ND-18-0664, 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) | |
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Southern Nuclear JUL 1 3 2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0664 10CFR 52.99(c)(3)
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 ofJuly 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 priorto initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern NuclearOperating 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 Guidelinefor 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 inthe MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions.
lO.b) The valvesidentified 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 ofthe safety-relateddisplays in the MCR.
Stroke testing will be performed on remotely operatedvalves identified in Table2.2.1-1 using the controls in the MCR.
Testing will be performed on remotely operated valveslisted inTable 2.2.1-1 using real or simulated signals into the RMS.
Acceptance Criteria Safety-related displays identified inTable 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 Table2.2.1-1 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 Table2.2.1-1 have safety relateddisplays retrievable in the Main Control Room (MCR), controls in the MCR cause the valvesto perform active safety functions, and the valves perform the activefunction identified inthe 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 accordancewith the Unit 3 and Unit 4 component test packagework orders (References 1 and 2, respectively), visually confirm thatwhen each ofthe displays ofthe plant parameter identified in Attachment Aissummoned 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 inthe 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 inAttachmentA in accordance with preoperational tests for Unit 3 and Unit 4 (References 3 and 4, respectiveiy). The valves are placed intothe required position, a containment high pressure signal is then simulated on the outletof2 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 activefunction of the containmentvacuum reliefmotoroperated isolation valves. This testing verifiesthe remotely operated valves identified in COL Appendix C Table2.2.1-1 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 evidencethat the ITAAC Acceptance Criteria requirements are met:
Safety-related displays identified inTable 2.2.1-1 can be retrieved in the MCR.
Controls inthe 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 NuclearOperating Company (SNC) performed a review ofall findings pertaining to the subject ITAAC and associated correctiveactions. 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 StrokeTest - ITAAC:SV3-2.2.01.09"
- 2. SNCXXXXXX, "CNS RemotelyOperated ValveStroke 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, "ContainmentPressure 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 Equipment Name*
Tag No.*
Remotely Operated Valve*
Safety-Related Display*
Active Function*
Instrument Air Supply Outside Containment Isolation Valve CAS-PL-V014 YES Yes (Valve Position)
Transfer Closed Component Cooling Water System (CCS)
Containment Isolation Motor-operated Valve (MOV) - Inlet Line Outside Reactor Containment (ORC)
CCS-PL-V200 YES Yes (Valve Position)
Transfer Closed CCS containment isolation MOV-outlet line IRC CCS-PL-V207 YES Yes (Valve Position)
Transfer Closed CCS containment isolation MOV-outlet line ORC CCS-PL-V208 YES Yes (Valve Position)
Transfer Closed SFS Discharge Line containment isolation MOV - ORC SFS-PL-V038 YES Yes (Valve Position)
Transfer Closed SFS Suction Line containment isolation MOV-IRC SFS-PL-V034 YES Yes (Valve Position)
Transfer Closed SFS Suction Line containment isolation MOV-ORC SFS-PL-V035 YES Yes (Valve Position)
Transfer Closed Containment Purge Inlet containment isolation valve -ORC VFS-PL-V003 YES Yes (Valve Position)
Transfer Closed Containment Purge Inlet containment isolation valve - IRC VFS-PL-V004 YES Yes (Valve Position)
Transfer Closed Containment Purge Discharge containment isolation valve - IRC VFS-PL-V009 YES Yes (Valve Position)
Transfer Closed Containment Purge Discharge containment isolation valve -ORC VFS-PL-V010 YES Yes (Valve Position)
Transfer Closed Vacuum Relief containment isolation A MOV - ORC VFS-PL-V800A YES Yes (Valve Position)
Transfer Closed/
Transfer Open Vacuum Relief containment isolation B MOV - ORC VFS-PL-V800B YES Yes (Valve Position)
Transfer Closed/
Transfer Open Fan Cooler Return containment isolation valve - IRC VWS-PL-V082 YES Yes (Valve Position)
Transfer Closed Fan Cooler Return containment isolation valve - ORC VWS-PL-V086 YES Yes (Valve Position)
Transfer Closed Fan Cooler Supply containment isolation valve - ORC VWS-PL-V058 YES Yes (Valve Position)
Transfer Closed Reactor Coolant Drain Tank (RCDT) Gas Outlet containment isolation valve - IRC WLS-PL-V067 YES Yes (Valve Position)
Transfer Closed RCDT Gas Outlet containment isolation valve - ORC WLS-PL-V068 YES Yes (Valve Position)
Transfer Closed Sump Discharge containment isolation valve - IRC WLS-PL-V055 YES Yes (Valve Position)
Transfer Closed Sump Discharge containment isolation valve - ORC WLS-PL-V057 YES Yes (Valve Position)
Transfer Closed
'Excerpt from COL Appendix C Table 2.2.1-1