ND-20-0750, ITAAC Closure Notification on Completion of ITAAC 2.1.02.11b.i (Index Number 48)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.11b.i (Index Number 48)

ML22151A313
Person / Time
Site:	Vogtle
Issue date:	05/31/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0750
Download: ML22151A313 (7)

Text

Ja mie M. Coleman 7825 River Road

>,. Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848 -6926 tel

MAY 3 1 2022

Docket No.: 52-025

ND-20-0750 1 O 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 3 ITAAC Closure Notification on Completion of ITAAC 2.1.02.11 b.i (Index Number 481

In accordance with 1 O CFR 52.99(c)(1 ), the purpose of this letter is to notify the Nuclear Regulato ry Commission (NRC) of the comp letion of Vogtle Electric Generating Plant (VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02. 11 b.i (Index Number 481 for verification that the valves identified in Vogtle Electric Generating Plant Combined License Append ix C Table 2.1.2 - 1 as having protection and safety monito ring system (PMS) control perform an active safety function after receiving a signal from the PMS. The closure process for this ITAAC is based on the guidance desc ribed in NEI 08-01, " Industry Guideline for the ITAAC Closure Process under 1 O CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulato ry commitments. Southern Nuclear Operating Company (SNC ) requests NRC staff confirmation of this determination and publication of the required not ice in the Federal Register per 1 O CFR 52.99.

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

Respectfully submitted,

~ ma ~

Regulatory Affairs Direc tor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02. 11 b.i (Index Number 481

JMC / DLW / sfr U.S. Nuclear Regulatory Commission ND-20-0750 Page 2 of 3

To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chambe rlain Mr. J.C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06

cc :

Nuclear Regula tory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Dav is Mr. J. Vasquez Mr. J. Earg le Ms. K. Mccurry Mr. J. Parent Mr. B. G riman Mr. V. Hal l U.S. Nuclear Regulatory Commission ND-20-0750 Page 3 of 3

Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

Dalton Utilities Mr. T. Bundros

Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S. L. Zwack

Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham U.S. Nuclear Regulatory Commission ND-20-0750 Enclosure Page 1 of 4

Southern Nuclear Operating Company ND-20-0750 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.1.02.11 b.i [Index Number 48]

U.S. Nuclear Regulatory Commission ND-20-0750 Enclosure Page 2 of 4

ITAAC Statement

Design Commitment

11.b) The valves identified in Table 2.1.2-1 as having PMS control perform an active safety function after receiving a signal from the PMS.

Inspections/Tests/ Analyses

i) Testing will be performed on the squib valves identified in Table 2.1.2-1 using real or simulated signals into the PMS without stroking the valve.

Acceptance Criteria

i) The squib valves receive a signal at the valve electrical leads that is capable of actuating the squib valve.

ITAAC Determination Basis

Multiple ITAAC are performed to verify that the valves identified in Combined License (COL)

Appendix C Table 2.1.2-1 (Attachment A) as having Protection and Safety Monitoring System (PMS) control perform an active safety function after receiving a signal from PMS. The subject ITAAC performed testing on the squib valves listed in Attachment A.

Testing was performed in accordance with preoperational tests and component work orders listed in Reference 1 to verify that the valves identified in Attachment A as having PMS control perform an active safety function after receiving a signal from PMS. Testing was performed on the squib valves identified using real and simulated signals into the PMS without stroking the valve and ensured the squib valves receive a signal at the valve electrical leads that is capable of actuating the squib valve.

Squib valve actuation signals generated in the PMS were sent to the Component Interface Modules (CIMs), resulting in an actuation of the CIM for the respective squib valve. The CIM is a safety-related component located inside the respective PMS cabinets which provides the capability for on / off control of individual safety-related plant components. Squib valve actuation signals output from the actuated CIM are sent to the respective squib valve through the squib valve controller. To provide overlap, the Reference 1 component test work orders verified that when PMS controls were operated in the Main Control Room (MCR), the CIM was actuated and a signal was received at the squib valve controlle r. From the squib valve controller, the Reference 1 preoperational tests used a test tool connected to the squib valve controller to initiate a test signal and verify the signal was received at the squib valve electrical leads.

The Reference 1 component test work orders for each squib valve identified in Attachment A were conducted by manually initiating a PMS signal from the MCR using the PMS Safety Display Panel Automatic Depressurization System (ADS) stage 4 squib valve soft controls. The squib valve actuation signal from the CIM was verified locally by measuring the arming and firing voltages at the Squib Valve Controller (SVC) cabinet. Each squib valve identified in Attachment A had the electrical leads disconnected to prevent stroking the valve.

U.S. Nuclear Regulatory Commission ND-20-0750 Enclosure Page 3 of 4

The Reference 1 preoperational tests for each squib valve identified in Attachment A were conducted by connecting a PMS SVC Test tool to the SVC. Circuit resistance was measured and inside and outside containment temperatures were measured at multiple locations and were used to calculate the circuit resistance expected during accident conditions. The calculated circuit resistances were verified to meet the minimum and maximum allowable resistances. The circuit resistance information was used to determine the circuit resistance input to the PMS SVC Test Tool. A multimeter along with a temporary data acquisition system was connected to the PMS SVC Test Tool to determine voltage and signal duration. The PMS SVC Test Tool was then used to initiate an arm and test fire sequence. Firing current was determined from the voltage measurements taken during the arm and test fire sequence.

The minimum signal necessary to actuate the squib valves is specified in valve design information as at least 3.7 amperes for 1 O milliseconds. The information recorded during testing of duration and voltage was utilized to confirm that a sufficient test signal was received at each of the squib valves.

The test results identified in Reference 1 confirmed that each squib valve, identified in Attachment A, receives an electrical signal at the valve electrical leads that is capable of actuating the squib valve after a signal is input to the PMS.

Reference 1 is available for NRC inspection as part of the Unit 3 ITAAC 2.1.02.11 b.i 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 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 for ITAAC 2.1.02. 11 b.i Completion Package (Reference 2) and is available for NRC review.

IT AAC Completion Statement

Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.11 b.i was performed for VEGP Unit 3 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. SV3-RCS-ITR-800048, Rev. 1, ITAAC Technical Report, "Unit 3 Testing Results of RCS Squib Valve: ITAAC 2.1.02.11 b.i, NRC Index Number: 48"

2. 2.1.02.11 b.i-U3-CP-Rev0, "ITAAC Completion Package" U.S. Nuclear Regulatory Commission ND-20-0750 Enclosure Page 4 of 4

Attachment A*

Eauipment Name TaQ No. Control PMS/ DAS Fourth-stage ADS Squib RCS-PL-V004A Yes/Yes Valve Fourth-stage ADS Squib RCS-PL-V004B Yes/Yes Valve Fourth-stage ADS Squib RCS-PL-V004C Yes/Yes Valve Fourth-stage ADS Squib RCS-PL-V004D Yes/Yes Valve

• Excerpt from COL App C Table 2.1.2-1