ND-23-0147, ITAAC Closure Notification on Completion of ITAAC 2.2.04.09a.ii (Index Number 241)

ITAAC Closure Notification on Completion of ITAAC 2.2.04.09a.ii (Index Number 241)

ML23073A247
Person / Time
Site:	Vogtle
Issue date:	03/14/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0147
Download: ML23073A247 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel March 14, 2023 Docket No.:

52-026 ND-23-0147 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 2.2.04.09a.ii [Index Number 241]

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 2.2.04.09a.ii [Index Number 241]. This ITAAC verified that the Main and Startup Feedwater pumps trip to limit feedwater flow to the steam generators. 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, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.09a.ii [Index Number 241]

JMC/CWM/sfr

U.S. Nuclear Regulatory Commission ND-23-0147 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-23-0147 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-23-0147 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.09a.ii [Index Number 241]

U.S. Nuclear Regulatory Commission ND-23-0147 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 9.a) Components within the main steam system, main and startup feedwater system, and the main turbine system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.

Inspections/Tests/Analyses ii) Testing will be performed to confirm the trip of the pumps identified in Table 2.2.4-3.

Acceptance Criteria ii) The pumps identified in Table 2.2.4-3 trip after a signal is generated by the PMS.

ITAAC Determination Basis Multiple ITAAC are performed to verify components within the main steam system, main and startup feedwater system, and the main turbine system identified in Table 2.2.4-3 provide backup isolation of the Steam Generator System (SGS) to limit steam generator blowdown and feedwater flow to the steam generator. The subject ITAAC performs testing to confirm the trip of the pumps identified in Combined License (COL) Appendix C Table 2.2.4-3 (Attachment A) after a trip is generated by the Protection and Safety Monitoring System (PMS).

Testing was performed in accordance with Unit 4 component test Work Orders as documented in SV4-SGS-ITR-800241 (Reference 1). These component tests utilized B-GEN-ITPCI-039 (Reference 3) to direct the performance of testing to verify that the pumps in Attachment A tripped after a signal was generated by the PMS.

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

The completed Unit 4 test results (Reference 1) confirm that the pumps identified in Table 2.2.4-3 trip after a signal is generated by the PMS.

Reference 1 is available for NRC inspection as part of the Unit 4 ITAAC 2.2.04.09a.ii 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 2.2.04.09a.ii (Reference 2) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-23-0147 Enclosure Page 3 of 4 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.04.09a.ii 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-SGS-ITR-800241 Rev 0, UNIT 4 Recorded Results of Main and Startup Feedwater Pump Trip After PMS Signal: ITAAC 2.2.04.09a.ii

2. 2.2.04.09a.ii-U4-CP-Rev0, ITAAC Completion Package

3. B-GEN-ITPCI-039, Version 11.0, PMS CIM Component Test Procedure

U.S. Nuclear Regulatory Commission ND-23-0147 Enclosure Page 4 of 4 Attachment A

• Excerpt from COL Appendix C Table 2.2.4-3 Table 2.2.4-3 Equipment Name*

Tag No.

• Control Function*

Main Feedwater Pump FWS-MP-02A Trip Main Feedwater Pump FWS-MP-02B Trip Main Feedwater Pump FWS-MP-02C Trip Startup Feedwater Pump FWS-MP-03A Trip Startup Feedwater Pump FWS-MP-03B Trip