ND-18-1102, Resubmittal Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.12a.i (Index Number 2481
| ML18235A290 | |
| 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 | |
| ITAAC 2.2.04.12a, ND-18-1102 | |
| Download: ML18235A290 (8) | |
Text
Sk Southern Nuclear AUG 2 0 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-18-1102 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Resubmittal 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 asof August 14, 2018, Vogtle Electric Generating Plant (VEGf^) Unit 3and Unit 4Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.04.12a.i [Index Number 248] 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 Priorto Initial Fuel Load for Item 2.2.04.12a.i [Index Number 248] ND-18-0806
[ML18171A038] dated June 18, 2018. This resubmittal supersedes ND-18-0806 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 NRCto 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,
<4^
Michael J. Yox Regulatory Affairs Direc^r Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.12a.i [Index Number 248]
MJY/SBB/amw
U.S. Nuclear Regulatory Commission ND-18-1102 Page 2 of 3 To:
Southern Nuclear Operating ComDanv/ 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. Yox 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 Reaulatorv 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. Convert Ooiethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1102 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., GDS Associates, Inc.
Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-18-1102 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-1102 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-18-1102 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 12.a) The motor-operated valves identified inTable 2.2.4-1 perform an active safety-related function to change position as indicated in the table.
Insoections/Tests/Analvses i) Tests ortypetests 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 forthe existence ofa reportverifying that the as-built motor-operated valves are bounded by the tests or type tests.
Acceptance Criteria i) Atest report exists and concludesthat each motor-operated valve changes position as indicated in Table 2.2.4-1 under design conditions.
ii) Areport exists and concludesthat the 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 Steam Generator System (SGS) motor-operated valves identified inthe Combined License (COL) Appendix C, Table2.2.4-1 perform an active safety-related function to change position as indicated inthe table.
\\) A test report exists and concludes that each motor-ooerated valve changes position as indicated in Table 2.2.4-1 under design conditions.
This portion ofthe subject ITAAC requires tests ortypetests ofmotor-operated valves to be performed to demonstrate the capability ofthe valve to operate under itsdesign conditions.
The motor-operated valves identified in COL Appendix C, Table2.2.4-1 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 in the design specification for the valves (Reference 2)todemonstrate thateach motor-operated valve is qualified to perform itsdesignated function when used in itsintended service. In accordance with ASME QME-1-2007, qualification is substantiated bydemonstrating the relationship between the sen/ice requirements and the type testing and analysisthat was conducted as part of this qualification program.
Type testing is performed, including natural frequency determination, side load static deflection testing, final staticseat and stem leakagetesting, steam testing, and watertesting, for the
U.S. Nuclear Regulatory Commission ND-18-1102 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 identifiedin 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 Unit3 and Unit 4 COL Appendix 0 Table 2.2.4-1 under design conditions.
ii) A reoort 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 performedforthe existence of a report verifying that the as-built motor-operated valves are bounded by the tests or type tests.
The motor-operated valves in VEGP Unit3 and Unit4 COL Appendix C Table 2.2.4-1 are verified by tests inaccordance with section i) above, to demonstrate the capabilityof the valves to operate under their design conditions. The EQ Reports inAttachmentA identify the 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 SGS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verification of equipment make/model/serialnumber, 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 verificationof installed componentconfiguration 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 inVEGP Unit 3 and Unit 4 COLAppendix 0 Table 2.2.4-1 are bounded by the tests or type tests.
Together, these EQ Reports and EQRR (References3 and 5), provide evidencethat the ITAAC Acceptance Criteria requirements are met:
Atest report exists and concludes that each motor-operated valve changes position as indicated in Table 2.2.4-1 under design conditions; and Areportexists and concludes that the as-built motor-operated valves are bounded by the tests or type tests.
U.S. Nuclear Regulatory Commission ND-18-1102 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit3 and Unit4 ITAAC 2.2.04.12a.i Completion Packages (References 6 and 7, respectively).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a reviewof allfindings 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 NRG 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.
Equipment Qualification (EQ) Reports as 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.
2.2.04.12a.i-U3-CP-RevO, "Completion Package for Unit3 ITAAC 2.2.04.12a.i [Index Number 248]"
7.
2.2.04.12a.i-U4-CP-RevO, "Completion Package for Unit4 ITAAC 2.2.04.12a.i [Index Number 248]"
8.
NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-1102 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.l-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.l-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.l-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.l-U3-EQRR-PCDXXX Notes:
+Excerpt from COL Appendix 0 Table 2.2.4-1
- The Unit 4 As-Bullt EQRR are numbered "2.2.04.12a.l-U4-EQRR-PCDXXX"