ND-22-0656, ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii (Index Number 348)

ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii (Index Number 348)

ML22349A667
Person / Time
Site:	Vogtle
Issue date:	12/15/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0656, ITAAC 2.3.05.03b.iii
Download: ML22349A667 (1)

Text

~ Southern Nuclear Jamie M Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel December 15, 2022 Docket No.: 52-026 ND-22-0656 10 CFR 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 2.3.05.03b.iii [Index Number 348]

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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.05.03b.iii [Index Number 348]. This ITAAC verified that the cask handling crane can lift, and hold rated loads and does not move over the spent fuel pool. The closure process for this ITAAC is based on the guidance described in NEl-08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is 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 Kelli Roberts at 706-848-6991.

Respectfully submitted,

~~ma~

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 ITAAC Closure Notification on Completion of 2.3.05.03b.iii [Index Number 348]

JMC/JTK/sfr

U.S. Nuclear Regulatory Commission ND-22-0656 Page 2 of 2 cc: Regional Administrator, Region II Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-22-0656 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-22-0656 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii [Index Number 348]

U.S. Nuclear Regulatory Commission ND-22-0656 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 3.b) The cask handling crane is single failure proof.

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

Inspections, Tests, Analyses 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.

Acceptance 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 Determination Basis 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 performed 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 heist'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.

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

The cask handling crane main hoist 125% static load test was performed in accordance with Unit 4 site acceptance test procedure SV4-MH02-VTP-002 (Reference 1) with a load equal to 125%

(+5%/-0%) of the cask handling crane main hoist rated load. This testing was performed as required by NUREG-0554 Section 8.2 (Reference 2) in accordance with ASME NOG-1 (Reference 3). The main hoist was 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 was static load tested using Reference 1 with a load equal to 125% (+5%/-0%) of the cask handling crane auxiliary hoist rated load. The auxiliary hoist was 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-22-0656 Enclosure Page 3 of 4 The Unit 4 site acceptance test procedure SV4-MH02-VTP-002 confirmed 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 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 main hoist 100% load test was performed in accordance with Unit 4 site acceptance test SV4-MH02-VTP-002 (Reference 1) with a load that is 100% (+5%/-0%) of the cask handling crane main hoist rated load. This test was performed as required by NUREG-0554 Section 8.2 (Reference 2) and was performed after the cask handling crane's static load test to 125% of rated load. The main hoist was tested and visually observed to exhibit no drift downward after lowering, stopping and holding the test load. The load was successfully supported under these conditions .

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

The Unit 4 site acceptance test procedure SV4-MH02-VTP-002 documented and confirmed that the cask handling crane main and auxiliary hoists were 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 handling crane does not move over the spent fuel pool.

The cask handling crane test was performed to demonstrate that the crane does not move over the spent fuel pool in accordance with Unit 4 site acceptance test procedure SV4-MH02-VTP-002 (Reference 1).

This test was performed during the cask handling crane operational testing. During this test, the crane was operated by running the bridge into the bridge limit switch at full speed to verify it came to a complete stop before it engaged the mechanical stop, which is located prior to traveling over the spent fuel pool. Performance of the Unit 4 site acceptance test procedure SV4-MH02-VTP-002 documented and confirmed that the cask handling crane does not move over the spent fuel pool.

The completed site acceptance test results were compared to the ITAAC acceptance criteria and documented in ITAAC Technical Report SV4-MHS-ITR-800348 (Reference 4). The results demonstrated that the ITAAC acceptance criteria were met.

References 1 through 4 are available for NRC inspection as well as the Unit 4 ITAAC Completion Package (Reference 5).

U.S. Nuclear Regulatory Commission ND-22-0656 Enclosure Page 4 of 4 ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all lTAAC 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 2.3.05.03b.iii (Reference 5) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.05.03b.iii was performed for VEGP Unit 4 and that the prescribed acceptance criteria are 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 NRC inspection)

1. SV4-MH02-VTP-002, Rev. 2, "Domestic AP1000 Cask Crane Site Acceptance Test"

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

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

4. SV4-MHS-ITR-800348, Rev. 0, "Unit 4 Recorded Results of Cask Handling Crane Load Tests :

ITAAC 2.3.05.03b.iii, NRC Index 348"

5. 2.3.05.03b.iii-U4-CP-Rev0, ITAAC Completion Package