ND-18-0534, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.09a.i (Index Number 201)
| ML18120A282 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/27/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0534 | |
| Download: ML18120A282 (6) | |
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Southern Nuclear APR 2 7 2018 Docket Nos.:
52-025 52-026 Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynestjoro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0534 10CFR 52.99(c)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.09a.i (Index Number 2011 Ladies and Gentlemen:
Pursuant to 10 CFR52.99(c)(3), Southern Nuclear Operating Companyhereby notifies the NRC that as ofApril 12, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.09a.i [Index Number 201] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. 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 Guidelinefor 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 completedand 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 Tom Petrak at 706-848-1575.
Respectfully submitted.
Michael J. Yox^;
Regulatory Affairs Director Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.09a.i [Index Number 201]
MJY/PGL/amw
U.S. Nuclear Regulatory Commission ND-18-0534 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Regulatory Commission Mr. W. Jones (w/o enclosures)
Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oolethorpe Power Corooration Mr. R. B. Brinkman
U.S. Nuclear Regulatory Commission ND-18-0534 Page 3 of 3 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 Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., CDS 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, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0534 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0534 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 2.2.03.09a.i [Index Number201]
U.S. Nuclear Regulatory Commission ND-18-0534 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment 9.a) The PXS provides a function to cool the outside of the reactor vessel during a severe accident.
Insoections/Tests/Analvses i) Aflow test and analysisforeach IRWST drain line to the containment will be conducted. The test is initiated by opening isolation valves in each line. Test fixtures may be used to simulate squib valves.
Acceptance Criteria i) The calculated flow resistancefor each IRWST drain line between the IRWST and the containment is ^ 4.44 x 10 ft/gpm^.
ITAAC Completion Description Multiple ITAAC are performed toverify that the Passive Core Cooling System (PXS) provides a function to coolthe outside ofthe reactorvessel during a severe accident. The subject ITAAC requires a flow testandanalysis on each In-containment Refueling Water Storage Tank (IRWST) drain line tothecontainment todemonstrate thatthe calculated flow resistance meets acceptance criteria.
Performance tests are conducted in accordance with Unit3 and Unit 4 preoperational test procedures (Reference 1and 2, respectively) to demonstrate that the flow resistance in each IRWSTdrain line to the containment is < 4.44 x 10 ft/gpm^.
This isaccomplished by installing a compression plug in the IRWST screenBdrain line, installing flow test fixtures for the squib valves in the containment recirculation sump lines, filling the IRWST with demineralized water to act as a temporarywater supply, and initiating flow from the Ascreen in the IRWST into the containmentrecirculation sump to recirculation injection line Bto the reactorvessel. All valves inthese linesare opened during the test and sufficient fiow is provided toopen thecheck valves. The flow rate between the IRWST andthecontainment sump A, differential pressure, and IRWST level are monitored and recorded. The process is then repeated with IRWST screen Btothe containment sump toreactor vessel injection line A.
The constant value for each flow resistance is calculated, based on tank level, differential pressure and discharge flow, adjusted for measurement uncertainty, and compared tothe acceptance criteria.
The flow resistance for each Unit 3 IRWST drain line between the IRWST and the containment iscalculated to be XXX ft/gpm^ (drain line A) and YYY ft/gpm^ (drain line B). Theflow resistance for each Unit 4 IRWSTdrain line between the IRWSTand the containment is calculated to be XXX ft/gpm^ (drain line A) and YYY ft/gpm^ (drain line B). Thecompleted Unit 3 and Unit 4 preoperational testsconfirm that thecalculated flow resistance for each IRWST drain linebetween the IRWST and the containment is ^ 4.44 x 10" ft/gpm^.
U.S. Nuclear Regulatory Commission ND-18-0534 Enclosure Page 3 of 3 References 1 and 2 are available for NRCinspection as part of tfie Unit 3 and Unit 4ITAAC 2.2.03.09a.i Completion Packages (References 3 and 4).
List of ITAAC Findings Inaccordance with plant procedures for ITAAC completion, Southern NuclearOperating Company (SNC) performed a review ofallfindings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.
References favaiiabie for NRC inspection)
- 1. 3-PXS-ITPP-5XX, "Passive Core Cooling System Preoperational Test Procedure"
- 2. 4-PXS-ITPP-5XX, "Passive Core CoolingSystem Preoperational Test Procedure" 3.
2.2.03.09a.i-U3-CP-Rev X, ITAAC Completion Package 4.
2.2.03.09a.i-U4-CP-Rev X, ITAAC Completion Package 5.
NEI 08-01,"Industry Guideline forthe ITAAC Closure Process Under10 CFR Part 52"