• occr during prlong= periods ofnormal Pow per o ation at high coe fowe or as a result of low power manevering.Because the enabled region conservatively bounds the region whom instUbilitles amactually Wee trhe selected power and tow values are not plet or cycle speci€ andthe UsA of the nominal values (1.s., without futher allowance for instrument ddft orUncertaibt) Is approptat. The BWROG guidance for esablishing thos setpointS isdiscussed in the attacpmert.

Calc # PE-0251 Rev. 002Attachment 3

BWROG GUIDANCE Page 5 of 14REACTOR CORE STABILITYOPTION IIl ENABLE REGION

The purpose of this guidance is to clarify application of the operating bypass for theBWR Owners Group Reactor Stability Detect and Suppress Solution Option Il,described in NEDO-31960-A and NEDO-31980 -A Supplement 1. As stated in thoseIcenrasng Topical Reports and In the Licensing Basis Methodology and Reload

Applications Topical Report NEDO-32465-A (Section 2.2), the trip function Is to beenabled when both core power Is greater than 30% of rated and core flow is less than60% of rated. These "enable regmon setpoints do not initiate any pmrcdv actions bythemselves, Instead, they define the region of thm poweriflow map in which the tripfunction Is enabled (Le., operational-bypass Is removed). These aatpntx have beenconservatively selected so that speclfic, additlonal uncertainty allowances need not beapplied. Thus, setpoints corresponding to the value listed above (30% of rated corepower and 50% of rated core flow) will be used to establish the enabled region of theOption Ill trip function. Further discussion of the validity of this approach is providedbelow.

iTrl r-Eabl -atminimu

The BVVROG Stability Option Ill Solution has two principal objectives. First. the tripfunction Is designed to automatically detect and suppress antickpated reactorinstabilities to provide a high level of assurance that the MCPR Safety Limit will not beexceeded. This suppression funclion is active In the region of the power/flow mapwhere appreciable reactor instabilities am possible. Second, the trip funcion shouldavoid unnecessary reactor scrams for non-stability related eventL Both of theseobjectives support safe operation of a BWR.

The current recommended Inderm Corrective Action (ICA) regions provide highconfidence that reactor instabliy events outside of the regions wm unfliely. The ICAsand other operational guidance developed by the BWROG are based on actual plantevents as wall as analytical studlies.

To meet both Option IIl objectives the region of the powedlow map where automaticsuppression Is required was defined to be significantly larger than the ICA regions.Large stability-related oscillations outside this region are considered highly unlikely.The additional margin beyond the ICA regions was included to provide assurance thatthe trip function Is available when needed and to allow utli to use the nominalboundaries as stated without additional conservatism. UtIlIties are not expected toIncrease the size of the region to account for Instrument drift or uncertainty because ofthe consernatism with which the setpolts were selected. A larger region may Increasethe probability of Inadvertent scra•m The region defined by the setpoints bounds theconditions at which actual plant instabilities have occurred.

SWROG 96113September 17, 1996Page 2

Caic # PE-0251 Rev. 002Attachment 3age 6 of 14

This mtewsl is being provided for NRC nforation. Because the guidance isconsient with the basis for the methodology described in NEDO-32466 (which Wasapproved by Refenwce 1), qsiffo NRC approval of this material Is not believed to benlessary.

If you have any questions or comments, please contact either Chat Lehmann (PP&L) on(610) 774-7984, or Hank Piefforien (GE) on (408) 925-3392.

Sincerely,

KP Donovan, Chairman

BWR Owners' Group

impgd/lhcp

oc TJ Rausch, BWROG Vice ChairmanBWROG Stablty Detect and Suppress Methodology CommitteeBWROG Primary Representatives (PartIcipating Utilte)SJ StarK GENEHC Pflef-eren, GENE

Calc # PE-0251 Rev. 002Attachment 3Page 7 of 14

Table 3-2: PBDA Trip Setpoints

Confirmation Count Setpoint: Amplitude Setpoint Sp___N____, (Peak/Average)

6 _>1.04

8 _>1.05

10 -1.07

12 >1.09

14 >1.11

16 i1.14

18 Ž1.18

20 >1.24

Note: This table is from GE Topical Report NEDO-32465-A, "Reactor Stability Detectand Suppress Solutions Licensing Basis Methodology." The entire Topical Report ismaintained in the Peach Bottom Records Management System as G-080-VC-150. Thistable is reproduced in PE-0251 for convenience and clarity. Table E-1 in NEDO-32465-A is also relevant.

OCr 3 P 03124FM GE MCLEAR DENTW4es 925 1490 ý 2f2-2- P'

RENuclear Energy


age 8 of 14October 4,2003WN 03-107

Document Contol DeskUnited States NuMdear Rogulary CommlssionOne White Pint North11555 tock kvll,, Piksllnckville Maryland 20852,-2738.

Subject: Part 21 Notfleation- Stabity Option 111 Period Band DetectonAlgorithm Allowable Settings

This letter providas information concming a reportable condition on the stability OptionMf Period Based Detction Algorithm ("'BIDA). The technical bases forth. fPBDA wasdefined by OGE Mclear Ene- (OGNE) and supplied to Hicens=e as safty relateddoametaton in licensing topical leports. Spedficaly, NDO-32465.A, ReactorStability Detect and Suppress Solutions Licesing Babs Me•todology for ReloadApplicatiozs, August 1996, defifte the P•DA pae confirmation adjustable variblesfor the Osillation Power Range Monitor (OPXM) to be the period tolerane and theconditioning filter cutoff freqeny. The period tolerance could be adjusted in the rangeof 100 to 300 msec, and the conditioning filter cutoff fiqun•y could be adustd in therange of 1.0 to 2.5 Hz. Subsequent plant-specifio submittals may have extended theperiod tolermace range on the low end to 50 mace and the cutoff frequency on the highend to 3.0 H.

On July24, 003, a slow growing core wide instability event occurd at NMP-2. TheOPM" instaled at 0MP-2 with 4 OPeRM chaels, eahwith 30 O Mcells Aplant-specific Cdtical Power Ratio (CPR) per ma cr"ve has been detelmined forNMP-2 and the OPRM was armed when the evet occume For the current cycle, thePBDA confirmtion count (CC) setpoint is 14 count, and the normulluzd an"litude tripsetpoint is 1.12. A cram, ocfre when at least one cell in two or more OPRM channelssimuftaneously exceeds both the CC and amplitude tdp seipoints.

In the NMP-2 eve, the OPRM detected the instability and hditid a reactor scram thatprovided Safety Limit Minimum Critical Power Ratio (SLMCPR) protection. However,post-.vent analyses kidicate, that the, OPRM did not perfotm as epected. Out of 120cells, only one Performed correctly in that it reached &h CC tip Getpoint first, then theamplitude ttip setpoint. At the time of the scrm, there were >20 cells with amplitude at

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or I to 2% above the ampiltud setpoint, and only 5 cell wft CC at or above the CCsetpoin. W'his was attributed to a large number of unexcted CC reset thsmghout theeveat.

At NWMP-2, the adjustable Period con~foinaion variables were set at 50 rsnec for theperiod tolerance and 3.0 Rz for the cutoff frequeny. The evabiation by GENEconcluded that the 3.0 Hz value does not adequately filter out high ftuquepy noise andproducts a signal w•ith lse peak and valley tdt causes frequent CC resets. Inaddition, the 50 osea value poduces fiequcet CC mree due to sal) variations In theoscillation period. A=4-sis by ONE has demined that expected CC paftmanca Isachieved with a cuto~ffrequeacy of 1.0 Hz and a period tolerance of 100 msec or largerWith these seutigs, the majority of the OPRM c•ll would have had CC at or above theCC setpot when fte amplitude tip wepoint was reached.

Even with the 50 sease and 3.0 Oz settig, the OPR, provided SLMCF1P prot-tion forthe Nb-2 evezIL Due to the robust OPRM desi•g it is possible that dia sctingscurrently in =a and allowed by licenoing documentation couldprovide SM•CPR.protection 6x other instability ents. Additital justification mays how t1st othervalues fbr the PBDA adjustable period condmation vmarble provide acceptableperforamance. However, GmeN cannot curtconfirm that perorance of the OPRM'with setting other tan period tolemma , of 100 msec or highe and atoff freuency of1.0 Ef will not contribuft to exceeadig the SLMCPR for all anticipated fistability events.

The reconmended changes to the PSDA period confirmaon adjustable variables docsnot produce a significant increae In the probability oft apu-ious scrom since both countsabove the CC satpoint and amplitude above the amplitude trip setpoimt are required for anOPEtM cal to tdp, and calls in multple OPRM cha•ms must trip befoe L scram isinitiated (in accordance with the reactor protection system logic). It I higl unliklythat the CC rnd amplitud, rip sepolnts would be reached simultaneously in multipleOPRM coUs in multiple OPRM channels cxccpt during an actual instability evnt

The rcoonmmded chagSes to the ThDA period confirmation adjustable variablee areexpected to hn=rease the occurence of OPPtM alarms bused on higb CC. noe OPRMalarm is not a licensing basis uirnodon ofthe OPM. An alam based on hig CC In asingle OPRId cell may resut in ambiguous Indication since It could be attributed either toan acual redction in stabifly margin or could hmve been generated as a eult of'tberd=om natuar of the OPRIM signal. Due to the large number of opportunities associatedwith cor, tunous monitoring of -120 OPRM CelL signal%, operating expcicuce is thatoccasional alam1 s am not assoiated with an actual reduction in stability margi.Thcrefo, it may be appropriate to incease the alsn CC setpoiftt, or disable the alarm ifit continues to provide ambiguous indication.

2

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October4, 2003 Page 10 of 14IM1 P 2-107

This cftditim does not pw uc a substmdl afety bhaud and twhe is no tlusat of fuelfailure. However, beause the condition could contribute to exceeding the SLMCPR, it isa reportable condiion.

Ifyou have any question, please call me at (408) 925-5362.

laoom S. Post ManagerEngineein Qualit and Safey Evaluatimn

cc: S. D. -Alxnder (QRC-NRMl. P/PAl) MalR Stop 6 P23, F. Foster (NRC-NRRWRIP/RORP) Mail Stop 12 W4A. B. Wang (NRC-NR/DRLPM/lD4) Mll Stop 7 El3. P. Klapprth (GENE)-L J. Neme (Menq)0. B. Stmback (OEM1. 1 r (GE NMPRCFIoe

AtWnhm=Mt

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Attachment 3

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Octobe 4, 2003 Attachment 3NIFN 02-107 Page 12 of 14

Attachment 2 - Informaidon per §21.21(d)(4)

(i) Hame aud address of the Individual Inforning the Cou•tiusiosnJasom &. Po0t, Mmger, nginering Qualty & SaftT Evaluation, GS Nuolear Energy,175 CurtnerAvenue, San Jose CA 95125

(11) Idexificati of to fetofty, dt. actvity, or the basde component supplied for such folltyor =h activity within the United Staws which fills to comply or contais a dc*c=All tbility solution Option U plats on potentially affected. Thems plants arc sted inAulmreait. The basic componast with the deftet is specliamon of do allowablevahm for the a4utable period confummada variables in the Period Based DetectionAlgorithm (PBDA) used In StaMty Option ilL

IWi) ldentfication of the firm couustrcting the thmlity or supplying the basic component wbichfi t conmply or coundns a•deft09 Nuclear w eg, San Jose, Cania

(iv) Hlatwe of hde defect or lMme to comply and afety hbazrd which Is creted or could becreated by such defeat or bilne to comply:

This condition does not produc. a substantal safety hazam. The daeet is that certainvalue of pedod tolemranc and conMdtionIg iler a ffquency within the previously

,peFMe acceptable mu could produ suificient successive confirmation cou resensuch dit SLMCP$ protectlan might not be provided for ill anticipated reamtorhIst•eblides. Evai with the deaft, the system provided SLMCPR. protection for tbe mgaatNii-2. Due to th robust C A 3 desk% it is possible ta the settings cuerendy in un.and allowed by liwe•sng documentation could provide SLMC protection for otherinstabty eavts. HMWWWa at this time G•N• cannot conflon that Peibmae of theOPRM with all cofditionwo filte and period tolermce settings cutently in = andallowed by lHeing documentation will not lead to a candition where the SLMCPRcould be violated for some anticipated instabil ty events. The recommtved caumps tothe FBDA period confirmation adjustable varbles do not produce a giftw¢n incmrein th. probability ofa spurious scram.

(v) The data an which the i xmaion ofsuh defect or fMuam to comply wa obtaied:August 5, 2003

(vi) In the ,aso of a basic component which conains a defeat or Edl]=e to comply, the numberand locations ofall suc components In use a, supplied for, or being supplied f one ormom tihoifies or adctvid subjc to th• nrgulations In this part:The potentially affected plants re listed in Attachment 1.

(vii) Tho corrective action whiah has beetr, is being, or wMi1 be btna the name of theindividual or organization rsponsible for the acion; and the length of time that has beenor will be taken to complete the action (note, these are a~tions specifically associated withthe identified Reportable Condition):

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October 4, 2003 Attachment 3W:N 02-107 [Page 13 of 14

a All potentially affected licen s have been notified by a Pat 21 R.eportableCondition Notification pet §21.21(d).

e GE will modify" dteues manul for plaow which use the GE supplied Power PangeNeutron Monitor to set the cutoff feqizuncy to I HIz and the period tolWeme to 100mge or greater with allowance to =a a diffrae value if applicable, besed onadditonaljuslficatmon.

(vih) Any advice rdatd to * defect or failus to wnoply about the f•cility, acdvity, orbaskccomponent that has been, Is beii o wM be Sgven to puchasers or licensees,

1. Tit instaility event stNMaP-W ad&d*a analmiysis has shown that selectionof I W. for dte coadtiuonis Ifte cutoff faequcAy is eff•etive In filtaeng thehigh hcq=uey noin compoets which b essential forrefcding excessive restsof sucmee period aIIrIa F -counI (CC) during oesabe operatons.Analysis by GENE does not suppor use of a conditioning filter cutoff fiquenoyhigher than I Hz. Absent ddialtiflcationofanother value, the cutofffreuqncyahould be set to I Hz.

2. 7he hitib* t.vent at NMP2 and additfonal awaei has shown that apedodtoleranc of les than 100 vose does not provide for an uffective trip fwmtf n byaccommodatiug amll o-cillation, parod vadations, which Is essential forredcing excesvav CC resets during umatible qmopeaios Analsis by GENEdoes not support use ofa period tolerance lower than 100 msec. AbsentaddItional jusification ofanothar value, ft period toletence should be set to 100msec or geater.

3. Additional infozundon Is being providtd to licensee relative to the alar'm ctlonofthe OPHi and di procedure for toning the pedod toler•nce mad corner

* An miami based on hAh CC ika single OPRM coil aosy mault in ambiguouIudicadon since it could be attnuted cither to an actual reduction In stabilitymargin or It could have been generated ag a result of the nrndom nature of theOP1ZM sidnaL Themfore, It may be appropriate to incea the Warm CCsetpohit or dbable the alarm if it continues to provide ambiguous indication;

uT:e PBDA pOZiod cxiuumiodn adjusable variables Should not be cbhan.d(ix, "tuned") in such a way as to limht the number of aarns, withoutadequate consideration of the impact ofthi chanm an ability ofthe PBDA todetect an actual instbilt event Ifonly a single value of each adjustablevariable is allowed basd on an a4=aaeustilcul, In a ptning procedurefor the PBDA perio confirmation adjustable variables himno applicable.

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age 14 of 14NEDO-32465-A

Table A-I: Example Amplitude and Growth Rate Algorithm Setpointe

Setpolnt Typical Value

S, 1.10

S2 0.92

Sffm 1.30

GR 3 1.30

T" (time window) 0.3 to 2.5 seconds

T2 (time window) 0.3 to 2.5 seconds

Note: This table is from GE Topical Report NEDO-32465-A "Reactor Stability Detectand Suppress Solutions Licensing Basis Methodology." The entire Topical Report ismaintained in the Peach Bottom Records Management System as G-080-VC-150. Thistable is reproduced in Calc PE-0251 for convenience and clarity.

EXELON TRANSMITTAL OF DESIGN INFORMATION

NSAFETY-RELATED Originating Organization Tracking No:-INON-SAFETY-RELATED ]ExelonI-REGULATORY RELATED I"]Other (specify) PU-2011-020 (rev. 0)

Station/Unit(s) Peach Bottom (U2/U3) Page I of 2

To: W. Barasa - S&L

Subject Transmittal of Instrument error uncertainty -term t by Sargent & Lundy.

Steve DraQovich __'__"/__ _

Preparer pPrepares rlugnve Datei

Approver /Appp6vers SIa)&4 6ate'

Status of Information: MApproved for Use OUnverified

Description of Information:

This TODI provides error terms for use in calculation PE-0251, "Provide Allowable Values (AV) and Nominal Trip Setpoints(NTSP) for Various Setpoint Functions of the NUMAC PRNM System." In particular, the provided values are required foruse In APRM STP Flow-Biased scram and rod block functions for SLO - Single Loop Operation only.

-LA a Loop Accuracy = 3.414 %PWRCA = CallbratlonAccuracy = 2.139 %PWRLD,= Drift for total loop = 6.42 %PWR

The above values were provided by GEH in accordance with the attached emall and were used In determining the resultsthat were provided In GEH Task Report 506, 'rTS Instrument Setpoints" for Peach Bottom (Units 2 & 3) EPU.

Purpose of Issuance and Umitations on Use: This information. Isbelngsupplled solely for the use in the referencedcalculation above, PE-0251, in support of EPU for Peach Bottom (Units 2.& 3).

Source.Documents:E-mail, dated May 4,2011, from Eic Helin of GEH to Steve Dragovich of Exelon

Distribution:Original: TODI fileCC: T. Wicket, J. Stahl, M. Coakley

Calc # PE-025 1, Rev. 002Attachment 4Page 1 of 2

Dragovich, Steve:(GenCo-Nuc)

From: Helin, Eric J (GE Power & Water) [[email protected]]

Sent- Wednesday, May 04, 2011 4:09 PM

To: Dragovich, Steve:(GenCo-Nuc)

Subject: SLO-TLO accuracy data

Steve:

As discussed earlier today, here are the differences in TLO and SLO accuracies.

TODI PU-2011I-= (rev. 0)Page 2 of 2

TLO SLO

APMA & APEA (%pwr) = 1.380582 1.354033 PEA/PMA

Loop AV Acc(%pwr) 1.433426 3.672462 Allaccuracy

LA, PMA, and errors forAPEArandomr AV

Loop LER Acc(%pwr) = 0.379257 3.264606 Accuraciesfor LER

DPMA & DPEA (% pwr) = 0.044721 0.044721 Drift forPMA/PEANTSP drift(ignore)

Loop NTSP Drift (%pwr)= 0.985554 §.42033 Drift for

LD total Ioop

Loop Instr Drift (% pwr) = 0.984539 5.420146 LER calc

Loop Instr Cal (%pwr) = 1.334268 2.1386 Calibrationaccuracy

Loop Instr Acc (%pwr) = 0.385622 3.413732 LoopLA )Accuracy

7

Eric

Eric J. HelinGE Hitachi Nuclear EnergyProject Manager, Steam Dryer Analytical ServicesT 910-819-1932C 910-398-0304E eric.helin@,e.comwww .,e-eneray.com/nuclear3901Castle Hayne RoadP.O. Box 780,M/C: A75Wilmington, NC 28402 USA

Calc # PE-0251, Rev. 002Attachment 4Page 2 of 2