ND-22-0521, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.03 (Index Number 179)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.03 (Index Number 179)

ML23020A067
Person / Time
Site:	Vogtle
Issue date:	01/20/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0521
Download: ML23020A067 (1)

Text

~ Southern Nuclear January 20, 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-22-0521 10 CFR 52.99(c)(1)

ITMC Closure Notification on Completion of ITMC 2.2.03.08c.i.03 [Index Number 179]

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 (ITMC) Item 2.2.03.08c.i.03

[Index Number 179], for verifying the In-containment Refueling Water Storage Tank injection line flow resistance values. The closure process for this IT MC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITMC 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,

~an~

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

JMC/DLW/sfr Vogtle Electric Generating Plant (VEGP) Unit 4 ITMC Closure Notification on Completion of ITMC 2.2.03.08c.i.03 [Index Number 1791

U.S. Nuclear Regulatory Commission ND-22-0521 Page 2 of 2 cc:

Regional Administrator, Region II Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-22-0521 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0521 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.2.03.0Bc.i.03 [Index Number 179]

U.S. Nuclear Regulatory Commission ND-22-0521 Enclosure Page 2 of 3 IT AAC 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.

3. IRWST Injection:

The IRWST will be partially filled with water. 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 line flow resistance from each source is as follows:

3. IRWST Injection:

The calculated flow resistance for each IRWST injection line between the IRWST and the reactor vessel is:

Line A: ~ 5.35 x 1 o-6 ft/gpm2 and s 9.09 x 1 o-6 ft/gpm2 and Line B: ~ 6.15 x 10-6 ft/gpm2 and s 1.05 x 10-5 ft/gpm2.

ITAAC Determination Basis Multiple ITMC are 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 ITMC performs a low-pressure injection test and analysis for each In-containment Refueling Water Storage Tank (IRWST) injection line by testing and calculating the flow resistance of each injection line.

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 path from each Unit 4 IRWST injection line to the reactor vessel has a flow resistance~ 5.35 x 10-6 ft/gpm2 ands 9.09 x 1 o-6 ft/gpm2 for line A and a flow resistance ~ 6.15 x 1 o-6 ft/gpm2 and s 1.05 x 10-5 ft/gpm2 for line B.

The test installed flow test fixtures for the squib valves in the IRWST injection lines, isolated the containment sump recirculation lines, filled the IRWST with demineralized water to act as a temporary water supply, and initiated flow between the IRWST injection line A and the reactor vessel. All valves in these lines were opened during the test and sufficient flow was provided to open the check valves. The flow rate between the IRWST and the injection line A to the reactor vessel, differential pressure, and IRWST level were measured. This test was repeated for the IRWST injection line B to the reactor vessel. The constant value for flow resistance was calculated based on measured tank level, differential pressure, discharge flow, adjusted for measurement uncertainty, and compared to the acceptance criteria.

U.S. Nuclear Regulatory Commission ND-22-0521 Enclosure Page 3 of 3 The flow resistance for Unit 4 was calculated to be 8.04 x 1 o-s ft/gpm2 for the IRWST injection line A flow path and 9.49 x 10-6 ft/gpm2 for the IRWST injection line B 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 IRWST injection line flow path and the reactor vessel meet the ITAAC acceptance criteria.

References 1 through 4 are available for NRC inspection as part of the ITAAC 2.2.03.08c.i.03 Completion Package (Reference 5).

List of IT AAC Findings 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 one (1) closed Notice of Nonconformance (NON) associated with this ITAAC.

1. NON 99900404/2011-201-02 (Closed)- ML17346A937 The ITAAC finding review is documented in the ITAAC Completion Package for ITAAC 2.2.03.08c.i.03 (Reference 5) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.i.03 was performed for VEGP Unit 4 and that the prescribed acceptance criteria were 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. 4-PXS-ITPP-507-V1.0-01, Rev. 1, "TPC for IRWST Flow Tests"

2. SV4-PXS-T0W-1191264, Rev. 0, "(ITAAC) Perform Preop Test 4-PXS-ITPP-507"

3. SV4-PXS-T2R-001, Rev. 0, "Vogtle Unit 4 4-PXS-ITPP-507 Section 4.2 IRWST Injection to DVI Nozzle Flow Resistance Test Engineering Report"

4. SV4-PXS-T2C-001, Rev. 0, "Vogtle Unit 4 4-PXS-ITPP-507 Section 4.2 IRWST Injection to DVI Nozzle Flow Resistance Test Calculation"

5. 2.2.03.08c.i.03-U4-CP-Rev0, ITAAC Completion Package