ND-18-0225, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.05.i (Index Number 684): Difference between revisions

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{{#Wiki_filter:Michael J. Yox                 7825 River Road Regulatory Affairs Director    Waynestxjro, GA 30830
{{#Wiki_filter:^
^ Southern Nuclear                                      Vogtle 3 & 4                  706-848-6459 tel 410-474-8587 cell
Southern Nuclear
    ' 2 2 2018                                                                        myox @southernco.com Docket Nos.:      52-025 52-026 ND-18-0225 10 CFR 52.99(c)(3)
'2 2 2018 Docket Nos.:
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.7.01.05.1 [Index Number 684]
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynestxjro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0225 10 CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.7.01.05.1 [Index Number 684]
Ladles and Gentlemen:
Ladles and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifiesthe NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.7.01.05.1
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifiesthe NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.7.01.05.1
[Index Number 684] has not been completed greater than 225-days prior to Initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to Initial fuel load.
[Index Number 684] has not been completedgreater than 225-days prior to Initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notificationsfor ITAAC that have not been completed 225-days prior to Initial fuel load.
This notification Is Informed by 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. In accordance with NEI 08-01, this notification Includes ITAAC for which required Inspections, tests, or analyses have not been performed or have been only partially completed.
This notification Is Informed by 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. In accordance with NEI 08-01, this notification Includes ITAAC for which required Inspections,tests, or analyses have not been performedor have been onlypartially completed.
All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).
All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met priorto plant operation, as required by 10 CFR 52.103(g).
This letter contains no new NRC regulatory commitments.
This letter contains no new NRC regulatory commitments.
If there are any questions, please contact Tom Petrak at 706-848-1575.
If there are any questions, please contact Tom Petrak at 706-848-1575.
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==Enclosure:==
==Enclosure:==
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.05.1 [Index Number 684]
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC2.7.01.05.1 [Index Number 684]
MJY/KJD/amw
MJY/KJD/amw


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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.
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.
Acceptance Criteria:
Acceptance Criteria:
i) The seismic Category I equipment identified in Table 2.7.1-1 is located on the Nuclear Island.
i) The seismic Category Iequipment identified inTable 2.7.1-1 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.
ii) A report exists and concludes that the seismic Category Iequipmentcan withstand seismic design basis loads without loss of safety function.
iii) A report exists and concludes that the as-built equipment including anchorage is seismicaily bounded by the tested or analyzed conditions.
iii) A reportexists and concludes that the as-built equipmentincluding anchorage is seismicaily bounded by the tested or analyzed conditions.
ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Nuclear Island Nonradioactive Ventilation System (VBS) equipment identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.7.1-1 (the Table) is designed and constructed in accordance with applicable requirements.
ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Nuclear Island Nonradioactive Ventilation System (VBS) equipment identifiedas seismic Category Iin the Combined License (COL) Appendix C, Table 2.7.1-1 (the Table) is designed and constructed inaccordance with applicable requirements.
if The seismic Cateoorv I equipment identified in Table 2.7.1-1 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 (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the VBS to confirm the satisfactory installation of the seismicallyqualified 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 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.
if The seismic Cateoorv I equipment identified in Table 2.7.1-1 is located on the Nuclear Island To assure that seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function, all the equipment in the Table is designed to be locatedon the seismic CategoryI Nuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the VBS to confirm the satisfactory installation of the seismicallyqualified 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 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.


U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 3 of 7 I!) A report exists and concludes that the seismic Cateoorv I eauioment can withstand seismic design basis loads without loss of safety function.
U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 3 of 7 I!) A report exists and concludes that the seismic Cateoorv I eauioment 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 3). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).
Seismic Category Iequipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category Ivalves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference3). Functionality ofthe subset ofactive safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).
Safety-related (Class 1E) 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 5). This equipment includes 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.
Safety-related (Class 1E)electrical equipment in the Table is seismically qualified bytype testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includes safety-related active valve accessories such as electric actuators, positionswitches, pilot solenoid valves and electricalconnector assemblies. The specificqualification method (i.e., type testing, analysis, or combination) used for each pieceofequipment in the Tableis identified in Attachment A.
Additional information about the methods used to qualify API 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).
Additional informationabout the methods used to qualifyAPI 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).
The EQ Reports (Reference 7) identified in Attachment Acontain 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.
The EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and conclude that the seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.
iiil A reoort exists and concludes that the as-built eauioment including anchorage is seismicallv bounded bv the tested or analyzed conditions.
iiil A reoort exists and concludes that the as-built eauioment including anchorage is seismicallv bounded bv the tested or analyzed conditions.
An inspection (Reference 1) is 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 otherinterfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.
An inspection (Reference 1) isconducted to confirm thesatisfactory 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 otherinterfaces. Thedocumentation ofinstalled configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.
As part of the seismic qualification program, consideration isgiven to the definition of the clearances needed around the equipment mounted in the plant to permit the equipmentto move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdone as part of seismic testing by measuring the maximum dynamic relative displacement of thetop and bottom of the equipment. EQ Reports (Reference 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification.
As part of theseismic qualification program, consideration isgiven tothedefinition of the clearances needed around the equipmentmounted in the plantto permit the equipmentto move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdone as part of seismic testing by measuring the maximum dynamic relative displacement of thetop andbottom of theequipment. EQ Reports (Reference 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade theestablished qualification.
Interface requirements are defined based on the test configuration and otherdesign requirements.
Interface requirements are defined based onthe test configuration and otherdesign requirements.
Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRG Regulatory Guide 1.100 (Reference 8).
Attachment Aidentifies the EQRR (Reference 2)completed to verify thatthe as-built seismic Category Iequipment listed in the Table, including anchorage, is seismically bounded by the tested oranalyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRG Regulatory Guide 1.100 (Reference 8).


U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 4 of 7 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met;
U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 4 of 7 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met; The seismic Category I equipment identified in Table 2.7.1-1 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; and A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
* The seismic Category I equipment identified in Table 2.7.1-1 is located on the Nuclear Island;
References 2 and 7 are available for NRC inspection as part of the Unit3 and Unit4 ITAAC 2.7.01.05.1 Completion Packages (References 9 and 10, respectively).
* A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; and
List of ITAAC Findings 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 685 and 686, found the following relevant ITAAC finding associated with this ITAAC.
* A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
References 2 and 7 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.7.01.05.1 Completion Packages (References 9 and 10, respectively).
List of ITAAC Findings 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 685 and 686, found the following relevant ITAAC finding associated with this ITAAC.
: 1) NGN 99901412/2012-201 -02 (Closed)
: 1) NGN 99901412/2012-201 -02 (Closed)
References favaiiabie for NRC inspection)
References favaiiabie for NRC inspection) 1.
: 1. ND-xx-xx-001, "EG Walkdown ITAAC Guideline"
ND-xx-xx-001, "EG Walkdown ITAAC Guideline"
: 2. EG As-Built Reconciliation Reports (EQRR) as identified in Attachment Afor Units 3 and 4
: 2. EG As-Built Reconciliation Reports (EQRR) as identified inAttachmentAfor Units 3 and 4
: 3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
: 3. American Society of Mechanical Engineers(ASME) Boiler and Pressure Vessel (B&PV)
Code, Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda
Code, Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda 4.
: 4. ASME QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007
ASME QME-1-2007, "Qualificationof Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007 5.
: 5. IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"
IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"
: 6. Vogtle 3&4 Updated Final SafetyAnalysis Report Appendix 3D, "Methodology forQualifying API 000 Safety-Related Electrical and Mechanical Equipment"
: 6. Vogtle 3&4 Updated Final SafetyAnalysis Report Appendix 3D, "Methodology forQualifying API 000 Safety-Related Electrical and Mechanical Equipment" 7.
: 7. Equipment Qualification (EQ) Reports as identified in Attachment A
Equipment Qualification (EQ) Reports as identified inAttachment A
: 8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"
: 8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"


U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 5 of 7
U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 5 of 7
: 9. 2.7.01.05.l-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.7.01.05.i [Index Number 684]"
: 9. 2.7.01.05.l-U3-CP-Rev X, "Completion Package for Unit3 ITAAC 2.7.01.05.i [Index Number 684]"
10.2.7.01.05.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.7.01.05.1 [Index Number 684]"
10.2.7.01.05.i-U4-CP-Rev X, "Completion Package for Unit4 ITAAC 2.7.01.05.1 [Index Number 684]"
: 11. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
: 11. NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"


U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 6 of 7 Attachment A System: Nuclear Island Nonradloactive Ventilation System Equipment                   Seismic    Type of      EQ Reports          As-Built EQRR Tag No.
U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 6 of 7 Attachment A System: Nuclear Island Nonradloactive Ventilation System Equipment Name^
* Name^                    Cat. 1 +   Quai.     (Reference 7)       (Reference 2)
Tag No.
* APP-PV11-VBR-MGR Supply Type Test        006/          2.7.01.05.i-U3-EQRR-Air Isolation   VBS-PL-V186     Yes
* Seismic Cat. 1 +
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Supply Type Test        006/          2.7.01.05.i-U3-EQRR-Air Isolation   VBS-PL-V187     Yes
Type of Quai.
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Return Type Test        006/          2.7.01.05.i-U3-EQRR-Air Isolation   VBS-PL-V188     Yes
EQ Reports (Reference 7)
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Return Type Test        006/          2.7.01.05.i-U3-EQRR-Air Isolation   VBS-PL-V189     Yes
As-Built EQRR (Reference 2)
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Exhaust Type Test        006/          2.7.01.05.i-U3-EQRR-Air Isolation   VBS-PL-V190     Yes
* MGR Supply Air Isolation Valve VBS-PL-V186 Yes Type Test
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Exhaust Type Test        006/          2.7.01.05.i-U3-EQRR-Air Isolation   VBS-PL-V191     Yes
& Analysis APP-PV11-VBR-006/
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005 APP-PV02-VBR-PWS MGR                                  Type Test        010/          2.7.01.05.i-U3-EQRR-PWS-PL-V418     Yes Isolation Valve                          & Analysis APP-PV02-VBR-         PGDXXX-Rev 0 009 APP-PV02-VBR-PWS MGR                                  Type Test        010/          2.7.01.05.i-U3-EQRR-PWS-PL-V420     Yes Isolation Valve                          & Analysis APP-PV02-VBR-         PGDXXX-Rev 0 009 APP-PV18-VBR-PWS MGR                                  Type Test        002/          2.7.01.05.i-U3-EQRR-PWS-PL-V498     Yes Vacuum Relief                            & Analysis APP-PV18-VBR-         PGDXXX-Rev 0 001 APP-PV11-VBR-MGR SDS Type Test        006/          2.7.01.05.i-U3-EQRR-(Vent) Isolation SDS-PL-V001     Yes
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Supply Air Isolation Valve VBS-PL-V187 Yes Type Test
                                        & Analysis APP-PV11-VBR-         PGDXXX-Rev 0 Valve 005
& Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Return Air Isolation Valve VBS-PL-V188 Yes Type Test
& Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Return Air Isolation Valve VBS-PL-V189 Yes Type Test
& Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Exhaust Air Isolation Valve VBS-PL-V190 Yes Type Test
& Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Exhaust Air Isolation Valve VBS-PL-V191 Yes Type Test
& Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 PWS MGR Isolation Valve PWS-PL-V418 Yes Type Test
& Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 PWS MGR Isolation Valve PWS-PL-V420 Yes Type Test
& Analysis APP-PV02-VBR-010/
APP-PV02-VBR-009 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 PWS MGR Vacuum Relief PWS-PL-V498 Yes Type Test
& Analysis APP-PV18-VBR-002/
APP-PV18-VBR-001 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR SDS (Vent) Isolation Valve SDS-PL-V001 Yes Type Test
&Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0


U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 7 of 7 Equipment                   Seismic    Type of    EQ Reports      As-Built EQRR Tag No.
U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 7 of 7 Equipment Name^
* Name^                      Cat. i +   Qual.     (Reference 7)   (Reference 2)
Tag No.
* APP-PV11-VBR-MCR SDS Type Test      006/     2.7.01.05.i-U3-EQRR-(Vent) Isolation SDS-PL-V002      Yes
* Seismic Cat. i +
                                          & Analysis APP-PV11-VBR-     PCDXXX-Rev 0 Valve 005 APP-PV03-VBR-MCR WWS            WWS-PL-                                006/      2.7.01.05.i-U3-EQRR-Yes      Analysis                    PCDXXX-Rev 0 Isolation Valve        V506                          APP-PV03-VBR-005
Type of Qual.
EQ Reports (Reference 7)
As-Built EQRR (Reference 2)
* MCR SDS (Vent) Isolation Valve SDS-PL-V002 Yes Type Test
&Analysis APP-PV11-VBR-006/
APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PCDXXX-Rev 0 MCR WWS Isolation Valve WWS-PL-V506 Yes Analysis APP-PV03-VBR-006/
APP-PV03-VBR-005 2.7.01.05.i-U3-EQRR-PCDXXX-Rev 0
+ Excerpt from COL Appendix C Table 2.7.1-1
+ Excerpt from COL Appendix C Table 2.7.1-1
* Tfie Unit 4 As-Built EQRR are numbered "2.7.01.05.i-U4-EQRR-PCDXXX-Rev 0"}}
* Tfie Unit 4 As-Built EQRR are numbered "2.7.01.05.i-U4-EQRR-PCDXXX-Rev 0"}}

Latest revision as of 09:21, 6 January 2025

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.05.i (Index Number 684)
ML18054A306
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 02/22/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.7.01.05.i, ND-18-0225
Download: ML18054A306 (11)
v • d • e


Text

^

Southern Nuclear

'2 2 2018 Docket Nos.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynestxjro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0225 10 CFR 52.99(c)(3)

Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.7.01.05.1 [Index Number 684]

Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifiesthe NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.7.01.05.1

[Index Number 684] has not been completedgreater than 225-days prior to Initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notificationsfor ITAAC that have not been completed 225-days prior to Initial fuel load.

This notification Is Informed by 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. In accordance with NEI 08-01, this notification Includes ITAAC for which required Inspections,tests, or analyses have not been performedor have been onlypartially completed.

All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met priorto plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtle 3 &4

U.S. Nuclear Regulatory Commission ND-18-0225 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC2.7.01.05.1 [Index Number 684]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0225 Page 3 of 4 To:

Southern Nuclear Operating ComDanv/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc; Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. P. B. Donnelly Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0225 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Sen/Ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Batch BIngham

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-18-0225 Enclosure Vogtle Electric Generating Riant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.05.1 [Index Number 684]

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 2 of 7 ITAAC Statement Desion Commitment:

5. The seismic Category I equipment identified in Table 2.7.1-1 can withstand seismic design basis loads without loss of safety function.

Inspections. Tests. Analyses:

i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.7.1-1 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.

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.

Acceptance Criteria:

i) The seismic Category Iequipment identified inTable 2.7.1-1 is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category Iequipmentcan withstand seismic design basis loads without loss of safety function.

iii) A reportexists and concludes that the as-built equipmentincluding anchorage is seismicaily bounded by the tested or analyzed conditions.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Nuclear Island Nonradioactive Ventilation System (VBS) equipment identifiedas seismic Category Iin the Combined License (COL) Appendix C, Table 2.7.1-1 (the Table) is designed and constructed inaccordance with applicable requirements.

if The seismic Cateoorv I equipment identified in Table 2.7.1-1 is located on the Nuclear Island To assure that seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function, all the equipment in the Table is designed to be locatedon the seismic CategoryI Nuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the VBS to confirm the satisfactory installation of the seismicallyqualified 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 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 3 of 7 I!) A report exists and concludes that the seismic Cateoorv I eauioment can withstand seismic design basis loads without loss of safety function.

Seismic Category Iequipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category Ivalves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference3). Functionality ofthe subset ofactive safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).

Safety-related (Class 1E)electrical equipment in the Table is seismically qualified bytype testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includes safety-related active valve accessories such as electric actuators, positionswitches, pilot solenoid valves and electricalconnector assemblies. The specificqualification method (i.e., type testing, analysis, or combination) used for each pieceofequipment in the Tableis identified in Attachment A.

Additional informationabout the methods used to qualifyAPI 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).

The EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and conclude that the seismic Category Iequipment can withstand seismic design basis loads without loss ofsafety function.

iiil A reoort exists and concludes that the as-built eauioment including anchorage is seismicallv bounded bv the tested or analyzed conditions.

An inspection (Reference 1) isconducted to confirm thesatisfactory 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 otherinterfaces. Thedocumentation ofinstalled configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.

As part of theseismic qualification program, consideration isgiven tothedefinition of the clearances needed around the equipmentmounted in the plantto permit the equipmentto move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdone as part of seismic testing by measuring the maximum dynamic relative displacement of thetop andbottom of theequipment. EQ Reports (Reference 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade theestablished qualification.

Interface requirements are defined based onthe test configuration and otherdesign requirements.

Attachment Aidentifies the EQRR (Reference 2)completed to verify thatthe as-built seismic Category Iequipment listed in the Table, including anchorage, is seismically bounded by the tested oranalyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRG Regulatory Guide 1.100 (Reference 8).

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 4 of 7 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met; The seismic Category I equipment identified in Table 2.7.1-1 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; and A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

References 2 and 7 are available for NRC inspection as part of the Unit3 and Unit4 ITAAC 2.7.01.05.1 Completion Packages (References 9 and 10, respectively).

List of ITAAC Findings 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 685 and 686, found the following relevant ITAAC finding associated with this ITAAC.

1) NGN 99901412/2012-201 -02 (Closed)

References favaiiabie for NRC inspection) 1.

ND-xx-xx-001, "EG Walkdown ITAAC Guideline"

2. EG As-Built Reconciliation Reports (EQRR) as identified inAttachmentAfor Units 3 and 4
3. American Society of Mechanical Engineers(ASME) Boiler and Pressure Vessel (B&PV)

Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda 4.

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

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

6. Vogtle 3&4 Updated Final SafetyAnalysis Report Appendix 3D, "Methodology forQualifying API 000 Safety-Related Electrical and Mechanical Equipment" 7.

Equipment Qualification (EQ) Reports as identified inAttachment A

8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 5 of 7

9. 2.7.01.05.l-U3-CP-Rev X, "Completion Package for Unit3 ITAAC 2.7.01.05.i [Index Number 684]"

10.2.7.01.05.i-U4-CP-Rev X, "Completion Package for Unit4 ITAAC 2.7.01.05.1 [Index Number 684]"

11. NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 6 of 7 Attachment A System: Nuclear Island Nonradloactive Ventilation System Equipment Name^

Tag No.

  • Seismic Cat. 1 +

Type of Quai.

EQ Reports (Reference 7)

As-Built EQRR (Reference 2)

  • MGR Supply Air Isolation Valve VBS-PL-V186 Yes Type Test

& Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Supply Air Isolation Valve VBS-PL-V187 Yes Type Test

& Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Return Air Isolation Valve VBS-PL-V188 Yes Type Test

& Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Return Air Isolation Valve VBS-PL-V189 Yes Type Test

& Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Exhaust Air Isolation Valve VBS-PL-V190 Yes Type Test

& Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR Exhaust Air Isolation Valve VBS-PL-V191 Yes Type Test

& Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 PWS MGR Isolation Valve PWS-PL-V418 Yes Type Test

& Analysis APP-PV02-VBR-010/

APP-PV02-VBR-009 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 PWS MGR Isolation Valve PWS-PL-V420 Yes Type Test

& Analysis APP-PV02-VBR-010/

APP-PV02-VBR-009 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 PWS MGR Vacuum Relief PWS-PL-V498 Yes Type Test

& Analysis APP-PV18-VBR-002/

APP-PV18-VBR-001 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0 MGR SDS (Vent) Isolation Valve SDS-PL-V001 Yes Type Test

&Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PGDXXX-Rev 0

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 7 of 7 Equipment Name^

Tag No.

  • Seismic Cat. i +

Type of Qual.

EQ Reports (Reference 7)

As-Built EQRR (Reference 2)

  • MCR SDS (Vent) Isolation Valve SDS-PL-V002 Yes Type Test

&Analysis APP-PV11-VBR-006/

APP-PV11-VBR-005 2.7.01.05.i-U3-EQRR-PCDXXX-Rev 0 MCR WWS Isolation Valve WWS-PL-V506 Yes Analysis APP-PV03-VBR-006/

APP-PV03-VBR-005 2.7.01.05.i-U3-EQRR-PCDXXX-Rev 0

+ Excerpt from COL Appendix C Table 2.7.1-1

  • Tfie Unit 4 As-Built EQRR are numbered "2.7.01.05.i-U4-EQRR-PCDXXX-Rev 0"
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