ND-18-1099, Unit 4 - Resubmittal Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.12a.i (Index Number 53)
| ML18235A364 | |
| 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 2.1.02.12a.i, ND-18-1099 | |
| Download: ML18235A364 (8) | |
Text
Southern Nuclear AUG 2 0 2018 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 Docket Nos.:
52-025 52-026 ND-18-1099 10CFR 52.99(c)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit3 and Unit 4 Resubmittal Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.12a.i [Index Number 531 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 14, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.12a.i [Index Number 53]
has not been completed greater than 225-days priorto initial fuel load. The Enclosure describes the planforcompleting this ITAAC. Southern Nuclear Operating Companywill, at a laterdate, 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 2.1.02.12a.i [Index Number 53] ND-18-0845
[ML18177A135] dated June 25, 2018. This resubmittal supersedes ND-18-0845 in its entirety.
This notification is informed by the guidance described in NEI 08-01, Industry Guidelinefor 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 allSection 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,
, '/riAA Michael J. Yox' Regulatory Affairs DirectorVogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.i [Index Number 53]
MJY/SBB/amw
U.S. Nuclear Regulatory Commission ND-18-1099 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. 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. Coovert Oalethorpe Power Corporation Mr. R. B. Brinkman Munlcipai Eiectric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utiiities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1099 Page 3 of 3 Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan 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., GDS 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-18-1099 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-1099 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.i [Index Number 53]
U.S. Nuclear Regulatory Commission ND-18-1099 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 12.a) The automatic depressurizatlon valves identified inTable 2.1.2-1 perform an active safety-related function to change position as indicated in the table.
Insoections. Tests. Analvses i) Tests ortypetests of motor-operated valveswill be performed that demonstratethe capability of the valve to operate under its design conditions.
ii) Inspection will be performed for the existence ofa report verifying thatthe as-built motor-operated valves are bounded by the tests or type tests.
Acceotance Criteria i) Atest report existsand concludes that each motor-operated valve changes position as indicated in Table 2.1.2-1 under design conditions.
ii) Areport exists and concludes thatthe as-built motor-operated valves are bounded by the tests or type tests.
ITAAC Completion Description Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Reactor Coolant System (RCS) motor-operated valves identified inthe Combined License (COL) Appendix C, Table2.1.2-1 perform an active safety-related function to change position as indicated in the table.
h A test report exists and concludes that each motor-operated valve chances oosition as indicated in Table 2.1.2-1 under design conditions.
This portion ofthe subject ITAAC requires tests ortype tests of motor-operated valves to be performed to demonstrate the capability of the valve to operateunder itsdesign conditions.
The motor-operated valves identified in COL Appendix C, Table 2.1.2-1 are qualified in accordancewith the provisions ofAmerican Society of Mechanical Engineers (ASME)
QME-1-2007, "Qualification of Active Mechanical Equipment Used 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 service requirements and the typetestingand analysisthat was conductedas part of this qualification program.
Type testing isperformed, including natural frequency determination, side load static deflection testing, final static seat andstem leakage testing, steamtesting, andwater testing, for the
U.S. Nuclear Regulatory Commission ND-18-1099 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.
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 Unit3 and Unit 4 COL Appendix 0 Table 2.1.2-1 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 portionof the subject ITAAC requires that an inspection is performed for the existence of a report verifyingthat the as-built motor-operated valves are bounded by tests or type tests.
The motor-operated valves in VEGP Unit3 and Unit4 COL Appendix C Table 2.1.2-1 are verified bytests inaccordance with section i) above, to demonstrate the capability of the valves to operate under theirdesign conditions. The EQ Reports inAttachmentAidentify 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 RCS 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 mountingand 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 inVEGP Unit 3 and Unit 4 COLAppendix0 Table 2.1.2-1 are bounded by the tests or type tests.
Together,these EQ Reportsand 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 2.1.2-1 under design conditions; and A report exists and concludes that the as-builtmotor-operated valves are bounded by the tests or type tests.
U.S. Nuclear Regulatory Commission ND-18-1099 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit3 and Unit4 ITAAC 2.1.02.12a.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 ofall ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which includes now-consolidated ITAAC Index 54, found the following relevant ITAAC findings associated withthis 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 of Mechanical Engineers (ASME) QME-1 -2007, "Qualification of Active 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 inAttachment A 4.
ND-XX-XX-001, "EQ Walkdown IT/V\\C Guideline"
- 5. As-Built Equipment Qualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4 6.
2.1.02.12a.i-U3-CP-Rev0, IT/\\AC Completion Package 7.
2.1.02.12a.i-U4-CP-Rev0, IT/\\AC Completion Package 8.
NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-1099 Enclosure Page 5 of 5 Attachment A System: Reactor Coolant System (RCS)
Equipment Name
- Tag No. +
Active Function
- EQ Reports (Reference 3)
As-Built EQRR (Reference 5)*
First-stage ADS Motor-operated Valve (MOV)
RCS-PL-V001A Transfer Open APP-PV01-VBR-013/
APP-PV01-VBR-014 2.1.02.12a.i-U3-EORR-PCDXXX First-stage ADS MOV RCS-PL-V001B Transfer Open APP-PV01-VBR-013/
APP-PV01-VBR-014 2.1.02.12a.i-U3-EORR-PCDXXX Second-stage ADS MOV RCS-PL-V002A Transfer Open APP-PV01-VBR-013/
APP-PV01-VBR-014 2.1.02.12a.i-U3-EORR-PCDXXX Second-stage ADS MOV RCS-PL-V002B Transfer Open APP-PV01-VBR-013/
APP-PV01-VBR-014 2.1.02.12a.i-U3-EQRR-PCDXXX Third-stage ADS MOV RCS-PL-V003A Transfer Open APP-PV01-VBR-013/
APP-PV01-VBR-014 2.1.02.12a.i-U3-EORR-PCDXXX Third-stage ADS MOV RCS-PL-V003B Transfer Open APP-PV01-VBR-013/
APP-PV01-VBR-014 2.1.02.12a.i-U3-EORR-PCDXXX First-stage ADS Isolation MOV RCS-PL-V011A Transfer Open APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.1.02.12a.i-U3-EORR-PCDXXX First-stage ADS Isolation MOV RCS-PL-V011B Transfer Open APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.1.02.12a.i-U3-EORR-PCDXXX Second-stage ADS Isolation MOV RCS-PL-V012A Transfer Open APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.1.02.12a.i-U3-EORR-PCDXXX Second-stage ADS Isolation MOV RCS-PL-V012B Transfer Open APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.1.02.12a.i-U3-EORR-PCDXXX Third-stage ADS Isolation MOV RCS-PL-V013A Transfer Open APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.1.02.12a.i-U3-EORR-PCDXXX Third-stage ADS Isolation MOV RCS-PL-V013B Transfer Open APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.1.02.12a.i-U3-EORR-PCDXXX Notes:
Excerpt from COL Appendix C Table 2.1.2-1
- The Unit 4 As-Built EQRR are numbered "2.1.02.12a.i-U4-EQRR-PCDXXX"