ND-19-0968, Unit 4 - Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.09 (Index Number 110)

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

ML19221B724
Person / Time
Site:	Vogtle
Issue date:	08/09/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0968
Download: ML19221B724 (10)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei AUG 0 9 2019 Docket Nos.: 52-025 52-026 ND-19-0968 10CFR 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 Resubmittal of 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 August 5, 2019, Vogtie 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.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.01.09 [Index Number 110] ND-18-0664

[ML18197A063], dated Jul. 13, 2018. This resubmittal supersedes ND-18-0664 in its entirety.

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 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.

Mi<<5hael J. Yox Regulatory Affairs Director Vogtie 3 & 4

U.S. Nuclear Regulatory Commission ND-19-0968 Page 2 of 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/JBN/sfr

U.S. Nuclear Regulatory Commission ND-19-0968 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

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

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

Mr. G. Chick Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-0968 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse 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. Z. 8. Harper Mr. J. L. Coward 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 Public Service 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-19-0968 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-19-0968 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-19-0968 Enclosure Page 2 of 6 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 PMS control perform an active safety function after receiving a signal from the PMS.

InsoectionsATests/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 PMS.

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 PMS control perform the active function identified in the table after receiving a signal from PMS.

ITAAC Completion Description Inspections and testing are performed to confirm the valves listed in Combined License(COL)

Appendix C Table 2.2.1-1 (Attachment A) have safety related displays retrievable in the Main Control Room (MCR), controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions, and the valves identified as having Protection and Safety Monitoring System (PMS)control perform the active function identified in the table after receiving a signal from the PMS.

Safetv-related disolavs 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 package work orders (References 1 and 2, respectively), visually confirm that when each of the displays of the plant parameter identified in Attachment A is summoned using the MCR PMS Visual Display Units(VDUs),the expected valve position appears on the PMS VDU.

U.S. Nuclear Regulatory Commission ND-19-0968 Enclosure Page 3 of 6 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 Unit 4(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 havino PMS control perform the active function identified in the table after receivino a sional from PMS.

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 3 and 4). These component test packages utilize B-GEN-ITPCI-039(Reference 5)to direct the performance of test procedures SV3/SV4-CAS-GJP-801 (References 6 and 7), 3/4-CCS-OTS-10-001 (References 8 and 9), 3/4-GEN-OTS 001 (References 10 and 11), 3/4-GEN-OTS-10-002(References 12 and 13), 3/4-GEN-OTS 003(References 14 and 15), 3/4-GEN-OTS-10-004(References 16 and 17), and 3/4-VWS-OTS-10-001 (References 18 and 19)to confirm that the remotely operated valves identified in Attachment A as having PMS control perform the active safety function identified in the table after receiving a signal from the PMS.

References 6 through 19 establish initial conditions with each valve verified locally and in the MCR to be in the open position. An actuation signal is generated by PMS using the PMS Maintenance and Test Panel(MTP)to generate a signal to close the valves in Attachment A.

Each valve is verified locally and in the MCR to be closed. Additionally, for VFS-PL-V800A/B references 10,11,14, and 15 establish initial conditions with each valve verified locally and in the MCR to be in the closed position. An actuation signal is generated by PMS using the PMS Maintenance and Test Panel(MTP)to generate a signal to open the valves. VFS-PL-V800/VB are verified locally and in the MCR to be open. This verifies that the remotely operated valves identified in Table 2.2.2-1 as having PMS control perform the active safety function identified in the table after receiving a signal from the PMS for both Unit 3 and Unit 4.

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 19 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.01.09 Completion Packages(Reference 20 and 21, respectively).

U.S. Nuclear Regulatory Commission ND-19-0968 Enclosure Page 4 of 6 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 ^available for NRG 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. SNCXXXXXX

4. SNCYYYYYY

5. B-GEN-ITPCI-039,"PMS CIM Component Test Procedure"

6. SV3-CAS-GJP-801,"Compressed Air System Valve Stroke Test"

7. SV4-CAS-GJP-801,"Compressed Air System Valve Stroke Test"

8. 3-CCS-0TS-10-001,"Component Cooling Water System Valve Stroke Test"

9. 4-CCS-0TS-10-001,"Component Cooling Water System Valve Stroke Test"

10. 3-GEN-OTS-10-001,"Division A Quarterly Valve Stroke Test" 11.4-GEN-OTS-10-001,"Division A Quarterly Valve Stroke Test"

12. 3-GEN-QTS-10-002,"Division B Quarterly Valve Stroke Test" 13.4-GEN-QTS-10-002,"Division B Quarterly Valve Stroke Test"

14. 3-GEN-QTS-10-003,"Division C Quarterly Valve Stroke Tesf 15.4-GEN-QTS-10-003,"Division C Quarterly Valve Stroke Tesf 16.3-GEN-0TS-10-004,"Division D Quarterly Valve Stroke Tesf 17.4-GEN-QTS-10-004,"Division D Quarterly Valve Stroke Tesf 18.3-VWS-QTS-10-001,"Central Chilled Water System Valve Stroke Test" 19.4-VWS-OTS-10-001,"Central Chilled Water System Valve Stroke Test" 20.2.2.01.09-U3-CP-Rev0, ITAAC Completion Package 21.2.2.01.09-U4-CP-Rev0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0968 Enclosure Page 5 of 6 Attachment A Containment System (CMS) Remotely Operated Valves Display, Control, and Active Function Remotely Safety- Control Active Equipment Name* Tag No.* Operated Related PMS/DAS Function*

Valve* Display*

Instrument Air Supply Outside CAS-PL- Yes(Valve Yes/No YES Transfer Closed Containment Isolation Valve V014 Position)

Component Cooling Water Yes/No System (CCS)Containment CCS-PL- Yes(Valve Isolation Motor-operated Valve YES Transfer Closed V200 Position)

(MOV)- Inlet Line Outside Reactor Containment(ORC)

CCS containment isolation MOV- CCS-PL- Yes(Valve Yes/No YES Transfer Closed outlet line IRC V207 Position)

CCS containment isolation MOV- CCS-PL- Yes(Valve Yes/No YES Transfer Closed outlet line ORC V208 Position)

SFS Discharge Line containment SFS-PL- Yes(Valve Yes/No YES Transfer Closed isolation MOV - ORC V038 Position)

SFS Suction Line containment SFS-PL- Yes(Valve Yes/No YES Transfer Closed isolation MOV - IRC V034 Position)

SFS Suction Line containment SFS-PL- Yes(Valve Yes/No YES Transfer Closed isolation MOV - ORC V035 Position)

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

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

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

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

Vacuum Relief containment VFS-PL- Yes (Valve Yes/No Transfer Closed/

YES isolation A MOV - ORC V800A Position) Transfer Open Vacuum Relief containment VFS-PL- Yes(Valve Yes/No Transfer Closed/

YES isolation B MOV - ORC V800B Position) Transfer Open Fan Cooler Return containment VWS-PL- Yes(Valve Yes/No YES Transfer Closed isolation valve - IRC V082 Position)

Fan Cooler Return containment VWS-PL- Yes(Valve Yes/No YES Transfer Closed isolation valve - ORC V086 Position)

Fan Cooler Supply containment VWS-PL- Yes(Valve Yes/No YES Transfer Closed isolation valve - ORC V058 Position)

Reactor Coolant Drain Tank Yes/No WLS-PL- Yes(Valve Transfer Closed (RCDT)Gas Outlet containment YES V067 Position) isolation valve - IRC RCDT Gas Outlet containment WLS-PL- Yes(Valve Yes/No Transfer Closed YES isolation valve - ORC V068 Position)

U.S. Nuclear Regulatory Commission ND-19-0968 Enclosure Page 6 of 6 Remotely Safety- Control Active Equipment Name* Tag No.* Operated Related RMS/DAS Function*

Valve* Display*

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

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

'Excerpt from COL Appendix C Table 2.2.1-1