ND-18-1139, ITAAC Closure Notification on Completion of ITAAC 2.3.09.03.iii (Index Number 425)

ITAAC Closure Notification on Completion of ITAAC 2.3.09.03.iii (Index Number 425)

ML18262A067
Person / Time
Site:	Vogtle
Issue date:	09/18/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-1139
Download: ML18262A067 (7)

Text

^ ^ , ... 1 Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 410-474-8587 cell SEP 18 2018 myox@southernco.corti Docket No.: 52-025 ND-18-1139 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 3 ITAAC Closure Notification on Completion of ITAAC 2.3.09.03.iii [Index Number 425]

Ladies 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 3 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.

Respectfully submitted.

Michael J. Yox'-

Regulatory Affairs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.09.03.iii [Index Number 425]

MJY/GJL/amw

U.S. Nuclear Regulatory Commission ND-18-1139 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. D. L. McKinney (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. Yox 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. 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 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 Oaiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-1139 Page 3 of 3 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 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, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-1139 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1139 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.09.03.III [Index Number 425]

U.S. Nuclear Regulatory Commission ND-18-1139 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.

Inspections.Tests. Analysis iii) An inspection ofthe as-built containment internal structures will be performed.

Acceptance Criteria iii) The equipment access opening and CMT-A opening constitute at least 98% ofthe vent patharea 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 feetaway from the containment shell. Other openingsthrough the ceilings of these rooms must be at least 3 feet 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 requiresan 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 equipmentaccess opening, personnel access opening, and CMT-A opening. Room 11207 contained an equipment access opening, personnel access opening, and CMT-B opening. SV3-AD11 -ZO-001 (Reference

2) documentsthat 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 hatchs installed. Table 1 identifies the watertight hatches forthe openings.

Table 1, Watertight Hatches Opening Hatch Number Room 11206 Personnel Hatch SV3-11300-AD-H11 Room 11207 Personnel Hatch SV3-11300-AD-H03 Equipment Hatch SV3-11300-AD-H04

U.S. Nuclear Regulatory Commission ND-18-1139 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 tfiat 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 openingand CMT-A opening in Room 11206, and the CMT-B opening in Room 11207.

The equipment access openingand the CMT-A opening are the onlyopenings in Room 11206 (100% ofvent patharea), and meets the acceptance criteria of at least 98% ofthe ventpath area from Room 11206 to Room 11300. The CMT-B opening is the onlyopening in Room 11207 (100%

of ventpatharea), and meets the acceptancecriteria ofat least 98% ofthe ventpatharea 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.

ITAAC Acceptance Criteria As-Built Minimum Survey Opening Distance (feet) Distance (feet)

Room 11206 Equipment Access 24.3 24.8 Opening CMT-A Opening 9.4 10.0 Room 11207 CMT-B Opening 24.6 25.1 The equipment access opening and CMT-A opening constitute at least 98%ofthe vent patharea 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-Aopening 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 of24.6 feet away from the containmentshell. No other openings throughthe 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-18-1139 Enclosure Page 4 of 4 ITAAC ComDietion Statement Based on the above information, SNO hereby notifiesthe NRG that ITAAC 2.3.09.03.111 was performed for VEGP Unit 3 and that the prescribed acceptance criteriawere met.

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

References favallable for NRG inspection)

1. SV3-VLS-FSK-800425, Rev. 1, Containment Hydrogen Vent Openings As-Built Verification

2. SV3-AD11 -ZO-001, Rev. 1, Design Specification for Safety-Related Floor Hatch Assemblies

3. 2.3.09.03.iii-U3-CP-Rev 0, ITAAC Completion Package