ND-19-0928, ITAAC Closure Notification on Completion of ITAAC 2.3.07.07b.vii (Index Number 881)

ITAAC Closure Notification on Completion of ITAAC 2.3.07.07b.vii (Index Number 881)

ML19261A894
Person / Time
Site:	Vogtle
Issue date:	09/18/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0928
Download: ML19261A894 (6)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tel SEP 1 8 2019 Docket No.: 52-025 ND-19-0928 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.07.07b.vii findex Number 8811 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 Vogtie Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.07.07b.vii [Index Number 881]for verifying the water volume of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping is greater than or equal to 46,050 gallons. 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 Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.07.07b.vii [Index Number 881]

MJY/GJL/sfr

U.S. Nuclear Regulatory Commission ND-19-0928 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (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. G. Chick Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak 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. P. 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. T. Fredette Mr. C. Weber Mr. S. Smith Qqiethorpe Power Corooration Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0928 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros 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 Mr. Z. 8. Harper 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, Batch Bingham

U.S. Nuclear Regulatory Commission ND-19-0928 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0928 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.07.07b.vii[Index Number 881]

U.S. Nuclear Regulatory Commission ND-19-0928 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 7.b) The SFS provides spent fuel cooling for 7 days by boiling the spent fuel pool water and makeup water from on-site storage tanks.

Insoections.Tests. Analysis vii) Inspection will be performed to verify the cask loading pit includes sufficient volume of water.

Acceptance Criteria vii) The water volume of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping is greater than or equal to 46,050 gallons.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Spent Fuel Pool Cooling System (SFS) provides spent fuel cooling for 7 days by boiling the spent fuel pool water and makeup water from on-site storage tanks. For this ITAAC, an inspection was performed to verify the water volume of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping is greater than or equal to 46,050 gallons.

An inspection was performed of the as-built dimensions of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping. Measurements were taken using survey equipment in accordance with 26139-000-4MP-T81C-N3201,"Construction Survey"(Reference 1). The volume was calculated using the inspection results of survey data starting from the bottom of the gate to the calculated invert elevation of the spent fuel pool cooling suction piping. The calculated volume of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping was compared to the minimum volume of 46,050 gallons specified in the ITAAC Acceptance Criteria. The results of the comparison are documented in Inspection Report SV3-SFS-FSK-800881 for the water volume of the cask loading pit room 12463(References 2). The results of the inspection verify the calculated volume of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping is 46,341 gallons.

The results are documented in the Unit 3 Principle Closure Document(Reference 2) which show the water volume of the cask loading pit above the bottom of the gate and below the spent fuel pool cooling suction piping is greater than 46,050 gallons and meets the ITAAC acceptance criteria.

Reference 2 is available for NRC inspection as part of the Unit 3 ITAAC completion package (Reference 3).

U.S. Nuclear Regulatory Commission ND-19-0928 Enclosure Page 3 of 3 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 2.3.07.07b.vii (Reference 3) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.07.07b.vii 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. 26139-000-4MP-T81C-N3201, Rev. 5,"Construction Survey"

2. SV3-SFS-FSK-800881, Rev. 1, "Water Volume of the Cask Loading Pit Room 12463"

3. 2.3.07.07b.vii-U3-CP-Rev0, ITAAC Completion Package