ND-22-0601, ITAAC Closure Notification on Completion of ITAAC 2.1.02.09c (Index Number 44)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.09c (Index Number 44)

ML23067A203
Person / Time
Site:	Vogtle
Issue date:	03/08/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0601
Download: ML23067A203 (1)

Text

>. Southern Nuclear March 8, 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-22-0601 10 CFR 52.99(c)(1)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.09c [Index Number 44]

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 2.1.02.09c [Index Number 44]

for verification that controls exist to trip the pressurizer heaters after a signal is generated by the PMS. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the IT AAC 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,

, ~

~man Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

JCM/CWM/sfr Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.09c [Index Number 44]

U.S. Nuclear Regulatory Commission ND-22-0601 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-22-0601 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0601 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of IT AAC 2.1.02.09c [Index Number 44]

U.S. Nuclear Regulatory Commission ND-22-0601 Enclosure Page 2 of 4 IT AAC Statement Design Commitment:

9.c) The pressurizer heaters trip after a signal is generated by the PMS.

Inspection, Tests, Analyses:

Testing will be performed to confirm trip of the pressurizer heaters identified in Table 2.1.2-3.

Acceptance Criteria:

The pressurizer heaters identified in Table 2.1.2-3 trip after a signal is generated by the PMS.

ITAAC Determination Basis Testing was performed to demonstrate the pressurizer heaters trip after a signal is generated by the Protection and Safety Monitoring System (PMS). This testing confirms that the pressurizer heaters identified in Combined Operating License (COL) Appendix C Table 2.1.2-3 (Attachment A) trip after a signal is generated by the PMS.

Testing was performed in accordance with Unit 4 Initial Test Program (ITP) work packages listed in Reference 2. These work packages utilized component test procedure B-GEN-ITPCl-039 (Reference 1) to confirm that the pressurizer heaters identified in Attachment A trip after a signal is generated by the PMS.

Reference 1 established initial conditions with each pressurizer heater breaker closed. An actuation signal was generated by PMS using the PMS Maintenance and Test Panel (MTP) to trip the pressurizer heater 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 provided in Reference 2 confirm that each of the pressurizer heaters identified in Table 2.1.2-3 trip after a signal is generated by the PMS.

Reference 2 is available for NRC inspection as part of the Unit 4 ITAAC 2.1.02.09c 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 IT AAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.1.02.09c (Reference 3) and is available for NRC review.

IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that IT AAC 2.1.02.09c was performed for VEGP Unit 4 and that the prescribed acceptance criteria were met.

U.S. Nuclear Regulatory Commission ND-22-0601 Enclosure Page 3 of 4 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. B-GEN-ITPCl-039, Version 11, "PMS CIM Component Test Procedure"

2. SV4-RCS-ITR-800044, Rev. 0, "Unit 4 Testing Results of Pressurizer Heater Trip: ITAAC 2.1.02.09c NRC Index Number: 44"

3. 2.1.02.09c-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0601 Enclosure Page 4 of 4 Attachment A

• Excerpt from Combined License Appendix C Table 2.1.2-3

• Equipment

• Tag No.

• Control Function Pressurizer Heaters RCS-EH-03 On/Off Pressurizer Heaters RCS-EH-04A On/Off Pressurizer Heaters RCS-EH-04B On/Off Pressurizer Heaters RCS-EH-04C On/Off Pressurizer Heaters RCS-EH-04D On/Off