ND-18-0664, Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.09 (Index Number 110)

Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.09 (Index Number 110)

ML18197A063
Person / Time
Site:	Vogtle
Issue date:	07/13/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0664
Download: ML18197A063 (8)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 706-848-6459 tel Vogtle 3 & 4 410-474-8587 cell myox@southernco.com JUL 1 3 2018 Docket Nos.: 52-025 52-026 ND-18-0664 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.09 [Index Number 1101 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 5, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.09 [Index Number 110]

has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met priorto plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.09 [Index Number 110]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0664 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Ms. A. C. Chamberlain Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Mr. P. B. Donnelly Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman Municipai Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-0664 Page 3 of 3 Westinqhouse Electric Company. LLC Dr. L. OrlanI (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. CorlettI Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hesler, 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 Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-0664 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0664 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.09 [Index Number 110]

U.S. Nuclear Regulatory Commission ND-18-0664 Enclosure Page 2 of 5 ITAAC Statement Design Commitment

9. Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

10.a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions.

lO.b) The valves identified in Table 2.2.1-1 as having RMS control perform an active safety function after receiving a signal from the RMS.

Inspections/Tests/Analvses Inspection will be performed for retrievability of the safety-related displays in the MCR.

Stroke testing will be performed on remotely operated valves identified in Table 2.2.1-1 using the controls in the MCR.

Testing will be performed on remotely operated valves listed in Table 2.2.1-1 using real or simulated signals into the RMS.

Acceptance Criteria Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.1-1 to perform active safety functions.

The remotely operated valves identified in Table 2.2.1-1 as having RMS control perform the active function identified in the table after receiving a signal from RMS.

ITAAC Completion Description This ITAAC requires that inspection and testing be performed to confirm the valves listed in Combined License (COL) Appendix C Table 2.2.1-1 have safety related displays retrievable in the Main Control Room (MCR), controls in the MCR cause the valves to perform active safety functions, and the valves perform the active function identified in the table after receiving a signal from the Rrotection and Safety Monitoring System (RMS).

Safetv-related displavs identified in Table 2.2.1-1 can be retrieved in the MCR Inspections performed in accordance with the Unit 3 and Unit 4 component test packagework orders (References 1 and 2, respectively), visually confirm that when each ofthe displays ofthe plant parameter identified in Attachment A is summoned using the MCR RMS Visual Display Units (VDUs), the expected valve position appears on the RMS VDU.

U.S. Nuclear Regulatory Commission ND-18-0664 Enclosure Page 3 of 5 Controls in the MGR operate to cause remotely operated valves identified in Table 2.2.1-1 to perform active safety functions Using Plant Control System (PLS) controls in the MCR, stroke testing each valve in Attachment A is performed in accordance with component test package work orders for Unit 3 and Unit4 (References 1 and 2, respectively). Each valve is stroked to its active function and proper valve position indication is verified locally and in the MCR. This testing demonstrates PLS controls in the MCR operate to cause the remotely operated valves identified in COL Appendix C Table 2.2.1-1 to perform their active safety functions.

The remotelv operated valves identified in Table 2.2.1-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS Testing is performed on the valves identified in Attachment A in accordance with preoperational tests for Unit 3 and Unit 4 (References 3 and 4, respectiveiy). The valves are placed into the required position, a containment high pressure signal is then simulated on the outlet of 2 ofthe 4 PMS containment pressure transmitters, and the valves are verified to perform their active function. Low containment pressure signals are generated to test the second active function of the containment vacuum relief motor operated isolation valves. This testing verifies the remotely operated valves identified in COL Appendix C Table 2.2.1-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

Together, these test results (References 1 through 4) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

• Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.1-1 to perform active safety functions.

• The remotely operated valves identified in Table 2.2.1-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

References 1 through 4 are available for NRC inspection as partofthe Unit 3 and Unit 4 ITAAC 2.2.01.09 Completion Packages (Reference 5 and 6, respectively).

List of ITAAC Findings 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 finding review, which includes now-consolidated ITAAC Indexes 111 and 112, found there are no relevant ITAAC findings associated with this ITAAC.

References favaiiabie for NRC inspection)

1. SNC920991 ,"CNS Remotely Operated Valve Stroke Test - ITAAC:SV3- 2.2.01.09"

2. SNCXXXXXX, "CNS Remotely Operated Valve Stroke Test - ITAAC:SV4- 2.2.01.09"

3. 3-PMS-ITPP-523, "Containment Pressure High-2 Actuation Preoperational Test Procedure"

4. 4-PMS-ITPP-523, "Containment Pressure High-2 Actuation Preoperational Test Procedure"

U.S. Nuclear Regulatory Commission ND-18-0664 Enclosure Page 4 of 5

5. 2.2.01.09-U3-CP-Rev0, ITAAC Completion Package

6. 2.2.01.09-U4-CP-Rev0, ITAAC Completion Package

7. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0664 Enclosure Page 5 of 5 Attachment A Containment System (CMS) Remotely Operated Valves Display and Active Function Remotely Safety-Active Equipment Name* Tag No.* Operated Related Function*

Valve* Display*

Instrument Air Supply Outside CAS-PL- Yes (Valve YES Transfer Closed Containment Isolation Valve V014 Position)

Component Cooling Water System (CCS)

Containment Isolation Motor-operated CCS-PL- Yes (Valve YES Transfer Closed Valve (MOV) - Inlet Line Outside Reactor V200 Position)

Containment (ORC)

CCS containment isolation MOV- outlet CCS-PL- Yes (Valve YES Transfer Closed line IRC V207 Position)

CCS containment isolation MOV- outlet CCS-PL- Yes (Valve YES Transfer Closed line ORC V208 Position)

SFS Discharge Line containment isolation SFS-PL- Yes (Valve YES Transfer Closed MOV - ORC V038 Position)

SFS Suction Line containment isolation SFS-PL- Yes (Valve YES Transfer Closed MOV-IRC V034 Position)

SFS Suction Line containment isolation SFS-PL- Yes (Valve YES Transfer Closed MOV-ORC V035 Position)

Containment Purge Inlet containment VFS-PL- Yes (Valve YES Transfer Closed isolation valve -ORC V003 Position)

Containment Purge Inlet containment VFS-PL- Yes (Valve YES Transfer Closed isolation valve - IRC V004 Position)

Containment Purge Discharge VFS-PL- Yes (Valve YES Transfer Closed containment isolation valve - IRC V009 Position)

Containment Purge Discharge VFS-PL- Yes (Valve YES Transfer Closed containment isolation valve -ORC V010 Position)

Vacuum Relief containment isolation A VFS-PL- Yes (Valve Transfer Closed/

YES MOV - ORC V800A Position) Transfer Open Vacuum Relief containment isolation B VFS-PL- Yes (Valve Transfer Closed/

YES MOV - ORC V800B Position) Transfer Open Fan Cooler Return containment isolation VWS-PL- Yes (Valve YES Transfer Closed valve - IRC V082 Position)

Fan Cooler Return containment isolation VWS-PL- Yes (Valve YES Transfer Closed valve - ORC V086 Position)

Fan Cooler Supply containment isolation VWS-PL- Yes (Valve YES Transfer Closed valve - ORC V058 Position)

Reactor Coolant Drain Tank (RCDT) Gas WLS-PL- Yes (Valve YES Transfer Closed Outlet containment isolation valve - IRC V067 Position)

RCDT Gas Outlet containment isolation WLS-PL- Yes (Valve YES Transfer Closed valve - ORC V068 Position)

Sump Discharge containment isolation WLS-PL- Yes (Valve YES Transfer Closed valve - IRC V055 Position)

Sump Discharge containment isolation WLS-PL- Yes (Valve YES Transfer Closed valve - ORC V057 Position)

'Excerpt from COL Appendix C Table 2.2.1-1