ML19263A636

COL Docs - Draft36 Icn from SNC

ML19263A636
Person / Time
Site:	Vogtle
Issue date:	09/19/2019
From:	NRC
To:	NRC/NRO/DLSE/LB4
References
Download: ML19263A636 (6)

Text

Vogtle PEmails From: Patel, Chandu Sent: Thursday, September 19, 2019 3:09 PM To: Vogtle PEmails

Subject:

Draft36 ICN from SNC Attachments: Draft 36 ICN.docx Chandu Patel, Senior Project Manager U.S. NRC, Office of New Reactors NRC/NRO/DNRL/LB4, Washington, DC 20555-0001 301.415.3025 MS T6C20M 1

Hearing Identifier: Vogtle_COL_Docs_Public Email Number: 480 Mail Envelope Properties (SN6PR09MB323299ABF1A26CA0B6CAD12082890)

Subject:

Draft36 ICN from SNC Sent Date: 9/19/2019 3:09:27 PM Received Date: 9/19/2019 3:09:30 PM From: Patel, Chandu Created By: Chandu.Patel@nrc.gov Recipients:

"Vogtle PEmails" <Vogtle.PEmails@nrc.gov>

Tracking Status: None Post Office: SN6PR09MB3232.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 171 9/19/2019 3:09:30 PM Draft 36 ICN.docx 57784 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

U.S. Nuclear Regulatory Commission ND-19-1015 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-1015 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02.08d.v [Index Number 36]

U.S. Nuclear Regulatory Commission ND-19-1015 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 8.d) The RCS provides automatic depressurization during design basis events.

Inspections/Tests/Analyses v) Inspections of the elevation of the ADS stage 4 valve 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 Determination Basis Multiple ITAAC are performed to demonstrate that the Vogtle Electric Generating Plant (VEGP)

Unit 3 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 11.5 feet below the In-containment Refueling Water Storage Tank (IRWST) overflow level.

During fabrication of the ADS stage 4 valves, the vendor measured 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 were performed at the vendors 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 was necessary to verify measurements were within the acceptable ITAAC ranges prior to shipment.

Completion of these measurements at the vendors facility is standard industry practice and was specified in the procurement specification. Completing these measurements at the vendors facility meets the definition of as-built inspections per NEI 08-01, Section 9.5, As-built

U.S. Nuclear Regulatory Commission ND-19-1015 Enclosure Page 3 of 4 Inspections (Reference 1). The results of the measurements were included in the Vogtle Unit 3 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 was 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 was 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 3 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.

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 review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.1.02.08d.v (Reference 7) and available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.08d.v 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 approved plant programs and procedures.

References (available for NRC inspection)

1. NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52

2. SV3-PV70-VQQ-002 Revision 3, Quality Release & Certificate of Conformance (QR &

C of C) 14 Squib Valve Assembly

3. NCSP 02-24 Rev 3, ITAAC Support Activities

4. 4MP-T81C-N3201 Rev 5 Construction Survey

5. SV3-RCS-P0K-800036 Rev 0 "ADS Stage 4 Valves Elevation of Bottom Inside Surface of Outlet And Direction of Discharge"

6. SV3-MW01-V0K-891550 Rev 1 "UNIT 3 ADS SPARGER AS-BUILT ELEVATION VERIFICATION

U.S. Nuclear Regulatory Commission ND-19-1015 Enclosure Page 4 of 4

7. 2.1.02.08d.v-U3-CP-Rev0, ITAAC Completion Package Attachment A ADS-4 Valve Discharge and Measured Elevations (Reference 5)

Half Valve ADS-4 Valve Component ADS-4 Valve RCS Line/Plant Outlet Outlet Bottom Tag No.*

Name* Discharge Elevation Dimension Inside Surface Plant Elevation Fourth-stage RCS-PL- East (SG-1) RCS-PL-L133A ADS Squib V004A Room 11301 /+111.888 1.092 +110.796 Valve Fourth-stage RCS-PL- West (SG-2) RCS-PL-L133B ADS Squib V004B Room 11302 /+112.028 1.092 +110.936 Valve Fourth-stage RCS-PL- East (SG-1) RCS-PL-L137A ADS Squib V004C Room 11301 //+111.985 1.092 +110.893 Valve Fourth-stage RCS-PL- West (SG-2) RCS-PL-L137B ADS Squib V004D Room 11302 /+111.928 1.092 +110.836 Valve

• Excerpt from COL Appendix C, Table 2.1.2-1 Attachment B ADS Sparger/IRWST Overflow Measured Elevations (Reference 6)

IRWST Elevation of Sparger Hub Overflow Centerline of Centerline Distance Component Tag No.# Elevation Connection of Below IRWST Name#

Sparger Arms to Overflow Level Sparger Hub ADS Sparger A PXS- 131.9 feet 121.0 feet 11.0 feet MW-01A ADS Sparger B PXS- 131.9 feet 120.9 feet 11.0 feet MW-01B

1. Excerpt from COL Appendix C, Table 2.1.2-5