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)
| 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
k Southern Nuclear MAY 3 12018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 ceii myox@southernco.com ND-18-0666 10 CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit4 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 theguidance 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 tosupport theCommission 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 anyquestions, 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
M M
M M
M M
M M
M
. D. A. Bost (w/o enclosures)
. M. D. Rauckhorst (w/o enclosures)
. M. D. Meier
. D. H. Jones (w/o enclosures)
. D. L. McKinney
. M. J. Vox
. D. L. Fulton
. J. B. Klecha G. Chick 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, GeorgiaPublicService 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 inTable 2.2.1-1 assume the indicated loss of motive power position.
Insoections/Tests/Analvses Testing ofthe remotely operatedvalves will be performed underthe conditions oflossofmotive power.
Acceptance Criteria After loss of motive power, each remotelyoperated valve identified inTable 2.2.1-1 assumes the indicated loss of motive power position.
ITAAC Completion Description Testing isperformed under the conditions of lossof motive power toverify the remotely operated valves identified in Table 2.2.1-1 of the Combined License (COL) Appendix C, (Attachment A), assume theindicated loss of motive power position. The testing verifies that the valves in Attachment A assume the indicated loss of motive power position.
The testing isperformed in accordance with the Unit 3 and Unit 4 component test package work orders (References 1and 2, respectively) for theContainment System (CNS) valves identified in Attachment A under the conditions of loss of motive power. The air-operated valves (AOVs) are placed into theopen position, then thepower tothe air supply solenoid isdeenergized, which results inboth isolation ofcompressed airsupplyfrom the valvesand venting ofthe actuator.
The valve position of each of thevalves islocally inspected toconfirm that thevalves failed closedafter motive power removal. The motor-operated valves (MOVs) are positioned as necessary for plant conditions, power isremoved and thevalves areverified locally to fail as is.
The Unit 3 and Unit 4 component test results (References 1 and2, respectively) confirm that each remotely operated valve identified in Attachment Aassumes theindicated 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 tothesubject 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, "IndustryGuidelinefor 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 Equipment Name*
Tag No.*
Remotely Operated Valve
- Loss of Motive Power Position
- Vaive Type Instrument Air Supply Outside Containment Isolation Valve CAS-PL-V014 Yes Closed AOV Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV)- Inlet Line Outside Reactor Containment (ORC)
CCS-PL-V200 Yes As Is MOV CCS Containment Isolation MOV - Outlet Line IRC CCS-PL-V207 Yes As Is MOV CCS Containment isolation MOV - Outlet Line ORC CCS-PL-V208 Yes As Is MOV SFS Discharge Line Containment Isolation MOV - ORC SFS-PL-V038 Yes As Is MOV SFS Suction Line Containment Isolation MOV - IRC SFS-PL-V034 Yes As Is MOV SFS Suction Line Containment Isolation MOV - ORC SFS-PL-V035 Yes As Is MOV Containment Purge Inlet Containment Isolation Valve - ORC VFS-PL-V003 Yes Closed AOV Containment Purge Inlet Containment Isolation Valve - IRC VFS-PL-V004 Yes Closed AOV Containment Purge Discharge Containment Isolation Valve-IRC VFS-PL-V009 Yes Closed AOV Containment Purge Discharge Containment Isolation Vaive - ORC VFS-PL-V010 Yes Closed AOV
U.S. Nuclear Regulatory Commission ND-18-0666 Enclosure Page 5 of 5 Attachment A CMS Remotely Operated Valves Equipment Name*
Tag No.*
Remotely Operated Valve
- Loss of Motive Power Position
- Valve Type Vacuum Relief Containment Isolation A MOV - ORC VFS-PL-V800A Yes As Is MOV Vacuum Relief Containment Isolation B MOV - ORC VFS-PL-V800B Yes As Is MOV Fan Coolers Return Containment Isolation Valve - IRC VWS-PL-V082 Yes Closed AOV Fan Coolers Return Containment Isolation Valve - ORC VWS-PL-V086 Yes Closed AOV Fan Coolers Supply Containment Isolation Valve - ORC VWS-PL-V058 Yes Closed AOV Reactor Coolant Drain Tank (RCDT) Gas Outlet Containment Isolation Valve - IRC WLS-PL-V067 Yes Closed AOV RCDT Gas Outlet Containment Isolation Valve - ORC WLS-PL-V068 Yes Closed AOV Sump Discharge Containment Isolation Valve - IRC WLS-PL-V055 Yes Closed AOV Sump Discharge Containment Isolation Valve - ORC WLS-PL-V057 Yes Closed AOV Excerptfrom COLAppendixC Table 2.2.1-1