ND-18-0818, Vogtie Electric Generating Plant Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.11a.i (Index Number 309): Difference between revisions

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{{#Wiki_filter:Michael J. Yox             7825 River Road k Southern Nuclear                                Regulatory Affairs Director Waynesboro, GA 30830 706-848-6459 tel Vogtie 3 & 4 410-474-8587   celi myox@southernco.com JUL I 8 2819 Docket Nos.:      52-025 52-026 ND-18-0818 10CFR 52.99(c)(3)
{{#Wiki_filter:kSouthern Nuclear JUL I 8 2819 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 celi myox@southernco.com ND-18-0818 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 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.11 a.i [Index Number 3091 Ladies and Gentlemen:
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 2.3.02.11 a.i [Index Number 3091 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 12, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.02.1 la.i [Index Number 309] 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.
Pursuantto 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofJune 12, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.02.1 la.i [Index Number 309] 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 prior to plant operation, as required by 10 CFR 52.103(g).
This notification is informed bythe guidance described in NEI 08-01, Industry Guideline forthe ITAACClosure 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, oranalyses 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.
This letter contains no new NRC regulatory commitments.
If there are any questions, please contact Tom Petrak at 706-848-1575.
If there are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted lAmamb Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4
Respectfully submitted lAmamb Michael J. Yox Regulatory Affairs Director Vogtie 3 &4


==Enclosure:==
==Enclosure:==
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.11 a.i [Index Number 309]
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.02.11 a.i [Index Number 309]
MJY/PGUamw
MJY/PGUamw


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Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
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. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. 8. Klecha Mr. G. Chick Mr. 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 Regulatory Commission Mr. W. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. 8. Klecha Mr. G. Chick Mr. 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 Regulatory 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 Oalethoroe Power Corooration Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
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 Oalethoroe Power Corooration Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson


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Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham
Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham


U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0818 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.1 la.i [Index Number 309]
U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0818 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.1la.i [Index Number 309]


U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 11 .a) The motor-operated and check valves identified in Table 2.3.2-1 perform an active safety-related function to change position as indicated in the table.
U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 11.a) The motor-operatedand check valves identified in Table 2.3.2-1 perform an active safety-related function to change position as indicated inthe table.
Inspections. Tests. Analvses i) Tests or type tests of motor-operated valves will be performed that demonstrate the capability of the valve to operate under its design conditions.
Inspections. Tests. Analvses i) Tests ortypetests ofmotor-operated valves will be performed that demonstrate the capability of the valve to operate under its design conditions.
ii) Inspection will be performed for the existence of a report verifying that the as-built motor-operated valves are bounded by the tested conditions.
ii) Inspection will be performed for the existenceofa report verifying that the as-built motor-operated valves are bounded by the tested conditions.
Acceptance Criteria i) Atest report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions.
Acceptance Criteria i) Atest report existsand concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions.
ii) A report exists and concludes that the as-built motor-operated valves are bounded bythe tests or type tests.
ii) Areport exists and concludes thatthe as-built motor-operated valves are bounded bythe tests or type tests.
ITAAC Completlon Description Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Chemical and Volume Control System (CVS) motor-operated valves identified in the Combined License (COL) Appendix C, Table 2.3.2-1 perform an active safety-related function to change position as indicated inthe table.
ITAAC Completlon Description Multiple Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) are performed to demonstrate that the Chemical and VolumeControl System (CVS) motor-operated valves identified inthe Combined License (COL) Appendix C, Table 2.3.2-1 perform an active safety-related function to change position as indicated inthe table.
h A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under desion conditions.
h A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under desion conditions.
This portion of the subject ITAAC requires tests ortype tests of motor-operated valves to be performed to demonstrate the capability of the valve to operate under its design conditions.
This portion of thesubject ITAAC requires testsortype tests of motor-operated valves tobe performed todemonstrate thecapability of the valve tooperate under its design conditions.
The motor-operated valves identified in COL Appendix C, Table 2.3.2-1 are qualified in accordance with the provisions of American Society of Mechanical Engineers (ASME)
Themotor-operated valves identified in COL Appendix C,Table 2.3.2-1 are qualified in accordance with the provisions of American Society ofMechanical Engineers (ASME)
QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants" (Reference 1).
QME-1-2007, "Qualification ofActive Mechanical Equipment Used in Nuclear Power Plants" (Reference 1).
Functional qualification is performed under the design conditions identified in the design specification for the valves (Reference 2) to demonstrate that each motor-operated valve is qualified to perform its designated function when used in its intended service. In accordance with ASME QME-1-2007, qualification is substantiated by demonstrating the relationship between the service requirements and the type testing and analysis that was conducted as part of this qualification program.
Functional qualification isperformed under thedesign conditions identified in thedesign specification for thevalves (Reference 2) todemonstrate that each motor-operated valve is qualified to perform its designated function when used in its intended service. In accordance with ASME QME-1-2007, qualification is substantiated bydemonstrating the relationship between the service requirements and the typetesting and analysis that was conducted as part of this qualification program.
Type testing is performed, including natural frequency determination, side load static deflection testing, final static seat and stem leakage testing, steam testing, and water testing, for the
Type testing isperformed, including natural frequency determination, side load static deflection testing, final static seat and stem leakage testing, steam testing, and water testing, for the


U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 3 of 5 ranges of the pressure, temperature and flow for each valve and the maximum seat-sealing differential pressure. In accordance with ASME QME-1-2007, the functional qualification process for these motor-operated valve assemblies also included valve and actuator internal inspections and measurement, orientation requirements, seat and stem leakage limitations, diagnostic data collection and analysis methods, static and dynamic flow diagnostic testing, and pressure locking and thermal binding evaluations. The qualification also followed the provisions of ASME QME-1-2007 for the extrapolation of functional qualification to another valve assembly, and demonstration of functional capability of production valve assemblies.
U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 3 of 5 ranges of the pressure, temperature and flowfor each valve and the maximum seat-sealing differential pressure. In accordance with ASME QME-1-2007, the functional qualification process for these motor-operated valve assemblies also included valve and actuator internal inspections and measurement, orientation requirements, seat and stem leakage limitations, diagnostic data collection and analysis methods, static and dynamic flow diagnostic testing, and pressure locking and thermal binding evaluations. The qualification also followed the provisions of ASME QME-1-2007 for the extrapolation of functional qualification to another valve assembly, and demonstration of functional capability of production valve assemblies.
The results of the qualification are documented in the Equipment Qualification (EQ) Reports (Reference 3) which are identified in Attachment A for each applicable valve. These reports summarize the test methodology and ASME QME-1-2007 functional qualification that demonstrate that each motor-operated valve changes position as indicated in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 under design conditions.
The results of the qualification are documented in the Equipment Qualification (EQ) Reports (Reference 3) which are identified in Attachment A for each applicable valve. These reports summarize the test methodology and ASME QME-1-2007 functional qualification that demonstrate that each motor-operated valve changes position as indicated in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 under design conditions.
iil A report exists and concludes that the as-built motor-operated valves are bounded bv the tests or tvpe tests.
iil A report exists and concludes that the as-built motor-operated valves are bounded bv the tests or tvpe tests.
This portion of the subject ITAAC requires that an inspection is performed for the existence of a report verifying that the as-built motor-operated valves are bounded by tests or type tests.
This portion of the subject ITAAC requires that an inspection is performed for the existence of a report verifying that the as-built motor-operated valves are bounded by tests or type tests.
The motor-operated valves in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 are verified by type tests in accordance with ITAAC 2.3.02.1 la.i to demonstrate the capability of the valves to operate under their design conditions. The EQ Reports in Attachment A identify the equipment mounting employed for the testing and the specific conditions tested.
The motor-operated valves in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 are verified by type tests in accordance with ITAAC 2.3.02.1 la.i to demonstrate the capability of the valves to operate under their design conditions. The EQ Reports in Attachment A identifythe equipment mounting employed for the testing and the specific conditions tested.
In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the CVS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verification of equipment make/model/serial number, verification of equipment mounting and location, and verification that the mechanical and electrical connections are bounded by the tested conditions.
In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the CVS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verification of equipment make/model/serial number, verification of equipment mounting and location, and verification that the mechanical and electrical connections are bounded by the tested conditions.
The documentation of installed configuration of the motor-operated valves includes photographs and/or sketches of equipment mounting and connections. The verification of installed component configuration is documented in the As-Built EQ Reconciliation Report(s) (EQRR)
The documentation of installed configuration of the motor-operated valves includes photographs and/or sketches of equipment mounting and connections. The verification of installed component configuration is documented inthe As-Built EQ Reconciliation Report(s) (EQRR)
(Reference 5).
(Reference 5).
Attachment A identifies the EQRR which verify that the installed configuration of the motor-operated valves identified in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 are bounded by the tests or type tests.
Attachment A identifies the EQRR which verifythat the installed configuration of the motor-operated valves identified in VEGP Unit3 and Unit4 COL Appendix C Table 2.3.2-1 are bounded by the tests or type tests.
Together, these EQ Reports and EQRR (References 3 and 5), provide evidence that the ITAAC Acceptance Criteria requirements are met:
Together, these EQ Reports and EQRR (References 3 and 5), provide evidence that the ITAAC Acceptance Criteria requirements are met:
* A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions; and
A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions; and A report exists and concludes that the as-built motor-operated valves are bounded by the tests or type tests.
* A report exists and concludes that the as-built motor-operated valves are bounded by the tests or type tests.


U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.02.11a.i Completion Packages (References 6 and 7, respectively).
U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.02.11a.i Completion Packages (References 6 and 7, respectively).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which includes now-consolidated ITAAC Index 310, found the following relevant ITAAC findings associated with this ITAAC;
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which includes now-consolidated ITAAC Index 310, found the following relevant ITAAC findings associated with this ITAAC; Notice of Nonconformance 99900905/2012-201-01 (closed)
* Notice of Nonconformance 99900905/2012-201-01 (closed)
Notice of Nonconformance 99900905/2012-201 -04 (closed)
* Notice of Nonconformance 99900905/2012-201 -04 (closed)
References favaiiabie for NRG inspection)
References favaiiabie for NRG inspection)
: 1. American Society of Mechanical Engineers (ASME) QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants"
: 1. American Society of Mechanical Engineers (ASME) QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants"
: 2. APP-PV01-Z0-001 Revision X, "3" and Larger Motor Operated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1, 2, and 3"
: 2. APP-PV01-Z0-001 Revision X, "3" and Larger Motor Operated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1, 2, and 3" 3.
: 3. Equipment Qualification (EQ) Reports as identified in Attachment A
Equipment Qualification (EQ) Reports as identified in Attachment A 4.
: 4. ND-XX-XX-001, EQ Walkdown \TAAC Guideline
ND-XX-XX-001, EQ Walkdown \\TAAC Guideline
: 5. As-Built Equipment Qualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4
: 5. As-Built Equipment Qualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4 6.
: 6. 2.3.02.11a.i-U3-CP- RevO, IT/\AC Completion Package
2.3.02.11a.i-U3-CP-RevO, IT/\\AC Completion Package 7.
: 7. 2.3.02.11a.i-U4-CP- RevO, ITAAC Completion Package
2.3.02.11a.i-U4-CP-RevO, ITAAC Completion Package 8.
: 8. NEI 08-01, "Industry Guideline for the IT/\AC Closure Process Under 10 CFR Part 52"
NEI 08-01, "IndustryGuideline for the IT/\\AC Closure Process Under 10 CFR Part 52"


U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 5 of 5 Attachment A System: Chemical and Volume Control System (CVS)
U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 5 of 5 Attachment A System: Chemical and Volume Control System (CVS)
Active      EQ Reports    As-Bullt EQRR Equipment Name
Equipment Name
* Tag No. *               (Reference 3)   (Reference 5)*
* Tag No.
Function
* Active Function
* APP-PV01-VBR-RCS Purification Motor-       CVS-PL-     Transfer       011 /     2.3.02.11a.i-U3-operated Isolation Valve         V001        Closed   APP-PV01-VBR-   EQRR-PCDXXX 012 APP-PV01-VBR-RCS Purification Motor-        CVS-PL-      Transfer        011 /      2.3.02.11a.i-U3-operated Isolation Valve         V002        Closed   APP-PV01-VBR-   EQRR-PCDXXX 012 APP-PV01-VBR-RCS Purification Motor-        CVS-PL-      Transfer        013/      2.3.02.11a.i-U3-operated Isolation Valve         V003        Closed   APP-PV01-VBR-   EQRR-PCDXXX 014 APP-PV01-VBR-CVS Makeup Line                CVS-PL-    Transfer        011 /      2.3.02.11a.i-U3-Containment Isolation Motor-                                           EQRR-PCDXXX V090        Closed   APP-PV01-VBR-operated Valve                                              012 APP-PV01-VBR-CVS Makeup Line                CVS-PL-    Transfer        011 /      2.3.02.11a.i-U3-Containment Isolation Motor-                          APP-PV01-VBR-  EQRR-PCDXXX V091        Closed operated Valve                                              012 Notes:
* EQ Reports (Reference 3)
^ Excerpt from COL Appendix C Table 2.3.2-1
As-Bullt EQRR (Reference 5)*
* The Unit 4 As-Built EQRR are numbered "2.3.02.11a.i-U4-EQRR-PCDXXX"}}
RCS Purification Motor-operated Isolation Valve CVS-PL-V001 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX RCS Purification Motor-operated Isolation Valve CVS-PL-V002 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX RCS Purification Motor-operated Isolation Valve CVS-PL-V003 Transfer Closed APP-PV01-VBR-013/
APP-PV01-VBR-014 2.3.02.11a.i-U3-EQRR-PCDXXX CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V091 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX Notes:
^Excerpt from COL Appendix C Table 2.3.2-1
*The Unit 4 As-Built EQRR are numbered "2.3.02.11a.i-U4-EQRR-PCDXXX"}}

Latest revision as of 18:14, 5 January 2025

Vogtie Electric Generating Plant Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.11a.i (Index Number 309)
ML18171A124
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 06/18/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.3.02.11a, ND-18-0818
Download: ML18171A124 (8)
v • d • e


Text

kSouthern Nuclear JUL I 8 2819 Docket Nos.:

52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 celi myox@southernco.com ND-18-0818 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 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.11 a.i [Index Number 3091 Ladies and Gentlemen:

Pursuantto 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofJune 12, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.02.1 la.i [Index Number 309] 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 bythe guidance described in NEI 08-01, Industry Guideline forthe ITAACClosure 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, oranalyses 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 lAmamb Michael J. Yox Regulatory Affairs Director Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.02.11 a.i [Index Number 309]

MJY/PGUamw

U.S. Nuclear Regulatory Commission ND-18-0818 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. Vox Mr. D. L. Fulton Mr. J. 8. Klecha Mr. G. Chick Mr. 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 Regulatory 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 Oalethoroe Power Corooration Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0818 Page 3 of 3 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. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangells 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0818 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.1la.i [Index Number 309]

U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 11.a) The motor-operatedand check valves identified in Table 2.3.2-1 perform an active safety-related function to change position as indicated inthe table.

Inspections. Tests. Analvses i) Tests ortypetests ofmotor-operated valves will be performed that demonstrate the capability of the valve to operate under its design conditions.

ii) Inspection will be performed for the existenceofa report verifying that the as-built motor-operated valves are bounded by the tested conditions.

Acceptance Criteria i) Atest report existsand concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions.

ii) Areport exists and concludes thatthe as-built motor-operated valves are bounded bythe tests or type tests.

ITAAC Completlon Description Multiple Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) are performed to demonstrate that the Chemical and VolumeControl System (CVS) motor-operated valves identified inthe Combined License (COL) Appendix C, Table 2.3.2-1 perform an active safety-related function to change position as indicated inthe table.

h A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under desion conditions.

This portion of thesubject ITAAC requires testsortype tests of motor-operated valves tobe performed todemonstrate thecapability of the valve tooperate under its design conditions.

Themotor-operated valves identified in COL Appendix C,Table 2.3.2-1 are qualified in accordance with the provisions of American Society ofMechanical Engineers (ASME)

QME-1-2007, "Qualification ofActive Mechanical Equipment Used in Nuclear Power Plants" (Reference 1).

Functional qualification isperformed under thedesign conditions identified in thedesign specification for thevalves (Reference 2) todemonstrate that each motor-operated valve is qualified to perform its designated function when used in its intended service. In accordance with ASME QME-1-2007, qualification is substantiated bydemonstrating the relationship between the service requirements and the typetesting and analysis that was conducted as part of this qualification program.

Type testing isperformed, including natural frequency determination, side load static deflection testing, final static seat and stem leakage testing, steam testing, and water testing, for the

U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 3 of 5 ranges of the pressure, temperature and flowfor each valve and the maximum seat-sealing differential pressure. In accordance with ASME QME-1-2007, the functional qualification process for these motor-operated valve assemblies also included valve and actuator internal inspections and measurement, orientation requirements, seat and stem leakage limitations, diagnostic data collection and analysis methods, static and dynamic flow diagnostic testing, and pressure locking and thermal binding evaluations. The qualification also followed the provisions of ASME QME-1-2007 for the extrapolation of functional qualification to another valve assembly, and demonstration of functional capability of production valve assemblies.

The results of the qualification are documented in the Equipment Qualification (EQ) Reports (Reference 3) which are identified in Attachment A for each applicable valve. These reports summarize the test methodology and ASME QME-1-2007 functional qualification that demonstrate that each motor-operated valve changes position as indicated in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 under design conditions.

iil A report exists and concludes that the as-built motor-operated valves are bounded bv the tests or tvpe tests.

This portion of the subject ITAAC requires that an inspection is performed for the existence of a report verifying that the as-built motor-operated valves are bounded by tests or type tests.

The motor-operated valves in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.2-1 are verified by type tests in accordance with ITAAC 2.3.02.1 la.i to demonstrate the capability of the valves to operate under their design conditions. The EQ Reports in Attachment A identifythe equipment mounting employed for the testing and the specific conditions tested.

In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the CVS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verification of equipment make/model/serial number, verification of equipment mounting and location, and verification that the mechanical and electrical connections are bounded by the tested conditions.

The documentation of installed configuration of the motor-operated valves includes photographs and/or sketches of equipment mounting and connections. The verification of installed component configuration is documented inthe As-Built EQ Reconciliation Report(s) (EQRR)

(Reference 5).

Attachment A identifies the EQRR which verifythat the installed configuration of the motor-operated valves identified in VEGP Unit3 and Unit4 COL Appendix C Table 2.3.2-1 are bounded by the tests or type tests.

Together, these EQ Reports and EQRR (References 3 and 5), provide evidence that the ITAAC Acceptance Criteria requirements are met:

A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions; and A report exists and concludes that the as-built motor-operated valves are bounded by the tests or type tests.

U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.02.11a.i Completion Packages (References 6 and 7, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which includes now-consolidated ITAAC Index 310, found the following relevant ITAAC findings associated with this ITAAC; Notice of Nonconformance 99900905/2012-201-01 (closed)

Notice of Nonconformance 99900905/2012-201 -04 (closed)

References favaiiabie for NRG inspection)

1. American Society of Mechanical Engineers (ASME) QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants"
2. APP-PV01-Z0-001 Revision X, "3" and Larger Motor Operated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1, 2, and 3" 3.

Equipment Qualification (EQ) Reports as identified in Attachment A 4.

ND-XX-XX-001, EQ Walkdown \\TAAC Guideline

5. As-Built Equipment Qualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4 6.

2.3.02.11a.i-U3-CP-RevO, IT/\\AC Completion Package 7.

2.3.02.11a.i-U4-CP-RevO, ITAAC Completion Package 8.

NEI 08-01, "IndustryGuideline for the IT/\\AC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0818 Enclosure Page 5 of 5 Attachment A System: Chemical and Volume Control System (CVS)

Equipment Name

  • Tag No.
  • Active Function
  • EQ Reports (Reference 3)

As-Bullt EQRR (Reference 5)*

RCS Purification Motor-operated Isolation Valve CVS-PL-V001 Transfer Closed APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX RCS Purification Motor-operated Isolation Valve CVS-PL-V002 Transfer Closed APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX RCS Purification Motor-operated Isolation Valve CVS-PL-V003 Transfer Closed APP-PV01-VBR-013/

APP-PV01-VBR-014 2.3.02.11a.i-U3-EQRR-PCDXXX CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090 Transfer Closed APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V091 Transfer Closed APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.3.02.11a.i-U3-EQRR-PCDXXX Notes:

^Excerpt from COL Appendix C Table 2.3.2-1

  • The Unit 4 As-Built EQRR are numbered "2.3.02.11a.i-U4-EQRR-PCDXXX"
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