ND-21-1034, ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)

ML22151A332
Person / Time
Site:	Vogtle
Issue date:	05/31/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-1034
Download: ML22151A332 (19)

Text

Jamie M. Coleman 7825 River Road

.,, Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel MAY 3 1 2022

Docket No.: 52-025

ND-21-1034 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i [Index Number 165)

Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1 ), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (IT AAC) Item 2.2.03.05a.i [Index Number 165) to demonstrate that the Passive Core Cooling System (PXS) components identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2.2.3-1 are designed and constructed in accordance with applicable requirements.

The closure process for this ITAAC is based on the guidance described in NEI 08 - 01, "Industry Guideline for the ITAAC Closure Process Under 1 O CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Sou thern Nuclear Op erating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 1 O CFR 52.99.

If there are any questions, please conta ct Kelli Roberts at 706-848-6991.

Respectfully submitted,

~em~ ~

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.05a.i [Index Number 165)

JMC /LBP/sfr U.S. Nuclear Regulatory Commission ND-21-1034 Page 2 of 3

To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J. M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Ch amberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06

Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall U.S. Nuclear Regulatory Commission ND-21-1034 Page 3 of 3

Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

Dalton Utilities Mr. T. Bundros

Westinghouse Electric Company, LLC Dr. L. O riani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack

Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph. D., GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 1 of 16

Southern Nuclear Operating Company ND-21-1034 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.0Sa.i [Index Number 165]

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 2 of 16

IT AAC Statement

Design Commitment:

5.a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design basis loads without loss of safety function.

7.a) The Class 1 E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

Inspections, Tests, Analyses:

i) Inspection will be performed to verify that the seismic Category I equipment and valves identified in Table 2.2.3-1 are located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type tests and analyses of seismic Category I equipment will be performed.

iii) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

i) Type tests, analyses, or a combination of type tests and analyses will be performed on Class 1 E equipment located in a harsh environment.

ii) Inspection will be performed of the as-built Class 1 E equipment and the associated wiring, cables, and terminations located in a harsh environment.

Acceptance Criteria:

i) The seismic Category I equipment identified in Table 2.2.3-1 is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.

iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the as-built screens including their anchorage are bounded by the seismic loads and also post-accident operating loads, including head loss and debris weights.

i) A report exists and concludes that the Class 1 E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 3 of 16

ii) A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

ITAAC Determination Basis

This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Passive Core Cooling System (PXS) equipment identified as seismic Category I or Class 1 E in the Combined License (COL) Appendix C, Table 2.2.3-1 (the Table) is designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment identified in Table 2.2.3-1 is located on the Nuclear Island.

To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ) ITAAC As-built Walkdown Guideline and the EO ITAAC As-built Installation Documentation Guideline (References 1 and 2), an inspection was conducted of the PXS to confirm the satisfactory installation of the seismically qualified equipment. The inspection included verification of equipment make / model / serial number and verification of equipment location (Building, Elevation, Room). The EO As-Built Reconciliation Reports (EORR) (Reference 3) identified in Attachment A documented the results of the inspection and concluded that the seismic Category I equipment is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.

Seismic Category I equipment in the Table requires type tests and / or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves, as well as other passive seismic Category I mechanical equipment, is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section Ill (Reference 4). Functionality of the subset of active safety-related valves under seismic loads was determined using the guidance of ASME OME-1-2007 (Reference 5). Structural integrity of the in-containment refueling water storage tank (IRWST) was demonstrated by analysis in accordance with American Concrete Institute (ACI) Standard 349-01 (Reference 6) and American Institute of Steel Construction (AISC) Specification N690 (Reference 7). Structural integrity of the pH adjustment baskets was demonstrated by analysis in accordance with AISC Specification N690 (Reference 7).

Safety-related (Class 1 E) electrical equipment in the Table was seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 8). This equipment includes safety-related (Class 1 E) field sensors and the safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in the Table is identified in Attachment A. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the Updated Final Safety U.S. Nuclear Regulatory Commission N D-21-1034 Enclosure Page 4 of 16

Analysis Report (UFSAR) Appendix 3D (Reference 9). The EQ Reports (Reference 1 0) identified in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.

iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the as-built screens including their anchorage are bounded by the seismic loads and also post-accident operating loads, including head loss and debris weights.

An inspection (References 1 and 2) was conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verified the equipment make / model / serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and / or sketches/ drawings of equipment/mounting / interfaces.

As part of the seismic qualification program, consideration is given to the definition of the clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety related equipment. When required, seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (Reference 10) identified the equipment mounting employed for qualification and established interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification. Interface requirements are defined based on the test configuration and other design requirements.

Attachment A identifies the EQRR (Reference 3) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 8), and NRC Regulatory Guide (RG) 1.100 (Reference 11 ). For the PXS containment recirculation and IRWST screens, the as-built screens including their anchorage are bounded by the se ismic loads and also post-accident operating loads, including head loss and debris weights.

i) A report exists and concludes that the Class 1 E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

The harsh env ironment Class 1 E equipment in the Table is qualified by type testing and / or analyses. Class 1 E electrical equipment type testing was performed in accordance with IEEE Standard 323-197 4 (Reference 12) and RG 1.89 (Reference 13) to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 1 0 CFR Part 50, Appendix A, General Design Criterion 4. Attachment A identifies the EQ program and specific qualification method for each piece of safety-related mechanical or Class 1 E electrical equipment located in a harsh environment. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 9).

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 5 of 16

EQ Reports (Reference 10) identified in Attachment A contain applicable test reports and associated documentation and concluded that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

ii) A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

An inspection (Reference 1 and 2) was conducted of the PXS to confirm the satisfactory installation of the Class 1 E equipment in the Table. The inspection verified the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirmed that the environmental conditions for the zone (Attachment A) in which the equipment is mounted are bounded by the tested and/or analyzed conditions. It also documented the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 3) identified in Attachment A documents this inspection and concluded that the as-built harsh environment Class 1 E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 12).

Together, these reports (References 3 and 10) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2.2.3-1 is located on the Nuclear Island;

• A report exists and concludes that the seismic Category I equipment can withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights;

• A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the as-built screens including their anchorage are bounded by the seismic loads and also post-accident operating loads, including head loss and debris weights;

• A report exists and concludes that the Class 1 E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and

• A report exists and concludes that the as-built Class 1 E equipment and the associated wiring, cables, and terminations identified in Table 2.2.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

U.S. Nuclear Regulatory Commission ND-21-1034 Enclosure Page 6 of 16

References 3 and 10 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.03.05a.i Completion Package (References 14).

ITAAC Finding Review

In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 166, 167, 170, and 171, found the following closed notice of non-conformance (NON) associated with this ITAAC:

1) NON 99901441 / 2014-201-03 (Closed-ML14307A578)

2) NON 99901431 / 2013-201-01 (Closed-ML14091A361)

3) NON 99901377 / 2012-201-02 (Closed - ML16357A724)

4) NON 99901377/2012-201-03 (Closed - ML16357A724)

5) NON 99900 404 / 2012-201-01 (Closed-ML16307A159)

6) NON 99900 4 04/ 2012-201-02 (Closed - ML12313A461)

7) NON 99900 404/ 2012-201-03 (Closed - ML12313A461)

The corrective actions for these findings have been completed and the findings are closed. The IT AAC completion review is documented in the IT AAC Completion Package for IT AAC 2.2.03.05a.i (Reference 14) and is available for NRC review.

IT AAC Completion Statement

Based on the above information, SNC hereby notifies the NRC tha t ITAAC 2.2.03.05a.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordan ce with the approved plant programs and procedures.

References (available for NRC inspection)

1. ND-RA-001-014, EQ ITAAC As-built Walkdown Guideline, Version 3.1

2. ND-RA-001-016, EQ ITAAC As-built Installation Documentation Guideline, Version 1.0

3. EQ As-Bu ilt Reconciliation Reports (EQRR) as identified in Attachment A

4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code, Section Ill, " Rules for Construction of Nuclear Power Plant Components," 1998 Edition w ith 2000 Addenda U.S. Nuclear Regulatory Comm ission ND-21-1034 Enclosure Page 7 of 16

5. ASME QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007

6. American Concrete Institute (ACI) Standard 349 - 01, "Code Requirements for Nuclear Safety Related Concrete Structures," 2001.

7. American National Standards Institute (ANSI)/ American Institute of Steel Construction (AISC) N690-1994, "Specification for the Design, Fabrication and Erection of Safety-Related Steel Structures for Nuclear Facilities"

8. IEEE Standard 344-1987, " IEEE Recommended Practices for Seismic Qualification of Class 1 E Equipment for Nuclear Powe r Generating Stations"

9. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 30, "Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment "

10. Equipment Qualification (EQ) Reports as identified in Attachment A

11. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equ ipment for Nuclear Powe r Plants"

12. IEEE Standard 323-197 4, "IEEE Standard for Qualifying Class 1 E Equipment for Nuclear Power Generating Stations"

13. Reg ulatory Gu ide 1.89, Rev 1, " Environmental Qua lification of Certain Electric Equipment Important to Safety for Nuclear Power Plants"

14. 2.2.03.05a.i-U3-CP-Rev0, "Completion Package for Unit 3 ITAAC 2.2.03.05a.i [Index Number 165]"

EQRR -U3-EQRR-

.i-U3-EORR.i-U3-EORR.i-U3-EQRR PCD003 PCO003 PCD003 PCD003.05a PCD003.05a PCD003 PCD002 PCD002 PCD002 PCD002 PCD002 PCD002 PCD002 PCD002 As-Built 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i 2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-1 1

-VDR-00 Reports 00-GCR-001 EQ SV3-ME02-Z0R-001 SV3-MT02-Z0R-102 SV3-MT02-Z0R-102 SV3-MT01-Z0R-101 SV3-MT01-Z0R-101 SV3-11 SV3-MY03 SV3-MY03-VDR-001 SV3-MY03-VDR-001 SV3-MY03-VDR-00 SV3-MY03-VDR-001 APP-MY0?-Z0C-002 APP-MY0?-Z0C-002 APP-MY0?-Z0C-002

of

Type Qual. Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis

System 2

A Qual Cooling N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Envir Program Core 1

Envir. Zone N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Attachment Passive 1 E/ 3 +

Harsh -I - -I - -I - -I - -I - -I - -I - -I - -I - -I - -I - -I - -I - -I -

System: Class Qual. Envir.

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

B B 1 C 03 No.+ -MT-Tag -MY-Y03A PXS-ME-01 PXS-MT-01A PXS-MT-01 PXS-MT-02A PXS-MT-02B PXS PXS-MY-Y01A PXS-MY-Y01 PXS-MY-Y0 PXS-MY-Y02A PXS-MY-Y02B PXS PXS-MY-Y03B PXS-MY-Y04A Commission e 3A 3B 4A Heat A B (CMT)

Regulatory Enclosur Name+ Exchanger Tank A B C Basket Basket Basket 16 Tank Tank Recirculation Recirculation 8 of Residual Heat HX) Screen Screen Screen A B Makeup U.S. Nuclear ND-21-1034 Page Equipment Adjustment Adjustment Adjustment Passive Removal PRHR Accumulator ~ccumulator Core A CMTB IRWST I RWST IRWST I RWST Containment Screen Containment Screen pH pH pH

EQRR -U3-EQRR-

.i-U3-EQRR-.i-U3-EQRR-PCD002 PCD002.05a.i-U3-EQRR-PCD002 PCD002 PCD002 PCD002 PCD002 PCD002 PCD002.05a.i-U3-EQRR-PCD001 PCD001 PCD001 As-Built 2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a.i-U3-EQRR-2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i 2.2.03.05a.i-U3-EQRR 2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-

/ / /

BR-001

-V Reports EQ

APP-MY0?-Z0C-002 APP-MY02-Z0C-001 APP-MY02-Z0C-001 APP-MY02-Z0C-001 APP-MY02-Z0C-001 APP-MY02-Z0C-001 APP-MY02-Z0C-001 APP-MY02-Z0C-001 APP-MY02-Z0C-001 SV3-PV01-VBR-012 SV3-PV01-VBR-011 SV3-PV01-VBR-012 SV3-PV01-VBR-011 SV3-PV14-VBR-002 SV3-PV14

of & & &

Type Qual. Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Analysis Type Analysis Type Analysis Type Analysis Testing Testing Testing System 2

A Qual *ES *ES *ES Cooling N/A N/A N/A N/A N/A N/A N/A N/A N/A M M Envir Program M

1 Core A 1 1 1 Envir. Zone N/A N/ N/A N/A N/A N/A N/A N/A N/A Attachment Passive 3 1E/ +

Harsh -I - -I - -I - -I - -I - -I - -I - -I - -I -

System: Class Qual. Envir. Yes/Yes Yes/Yes Yes/Yes

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

No.+

Tag -PL-V002B Commission PXS-MY-Y04B PXS-MY-Y81 PXS-MY-Y82 PXS-MY-Y83 PXS-MY-Y84 PXS-MY-Y85 PXS-MY-Y86 PXS-MY-Y87 PXS-MY-Y88 PXS-PL-V002A PXS PXS-PL-V014A

+ 4B 1 A 1 B 1 C 1 D 2A 2B 2C 2D Regulatory Enclosure Name Basket Valve Valve 16 Screen Screen Screen Screen Screen Screen Screen Isolation Isolation Nuclear 9 of Inlet Discharge Valve Adjustment A B Inlet A U.S. ND-21-1034 Page Equipment pH Downspout Downspout Downspout Screen Downspout Downspout Downspout Downspout Downspout CMT Motor-operated CMT Motor-operated CMT Isolation EQRR

.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR-PCD001 PCD001.05a PCD001 PCD001 PCD001 PCD001 PCD001 PCD001.05a.i-U3-EQRR-PCD001 PCD001 PCD001 As-Built.03.05a.03.05a.i-U3-EQRR-.03.05a 2.2.03.05a 2.2 2.2.03 2.2 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a 2.2

/ / / / / / / / / / /

-002 -002

Reports -VBR-002

EQ SV3-PV14-VBR SV3-PV14-VBR-001 SV3-PV14-VBR-002 SV3-PV14-VBR-001 SV3-PV14-VBR SV3-PV14-VBR-001 SV3-PV03-VBR-004 SV3-PV03-VBR-003 SV3-PV03-VBR-004 SV3-PV03-VBR-003 SV3-PV03-VBR-004 SV3-PV03-VBR-003 SV3-PV03-VBR-004 SV3-PV03-VBR-003 SV3-PV16-VBR-002 SV3-PV16-VBR-001 SV3-PV16 SV3-PV16-VBR-001 SV3-PV01-VBR-012 SV3-PV01-VBR-011 SV3-PV01-VBR-012 SV3-PV01-VBR-011

of & & & & & & &

Type Qual. Type Analysis Type Analysis Type Analysis Analysis Analysis Analysis Analysis Type Analysis Type Analysis Type Analysis Type Analysis Testing Testing Testing Testing Testing Testing Testing System al 2 Qu m A *ES *ES *ES N/A N/A N/A N/A N/A N/A N/A N/A Cooling Progra M M M Envir Core 1 1 1 1 A Attachment Envir. Zone N/A N/A N/A N/A N/ N/A N/A N/A

Passive rsh 3 +

1E/ Ha em: -I - -I - -I - -I - -I - -I - -I - -I -

Syst Class Qual. Envir. Yes/Yes Yes/Yes Yes/Yes

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

sion No.+ -V022B

Tag Commis PXS-PL-V014B PXS-PL-V015A PXS-PL-V015B PXS-PL-V016A PXS-PL-V016B PXS-PL-V017A PXS-PL-V017B PXS-PL-V022A PXS-PL PXS-PL-V027A PXS-PL-V027B

+ arge Check Check Check Check essure Regulatory Enclosure 16 Name Pressure Pr Discharge Disch A B A B of Valve Valve Valve Valve Valve Nuclear 10 Discharge Discharge Discharge Valve Valve Equipment B Discharge A B Discharge A B Discharge A B Discharge U.S. ND-21-1034 Page CMT Isolation CMT Isolation CMT Isolation CMT Valve CMT Valve CMT Valve CMT Valve Accumulator Relief !Accumulator Relief Accumulator Isolation !Accumulator Isolation

-EQRR EQRR

.i-U3-EQRR-.i-U3-EQRR-.i-U3.i-U3-EQRR-.i-U3-EQRR-PCD001 PCD001 PCD001 PCD001.05a.i-U3-EQRR-PCD001 PCD001.05a.i-U3-EQRR-PCD001 PCD001 PCD001 PCD001 PCD001 As-Built 2.2.03.05a 2.2.03.05a 2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a.i-U3-EQRR-2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03.05a

/ / / / / / / / / 1 / /

Reports EQ -PV03-VBR-014 SV3-PV03-VBR-014 SV3-PV03-VBR-013 SV3-PV03-VBR-014 SV3-PV03-VBR-013 SV3-PV03-VBR-014 SV3-PV03-VBR-013 SV3 SV3-PV03-VBR-013 SV3-PV14-VBR-002 SV3-PV14-VBR-001 SV3-PV02-VBR-016 SV3-PV02-VBR-015 SV3-PV01-VBR-012 SV3-PV01-VBR-011 SV3-PV20-VBR-002 SV3-PV20-VBR-001 SV3-PV20-VBR-002 SV3-PV20-VBR-00 SV3-PV01-VBR-012 SV3-PV01-VBR-011 SV3-PV01-VBR-012 SV3-PV01-VBR-011

of & & & & & &

lysis Type Qual. Ana Analysis Analysis Analysis Type Analysis Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Testing Testing Testing Testing Testing Testing System 2

A Qual *ES *ES *ES *ES *ES Cooling N/A N/A N/A N/A N/A N/A M M M M M Envir Program Core 1 N/A N/A N/A N/A N/A N/A 1 1 1 1 1 Attachment Envir. Zone Passive 1 E/ 3 +

Harsh -I - -I - -I - -I - -I -

System: Class Envir. Yes/No Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Qual.

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

+ OBA

No.

Tag PXS-PL-V042 PXS-PL-V043 PXS-PL-V101 Commission PXS-PL-V028A PXS-PL-V028B PXS-PL-V029A PXS-PL-V029B PXS-PL-V1 PXS-PL-V1088 PXS-PL-V117A PXS-PL-V117B

+ arge n ation Valve Valve Regulatory Enclosure Name Discharge Discharge Disch Discharge Isol Valve 16 A B A B Isolatio Isolation Recirculation Recirculation of Supply Supply Inlet Control Control Motor-operated ent Motor-operated 11 Valve Valve ator Valve Valve Valve HX HX HX Nuclear U.S. ND-21-1034 Page Equipment Isolation Isolation lAccumulator Check lAccumulator Check Accumul Check Accumulator Check Nitrogen Containment Valve Nitrogen Containment Check PRHR Motor-operated PRHR PRHR Containment A Valve Containm B Valve

lt EQRR.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR -U3-EQRR.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR-

.05a PCD001 PCD001.05a PCD001 PCD001.05a PCD001.05a.i-U3-EQRR-PCD001.05a.i-U3-EQRR-PCD001 PCD001.05a.i-U3-EQRR-PCD001 PCD001 PCD001 As-Bui.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a 2.2.03 2.2.03.05a.i 2.2.03 2.2.03 2.2.03 2.2.03.05a 2.2.03 2.2 2.2.03.05a

/ / / 4 / / / 4 / / / / /

-002 -013

-VBR-014 -VBR-01 -VBR-013 Reports EQ SV3-PV70-VBR-003 SV3-PV70-VBR SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV03 SV3-PV03-VBR-013 SV3-PV03 SV3-PV03-VBR-013 SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV03-VBR-01 SV3-PV03-VBR-013 SV3-PV03-VBR-014 SV3-PV03-VBR SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV03-VBR-014 SV3-PV03

of e & & & & & &

Type Qual. Typ Analysis Type Analysis Analysis Analysis Type Analysis Type Analysis Analysis Analysis Type Analysis Type Analysis Analysis Testing Testing Testing Testing Testing Testing System 2

A Qual *ES *ES *ES *ES *ES *ES Cooling M M N/A N/A M M N/A N/A N/A Envir Program M M

1 e Core ir. 1 1 1 1 1 1 Env Zone N/A N/A N/A N/A N/A Attachment h

3 + s Hars es em: Passiv ss 1 E/ /Y -I - -I - -I - -I - -I -

Syst Cla Qual. Envir. Yes/Ye Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

ion No.+ -V118A -V118B -V119A

Tag -PL -PL -PL-V120B

Commiss PXS PXS-PL PXS PXS-PL-V119B PXS-PL-V120A PXS PXS-PL-V122A PXS-PL-V122B PXS-PL-V123A PXS-PL-V123B PXS-PL-V124A

+ ion eck ation culation Squib B Squib Regulatory Enclosure Name A Check B Ch A A Check 16 Recircul Recirculation Recirculation Recir Recirculation Recirculat of Valve Valve Nuclear 12 Valve Valve Valve Valve Injection Injection Injection Injection Injection

U.S. ND-21-1034 Page Equipment Squib Squib Containment A Containment B Squib Containment A Check Containment B Check Containment IA Containment B Squib IRWST Valve IRWST Valve IRWST Valve IRWST Valve IRWST Valve EQRR -U3-EORR- -U3-EQRR-

.i-U3-EQRR-.i-U3-EORR-.i-U3-EQRR-.i-U3-EORR-PCD001 PCD001 PCD001 PCD001 PCD001.05a.i-U3-EQRR-PCD004 PCD004.05a.i-U3-EQRR-PCD004 PCD004.05a PCD004 As-Built.03.05a.i.03.05a.i-U3-EQRR-.03 2.2.03.05a.i 2.2 2.2 2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a 2.2.03 2.2.03.05a 2.2

/ / / / / / / / / /

Reports 0-VBR-003 0-VBR-004 0-VBR-003 0-VBR-004

EQ -JE61-VBR-001

SV3-PV03-VBR-014 SV3-PV03-VBR-013 SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV70-VBR-003 SV3-PV70-VBR-002 SV3-PV1 SV3-PV1 SV3-PV1 SV3-PV1 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001

of & & & & & & & & &

Type Qual. Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Testing Testing Testing Testing Testing Testing Testing Testing Testing System 2

A Qual *ES *ES *ES *ES Cooling N/A M M M M E*S E*S E*S E*S E*S Envir Program Core 1 N/A 1 1 1 1 1 1 1 1 1 Attachment Envir. Zone Passive 3 +

1 E/ Harsh em: -I -

Syst Class Qual. Envir. Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

B C D No.+ -V124B -V125A -V125B -011A Tag -PL-V130A PXS PXS-011 PXS-011 PXS-011 PXS-012A

Commission PXS-PL PXS-PL PXS-PL PXS PXS-PL-V130B

+

B Check Squib B Squib Regulatory Enclosure Name A Isolation Isolation 16 Sensor Sensor Sensor Sensor Sensor 034 of ection Nuclear 13 Injection Inj Injection Gutter Gutter Level Level Level Level Equipment A A A A B Level U.S. N 0-21-1 Page IRWST Valve IRWST Valve IRWST Valve IRWST Valve IRWST Valve CMT CMT CMT CMT CMT EQRR

.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR-.i-U3-EQRR-PCO004 PCD004 PCD004 PCO004 PCD004 PCD004 PCD004 PCD004 PCD004 As-Built 2.2.03.05a.i-U3-EQRR-2.2.03.05a 2.2.03.05a 2.2.03.05a 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EORR-2.2.03.05a 2.2.03.05a.i-U3-EQRR-

/ / / / / / / / /

Reports EQ -JE61-VBR-001

SV3-JE61-VBR-002 SV3 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001

of & & & & & & & & &

Type Qual. Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Testing Testing Testing Testing Testing Testing Testing Testing Testing System 2 A Qual Cooling E*S E*S E*S E*S E*S E*S E*S E*S E*S Envir Program Core 1 1 1 1 1 1 1 1 1 1 Attachment Envir. Zone Passive 3 1 E/ +

Harsh System: Class Envir. Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Qual.

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

No.+

Tag PXS-012B PXS-012C PXS-012O PXS-013A PXS-013B PXS-013C PXS-013O PXS-014A PXS-014B Commission

+

Regulatory Enclosure Name Sensor Sensor Sensor Sensor Sensor Sensor Sensor Sensor Sensor 16 of Nuclear 14 Level Level Level Level Level Level Level Equipment B B Level B A A A B Level B U.S. ND-21-1034 Page GMT GMT GMT GMT GMT GMT GMT A GMT GMT

-EQRR-t EQRR.i-U3-EQRR- -U3-EQRR-.i-U3-EQRR-

.05a.i-U3-EQRR-PCD004 PCD004 PCD004 PCD004 PCD004 PCD004 PCD004 PCD004 PCD004 As-Buil.03.05a 2.2.03 2.2 2.2.03.05a.i 2.2.03.05a.i-U3-EQRR 2.2.03.05a.i-U3-EQRR 2.2.03.05a.i-U3-EQRR 2.2.03.05a.i-U3 2.2.03.05a.i-U3-EQRR-2.2.03.05a

/ / / / / / / / /

R-003

Reports -VBR-002 E52-VBR-003 E52-VB EQ SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE52-VBR-002 SV3-JE52-VBR-001 SV3-JE52-VBR-002 SV3-JE52-VBR-001 SV3-JE52 SV3-JE52-VBR-001 SV3-JE52-VBR-004 SV3-J SV3-JE52-VBR-004 SV3-J SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE61-VBR-002 SV3-JE61-VBR-001

of & & & & & & & & &

Type Qual. Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Type Analysis Testing Testing Testing Testing Testing Testing Testing Testing Testing System 2

A Qual Cooling E*S E*S E*S E*S E*S E*S E*S E*S E*S Envir Program Core 1 e 1 1 1 1 1 1 1 1 1 Attachment Envir. Zon Passive 3 1 E/ +

em: Harsh Syst Class Envir. Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Yes/Yes Qual.

3 I+

Yes Yes Yes Yes Yes Yes Yes Yes Yes Seismic Cat.

No.+ -049A

Tag PXS-014C PXS-014D PXS-046 PXS-047 PXS-048 PXS PXS-049B PXS-050 PXS-051 Commission

+ Level Level Level

-up Regulatory Enclosure Name Sensor Sensor 16 Sensor Sensor Range Range Range Flood Flood-up of Flow Flow Nuclear 15 Level Level Wide Wide Wide HX HX Sensor Sensor B B U.S. ND-21-1034 Page Equipment CMT CMT IRWST Sensor IRWST Sensor I RWST Sensor PRHR PRHR Containment Level Containment Level ilt EQRR -U3-EQRR-

PCD004 PCD004 PCD004 PCD004.05a.i-U3-EQRR-PCD004 PCD001 As-Bu 2.2.03.05a.i 2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03.05a.i-U3-EQRR-2.2.03 2.2.03.05a.i-U3-EQRR-

/ / / / / /

-002

Reports EQ SV3-JE61-VBR-002 SV3-JE61-VBR-001 SV3-JE52-VBR SV3-JE52-VBR-001 SV3-JE52-VBR-002 SV3-JE52-VBR-001 SV3-JE52-VBR-002 SV3-JE52-VBR-001 SV3-JE52-VBR-002 SV3-JE52-VBR-001 SV3-PV17-VBR-004 SV3-PV17-VBR-003 operator)

of & & & & &

Type Qual. Type Testing Analysis Type Testing Analysis Type Testing Analysis Type Testing Analysis Type Testing Analysis Analysis r, solenoid

2 g System A Qual *S *S *S *S operato Coolin E E E E*S E N/A Envir Program, squib 1

e Core 1 1 1 1 1 N/A Attachment Envir. Zone operator

3 +

1 E/ Harsh em: Passiv s/Yes -I -

Syst Class Qual. Envir. Ye Yes/Yes Yes/Yes Yes/Yes Yes/Yes the motor and spray 3

I+ with Yes Yes Yes Yes Yes Yes switch Seismic Cat..3-1 (valve)

(limit operation sion No.+ or Table 2.2 Program Tag PXS-052 PXS-066 PXS-067 PXS-068 PXS-069 C Program

Commis PXS-PL-V208A UFSAR applicable of not

+ Appendix Equipment submergence row Test.5-1 Equipment for Regulatory Enclosure Name Nar Narrow Narrow Narrow COL 3D Environment 16 Flood-up Sensor Sensor Sensor Sensor Leak indicates of from Table (-)

Nuclear 16 Sensor Lower Level Lower Level Lower Level Lower Level -Mechanical Equipment Suction See E -Electrical M S = Qualified * -Harsh Dash U.S. ND-21-1034 Page Containment Level I RWST Range IRWST Range IRWST Range I RWST Range RNS Valve Notes: + Excerpt 1. 2. 3.