ND-22-0526, ITAAC Closure Notification on Completion of ITAAC 2.1.02.08d.v (Index Number 36)
| ML22189A176 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/08/2022 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-22-0526 | |
| Download: ML22189A176 (7) | |
Text
>-a Southern Nuclear JUL O 8 2022 Docket No.:
52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0526 10 CFR 52.99(c)(1)
ITAAC Closure Notification on Completion of ITAAC 2.1.02.08d.v (Index Number 36)
Ladies and Gentlemen:
In accordance with 1 O 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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.08d.v (Index Number
- 36) for verifying the discharge location and elevation of the Automatic Depressurization System (ADS) Stage 4 valves and the elevation of the ADS spargers. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 1 O CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.
This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 1 O CFR 52.99.
If there are any questions, please contact Kelli A. Roberts at 706-848-6991.
Respectfully submitted,
~t ~
Ja~
~ -~o~eman Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
JMC/JTK/sfr Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.08d.v (Index Number 36)
U.S. Nuclear Regulatory Commission ND-22-0526 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Regulatory Commission Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall
U.S. Nuclear Regulatory Commission ND-22-0526 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., GOS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-22-0526 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0526 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.0Bd.v [Index Number 36]
U.S. Nuclear Regulatory Commission ND-22-0526 Enclosure Page 2 of 4 IT AAC 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 11 O 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 I RWST overflow level.
IT AAC Determination Basis 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 11 O 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 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 was necessary to verify measurements were within the acceptable ITAAC ranges prior to shipment. Completion of these measurements at the vendor's facility is standard industry practice and was specified in the procurement specification. Completing these measurements at the vendor's facility meets the definition of "as-built inspections" per NEI 08-01, Section 9.5, "As-built Inspections" (Reference 1 ). The results of the measurements were included in the Vogtle Unit 4 ADS-4 Stage Valve Quality Release & Certificate of Conformance (Reference 2).
U.S. Nuclear Regulatory Commission ND-22-0526 Enclosure Page 3 of 4 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 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 4 inspection reports (References 5 and 6) and reflected in Attachments A and B, which demonstrate that the acceptance criteria of the IT AAC have been met.
IT AAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all IT AAC 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.
IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.08d.v was performed for VEGP Unit 4 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, Rev 5 Corrected, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52"
- 2. SV4-PV70-VQQ-002, Revision 3, "Quality Release & Certificate of Conformance (QR &
C of C) 14" Squib Valve Assembly"
- 3. ND-RA-001-012, Rev 6, "Functional and Physical Arrangement Scoping Process"
- 4. 26139-000-4MP-T81 C-N3201 Rev 7, "Construction Survey"
- 5. SV4-RCS-FSK-900036 Rev O, " UNIT 4 ADS Stage 4 Valves Elevation of Bottom Inside Surface of Outlet And Direction of Discharge"
- 6. SV4-MW01 -FSK-891550 Rev 0, "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-22-0526 Enclosure Page 4 of 4 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.*
Discharge Elevation (Feet)
Dimension Inside Surface Name*
(Feet)
Plant Elevation (Feet)
Fourth-RCS-PL-East (SG-1)
RCS-PL-L 133A stage ADS V004A Room 11301
/+111.948 1.092
+110.856 Squib Valve Fourth-RCS-PL-West (SG-2)
RCS-PL-L 133B stage ADS V004B Room 11302
/+111.921 1.092
+110.829 Squib Valve Fourth-RCS-PL-East (SG-1)
RCS-PL-L 137 A stage ADS V004C Room 11301
/+ 111.932 1.092
+110.84 Squib Valve Fourth-RCS-PL-West (SG-2)
RCS-PL-L 137B stage ADS V004D Room 11302
/+111.929 1.092
+110.837 Squib Valve
- Excerpt from COL Appendix C, Table 2.1.2-1 Attachment B ADS Sparger/lRWST Overflow Measured Elevations (Reference 6)
IRWST Elevation of Sparger Hub Component Overflow Centerline of Centerline Distance Tag No.**
Elevation Connection of Below IRWST Name#
Sparger Arms to Overflow Level Sparqer Hub ADS Sparger A PXS-131.9feet 120.9 feet 11 feet MW-01A ADS Sparger B PXS-131.9 feet 120.9 feet 11 feet MW-01B
- Excerpt from COL Appendix C, Table 2.1.2-5