ND-18-0806, Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.12a.i (Index Number 248)
| ML18171A038 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/18/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0806 | |
| Download: ML18171A038 (8) | |
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Southern Nuclear JUL 1 8 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 Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-0806 10CFR 52.99(c)(3)
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 2.2.04.12a.i [Index Number 2481 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 6, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) 2.2.04.12a.i [Index Number 248]
has not been completed greater than 225-days priorto initial fuel load. The Enclosure describes the plan for completingthis 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 letter contains no new NRC regulatory commitments.
If there are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted.
ij/ninam(o Michael J. Yox Regulatory Affairs Director Vogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit4 Completion Plan for Uncompleted ITAAC 2.2.04.12a.i [Index Number 248]
MJY/LBP/amw
U.S. Nuclear Regulatory Commission ND-18-0806 Page 2 of 3 To:
Southern Nuclear Operatina Company/ Georgia Power Company M
M M
M M
M M
M M
D. A. Bost (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 M
M M
A. 8. Parton W. A. Sparkman C. E. Morrow Ms. K. M. Stacy M
M M. K. Washington 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 Oalethorpe Power Corporation Mr. R. B. Brinkman
U.S. Nuclear Regulatory Commission ND-18-0806 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. C. 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., GDS Associates, Inc.
Mr. 8. Roetger, Georgia PublicService 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-18-0806 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0806 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.12a.l [Index Number 248]
U.S. Nuclear Regulatory Commission ND-18-0806 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 12.a) The motor-operated valves Identified In Table 2.2.4-1 perform an activesafety-related function to change position as Indicated Inthe table.
Insoectlons/Tests/Analvses I) Tests ortype tests of motor-operated valves will be performed to 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-bullt motor-operated valves are bounded by the tests or type tests.
Acceptance Criteria I) Atest report exists andconcludes thateach motor-operated valve changesposition as Indicated InTable 2.2.4-1 under design conditions.
II) Areport exists and concludes that the as-bullt motor-operated valves are bounded by the tests or type tests.
ITAAC Comnletion Description Multiple Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) are performed to demonstratethat the Steam GeneratorSystem (SGS) motor-operated valves Identified In the Combined License (COL) Appendix C,Table 2.2.4-1 perform an active safety-related function to change positionas Indicated In the table.
h Atest report exists and concludes that each motor-operated valve chances position as Indicated In Table 2.2.4-1 under desion conditions.
This portion of the subject ITAAC requires testsortype testsof motor-operated valves tobe performed todemonstrate the capability of the valve to operate under Its design conditions.
The motor-operated valves Identified In COL Appendix C, Table 2.2.4-1 are qualified In accordance with the provisions of American Society of Mechanical Engineers (ASME)
QME-1-2007, "Qualification ofActive Mechanical Equipment Used In Nuclear Power Plants" (Reference 1).
Functional qualification Is performed under thedesign 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 bydemonstrating the relationship between the service requirements and the type testing and analysis thatwasconducted 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
U.S. Nuclear Regulatory Commission ND-18-0806 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 flowdiagnostic 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 Afor 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 Unit4 COL Appendix C Table 2.2.4-1 under design conditions.
iil A reoort exists and concludes that the as-built motor-ooerated valves are bounded bv the tests or tvoe tests.
This portion ofthe subject ITAAC requiresthat an inspection is performed forthe existence ofa report verifying that the as-built motor-operated valves are bounded by the tests or type tests.
The motor-operated valves inVEGP Unit 3 and Unit 4 CQLAppendixC Table 2.2.4-1 are verified bytypetests in accordancewith ITAAC 2.2.04.12a.i to demonstrate the capability ofthe valvesto operate undertheirdesign conditions. The EQ Reports in Attachment Aidentify the equipment mounting employedforthe testing and the specificconditionstested.
In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the SGS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verification ofequipment 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 installedconfiguration ofthe motor-operated valves includes photographs and/or sketches ofequipmentmounting and connections. The verification of installed component configuration is documented in the 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 Unit 3 and Unit 4 CQL Appendix C Table 2.2.4-1 are bounded by the tests or type tests.
Together, these EQ Reports and EQRR (References 3 and5), provide evidence that the ITAAC Acceptance Criteria requirements are met:
Atest report existsand concludesthat each motor-operated valve changes position as indicated in Table 2.2.4-1 under design conditions; and Areport exists and concludes thatthe as-built motor-operated valves are bounded by the tests or type tests.
U.S. Nuclear Regulatory Commission ND-18-0806 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit3 and Unit4ITAAC 2.2.04.12a.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 findings pertaining to the subject ITAAC and associated corrective actions. This finding review which includes now-consolidated ITAAC 249, found there are no relevant ITAAC findings associated with this ITAAC.
References ^available for NRC inspection)
- 1. American Society of Mechanical Engineers (ASME) QME-1 -2007, "Qualification ofActive Mechanical Equipment Used in Nuclear Power Plants"
- 2. APP-PV01 -ZO-001 Revision X, "3" and Larger MotorOperated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1,2, and 3"
- 3. EquipmentQualification (EQ) Reports as identified inAttachmentA 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. 2.2.04.12a.i-U3-CP-RevO, "Completion Package for Unit 3 ITAAC 2.2.04.12a.i [Index Number 248]"
- 7. 2.2.04.12a.i-U4-CP-RevO, "Completion Package for Unit 4 ITAAC 2.2.04.12a.i [Index Number 248]"
- 8. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0806 Enclosure Page 5 of 5 Attachment A System: Steam Generator System (SGS)
Equipment Name ^
Tag No. +
Active Function +
EQ Reports (Reference 3)
As-Built EQRR (Reference 5)*
Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Transfer Closed APP-PV01-VBR-013/
APP-PV01-VBR-014 2.2.04.12a.i-U3-EQRR-PCDXXX Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B Transfer Closed APP-PV01-VBR-013/
APP-PV01-VBR-014 2.2.04.12a.i-U3-EQRR-PCDXXX Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.2.04.12a.i-U3-EQRR-PCDXXX Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067B Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.2.04.12a.i-U3-EQRR-PCDXXX Notes:
+Excerpt from COL Appendix C Table 2.2.4-1
- The Unit 4 As-Built EQRR are numbered "2.2.04.12a.i-U4-EQRR-PCDXXX"