ND-22-0759, ITAAC Closure Notification on Completion of ITAAC 2.1.02.08e (Index Number 40)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.08e (Index Number 40)

ML22292A223
Person / Time
Site:	Vogtle
Issue date:	10/19/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.1.02.08e, ND-22-0759
Download: ML22292A223 (5)

Text

A Southern Nuclear Jamie M. Coleman Regu latory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel OCT 1 9 2022 Docket No.: 52-026 ND-22-0759 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington , DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.1.02.08e [Index Number 40]

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 2.1.02.08e [Index Number 40].

This ITAAC verified that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 lbm/sec at 2500 psia in the Reactor Coolant System (RCS) . The closure process for this ITAAC is based on the guidance described in NEl-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, C(jOJVwt (yu~

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.08e [Index Number 40]

JMC/PAW/sfr

U.S. Nuclear Regulatory Commission ND-22-0759 Enclosure 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-22-0759 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0759 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.0Se [Index Number 40]

U.S. Nuclear Regulatory Commission ND-22-0759 Enclosure Page 2 of 3 ITAAC Statement Design Commitment:

8.e) The RCS provides emergency letdown during design basis events.

Inspections, Tests, Analyses:

Inspections of the reactor vessel head vent valves and inlet and outlet piping will be conducted.

Acceptance Criteria:

A report exists and concludes that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 lbm/sec at 2500 psia in the RCS.

ITAAC Determination Basis The Reactor Coolant System (RCS) provides emergency letdown during design basis events. This ITAAC performs inspections of the reactor vessel head vent (RVHV) valves and inlet and outlet piping to verify that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 lbm/sec at 2500 psia in the RCS.

The flow capacity of the RVHV pipe routing is restricted (choked) up to the orifice downstream of the RVHV valves RCS-PL-V1 SOC and D. The flow resistance of the RVHV valves and inlet and outlet piping was calculated with Darcy's formula using line routing information (i.e. , pipe length, pipe diameter, number and type of pipe fittings, entrance/exit losses and valves) (Reference 2).

Following installation , inspections of construction records were performed to verify the line routing information of the RVHV inlet and outlet piping including valves up to the downstream orifice is consistent with the information in the flow capacity design calculation . The inspection results documented in Reference 1 verify that there is negligible difference between the as-designed and as-built RVHV piping configuration. The calculated RVHV flow capacity of 12.34 lbm/sec at 2500 psia in the RCS remains valid for the as-built system configuration.

The inspection results documented in Reference 1 verify that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 lbm/sec at 2500 psia in the RCS , which meets the ITAAC acceptance criteria. References 1 and 2 are available for NRC inspection as part of the ITAAC Completion Package (Reference 3).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion , Southern Nuclear Operating Company (SNC) performed a review of all lTAAC 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 (Reference 3) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-22-0759 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.0Se 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. SV4-RCS-ITR-800040 Rev 0, "Unit 4 Inspections and Associated Analysis of the RCS Reactor Vessel Head Vent Line: ITAAC 2.1.02.08e NRC Index Number 40"

2. APP-RCS-M3C-067 Rev 4, "Orifice Functional Requirements for RCS (Reactor Coolant System) Reactor Vessel Head Vent Flow Orifices (APP-RCS-PY-R01A/B)"

3. 2.1 .02.08e-U4-CP-Rev0, ITAAC Completion Package"