ND-18-0666, Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.11b (Index Number 118)

Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.11b (Index Number 118)

ML18152B741
Person / Time
Site:	Vogtle
Issue date:	05/31/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0666
Download: ML18152B741 (8)

Text

Michael J. Yox 7825 River Road k Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel 410-474-8587 ceii myox@southernco.com MAY 3 12018 Docket Nos.: 52-025 52-026 ND-18-0666 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.11b [Index Number 118]

Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of May 29, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01 .lib [Index Number 118]

has not beencompleted 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 befully 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 prior to 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 Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.11b [Index Number 118]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0666 Page 2 of 3 To:

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

M . M. D. Rauckhorst (w/o enclosures)

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

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

Nuclear Reaulatorv 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 Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Ooiethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0666 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (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. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia PublicService Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0666 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0666 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.11b [Index Number 118]

U.S. Nuclear Regulatory Commission ND-18-0666 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 11 .b) After loss of motive power, the remotely operated valves identified in Table 2.2.1-1 assume the indicated loss of motive power position.

Insoections/Tests/Analvses Testing ofthe remotely operated valves will be performed underthe conditions of loss of motive power.

Acceptance Criteria After loss of motive power, each remotelyoperated valve identified in Table 2.2.1-1 assumes the indicated loss of motive power position.

ITAAC Completion Description Testing is performed under the conditions of loss of motive power to verify the remotely operated valves identified in Table 2.2.1-1 of the Combined License (COL) Appendix C, (Attachment A), assume the indicated loss of motive power position. The testing verifies that the valves in Attachment A assume the indicated loss of motive power position.

The testing is performed in accordance with the Unit 3 and Unit 4 component test package work orders (References 1 and 2, respectively) for the Containment System (CNS) valves identified in Attachment A under the conditions of loss of motive power. The air-operated valves (AOVs) are placed into the open position, then the power to the air supply solenoid isdeenergized, which results in both isolation of compressed air supplyfrom the valves and venting of the actuator.

The valve position of each of thevalves is locally inspected to confirm that the valves failed closedafter motive power removal. The motor-operated valves (MOVs) are positioned as necessary for plant conditions, power is removed and thevalves are verified locally to fail as is.

The Unit 3 and Unit 4 component test results (References 1 and 2, respectively) confirm that each remotely operated valve identified in Attachment Aassumes the indicated loss of motive power position.

References 1 and 2 are available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.2.01 .lib Completion Packages (References 3 and 4, 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 reviewfound there are no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-18-0666 Enclosure Page 3 of 5 References ^available for NRG inspection)

1. SNC920991, "CNS Remotely Operated Valve Stroke Test ITAAC:SV3-2.2.01 .lib"

2. XXXXXX, "CNS Remotely Operated Valve Stroke Test ITAAC:SV4-2.2.01 .lib"

3. 2.2.01.11b-U3-CP-RevO, ITAAC Completion Package

4. 2.2.01.11b-U4-CP-RevO, ITAAC Completion Package

5. NEI 08-01, "IndustryGuideline for tfie ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0666 Enclosure Page 4 of 5 Attachment A ONS Remotely Operated Valves Remotely Loss of Motive Equipment Name* Tag No.* Operated Vaive Type Power Position

• Valve

• Instrument Air Supply Outside AOV CAS-PL-V014 Yes Closed Containment Isolation Valve Component Cooling Water System (CCS) Containment Isolation Motor-operated CCS-PL-V200 Yes As Is MOV Valve (MOV) - Inlet Line Outside Reactor Containment (ORC)

CCS Containment Isolation CCS-PL-V207 Yes As Is MOV MOV - Outlet Line IRC CCS Containment isolation CCS-PL-V208 Yes As Is MOV MOV - Outlet Line ORC SFS Discharge Line Containment SFS-PL-V038 Yes As Is MOV Isolation MOV - ORC SFS Suction Line Containment SFS-PL-V034 Yes As Is MOV Isolation MOV - IRC SFS Suction Line Containment SFS-PL-V035 Yes As Is MOV Isolation MOV - ORC Containment Purge Inlet Containment Isolation VFS-PL-V003 Yes Closed AOV Valve - ORC Containment Purge Inlet Containment Isolation VFS-PL-V004 Yes Closed AOV Valve - IRC Containment Purge Discharge VFS-PL-V009 Yes Closed AOV Containment Isolation Valve-IRC Containment Purge Discharge Containment Isolation VFS-PL-V010 Yes Closed AOV Vaive - ORC

U.S. Nuclear Regulatory Commission ND-18-0666 Enclosure Page 5 of 5 Attachment A CMS Remotely Operated Valves Remotely Loss of Motive Equipment Name* Tag No.* Operated Valve Type Power Position

• Valve

• Vacuum Relief Containment VFS-PL-V800A Yes As Is MOV Isolation A MOV - ORC Vacuum Relief Containment VFS-PL-V800B Yes As Is MOV Isolation B MOV - ORC Fan Coolers Return Containment VWS-PL-V082 Yes Closed AOV Isolation Valve - IRC Fan Coolers Return Containment VWS-PL-V086 Yes Closed AOV Isolation Valve - ORC Fan Coolers Supply Containment VWS-PL-V058 Yes Closed AOV Isolation Valve - ORC Reactor Coolant Drain Tank (RCDT) Gas Outlet WLS-PL-V067 Yes Closed AOV Containment Isolation Valve - IRC RCDT Gas Outlet Containment WLS-PL-V068 Yes Closed AOV Isolation Valve - ORC Sump Discharge Containment WLS-PL-V055 Yes Closed AOV Isolation Valve - IRC Sump Discharge Containment WLS-PL-V057 Yes Closed AOV Isolation Valve - ORC Excerpt from COL Appendix C Table 2.2.1-1