ND-18-1294, ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.i (Index Number 346)

ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.i (Index Number 346)

ML19031C892
Person / Time
Site:	Vogtle
Issue date:	01/28/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.3.05.03b.i, ND-18-1294
Download: ML19031C892 (6)

Text

~ Southern Nuclear Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell JAN 2 8 2019 myox@southernco.com Docket No.: 52-025 ND-18-1294 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 3 ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.i [Index Number 346]

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 2.3.05.03b.i [Index Number 346] for verifying the Material Handling System Cask Handling Crane is single failure proof. 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, Mi!!di!Jv/!

Regulatory Affairs Direetor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.05.03b.i [Index Number 346]

MJY/GCW/sfr

U.S. Nuclear Regulatory Commission ND-18-1294 Page2of3 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. S. 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 Regulatory Commission Mr. W. Jones (w/o enclosures)

Mr. F. D. Brown Ms. J. M. Heisserer 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. I. Cozens Mr. J. Gaslevic Mr. V. Hall Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-1294 Page 3 of3 Westinghouse 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. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-1294 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-1294 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.05.03b.i [Index Number 346]

U.S. Nuclear Regulatory Commission ND-18-1294 Enclosure Page 2 of3 ITAAC Statement Design Commitment 3.b) The cask handling crane is single failure proof.

Inspections. Tests. Analvsis i) Validation of double design factors is provided for hooks where used as load bearing components. Validation of redundant factors is provided for load bearing components such as:

• Hoisting ropes

• Sheaves

• Equalizer assembly

• Holding brakes Acceptance Criteria i) A report exists and concludes that the cask handling crane is single failure proof. A certificate of conformance from the vendor exists and concludes that the cask handling crane is single failure proof.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the cask handling crane is single failure proof. The subject ITAAC requires that validation of double design factors is provided for hooks where used as load bearing components, and that validation of redundant factors is provided for load bearing components such as hoisting ropes, sheaves, equalizer assembly and holding brakes.

The cask handling crane is a single failure proof design which conforms to the guidelines of NUREG-0554 "Single-Failure-Proof Cranes for Nuclear Power Plants" (Reference 1),

supplemented by American Society of Mechanical Engineers (ASME) NOG-1-1998, "Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)"

(Reference 2). Single failure proof design is described in NUREG-0554 as "a single failure will not result in the loss of the capability of the system to safely retain the load." The requirements to follow NUREG-0554, supplemented by ASME NOG-1-1998, for the design of the cask handling crane were imposed in the AP1 000 Cask Handling Crane for System MHS design specification (Reference 3).

The cask handling crane single failure proof report (Reference 4) exists and concluded that the cask handling crane is single failure proof. Additionally, a certificate of conformance (Reference

5) from the cask handling crane vendor (manufacturer) exists and concluded that the cask handling crane is single failure proof.

U.S. Nuclear Regulatory Commission ND-18-1294 Enclosure Page 3 of3 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 2.3.05.03b.i (Reference 6) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.05.03b.i was performed for VEGP Unit 3 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 NRC inspection)

1. NUREG-0554, "Single-Failure-Proof Cranes for Nuclear Power Plants", May 1979

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

3. APP-MH02-Z0-101, Rev 3, "Design Specification for AP1000 Cask Handling Crane for System MHS"

4. WEC_SV0_000007, "Vogtle Unit 3 MH02 Cask Handling Crane Supporting References to Topical Report EDR-1", January 20, 2019

5. SV3-MH02-VQQ-004, Rev. 0, "Quality Release and Certificate of Conformance for SV3 AP1000 Cask Crane"

6. 2.3.05.03b.i-U3-CP-Rev 0, ITAAC Completion Package