ND-18-0913, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.07.1 (Index Number 107)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.07.1 (Index Number 107)

ML18180A090
Person / Time
Site:	Vogtle
Issue date:	06/28/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.01.07.i, ND-18-0913
Download: ML18180A090 (6)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@souttiernco.com m 1 >> 2018 Docket Nos.: 52-025 52-026 ND-18-0913 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 Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.07.1 [Index Number 1071 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 25, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.07.1 [Index Number 107]

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 Guideline for 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 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 Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox C/ ^

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.07.1 [Index Number 107]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0913 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Vox 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 Reaulatorv 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 Oqlethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0913 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. 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., 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0913 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0913 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.07.1 [Index Number 107]

U.S. Nuclear Regulatory Commission ND-18-0913 Enclosure Page 2 of 3 ITAAC Statement Design Commitment

7. The CNS provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere.

InspectionsTTests/Analvses i) A containment integrated leak rate test will be performed.

Acceptance Criteria i) The leakage rate from containment for the integrated leak rate test is less than U.

ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Containment System (CNS) provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere. The subject ITAAC performsa Type Acontainment integrated leak rate test (ILRT) to confirm that the leakage rate from containment is less than La. U is defined as the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J.

ILRT is performed in accordance with Unit 3 and Unit 4 test procedures (Reference 1 and 2, respectively), to demonstrate that the leakage rate from containment is less than La. The testing is consistent with the applicable Type A testing guidance contained in ANSI/ANS-56.8-1994 (reference 3).

The ILRT tests include prerequisites that verify local leak rate testing (LLRT) is complete to support performance of the ILRT. Containment isolation valves are placed in theirpost-accident positions and closure is accomplished by normal operation and with no preliminary exercising or adjustments. Those portions of fluid systems that are part of the reactor coolant pressure boundary and are open directly to the containment atmosphere under post-accident conditions and become an extension of the boundary of the containment, are opened or vented to the containment atmosphere priorto and during the test. When required, portions of the systems inside containment that penetrate containment and could rupture as a result of a loss of coolant accident are vented to the containment atmosphere and drained of water to the extent necessary to provide exposure of the containment isolation valves to containment air test pressure and to allow them to be subjectedto the full differential test pressure. Tanks inside the containment are vented to the containment atmosphere as necessary to protect them from the effects of external test pressure and/or to preclude leakage which could affect the accuracy of the test results. Similarly, instrumentation and other components that could be adversely affected by the test pressure are vented or removed from containment.

The containment is pressurized and time is allottedfor outgassing. Containment pressure is then increased to full test pressure, allowed to stabilize and then the leak test is commenced.

During the test, containment pressure, calculated mass, dry bulb temperature and dew-point temperature are recorded. After the required data is obtained a slow, monitored pressure

U.S. Nuclear Regulatory Commission ND-18-0913 Enclosure Page 3 of 3 decrease Is started and utilized to verify the accuracy of the leak rate data obtained during the ILRT.

The leakage rate from containment Is corrected for measurement uncertainty and calculated utilizing the methodology described In ANSI/ANS-56.8-1994. The containment leakage rate for Unit 3 Is O.XX Laand for Unit 4 Is O.YY U. The Unit 3 and Unit 4 completed IRLT tests (References 1 and 2, respectively) confirm the leakage rate from containment Is less than La.

References 1 and 2 are available for NRG Inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.01.07.1 Completion Packages (References 4 and 5, respectively).

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.

References favailable for NRG inspection)

1. 3-CNS-ITPP-501, "Containment Integrated Leak Rate Test (Type A)"

2. 4-CNS-ITPP-501, "Containment Integrated Leak Rate Test (Type A)"

3. ANSI/ANS-56.8-1994, "Containment System Leakage Testing Requirements"

4. 2.2.01.07.l-U3-CP-Rev0, ITAAC Completion Package

5. 2.2.01.07.l-U4-CP-Rev0, ITAAC Completion Package

6. NEI 08-01, "IndustryGuideline for the ITAAC Closure Process Under 10 CFR Part 52"