JAFP-19-0105, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...

Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...

ML19310D579
Person / Time
Site:	FitzPatrick
Issue date:	11/06/2019
From:	David Gudger Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-19-0105
Download: ML19310D579 (68)

Text

200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 10 CFR 50.91(a)(5)

JAFP-19-0105 November 6, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333

SUBJECT:

Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation

References:

1. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S.

Nuclear Regulatory Commission, "License Amendment Request -

Proposed Change to Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation (ML19248B085) dated September 5, 2019

2. Electronic mail from S. Lee (Project Manager, U.S. Nuclear Regulatory Commission) to C. Williams (Exelon), FitzPatrick Supplemental Information Needed for Acceptance: Revise Allowable Value for Reactor Water Cleanup System Primary Containment Isolation (EPID L-2019-LLA-0190)," October 18, 2019. 7:38 AM

3. Letter from Guy S. Vissing, Senior Project Manager, Section 1, (U.S.

Nuclear Regulatory Commission) to Mr. James Knubel, Chief Nuclear Officer, Power Authority of the State of New York, James A.

FitzPatrick Nuclear Power Plant - Amendment for Technical Specification change regarding Automatic Transient Without SCRAM Recirculation Pump Trip/Alternate Rod Insertion Setpoint Change (TAC NO. MA8171), October 10, 2000

4. Letter from Guy S. Vissing, Senior Project Manager, Section 1, (U.S.

Nuclear Regulatory Commission) to Mr. Michael Kansler, Senior Vice President and Chief Operating Officer, Entergy Nuclear Operations, James A. FitzPatrick Nuclear Power Plant - Amendment RE:

Conversion to Improved Technical Specifications (TAC NO. MA5049),

July 3, 2002

Response to Request for Supplemental Information regarding James A. FitzPatrick License Amendment Request to revise the Reactor Water Clean Up Isolation setpoint November 6, 2019 Page 2 By letter dated September 5, 2019, (Reference 1) Exelon Generation Company, LLC (Exelon) requested a change to the James A. FitzPatrick (JAF) Technical Specifications (TS) in accordance with 10 CFR 50.90. The proposed amendment request would revise the TS Allowable Value for Reactor Water Clean Up (RWCU) isolation on low Reactor Pressure Vessel (RPV) water level from Level 3 ~177 inches) to Level 2 ~107 inches).

By electronic mail dated October 18 (Reference 2), the NRC identified areas where additional information was necessary to complete the acceptance review. to this letter contains the NRC's request for supplemental information immediately followed by Exelon's response.

Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1.

The information attached to this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.

Furthermore, the information attached to this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

There are no commitments contained in this response.

If you should have any questions regarding this submittal, please contact Christian Williams at 610-765-5729.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 6th day of November 2019.

Respectfully,

/~'""-'.'J I L ,)~

David T. Gudger Acting Director, Licensing Exelon Generation Company, LLC Attachments: 1. Request for Supplemental Information and Exelon Response

Enclosures:

1. JAF Calculation - JAF-CALC-NBl-00205 RO

2. JAF Calculation - JAF-CALC-NBl-00206 RO cc: Regional Administrator - NRC Region I w/ attachments NRC Senior Resident Inspector- JAF "

NRC Project Manager, NRR-JAF A. L. Peterson, NYSERDA

Attachment 1 Page 1 of 4 ATTACHMENT 1 SUPPLEMENTAL INFORMATION NEEDED J. A. FITZPATRICK LICENSE AMENDMENT REQUEST TO REVISE THE TECHNICAL SPECIFICATIONS ALLOWABLE VALUE FOR INITIATING REACTOR WATER CLEANUP SYSTEM ISOLATION ON REACTOR WATER LEVEL 2 RATHER THAN LEVEL 3 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 By letter dated September 5, 2019 (ADAMS Accession No. ML19248B085), Exelon Generation submitted a license amendment request (LAR) to revise the Technical Specifications (TS) Allowable Value (AV) for the Reactor Water Cleanup (RWCU) system Primary Containment Isolation. NRC staff has reviewed the LAR and determined the following additional information is needed to start the review.

1. Please provide the calculation or a summary of the calculation for the revised allowable value for the RWCU system isolation. If a summary of the calculation is provided it should include the analytical value, the AV, the total loop accuracy, the limiting setpoint, the nominal setpoint, and the As-Left Tolerance and As-Found Tolerance values used for performing calibration surveillances. In addition, please address how the random and bias errors were identified, estimated, and combined. Provide a list of the assumptions and the basis for the assumptions used as part of the summary of the calculation.

Exelon Response: Enclosures 1 and 2 of this letter are the requested calculations. The specific requested information is included in each of these two calculations.

2. Please explain the methodology used in the calculation and a brief explanation of how the calculation meets the guidance within Regulatory Guide 1.105 and RIS 2006-17. Is Fitzpatrick committed to TSTF-493? If so explain how the guidance of TSTF-493 has been implemented in the calculation. If not, please describe how the setpoint will be maintained and performance monitoring will be conducted using the As-Left Tolerance and As-Found Tolerance Values.

Exelon Response: The proposed allowable value has been established consistent with the JAFNPP Procedure, CC-JAF-IC-G-003 Rev.0, "Instrument Loop Accuracy and Setpoint Calculation Methodology." This procedure is the current version of the previous JAFNPP Engineering Standard, IES-3A, "Instrument Loop Accuracy and Setpoint Calculation Methodology." The methodology used to determine the allowable values is consistent with the methodology described in ISA-S67.04-1994, Part I, "Setpoints for Nuclear Safety-Related Instrumentation." JAFNPP is not committed to complying with RG 1.105,

Attachment 1 Page 2 of 4 Revision 3, "Setpoints for Safety-Related Instrumentation," which endorses ISA-S67.04-1994, Part I with exceptions and clarifications. However, as part of the upgrade to Improved Technical Specifications (ITS), JAFNPP provided a comparison of IES-3A with RG 1.105, Revision 3. The NRC reviewed IES-3A and the supporting comparison to RG 1.105, Revision 3 and documented the acceptability of this standard in the Safety Evaluation for Technical Specification Amendment (TSA) 274 (Ref. 4).

JAF has not yet adopted Technical Specification Task Force (TSTF) Traveler TSTF-493. Therefore, the applicable notes from the TSTF will not be added to the JAF Technical Specifications.

3. Fitzpatrick uses more than one set of Analytical Limits, Limiting Setpoints, and Allowable Values that have been identified/labeled as Reactor Water Level Low-Low, or Level 2 (L2).

a. Please provide a brief description as to how plant operators and maintenance staff are trained to use and maintain the Level 2 setting using different level values represented by same level setting name designation (i.e. Level 2), so as to avoid confusion by the operators during normal or plant transient conditions.

Exelon Response: Operations and Maintenance are required to reference procedures when operating the plant or performing any maintenance. Maintenance activities and Plant Operations are specifically controlled using Level 1 Procedures. Level 1 Procedures are defined as Continuous Use which requires reading each step of the procedure prior to performing that step, performing each step in the sequence specified and placekeeping each step as complete before proceeding to the next step. The use of procedures is reinforced during training and daily through supervisory observations. The process eliminates possible confusion with different level setpoints as the applicable level 2 for each application is specifically spelled out in applicable procedures.

b. Please provide the available precedencies that may have used more than one nominal setpoint value for Reactor Level Low-Low or L2.

Exelon Response: James A. FitzPatrick received approval for the alternate Low-Low (L2) setpoint through Amendment 264 which was issued on October 10, 2000 (Reference 3). A review of Exelon Plant Technical Specifications (TS) identified one (1) other plant which maintained more than one (1) nominal setpoint value for Reactor Level Low-Low or L2. LaSalle Station maintains High Pressure Core Spray (HPCS) Level 2 isolation setpoint at an allowable value of > -83 inches (TS Table 3.3.5.1-1). In contrast, Surveillance Requirement (SR) 3.3.4.2.3

Attachment 1 Page 3 of 4 (Anticipated Transient Without SCRAM (ATWS)) defines the Level 2 isolation setpoint as > -54 inches. Additionally, the LaSalle Reactor Water Cleanup (RWCU) isolation setpoint for Level 2 is > -58 inches (TS Table 3.3.6.1-1).

c. Describe why two different nominal set point values are being used for the Reactor Water Level Low-Low Level 2 setting, and briefly explain the bases for the results of the different analyses that have been performed for determining the different appropriate analytical limits and resulting allowable values for these settings. Finally, please explain why the lower of these two values was selected for initiating the RWCU isolation function.

Exelon Response: Analyses supporting JAF operation utilize two values for the RPV Level 2 Analytical Limit dependent on application. The higher of the two values is used for initiation of the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems, while the lower value is used for Anticipated Transient Without Scram-Recirculation Pump Trip (ATWS-RPT) initiation (as well as for initiation of Alternate Rod Injection, ARI). Use of staggered limits (and associated setpoints) provides an opportunity for HPCI and/or RCIC to restore RPV water level during slow moving transients without further actions that would complicate transient response (including RWCU isolation). The use of two Level 2 settings was submitted and approved by the NRC under TS amendment 264 (Reference 3). Allowable Values associated with each Analytical Limit is dependent on instrumentation characteristics and may differ between functions. A normal scram results in RPV level lowering below the 126.5 but would be expected to remain above the proposed setpoint of RWCU. A level below 126.5 was selected to prevent isolation of the RWCU system during a normal scram.

4. Please provide the basis for the Reactor Water Level references (e.g., Top of Active Fuel (TAF)).

Exelon Response: Reactor Water Level as described in the JAF Technical Specifications in in reference to the Top of Active Fuel (TAF).

ENCLOSURE 1 JAF CALCULATION - JAF-CALC-NBI-00205 R0

Design Analysis I Last Page No. s 30 Analysis No.: 1 JAF-CALC-NBl-00205 Revision: 0 Major 12;1 MinorD

Title:

3 Setpoint Calculation for Vessel Lo-Lo LVL Primary Containment Isolation Function (02-3LT-57A,B and 02-3STU-258A,B)

EC No.: 4 625092 Revision: s 00 Station(s): 1 JAF Component(s): 14 Unit No.:

• 1 02-3STU-258A Discipline: s l&C 02-3STU-2588 Descrip. Code/Keyword: 10 U1/Uncertainty Safety/QA Class: 11 SR System Code: 12 02-3 Structure: 13 N/A CONTROLLED DOCUMENT REFERENCES 1s Document No.: From/To Document No.: l=rom/To JAF-CALC-NBl-00202 Rev. 2 From ISP-100A-PCIS, Rev. 017 To ISP-201A Rev. 19 To ISP-1008-PCIS, Rev. 017 To ISP-201 B, Rev. 20 To Is this Design Analysis Safeguards Information? 1

• YesD No 12;1 If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? 11 YesD No 12;1 If yes, ATl/AR#:

This Design Analysis SUPERCEDES: 1

• in its entirety.

Description of Revision (list changed pages when all pages of original analysis were not changed): 1 The issuance of this new calculation is in support of the new Reactor Water Cleanup Primary Containment Isolation setpoint change.

Co-preparer: Dong Liang Li [/a~~-~~* lo{30[1q, Print Name SignNlme ~Q Date Preparer: 20 Jessica Quraeshi .J  : ., -~- 1ol3dl1ci-Print Name /Sij n Name '-""' Date Method of Review: 21 Detailed Review 181 AlternM Cal:o~ttached) D Testing D Reviewer: 22

.;r~meMe.s.:Sey_ J:.sD,J ~me ~..__... I\ I< /zo 1'1 Date I Review Notes: 23 Independent review 12;1 Peer review D

[l... ev*i e..,,J p e~ I',...,_ ~ct 'ti\ &i. cc'.~ 4"'- c e ~*:.t-'tt cc -AA- 3oi ~ cc~AI\ -3oq - I ca (.

A\\. c.a-rx ~.A -h ".ACA c r?o f'r. J..-~....t ~ 6 +i < ~A.c. *h 'r:Y, (For External Analyses Only)

External Approver: 24 Prin~le- Sign Name Date Exelon Reviewer:

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25 Sion Narue Date N~

Independent 3rd Party Review Reqd? 26 YesD Exelon Approver: 21

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CALCULATION SHEET I Paqe No: 2 Total Paqes: 30 Calculation Number: [[::JAF-CALC-NBI|JAF-CALC-NBI]] -00205 Revision No: O REVISION

SUMMARY

SHEET Revision No. Affected Pages Reason for Revision All Initial issue 0

CALCULATION SHEET I PaQe No: 3 Total PaQes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O Table of Contents 1.0 Purpose .......................................................................................................................... 4 2.0 Inputs ............................................................................................................................. 6 3.0 Assumptions .................................................................................................................. 11 4.0 References ....................................................................................................................11 5.0 Method of Analysis ........................................................................................................14 6.0 Numeric Analysis ........................................................................................................... 15 7.0 Scaling ..........................................................................................................................27 8.0 Conclusions ...................................................................................................................29 9.0 Results ..........................................................................................................................30

CALCULATION SHEET IPage No: 4 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 1.0 Purpose The purpose of this calculation is to determine the instrument channel uncertainties associated with the Reactor Water LO-LO Level 2 PCIS trip loop. This calculation establishes the Trip Setpoint (NTSP) and an Allowable Value for this function .

Table 1 Instrumentation Table Manuf/ Rack/ Environmental Zone Component ID Function Model No. Cabinet 2-3LT-57A,B Reactor Vessel Rosemount Rack 25-05 300-3 Recirc Pump Trip 1153DB5RC and MSIV Closure Level Transmitter 2-3MTU-257A,B Reactor LO Level Rosemount Panel 09-91 , 92 ATTS PCIS Master Trip 510DU Unit (710DU) 2-3STU-258A,B Reactor LO Level Rosemount Panel 09-91 , 92 ATTS PCIS Slave Trip Unit 510DU (710DU) 1.1 Loop Function and Diagram The transmitters 02-3LT-57A,B monitor reactor water level. The transmitters send a signal through Master Trip Units (MTU) to the bistable units 02-3STU-258A,B which actuate the primary relays 05A-K124A,B .

The Reactor Water Cleanup (RWCU) isolations occur when either 05A-K124A or 05A-K1248 contacts actuate due to low water level in the reactor vessel. The purpose of this logic is to close 12MOV-15, 12MOV-18, and 12MOV-69 which isolates RWCU. The Reactor Vessel Water Level 2 function associated with isolation is assumed in the analysis of the recirculation line break (LOCA).

CALCULATION SHEET I PaQe No: 5 Total PaQes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O Figure 1 Reactor Building Relay Room Elevation 284' 8" Panel 09-91 MTU Analog Output 02-3STU-258A 02-3LT-57A II 02-3MTU-257A 1----+-l (Vessel Low Level 2 (Vessel Low I Logic A1) Level 2 RWCU Isolation Logic)

Not addressed with this calculation - see I MTE1 I JAF-CALC-NBl-00202 I

I 05A-K124A I MTE2 I Note: The A, B loops are identical.

CALCULATION SHEET I Page No: 6 Total Pao es: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 2.0 Inputs Table 2 Env1ronmen

. tll a nput s Radiation Zones Location Event Humidity Temp (°F) Ref.

(TIO)

Reactor Building Normal 40-70% R.H. 1.8x104 R 65-100 300 ft Elevation (40 yrs)

Column 3.5 300-3 4.1.26 Line- R Accident 100% R.H. 7.55x103 R 110 Dose Pt. 3A (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

(LOCA) 90R 174 (HELB)

Relay Room Normal 40-50% R.H. 1.75x10 2 R 60-90 284'8 ft Elevation 4.1.7 ATTS Column 10 (40 years) 4.4.2 Line G 4.4.3 Accident Same as Same as Same as normal normal normal Table 3 MTE Table MAKE/MODEL RANGE OF ACCURACY FOR USED TO Comments SCALE(S) SCALE CALIBRATE Fluke/8060A As +/- (0.05%(RDG) + 2 Transmitter Mfg .

Or Equivalent Necessary digits) 2-3LT-57A,B Specs/PECO DMM (Resolution 0.001 (Ref. 4.2.1 and Energy Corp.

VDC) 4.2.2)

Manometer 0-2000 in. Transmitter ISP-201 A,B has H20 (Ref. +/- 0.1% (RDG) 2-3LT-57A,B a range of 0-4 .1.19) (Ref. 4.2.1 and 16.8 In Hg 4.2.2)

Digital 16 mA +/- 0.17% of span 2-3MTU-257A,B Includes Readout 2-3STU-258A,B standard used to Assembly 4.2.3 calibrate MTE 4.2.4 4.1.24

CALCULATION SHEET I Page No: 7 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O Table 4 Des1an nput s Component ID Design Value Ref Comments Reactor Vessel AL 454.94 inches above 4.1.13 Determination of the Analytical Water Level 2 trip vessel zero Limit 4.1.28 (102.44 inches TAF) 2-3 LT-57A,B Input -230.89 to-81.81" H20 4.1.16 The transmitter measures (Transmitter) b.P inches of H20 through the (149.08 In H20 b.P differential pressure between Span) the reference leg and the measurement leg. The b.P range of the transmitter is

-230.89 to -81.81 In H20. This is equivalent to 14.5 to 224.5 In H20 above top of active fuel (TAF). Therefore, span above TAF is 210 In H20.

4.2.1 Equivalent 0 psig calibration 16.80 to 6.00 In Hg b.P 4.2.2 including correction for static 4.2.3 pressure span shift:

4.2.4 -229.10 to -81.18 In H20 b.P Output 4-20 mAdc 4.3.3 4 vdc span over 210 In H20 (1-5 VDC) 4.3.4 span and 149.08" H20 b.P Nominal Span RA1 +/- 0.25% 4.4.1 DDR1 +/- 1.75% Span 4.1.21 Per 30 months DR1 +/-0.2% URL 4.4.1 URL=750 In H20 (for Range 5)

(30 months)

RE1 +/-4.0% URL 4.4.1 During and after exposure to 2.2 X 107 rads TID SE1 +/-0.5% URL 4.4.1 During and after a seismic disturbance defined by a required response spectrum with ZPA of 4g's SP1 +/- 0.2% URL per 1000 4.4.1 Span effect correction psi (Zero) and +/- 0.5% uncertainty reading per 1000 psi (Span)

PS1 < +/-0.005% Span per 4.4.1 Volt TE1 +/- (0.75% URL+ 0.5% 4.4.1 URL= 750 In H20 (for Range Span) per 100°F b. T 5)

ALT1 +/- 0.01 Vdc 4.2 .1 Technician precision in setting

(+/-0.25% Span) 4.2 .2 the As Left device during calibration.

02-3MTU-257 A,B Input 4-20 mAdc 4.2.3 (4-20 mAdc)

• 14.5 to 224.5 In 02-3STU-258A, B (16 mAdc span) 4.2.4 H20 RA2A +/- 0.15% span (MTU) 4.4.2 MTU AnaloQ Output to Slave

CALCULATION SHEET IPage No: 8 Total Pages: 30 Calculation Number: J AF-CALC- NBI-00205 Revision No: O 4.4.3 ALT2A +/- 0.1875% span 4.2.3 Calibration Tolerance 4.2.4 RA3T +/- 0.20% span (STU) 4.4.2 Trip point repeatability (Trip ) 4.4.3 requirements listed are valid for up to 6 months of operation.

This value is taken as Rated Accuracv.

ALT3r +/- 0.2% span 4.1.1 Diffa +/- 0.5 - 7.5% span 4.4.2 Reset Differential adjustment 4.4.3

CALCULATION SHEET I Paae No: 9 Total Paaes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 3.0 Assumptions 3.1 In accordance with CC-JAF-IC-G-003 (Ref. 4.1.1 ), this function is a Type 2 setpoint and Rigor R2.

3.2 Temperature and radiation levels in the relay room, for the ATTS cabinets are negligible and considered a mild environment during normal and accident operating conditions. The Rosemount STU is located in the ATTS cabinets, a controlled environment area.

Therefore, for the purposes of this calculation, the random error for normal and accident conditions are the same per Ref. 4.1.7, 4.4.2, and 4.4.3.

3.3 Analyses supporting JAF operation utilize two values for the RPV Level 2 Analytical Limit dependent on application. The higher of the two values (114.44") is used for initiation of the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems, while the lower value (102.44") is used for Anticipated Transient Without Scram-Recirculation Pump Trip (ATWS-RPT) initiation (as well as for initiation of Alternate Rod Injection, ARI). Use of staggered limits (and associated setpoints) provides an opportunity for HPCI and/or RCIC to restore RPV water level during slow moving transients without further actions that would complicate transient response (including RWCU isolation). For this reason, we will use the lower Analytical Limit, 102.44", for RWCU isolation as evaluated by GE Analysis (Ref.

4.1.28) 3.4 For M&TE devices, it is assumed that the standard used in calibration of the M&TE has an accuracy which is 4 times better than the accuracy of the calibrated M&TE as per the requirement stated in Section 4.6.2 of Test Equipment Calibration Program (Ref. 4.1.11 ).

3.5 Seismic uncertainty effects are not included in this calculation based on the following: Per Reference 4.1.10, this instrument loop's functions are not required during and following a seismic event. They are, however, required to be operable before a seismic event. Should a seismic event occur, operability will be evaluated per Reference 4.1.12.

The effects of normal vibration (or a minor seismic event that does not cause an unusual event) on a component will be calibrated out on a periodic basis. As such, the uncertainty associated with this effect is negligible.

3.6 It is assumed that the effects of normal radiation are calibrated out on a periodic basis. Outside containment, there is not a substantial increase in radiation during normal operation. For this reason, the uncertainty introduced by radiation effects is assumed to be negligible.

CALCULATION SHEET I Page No: 10 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 3.7 Per Reference 4.4.1, the Rosemount 1153 transmitter specification has a Relative Humidity range of 0-100% R.H. There are no humidity-related effects in the vendors' specification. Therefore, it is assumed that all other specifications are valid for 0-100% R.H. and HE1=0.

3.8 Per Reference 4.1.15 the energy release into the Reactor Building from a HELB event would be terminated prior to reactor vessel level decreasing to the level 3 trip. Therefore, IRE for environmentally harsh conditions resulting from an accident outside the drywell will not be considered.

3.9 Generally, the temperature at which an instrument is calibrated is within the normal operating range of the instrument. Also, any ambient temperature effects are typically small. Therefore, the uncertainty associated with the temperature variations during calibration is assumed to be negligible. This assumption applies only to temperatures changes during calibration. Temperature effects over the expected range of equipment operation from the calibration temperature must still be considered.

3.10 This calculation has been completed for one LO-LO Level loop transmitter and STU (Loop 02-3LT-57A). Because the configuration of LO-LO level loops are identical, with the transmitters located on a similar rack, this configuration is applicable to loop 02-3LT-57B, per Ref. 4.3.3 and 4.3.4.

3.11 Rosemount Model Trip Units 510U and 710DU are interchangeable, and this calculation encompasses the use of either model. During accident conditions the two models have difference specifications and the worst case specification will be used to ensure interchangeability.

However, for this calculation, the trip units are located in the relay room for which the normal condition exists during accident environment as per Section 2.0 Table 2.

CALCULATION SHEET I Page No: 11 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 4.0 References 4.1 JAFNPP Documents 4.1.1 CC-JAF-IC-G-003, Rev. 0'1nstrument Loop Accuracy and Setpoint Calibration Methodology" 4.1.2 CC-AA-309-1001, Rev. 10 "Guidelines for Preparation and Processing of Design Analyses" 4.1.3 JAF-CALC-05-00132, "Effect of the Revised Mass and Energy Released From RWCU Pipe Breaks on the Reactor Building Pressure and Temperatures" Rev. 0 4.1.4 JAFNPP, Final Safety Analysis Report 4.1.5 JAFNPP, Technical Specifications and Bases 4.1.6 JAFNPP Design Basis Document (DBD) -016, "Primary Containment Isolation System", Revision 4.

4.1.7 JAFNPP Design Basis Document (DBD) -070, "Control Room Ventilation & Cooling Design Basis Document", Revision 14.

4.1.8 JAFNPP, ITS and Bases 4.1.9 ROME PEDB, JAFNPP 4.1.10 USl-A-46, JAFNPP "Safe Shutdown Equipment and Relay Evaluation", Rev. 5 4.1.11 Procedure PL-AA-001-0001, "Admin Process for the Performance of M&TE Calibration Activities at the Station."

4.1.12 Procedure AOP-14, "Earthquake", Rev. 19.

4.1.13 TODl-EC-625092-01, "JAF Reactor Water Cleanup Setpoint Change Design Inputs," April 2019 4.1.14 JAF-RPT-PC-01283, Instrument Drift Analysis for PCIS, Rev. 0.

4.1.15 JAF-RPT-MULT-00206 Rev. 1, "Consideration of Temperature-Induced Uncertainties in Automatic Actuation Setpoints".

4.1.16 EDE-21-0889, Supplement 1, Revision 0, August 1991, "Fitzpatrick Reactor Vessel Water Level Indication Evaluation (Power Uprate Condition)"

4.1.17 EDP-20, Rev 9, "Procedure for Establishing if Plant Equipment is within the scope of 10CFR50.49 (EQ)."

4.1.18 ETR 2062.1, Rev. 2, Ecotech Study for NYPA, "General Analysis of Cable Circuitry performance at JAFNPP," issued 3-13-90, (EQ-371)

CALCULATION SHEET I Page No: 12 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 4.1.19JAF l&C M&TE Calibration Program Master list, Dated 10-14-97.

4.1.20 IMP-71.26, Rev. 7 - ECCS and RPS Power Supply Functional Test (ATTS).

4.1.21 JAF-CALC-MULTl-03457 Rev.1, Drift020 Rosemount 1153DB5 Transmitters 4.1.22 EC 62731, Incorporation of Design Equivalent Modification D1 082, Rosemount Trip/Calibration Unit 510DU Replaced by 710DU 4.1.23 EC 5681/15660, Evaluation of Alternate M&TE 4.1.24 EC 44380, Inclusion of new Temperature Uncertainty Error 4.1.25 DRN-03-00587, Minor Calculation Change for Process Measurement Uncertainty 4 .1.26 Specification 22A 1290AC, Rev. 0, Reactor Building Ventilation Cooling and Heating Systems 4.1.27 JAF-CALC-MISC-03364 Rev. 0, Rosemount Digital Readout Assembly- Test Equipment Total Uncertainty 4.1.28 GEH-005N2981, Rev. 0, JAFNPP Reactor Water Level Setpoint Change for Reactor Water Cleanup System Isolation.

4.2 Instrument Surveillance Procedures 4.2.1 ISP-201A, Rev. 19 4 .2.2 ISP-201 B, Rev. 20 4.2.3 ISP-100A-PCIS, Rev. 17 4.2.4 ISP-100B-PCIS, Rev. 17

4.3 Drawings

4.3.1 1.60-25 Rev. 14; Elem. Diag. Analog Trip SYS ATTS 4.3.2 FM-47A, Rev. 52; Flow Diagram Nuclear Boiler Vessel Instruments System 02-3.

4.3.3 LP-02-3E Rev. 3; Loop Diagram NBI Reac Recirc Pmp Trip Level and Pressure, MST Viv Closure Level and ARI ATWS Pressure "A".

4.3.4 LP-02-3F Rev. 3; Loop Diagram NBI Reac Recirc Pmp Trip Level and Pressure, MST Viv Closure Level and ARI ATWS Pressure "B".

CALCULATION SHEET I Page No: 13 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 4.3.5 5.01-136 Rev. 4; "Reactor Assembly".

4A VendorDocumen~

4.4.1 Rosemount Model 1153 Series B Pressure Transmitters Manual: Publication No. 4302, Rev. 7, (R369-0030).

4.4.2 Rosemount Model 710 DU Trip/Calibration System Instruction Manual 4471, Rev. 2, (R369-0029).

4.4.3 Rosemount Model 510 DU Trip/Calibration System Instruction Manual 4247-1, Rev. 1, (R369-0032)

CALCULATION SHEET I Page No: 14 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 5.0 Method of Analysis INSTRUMENT CHANNEL UNCERTAINTY (CU)

Per Reference 4.1.1 , the instrument channel uncertainty can be calculated with a single loop equation containing all potential uncertainty values, or by a series of related term equations. The specific channel calculation will coincide with the channel's layout from process measurement to final output module or modules. Random channel uncertainties may be combined using Square Root Sum-of-Squares (SRSS) method. Any positive (B+) or negative (B-) bias associated with the instrument channel uncertainty is combined algebraically.

The typical equation for linear CU will have the following form:

CU= +/-.JPM2 + PE 2 + (e 1 ) 2 + (e 2 ) 2 + .... +(en) 2 +B+/- +IR Where:

PM = Random uncertainties that exist in the channel's basic Process Measurement.

PE = Random uncertainties that exist in the channels Primary Element or; any system element that quantitatively converts the measured variable energy into a form suitable for measurement.

B+/- = A sum total of all the bias components of the individual components and uncertainty of the process that consistently has the same algebraic sign and is expressed as an estimated limit of error.

IR = Insulation Resistance Effect leakage allowance in% of span; resulting from high humidity and temperature subsequent to an accident.

en = Random uncertainties that are associated with any module or; assembly of interconnected components that constitutes an identifiable device, instrument, or piece of equipment.

CALCULATION SHEET I Page No: 15 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.0 Numeric Analysis 6.1 Process Measurement Effects (PM) 6.1.1 Reference Leg Temperature Effects Reference 4.1.15 evaluates the PM for a small-break LOCA resulting in a

=

PMs1As +1.7024 In H20.

Therefore:

PMs1As =+1.7024 In H20

=+(1.7024 In H20) I (210 In H20)

=+ 0.81 % Span There are no random errors identified in Reference 4.1.15.

Therefore:

PMRANDOM =0 6.1.2 Primary Element Acct.lacy (PE)

There is no primary element in this configuration.

Therefore:

PE=O 6.1.3 Insulation Resistance Effect (IR)

Per Section 3.8 accident uncertainties outside the drywell (HELB) do not have to be considered.

Therefore:

IR= 0 6.2 Instrument Module Uncertainties 6.2.1 Transmitter (e1) 6.2.1.1 Reference Accuracy (RA1)

RA1 is included in the DDR1 term.

CALCULATION SHEET IPage No: 16 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.2.1.2 Determined Drift (DDR1)

Per Reference 4 .1.21 the instrument drift evaluation provides a value for transmitter drift performance based on a statistical study of actual "as found" and "as-left" data. The maximum expected drift for a 30-month period for Rosemount transmitter is given as +/-1.75% span.

Therefore:

DDR1 = +/-1.75% span 6.2.1.3 Humidity Effect (HE1)

Per Section 3.7, humidity effects are not specified .

Therefore:

HE1=0 6.2.1.4 RadiationEffect(RE1)

Section 2.0, Input Table, RE1 = +/- 4.0% URL accuracy during and after testing to 2.2x107 . Per Section 3.6, radiation effect is assumed to be negligible.

RE1=0 6.2.1 .5 Seismic Effect (SE1)

Per Section 3.5, there is no seismic effect, therefore; SE 1 =O 6.2.1.6 Static Pressure Effect (SP1)

The static pressure effect for the Rosemount 1153 consists of two components: Zero effect and Span effect.

Zero effect: SP1(zero)

Per Section 2, Table 4, the Rosemount 1153 transmitter zero effect is

+/- 0.2% URL per 1000 psi. Using a nominal pressure of 1040 psi , then:

For Range 5; URL= 750 In H20 6P SP1(zero) = [(+/-0.2%) *(750 In H20 6P) / 1000 psi]*1040psi

= +/- 1.56 In H20 6P SP1(zero> = (+/- 1.56 In H20) I (149 .08 In H20 6P)

= +/-1.05 % Span

CALCULATION SHEET I Paoe No: 17 Total Pao es: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: 0 Span shift: SP1(span)

Per Section 2 Table 4, the Rosemount 1153 transmitter span shift can be calibrated out, however the correction uncertainty is +/- 0.5% of reading per 1000 psi. Using a nominal pressure of 1040 psi, and the maximum 6P of 230.89 In H20 then:

SP1(span) =[(+/-0.5% ) *(230.89" H20 6P) / 1000 psi]*1040psi

=+/- 1.201" H20 6P SP1(span) =(+/- 1.201" H20) I (149.08" H20 6P)

=+/-0.8056 % Span Using the Square Root Sum of Squares to combine the Zero effect and Span shift:

SP1 = +/- (1.05% 2 + 0.81 % 2 )Y.

SP1 = +/- 1.326 % Span 6.2.1. 7 Power Supply Effect (PS1)

For this calculation, the power supply effect PS1 is included in the DDR1 term.

CALCULATION SHEET IPage No: 18 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.2.1.8 TemperatureEffect(TE1)

Per Section 2.0, Table 4 the Rosemount temperature effect is +/-(0.75%

URL + 0.5% Span) per 100°F lff. Per Section 3.8 accident uncertainties for an accident outside the drywell, (HELB) do not have to be considered since the energy release into the Reactor Building will be terminated prior to Reactor Vessel level reaching the level 3 setpoint. Per Ref. 4.1.15, Table 1 during LOCA conditions, the temperature in the Reactor Building is 110°F. From Section 2.0 the normal temperature is 65-100°F.

URL = 750" H20 ~p (for Range 5)

TE1 = +/-((0.75%)*(750" H20 6P) +(0.5%)*(149.08 In H20 6P)]

• (110°F - 65°F )/(100°F)

= +/-2.867 In H20 ~p TE1 =+/- (2.867 In H20 ~P)/(149.08 In H20 ~P)

= 1.92% Span 6.2.1.9 Measuring &Test Equipment Uncertainty (MTE1)

MTE1 is included in the DDR1 term.

6.2.1.1 O As-Left Tolerance (ALT1)

Per Section 2.0, As-Left Tolerance is +/-0.01 Vdc. Then :

ALT1 = (+/- 0.01 Vdc) I (4 Vdc)

= +/- 0.25% Span 6.2.1.11 Module Uncertainty From Section 5, the general form of the device uncertainty equation is; e =+/- (RA2 + DR2 + TE 2 + RE 2 + SE 2 + HE2 +SP 2 + MTE 2 + ALT2 + PS 2 ) 112 + B*

Substituting RA1, DR1, PS1 & MTE1 with the value of DDR1, and B+/- = 0 (Since no biases were identified), and removing the uncertainties listed as negligible or not applicable:

e1 = +/-[ (1 .75%) 2 + (1 .326%) 2 + (1.92%) 2 + (0.25%)2p12 e1 =+/-2.93 % Span

CALCULATION SHEET I Paae No: 19 Total Paaes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.2.2 Rosemount Master Trip Unit Analog Output (e2A)

The uncertainties determined here are applicable to the MTU analog output that feeds the STU bistable input.

6.2.2.1 Reference Accuracy - MTU Analog Output (RA2A)

The MTU RA for analog output (RA2A) to slave function is given in Section

2.0. Therefore

RA2A =+/- 0.15% Span 6.2.2.2 Drift (DR2A)

The trip point repeatability, Rated Accuracy, is valid for 6 months.

Therefore, with a calibration frequency (SI) for the Trip Unit at 6 months, any drift value is included within the Rated accuracy.

Therefore:

DR2A =0 6.2.2.3 Temperature Effect(TE2A)

Per Section 3.2, the temperature effect associated with the MTU is included in the reference accuracy (Ref. 4.4.2 and 4.4.3) because the temperature profile is bounded (Ref. 4.1.7).

Therefore:

TE2A = 0 6.2.2.4 Humidity Effect (HE2A)

There are no humidity-related effects described in the vendor's specifications for this device. Per Section 3.2, humidity effects are considered negligible.

Therefore:

HE2A = 0

CALCULATION SHEET IPage No: 20 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.2.2.5 Radiation Effect(RE2A)

Per Section 3 .2, normal radiation induced effects are assumed to be small and capable of being adjusted out at each calibration. As such, normal radiation effects are considered negligible.

Therefore:

RE2A =0 6.2.2.6 Seismic Effect (SE2A)

Per Section 3 .5, seismic effects are not applicable.

Therefore:

SE2A =0 6.2.2.7 Static Pressure Effect (SP2A)

The MTU is an electrical device and as such is not affected by static pressure effects.

Therefore:

SP2A =0 6.2.2.8 Power Supply Effect (PS2A)

There are no power supply variation effects stated in the vendor's specifications for this device. PS effect is considered to be negligible.

(Ref. 4.4 .2 and 4.4.3).

Therefore:

PS2A =0 6.2.2.9 Measuring &Test Equipment Uncertainty (MTE2A)

The Rosemount Digital Readout (RDR) assembly will be used in calibrating the trip units. Per Section 2.0, Table 3 the readout assembly accuracy is specified as+/- 0.17% of span.

Therefore:

MTE2A =+/- 0.17% Span 6.2.2.10 As-Left Tolerance (ALT2A)

Per Section 2 .0, As-Left Tolerance is+/- 0.03 mAdc ALT2A = (+/- 0.03 mAdc) I (16 mAdc)

=+/- 0.1875 % Span

CALCULATION SHEET I Page No: 21 Total Paaes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.2.2.11 MTU Module Uncertainty From Section 5.0, the general form of the device uncertainty equation is; e = +/-(RA2 + DR2 + TE 2 + RE 2 + SE2 + HE2 +SP2 + MTE 2 + ALT 2 + PS 2 ) 112 + 8+/-

Removing the uncertainties listed as negligible or not applicable, the analog function will be:

= +/- (0.15% 2 + 0.17% 2 + 0.1875% 2) 112

= +/- 0.29 % span 6.2.3 Rosemount Slave Trip Unit - Trip Function (ear) 6.2.3.1 STU Trip Reference Accuracy (RAar)

The STU Reference Accuracy for the trip function is given in Section 2 Table 4 as+/- 0.2% of span.

Therefore:

RA3r =+/- 0.2% span 6.2.3.2 Drift (DRar)

The trip point repeatability, Reference Accuracy, is valid for 6 months.

Therefore, with a calibration frequency (SI) for the Trip Unit at 6 months, any drift value is included within the Reference accuracy.

Therefore:

OR3r =0

CALCULATION SHEET IPage No: 22 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: 0 6.2.3.3 Temperature Effect(TE3T)

Per Section 3.2, the temperature effect associated with the STU is included in the reference accuracy (Ref. 4.4.2 and 4.4 .3) because the temperature profile is bounded (Ref. 4.1.7).

TE3T =0 6.2.3.4 Humidity Effect (HE3T)

There are no humidity-related effects described in the vendor's specifications for this device. Per Section 3.2, humidity effects are considered negligible.

Therefore:

HE3T =0 6.2.3.5 Radiation Effect(RE3T)

Per Section 3.2, normal radiation induced effects are assumed to be small and capable of being adjusted out at each calibration. As such, normal radiation effects are considered negligible.

Therefore:

REJr =0 6.2.3.6 Seismic Effect (SE3r)

Per Section 1.2.5, seismic effects are not applicable for these devices.

Therefore:

SEJr =0 6.2.3. 7 Static Pressure Effect (SP3r)

The STU is an electrical device and as such is not affected by static pressure effects.

Therefore:

SP3T = 0 6.2.3.8 Power Supply Effect (PS3T)

There are no power supply variation effects stated in the vendor's specifications for this device (Ref. 4.4.2).

Therefore:

PS3r =0

CALCULATION SHEET I Paoe No: 23 Total Paoes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.2.3.9 Measuring &Test Equipment Uncertainty (MTE3r)

The Rosemount Digital readout assembly is considered in MTE2A.

Therefore:

MTE3r = 0 6.2.3.10 As-Left Tolerance (ALT3r)

Per Section 2.0, As-Left Tolerance is+/- 0.2% span.

Therefore:

ALT 3T = +/- 0.2% span 6.2.3.11 STU Module Uncertainty From Section 5.0, the general form of the device uncertainty equation is; e = +/- [RA2 + DR2 + TE2 + RE2 + SE2 + HE2 +SP 2 + MTE2 + ALT2 + PS 2 ]1 12 + 8+/-

Removing the uncertainties listed as negligible or not applicable, and setting 8+/- =0 Substituting:

e3T = +/- (0.2% 2 + 0.2% 2) 112

=+/-0.28% Span

CALCULATION SHEET IPage No: 24 Total Pages: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.3 TOTAL LOOP UNCERTAINTY (CU)

The general equation is found in Reference 4.1.1 . This equation is reduced to the applicable terms for each module as developed below:

CU =+/- [PM 2 + PE2+ (e1 )2 +(e2)2t ....+(e n)2] 112 + B+/- +IRE Where:

PM= 0 (No Primary Measurement effect has been identified for this loop)

PE= 0 e1 = +/- 2.93 % Span e2A =+/- 0.29 % Span e3r = +/- 0.28 % Span B = PMsias(Temp) =+ 0.81  % Span IRE =O 6.3.1 STU trip function (Transmitter, MTU & STU):

Deleting the negligible and not applicable terms:

Substituting from above:

e1 =+/- 2.93 % Span e2A =+/- 0.29 % Span e3r = +/- 0.28 % Span PMsias(Temp) = + 0.81 % Span CUsru =+/- [(2.93%) 2 + (0.29%)2+(0.28%)2]1'2 + 0.81 %

=+/- 2.96 % Span + 0.81 % Span CUsru+ =+ 3.77 % Span

=3.77%

• 210 In H20 =7.917 In H20 CUsru- =-2.15% Span

=-2 .15%

• 210 In H20 =-4.515 In H20

CALCULATION SHEET J PaQe No: 25 Total PaQes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 6.4 Trip Setpoint (NTSP)

Per Reference 4.1.1, the Trip Setpoint for decreasing plant parameters is:

NTSP = AL + CUsru + Margin From Section 2, Data Input table, AL =102.44 In H20 above TAF Substituting from above using the positive side of the CU for a decreasing parameter:

NTSP = (102.44 In H20) + (7.917 In H20) +Margin NTSP = 110.36 In H20 + Margin NTSP =110.76 In H20 Decreasing This is the lowest value that the STU can be set to and not exceed the Analytical Limit. The Trip Setpoint was calculated to be 110.36 In H20 with 0.4 In H20 margin added, therefore the Trip Setpoint is 110.76 In H20. See Section 6.5.5 for justification of added margin.

6.5 Allowable Value(s)

Per Reference 4.1.1, for any setpoint that has an Analytical Limit (AL) an Allowable Value (AV) shall be calculated for the total loop for that bistable and for each separate calibration test that is conducted on the associated instruments in that loop.

For decreasing plant parameters the AV is determined by:

AV = NTS P -AVTSMc11anre1 Where:

AVTSMchannel =Allowable value to Trip Setpoint Margin; the statistical combination of the calibration error.

Module AVTSM = +/- [RA2 + MTE 2 +ALT 2 + DR 2]1 12 AVTSMchanne1 = +/- [AVTSM1 2 + AVTSM2 2 + ... AVTSMn 2]1 12 6.5.1 Transmitter AVTSM The module 1 (transmitter) AVTSM is determined from comparison of Section 6.2 and applicable terms as follows:

A VTSMe1 = +/- [RA2 + DR 2 + MTE 2 +ALT 2]1 12 Per Reference 4.1.14 and 4.1.8, this is the components of DDR1 and ALT, Therefore substituting DDR1 and ALT values:

AVTSMe1 = +/- [DDR1 2 +ALT1 2]1'2 AVTSMe1 = +/- [(1.75%) 2 + (0.25%)2p12

CALCULATION SHEET IPaQe No: 26 Total PaQes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: 0 AVfSMe1 = +/- 1.77 % Span 6.5.2 MTU Analog Output AVTSM The module 2 A VfSM is determined from comparison of Section 6.3 applicable terms as follows:

A VfSMe2A = +/- [RA2 + DR2+ MTE2 + ALT 2]1'2 Substituting:

A vrsMe2A = +/- ((0.15%) 2 + o + (0.17%) 2 + (0.1875%)2]1'2 AVfSMe2A = +/- 0.29% Span 6.5.3 STU trip function AVTSM The module 2 A VfSM is determined from comparison of Section 6.3 applicable terms as follows:

A VfSMe3r = +/- [RA2 + DR 2+ MTE 2 + ALT2] 112 Substituting:

AVfSMe3r = +/- [(0.2%) 2 + O + (0)2 + (0.2%)2p12 AVfSMe3r = +/- 0.28% Span 6.5.4 Channel AVTSM The A VfSM can then be determined by combining the module values as follows:

AVfSM = +/- [A VfSMe1 2 + A VfSMe2A + A VTSMe3r2] 112

= +/- ((1.77%) 2 + (0.29%) 2 + (0.28%)2]1/2 AVfSM = +/- 1 .815 % Span 6.5.5 Calculated Allowable Value (CAV)

Recalling the GAV for a decreasing parameter is determined by:

GAV = NTSP - (AVTSM + Margin)

GAV= 110.76" H20- (1 .815%

• 210" H20 + 0.4" H20)

GAV= 106.55" H20 We will set the Allowable value to 107.0" H20 to allow for margin in order to not challenge the Analytical Limit of 102.44" H20. Since we are adding margin to the Calculated Allowable Value, we also need to add margin to the NTSP to account for the As Found Tolerance.

CALCULATION SHEET J Paoe No: 27 Total Pao es: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: O 7.0 SCALING Scaling for the transmitter calibration is provided in JAF-CALC-NBl-00202 and thus will not be repeated here. The Master Trip Unit analog outputs are currently checked for calibration using the ATTS Calibration Unit as part of the indication checks and STU trip checks. If the MTU analog outputs require independent calibration, refer to the vendor manual or old l&C Department procedures that calibrated the master trip unit analog output functions.

7 .1 STU (Trip Function)

The input signal to STU is 4-20 mA, and the output is a trip. The new proposed field trip setpoint determined in Section 6.4 of this calculation is 110.76 In H20 (transmitter output). This value is converted to % span and milliamps, using the information from Section 2.0 as follows:

02-3STU-258A. B NTSP in% Span= [(110.76-14.5) In H20 / 210 In H20]

• 100

= 45.6%

NTSP in mA = 4mA + 45.6%

• 16mA = 11.33 mA 7.1.1 STU Trip As Found Tolerance(AFTJr)

Per Ref. 4.1.1 , for Safety-Related functions the AFT can be determined by the following equation:

AFT3r= +/-AVTSMe3r

= +/- 0.28 % Span

=+/- 0.28%

• 16mA =+/- 0.0448 mA 7.1.2 As Left Tolerance(ALTJr)

From Ref 4.1.1, the As-Left Tolerance is set equal to the RA of the device.

From Table 4:

ALT3T =+/- 0.2 % span

=0.2%*16mA

=+/-0.032 mA

CALCULATION SHEET I Page No: 28 Total Paaes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: 0 7 .2 STU Allowable Values The Allowable Values for 02-3STU-258A,B will be scaled to support the testing units in mA:

Allowable Value calculated in Section 6.5 is 106.6 In H20 above Top of Active Fuel (TAF) with added margin the allowable value is 107 In H20. This is converted to % span, milliamps, In H20 6P and using the information from Section 2.0 as follows:

AV in% Span= [(107-14.5) In H20 / 210 In H20]

• 100 = 44.0%

AV in mA = 4mA + 44.0%

• 16mA = 11.04 mA

CALCULATION SHEET I Paoe No: 29 Total Paoes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: 0

8.0 CONCLUSION

S Line Diagram The figure below shows the relation of the limits, setpoints and the allowable values.

224.S- 100%

Trip Setpoint 110.76"

~~-+-~~~.......-~~~~~~~~~--

(NTSP)

AVTSM +Margin= 4.21" CU+Margin = 8.32" Allowable Value 107.0" 106.55" Calculated Allowable Value 102.44" Analytical Limit 14.5" (0% Span)

Measured Range Note 1: Levels are with respect to Top of Active Fuel (TAF)

Note 2: Not to scale

CALCULATION SHEET I Paae No: 30 Total Paa es: 30 Calculation Number: JAF-CALC - NBI-00205 Revision No: O 9.0 RESULTS Function cu NTSP CAV AV AL 110.76 106.55 ~107 102.44 In HzO Reactor +7 .917,- In HzO In HzO In H20 Above TAF Vessel Water 4 .515 Decreasing Decreasing Decreasing Level 2 trip In HzO Scaling AFT and ALT Results Module AFT ALT Trip Trip 2-3STU-258A, B +/- 0.045 +/- 0.032 mAdc mAdc

ENCLOSURE 2 JAF CALCULATION - JAF-CALC-NBI-00206 R0

Design Analysis I Last Page No. 6 31 Analysis No.: 1 JAF-CALC-NBl-00206 Revision: 0 Major [gl MinorD

Title:

3 Setpoint Calculation for Vessel Lo-Lo LVL Primary Containment Isolation Function (02-3LT-58A,B and 02-3STU-259A,B)

EC No.: 4 625092 Revision: 5 00 Station(s): 1 JAF Component(s): 1 4

Unit No.: e 1 02-3STU-259A Discipline:

• l&C 02-3STU-259B Descrip. Code/Keyword: 10 U1/Uncertainty Safety/QA Class: 11 SR System Code: 12 02-3 Structure: 13 N/A CONTROLLED DOCUMENT REFERENCES 15 Document No.: From/To Document No.: From/To JAF-CALC-NBl-00203 Rev. 2 From ISP-100C-PCIS, Rev. 15 To ISP-201 C, Rev. 19 To ISP-1000-PCIS, Rev. 15 To ISP-201 D, Rev. 21 To Is this Design Analysis Safeguards Information? 16 YesD No [gj If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified YesD No [gj If yes, ATl/AR#:

Assumptions? 11 This Design Analysis SUPERCEDES: 18 in its entirety.

Description of Revision (list changed pages when all pages of original analysis were not changed): 1*

The issuance of this new calculation is in support of the new Reactor Water Cleanup Primary Containment Isolation setpoint change.

Co-preparer: Dong Liang Li u~ . ---~* IC /?,o l 1tti

~'1ame Print Name Date Preparer: 20 Jessica Quraeshi Print Name /Siar1Naril&

-A~r"u

- . ... J lC>I Date sol I q Method of Review: 21 Detailed Review [2] Alternat~lculatlons (attached) D Testing D Reviewer: 22 S"' w\e s :ks.kso4'>

Print Name

~~

gn Name ll Is /;z:o 19 Date Review Notes: 23 Independent review [gl Peer r~iew D

~e..J-: e..w (?e.r- -hr,,..,, ed., 1,,, "'tc" :-ol&tr<<;..~ W * ~ CC:: -A-A- 3 D '1 i- c ('..-AA ~3 cfi -< oai.

A (l (For External Analyses Only)

/'I') WflVl '°"' + S" ,,,, rd r ~() , Q 4-e-c:A. s e\ -h '.sfc...c -b rV . I External Approver: 2 4 N/A Print Name Sign Name Date Exelon Reviewer: 25 NIA Print Name Sian Name - Date Independent 3rd Party Review Reqd? 26 YesD No ~~

Exelon Approver: 21

.5f'e~il<" c ~~-"'~

")( Sl'lrin~

- - -- l\)s ,q Print Name /.// Date I

CALCULATION SHEET I Page No: 2 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 REVISION

SUMMARY

SHEET Revision No. Affected Paces Reason for Revision All Initial issue 0

CALCULATION SHEET I Paoe No: 3 Total Paoes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 Table of Contents 1.0 Purpose ................................................................................................................ 4 2.0 Inputs .................................................................................................................... 6 3.0 Assumptions ....................................................................................................... 12 4.0 References ......................................................................................................... 12 5.0 Method of Analysis ............................................................................................. 15 6.0 Numeric Analysis ................................................................................................ 16 7.0 Scaling ............................................................................................................... 28 8.0 Conclusions ........................................................................................................ 30 8.0 Results ............................................................................................................... 31

CALCULATION SHEET I Page No: 4 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 1.0 Purpose The purpose of this calculation is to determine the instrument channel uncertainties associated with the Reactor Water LO-LO Level 2 PCIS trip loop. This calculation establishes the Trip Setpoint (NTSP) and an Allowable Value for this function .

Table 1 Instrumentation Table Component Manuf/ Rack/ Environmental Function ID Model No. Cabinet Zone 2-3LT-58A,B Reactor Vessel Rosemount Rack 25-06 300-5 Recirc Pump Trip 1153DB5RC and MSIV Closure Level Transmitter 2-3MTU- Reactor LO Level Rosemount Panel 09-93, ATIS 258A,B PCIS Master Trip 510DU 94 Unit (710DU) 2-3STU- Reactor LO Level Rosemount Panel 09-93, ATIS 259A,B PCIS Slave Trip 510DU 94 Unit (710DU) 1.1 Loop Function and Diagram The transmitters 02-3LT-58A,B monitor reactor water level. The transmitters send a signal through Master Trip Units (MTU) to the bistable units 02-3STU-259A,B which actuate the primary relays 05A-K124C,D.

The Reactor Water Cleanup (RWCU) isolations occur when either 05A-K 124C or 05A-K124D contacts actuate due to low water level in the reactor vessel. The purpose of this logic is to close 12MOV-15, 12MOV-18 and 12MOV-69 which isolates RWCU. The Reactor Vessel Water Level 2 function associated with isolation is assumed in the analysis of the recirculation line break (LOCA) .

CALCULATION SHEET I Page No: 5 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 Figure 1 Reactor Building Relay Room Elevation 284' 8" Panel 09-93 MTU Analog 02-3MTU-258A Output 02-3STU-259A I 02-3LT-58A :1-----+--I (Vessel Low Level 2 (Vessel Low Logic A1) Level 2 RWCU Isolation Logic)

Not addressed with this calculation - see JAF-CALC-NBl-00203 I MTE1 I I I 05A-K124C I MTE2 I Note: The A, B loops are identical.

CALCULATION SHEET I Page No: 6 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 2.0 Inputs Table 2 Env1ronmen

. ta 11 nputs Radiation Zones Location Event Humidity Temp (°F) Ref.

(TIO)

Reactor Normal 40-70% R.H. 1.8x104 R 65-100 Building 300 (40 yrs) ft Elevation 300-5 4.1.26 Accident 100% R.H. 2.42x10 3 R 110 (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

(LOCA) 90 R 159 (HELB) Worst Case Relay Room Normal 40-50% R.H. 1.75x10 2 R 60-90 284',8" (40 years) 4.1.7 ATTS 4.4.2 4.4.3 Accident Same as Same as Same as normal normal normal

CALCULATION SHEET I Page No: 7 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 Table 3 MTE Table MAKE/MODEL RANGE ACCURACY FOR USED TO Comments OF SCALE CALIBRATE SCALE(S)

Fluke/8060A As +/- (0.05%(RDG) + 2 Transmitter Mfg.

Or Equivalent Necessary digits) 2-3LT-58A,B Specs/PECO DMM (Resolution 0.001 (Ref. 4.2.1 and Energy Corp.

VDC) 4.2.2)

Manometer 0-2000 in. Transmitter ISP-201C,D H20 (Ref. +/- 0.1% (ROG) 2-3LT-58A,B has a range of 4.2.19) (Ref. 4.2.1 and 0-16.8 In Hg 4.2.2)

Digital 16 mA +/- 0.17% of span 2-3MTU-258A, B Includes Readout 2-3STU-259A,B standard used Assembly 4.2.3 to calibrate 4.2.4 MTE 4.1.24

CALCULATION SHEET I PaQe No: 8 Total PaQes: 31 Calculation Number: JAF- CALC- NBI - 00206 Revision No: 0 Table 4 Des1gn nput s Component ID Design Value Ref Comments Reactor Vessel AL 454.94 inches above 4.1.13 Determination of the A nalytical Water Level 2 trip vessel zero Limit 4.1.28 (102.44 inches TAF) 2-3 LT-58A,B Input -229.3 to -80.22" HzO 4.1.16 The transmitter measures (Transmitter) LlP inches of HzO through the (149.08 In HzO L\P differential pressure between Span) the reference leg and the measurement leg . The L\P range of the transmitter is

-230.89 to -81.81 In HzO. This is equivalent to 14.5 to 224.5 In HzO above top of active fuel (TAF) . Therefore, span above TAF is 210 In HzO.

4.2.1 Equivalent 0 psig calibration 16.80 to 6.00 In Hg L\P 4.2.2 including correction for static 4.2.3 pressure span shift:

4.2.4 -229.10 to -81 .18 In HzO L\P Output 4-20 mAdc 4.3.3 4 vdc span over 210 In HzO (1-5 VDC) 4.3.4 span and 149.08" HzO L\P Nominal Span RA1 +/- 0.25% 4.4.1 DDR1 +/- 1.75% Span 4.1.21 Per 30 months DR1 +/-0.2% URL 4.4.1 URL=750 In HzO (for Range 5)

(30 months)

RE1 +/-4.0% URL 4.4.1 During and after exposure to 2.2 X 101 rads TIO SE1 +/-0.5% URL 4.4.1 During and after a seismic disturbance defined by a required response spectrum with ZPA of 4Q's SP1 +/- 0.2% URL per 1000 4.4.1 Span effect correction psi (Zero) and+/- 0.5% uncertainty reading per 1000 psi (Span)

PS1 < +/-0.005% Span per 4.4.1 Volt TE1 +/- (0.75% URL+ 0.5% 4.4.1 URL = 750 In HzO (for Range Span) per 100°F L\T 5)

ALT1 +/- 0.01 Vdc 4.2.1 Technician precision in setting

(+/-0.25% Span) 4.2.2 the As Left device during calibration.

CALCULATION SHEET I Page No: 9 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 02-3MTU-258A,B Input 4-20 mAdc 4.2.3 (4-20 mAdc) .. 14.5 to 224.5 In 02-3STU-259A,B (16 mAdc span) 4.2.4 H20 RA2A +/- 0.15% span (MTU) 4.4.2 MTU Analog Output to Slave 4.4.3 ALT2A +/- 0.1875% span 4.2.3 Calibration Tolerance 4.2.4 RA3T +/- 0.20% span (STU) 4.4.2 Trip point repeatability (Trip) 4.4.3 requirements listed are valid for up to 6 months of operation.

This value is taken as Rated Accuracy.

ALT3r +/- 0.2% span 4.1.1

CALCULATION SHEET I Page No: 10 Total Paaes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 3.0 Assumptions 3.1 In accordance with CC-JAF-IC-G-003 (Ref. 4.1.1 ), this function is a Type 2 setpoint and Rigor R2.

3.2 Temperature and radiation levels in the relay room, for the ATTS cabinets are negligible and considered a mild environment during normal and accident operating conditions. The Rosemount STU is located in the ATTS cabinets, a controlled environment area.

Therefore, for the purposes of this calculation, the random error for normal and accident conditions are the same per Ref. 4.1.7, 4.4.2, and 4.4.3.

3.3 Analyses supporting JAF operation utilize two values for the RPV Level 2 Analytical Limit dependent on application . The higher of the two values (114.44") is used for initiation of the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems, while the lower value (102.44") is used for Anticipated Transient Without Scram-Recirculation Pump Trip (ATWS-RPT) initiation (as well as for initiation of Alternate Rod Injection, ARI). Use of staggered limits (and associated setpoints) provides an opportunity for HPCI and/or RCIC to restore RPV water level during slow moving transients without further actions that would complicate transient response (including RWCU isolation) . For this reason, we will use the lower Analytical Limit, 102.44", for RWCU isolation as evaluated by GE Analysis (Ref. 4.1.28) 3.4 For M&TE devices, it is assumed that the standard used in calibration of the M&TE has an accuracy which is 4 times better than the accuracy of the calibrated M&TE as per the requirement stated in Section 4.6.2 of Test Equipment Calibration Program (Ref. 4.1.11 ).

3.5 Seismic uncertainty effects are not included in this calculation based on the following: Per Reference 4.1.10, this instrument loop's functions are not required during and following a seismic event. They are, however, required to be operable before a seismic event. Should a seismic event occur, operability will be evaluated per Reference 4.1.12.

The effects of normal vibration (or a minor seismic event that does not cause an unusual event) on a component will be calibrated out on a periodic basis. As such, the uncertainty associated with this effect is negligible.

CALCULATION SHEET I Pai:ie No: 11 Total Pai:ies: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 3.6 It is assumed that the effects of normal radiation are calibrated out on a periodic basis. Outside containment, there is not a substantial increase in radiation during normal operation. For this reason, the uncertainty introduced by radiation effects is assumed to be negligible.

3. 7 Per Reference 4.4.1, the Rosemount 1153 transmitter specification has a Relative Humidity range of 0-100% R.H. There are no humidity-related errors in the vendors' specification. Therefore, it is assumed that all other specifications are valid for 0-100% R.H. and HE1 =O.

3.8 Per Reference 4.1.15 the energy release into the Reactor Building from a HELB event would be terminated prior to reactor vessel level decreasing to the level 3 trip. Therefore, IRE for environmentally harsh conditions resulting from an accident outside the drywell will not be considered.

3.9 Generally, the temperature at which an instrument is calibrated is within the normal operating range of the instrument. Also, any ambient temperature effects are typically small. Therefore, the uncertainty associated with the temperature variations during calibration is assumed to be negligible. This assumption applies only to temperatures changes during calibration. Temperature effects over the expected range of equipment operation from the calibration temperature must still be considered.

3.10 This calculation has been completed for one LO-LO Level loop transmitter and STU (Loop 02-3LT-58A). Because the configuration of LO-LO level loops are identical, with the transmitters located on a similar rack, this configuration is applicable to loop 02-3LT-58B, per Ref. 4.3.3 and 4.3.4.

3.11 Rosemount Model Trip Units 51 OU and 71 ODU are interchangeable, and this calculation encompasses the use of either model. During accident conditions the two models have difference specifications and the worst case specification will be used to ensure interchangeability.

However, for this calculation, the trip units are located in the relay room for which the normal condition exists during accident environment as per Section 2.0 Table 2.

CALCULATION SHEET I Paoe No: 12 Total Paoes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 4.0 References 4.1 JAFNPP Documents 4.1.1 CC-JAF-IC-G-003, Rev. 0'1nstrument Loop Accuracy and Setpoint Calibration Methodology" 4.1.2 CC-AA-309-1001, Rev. 10 "Guidelines for Preparation and Processing of Design Analyses" 4.1.3 JAF-CALC-05-00132, "Effect of the Revised Mass and Energy Released from RWCU Pipe Breaks on the Reactor Building Pressure and Temperatures" Rev. 0 4.1 .4 JAFNPP, Final Safety Analysis Report 4.1.5 JAFNPP, Technical Specifications and Bases 4.1.6 JAFNPP Design Basis Document (DBD) -016, "Primary Containment Isolation System", Revision 4.

4.1.7 JAFNPP Design Basis Document (DBD) -070, "Control Room Ventilation & Cooling Design Basis Document", Revision 14.

4.1.8 JAFNPP, ITS and Bases 4.1.9 ROME PEDB, JAFNPP 4.1.10 USl-A-46, JAFNPP "Safe Shutdown Equipment and Relay Evaluation," Rev. 5 4.1.11 Procedure PL-AA-001-0001, "Admin Process for the Performance of M&TE Calibration Activities at the Station."

4.1.12 Procedure AOP-14, "Earthquake", Rev. 19.

4.1.13 TODl-EC-625092-01, "JAF Reactor Water Cleanup Setpoint Change Design Inputs," April 2019 4.1.14 JAF-RPT-PC-01283, Instrument Drift Analysis for PCIS, Rev. 0.

4.1.15JAF-RPT-MULT-00206 Rev. 1, "Consideration ofTemperature-lnduced Uncertainties in Automatic Actuation Setpoints".

4.1.16 EDE-21-0889, Supplement 1, Revision 0, August 1991, "Fitzpatrick Reactor Vessel Water Level Indication Evaluation (Power Uprate Condition)"

CALCULATION SHEET I Page No: 13 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 4.1.17 EDP-20, Rev 9, "Procedure for Establishing if Plant Equipment is within the scope of 10CFR50.49 (EQ)."

4.1.18 EQ-371, Rev. 0, Ecotech Study for NYPA, "General Analysis of Cable Circuitry performance at JAFNPP" 4.1.19 JAF l&C M&TE Calibration Program Master List, Dated 10-14-97.

4.1.20 IMP-71.26, Rev. 7 - ECCS and RPS Power Supply Functional Test (ATTS).

4.1.21 JAF-CALC-MULTl-03457 Rev.1, Drift020 Rosemount 1153DB5 Transmitters 4.1.22 EC 62731, Incorporation of Design Equivalent Modification D1 082, Rosemount Trip/Calibration Unit 51 ODU Replaced by 71 ODU 4.1.23 EC 5681/15660, Evaluation of Alternate M&TE 4.1.24 EC 44380, Inclusion of new Temperature Uncertainty Error 4.1.25 DRN-03-00587, Minor Calculation Change for Process Measurement Uncertainty 4.1.26 Specification 22A 1290AC, Rev. 0, Reactor Building Ventilation Cooling and Heating Systems 4.1.27 JAF-CALC-MISC-03364 Rev. 0, Rosemount Digital Readout Assembly - Test Equipment Total Uncertainty 4.1.28 GEH-005N2981, Rev. 0, JAFNPP Reactor Water Level Setpoint Change for Reactor Water Cleanup System Isolation.

4.2 Instrument Surveillance Procedures 4.2.1 ISP-201 C, Rev. 19 4.2.2 ISP-201 D, Rev. 21 4.2.3 ISP-1 OOC, PCIS, Rev.15 4.2.4 ISP-100D, PCIS, Rev.15

CALCULATION SHEET I Page No: 14 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0

4.3 Drawings

4 .3.1 1.60-25 Rev. 14; Elem. Diag. Analog Trip SYS ATTS 4.3.2 FM-47A, Rev. 52; Flow Diagram Nuclear Boiler Vessel Instruments System 02-3.

4.3.3 LP-02-3G Rev. 3; Loop Diagram NBI Reactor Recirculation Pump Trip Level and Pressure, MST Valve Closure Level and ARI ATWS Pressure "A" 4.3.4 LP-02-3H Rev.3; Loop Diagram NBI Reactor Recirc Pump Trip Level and Pressure, MST Viv Closure Level and ARI ATWS Pressure "B" 4.3.5 5.01-136 Rev. 4; "Reactor Assembly".

4.4 Vendor Documents 4.4.1 Rosemount Model 1153 Series B Pressure Transmitters Manual: Publication No. 4302, Rev. 7, (R369-0030).

4.4 .2 Rosemount Model 710 DU Trip/Calibration System Instruction Manual 4471, Rev. 2, (R369-0029).

4.4 .3 Rosemount Model 510 DU Trip/Calibration System Instruction Manual 4247-1, Rev. 1, (R369-0032)

CALCULATION SHEET I Paoe No: 15 Total Paoes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 5.0 Method of Analysis INSTRUMENT CHANNEL UNCERTAINTY (CU)

Per Reference 4.1.1, the instrument channel uncertainty can be calculated with a single loop equation containing all potential uncertainty values, or by a series of related term equations. The specific channel calculation will coincide with the channel's layout from process measurement to final output module or modules. Random channel uncertainties may be combined using Square Root Sum-of-Squares (SRSS) method. Any positive (B+) or negative (B-) bias associated with the instrument channel uncertainty is combined algebraically.

The typical equation for linear CU will have the following form:

CU= +/-.JPM 2 + PE 2 + (e 1 ) 2 + (e 2 ) 2 + .... +(en) 2 +B+/- + IR Where:

PM = Random uncertainties that exist in the channel's basic Process Measurement.

PE = Random uncertainties that exist in the channels Primary Element or; any system element that quantitatively converts the measured variable energy into a form suitable for measurement.

B+/- =A sum total of all the bias components of the individual components and uncertainty of the process that consistently has the same algebraic sign and is expressed as an estimated limit of error.

IR =Insulation Resistance Effect leakage allowance in% of span; resulting from high humidity and temperature subsequent to an accident.

en= Random uncertainties that are associated with any module or; assembly of interconnected components that constitutes an identifiable device, instrument, or piece of equipment.

CALCULATION SHEET I Page No: 16 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.0 Numeric Analysis 6.1 Process Measurement Effects 6.1 .1 Reference Leg Temperature Effects Reference 4.1.15 evaluates the PM for a small-break LOCA resulting

=

in a PMs1As 1.6523 In H20.

Therefore:

PMs1As =1.6523 In H20

= (1.6523 In H20)/(210 In H20)

= 0.79% Span There are no random errors identified in Reference 4.1.15.

Therefore:

PMRANDOM =0 6.1.2 Primary Element Accuracy (PE)

There is no primary element in this configuration .

Therefore:

PE =O 6.1.3 Insulation Resistance Effect (IR)

Per Section 3.8 accident uncertainties outside the drywell (HELB) do not have to be considered.

Therefore:

IR=O 6.2 Instrument Module Uncertainties 6.2.1 Transmitter (e1) 6.2.1.1 Reference Accuracy (RA1)

RA1 is included in the DDR1 term .

CALCULATION SHEET I Paoe No: 17 Total Paoes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.2.1.2 Determined Drift (DDR1)

Per Reference 4.1.21 the instrument drift evaluation provides a value for transmitter drift performance based on a statistical study of actual "as found" and "as-left" data. The maximum expected drift for a 30-month period for Rosemount transmitter is given as +/-1.75% span.

Therefore:

DDR1 = +/-1.75% span 6.2.1.3 Humidity Effect (HE1)

Per Section 3.7, humidity effects are not specified.

Therefore:

HE1 =O 6.2.1.4 Radiation Effect(RE1)

Section 2.0, Input Table, RE1 = +/- 4.0% URL accuracy during and after testing to 2.2x10 7

• Per Section 3.6, radiation effect is assumed to be negligible.

RE1=0 6.2.1.5 Seismic Effect (SE1)

Per Section 3.5, there is no seismic effect, therefore; SE1=0 6.2.1.6 Static Pressure Effect (SP1)

The static pressure effect for the Rosemount 1153 consists of two components: Zero effect and Span effect.

Zero effect: SP1(zero)

Per Section 2, Table 4, the Rosemount 1153 transmitter zero effect error is +/- 0.2% URL per 1000 psi. Using a nominal pressure of 1040 psi, then: For Range 5; URL = 750 In HzO 6P SP1(zero) = [(+/-0.2%) *(750 In HzO 6P) / 1000 psi]*1040psi

= +/- 1.56 In HzO 6P SP1(zero) = (+/- 1.56 In HzO) I (149.08 In HzO 6P)

SP1(zero) = +/-1.05 % Span

CALCULATION SHEET I Paae No: 18 Total Paaes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 Span shift: SP1(span)

Per Section 2 Table 4, the Rosemount 1153 transmitter span shift can be calibrated out, however the correction uncertainty is+/- 0.5% of reading per 1000 psi. Using a nominal pressure of 1040 psi, and the maximum ~P of 229.3 In H20 then:

SP1(span) =[(+/-0.5% ) *(229.3" H20 LlP) / 1000 psi]*1040psi

=+/- 1.19" H20 LlP SP1(span) =(+/- 1.19" H20) I (149.08" H20 LlP)

=+/-0.80 % Span Using the Square Root Sum of Squares to combine the zero effect and Span shift:

SP1 = +/- [(1.05%) 2 + (0.80%)2] Yz SP1 = +/- 1.32 % Span 6.2.1. 7 Power Supply Effect (PS1)

For this calculation, the power supply effect PS1 is included in the DDR1 term.

CALCULATION SHEET I Page No: 19 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: O 6.2.1.8 Temperature Effect(TE1)

Per Section 2.0, Table 4 the Rosemount temperature effect is +/-(0.75%

URL + 0.5% Span) per 100°F lff. Per Section 3.8 accident uncertainties for an accident outside the drywell, (HELB) do not have to be considered since the energy release into the Reactor Building will be terminated prior to Reactor Vessel level reaching the level 3 setpoint. Per Ref. 4.1.15, Table 1 during LOCA conditions, the temperature in the Reactor Building is 110°F. From Section 2.0 the normal temperature is 65-100°F.

URL = 750" H20 ~p (for Range 5)

TE1 =+/-[(0.75%)*(750" H20 6P) +(0.5%)*(149.08 In H20 6P)]

• (110°F - 65°F )/(100°F)

= +/-2.867 In H20 ~p TE1 = +/- (2.867 In H20 ~P)/(149.08 In H20 ~P)

= 1.92% Span 6.2.1.9 Measuring &Test Equipment Uncertainty (MTE1)

MTE1 is included in the DDR1 term.

6.2.1.10 As-Left Tolerance (ALT1)

Per Section 2.0, As-Left Tolerance is +/-0.01 Vdc. Then:

ALT1 = (+/- 0.01 Vdc) I (4 Vdc)

=+/- 0.25% Span 6.2.1.11 Module Uncertainty From Section 5, the general form of the device uncertainty equation is; e =+/- (RA2 + DR2 + TE 2 + RE 2 + SE2 + HE2 +SP2 + MTE2 + ALT2 + PS 2 ) 112 + B+/-

Substituting RA1, DR1, PS1 & MTE1 with the value of DDR1, and B+/- = 0 (Since no biases were identified), and removing the uncertainties listed as negligible or not applicable:

e1 = +/-( DDR1 2 + SP1 2 + TE1 2 +ALT1 2) 112 e1 =+/-[ (1.75 %) 2 + (1.32 %) 2 + (1.92 %) 2 + (0.25 %) 2]1 12 e1 = +/- 2.93% Span

CALCULATION SHEET I Paqe No: 20 Total Paqes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: O 6.2.2 Rosemount Master Trip Unit Analog Output (e2A)

The uncertainties determined here are applicable to the MTU analog output that feeds the STU bistable input.

6.2.2.1 Reference Accuracy - MTU Analog Output (RA2A)

The MTU RA for analog output (RA2A) to slave function is given in Section 2.0 RA2A =+/- 0.15% Span 6.2.2.2 Drift (DRZA)

The trip point repeatability, Rated Accuracy, is valid for 6 months.

Therefore, with a calibration frequency (SI) for the Trip Unit at 6 months, any drift value is included within the Rated accuracy.

Therefore:

DR2A = 0 6.2.2.3 Temperature Effect(TE2A)

Per Section 3.2, the temperature effect associated with the MTU is included in the reference accuracy (Ref. 4.4.2 and 4.4.3) because the temperature profile is bounded (Ref. 4.1.7).

Therefore:

TEzA= 0 6.2.2.4 Humidity Effect (HE2A)

There are no humidity-related effects described in the vendor's specifications for this device. Per Section 3.2, humidity effects are considered negligible.

Therefore:

HE2A =0

CALCULATION SHEET I Page No: 21 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.2.2.5 Radiation Effect(RE2A)

Per Section 3.2, normal radiation induced effects are assumed to be small and capable of being adjusted out at each calibration. As such, normal radiation effects are considered negligible.

Therefore:

RE2A =0 6.2.2.6 Seismic Effect (SE2A)

Per Section 3.5, seismic effects are not applicable.

Therefore:

SE2A =0 6.2.2.7 Static Pressure Effect (SP2A)

The MTU is an electrical device and as such is not affected by static pressure changes.

Therefore:

SP2A =0 6.2.2.8 Power Supply Effect (PS2A)

There are no power supply variation effects stated in the vendor's specifications for this device. PS effect is considered to be negligible.

(Ref. 4.4.2 and 4.4.3).

Therefore:

PS2A = 0 6.2.2.9 Measuring &Test Equipment Uncertainty (MTE2A)

The Rosemount Digital Readout (RDR) assembly will be used in calibrating the trip units. Per Section 2.0, Table 3 the readout assembly accuracy is specified as+/- 0.17% of span.

Therefore:

MTE2A =+/- 0.17% Span

CALCULATION SHEET I Page No: 22 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.2.2.10 As-Left Tolerance (ALT2A)

Per Section 2.0, As-Left Tolerance is+/- 0.03 mAdc AlT2A = (+/- 0.03 mAdc) I (16 mAdc)

=+/- 0.1875 % Span 6.2.2.11 MTU Module Uncertainty From Section 5.0, the general form of the device uncertainty equation is; e =+/-(RA2 + DR2 + TE2 + RE 2 + SE2 + HE2 +SP 2 + MTE2 + ALT2 + PS 2)112

+ 9+/-

Removing the uncertainties listed as negligible or not applicable, the analog function will be:

= +/- [(0.15%)2 + (0.17%)2 + (0.1875%)2]112

= +/- 0.29 % span 6.2.3 Rosemount Slave Trip Unit - Trip Function (e3T) 6.2.3.1 STU Trip Reference Accuracy (RA3T)

The STU Reference Accuracy for the trip function is given in Section 2 Table 4 as +/- 0.2% of span.

Therefore:

RA3r =+/- 0.2% span 6.2.3.2 Drift (DR3r)

The trip point repeatability, Reference Accuracy, is valid for 6 months.

Therefore, with a calibration frequency (SI) for the Trip Unit at 6 months, any drift value is included within the Reference accuracy.

Therefore:

DR3T =0

CALCULATION SHEET I PaQe No: 23 Total PaQes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.2.3.3 Temperature Effect(fEar)

Per Section 3.2, the temperature effect associated with the STU is included in the reference accuracy (Ref. 4.4.2 and 4.4.3) because the temperature profile is bounded (Ref. 4.1.7).

TE3T =0 6.2.3.4 Humidity Effect (HEar)

There are no humidity-related effects described in the vendor's specifications for this device. Per Section 3.2, humidity effects are considered negligible.

Therefore:

HE3T = 0 6.2.3.5 Radiation Effect(REar)

Per Section 3.2, normal radiation induced effects are assumed to be small and capable of being adjusted out at each calibration. As such, normal radiation effects are considered negligible.

Therefore:

RE3T =0 6.2.3.6 Seismic Effect (SEar)

Per Section 1.2.5, seismic effects are not applicable for these devices.

Therefore:

SE3T =0 6.2.3.7 Static Pressure Effect (SPar)

The STU is an electrical device and as such is not affected by static pressure changes.

Therefore:

SP3T =0

CALCULATION SHEET I Page No: 24 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.2.3.8 Power Supply Effect (PS3T)

There are no power supply variation effects stated in the vendor's specifications for this device (Ref. 4.4.2).

Therefore:

PS3T =0 6.2.3.9 Measuring &Test Equipment Uncertainty (MTE3T)

The Rosemount Digital readout assembly is considered in MTE2A.

Therefore:

MTE3T = 0 6.2.3.10 As-Left Tolerance (ALT3T)

Per Section 2.0, As-Left Tolerance is+/- 0.2% span .

Therefore:

ALT3T = +/- 0.2% span 6.2.3.11 STU Module Uncertainty From Section 5.0, the general form of the device uncertainty equation is; e = +/- [RA2 + DR 2 + TE 2 + RE 2 + SE2 + HE2 +SP 2 + MTE2 + ALT2 + PS 2 ]1 12

+ B+/-

Removing the uncertainties listed as negligible or not applicable, and setting B+/- = 0 Substituting:

e3T = +/- [(0.2%) 2 + (0.2%)2]112

=+/-0.28% Span

CALCULATION SHEET I Page No: 25 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.3 TOTAL LOOP UNCERTAINTY (CU)

The general equation is found in Reference 4.1.1. This equation is reduced to the applicable terms for each module as developed below:

CU =+/- [PM 2 +PE 2 +(e1) 2 +(e2)2+ .... +(en) 2] 112 +B+/-+IRE Where:

PM = 0 (No Primary Measurement effect has been identified for this loop)

PE= 0 e1 = +/- 2.93 % Span e2A = +/- 0.29 % Span e3r = +/- 0.28 % Span B =PMsias(Temp) =+ 0.79 % Span IRE= 0 6.3.1 STU trip function (Transmitter, MTU & STU):

Deleting the negligible and not applicable terms:

Substituting from above:

e1 = +/- 2.93 % Span ezA =+/- 0.29 % Span e3r = +/- 0.28 % Span PMsias(Temp) = + 0.79 % Span CUsru = +/- [(2.93%) 2 + (0.29%) 2+(0.28%)2]1f2 + 0.79

=+/- 2.96 % Span+ 0.79 % Span CUsru+ = + 3. 75 % Span

= 3.75%

• 210 In HzO =7.88 In HzO CUsru- = -2.17% Span

= -2.17%

• 210 In HzO =-4.56 In HzO

CALCULATION SHEET I Page No: 26 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.4 Trip Setpoint (NTSP)

Per Reference 4 .1.1, the Trip Setpoint for decreasing plant parameters is:

NTSP = AL + CUsru + Margin From Section 2, Data Input table, AL =102.44 In H20 above TAF Substituting from above using the positive side of the CU for a decreasing parameter:

NTSP = (102.44 In H20) + (7.88 In H20) +Margin NTSP = 110.32 In H20 + 0.4 In H20 NTSP = 110.72 In H20 Decreasing This is the lowest value that the STU can be set to and not exceed the Analytical Limit. The Trip Setpoint was calculated to be 110.32 In H20 with 0.4 In H20 margin added, therefore the Trip Setpoint is 110.72 In H20. See Section 6.5.5 for justification of added margin.

6.5 Allowable Value(s)

Per Reference 4.1 .1, for any setpoint that has an AL an Allowable Value (AV) shall be calculated for the total loop for that bistable and for each separate calibration test that is conducted on the associated instruments in that loop.

For decreasing plant parameters, the AV is determined by:

AV = NTSP -AVTSMChanrel Where:

AVTSMchannel =Allowable value to Trip Setpoint Margin; the statistical combination of the calibration error.

Module A VTSM = +/- [RA2 + MTE 2 + AL T2 + DR 2]1 12 AVTSMchanne1 = +/- [AVTSM1 2 + AVTSM22 + ... AVTSMn2] 112 6.5.1 Transmitter A VTSM The module 1 (transmitter) AVTSM is determined from comparison of Section 6.2 and applicable terms as follows:

CALCULATION SHEET I Page No: 27 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 AVTSMe1 = +/- [RA2 + DR2 + MTE2 +ALT2]112 Per Reference 4.1.14 and 4.1.8, this is the components of DDR1 and ALT, therefore substituting DDR1 and Alt values:

=

AVTSMe1 +/- [DDR1 2 + ALT1 2]1 12 AVTSMe1 = +/- [(1.75%) 2 + (0.25%)2p12 AVTSMe1 = +/- 1.77 % Span 6.5.2 MTU Analog Output AVTSM The module 2 AVTSM is determined from comparison of Section 6.3 applicable terms as follows:

AVTSMe2A = +/- [RA2 + DR 2+ MTE2 + ALT 2]1 12 Substituting:

AVTSMe2A = +/- [(0.15%) 2 + 0 + (0.17%) 2+ (0.1875%)2]1 12 AVTSMe2A = +/- 0.29% Span 6.5.3 STU trip function AVTSM The module 2 AVTSM is determined from comparison of Section 6.3 applicable terms as follows:

=

AVTSMe3r +/- [RA2 + DR 2+ MTE2 + ALT2]1'2 Substituting:

AVTSMe3r = +/- [(0.2%) 2 + 0 + (0) 2+ (0.2%)2]112 AVTSMe3T = +/- 0.28% Span 6.5.4 Channel AVTSM The AVTSM can then be determined by combining the module values as follows:

AVTSM = +/- [AVTSMe1 2 + AVTSMe2A + AVTSMe3r2] 112

= +/- [(1.77%) 2 + (0.29%) 2 + (0.28%) 2] 112 AVTSM = +/- 1.815 % Span

CALCULATION SHEET I Paoe No: 28 Total Paoes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 6.5.5 Calculated Allowable Value (CAV)

Recalling the CAV for a decreasing parameter is determined by:

CAV = NTSP - (AVTSM +Margin)

CAV = 110.72" H20 - (1 .815%

• 210" H20 + 0.4" H20)

CAV = 106.5" H20 We will set the Allowable value to 107.0" H20 to allow for margin in order to not challenge the Analytical Limit of 102.44" H20. Since we are adding margin to the Calculated Allowable Value, we also need to add margin to the NTSP to account for the As Found Tolerance.

7.0 SCALING Scaling for the transmitter calibration is provided in JAF-CALC-NBl-00203 and thus will not be repeated here. The Master Trip Unit analog outputs are currently checked for calibration using the ATTS Calibration Unit as part of the indication checks and STU trip checks . If the MTU analog outputs require independent calibration, refer to the vendor manual or old l&C Department procedures that calibrated the master trip unit analog output functions.

7.1 STU (Trip Function)

The input signal to STU is 4-20 mA, and the output is a trip. The new proposed field trip setpoint determined in Section 6.4 of this calculation is 110.32 In H20 (transmitter output). This value is converted to% span and milliamps, using the information from Section 2.0 as follows:

02-3STU-258A. B NTSP in% Span= [(110.32-14.5) In H20 I 210 In H20]

• 100

= 45.6%

NTSP in mA = 4mA + 45.6%

• 16mA = 11 .3 mA 7.1.1 STU Trip As Found Tolerance(AFT3T)

Per Ref. 4.1.1, for Safety-Related functions the AFT can be determined by the following equation :

AFT3r= +/-AVTSMe3r

= +/- 0.28 % Span

= +/- 0.28%

• 16mA = +/- 0.0448 mA 7.1.2 As Left Tolerance(ALT3T)

From Ref 4.1.1, the As-Left Tolerance is set equal to the RA of the device. From Table 4:

CALCULATION SHEET I Paae No: 29 Total Pages: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: 0 ALT3T = +/- 0.2 % span

= 0.2%*16mA

= +/-0.032 mA 7.2 STU Allowable Values The Allowable Values for 02-3STU-259A,B will be scaled to support the testing units in mA:

Allowable Value calculated in Section 6.5 is 106.5 In H20 above Top of Active Fuel (TAF) with added margin, the allowable value is 107 In H20. This is converted to% span, milliamps, In H20 6P and using the information from Section 2.0 as follows:

AV in% Span= [(107-14.5) In H20 I 210 In H20]

• 100 = 44.0%

AV in mA = 4mA + 44.0%

• 16mA = 11.04 mA

CALCULATION SHEET I Page No: 29 Total Paaes: 30 Calculation Number: JAF-CALC-NBI-00205 Revision No: 0

8.0 CONCLUSION

S Line Diagram The figure below shows the relation of the limits, setpoints and the allowable values.

224.5" (100% $Dan}

'~

Trip Setpoint 110.72" (NTSP) ~~

AVTSM +Margin= 4.22" CU+Margin = 8.28" Allowable Value 107.0"

~,

106.5" Calculated Allowable Value 102.44" Analytical Limit

, / 14.5" (0% Span)

Measured Range Note 1: Levels are with respect to Top of Active Fuel (TAF)

Note 2: Not to scale

CALCULATION SHEET I PaQe No: 31 Total PaQes: 31 Calculation Number: JAF-CALC-NBI-00206 Revision No: O 9.0 RESULTS Function cu NTSP CAV AV AL 110.72 106.5 ~107.0 102.44 In H20 Reactor +7.88, In H20 In H20 In H20 Above TAF Vessel -4.56 Decreasing Decreasing Decreasing Water Level In H20 2 trip Scaling AFT and ALT Results Module AFT ALT Trip Trip 2-3STU-259A, B +/- 0.045 +/- 0.032 mAdc mAdc