ND-19-0668, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.05.03b.iii (Index Number 348)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.05.03b.iii (Index Number 348)

ML19170A326
Person / Time
Site:	Vogtle
Issue date:	06/19/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0668
Download: ML19170A326 (8)

Text

k. Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel JUN t 9 2019 Docket Nos.: 52-025 52-026 ND-19-0668 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 Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.05.03b.iii findex Number 348]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 18, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.05.03b.iii

[Index Number 348] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.3.05.03b.iii [Index Number 348]. 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.

Southern Nuclear Operating Company(SNC) previously submitted, via letter ND-17-1365

[ML17244A634 and ML17244A636], a Unit 3 Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.3.05.03b.iii [Index Number 348]. This resubmittal supersedes the previous notices in their entirety.

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 all Section 52.99(c)(3) ITAAC Closure Notifications will be submitted to 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

U.S. Nuclear Regulatory Commission ND-19-0668 Page 2 of 4 Respectfully submitted, Mictiael J. Yox Regulatory Affairs Qfrector Vogtle 3 & 4 Enclosure; Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.05.03b.iii [Index Number 348]

MJY/GCW/sfr

U.S. Nuclear Regulatory Commission ND-19-0668 Page 3 of 4 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. Yox 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 Reoulatorv 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0668 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson 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 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. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-19-0668 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0668 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.05.03b.i[i [Index Number 348]

U.S. Nuclear Regulatory Commission ND-19-0668 Enclosure Page 2 of 4 ITAAC Statement Desian Commitment 3.b) The cask handling crane is single failure proof.

4. The cask handling crane cannot move over the spent fuel pool.

Insoections/Tests/Analvses ii) Testing of the cask handling crane is performed.

iii) Testing of the cask handling crane is performed.

Testing of the cask handling crane is performed.

Acceotance Criteria ii) The cask handling crane shall be static load tested to 125% of the rated load.

iii) The cask handling crane shall lift a test load that is 100% of the rated load. Then it shall lower, stop, and hold the test load.

The cask handling crane does not move over the spent fuel pool.

ITAAC Completion DescriDtlon Multiple ITAAC are performed to verify that the cask handling crane is single failure proof and cannot move over the spent fuel pool. This ITAAC performs static load testing to verify the cask handling crane main and auxiliary hoists can support 125% of the rated load, a lift test of a load that is 100% of the cask handling crane main and auxiliary hoist's rated load, including lowering, stopping and holding the test load, and testing of the cask handling crane to demonstrate it does not move over the spent fuel pool.

ih The cask handlino crane shall be static load tested to 125% of the rated load.

The cask handling crane main hoist 125% static load test is performed in accordance with Unit 3 and Unit 4 site acceptance test procedures SV3-MH02-VTP-002 and SV4-MH02-VTP-002 (References 1 and 2) with a load equal to 125%(+5%/-0%) of the cask handling crane main hoist rated load. This testing is performed as required by NUREG-0554 Section 8.2(Reference

3) in accordance with ASME NOG-1 (Reference 4). The main hoist is tested and visually observed to exhibit no drift downward after stopping and holding the test load. The load was successfully supported under these conditions.

Similarly, the cask handling crane auxiliary hoist is static load tested using References 1 and 2 with a load equal to 125%(+5%/-0%) of the cask handling crane auxiliary hoist rated load. The auxiliary hoist is tested and visually observed to exhibit no drift downward after stopping and holding the test load. The load was successfully supported under these conditions.

U.S. Nuclear Regulatory Commission ND-19-0668 Enclosure Page 3 of 4 The Unit 3 and Unit 4 site acceptance test procedures SV3-MH02-VTP-002 and SV4-MH02-VTP-002 confirm that the cask handling crane main and auxiliary hoists were static load tested to 125% of the cask handling crane main and auxiliary hoist's rated load.

iii) The cask handlino crane shall lift a test load that is 100% of the rated load. Then it shall lower. stoD. and hold the test load.

The cask handling crane main hoist 100% load test is performed in accordance with Unit 3 and Unit 4 site acceptance test procedures SV3-MH02-VTP-002 and SV4-MH02-VTP-002 (References 1 and 2) with a load that is 100% (-i-5%/-0%) of the cask handling crane main hoist rated load. This testing is performed as required by NUREG-0554 Section 8.2(Reference 3) and is performed after the cask handling crane's static load test to 125% of rated load. The main hoist is tested and visually observed to exhibit no drift downward after lowering, stopping and holding the test load. The load is successfully supported under these conditions.

Similarly, the cask handling crane auxiliary hoist is 100% load tested using References 1 and 2 with a load equal to 100%(+5%/-0%) of the cask handling crane auxiliary hoist rated load. The auxiliary hoist is tested and visually observed to exhibit no drift downward after lowering, stopping and holding the test load. The load is successfully supported under these conditions.

The Unit 3 and Unit 4 site acceptance test procedures SV3-MH02-VTP-002 and SV4-MH02-VTP-002 document and confirm that the cask handling crane main and auxiliary hoists are load tested to 100% of the cask handling crane main and auxiliary hoist's rated load, including lowering, stopping and holding the test load.

The cask handlino crane does not move over the soent fuel oool.

The cask handling crane test is performed to demonstrate the crane does not move over the spent fuel pool in accordance with Unit 3 and Unit 4 site acceptance test procedures SV3-MH02-VTP-002 and SV4-MH02-VTP-002(References 1 and 2).

These tests are performed during the cask handling crane operational testing. During these tests, the crane is operated by running the trolley into the trolley limit switch at full speed to verify it comes to a complete stop before it engages the mechanical stop which is located prior to traveling over the spent fuel pool. Performance of the Unit 3 and Unit 4 site acceptance test procedures SV3-MH02-VTP-002 and SV4-MH02-VTP-002 document and confirm that the cask handling crane does not move over the spent fuel pool.

References 1 and 2 are available for NRC inspection as part of Unit 3 and Unit 4ITAAC Completion Packages(References 5 and 6).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company(SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-19-0668 Enclosure Page 4 of 4 References ^available for NRG inspection)

1. SV3-MH02-VTP-002,"Domestic AP1000 Cask Crane Site Acceptance Test"

2. SV4-l\/IH02-VTP-002,"Domestic API000 Cask Crane Site Acceptance Test"

3. NUREG-0554,"Single-Failure-Proof Cranes for Nuclear Power Plants"

4. ASME NOG-1-1998,"Rules for Construction of Overhead and Gantry Cranes(Top Running Bridge, Multiple Girder)"

5. 2.3.05.03b.iii-U3-CP-Rev0, ITAAC Completion Package

6. 2.3.05.03b.iii-U4-CP-Rev0, ITAAC Completion Package

7. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"