ND-22-0219, Technical Specifications Setpoint Report

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Technical Specifications Setpoint Report
ML22227A109
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/11/2022
From: Whitley B
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML22227A108 List:
References
ND-22-0219
Download: ML22227A109 (41)


Text

Brian H. Whitley Southern Nuclear Director, Regulatory Affairs Operating Company, Inc.

3535 Colonnade Parkway Birmingham, AL 35243 Tel 205.992.7079 August 11, 2022 Docket Nos.: 52-025 ND-22-0219 52-026 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 Technical Specifications Setpoint Report Ladies and Gentlemen:

In accordance with Technical Specifications (TS) 5.5.14.e for Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Southern Nuclear Operating Company (SNC) submits the Technical Specifications Setpoint Report that provides the Setpoint Program document required by Technical Specifications 5.5.14.e.

Enclosures 1 and 3 provide the Non-Proprietary version of Technical Specifications Setpoint Report for Units 3 and 4, respectively.

Enclosures 2 and 4 provide the Proprietary version of Technical Specifications Setpoint Report for Units 3 and 4, respectively. These enclosures contain Proprietary information; therefore, SNC requests that these enclosures be withheld under the provisions of 10 CFR 2.390. provides the SNC affidavit for withholding the proprietary information contained in Enclosures 2 and 4. is CAW-22-010, which includes: the Affidavit and Proprietary Information Notice.

Enclosures 2 and 4 contain information proprietary to Westinghouse Electric Company LLC (Westinghouse); it is supported by an Affidavit signed by Westinghouse, the owner of information. The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the Nuclear Regulatory Commission (Commission) and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commissions regulations.

Accordingly, it is respectfully requested that the information that is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commissions regulations.

Correspondence with respect to the proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-22-010 and should be addressed to Camille T.

Zozula, Manager, Regulatory Compliance & Corporate Licensing. Correspondence with respect to proprietary aspects of this letter and its enclosures should also be addressed to Brian H. Whitley at the contact information within this letter.

>-a Southern Nuclear

U.S. Nuclear Regulatory Commission ND-22-0219 Page 2 of 4 This letter contains no regulatory commitments. This letter has been reviewed and determined not to contain security-related information.

If you have any questions, please contact Amy Chamberlain at 205.992.6361.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 11 th of August 2022.

Respectfully submitted, Brian H. Whitley(

Regulatory Affairs Director Southern Nuclear Operating Company

Enclosures:

1) Vogtle Electric Generating Plant (VEGP) Unit 3 Technical Specification Setpoint Report (Non-Proprietary)
2) Vogtle Electric Generating Plant (VEGP) Unit 3 Technical Specification Setpoint Report (Proprietary) (Withheld Information)
3) Vogtle Electric Generating Plant (VEGP) Unit 4 Technical Specification Setpoint Report (Non-Proprietary)
4) Vogtle Electric Generating Plant (VEGP) Unit 4 Technical Specification Setpoint Report (Proprietary) (Withheld Information)
5) Affidavit from Southern Nuclear Operating Company for Withholding Under 10 CFR 2.390
6) CAW-22-010

U.S. Nuclear Regulatory Commission ND-22-0219 Page 3 of 4 cc:

Southern Nuclear Operating Company/ Georgia Power Company Mr. S. E. Kuczynski (w/o enclosures)

Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

Mr. H. Nieh (w/o enclosures)

Mr. G. Chick Mr. J. B. Williams Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. B.H. Whitley Ms. C.A. Gayheart Ms. M. Ronnlund Mr. J.M. DeLano Mr. A. Nix Mr. T.M. Drouin Ms. J. M. Coleman Mr. A. S. Parton Ms. K. A. Roberts Mr. S. C. Leighty Mr. W. Garrett Mr. C. T. Defnall Mr. A.S. Parton Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Regulatory Commission Mr. M. King (w/o enclosures)

Mr. G. Bowman Ms. A. Veil Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Mr. J. Eargle Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette

U.S. Nuclear Regulatory Commission ND-22-0219 Page 4 of 4 Nuclear Regulatory Commission (continued)

Mr. C. Santos Ms. K. McCurry Mr. B. Davis Mr. B. Gleaves Mr. J. Parent Mr. B. Griman Mr. V. Hall Mr. P. OBryan State of Georgia Mr. R. Dunn (w/o enclosures 2 and 4)

Oglethorpe Power Corporation Mr. D. Sorrick (w/o enclosures 2 and 4)

Mr. B. Brinkman (w/o enclosures 2 and 4)

Mr. E. Rasmussen (w/o enclosures 2 and 4)

Municipal Electric Authority of Georgia Mr. J. E. Fuller (w/o enclosures 2 and 4)

Mr. S. M. Jackson (w/o enclosures 2 and 4)

Dalton Utilities Mr. T. Bundros (w/o enclosures 2 and 4)

Westinghouse Electric Company, LLC Mr. L. Oriani, Ph.D. (w/o enclosures)

Mr. T. Rubenstein (w/o enclosures)

Mr. M. Corletti Mr. D. Hawkins Ms. S. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Mr. S. Blanton, Balch Bingham Ms. L. A. Matis, Tetra Tech NUS, Inc. (w/o enclosures 2 and 4)

Mr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc. (w/o enclosures 2 and 4)

Mr. S. Roetger, Georgia Public Service Commission (w/o enclosures 2 and 4)

Mr. R.L. Trokey, Georgia Public Service Commission (w/o enclosures 2 and 4)

Mr. K. C. Greene, Troutman Sanders (w/o enclosures 2 and 4)

Southern Nuclear Operating Company ND-22-0219 Vogtle Electric Generating Plant (VEGP) Unit 3 Technical Specifications Setpoint Report (Non-Proprietary)

(This Enclosure consists of 15 pages, including this cover page)

Vogtle Electric Generating Plant (VEGP) Unit 3 Technical Specification Setpoint Report Revision 0 February 2022 ND-22-0219: Enclosure 1 Page 2 of 15

Technical Specification Setpoint Report - Unit 3 Page 1 of 13 Rev. 0

==

Introduction:==

This report documents the current values of the Vogtle Unit 3 Technical Specifications required automatic protection instrumentation function Nominal Trip Setpoint (NTS), As-Left Tolerance (ALT), and As-Found Tolerance (AFT) for sensors and Process Rack and references to the associated calculation documentation.

This Report satisfies the requirement of the Technical Specifications 5.5.14.e, which states the following:

The SP shall establish a document containing the current value of the specified NTS, AFT, and ALT for each Technical Specification required automatic protection instrumentation function and references to the calculation documentation. Changes to this document shall be governed by the regulatory requirement of 10 CFR 50.59. In addition, changes to the specified NTS, AFT, and ALT values shall be governed by the approved setpoint methodology. This document, including any revisions or supplements, shall be provided upon issuance to the NRC.

ND-22-0219: Enclosure 1 Page 3 of 15

Technical Specification Setpoint Report - Unit 3 Page 2 of 13 Rev. 0 Table 1: Technical Specification 3.3.1-1 RTS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 1a.

Power Range Neutron Flux - High 1

118% RTP 1b.

Power Range Neutron Flux - Low 1

25% RTP

2.

Power Range Neutron Flux - High Positive Rate 1

12% RTP

3.

Overtemperature T 4

See Note (3)

4.

Overpower T (limiting case) 4 108.5% RTP (4) 5a.

Pressurizer Pressure - Low 2 5

1955 psig 5b.

Pressurizer Pressure - High 2 5

2405 psig

6.

Pressurizer Water Level - High 3 6

66% level

7.

Reactor Coolant Flow - Low 2 7

90% flow

8.

Reactor Coolant Pump (RCP)

Bearing Water Temperature -

High 2 8

185 °F

9.

Reactor Coolant Pump (RCP)

Speed - Low 2 9

91.0% rated speed

10.

Steam Generator (SG) Narrow Range Water Level - Low 2 10 21% level

11.

SG Narrow Range Water Level -

High 3 10 76% level

12.

Passive Residual Heat Removal Actuation Not Applicable a, c ND-22-0219: Enclosure 1 Page 4 of 15

Technical Specification Setpoint Report - Unit 3 Page 3 of 13 Rev. 0 Table 2: Technical Specification Section 3.3.2 & 3.3.3 RTS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 3.3.2 Source Range Neutron Flux - High 3

1.0 x 105 cps 3.3.3 Intermediate Range Neutron Flux -

High 2

25% RTP Table 3: Technical Specification 3.3.8-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 1a.

Containment Pressure - Low 11 0.1 psig 1b.

Containment Pressure - Low 2

-0.8 psig

2.

Containment Pressure - High 2 5.0 psig

3.

Containment Radioactivity - High 21 2.0 rad/hr

4.

Containment Radioactivity - High 2 100 rad/hr

5.

Pressurizer Pressure - Low 3 5

1855 psig

6.

Pressurizer Water Level - Low 6

20.0% level

7.

Pressurizer Water Level - Low 2 10.0% level

8.

Pressurizer Water Level - High 23% level

9.

Pressurizer Water Level - High 2 55% level

10.

Pressurizer Water Level - High 3 66% level a, c a, c ND-22-0219: Enclosure 1 Page 5 of 15

Technical Specification Setpoint Report - Unit 3 Page 4 of 13 Rev. 0 Table 3: Technical Specification 3.3.8-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

11.

RCS Tcold - Low 2 14 505 °F

12.

Reactor Coolant Average Temperature (Tavg) - Low 14 550 °F

13.

Reactor Coolant Average Temperature (Tavg) - Low 2 525 °F

14.

RCS Wide Range Pressure - Low 16 1200 psig 15 CMT Level - Low 3 15 57.5% span 16 CMT Level - Low 6 15 56.0% span

17.

Source Range Neutron Flux Doubling 20 Factor of 2.2 increase over baseline

18.

IRWST Lower Narrow Range Level - Low 3 24 109.3 ft

19.

Reactor Coolant Pump Bearing Water Temperature - High 2 8

185 °F

20.

SG Narrow Range Water Level -

Low 2 10 21% level

21.

SG Wide Range Water Level -

Low 2 19 35% span a, c ND-22-0219: Enclosure 1 Page 6 of 15

Technical Specification Setpoint Report - Unit 3 Page 5 of 13 Rev. 0 Table 3: Technical Specification 3.3.8-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

22.

SG Narrow Range Water Level -

High 10 66.8% level

23.

SG Narrow Range Water Level -

High 3 76% level

24.

Steam Line Pressure - Low 2 13 560.3 psig

25.

Steam Line Pressure - Negative Rate - High 100 psig Table 4: Technical Specification 3.3.10-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

Hot Leg Level - Low 4 17 9.7% span

2.

Hot Leg Level - Low 2 17 58.1% span Table 5: Technical Specification Section 3.3.11-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 3.3.11 Startup Feedwater Flow -Low 2 18 200 gpm a, c a, c a, c ND-22-0219: Enclosure 1 Page 7 of 15

[

]

Technical Specification Setpoint Report - Unit 3 Page 6 of 13 Rev. 0 Table 6: Technical Specification 3.3.13-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

Main Control Room Air Supply Iodine or Particulate Radiation Detector - High 2 22 4.86 x 10E-8 Ci/m3 (iodine detector) 5.04 x 10E-9 Ci/m3 (particulate detector)

2.

Main Control Room Differential Pressure - Low 23 0.185 inH2O

3.

Class 1E 24-Hour Battery Charger Undervoltage 26 0.80 p.u Volts Table 7: Technical Specification 3.3.14-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

Spent Fuel Pool Level - Low 2 25 23.5 ft

2.

IRWST Wide Range Level - Low 12 23.04 ft Table 8: Technical Specification 3.3.20-1 ADS and IRWST Injection Blocking Device Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

CMT Level for Automatic Unblocking 15 81.3% span a, c a, c a, c ND-22-0219: Enclosure 1 Page 8 of 15

[

]

Technical Specification Setpoint Report - Unit 3 Page 7 of 13 Rev. 0 RTS Overtemperature T (OTT) and Overpower T (OPT) Parameters (LCO 3.3.1)

Background Information: Although some time constants are not in use currently (i.e. those set to OFF), all available trip setpoint parameters are included for completeness and to create a template for their potential inclusion later. The rationale for presenting the information this way is that the PMS requires non-zero time constants to avoid an error (7, 8 and 9 for the Overpower T time constants and 13 and 14 for the temperature time constants). In these cases, the time constants are set to [ ]a,c initially simply to avoid the error response, then promptly set to OFF (effectively a [ ]a,c time constant as stated in the Vogtle SCD and assumed in the setpoint methodologies). If these time constants are to be utilized in their associated trip setpoint methods at a later time, the value specified in the SCD would be entered and remain ON in the PMS.

1. OTT The OTT trip setpoint (OTTSP) is defined as follows:

OTTSP = OTTSP° - f1(I) 1.a OTTSP° is the core Departure from Nucleate Boiling (DNB) thermal design limit with design axial power distribution as specified in Table 6.

1.b f1(I) is the OTT Axial Flux Difference (AFD) Penalty Function as specified in Table 7.

1.c The pressurizer pressure time constant [ ]a,c.

1.d The pressurizer pressure time constant [ ]a,c.

1.e The margin to OTT trip time constant [ ]a,c.

1.f The margin to OTT trip time constant [ ]a,c.

1.g The margin to OTT trip time constant [ ]a,c.

2. OPT The OPT trip setpoint (OPTSP) is defined as follows:

OPTSP = COP° - f2(I) 2.a COP° = [ ]a,c 2.b f2(I) is the OPT AFD Penalty Function as specified in Table 8.

2.c The margin to OPT trip time constant [ ]a,c.

2.d The margin to OPT trip time constant [ ]a,c.

2.e The margin to OPT trip time constant [ ]a,c.

Note 1: The initialization values for 7, 8 and 9 shall each be set to [ ]a,c. However, the configuration status for 7, 8 and 9 shall be set to OFF (which results in each time constant equaling [ ]a,c seconds as specified).

7, 8 and 9 Time Constants: The way the 2nd Order Lead/Lag Filter element works is that a code initialization value must be entered because the code will not compile otherwise (even if the filter is turned OFF). The code initialization value chosen is the current low limit; if this value is not low enough, an additional analysis could be performed to challenge the 6x CONTRM time requirement for this low limit value.

ND-22-0219: Enclosure 1 Page 9 of 15

Technical Specification Setpoint Report - Unit 3 Page 8 of 13 Rev. 0

3. The T Power Signal parameter values are:

3.a The Tcold dynamic compensation time constant [ ]a,c.

3.b The Tcold dynamic compensation time constant [ ]a,c.

3.c The Tcold dynamic compensation time constant [ ]a,c.

3.d The Thot dynamic compensation time constant [ ]a,c.

3.e The Thot dynamic compensation time constant [ ]a,c.

3.f The Thot dynamic compensation time constant [ ]a,c.

4. Additional temperature measurement algorithm values are:

4.a The Tcold filter time constant [ ]a,c.

4.b The Thot filter time constant [ ]a,c.

Note 2: The initialization values for 13 and 14 shall both be set to [ ]a,c. However, the configuration status for 13 and 14 shall be set to OFF (which results in both time constants equaling [ ]a,c as specified).

13 and 14 Time Constants: Actual Resistance Temperature Detector (RTD)-thermowell pair response time and filter value must not exceed [ ]a,c, per the Safety Analysis. Also note that the way the Lag Filter element works is that a code initialization value must be entered because the code will not compile otherwise (even if the filter is turned OFF). The code initialization value chosen is the current low limit; if this value is not low enough, an additional analysis could be performed to challenge the 6x CONTRM time requirement for this low limit value.

ND-22-0219: Enclosure 1 Page 10 of 15

Technical Specification Setpoint Report - Unit 3 Page 9 of 13 Rev. 0 Table 11 OTTSP° Function Table 12 f1(I) - OTT AFD Penalty Function a, c a, c ND-22-0219: Enclosure 1 Page 11 of 15

Technical Specification Setpoint Report - Unit 3 Page 10 of 13 Rev. 0 Table 13 f2(I) - OPT AFD Penalty Function Note:

Updating the trip setpoints prior to reaching [ ]a,c would maintain conservative protection and is acceptable.

a, c ND-22-0219: Enclosure 1 Page 12 of 15

Technical Specification Setpoint Report - Unit 3 Page 11 of 13 Rev. 0 Notes:

1) For RTDs that are not shared.
2) For RTDs that are shared.
3) For the Overtemperature T function, the NTS should be [ ]a,c lower than the Safety Analysis Limit (SAL). The SAL can be found in APP-SSAR-F5-001, Revision 1, Table 1.2.3.a.
4) [ ]a,c without the f (I) penalty.
5) The Overtemperature T input cards calibration tolerances should not exceed:

[ ]a,c for TCOLD for tag numbers TE125A1/B1/C1/D1 only,

[ ]a,c for TCOLD for tag numbers TE121A1/B1/C1/D1, TE122A/B/C/D only,

[ ]a,c for THOT,

[ ]a,c for pressure, and

[ ]a,c RTP for I (AC160 input modules)

6) The Overpower T input cards calibration tolerances should not exceed:

[ ]a,c for TCOLD for tag numbers TE125A1/B1/C1/D1 only,

[ ]a,c for TCOLD for tag numbers TE121A1/B1/C1/D1, TE122A/B/C/D only,

[ ]a,c for THOT

[ ]a,c RTP for I (AC160 input modules)

ND-22-0219: Enclosure 1 Page 13 of 15

Technical Specification Setpoint Report - Unit 3 Page 12 of 13 Rev. 0

References:

1. APP-PMS-M3C-117, Revision 1, Power Range Neutron Flux Reactor Trip Setpoint and High Positive Rate Uncertainty Calculations for the AP1000 Plant, October 2017.
2. APP-PMS-M3C-107, Revision 1, Intermediate Range Neutron Flux Reactor Trip Setpoint Uncertainty Calculations for the AP1000 Plant, July 2017.
3. APP-PMS-M3C-110, Revision 1, Source Range Neutron Flux Reactor Trip Setpoint Uncertainty Calculations for the AP1000 Plant, April 2017.
4. APP-PMS-M3C-124, Revision 1, Overtemperature T and Overpower T Reactor Trip Setpoint Uncertainty Calculations for the AP1000 Plant, February 2018.
5. APP-PMS-M3C-100, Revision 1, Pressurizer Pressure RTS/ESAS Setpoints, and EOP Uncertainty Calculations for AP1000 Plant, March 2017.
6. APP-PMS-M3C-111, Revision 1, Pressurizer Water Level RTS/ESFAS Setpoints, EOP, and PLS Uncertainty Calculations for AP1000 Plant, October 2017.
7. APP-PMS-M3C-112, Revision 1, Reactor Coolant System (RCS) Hot Leg Flow PMS Uncertainty Calculations for the AP1000 Plants, October 2017.
8. APP-PMS-M3C-105, Revision 1, Reactor Coolant Pump Bearing Water Temperature Reactor Trip and ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, March 2017.
9. APP-PMS-M3C-103, Revision 1, Reactor Coolant Pump Speed Reactor Trip Setpoint Calculations for the AP1000 Plant, April 2017.
10. APP-PMS-M3C-113, Revision 1, Steam Generator Narrow Range Water Level RTS/ESFAS Setpoints and EOP Uncertainty Calculations for the AP1000 Plant, October 2017.
11. APP-PMS-M3C-108, Revision 1, Containment Pressure ESFAS and EOP Uncertainty Calculations for the AP1000 Plant, March 2018.
12. APP-PMS-M3C-133, Revision 0, In-Containment Refueling Water Storage Tank (IRWST)

Wide Range Level PMS Uncertainty Calculations for the AP1000 Plants, June 2017.

13. APP-PMS-M3C-101, Revision 2, Main Steam Line Pressure ESFAS Setpoint and EOP Uncertainty Calculations for the AP1000 Plant, April 2017.
14. APP-PMS-M3C-106, Revision 1, Reactor Coolant System Tcold and Tavg ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, July 2017.
15. APP-PMS-M3C-125, Revision 3, Core Makeup Tank Level ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, January 2021.
16. APP-PMS-M3C-102, Revision 3, Reactor Coolant System Wide Range Pressure ESFAS Setpoint and EOP Uncertainty Calculations for the AP1000 Plant, July 2017.
17. APP-PMS-M3C-116, Revision 1, Hot Leg Level Uncertainty Calculations for the AP1000 Plants, April 2017.
18. APP-PMS-M3C-109, Revision 2, Startup Feedwater Flow ESFAS Setpoint Uncertainty Calculations for AP1000 Plant, March 2017.
19. APP-PMS-M3C-118, Revision 1, Steam Generator Wide Range Water Level ESFAS Setpoint and EOP Uncertainty Calculations for AP1000, July 2017.

ND-22-0219: Enclosure 1 Page 14 of 15

Technical Specification Setpoint Report - Unit 3 Page 13 of 13 Rev. 0

20. APP-PMS-M3C-123, Revision 1, Boron Dilution Block - Source Range Flux Doubling Uncertainty Calculations for the AP1000 Plant, May 2017.
21. APP-PMS-M3C-115, Revision 1, Containment Radioactivity ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, June 2017.
22. APP-PMS-M3C-114, Revision 1, Control Room Air Supply Radiation ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, August 2017.
23. APP-PMS-M3C-137, Revision 1, Main Control Room (MCR) Differential Pressure PMS Uncertainty Calculations for the AP1000 Plant, January 2022.
24. APP-PMS-M3C-122, Revision 1, In-Containment Refueling Water Storage Tank (IRWST)

Narrow Range Level PMS Uncertainty Calculations for the AP1000 Plants, May 2017.

25. APP-PMS-M3C-104, Revision 2, Spent Fuel Pool Level PMS Uncertainty Calculations for the AP1000 Plants, April 2017.
26. APP-PMS-E0C-002, Revision 0, Undervoltage Relay Setpoint and Uncertainty Calculation for Class 1E Batter Chargers (DC01), November 2020.

ND-22-0219: Enclosure 1 Page 15 of 15

Southern Nuclear Operating Company ND-22-0219 Vogtle Electric Generating Plant (VEGP) Unit 4 Technical Specifications Setpoint Report (Non-Proprietary)

(This Enclosure consists of 15 pages, including this cover page)

Vogtle Electric Generating Plant (VEGP) Unit 4 Technical Specification Setpoint Report Revision 0 February 2022 ND-22-0219: Enclosure 3 Page 2 of 15

Technical Specification Setpoint Report - Unit 4 Page 1 of 13 Rev. 0

==

Introduction:==

This report documents the current values of the Vogtle Unit 4 Technical Specifications required automatic protection instrumentation function Nominal Trip Setpoint (NTS), As-Left Tolerance (ALT), and As-Found Tolerance (AFT) for sensors and Process Rack and references to the associated calculation documentation.

This Report satisfies the requirement of the Technical Specifications 5.5.14.e, which states the following:

The SP shall establish a document containing the current value of the specified NTS, AFT, and ALT for each Technical Specification required automatic protection instrumentation function and references to the calculation documentation. Changes to this document shall be governed by the regulatory requirement of 10 CFR 50.59. In addition, changes to the specified NTS, AFT, and ALT values shall be governed by the approved setpoint methodology. This document, including any revisions or supplements, shall be provided upon issuance to the NRC.

ND-22-0219: Enclosure 3 Page 3 of 15

Technical Specification Setpoint Report - Unit 4 Page 2 of 13 Rev. 0 Table 1: Technical Specification 3.3.1-1 RTS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 1a.

Power Range Neutron Flux - High 1

118% RTP 1b.

Power Range Neutron Flux - Low 1

25% RTP

2.

Power Range Neutron Flux - High Positive Rate 1

12% RTP

3.

Overtemperature T 4

See Note (3)

4.

Overpower T (limiting case) 4 108.5% RTP (4) 5a.

Pressurizer Pressure - Low 2 5

1955 psig 5b.

Pressurizer Pressure - High 2 5

2405 psig

6.

Pressurizer Water Level - High 3 6

66% level

7.

Reactor Coolant Flow - Low 2 7

90% flow

8.

Reactor Coolant Pump (RCP)

Bearing Water Temperature -

High 2 8

185 °F

9.

Reactor Coolant Pump (RCP)

Speed - Low 2 9

91.0% rated speed

10.

Steam Generator (SG) Narrow Range Water Level - Low 2 10 21% level

11.

SG Narrow Range Water Level -

High 3 10 76% level

12.

Passive Residual Heat Removal Actuation Not Applicable a, c ND-22-0219: Enclosure 3 Page 4 of 15

Technical Specification Setpoint Report - Unit 4 Page 3 of 13 Rev. 0 Table 2: Technical Specification Section 3.3.2 & 3.3.3 RTS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 3.3.2 Source Range Neutron Flux - High 3

1.0 x 105 cps 3.3.3 Intermediate Range Neutron Flux -

High 2

25% RTP Table 3: Technical Specification 3.3.8-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 1a.

Containment Pressure - Low 11 0.1 psig 1b.

Containment Pressure - Low 2

-0.8 psig

2.

Containment Pressure - High 2 5.0 psig

3.

Containment Radioactivity - High 21 2.0 rad/hr

4.

Containment Radioactivity - High 2 100 rad/hr

5.

Pressurizer Pressure - Low 3 5

1855 psig

6.

Pressurizer Water Level - Low 6

20.0% level

7.

Pressurizer Water Level - Low 2 10.0% level

8.

Pressurizer Water Level - High 23% level

9.

Pressurizer Water Level - High 2 55% level

10.

Pressurizer Water Level - High 3 66% level a, c a, c ND-22-0219: Enclosure 3 Page 5 of 15

Technical Specification Setpoint Report - Unit 4 Page 4 of 13 Rev. 0 Table 3: Technical Specification 3.3.8-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

11.

RCS Tcold - Low 2 14 505 °F

12.

Reactor Coolant Average Temperature (Tavg) - Low 14 550 °F

13.

Reactor Coolant Average Temperature (Tavg) - Low 2 525 °F

14.

RCS Wide Range Pressure - Low 16 1200 psig 15 CMT Level - Low 3 15 57.5% span 16 CMT Level - Low 6 15 56.0% span

17.

Source Range Neutron Flux Doubling 20 Factor of 2.2 increase over baseline

18.

IRWST Lower Narrow Range Level - Low 3 24 109.3 ft

19.

Reactor Coolant Pump Bearing Water Temperature - High 2 8

185 °F

20.

SG Narrow Range Water Level -

Low 2 10 21% level

21.

SG Wide Range Water Level -

Low 2 19 35% span a, c ND-22-0219: Enclosure 3 Page 6 of 15

Technical Specification Setpoint Report - Unit 4 Page 5 of 13 Rev. 0 Table 3: Technical Specification 3.3.8-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

22.

SG Narrow Range Water Level -

High 10 66.8% level

23.

SG Narrow Range Water Level -

High 3 76% level

24.

Steam Line Pressure - Low 2 13 560.3 psig

25.

Steam Line Pressure - Negative Rate - High 100 psig Table 4: Technical Specification 3.3.10-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

Hot Leg Level - Low 4 17 9.7% span

2.

Hot Leg Level - Low 2 17 58.1% span Table 5: Technical Specification Section 3.3.11-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT 3.3.11 Startup Feedwater Flow -Low 2 18 200 gpm a, c a, c a, c ND-22-0219: Enclosure 3 Page 7 of 15

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Technical Specification Setpoint Report - Unit 4 Page 6 of 13 Rev. 0 Table 6: Technical Specification 3.3.13-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

Main Control Room Air Supply Iodine or Particulate Radiation Detector - High 2 22 4.86 x 10E-8 Ci/m3 (iodine detector) 5.04 x 10E-9 Ci/m3 (particulate detector)

2.

Main Control Room Differential Pressure - Low 23 0.185 inH2O

3.

Class 1E 24-Hour Battery Charger Undervoltage 26 0.80 p.u Volts Table 7: Technical Specification 3.3.14-1 ESFAS Instrumentation Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

Spent Fuel Pool Level - Low 2 25 23.5 ft

2.

IRWST Wide Range Level - Low 12 23.04 ft Table 8: Technical Specification 3.3.20-1 ADS and IRWST Injection Blocking Device Function Reference NTS Sensor ALT Sensor AFT Rack ALT/AFT

1.

CMT Level for Automatic Unblocking 15 81.3% span a, c a, c a, c ND-22-0219: Enclosure 3 Page 8 of 15

[

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Technical Specification Setpoint Report - Unit 4 Page 7 of 13 Rev. 0 RTS Overtemperature T (OTT) and Overpower T (OPT) Parameters (LCO 3.3.1)

Background Information: Although some time constants are not in use currently (i.e. those set to OFF), all available trip setpoint parameters are included for completeness and to create a template for their potential inclusion later. The rationale for presenting the information this way is that the PMS requires non-zero time constants to avoid an error (7, 8 and 9 for the Overpower T time constants and 13 and 14 for the temperature time constants). In these cases, the time constants are set to [ ]a,c initially simply to avoid the error response, then promptly set to OFF (effectively a [ ]a,c time constant as stated in the Vogtle SCD and assumed in the setpoint methodologies). If these time constants are to be utilized in their associated trip setpoint methods at a later time, the value specified in the SCD would be entered and remain ON in the PMS.

1. OTT The OTT trip setpoint (OTTSP) is defined as follows:

OTTSP = OTTSP° - f1(I) 1.a OTTSP° is the core Departure from Nucleate Boiling (DNB) thermal design limit with design axial power distribution as specified in Table 6.

1.b f1(I) is the OTT Axial Flux Difference (AFD) Penalty Function as specified in Table 7.

1.c The pressurizer pressure time constant [ ]a,c.

1.d The pressurizer pressure time constant [ ]a,c.

1.e The margin to OTT trip time constant [ ]a,c.

1.f The margin to OTT trip time constant [ ]a,c.

1.g The margin to OTT trip time constant [ ]a,c.

2. OPT The OPT trip setpoint (OPTSP) is defined as follows:

OPTSP = COP° - f2(I) 2.a COP° = [ ]a,c 2.b f2(I) is the OPT AFD Penalty Function as specified in Table 8.

2.c The margin to OPT trip time constant [ ]a,c.

2.d The margin to OPT trip time constant [ ]a,c.

2.e The margin to OPT trip time constant [ ]a,c.

Note 1: The initialization values for 7, 8 and 9 shall each be set to [ ]a,c. However, the configuration status for 7, 8 and 9 shall be set to OFF (which results in each time constant equaling [ ]a,c seconds as specified).

7, 8 and 9 Time Constants: The way the 2nd Order Lead/Lag Filter element works is that a code initialization value must be entered because the code will not compile otherwise (even if the filter is turned OFF). The code initialization value chosen is the current low limit; if this value is not low enough, an additional analysis could be performed to challenge the 6x CONTRM time requirement for this low limit value.

ND-22-0219: Enclosure 3 Page 9 of 15

Technical Specification Setpoint Report - Unit 4 Page 8 of 13 Rev. 0

3. The T Power Signal parameter values are:

3.a The Tcold dynamic compensation time constant [ ]a,c.

3.b The Tcold dynamic compensation time constant [ ]a,c.

3.c The Tcold dynamic compensation time constant [ ]a,c.

3.d The Thot dynamic compensation time constant [ ]a,c.

3.e The Thot dynamic compensation time constant [ ]a,c.

3.f The Thot dynamic compensation time constant [ ]a,c.

4. Additional temperature measurement algorithm values are:

4.a The Tcold filter time constant [ ]a,c.

4.b The Thot filter time constant [ ]a,c.

Note 2: The initialization values for 13 and 14 shall both be set to [ ]a,c. However, the configuration status for 13 and 14 shall be set to OFF (which results in both time constants equaling [ ]a,c as specified).

13 and 14 Time Constants: Actual Resistance Temperature Detector (RTD)-thermowell pair response time and filter value must not exceed [ ]a,c, per the Safety Analysis. Also note that the way the Lag Filter element works is that a code initialization value must be entered because the code will not compile otherwise (even if the filter is turned OFF). The code initialization value chosen is the current low limit; if this value is not low enough, an additional analysis could be performed to challenge the 6x CONTRM time requirement for this low limit value.

ND-22-0219: Enclosure 3 Page 10 of 15

Technical Specification Setpoint Report - Unit 4 Page 9 of 13 Rev. 0 Table 11 OTTSP° Function Table 12 f1(I) - OTT AFD Penalty Function a, c a, c ND-22-0219: Enclosure 3 Page 11 of 15

Technical Specification Setpoint Report - Unit 4 Page 10 of 13 Rev. 0 Table 13 f2(I) - OPT AFD Penalty Function Note:

Updating the trip setpoints prior to reaching [ ]a,c would maintain conservative protection and is acceptable.

a, c ND-22-0219: Enclosure 3 Page 12 of 15

Technical Specification Setpoint Report - Unit 4 Page 11 of 13 Rev. 0 Notes:

1) For RTDs that are not shared.
2) For RTDs that are shared.
3) For the Overtemperature T function, the NTS should be [ ]a,c lower than the Safety Analysis Limit (SAL). The SAL can be found in APP-SSAR-F5-001, Revision 1, Table 1.2.3.a.
4) [ ]a,c without the f (I) penalty.
5) The Overtemperature T input cards calibration tolerances should not exceed:

[ ]a,c for TCOLD for tag numbers TE125A1/B1/C1/D1 only,

[ ]a,c for TCOLD for tag numbers TE121A1/B1/C1/D1, TE122A/B/C/D only,

[ ]a,c for THOT,

[ ]a,c for pressure, and

[ ]a,c RTP for I (AC160 input modules)

6) The Overpower T input cards calibration tolerances should not exceed:

[ ]a,c for TCOLD for tag numbers TE125A1/B1/C1/D1 only,

[ ]a,c for TCOLD for tag numbers TE121A1/B1/C1/D1, TE122A/B/C/D only,

[ ]a,c for THOT

[ ]a,c RTP for I (AC160 input modules)

ND-22-0219: Enclosure 3 Page 13 of 15

Technical Specification Setpoint Report - Unit 4 Page 12 of 13 Rev. 0

References:

1. APP-PMS-M3C-117, Revision 1, Power Range Neutron Flux Reactor Trip Setpoint and High Positive Rate Uncertainty Calculations for the AP1000 Plant, October 2017.
2. APP-PMS-M3C-107, Revision 1, Intermediate Range Neutron Flux Reactor Trip Setpoint Uncertainty Calculations for the AP1000 Plant, July 2017.
3. APP-PMS-M3C-110, Revision 1, Source Range Neutron Flux Reactor Trip Setpoint Uncertainty Calculations for the AP1000 Plant, April 2017.
4. APP-PMS-M3C-124, Revision 1, Overtemperature T and Overpower T Reactor Trip Setpoint Uncertainty Calculations for the AP1000 Plant, February 2018.
5. APP-PMS-M3C-100, Revision 1, Pressurizer Pressure RTS/ESAS Setpoints, and EOP Uncertainty Calculations for AP1000 Plant, March 2017.
6. APP-PMS-M3C-111, Revision 1, Pressurizer Water Level RTS/ESFAS Setpoints, EOP, and PLS Uncertainty Calculations for AP1000 Plant, October 2017.
7. APP-PMS-M3C-112, Revision 1, Reactor Coolant System (RCS) Hot Leg Flow PMS Uncertainty Calculations for the AP1000 Plants, October 2017.
8. APP-PMS-M3C-105, Revision 1, Reactor Coolant Pump Bearing Water Temperature Reactor Trip and ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, March 2017.
9. APP-PMS-M3C-103, Revision 1, Reactor Coolant Pump Speed Reactor Trip Setpoint Calculations for the AP1000 Plant, April 2017.
10. APP-PMS-M3C-113, Revision 1, Steam Generator Narrow Range Water Level RTS/ESFAS Setpoints and EOP Uncertainty Calculations for the AP1000 Plant, October 2017.
11. APP-PMS-M3C-108, Revision 1, Containment Pressure ESFAS and EOP Uncertainty Calculations for the AP1000 Plant, March 2018.
12. APP-PMS-M3C-133, Revision 0, In-Containment Refueling Water Storage Tank (IRWST)

Wide Range Level PMS Uncertainty Calculations for the AP1000 Plants, June 2017.

13. APP-PMS-M3C-101, Revision 2, Main Steam Line Pressure ESFAS Setpoint and EOP Uncertainty Calculations for the AP1000 Plant, April 2017.
14. APP-PMS-M3C-106, Revision 1, Reactor Coolant System Tcold and Tavg ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, July 2017.
15. APP-PMS-M3C-125, Revision 3, Core Makeup Tank Level ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, January 2021.
16. APP-PMS-M3C-102, Revision 3, Reactor Coolant System Wide Range Pressure ESFAS Setpoint and EOP Uncertainty Calculations for the AP1000 Plant, July 2017.
17. APP-PMS-M3C-116, Revision 1, Hot Leg Level Uncertainty Calculations for the AP1000 Plants, April 2017.
18. APP-PMS-M3C-109, Revision 2, Startup Feedwater Flow ESFAS Setpoint Uncertainty Calculations for AP1000 Plant, March 2017.
19. APP-PMS-M3C-118, Revision 1, Steam Generator Wide Range Water Level ESFAS Setpoint and EOP Uncertainty Calculations for AP1000, July 2017.

ND-22-0219: Enclosure 3 Page 14 of 15

Technical Specification Setpoint Report - Unit 4 Page 13 of 13 Rev. 0

20. APP-PMS-M3C-123, Revision 1, Boron Dilution Block - Source Range Flux Doubling Uncertainty Calculations for the AP1000 Plant, May 2017.
21. APP-PMS-M3C-115, Revision 1, Containment Radioactivity ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, June 2017.
22. APP-PMS-M3C-114, Revision 1, Control Room Air Supply Radiation ESFAS Setpoint Uncertainty Calculations for the AP1000 Plant, August 2017.
23. APP-PMS-M3C-137, Revision 1, Main Control Room (MCR) Differential Pressure PMS Uncertainty Calculations for the AP1000 Plant, January 2022.
24. APP-PMS-M3C-122, Revision 1, In-Containment Refueling Water Storage Tank (IRWST)

Narrow Range Level PMS Uncertainty Calculations for the AP1000 Plants, May 2017.

25. APP-PMS-M3C-104, Revision 2, Spent Fuel Pool Level PMS Uncertainty Calculations for the AP1000 Plants, April 2017.
26. APP-PMS-E0C-002, Revision 0, Undervoltage Relay Setpoint and Uncertainty Calculation for Class 1E Batter Chargers (DC01), November 2020.

ND-22-0219: Enclosure 3 Page 15 of 15

Southern Nuclear Operating Company ND-22-0219 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 Affidavit from Southern Nuclear Operating Company for Withholding Under 10 CFR 2.390 (This Enclosure consists of 3 pages, including this cover page)

ND-22-0219 Affidavit from Southern Nuclear Operating Company for Withholding Under 10 CFR 2.390 Page 2 of 3 Affidavit of Brian H. Whitley

1. My name is Brian H. Whitley. I am the Regulatory Affairs Director for Southern Nuclear Operating Company (SNC). I have been delegated the function of reviewing proprietary information sought to be withheld from public disclosure and am authorized to apply for its withholding on behalf of SNC.
2. I am making this affidavit on personal knowledge, in conformance with the provisions of 10 CFR Section 2.390 of the Commissions regulations, and as derived from Westinghouse Electric Company documents SV0-PMS-GS-001, Revision 2 and SV0-PMS-GS-002, Revision 0. I have personal knowledge of the criteria and procedures used by SNC to designate information as a trade secret, privileged or as confidential commercial or financial information.
3. Based on the reason(s) at 10 CFR 2.390(a)(4), this affidavit seeks to withhold from public disclosure Enclosures 2 and 4 of SNC letter ND-22-0219 for Vogtle Electric Generating Plant (VEGP) Unit 3 Technical Specification Setpoint Report and Vogtle Electric Generating Plant (VEGP) Unit 4 Technical Specification Setpoint Report, respectively.
4. The following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
a. The information sought to be withheld from public disclosure has been held in confidence by SNC and Westinghouse Electric Company.
b. The information is of a type customarily held in confidence by SNC and Westinghouse Electric Company and not customarily disclosed to the public.

ND-22-0219 Affidavit from Southern Nuclear Operating Company for Withholding Under 1 O CFR 2.390

c. The release of the information might result in the loss of an existing or potential competitive advantage to SNC and/or Westinghouse Electric Company.
d. Other reasons identified in Enclosure 6 of SNC letter ND-22-0219 for Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Westinghouse Application for Withholding Proprietary Information from Public Disclosure CAW-22-010 and accompanying Affidavit, and those reasons are incorporated here by reference.
5. Additionally, release of the information may harm SNC because SNC has a contractual relationship with the Westinghouse Electric Company regarding proprietary information.

SNC is contractually obligated to seek confidential and proprietary treatment of the information.

6. The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.
7. To the best of my knowledge and belief, the information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method.

I declare under penalty of perjury that the foregoing is true and correct.

-""""'£..... ""'....;.~..... u_. M_1

--1!

1 ,..._ _________ Executed on *8111/i.l..,.

~

Brian H. Whitley Date Page 3 of 3

Southern Nuclear Operating Company ND-22-0219 Vogtle Electric Generating Plant (VEGP) Units 3 and 4 CAW-22-010 (This Enclosure consists of 4 pages, including this cover page)

      • This record was final approved on 3/21/2022, 8:47:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-22-010 Page 1 of 3 Commonwealth of Pennsylvania:

County of Butler:

(1)

I, Zachary Harper, Manager, Licensing Engineering, have been specifically delegated and authorized to apply for withholding and execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse).

(2)

I am requesting the proprietary portions of VEGP Unit 3 Technical Specification Setpoint Report and VEGP Unit 4 Technical Specification Setpoint Report be withheld from public disclosure under 10 CFR 2.390.

(3)

I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged, or as confidential commercial or financial information.

(4)

Pursuant to 10 CFR 2.390, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.

(i)

The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse and is not customarily disclosed to the public.

(ii)

The information sought to be withheld is being transmitted to the Commission in confidence and, to Westinghouses knowledge, is not available in public sources.

(iii)

Westinghouse notes that a showing of substantial harm is no longer an applicable criterion for analyzing whether a document should be withheld from public disclosure. Nevertheless, public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

      • This record was final approved on 3/21/2022, 4:34:44 PM. (This statement was added by the PRIME system upon its validation)

ND-22-0219: Enclosure 6 Page 2 of 4

      • This record was final approved on 3/21/2022, 8:47:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-22-010 Page 2 of 3 (5)

Westinghouse has policies in place to identify proprietary information. Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:

(a)

The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

(b)

It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage (e.g., by optimization or improved marketability).

(c)

Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d)

It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(e)

It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f)

It contains patentable ideas, for which patent protection may be desirable.

(6)

The attached documents are bracketed and marked to indicate the bases for withholding. The justification for withholding is indicated in both versions by means of lower-case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower-case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (5)(a) through (f) of this Affidavit.

      • This record was final approved on 3/21/2022, 4:34:44 PM. (This statement was added by the PRIME system upon its validation)

ND-22-0219: Enclosure 6 Page 3 of 4

      • This record was final approved on 3/21/2022, 8:47:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-22-010 Page 3 of 3 I declare that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief. I declare under penalty of perjury that the foregoing is true and correct.

Executed on: 3/21/2022 Signed electronically by Zachary Harper Executed on: 3/21/2022 Signed electronically by

      • This record was final approved on 3/21/2022, 4:34:44 PM. (This statement was added by the PRIME system upon its validation)

ND-22-0219: Enclosure 6 Page 4 of 4