ND-19-0756, ITAAC Closure Notification on Completion of ITAAC 2.3.09.03.Ill (Lndex Number 425)

ITAAC Closure Notification on Completion of ITAAC 2.3.09.03.Ill (Lndex Number 425)

ML19177A266
Person / Time
Site:	Vogtle
Issue date:	06/26/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0756
Download: ML19177A266 (7)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUN 2 6 2019 Docket No.: 52-026 ND-19-0756 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.3.09.03.Ill flndex Number 4251 Ladles and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter Is to notify the Nuclear Regulatory Commission (NRC)of the completion of Vogtle Electric Generating Plant(VEGP) Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.09.03.III [Index Number 425]for verifying the Containment Hydrogen Control System (VLS) provides the nonsafety-related function to control the containment hydrogen concentration for beyond design basis accidents. The closure process for this ITAAC Is based on 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.

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.

Resp^tfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.3.09.03.Ill [Index Number 425]

MJY/GJL/sfr

U.S. Nuclear Regulatory Commission ND-19-0756 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(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. K. A. Roberts 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. J. C. Haswell 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 Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. P. O'Bryan Mr. T. Fredette Mr. C. Weber Oqlethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0756 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (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. 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0756 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0756 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.3.09.03.iii [Index Number 425]

U.S. Nuclear Regulatory Commission ND-19-0756 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment

3. The VLB provides the nonsafety-related function to control the containment hydrogen concentration for beyond design basis accidents.

Insoections.Tests. Analvsis iii) An inspection of the as-built containment internal structures will be performed.

Acceptance Criteria iii) The equipment access opening and CMT-A opening constitute at least 98% of the vent path area from Room 11206 to Room 11300. The minimum distance between the equipment access opening and the containment shell is at least 24.3 feet. The minimum distance between the CMT-A opening and the containment shell is at least 9.4 feet. The CMT-B opening constitutes at least 98% of the vent path area from Room 11207 to Room 11300 and is a minimum distance of 24.6 feet away from the containment shell. Other openings through the ceilings of these rooms must be at least 3feet from the containment shell.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Containment Hydrogen Control System (VLB) provides the nonsafety-related function to control the containment hydrogen concentration for beyond design basis accidents. The subject ITAAC requires an inspection of the as-built containment internal structures be performed.

A visual inspection (Reference 1) of the ceilings in containment Rooms 11206 and 11207 was performed to identify all openings to Room 11300 above. Three openings were identified in each of the ceilings of Room 11206 and 11207. Room 11206 contained an equipment access opening, personnel access opening, and CMT-A opening. Room 11207 contained an equipment access opening, personnel access opening, and CMT-B opening. SV4-AD11-Z0-001 (Reference

2) documents that the personnel access opening in Room 11206 will have a watertight hatch installed. In addition, the equipment access opening and the personnel access opening in Room 11207 will have watertight hatches installed. Table 1 identifies the watertight hatches for the openings.

Table 1, Watertight Hatches Opening Hatch Number Room 11206 Personnel Hatch SV4-11300-AD-H11 Room 11207 Personnel Hatch SV4-11300-AD-H03 Equipment Hatch SV4-11300-AD-H04

U.S. Nuclear Regulatory Commission ND-19-0756 Enclosure Page 3 of 4 Vogtle Unit 3 & 4 Updated Final Safety Analysis Report(UFSAR)Sections 3.4.1.1.2 and 3.4.1.2.2.1 document that watertight hatches are provided to close openings not required for hydrogen venting. Therefore, these openings are not credited for hydrogen venting in this ITAAC. The only openings applicable to this ITAAC are the equipment access opening and CMT-A opening in Room 11206, and the CMT-B opening in Room 11207.

The equipment access opening and the CMT-A opening are the only openings in Room 11206 (100% of vent path area) and meets the acceptance criteria of at least 98% of the vent path area from Room 11206 to Room 11300. The CMT-B opening is the only opening in Room 11207(100%

of vent path area) and meets the acceptance criteria of at least 98% of the vent path area from Room 11207 to f^oom 11300.

An inspection (Reference 1) of the applicable openings in Rooms 11206 and 11207 was performed to verify the hydrogen vent path openings and the distance between the openings and the containment shell met the acceptance criteria. Measurements were taken and documented in Reference 1, and Table 2 below provides a summary of the results.

Table 2, Inspection Results ITAAC Acceptance Criteria As-Built Minimum Survey Opening Distance (feet) Distance (feet)

Room 11206 Equipment Access 24.3 24.7 Opening CMT-A Opening 9.4 9.8 Room 11207 CMT-B Opening 24.6 25.1 The equipment access opening and CMT-A opening constitute at least 98% of the vent path area from Room 11206 to Room 11300. The minimum distance between the equipment access opening and the containment shell is at least 24.3 feet. The minimum distance between the CMT-A opening and the containment shell is at least 9.4 feet. The CMT-B opening constitutes at least 98% of the vent path area from Room 11207 to Room 11300 and is a minimum distance of 24.6 feet away from the containment shell. No other openings through the ceilings of rooms 11206 and 11207 were identified.

ITAAC Finding Review 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 review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.09.03.iii (Reference 3)and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-19-0756 Enclosure Page 4 of 4 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 2.3.09.03.iii was performed for VEGP Unit 4 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References(available for NRG inspection)

1. SV4-VLS-FSK-800425, Rev. 1, Containment Hydrogen Vent Openings As-Buiit Verification

2. SV4-AD11-ZO-001, Rev. 1, Design Specification for Safety-Related Floor Hatch Assemblies

3. 2.3.09.03.iii-U4-CP-Rev 0, ITAAC Completion Package