ND-20-1354, ITAAC Closure Notification on Completion of ITAAC 2.2.01.07.i (Index Number 107)

ITAAC Closure Notification on Completion of ITAAC 2.2.01.07.i (Index Number 107)

ML20345A263
Person / Time
Site:	Vogtle
Issue date:	12/10/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-1354
Download: ML20345A263 (7)

Text

,1 l. I I Michael J. Vox 7825 River Road

^OU'tn0rn iNUCl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel Docket No.: 52-025 ND-20-1354 DEC 1 0 2020 10CFR 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 2.2.01.07.i [Index Number 107]

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 2.2.01.07.1 [Index Number 107], for verifying the leakage rate from containment for the integrated leak rate test is less than La.

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 is 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. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.01.07.1 [Index Number 107]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-20-1354 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. 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. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Ms. M. Bailey (w/o enclosures)

Mr. M. King Mr. H. K. Nieh Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mrs. M. Bailey Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. E. Davidson Mr. T. Fanelli Mr. S. Rose Ms. K. McCurry

U.S. Nuclear Regulatory Commission ND-20-1354 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Daiton Utilities Mr. T. Bundros Westinohouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. 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. Mails, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, inc.

Mr. 8. Roetger, Georgia Public Sen/ice 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-20-1354 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-1354 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.01.07.1 [Index Number 107]

U.S. Nuclear Regulatory Commission ND-20-1354 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

7. The CMS 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.

I nsoections/Tests/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 La.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Containment System (CMS) 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 performed a Type A containment integrated leak rate test (ILRT) to confirm that the leakage rate from containment was less than La. La is defined as the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J.

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

The ILRT test included prerequisites that verified the local leak rate testing (LLRT) was completed to support performance of the ILRT. Containment isolation valves were placed in their post-accident positions and closure was 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, were opened or vented to the containment atmosphere prior to 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 were 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 allowed them to be subjected to the full differential test pressure. Tanks inside the containment were vented to the containment atmosphere as necessary to protect them from the effects of external test pressure and/or to preclude leakage which could have affected the accuracy of the test results. Similarly, instrumentation and other components that could be adversely affected by the test pressure were vented or removed from containment.

The containment was pressurized and time was allotted for outgassing. Containment pressure was then increased to full test pressure, allowed to stabilize and then the leak test was commenced. During the test, containment pressure, calculated mass, dry bulb temperature and dew-point temperature were recorded. After the required data was obtained, a slow, monitored

U.S. Nuclear Regulatory Commission ND-20-1354 Enclosure Page 3 of 4 pressure decrease was started and utilized to verify the accuracy of the leak rate data obtained during the ILRT.

The leakage rate from containment was corrected for measurement uncertainty and calculated utilizing the methodology described in ANSI/ANS-56.8-1994. The containment leakage rate for Unit 3 was 0.0269 La. The Unit 3 completed ILRT test(Reference 1)confirmed the leakage rate from containment was less than La and is documented in Reference 2.

References 1 and 2 are available for NRG inspection as well as the Unit 3 ITAAC 2.2.01.07.1 Completion Package(Reference 4).

ITAAC Finding Review 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 one finding of a performance deficiency documented in Inspection Report 05200025/2020009 for failure to complete the containment system prior to commencing the Unit 3 ILRT. This condition was related to retaining rings for the containment Electrical Penetration Assemblies(EPAs) not being installed prior to the performance of the ILRT. To address this concern, the following actions were taken, as part of Corrective Action Report(CAR)80003535.

• Pressure retaining rings were installed around the affected welds

• ASME pressure testing (solution film testing) was performed on the retaining rings

• LLRT testing was performed on each pressure retaining ring

• LLRT data was added to the type B and C testing The LLRT results were added to the Upper Confidence Level calculation and the impact was negligible.

The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.01.07.1 (Reference 4) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.07.1 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.

U.S. Nuclear Regulatory Commission ND-20-1354 Enclosure Page 4 of 4 References (available for NRG inspection^

1. 3-CNS-ITPP-501, Rev 6.0,"Containment Integrated Leak Rate Test(Type A)"

2. SV3-CNS-ITR-800107, Rev 0, "Unit 3 Recorded Results of Containment Integrated Leak Rate Test: ITAAC 2.2.01.07.1"

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

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