ND-17-2100, Vogtie Electric Generating Plant Unit 4 - ITAAC Closure Notification on Completion of ITAAC 2.3.11.02.1 (Index Number 450)

Vogtie Electric Generating Plant Unit 4 - ITAAC Closure Notification on Completion of ITAAC 2.3.11.02.1 (Index Number 450)

ML17355A310
Person / Time
Site:	Vogtle
Issue date:	12/18/2017
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.3.11.02.1, ND-17-2100
Download: ML17355A310 (8)

Text

Southern Nuclear DEC I 8 2017 Docket No.:

52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@soutfiernco.com ND-17-2100 10CFR 52.99(c)(1)

Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.3.11.02.1 findex Number 4501 Ladles and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter Is to notifythe Nuclear Regulatory Commission (NRC) ofthe completion of Vogtie Electric Generating Plant(VEGP)

Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.11.02.1 [Index Number 450] which confirms Gaseous Radwaste System (WGS) activated carbon delay bed location and seismic analysis. The closure process for this ITAAC Is based on the guidance described In Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice In the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.11.02.1 [Index Number 450]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-17-2100 Page 2 of 3 To:

Southern Nuclear Operating Company I 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. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. S. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. 0. Chamberlain Mr. D. R. Culver Mr. R. L. Belike 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. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Ms. V. L. Ordaz Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oqiethoroe Power Corporation Mr. K. T. Haynes Mr. R. B. Brinkman Municipai Eiectric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-17-2100 Page 3 of 3 Dalton Utilities Mr. T. Bundros 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 Mr. D. Hawkins Ms. 8. DITommaso Mr. J. L. Coward Ms. N. E. Deangells Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, inc.

Mr. 8. Roetger, Georgia PublicService 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-17-2100 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-17-2100 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.11.02.1 [Index Number 450]

U.S. Nuclear Regulatory Commission ND-17-2100 Enclosure Page 2 of 5 ITAAC Statement Design Commitment:

2.

The equipment identified as having seismic design requirements in Table 2.3.11-1 can withstand seismic design basis loads without loss of its structural integrityfunction.

Inspections. Tests. Analvses:

i)

Inspection will be performed to verify that the equipment identified as having seismic design requirements in Table2.3.11-1 is locatedon the Nuclear Island.

ii)

Typetests, analyses, ora combination oftypetests and analyses ofseismically designed equipment will be performed.

ill)

Inspection will be performed for the existence of a report verifying thatthe as-built equipment including anchorageisseismically bounded bythe tested or analyzed conditions.

Acceptance Criteria:

i)

Theequipment identified as having seismic design requirements in Table 2.3.11-1 is located on the Nuclear Island.

ii)

Areport exists andconcludes that the seismically designed equipment canwithstand appropriate seismic design basis loads without lossof its structural integrity function.

iii)

Areport exists andconcludes that theas-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

ITAAC Determination Basis This ITAAC requires thatinspections, tests, andanalyses be performed anddocumented to ensure the Gaseous Radwaste System(WGS) equipment identified as having seismic design requirements in the Combined License (COL) Appendix CTable 2.3.11-1 (Table) can withstand seismic design basis loads without the loss of its structural integrity function. The subject ITAAC required; An inspection be performed toverify thattheWGS Activated Carbon Delay Beds are located on the Nuclear Island.

Type tests, analyses, ora combination of type tests and analyses beperformed on the WGS Activated Carbon Delay Beds.

An Inspection be performed for theexistence of a report that concludes that the as-built equipment, the WGS Activated Carbon Delay Beds, including anchorage isseismically bounded by the tested or analyzed conditions.

Toassure thatthe equipment identified in the Table can withstand the appropriate seismic design basis loads without loss of its structural integrity function, an inspection was conducted ofthe WGS to confirm the satisfactory installation ofthe equipment with seismicdesign requirements identified in Attachment A. The inspection included verification of equipment

U.S. Nuclear Regulatory Commission ND-17-2100 Enclosure Page 3 of 5 number and location. The inspections to verify instailed component locations are documented in Quality Assurance (OA) inspection reports (References 1 and 2). The resultsofthe inspections conclude that each component identified inAttachment A is located on the Nuclear Island.

Seismic loads for the equipment were established using one-half ofthe AP1000 Safe Shutdown Earthquake (SSE)floor response spectra. Seismic analyses ofthe equipmentidentified in the Table were performed to demonstrate structural integrity in accordance with American Society of Mechanical Engineers (ASME) Code Section VIII, Rulesfor Construction of Pressure Vessels (Reference 3). The analyses are documented inthe WGSdelay bed design report(Reference

4) and concludethat the equipmentidentified inthe Table as having seismic design requirements can withstand appropriateseismic design basis loads without loss of itsstructural integrity function.

In accordance with the fabrication and construction installation work packages, inspections were performed on the WGSActivated Carbon Delay Bedsand anchorage to confirm the satisfactory installation ofthe seismicallydesigned equipment. The inspection included verification of equipment fabrication, equipment mounting, equipment anchorage, and critical attributes from the seismicanalyses. In accordance with NEI 08-01, Section9.5, inspection ofWGSActivated Carbon Delay Bedequipmentmounting and verification ofcritical attributesfrom the seismic analyses were performed at otherthan the final installed location, due to inaccessibility ofthe equipment after installation. Non-conformances and design changes issued during fabrication and installation against the equipmentand anchorage were analyzed against the seismic analyses to ensure inspection results performed at otherthan the equipment's final location remained valid for supporting ITAAC acceptance criteria. Non-conformances and design changes issued upthrough installation ofthe equipment including attachment to the seismic Category 1 structure were analyzed against the seismic analysis to verify thatthe analyzed conditionswere still boundingwhen consideringthe cumulative effects ofany deviating conditions.

The results of the verifications were documented in the as-built seismic reconciliation report (Reference 5). Theverifications demonstrated thatthe as-built equipment in COL Appendix C, Table 2.3.11-1, including anchorage, isseismically bounded by the analyzed conditions.

Together, these reports (References 1,2,4, and5) provide evidence thatthe ITAAC Acceptance Criteria requirements are met:

The equipmentidentified as having seismic design requirementsin Table 2.3.11-1 is located on the Nuclear Island.

A report exists and concludes that the seismicallydesigned equipment can withstand appropriateseismic design basis loads without loss of itsstructural integrity function.

Areport existsand concludesthat the as-built equipment including anchorage is seismicaliy bounded by the tested or analyzed conditions.

U.S. Nuclear Regulatory Commission ND-17-2100 Enclosure Page 4 of 5 ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a reviewof ITAAC Findings and associated corrective actions. This review which included now-consolidated ITAAC Indexes 450, 451, and 452 found no relevant ITAAC Findings associated with this ITAAC. The ITAAC finding review is referenced in the Vogtle Unit 4 ITAAC Completion Package for ITAAC 2.3.11.02.1 (Reference 6) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.11.02.1 [Index Number450]was performedforVEGP Unit 4 and that the prescribed acceptance criteria are met.

Systems, structures, and componentsverified as partofthis ITAAC are being maintained in theiras-designed, ITAAC compliant condition inaccordance with approved plant programsand procedures.

References (available for NRC inspection)

1. M315-15-10317 Rev. 0, Quality Assurance Type "A" Inspection Report - Mechanical: Fixed Equipment, Vessels and Tanks 2.

SV4-WGS-M6K-881481 Rev. 0, SV4 WGS Module KB04 As-Built Location Sketch

3. American Societyof Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code,Section VIII, Rules for Construction of Pressure Vessels, 2001 Edition with 2003 Addenda 4.

APP-MV6H-VDR-001 Rev. 2, API 000 MV6H WGS Delay Bed Design Report

5. SV4-MV6H-VFR-001 Rev. 1, Vogtle Unit 4 ITAAC 2.3.11.02.1As-BuiltSeismic Reconciliation Report

6. 2.3.11.02.i-U4-CP-Rev 0, Completion Package for Unit 4 ITAAC 2.3.11.02.1 [COL Index Number450] (WGS Activated Carbon DelayBed Location and Seismic Analysis)

U.S. Nuclear Regulatory Commission ND-17-2100 Enclosure Page 5 of 5 Attachment A ITAAC Number: 2.3.11.02.1 Excerpt from VEGP Unit 4 COL Appendix 0 Tabie 2.3.11-1 Equipment Name Tag iD Seismic Category 1 Type of Quaiification Design Report Number As-Buiit Reconciiiation Document WGS Activated Carbon Delay Bed A WGS-MV-02A No Analysis APP-MV6H-VDR-001 Rev.2 SV4-MV6H-VFR-001 Rev.1 WGS Activated Carbon Delay Bed B WGS-MV-02B No Analysis APP-MV6H-VDR-001 Rev.2 SV4-MV6H-VFR-001 Rev.1 (1)

The WGS activated carbon delay beds (WGS-MV-02A and WGS-MV-02B) are designed to one-half Safe Shutdown Earthquake (SSE).