ND-20-1221, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.08d.v (Index Number 361): Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:Michael J. Yox                 7825 River Road
{{#Wiki_filter:^
^Southern Nuclear                                    Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel Docket No.:     52-026 OCT 2 2 2020                                                                         ND-20-1221 10CFR 52.99(c)(3)
Southern Nuclear Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket No.:
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.08d.v [Index Number 361 Ladies and Gentlemen:
52-026 OCT 2 2 2020 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-20-1221 10CFR 52.99(c)(3)
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 15, 2020, Vogtle Electric Generating Plant(VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.1.02.08d.v [Index Number 36] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.1.02.08d.v [Index Number 36]. 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.
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.08d.v [Index Number 361 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 15, 2020, Vogtle Electric Generating Plant (VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.1.02.08d.v [Index Number 36] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.1.02.08d.v [Index Number 36]. 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.
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. 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).
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. 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).
This letter contains no new NRC regulatory commitments.
This letter contains no new NRC regulatory commitments.
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==Enclosure:==
==Enclosure:==
Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.1.02.08d.v [Index Number 36]
Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.1.02.08d.v [Index Number 36]
MJY/WLP/sfr
MJY/WLP/sfr


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Mr. M. D. Meier (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Reoulatorv Commission M C. P. Patel M G. J. Khouri M    N. D. Karlovich M    A. Lerch M    C. J. Even M    B. J. Kemker Ms. N. C. Coovert M C. Welch M    J. Gaslevic M    V. Hall M    G. Armstrong M    M. Webb M  T. Fredette M    S. Smith M    C. Santos M  s. M. Bailey M    S. Rose M    B. Davis M    J. Vasquez M    J. Eargle M M. King M    E. Davidson M    T. Fanelli
Nuclear Reoulatorv Commission M
M M
M M
M Ms. N. C. Coovert M
M M
M M
M M
M M
M M
M M
M M
M C. P. Patel G. J. Khouri N. D. Karlovich A. Lerch C. J. Even B. J. Kemker C. Welch J. Gaslevic V. Hall G. Armstrong M. Webb T. Fredette S. Smith C. Santos
: s. M. Bailey S. Rose B. Davis J. Vasquez J. Eargle M. King E. Davidson T. Fanelli


U.S. Nuclear Regulatory Commission ND-20-1221 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
U.S. Nuclear Regulatory Commission ND-20-1221 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
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Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham
Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham


U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-1221 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.1.02.08d.v [Index Number 36]
U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-1221 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.1.02.08d.v [Index Number 36]


U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 8.d)     The RCS provides automatic depressurization during design basis events.
U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 8.d)
I nspections/Tests/Analvses v)       Inspections of the elevation of the ADS stage 4 valve discharge will be conducted.
The RCS provides automatic depressurization during design basis events.
vi)     Inspections of the ADS stage 4 valve discharge will be conducted.
I nspections/T ests/Analvses v)
viii)   Inspection of the elevation of each ADS sparger will be conducted.
Inspections of the elevation of the ADS stage 4 valve discharge will be conducted.
Acceptance Criteria v)       The minimum elevation of the bottom inside surface of the outlet of these valves is greater than plant elevation 110 feet.
vi)
vi)     The discharge of the ADS stage 4 valves is directed into the steam generator compartments.
Inspections of the ADS stage 4 valve discharge will be conducted.
viii)   The centerline of the connection of the sparger arms to the sparger hub is ^ 11.5 feet below the IRWST overflow level.
viii)
ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Vogtle Electric Generating Plant(VEGP)
Inspection of the elevation of each ADS sparger will be conducted.
Unit 4 Reactor Coolant System (RCS) provides automatic depressurization during design basis events. This ITAAC requires that inspections be conducted to verify that the minimum elevation of the bottom inside surface of the outlet of the Automatic Depressurization System (ADS)stage 4 valves is greater than plant elevation 110 feet, that the discharge of the ADS stage 4 valves is directed into the steam generator compartments, and that for each ADS sparger (Sparger A and Sparger B)the centerline of the connection of the sparger arms to the sparger hub is s 11.5 feet below the In-containment Refueling Water Storage Tank (IRWST) overflow level.
Acceptance Criteria v)
The minimum elevation of the bottom inside surface of the outlet of these valves is greater than plant elevation 110 feet.
vi)
The discharge of the ADS stage 4 valves is directed into the steam generator compartments.
viii)
The centerline of the connection of the sparger arms to the sparger hub is ^ 11.5 feet below the IRWST overflow level.
ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Vogtle Electric Generating Plant (VEGP)
Unit 4 Reactor Coolant System (RCS) provides automatic depressurization during design basis events. This ITAAC requires that inspections be conducted to verify that the minimum elevation of the bottom inside surface of the outlet of the Automatic Depressurization System (ADS) stage 4 valves is greater than plant elevation 110 feet, that the discharge of the ADS stage 4 valves is directed into the steam generator compartments, and that for each ADS sparger (Sparger A and Sparger B) the centerline of the connection of the sparger arms to the sparger hub is s 11.5 feet below the In-containment Refueling Water Storage Tank (IRWST) overflow level.
During fabrication of the ADS stage 4 valves, the vendor measures key dimensions, including the valve body outlet circular dimension, which when halved and subtracted from the RCS line centerline elevation, is the elevation of the bottom inside surface of the outlet of the ADS stage 4 valves. The dimensional inspections are performed at the vendor's facility using both standard industry measurement techniques and specialized equipment. Due to the nature of the manufacturing process of the ADS stage 4 valves (i.e., 14" squib valves), it is necessary to verify measurements are within the acceptable ITAAC ranges prior to shipment. Completion of these measurements at the vendor's facility is standard industry practice and is specified in the procurement specification. Completing these measurements at the vendor's facility meets the
During fabrication of the ADS stage 4 valves, the vendor measures key dimensions, including the valve body outlet circular dimension, which when halved and subtracted from the RCS line centerline elevation, is the elevation of the bottom inside surface of the outlet of the ADS stage 4 valves. The dimensional inspections are performed at the vendor's facility using both standard industry measurement techniques and specialized equipment. Due to the nature of the manufacturing process of the ADS stage 4 valves (i.e., 14" squib valves), it is necessary to verify measurements are within the acceptable ITAAC ranges prior to shipment. Completion of these measurements at the vendor's facility is standard industry practice and is specified in the procurement specification. Completing these measurements at the vendor's facility meets the


U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 3 of 4 definition of "as-built inspections" per NEI 08-01, Section 9.5,"As-built Inspections"(Reference 1). The results of the measurements are included in the Vogtle Unit 4 ADS-4 Stage Valve Quality Release & Certificate of Conformance (Reference 2).
U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 3 of 4 definition of "as-built inspections" per NEI 08-01, Section 9.5, "As-built Inspections" (Reference 1). The results of the measurements are included in the Vogtle Unit 4 ADS-4 Stage Valve Quality Release & Certificate of Conformance (Reference 2).
An inspection of the routing of the RCS lines associated with the ADS stage 4 valves is performed during a walk down of the as-built lines in accordance with the site walk down inspection procedure (Reference 3)to confirm that the discharge of ADS stage 4 valves, which are installed at the end of the RCS lines, is directed into the steam generator compartments.
An inspection of the routing of the RCS lines associated with the ADS stage 4 valves is performed during a walk down of the as-built lines in accordance with the site walk down inspection procedure (Reference 3) to confirm that the discharge of ADS stage 4 valves, which are installed at the end of the RCS lines, is directed into the steam generator compartments.
The elevation of the RCS lines. Sparger A and B hub centerlines, and IRWST overflow level is determined using survey equipment in accordance with site survey and measurement procedures (Reference 4).
The elevation of the RCS lines. Sparger A and B hub centerlines, and IRWST overflow level is determined using survey equipment in accordance with site survey and measurement procedures (Reference 4).
The walk down and survey inspection results are documented in the Unit 4 inspection reports (References 5 and 6)and reflected in Attachments A and B, which demonstrate that the acceptance criteria of the ITAAC have been met. References 2 through 6 are available for NRC inspection as part of the ITAAC 2.1.02.08d.v Completion Package (Reference 7).
The walk down and survey inspection results are documented in the Unit 4 inspection reports (References 5 and 6) and reflected in Attachments A and B, which demonstrate that the acceptance criteria of the ITAAC have been met. References 2 through 6 are available for NRC inspection as part of the ITAAC 2.1.02.08d.v Completion Package (Reference 7).
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 review found that there are no relevant ITAAC findings associated with this ITAAC.
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 review found that there are no relevant ITAAC findings associated with this ITAAC.
References favaiiabie for NRC inspection)
References favaiiabie for NRC inspection)
: 1. NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52
: 1. NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52
: 2. SV4-PV70-VQQ-002 Revision X, Quality Release & Certificate of Conformance(QR & C of C) 14" Squib Valve Assembly
: 2. SV4-PV70-VQQ-002 Revision X, Quality Release & Certificate of Conformance (QR & C of C) 14" Squib Valve Assembly
: 3. NCSP02-24 Rev X, ITAAC Support Activities(AP 1000)
: 3. NCSP02-24 Rev X, ITAAC Support Activities (AP 1000)
: 4. 4MP-T81C-N3201 Rev X, Construction Survey
: 4. 4MP-T81C-N3201 Rev X, Construction Survey
: 5. SV4-RCS-P0K-800036 Rev X, ADS Stage 4 Valves Elevation of Bottom Inside Surface of Cutlet and Direction of Discharge
: 5. SV4-RCS-P0K-800036 Rev X, ADS Stage 4 Valves Elevation of Bottom Inside Surface of Cutlet and Direction of Discharge
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U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 4 of 4 Attachment A ADS-4 Valve Discharge and Measured Elevations (Reference 5)
U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 4 of 4 Attachment A ADS-4 Valve Discharge and Measured Elevations (Reference 5)
Half Valve    ADS-4 Valve ADS-4 Valve    RCS Line/Plant         Outlet      Outlet Bottom Component Tag No.*    Discharge    Elevation (Feet)     Dimension     Inside Surface Name*
Component Name*
(Feet)     Plant Elevation (Feet)
Tag No.*
Fourth-       RCS-PL-   East(SG-1)     RCS-PL-L133A stage ADS      V004A    Room 11301      /+XXX.XXX           x.xxx         + XXX.XXX Squib Valve Fourth-        RCS-PL-   West(SG-2)     RCS-PL-L133B stage ADS      V004B    Room 11302      /+ XXX.XXX           X.XXX         + XXX.XXX Squib Valve Fourth-        RCS-PL-   East(SG-1)     RCS-PL-L137A stage ADS      V004C    Room 11301      /+ XXX.XXX           x.xxx         + XXX.XXX Squib Valve Fourth-        RCS-PL-   West(SG-2)     RCS-PL-L137B stage ADS      V004D    Room 11302      /+ XXX.XXX           x.xxx         XXX.XXX Squib Valve Excerpt from COL Appendix C, Table 2.1.2-1 Attachment B ADS Sparger/I RWST Overflow Measured Elevations (Reference 6)
ADS-4 Valve Discharge RCS Line/Plant Elevation (Feet)
IRWST              Elevation of        Sparger Hub Overflow          Centerline of      Centerline Distance Component Tag No.**     Elevation         Connection of         Below IRWST Name**
Half Valve Outlet Dimension (Feet)
Sparger Arms to         Overflow Level Sparger Hub ADS Sparger A       PXS-       XXX.X feet           XXX.X feet             XX.X feet MW-01A ADS Sparger B       PXS-       XXX.X feet           XXX.X feet             XX.X feet MW-01B Excerpt from COL Appendix C, Table 2.1.2-5}}
ADS-4 Valve Outlet Bottom Inside Surface Plant Elevation (Feet)
Fourth-stage ADS Squib Valve RCS-PL-V004A East (SG-1)
Room 11301 RCS-PL-L133A
/+XXX.XXX x.xxx
+ XXX.XXX Fourth-stage ADS Squib Valve RCS-PL-V004B West (SG-2)
Room 11302 RCS-PL-L133B
/+ XXX.XXX X.XXX
+ XXX.XXX Fourth-stage ADS Squib Valve RCS-PL-V004C East (SG-1)
Room 11301 RCS-PL-L137A
/+ XXX.XXX x.xxx
+ XXX.XXX Fourth-stage ADS Squib Valve RCS-PL-V004D West (SG-2)
Room 11302 RCS-PL-L137B
/+ XXX.XXX x.xxx XXX.XXX Excerpt from COL Appendix C, Table 2.1.2-1 Attachment B ADS Sparger/I RWST Overflow Measured Elevations (Reference 6)
Component Name**
Tag No.**
IRWST Overflow Elevation Elevation of Centerline of Connection of Sparger Arms to Sparger Hub Sparger Hub Centerline Distance Below IRWST Overflow Level ADS Sparger A PXS-MW-01A XXX.X feet XXX.X feet XX.X feet ADS Sparger B PXS-MW-01B XXX.X feet XXX.X feet XX.X feet Excerpt from COL Appendix C, Table 2.1.2-5}}

Latest revision as of 14:54, 29 November 2024

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.08d.v (Index Number 361)
ML20297A370
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 10/22/2020
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-1221
Download: ML20297A370 (7)
v • d • e


Text

^

Southern Nuclear Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket No.:

52-026 OCT 2 2 2020 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-20-1221 10CFR 52.99(c)(3)

Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.08d.v [Index Number 361 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 15, 2020, Vogtle Electric Generating Plant (VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.1.02.08d.v [Index Number 36] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.1.02.08d.v [Index Number 36]. 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.

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. 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).

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 Dii^ctor Vogtle 3&4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.1.02.08d.v [Index Number 36]

MJY/WLP/sfr

U.S. Nuclear Regulatory Commission ND-20-1221 Page 2 of 3 To:

Southern Nuclear Operating Company/Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

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

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

Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission M

M M

M M

M Ms. N. C. Coovert M

M M

M M

M M

M M

M M

M M

M M

M C. P. Patel G. J. Khouri N. D. Karlovich A. Lerch C. J. Even B. J. Kemker C. Welch J. Gaslevic V. Hall G. Armstrong M. Webb T. Fredette S. Smith C. Santos

s. M. Bailey S. Rose B. Davis J. Vasquez J. Eargle M. King E. Davidson T. Fanelli

U.S. Nuclear Regulatory Commission ND-20-1221 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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 Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-1221 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.1.02.08d.v [Index Number 36]

U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 8.d)

The RCS provides automatic depressurization during design basis events.

I nspections/T ests/Analvses v)

Inspections of the elevation of the ADS stage 4 valve discharge will be conducted.

vi)

Inspections of the ADS stage 4 valve discharge will be conducted.

viii)

Inspection of the elevation of each ADS sparger will be conducted.

Acceptance Criteria v)

The minimum elevation of the bottom inside surface of the outlet of these valves is greater than plant elevation 110 feet.

vi)

The discharge of the ADS stage 4 valves is directed into the steam generator compartments.

viii)

The centerline of the connection of the sparger arms to the sparger hub is ^ 11.5 feet below the IRWST overflow level.

ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Vogtle Electric Generating Plant (VEGP)

Unit 4 Reactor Coolant System (RCS) provides automatic depressurization during design basis events. This ITAAC requires that inspections be conducted to verify that the minimum elevation of the bottom inside surface of the outlet of the Automatic Depressurization System (ADS) stage 4 valves is greater than plant elevation 110 feet, that the discharge of the ADS stage 4 valves is directed into the steam generator compartments, and that for each ADS sparger (Sparger A and Sparger B) the centerline of the connection of the sparger arms to the sparger hub is s 11.5 feet below the In-containment Refueling Water Storage Tank (IRWST) overflow level.

During fabrication of the ADS stage 4 valves, the vendor measures key dimensions, including the valve body outlet circular dimension, which when halved and subtracted from the RCS line centerline elevation, is the elevation of the bottom inside surface of the outlet of the ADS stage 4 valves. The dimensional inspections are performed at the vendor's facility using both standard industry measurement techniques and specialized equipment. Due to the nature of the manufacturing process of the ADS stage 4 valves (i.e., 14" squib valves), it is necessary to verify measurements are within the acceptable ITAAC ranges prior to shipment. Completion of these measurements at the vendor's facility is standard industry practice and is specified in the procurement specification. Completing these measurements at the vendor's facility meets the

U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 3 of 4 definition of "as-built inspections" per NEI 08-01, Section 9.5, "As-built Inspections" (Reference 1). The results of the measurements are included in the Vogtle Unit 4 ADS-4 Stage Valve Quality Release & Certificate of Conformance (Reference 2).

An inspection of the routing of the RCS lines associated with the ADS stage 4 valves is performed during a walk down of the as-built lines in accordance with the site walk down inspection procedure (Reference 3) to confirm that the discharge of ADS stage 4 valves, which are installed at the end of the RCS lines, is directed into the steam generator compartments.

The elevation of the RCS lines. Sparger A and B hub centerlines, and IRWST overflow level is determined using survey equipment in accordance with site survey and measurement procedures (Reference 4).

The walk down and survey inspection results are documented in the Unit 4 inspection reports (References 5 and 6) and reflected in Attachments A and B, which demonstrate that the acceptance criteria of the ITAAC have been met. References 2 through 6 are available for NRC inspection as part of the ITAAC 2.1.02.08d.v Completion Package (Reference 7).

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 review found that there are no relevant ITAAC findings associated with this ITAAC.

References favaiiabie for NRC inspection)

1. NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52
2. SV4-PV70-VQQ-002 Revision X, Quality Release & Certificate of Conformance (QR & C of C) 14" Squib Valve Assembly
3. NCSP02-24 Rev X, ITAAC Support Activities (AP 1000)
4. 4MP-T81C-N3201 Rev X, Construction Survey
5. SV4-RCS-P0K-800036 Rev X, ADS Stage 4 Valves Elevation of Bottom Inside Surface of Cutlet and Direction of Discharge
6. SV4-MW01-V0K-891550 Rev X, UNIT 4 ADS Sparger As-built Elevation Verification
7. 2.1.02.08d.v-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-20-1221 Enclosure Page 4 of 4 Attachment A ADS-4 Valve Discharge and Measured Elevations (Reference 5)

Component Name*

Tag No.*

ADS-4 Valve Discharge RCS Line/Plant Elevation (Feet)

Half Valve Outlet Dimension (Feet)

ADS-4 Valve Outlet Bottom Inside Surface Plant Elevation (Feet)

Fourth-stage ADS Squib Valve RCS-PL-V004A East (SG-1)

Room 11301 RCS-PL-L133A

/+XXX.XXX x.xxx

+ XXX.XXX Fourth-stage ADS Squib Valve RCS-PL-V004B West (SG-2)

Room 11302 RCS-PL-L133B

/+ XXX.XXX X.XXX

+ XXX.XXX Fourth-stage ADS Squib Valve RCS-PL-V004C East (SG-1)

Room 11301 RCS-PL-L137A

/+ XXX.XXX x.xxx

+ XXX.XXX Fourth-stage ADS Squib Valve RCS-PL-V004D West (SG-2)

Room 11302 RCS-PL-L137B

/+ XXX.XXX x.xxx XXX.XXX Excerpt from COL Appendix C, Table 2.1.2-1 Attachment B ADS Sparger/I RWST Overflow Measured Elevations (Reference 6)

Component Name**

Tag No.**

IRWST Overflow Elevation Elevation of Centerline of Connection of Sparger Arms to Sparger Hub Sparger Hub Centerline Distance Below IRWST Overflow Level ADS Sparger A PXS-MW-01A XXX.X feet XXX.X feet XX.X feet ADS Sparger B PXS-MW-01B XXX.X feet XXX.X feet XX.X feet Excerpt from COL Appendix C, Table 2.1.2-5

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