ND-22-0646, ITAAC Closure Notification on Completion of ITAAC 2.1.02.13b (Index Number 64)

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ITAAC Closure Notification on Completion of ITAAC 2.1.02.13b (Index Number 64)
ML23073A275
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/14/2023
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0646, ITAAC 2.1.02.13b
Download: ML23073A275 (1)


Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel March 14, 2023 Docket No.: 52-026 ND-22-0646 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 2.1.02.13b [Index Number 64]

Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), Southern Nuclear Operating Company hereby notifies the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP) Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.13b [Index Number 64]. This ITAAC confirms that the Reactor Coolant Pumps (RCP) trip after receiving a signal from the Protection and Safety Monitoring System (PMS). 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 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 10 CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.13b [Index Number 64]

JMC/MKO/sfr

U.S. Nuclear Regulatory Commission ND-22-0646 Page 2 of 2 cc: Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

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

U.S. Nuclear Regulatory Commission ND-22-0646 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0646 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.13b [Index Number 64]

U.S. Nuclear Regulatory Commission ND-22-0646 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 13.b) The RCPs trip after receiving a signal from the PMS.

Inspections/Tests/Analyses Testing will be performed using real or simulated signals into the PMS.

Acceptance Criteria The RCPs trip after receiving a signal from the PMS.

ITAAC Determination Basis Testing was performed to verify the Reactor Coolant Pumps (RCPs) trip after receiving a signal from the Protection and Safety Monitoring System (PMS).

Testing was performed in accordance with Unit 4 ITP Work Packages listed and documented in SV4-RCS-ITR-800064 (Reference 1). These component tests utilized B-GEN-ITPCI-039 (Reference 3) to direct the performance of testing to confirm that the RCPs tripped after a signal was generated from the PMS.

These component tests established initial conditions with each RCP breaker in the test position and closed. An actuation signal was generated by PMS using the PMS Maintenance and Test Panel (MTP) to trip the RCP breakers. Each breaker was verified locally to be open (trip position) after the receipt of the trip signal.

The completed Unit 4 component test results were reviewed in Reference 1 and confirmed that the VEGP Unit 4 RCPs trip after a signal was generated from the PMS.

Reference 1 is available for NRC inspection as part of the Unit 4 ITAAC 2.1.02.13b Completion Package (Reference 2).

ITAAC 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 ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.1.02.13b (Reference 2) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-22-0646 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.13b 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. SV4-RCS-ITR-800064, Rev. 0, Unit 4 Testing Results for Reactor Coolant Pump Trip from PMS: ITAAC 2.1.02.13b, NRC Index Number: 64
2. 2.1.02.13b-U4-CP-Rev0, ITAAC Completion Package
3. B-GEN-ITPCI-039, Version 11.0, PMS CIM Component Test Procedure