ND-21-1021, ITAAC Closure Notification on Completion of ITAAC Item 2.2.04.05a.i (Index Number 226)

ITAAC Closure Notification on Completion of ITAAC Item 2.2.04.05a.i (Index Number 226)

ML22097A265
Person / Time
Site:	Vogtle
Issue date:	04/08/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-1021
Download: ML22097A265 (16)

Text

Jamie Wl. Coleman 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6926 tel Docket Nos.;52-025 ND-21-1021 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 Item 2.2.04.05a.i Rndex Number 2261 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 (ITAAC) Item 2.2.04.05a.i [Index Number 226] to demonstrate that the Steam Generator System (SGS) equipment identified as seismic Category I or Class IE in the Combined License (COL) Appendix C, Table 2.2.4-1 is 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 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company(SNC) requests NRC staff confirmation of this determination and publication of the required noticein the Federal Register per 10 CFR 52.99.

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

Respectfully submitted, A

'TN' Jamie M. Coleman'-

Regulatory Affairs Director Vogtle 3 & 4 Enclosure; Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.04.05a.i [Index Number 226]

JMC/BSZ/sfr

U.S. Nuclear Regulatory Commission ND-21-1021 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena II I Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox 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. Chamberlain 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. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-21-1021 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. Oriani 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., CDS 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, Batch Bingham

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-21-1021 Enclosure Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.04.05a.i [Index Number 226]

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 2 of 13 ITAAC Statement Design Commitment:

5.a) The seismic Category I equipment identified in Table 2.2.4-1 can withstand seismic design basis loads without loss of safety function.

7.a) The Class 1E equipment identified in Table 2.2.4-1 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 identified in Table 2.2.4-1 Is 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.

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

Acceptance Criteria:

i) The seismic Category I equipment identified in Table 2.2.4-1 is located on the Nuclear Island, ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function, iii) A report exists and concludes that the as-bullt equipment including anchorage is seismically bounded by the tested or analyzed conditions, i) A report exists and concludes that the Class 1E equipment identified in Table 2.2.4-1 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, ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 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-21-1021 Enclosure Page 3 of 13 ITAAC Determination Basis This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Steam Generator System (SGS) equipment identified as seismic Category I or Class IE in the Combined License (COL) Appendix C, Table 2.2.4-1 (the Table) is designed and constructed in accordance with applicable requirements, i) The seismic Category I equipment identified in Table 2.2.4-1 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 Waikdown Guideline and EQ ITAAC As-built Installation Documentation Guideline (References 1 and 2), an inspection was conducted of the SGS to confirm the satisfactory installation of the seismically qualified equipment. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room).

The EQ As-Built Reconciliation Reports(EQRR)(Reference 3) identified in Attachment A document the results of the inspection and conclude 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 loads without loss of safety function.

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 is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 4). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007(Reference 5).

Safety-related (Class IE) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 6). This equipment includes safety-related (Class 1E)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 API000 safety-related equipment is provided in the Updated Final Safety Analysis Report(UFSAR) Appendix 3D (Reference 7). The EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function, iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

An inspection (References 1 and 2) was conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verifies 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

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 4 of 13 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 8) identify the equipment mounting employed for qualification and establish 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, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 6), and NRC Regulatory Guide (RG) 1.100 (Reference 9).

i) A report exists and concludes that the Class 1E equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and followinq a design basis accident without loss of safety function for the time required to perform the safety function.

The harsh environment Class 1E equipment in the Table was qualified by type testing and/or analyses. Class 1E electrical equipment type testing is performed in accordance with IEEE Standard 323-1974 (Reference 10) and RG 1.89 (Reference 11) to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment A identifies the EQ program and specific qualification method for each safety-related mechanical or Class 1E electrical equipment located in a harsh environment. Additional information about the methods used to qualify API 000 safety-related equipment is provided in the UFSAR Appendix 3D (Reference 7).

EQ Reports (Reference 8) identified in Attachment A contain applicable test reports and associated documentation and conclude 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 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

An inspection (References 1 and 2) was conducted of the SGS to confirm the satisfactory installation of the Class 1E equipment in the Table. The inspection verifies the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations, and confirms 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 documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 3) identified in Attachment A document this inspection, and conclude that the as-built harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 10).

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 5 of 13 Together, these reports (References 3 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:

The seismic Category I equipment identified in Table 2.2.4-1 is located on the Nuclear Island; A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions; A report exists and concludes that the Class 1E equipment identified in Table 2.2.4-1 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 1E equipment and the associated wiring, cables, and terminations identified in Table 2.2.4-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

References 3 and 8 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.04.05a.i Completion Packages (Reference 12).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 227, 228, 231, and 232, found the following relevant ITAAC findings associated with this ITAAC:

1) Non-Cited Violation (NCV)05200025/2021005-03 (Closed- ML22045A005)

The corrective actions for this finding has been completed and the finding is closed. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.04.05a.i (Reference 12) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.04.05a.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 accordance with the approved plant programs and procedures.

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 6 of 13 References(available for NRC inspection)

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

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

3. EQ As-Built Reconciliation Reports as identified in Attachment A for Units 3

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

Code,Section II I, Rules for Construction of Nuclear Power Plant Components, 1998 Edition with 2000 Addenda

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

6. IEEE Standard 344-1987, IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations

7. Vogtie 3&4 Updated Final Safety Analysis Report Appendix 3D,Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment

8. Equipment Qualification Reports as identified in Attachment A

9. Regulatory Guide 1.100, Rev. 2, Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants 10 IEEE Standard 323-1974, IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations

11. Regulatory Guide 1.89, Rev 1, Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants

12. 2.2.04.05a.i-U3-CP-Rev0, Completion Package for Unit 3 ITAAC 2.2.04.05a.i [Index Number 226]

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 7 of 13 Attachment A System: Steam Generator System Class 1E/ Envir Seismic Envir. Type of Equipment Name ^ Tag No. ^ Qual. For Qual EQ Reports As-Built EQRR Cat. I ^ Zone 1 Qual.

Harsh Envir.^^ Program ^

Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V030A Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG01 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V030B Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG02 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V031A Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG01 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V031B Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG02 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V032A Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG01 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V032B Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG02 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V033A Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG01 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V033B Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG02 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V034A Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG01 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 8 of 13 Class 1E/ Envir Seismic Envir. Type of Equipment Name ^ Tag No. ^ Qual. For Qual EQ Reports As-Built EQRR Cat. I ^ Zone 1 Qual.

Harsh Envir/^ Program ^

Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V034B Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG02 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V035A Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG01 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Main Steam Safety Type SV3-PV65-VBR-012/

SGS-PL-V035B Yes -/- N/A N/A 2.2.04.05a.i-U3-Valve SG02 Testing & SV3-PV65-VBR-011 EQRR-PCD002 Analysis Power-operated Relief Valve Block Type SV3-PV01-VBR-016/

SGS-PL-V027A Yes Yes/Yes 5 M *ES 2.2.04.05a.i-U3-Motor-operated Valve Testing & SV3-PV01-VBR-015 EQRR-PCD002 Steam Generator 01 Analysis Power-operated Relief Valve Block Type SV3-PV01-VBR-016/

SGS-PL-V027B Yes Yes/Yes 5 M *ES 2.2.04.05a.i-U3-Motor-operated Valve Testing & SV3-PV01-VBR-015 EQRR-PCD002 Steam Generator 02 Analysis Steam Line Type Condensate Drain SGS-PL-V036A Yes Yes/Yes 5 M*ES SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-PV14-VBR-001 Isolation Valve EQRR-PCD002 Analysis Steam Line Type Condensate Drain SGS-PL-V036B Yes Yes/Yes 5 M *ES SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-PV14-VBR-001 Isolation Valve EQRR-PCD002 Analysis Main Steam Line Type SV3-PV64-VBR-012/

SGS-PL-V040A Yes Yes/Yes 5 M *ES 2.2.04.05a.i-U3-Isolation Valve Testing & SV3-PV64-VBR-011 EQRR-PCD002 Analysis Main Steam Line Type SV3-PV64-VBR-012/

SGS-PL-V040B Yes Yes/Yes 5 M *ES 2.2.04.05a.i-U3-Isolation Valve Testing & SV3-PV64-VBR-011 EQRR-PCD002 Analysis Steam Line Type Condensate Drain SGS-PL-V086A Yes Yes/Yes 5 M *ES SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-PV14-VBR-001 Control Valve EQRR-PCD002 Analysis

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 9 of 13 Class 1E/ Envir Seismic Envir. Type of Equipment Name ^ Tag No. ^ Qual. For Qual EQ Reports As-Built EQRR Cat. I ^ Zone 1 Qual.

Harsh Envir.^^ Program ^

Steam Line Type Condensate Drain SGS-PL-V086B Yes Yes/Yes 5 SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-M *ES Testing &

Control Valve SV3-PV14-VBR-001 EQRR-PCD002 Analysis Main Feedwater Type SGS-PL-V057A Yes Yes/Yes 5 SV3-PV67-VBR-012/ 2.2.04.05a.i-U3-Isolation Valve M *ES Testing & SV3-PV67-VBR-011 EQRR-PCD002 Analysis Main Feedwater Type SGS-PL-V057B Yes Yes/Yes 5 M*ES SV3-PV67-VBR-012/ 2.2.04.05a.i-U3-Isolation Valve Testing &

SV3-PV67-VBR-011 EQRR-PCD002 Analysis Startup Feedwater Type Isolation Motor- SGS-PL-V067A Yes Yes/Yes 5 SV3-PV01-VBR-012/ 2.2.04.05a.i-U3-M*ES Testing &

operated Valve SV3-PV01-VBR-011 EQRR-PCD002 Analysis Startup Feedwater Type Isolation Motor- SGS-PL-V067B Yes Yes/Yes 5 SV3-PV01-VBR-012/ 2.2.04.05a.i-U3-M*ES Testing &

SV3-PV01-VBR-011 EQRR-PCD002 operated Valve Analysis Steam Generator Type Blowdown Isolation SGS-PL-V074A Yes Yes/Yes 10 SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-M *ES Testing &

Valve SV3-PV14-VBR-001 EQRR-PCD002 Analysis Steam Generator Type Blowdown Isolation SGS-PL-V074B Yes Yes/Yes 10 SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-M *ES Testing &

Valve SV3-PV14-VBR-001 EQRR-PCD002 Analysis Steam Generator Type Blowdown Isolation SGS-PL-V075A Yes Yes/Yes 10 M*ES SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-Testing &

Valve SV3-PV14-VBR-001 EQRR-PCD002 Analysis Steam Generator Type Blowdown Isolation SGS-PL-V075B Yes Yes/Yes 10 SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-M*ES Testing &

Valve SV3-PV14-VBR-001 EQRR-PCD002 Analysis Power-operated Type SGS-PL-V233A Yes Yes/Yes 5 SV3-PV66-VBR-002 / 2.2.04.05a.i-U3-Relief Valve M*ES Testing & SV3-PV66-VBR-001 EQRR-PCD002 Analysis Power-operated Type SGS-PL-V233B Yes Yes/Yes 5 SV3-PV66-VBR-002 / 2.2.04.05a.i-U3-Relief Valve M*ES Testing & SV3-PV66-VBR-001 EQRR-PCD002 Analysis

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 10 of 13 Class IE/ Envir Seismic Envir. Type of Equipment Name ^ Tag No. ^ Qual. For Qual EQ Reports As-Built EQRR Cat. I ^ Zone 1 Qual.

Harsh Envir/^ Program ^

Main Steam Isolation Type Valve Bypass SGS-PL-V240A Yes Yes/Yes 5 M *ES SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-PV14-VBR-001 Isolation EQRR-PCD002 Analysis Main Steam Isolation Type Valve Bypass SGS-PL-V240B Yes Yes/Yes 5 M *ES SV3-PV14-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-PV14-VBR-001 Isolation EQRR-PCD002 Analysis Main Feedwater Type SV3-PV69-VBR-002 /

SGS-PL-V250A Yes Yes/Yes 5 M *ES 2.2.04.05a.i-U3-Control Valve Testing & SV3-PV69-VBR-001 EQRR-PCD002 Analysis Main Feedwater Type SGS-PL-V250B Yes Yes/Yes 5 M *ES SV3-PV69-VBR-002 / 2.2.04.05a.i-U3-Control Valve Testing & SV3-PV69-VBR-001 EQRR-PCD002 Analysis Startup Feedwater Type SV3-PV69-VBR-002 /

SGS-PL-V255A Yes Yes/Yes 5 M*ES 2.2.04.05a.i-U3-Control Valve Testing & SV3-PV69-VBR-001 EQRR-PCD002 Analysis Startup Feedwater Type SGS-PL-V255B Yes Yes/Yes 5 M*ES SV3-PV69-VBR-002 / 2.2.04.05a.i-U3-Control Valve Testing & SV3-PV69-VBR-001 EQRR-PCD002 Analysis Main Feedwater Type SV3-PV16-VBR-002/

SGS-PL-V257A Yes -/- N/A N/A 2.2.04.05a.i-U3-Thermal Relief Valve Testing & SV3-PV16-VBR-001 EQRR-PCD002 Analysis Main Feedwater Type SV3-PV16-VBR-002/

SGS-PL-V257B Yes -/- N/A N/A 2.2.04.05a.i-U3-Thermal Relief Valve Testing & SV3-PV16-VBR-001 EQRR-PCD002 Analysis Startup Feedwater Type SV3-PV16-VBR-002/

SGS-PL-V258A Yes -/- N/A N/A 2.2.04.05a.i-U3-Thermal Relief Valve Testing & SV3-PV16-VBR-001 EQRR-PCD002 Analysis Startup Feedwater Type SV3-PV16-VBR-002/

SGS-PL-V258B Yes -/- N/A N/A 2.2.04.05a.i-U3-Thermal Relief Valve Testing & SV3-PV16-VBR-001 EQRR-PCD002 Analysis Steam Generator 1 Type Narrow Range Level SGS-001 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Sensor EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 11 of 13 Class IE/ Envir Seismic Envir. Type of Equipment Name + Tag No. ^ Qual. For Qual EQ Reports As-Built EQRR Cat. I ^ Zone ^ Qual.

Harsh Envir/^ Program ^

Steam Generator 1 Type Narrow Range Level SGS-002 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 1 Type Narrow Range Level SGS-003 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 1 Type Narrow Range Level SGS-004 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 2 Type Narrow Range Level SGS-005 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 2 Type Narrow Range Level SGS-006 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2,04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 2 Type Narrow Range Level SGS-007 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 2 Type Narrow Range Level SGS-008 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 1 Type Wide Range Level SGS-011 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 1 Type Wide Range Level SGS-012 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 2 Type Wide Range Level SGS-013 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis Steam Generator 2 Type Wide Range Level SGS-014 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing &

Sensor SV3-JE52-VBR-001 EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 12 of 13 Class IE/ Envir Seismic Envir. Type of Equipment Name Tag No.

• Qual. For Qual EQ Reports As-Built EQRR Cat. I" Zone ^ Qual.

Harsh Envir/^ Program ^

Steam Generator 1 Type Wide Range Level SGS-015 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Sensor EQRR-PCD001 Analysis Steam Generator 1 Type Wide Range Level SGS-016 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Sensor EQRR-PCD001 Analysis Steam Generator 2 Type Wide Range Level SGS-017 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Sensor EQRR-PCD001 Analysis Steam Generator 2 Type Wide Range Level SGS-018 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Sensor EQRR-PCD001 Analysis Main Steam Line Type Steam Generator 1 SGS-030 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Pressure Sensor EQRR-PCD001 Analysis Main Steam Line Steam Generator 1 SGS-031 Yes Yes/No N/A N/A Type SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Pressure Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Main Steam Line Type Steam Generator 1 SGS-032 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Pressure Sensor EQRR-PCD001 Analysis Main Steam Line Steam Generator 1 SGS-033 Yes Yes/No N/A N/A Type SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Pressure Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Main Steam Line Type Steam Generator 2 SGS-034 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Pressure Sensor EQRR-PCD001 Analysis Main Steam Line Steam Generator 2 SGS-035 Yes Yes/No N/A N/A Type SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Pressure Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Main Steam Line Type Steam Generator 2 SGS-036 Yes Yes/Yes 1 E*S SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Testing & SV3-JE52-VBR-001 Pressure Sensor EQRR-PCD001 Analysis

U.S. Nuclear Regulatory Commission ND-21-1021 Enclosure Page 13 of 13 Class 1E/ Envir Seismic Envir. Type of Equipment Name + Tag No. ^ Qual. For Qual EQ Reports As-Built EQRR Cat. I ^ Zone 1 Qual.

Harsh Envir/^ Program ^

Main Steam Line Steam Generator 2 SGS-037 Yes Yes/No N/A N/A Type SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Pressure Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Steam Generator 1 SGS-55A Yes Yes/No N/A N/A Type SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Startup Feedwater Flow Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Steam Generator 1 SGS-55B Yes Yes/No N/A N/A Type SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Startup Feedwater Flow Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Steam Generator 2 SGS-56A Yes Yes/No N/A N/A Type SV3-JE52-VBR-002 / 2.2.04.05a.i-U3-Startup Feedwater Flow Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Steam Generator 2 SGS-56B Yes Yes/No N/A N/A Type SV3-JE52-VBR-002/ 2.2.04.05a.i-U3-Startup Feedwater Flow Sensor Testing SV3-JE52-VBR-001 EQRR-PCD001 Notes:

^ Excerpt from COL Appendix C Table 2.2.4-1

1. See Table 3D.5-1 of UFSAR

2. E - Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)

M - Mechanical Equipment Program (valve)

S = Qualified for submergence or operation with spray

• - Harsh Environment

3. Dash (-) indicates not applicable