ND-18-1100, Vogtie, Units 3 and 4, Resubmittal Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.11a.i (Index Number 114)
| ML18235A302 | |
| 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-18-1100 | |
| Download: ML18235A302 (8) | |
Text
Southern Nuclear AUG 2 0 2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit3 and Unit4 Resubmittal Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.11a.i [Index Number 1141 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating 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 2.2.01.Ila.i [Index Number 114] has not been completedgreater 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 completed225-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 2.2.01.11 a.i [Index Number 114] ND-18-0816
[ML18171A053] datedJune 18, 2018. This resubmittal supersedes ND-18-0816 in its entirety.
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 plantoperation, 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 DirectorA/ogtle 3 &4 Michael J. Yox Regulatory Affairs Director Vogtie 3 &4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 ceil myox@southernco.com ND-18-1100 10CFR 52.99(c)(3)
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.11 a.i [IndexNumber 114]
MJY/SBB/amw
U.S. Nuclear Regulatory Commission ND-18-1100 Page 2 of 3 To:
Southern Nuclear Operating Companv/ 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 Reoulatorv 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 Oolethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1100 Page 3 of 3 Westlnqhouse 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. 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. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham
U.S. Nuclear Regulatory Commission ND-18-1100 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-1100 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.11a.l [Index Number 114]
U.S. Nuclear Regulatory Commission ND-18-1100 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 11.a) The motor-operated and check valves identified inTable 2.2.1-1 performan active safety-related function to change position as indicated inthe table.
Insoections. Tests. Analvses i) Tests ortypetests ofmotor-operated valves will be performed to demonstrate the capability of each valve to operate under design conditions.
ii) Inspection will be performed for the existenceofa report verifying that the as-built motor-operated valves are bounded by the tests or type tests.
Acceotance Criteria i) Atest report exists and concludesthat each motor-operated valve changes position as indicated in Table 2.2.1-1 under design conditions.
ii) Areport exists and concludes thatthe as-built motor-operated valves are bounded bythe tests or type tests.
ITAAC ComDietion Description Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Containment System (CMS) motor-operatedvalves identified inthe Combined License (COL) Appendix C, Table2.2.1-1 perform an activesafety-related function to change position as indicated inthe table.
\\) A test reoort exists and concludes that each motor-operated valve changes position as indicated in Table 2.2.1-1 under design conditions.
This portion ofthe subject ITAAC requires tests ortypetests ofmotor-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, Table2.2.1-1 are qualified in accordance with 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 designconditions identified in the design specification for the valves (Reference 2)to demonstrate thateach motor-operated valve is qualified to perform itsdesignatedfunction when used in itsintended service. In accordance with ASME QME-1-2007, qualification is substantiated bydemonstrating the relationship between the sen/ice requirementsand the type testingand 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, steamtesting, and water testing, for the
U.S. Nuclear Regulatory Commission ND-18-1100 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 collectionand analysis methods, static and dynamic flow diagnostic testing, and pressure lockingand thermal binding evaluations. The qualification also followed the provisions of ASME QME-1-2007 for the extrapolation of functional qualificationto another valve assembly, and demonstration of functional capability of production valve assemblies.
The results of the qualification are documented inthe Equipment Qualification (EQ) Reports (Reference 3) whichare identified inAttachment Afor each applicable valve. These reports summarize the test methodology and ASME QME-1-2007functional qualification that demonstrate that each motor-operated valve changes position as indicated in VEGP Unit3 and Unit4 CQL Appendix C Table 2.2.1-1 under design conditions.
ii) A report exists and concludes that the as-built motor-operated valves are bounded bv the tests or tvoe tests.
Thisportion ofthe subject ITAAC requires that an inspection is performed for the existence ofa reportverifying that the as-built motor-operatedvalves are bounded by tests or type tests.
The motor-operated valves inVEGP Unit 3 and Unit 4 COL Appendix 0 Table 2.2.1-1 are verified bytests in accordance with section i) above, to demonstratethe capability ofthe valves to operate undertheirdesign conditions. The EQ Reports inAttachment Aidentify the equipmentmounting employedforthe testing and the specific conditions tested.
In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the CMS 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 thatthe mechanical and electrical connections are bounded by the tested conditions.
The documentation of installed configuration ofthe 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)
(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 2.2.1-1 are bounded by the tests or type tests.
Together, these EQ Reports and EQRR (References 3 and 5), provide evidence thatthe ITAAC Acceptance Criteria requirements are met:
Atest report exists and concludes that each motor-operated valve changes position as indicated in Table 2.2.1-1 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-18-1100 Enclosure Page 4 of 5 References 3 and 5 are available for NRG Inspection as part of the Unit 3 and Unit 4ITAAC 2.2.01.11a.l Completion Packages (References 6 and 7, respectively).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern NuclearOperating 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 Index115, found the following relevant ITAAC finding associated with this ITAAC:
Unresolved Item (URI)05200025/2017002-02 (closed)
References favaiiable for NRG inspection)
- 1. American Societyof Mechanical Engineers (ASME) QME-1 -2007, "Qualification of Active Mechanical Equipment Used In Nuclear Power Plants"
- 2. APP-PV11 -ZO-001 Revision X, "Design Specification for Butterfly Valves, ASME Boiler and Pressure Vessel Code Section III, Class 2 and 3"
- 3. Equipment Qualification (EQ) Reports as Identified In Attachment A 4.
ND-XX-XX-001, EQ Walkdown ITAAC Guideline
- 5. As-Bullt EquipmentQualification Reconciliation Reports (EQRR) as Identified In Attachment A for Units 3 and 4 6.
2.2.01.11a.l-U3-CP-RevO, ITAAC Completion Package 7.
2.2.01.11 a.l-U4-CP-RevO, ITAAC Completion Package 8.
NEI 08-01, "IndustryGuideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-1100 Enclosure Page 5 of 5 Attachment A System: Containment System (CNS)
Equipment Name
- Tag No. +
Active Function
- EQ Reports (Reference 3)
As-Bullt EQRR (Reference 5)*
Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV) - Inlet Line Outside Reactor Containment (ORC)
CCS-PL-V200 Transfer Closed APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX CCS Containment Isolation MOV - Outlet Line IRC CCS-PL-V207 Transfer Closed APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX CCS Containment Isolation MOV - Outlet Line ORC CCS-PL-V208 Transfer Closed APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX SFS Discharge Line Containment Isolation MOV
-ORC SFS-PL-V038 Transfer Closed APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX SFS Suction Line Containment Isolation MOV
-IRC SFS-PL-V034 Transfer Closed APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX SFS Suction Line Containment Isolation MOV
-ORC SFS-PL-V035 Transfer Closed APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX Vacuum Relief Containment Isolation A MOV - ORC VFS-PL-V800A Transfer Closed /
Transfer Open APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11 a.i-U3-EORR-PCDXXX Vacuum Relief Containment Isolation 8 MOV - ORC VFS-PL-V800B Transfer Closed /
Transfer Open APP-PV11-VBR-005/
APP-PV11-VBR-006 2.2.01.11a.i-U3-EORR-PCDXXX Notes:
Excerpt from COL Appendix C Table 2.2.1-1
- The Unit 4 As-Built EQRR are numbered "2.2.01.11a.i-U4-EQRR-PCDXXX"