ND-18-1103, Vogtie, Units 3 and 4, Resubmittal Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.11a.i (Index Number 309)
| ML18235A273 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/20/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-1103 | |
| Download: ML18235A273 (8) | |
Text
hk. Southern Nuclear AUG 2 0 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-8459 tei 410-474-8587 ceil myox @southernco.com ND-18-1103 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 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.11a.i [Index Number 3091 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern NuclearOperating Company hereby notifies the NRC that as ofAugust 14,2018, 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 planfor completing this ITAAC. Southern Nuclear Operating Companywill, 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 2.3.02.11 a.i [Index Number 309] ND-18-0818
[ML18171A124] dated June 18,2018. This resubmittal supersedes ND-18-0818 in itsentirety.
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, 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 Michael J. Yox Regulatory Affairs Director Vogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.02.1 la.i [Index Number 309]
MJY/SBB/amw
U.S. Nuclear Regulatory Commission ND-18-1103 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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. J. B. Klecha Mr. G. Chick Mr. M. J. Vox Mr. A. 8. Parton Ms. A. L. Pugh Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. C. T. Defnall Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Reauiatorv Commission Mr. W. Jones (w/o enclosures)
Mr. F. D. Brown Ms. J. M. Heisserer Ms. A. E. Rivera-Varona Mr. M. E. Ernstes Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1103 Page 3 of 3 Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. C. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward 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 Pubiic Service Commission Ms. 8. W. Kernizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-1103 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-1103 Enclosure Vogtle Electric Generating Riant (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-18-1103 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 11.a) The motor-operated and check valves identified inTable 2.3.2-1 performan active safety-related function to change position as indicated inthe table.
Insoections. 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.
Acceotance 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 Completion 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 inthe Combined License (COL) AppendixC, Table 2.3.2-1 perform an active safety-relatedfunction to change position as indicated in the table.
\\) A test reoort exists and concludes that each motor-operated valve chances position as indicated in Table 2.3.2-1 under design conditions.
This portion of thesubject ITAAC requires tests ortype tests of motor-operated valves to be performed todemonstrate the capability of the valve tooperate under its design conditions.
The motor-operated valves identified in COL Appendix C, Table2.3.2-1 are qualified in accordance with the provisions ofAmerican Societyof Mechanical Engineers (ASME)
QME-1-2007, "Qualification of Active Mechanical EquipmentUsed in Nuclear Power Plants" (Reference 1).
Functional qualification is performed underthe design conditions identified inthe design specification for the valves (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 by demonstrating the relationship betweenthe service requirements and the typetestingand analysisthat was conductedas part of this qualification program.
Type testing is performed, including natural frequency determination, sideload static deflection testing, final static seat and stem leakage testing, steam testing, and water testing, for the
U.S. Nuclear Regulatory Commission ND-18-1103 Enclosure Page 3 of 5 ranges ofthe pressure,temperature and flow foreach 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 actuatorinternal 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 andthermal binding evaluations. Thequalification alsofollowed the provisions of ASME QME-1 -2007 forthe extrapolation offunctional qualification to another valve assembly, and demonstration offunctional capability of production valve assemblies.
The resultsofthe qualification are documentedinthe Equipment Qualification (EG) Reports (Reference 3)which are identified in Attachment Afor each applicable valve. These reports summarize the test methodologyand ASME QME-1-2007 functional qualification that demonstratethat each motor-operated valve changes position as indicated in VEGP Unit 3 and Unit 4 CQLAppendixC Table 2.3.2-1 under design conditions.
W) A report exists and concludes that the as-built motor-operated valves are bounded bv the tests or tvoe tests.
This portion of thesubject ITAAC requires that an inspection isperformed for theexistence of a report verifying that the as-built motor-operated valves are bounded bytests ortypetests.
The motor-operated valves in VEGP Unit 3 and Unit 4 CQL Appendix 0 Table2.3.2-1 are verified by tests in accordance with section i) above, todemonstrate thecapability of thevalves tooperate under their design conditions. The EQ Reports in Attachment Aidentify the equipment mounting employed for thetesting andthe specific conditions tested.
In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted ofthe CVS to confirm the satisfactory installation ofthe motor-operated valves. The inspection includes verification of equipment make/model/serial number, verification of equipment mounting and location, andverification thatthe mechanical andelectrical connections are bounded by the tested conditions.
The documentation ofinstalled configuration ofthe motor-operated valves includes photographs and/orsketches ofequipment mounting and connections. The verification of installed component configuration isdocumented in the As-Built EQ Reconciliation Report(s) (EQRR)
(Reference 5).
AttachmentA identifies the EQRRwhich verify that the installedconfiguration of the motor-operated valves identified in VEGP Unit 3 and Unit 4 COL Appendix 0 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:
Atest report exists and concludes thateach motor-operated valve changes position as indicated in Table 2.3.2-1 under design conditions; and Areport exists andconcludes thatthe as-built motor-operated valves are bounded by the tests or type tests.
U.S. Nuclear Regulatory Commission ND-18-1103 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part oftfie 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 plantprocedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review ofall ITAAC findings pertaining tothe subject ITAAC and associated correctiveactions. Thisfinding review, which includes now-consolidated ITAAC Index310, 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 favailable for NRG inspection)
- 1. American Society ofMechanical Engineers (ASME) QME-1 -2007, "Qualification ofActive Mechanical Equipment Used in Nuclear Power Plants"
- 2. APP-PV01 -ZO-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) Reportsas identified in Attachment A 4.
ND-XX-XX-001, EQ Walkdown ITAAC 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
U.S. Nuclear Regulatory Commission ND-18-1103 Enclosure Page 5 of 5 Attachment A System: Chemical and VolumeControl System (CVS)
Equipment Name
- Tag No.
- Active Function
- EQ Reports (Reference 3)
As-Built 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"