ND-20-0748, 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)

ML21130A599
Person / Time
Site:	Vogtle
Issue date:	05/10/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.1.02.09c, ND-20-0748
Download: ML21130A599 (7)

Text

^ ,1 l. I I MichaelJ. Yox 7825 River Road

^OUtn0rn lNUCl03r Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 te!

MAY 1 0 2021 Docket No.: 52-025 ND-20-0748 10CFR 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 3 ITAAC Closure Notification on Completion of ITAAC 2.1.02.09c (Index Number 441 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) Units 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 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.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.1.02.09c [Index Number 44]

MJY/GRS/sfr

U.S. Nuclear Regulatory Commission ND-20-0748 Enclosure Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M.Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reaulatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil C. P. Patel

. G. J. Khouri C. J. Even B. J. Kemker Ms. N. C. Coovert M C. Welch M . J. Gaslevic M . O. Lopez-Santiago M . G. Armstrong M M. Webb M . T. Fredette M . C. Santos M B. Davis M . J. Vasquez M . J. Eargle M E. Davidson M . T. Fanelli Ms. K. McCurry M . J. Parent M B. Griman

U.S. Nuclear Regulatory Commission ND-20-0748 Enclosure Page 3 of 3 Oaiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. OrianI Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Sen/Ice Commission Mr. R. L. Trokey, Georgia Public Sen/Ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Batch BIngham

U.S. Nuclear Regulatory Commission ND-20-0748 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-0748 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.1.02.09c [Index Number 44]

U.S. Nuclear Regulatory Commission ND-20-0748 Enclosure Page 2 of 4 ITAAC Statement Design Commitment:

9.C) The pressurizer heaters trip after a signal is generated by the RMS.

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 RMS.

ITAAC Determination Basis Testing was performed to demonstrate the pressurizer heaters trip after a signal is generated by the Protection and Safety Monitoring System (RMS). 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 RMS.

Testing was performed in accordance with Unit 3 Initial Test Program (ITR) work package 1109892(Reference 1). This work package utilized component test procedure B-GEN-ITRCI-039(Reference 2)to confirm that the pressurizer heaters identified in Attachment A trip after a signal is generated by the RMS.

References 1 and 2 established initial conditions with each pressurizer heater breaker closed.

An actuation signal was generated by RMS using the RMS Maintenance and Test Panel(MTR) 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 3 component test results (reference 1), reviewed in Reference 3 confirm that each of the pressurizer heaters identified in Table 2.1.2-3 trip after a signal is generated by the RMS.

Reference 3 is available for NRC inspection as part of the ITAAC 2.1.02.09c Completion Package (Reference 4).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company(SNC) performed a review of all ITAAC 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 for ITAAC 2.1.02.09c(Reference 4) and is available for NRC review.

ITAAC Compietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.09c was performed for VEGR Unit 3 and that the prescribed acceptance criteria were met.

U.S. Nuclear Regulatory Commission ND-20-0748 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 NRG Inspection)

1. WO 1109892,"PMS CIM Component Test for ECS Components ITAAC; SV3-2.1.02.09c and 2.1.02.13b"

2. B-GEN-ITPCI-039,"Version 7, PMS CIM Component Test Procedure"

3. SV3-PMS-ITR-800044, Rev. 0,"Unit 3 Testing Results of Pressurizer Heater Trip: ITAAC 2.1.02.09c NRC Index Number: 44"

4. 2.1.02.09c-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-20-0748 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