ND-22-0522, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.04 (Index Number 180)
| ML23020A045 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/19/2023 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| ND-22-0522, ITAAC 2.2.03.08c.i.04 | |
| Download: ML23020A045 (1) | |
Text
A Southern Nuclear January 19, 2023 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-22-0522 10 CFR 52.99(c)(1)
ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.04 [Index Number 1801 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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.i.04
[Index Number 180], for verifying the Containment Recirculation line flow resistance values.
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 is 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 10 CFR 52.99.
If there are any questions, please contact Kelli Roberts at 706-848-6991.
Respectfully submitted, ij(V{Yvl Co-ft maJY' Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
JMC/DLW/sfr Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.03.08c.i.04 [Index Number 180]
U.S. Nuclear Regulatory Commission ND-22-0522 Page 2 of 2 cc:
Regional Administrator, Region II Director, Office of Nuclear Reactor Regulation (NRA)
Director, Vogtle Project Office NRA Senior Resident Inspector-Vogtle 3 & 4
U.S. Nuclear Regulatory Commission ND-22-0522 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0522 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.03.0Bc.i.04 [Index Number 180]
U.S. Nuclear Regulatory Commission ND-22-0522 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.
Inspections/Tests/ Analyses i) A low-pressure injection test and analysis for each CMT, each accumulator, each IRWST injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve(s) in the line being tested. Test fixtures may be used to simulate squib valves.
- 4. Containment Recirculation:
A temporary water supply will be connected to the recirculation lines. All valves in these lines will be open during the test. Sufficient flow will be provided to open the check valves.
Acceptance Criteria i) The injection lin~ flow resistance from each source is as follows:
- 4. Containment Recirculation:
The calculated flow resistance for each containment recirculation line between the containment and the reactor vessel is:
Line A: s 1.33 x 1 o-s ft/gpm2 and Line B: s 1.21 x 1 o-s ft/gpm2*
ITAAC Determination Basis Multiple IT AAC were performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. This IT AAC performed a low-pressure injection test and analysis on each containment recirculation line between the containment and the reactor vessel to demonstrate that the calculated flow resistance meets acceptance criteria.
Performance tests were conducted in accordance with the Unit 4 preoperational test procedure 4-PXS-ITPP-507 (References 1 and 2) which demonstrated that the flow resistance in each containment recirculation line between the containment and the reactor vessel for line A was s 1.33 x 1 o-s ft/gpm2 and for line B was ::s; 1.21 x 10*5 ft/gpm2*
The test installed a temporary valve in the In-containment Refueling Water Storage Tank (IRWST) screen drain lines, installed a jumper between the A and B containment sump injection lines, installed flow test fixtures for the squib valves in the containment recirculation sump lines, filled the IRWST with demineralized water to act as a temporary water supply, and initiated flow from the A screen in the IRWST into the containment recirculation sump to recirculation injection line B to the reactor vessel. Flow was throttled from the A IRWST screen to obtain the flow rate for the design conditions predicted for the ITAAC resistance measurement. All valves in the recirculation line flow path were opened during the test and sufficient flow was provided to open the check valves. The flow rate between the containment sump B and the reactor vessel
U.S. Nuclear Regulatory Commission ND-22-0522 Enclosure Page 3 of 3 injection line, differential pressure, and IRWST level were monitored and recorded. The process was then repeated with IRWST screen 8 to the containment sump to reactor vessel injection line A. The constant value for each flow resistance was calculated based on IRWST level, differential pressure and discharge flow, adjusted for measurement uncertainty, and compared to the acceptance criteria.
The flow resistance for Unit 4 was calculated to be 1.14 x 10-5 ft/gpm2 for the line A containment recirculation flow path and 1.14 x 10-5 ft/gpm2 for the line 8 containment recirculation flow path (References 3 and 4). The Unit 4 test results were documented in Reference 2 and confirm that the calculated flow resistance between each containment sump to reactor vessel via the containment recirculation line flow path meets the IT AAC acceptance criteria.
References 1 through 4 are available for NRC inspection as part of the ITAAC 2.2.03.0Bc.i.04 Completion Package (Reference 5).
IT AAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject IT AAC and associated corrective actions. This review found there were no relevant IT AAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.03.0Bc.i.04 (Reference 5) and is available for NRC review.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.0Bc.i.04 was performed for VEGP Unit 4 and that the prescribed acceptance criteria were met.
Systems, structures, and components verified as part of this IT AAC are being maintained in their as-designed, IT AAC compliant condition in accordance with approved plant programs and procedures.
References (available for NRC inspection)
- 1. 4-PXS-ITPP-507-V1.0-01, Rev. 1.0, "TPC for IRWST Flow Tests"
- 2. SV4-PXS-T0W-1191264, Rev 0, "(ITAAC) Perform Preop Test 4-PXS-ITPP-507"
- 3. SV4-PXS-T2R-020, Rev. 0, "Vogtle Unit 4 4-PXS-ITPP-507 Section 4.3.2 and Section 4.3.4 Containment Recirculation Sump to DVI Nozzle Flow Resistance Test Engineering Report"
- 4. SV4-PXS-T2C-002, Rev. 0, "Vogtle Unit 4 4-PXS-ITPP-507 Section 4.3.2 and Section 4.3.4 Containment Recirculation Sump to DVI Nozzle Flow Resistance Test Calculation"
- 5. 2.2.03.08c.i.04-U4-CP-Rev0, ITAAC Completion Package