ND-18-1104, Unit 4 - Resubmittal Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.12a.i (Index Number 384)
| ML18235A067 | |
| 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 2.3.06.12a.i, ND-18-1104 | |
| Download: ML18235A067 (8) | |
Text
mk. Southern Nuclear AUG 20 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit4 Resubmittal Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.06.12a.i [Index Number 3841 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 2.3.06.12a.i [Index Number 384] 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 Uncomplketed ITAAC 225-days Priorto Initial Fuel Loadfor Item 2.3.06.12a.i [Index Number384] ND-18-0820
[ML18171A143] dated June 19,2018. This resubmittal supersedes ND-18-0820 in itsentirety.
This notification is informed by the guidance described in NEI 08-01, IndustryGuideline 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 completedand 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 Direct Vogtie 3 & 4 7825 River Road Waynestioro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-1104 10CFR 52.99(c)(3)
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.12a.i [Index Number 384]
MJY/SBB/amw
U.S. Nuclear Regulatory Commission ND-18-1104 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. D. L. McKlnney (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 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 Oolethorpe Power Corporation Mr. R. B. Brinkman Municipal Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-1104 Page 3 of 3 Westinqhouse Electric Company. LLC Dr. L. Orlani (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. 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-18-1104 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-1104 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.12a.l [Index Number 384]
U.S. Nuclear Regulatory Commission ND-18-1104 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 12.a) The motor-operatedand check valves identified inTable 2.3.6-1 perform an active safety-related function to change positionas indicated inthe table.
Insoections. Tests. Analvses i) Tests ortype tests of motor-operated valveswill be performed that demonstratethe capability of the valve to operate under its design conditions.
ii) Inspection will be performed forthe existence of a reportverifying that the as-built motor-operated valves are bounded by the tested conditions.
Acceptance Criteria i) Atest reportexists and concludes that each motor-operated valvechanges position as indicated in Table 2.3.6-1 under design conditions.
ii) Areport exists and concludesthat the as-built motor-operated valvesare bounded bythe tested conditions.
ITAAC Completlon Description Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Normal Residual Heat Removal System (RNS) motor-operated valves identified inthe Combined License (COL) Appendix C, Table 2.3.6-1 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 2.3.6-1 under design conditions.
This portion ofthe subject ITAAC requires tests ortypetests ofmotor-operated valves to be performed to demonstratethe capability ofthe valve to operate under itsdesign conditions.
The motor-operated valves identified in COL Appendix C, Table 2.3.6-1 are qualified in accordance with the provisions ofAmerican Societyof 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 inthe design specification for the valves (Reference 2) to demonstrate that each motor-operated valve is qualified to perform itsdesignatedfunction when used in itsintended service. In accordance with ASME QME-1-2007, qualification is substantiated by demonstrating the relationship between the service requirements and the type testing and analysis that was conducted as part of this qualification program.
Type testing is performed, including natural frequency determination, side load staticdeflection testing,final staticseat and stem leakage testing, steam testing, and watertesting, for the
U.S. Nuclear Regulatory Commission ND-18-1104 Enclosure Page 3 of 5 ranges of tfie pressure, temperature and flow for each valve and the maximumseat-sealing differential pressure. Inaccordance withASMEQME-1-2007, the functional qualification process forthese 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 dynamicflow 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 qualificationare documented in the Equipment Qualification (EG) Reports (Reference 3) whichare 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 CQL Appendix C Table 2.3.6-1 under design conditions.
iil A reoort exists and concludes that the as-built motor-operated valves are bounded bv the tested conditions.
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 tested conditions.
The motor-operated valves in VEGP Unit 3 and Unit4 COL Appendix C Table 2.3.6-1 are verified bytests inaccordance with section i) above, to demonstrate the capability of the valves to operate under their design 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 RNS to confirm the satisfactory installation of the motor-operated valves. The inspection includesverification ofequipmentmake/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 installed configuration of the motor-operated valves includes photographs and/or sketches of equipment mounting and connections. The verification of installed componentconfiguration is documentedinthe 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 inVEGP Unit 3 and Unit 4 COLAppendix0 Table 2.3.6-1 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 positionas indicated in Table 2.3.6-1 under design conditions; and A report exists and concludes that the as-built motor-operated valves are bounded by the tested conditions.
U.S. Nuclear Regulatory Commission ND-18-1104 Enclosure Page 4 of 5 References 3 and 5 are available for NRCinspection as part of the Unit 3 and Unit 4 ITAAC 2.3.06.12a.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 385, 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 (available for NRG insDection)
- 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 inAttachment 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.
2.3.06.12a.i-U3-CP-RevO, IT/\\AC Completion Package 7.
2.3.06.12a.i-U4-CP-RevO, ITAAC Completion Package 8.
NEI 08-01,"Industry Guideline forthe ITAAC Closure Process Under10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-1104 Enclosure Page 5 of 5 Attachment A System: Normal Residual Heat Removal System (RNS)
Equipment Name
- Tag No. ^
Active Function
+
EQ Reports (Reference 3)
As-Built EQRR (Reference 5)*
RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 Transfer Closed APP-PV01-VBR-011 /
APP-PV01-VBR-012 2.3.06.12a.i-U3-EQRR-PCDXXX Notes:
- Excerpt from COL Appendix C Table 2.3.6-1
- The Unit 4 As-Built EQRR are numbered "2.3.06.12a.i-U4-EQRR-PCDXXX"