ND-18-0820, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.12a.i (Index Number 384)
| ML18171A143 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/19/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.3.06.12a.i, ND-18-0820 | |
| Download: ML18171A143 (8) | |
Text
ik. Southern Nuclear JUL 19 2018 Docket Nos.:
52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynestxsro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-0820 10CFR 52.99(c)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit3 and Unit 4 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 ofJune 12, 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 greaterthan 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.
This notification is informed bythe guidance described in NEI 08-01, Industry Guideline forthe 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, oranalyses have not been performed or have beenonly partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submittedto 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, uWniJaiuflh -ftr Michael J. Yox Regulatory Affairs Director Vogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.06.12a.i [Index Number 384]
MJY/PGL/amw
U.S. Nuclear Regulatory Commission ND-18-0820 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. 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 Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0820 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. 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. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., CDS 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-18-0820 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0820 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.12a.i [Index Number 384]
U.S. Nuclear Regulatory Commission ND-18-0820 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 12.a) The motor-operated and check valves identified inTable 2.3.6-1 performan active safety-related function to change position as indicated in the 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.
Acceotance Criteria i) Atest report existsand concludes that each motor-operated valve changes position as indicated in Table 2.3.6-1 under design conditions.
ii) Areport exists andconcludes thatthe as-built motor-operated valves are bounded by the tested conditions.
ITAAC Completion 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.
h A test report exists and concludes that each motor-operated valve chances position as indicated in Table 2.3.6-1 under desion conditions.
This portion of thesubject ITAAC requires tests ortype tests of motor-operated valves to be performed todemonstrate thecapability of the valve tooperate under its design conditions.
Themotor-operated valves identified in COL Appendix C,Table 2.3.6-1 are qualified in accordancewith the provisions ofAmerican Society of Mechanical Engineers (ASME)
QME-1-2007, "Quaiification ofActive Mechanical Equipment Used in Nuclear Power Plants" (Reference 1).
Functional qualification isperformed under the design conditions identified in the design specification for thevalves (Reference 2) todemonstrate thateachmotor-operated valve is qualified toperform 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 andthe type testing and analysis thatwasconducted as part of this qualification program.
Type testing isperformed, inciuding natural frequency determination, side load static deflection testing, final static seat andstem leakage testing, steam testing, andwater testing, for the
U.S. Nuclear Regulatory Commission ND-18-0820 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 Unit4 COL Appendix C Table 2.3.6-1 under design conditions.
iil A report exists and concludes that the as-built motor-operated valves are bounded bv the tested conditions.
This portion of the subject ITAAG requires that an inspection is performedforthe existence of a report verifying that the as-builtmotor-operated valves are bounded bythe tested conditions.
The motor-operated valves in VEGP Unit 3 and Unit 4 COLAppendixC Table 2.3.6-1 are verified bytypetests in accordancewith ITAAC 2.3.06.12a.i to demonstrate the capability ofthe valves to operate undertheir design conditions. The EQ Reports in Attachment A identify the equipmentmounting employed forthe testing and the specific conditions tested.
In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the RNS to confirmthe 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 installedconfiguration 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 verifythat the installed configuration of the motor-operated valves identified in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.3.6-1 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 reportexists and concludes that each motor-operated valvechanges position as indicated in Table 2.3.6-1 under design conditions: and Areport exists and concludesthat the as-built motor-operated valvesare boundedby the tested conditions.
U.S. Nuclear Regulatory Commission ND-18-0820 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection 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 of all 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 favaiiabie 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-Z0-001 Revision X, "3" and Larger Motor Operated 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 EquipmentQualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4 6.
2.3.06.12a.i-U3-CP-Rev0, ITAAC Completion Package 7.
2.3.06.12a.i-U4-CP-RevO, ITAAC Completion Package
U.S. Nuclear Regulatory Commission ND-18-0820 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 T ransfer 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"