ND-18-0257, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.07.05.i (Index Number 396)
| ML18054A369 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/22/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.3.07.05.i, ND-18-0257 | |
| Download: ML18054A369 (10) | |
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Southern Nuclear F£B 2 2 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 tei 410-474-8587 ceii myox @southernco.com ND-18-0257 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.07.05.1 [Index Number 3961 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item2.3.07.05.1
[Index Number396] 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 notificationsfor ITAAC that have not been completed 225-days prior to initial fuel load.
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 allSection 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteriaare 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.
Michael J. Yox Regulatory Affairs Director Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.07.05.1 [Index Number 396]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0257 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKlnney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. 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. P. B. Donnelly 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0257 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. C. 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-18-0257 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-18-0257 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.07.05.1 [Index Number 396]
U.S. Nuclear Regulatory Commission ND-18-0257 Enclosure Page 2 of 7 ITAAC Statement Desion Commitment:
- 5. The seismic Category Icomponents identified in Table 2.3.7-1 can withstand seismic design basis loads without loss of safety functions.
Insoections. Tests. Analyses:
i) Inspection will be performed to verify that the seismic Category Icomponents identified in Table 2.3.7-1 are located on the Nuclear Island.
ii) Type tests, analyses, or a combination oftypetests and analyses ofseismicCategory I equipment will be performed.
iii) Inspection will be performed for the existenceofa report verifying that the as-built equipment including anchorage isseismically bounded bythe tested oranalyzed conditions.
Acceotance Criteria:
i) Theseismic Category Icomponents identified in Table 2.3.7-1 are located onthe Nuclear Island.
ii) Areport exists and concludes that theseismic Category Iequipment canwithstand seismic design basis loads without loss of safety function.
iii) Areport exists and concludes that theas-built equipment including anchorage isseismically bounded by the tested or analyzed conditions.
ITAAC Completion Description This ITAAC requires thatinspections, tests, andanalyses be performed anddocumented to ensurethe SpentFuel Pool Cooling System (SFS) components (equipment) identified as seismic Category Iin theCombined License (COL) Appendix C, Table 2.3.7-1 (the Table) are designed and constructed inaccordance with applicable requirements.
ii The seismic Cateoorv Icomponents identified in Table 2.3.7-1 are located on the Nuclear Island.
To assure that seismicCategory Icomponentscan withstand seismicdesign basis loads without lossof safety function, all the components in theTable are designed to be located on the seismic Category INuclear Island. In accordance with Equipment Qualification (EG)
Walkdown ITAAC Guideline (Reference 1), an inspection is conducted ofthe SFS to confirm the satisfactory installation of the seismically qualified components. Theinspection includes verification of component make/model/serial number andverification of component location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified inAttachment A document the results of the inspection and conclude that the seismic CategoryIcomponentsare located on the Nuclear Island.
U.S. Nuclear Regulatory Commission ND-18-0257 Enclosure Page 3 of 7 ill A report exists and concludes that tfie seismic Category I eouioment can withstand seismic desion basis loads without loss of safety function.
Seismic Category Iequipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).
Safety-related (Class 1E)electrical equipment in the Table is seismically qualified bytype testing combinedwith analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includes safety-related (Class 1E) field sensors and the safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valvesand electrical connectorassemblies. The specific qualification method (i.e., type testing, analysis, orcombination) used for each piece of equipment in the Table is identified in Attachment A. Additional information aboutthe methods used to qualify API 000safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6). The EQ Reports (Reference 7) identified in Attachment Acontainapplicable test reports and associated documentation and conclude thatthe seismic Category Iequipment can withstand seismic design basis loadswithout lossof safety function.
iiil A reoort exists and concludes that the as-built eouioment includino anchoraoe is seismicallv bounded bv the tested or analvzed conditions.
An inspection (Reference 1) isconducted to confirm thesatisfactory installation ofthe seismically qualified equipment in the Table. Theinspection verifies the equipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces. Thedocumentation ofinstalled configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.
As part of theseismic qualification program, consideration isgiven tothedefinition of the clearances needed around the equipmentmounted in the plantto permit the equipmentto move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdone as part of seismic testing by measuring the maximum dynamic relative displacement of thetop andbottom of theequipment. EQ Reports (Reference 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade theestablished qualification.
Interface requirements are defined based on the test configuration and otherdesign requirements.
Attachment Aidentifies the EQRR (Reference 2)completed to verify thatthe as-built seismic Category Iequipment listed in the Table, including anchorage, are seismically bounded by the testedoranalyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRG Regulatory Guide 1.100 (Reference 8).
U.S. Nuclear Regulatory Commission ND-18-0257 Enclosure Page 4 of 7 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met:
The seismic Category Icomponents identified in Table 2.3.7-1 are located on the Nuclear Island; A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; and A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.
References 2 and 7 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.07.05.1 Completion Packages (References 9 and 10, respectively).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion. Southern NuclearOperating Company (SNC) performed a review ofall ITAAC findings pertaining tothe subject ITAAC and associated correctiveactions. Thisfinding review, which included now-consolidated ITAAC Indexes 397 and 398, found one relevant ITAAC finding associated withthis ITAAC.
- 1) Notice of Nonconformance (NGN) 99901412/2012-201-02 (Closed)
References (available for NRC mspectlon) 1.
ND-xx-xx-001, "EG Walkdown IT/\\AC Guideline"
- 2. EGAs-Built Reconciliation Reports (EQRR) as identified inAttachment Afor Units 3 and 4
Code,Section III, "RulesforConstruction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda
- 4. ASMEQME-1 -2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants," The American Society of Mechanical Engineers, June 2007
- 5. IEEEStandard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipmentfor Nuclear Power Generating Stations"
- 6. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipmenf
- 7. Equipment Qualification (EQ) Reportsas identified inAttachment A
- 8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"
U.S. Nuclear Regulatory Commission ND-18-0257 Enclosure Page 5 of 7 9.
2.3.07.05.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.07.05.1 [Index Number 396]"
- 10. 2.3.07.05.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.3.07.05.1 [Index Number 396]"
- 11. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0257 Enclosure Page 6 of 7 Attachment A System: Spent Fuel Pool Cooling System (SFS)
Equipment Name
- Tag No.
- Seismic Cat. 1 Type of Qual. EQ Reports (Reference 7)
As-Buiit EQ EQRR (Reference 2)
- Spent Fuel Pool Level Sensor SFS-019A Yes Type Test APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Spent Fuel Pool Level Sensor SFS-019B Yes Type Test APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Spent Fuel Pool Level Sensor SFS-019C Yes Type Test APP-JE52-VBR-002 /
APP-JE52-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Refueling Cavity Drain to SGS Compartment Isolation Vaive SFS-PL-V031 Yes Type Test &
Analysis APP-PV11-VBR-002 /
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Refueling Cavity to SFS Pump Suction Isolation Valve SFS-PL-V032 Yes Type Test &
Analysis APP-PV11-VBR-002 /
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Refueling Cavity Drain to Containment Sump Isolation Valve SFS-PL-V033 Yes Type Test &
Analysis APP-PV10-VBR-002/
APP-PV10-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX IRWST to SFS Pump Suction Line Isolation Valve SFS-PL-V039 Yes Type Test &
Analysis APP-PV11-VBR-002/
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Fuel Transfer Canal to SFS Pump Suction Iso. Valve SFS-PL-V040 Yes Type Test &
Analysis APP-PV11-VBR-002/
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Cask Loading Pit to SFS Pump Suction Isolation Valve SFS-PL-V041 Yes Type Test &
Analysis APP-PV11-VBR-002 /
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Cask Loading Pit to SFS Pump Suction Isolation Valve SFS-PL-V042 Yes Type Test &
Analysis APP-PV11-VBR-002 /
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX SFS Pump Discharge Line to Cask Loading Pit Isolation Valve SFS-PL-V045 Yes Type Test &
Analysis APP-PV11-VBR-002/
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX Cask Loading Pit to WLS Isolation Valve SFS-PL-V049 Yes Type Test &
Analysis APP-PV10-VBR-002/
APP-PV10-VBR-001 2.3.07.05. i-U3-EQRR-PCDXXX Spent Fuel Pool to Cask Washdown Pit Isolation Valve SFS-PL-V066 Yes Type Test &
Analysis APP-PV10-VBR-008 /
APP-PV10-VBR-007 2.3.07.05.i-U3-EQRR-PCDXXX CaskWashdown Pit Drain Isolation Valve SFS-PL-V068 Yes Type Test &
Analysis APP-PV11-VBR-002 /
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX
U.S. Nuclear Regulatory Commission ND-18-0257 Enclosure Page 7 of 7 Attachment A System: Spent Fuel Pool Cooling System (SFS)
Equipment Name
- Tag No. ^
Seismic Cat. i ^ Type of Qual. EQ Reports (Reference 7)
As-Buiit EQ EQRR (Reference 2)
- Refueling Cavity Drain Line Check Valve SFS-PL-V071 Yes Analysis APP-PV03-VBR-014 /
APP-PV03-VBR-013 2.3.07.05.i-U3-EQRR-PCDXXX Refueling Cavity Drain Line Check Valve SFS-PL-V072 Yes Analysis APP-PV03-VBR-014/
APP-PV03-VBR-013 2.3.07.05.i-U3-EQRR-PCDXXX SFS Containment Floodup Isolation Valve SFS-PL-V075 Yes Type Test &
Analysis APP-PV11-VBR-002/
APP-PV11-VBR-001 2.3.07.05.i-U3-EQRR-PCDXXX
+ Excerpt from COL Appendix C Table 2.3.7-1
- The Unit 4 As-Built EQRR are numbered "2.3.07.05.i-U4-EQRR-PCDXXX"