ND-21-0156, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.07.07b.vii (Index Number 881)
| ML21060B449 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/01/2021 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-21-0156 | |
| Download: ML21060B449 (6) | |
Text
ak Southern Nuclear MAR 0 1 2021 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket No.:
52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-21-0156 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.07.07b.vii [Index Number 8811 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 1, 2021, Vogtle Electric Generating Plant (VEGP) Unit 4 Uncompleted Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 2.3.07.07b.vii [Index Number 881] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.3.07.07b.vii [Index Number 881]. 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.
This notification is informed by the guidance described in NEI-08-01, Industry Guideline for the ITAAC Closure Process Cinder 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)(1) 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 Kelli Roberts at 706-848-6991.
Respectfully submitted.
Michael J. Yox Regulatory Affairs Director Vogtle 3&4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.3.07.07b.vii [Index Number 881]
MJY/TST/sfr
U.S. Nuclear Regulatory Commission ND-21-0156 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)
Mr. D. L. McKlnney (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. G. Chick Mr. S. Stimac Mr. P. Martino 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. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Requlatorv Commission Ms. M. Bailey (w/o enclosures)
Mr. M. King Ms. A. Veil M
M M
M Ms. N. C. Coovert M
M M
M M
M M
M M
M M
M M
. C. P. Patel
. G. J. Khourl
. C. J. Even B. J. Kemker
. C. Welch
. J. Gaslevic
. O. Lopez-Santiago G. Armstrong M. Webb T. Fredette C. Santos
. B. Davis
. J. Vasquez
. J. Eargle
. E. Davidson
. T. Fanelll
. S. Rose Ms. K. McCurry
U.S. Nuclear Regulatory Commission ND-21-0156 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinohouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-21-0156 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0156 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion Plan for Uncompleted ITAAC Item 2.3.07.07b.vii [Index Number 881]
U.S. Nuclear Regulatory Commission ND-21-0156 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.
inspections/Tests/Anaivses 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 Completion Description 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 is 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 is 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 are taken using survey equipment in accordance with 26139-000-4MP-T81C-N3201, "Construction Survey" (Reference 1). The volume is 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 is 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 SV4-SFS-FSK-800881 for the water volume of the cask loading pit room 12463 (Reference 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 xx,xxx gallons and meets the ITAAC Acceptance Criteria of greater than 46,050 gallons.
References 1 and 2 are available for NRC inspection as well as the Unit 4 ITAAC completion package (Reference 3).
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-21-0156 Enclosure Page 3 of 3 References ^available for NRG inspection)
- 1. 26139-000-4MP-T81C-N3201, "Construction Survey"
- 2. SV4-SFS-FSK-800881, "Water Volume of the Cask Loading Pit Room 12463"
- 3. 2.3.07.07b.vii-U4-CP-Rev0, ITAAC Completion Package
- 4. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"