ND-20-0433, ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.06a (Index Number 787)

ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.06a (Index Number 787)

ML20118C603
Person / Time
Site:	Vogtle
Issue date:	04/27/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 3.3.00.06a, ND-20-0433
Download: ML20118C603 (6)

Text

C il Ki i Michael J. Yox 7825 River Road SL Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogfle3&4 706-848-6459 fel April 27, 2020 Docket Nos.: 52-026 ND-20-0433 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 4 ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.06a Hndex Number 7871 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 4 Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) Item 3.3.00.06a [Index Number 787]. This ITAAC concludes that the as-built available room volumes of the radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11). 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) request 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 Vogtle 3&4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 3.3.00.06a [Index Number 787]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-20-0433 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. D. H. Jones (w/o enclosures)

Mr. G. Chick Mr. M. Page 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 Ms. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reouiatorv Commission Mr. W. Jones (w/o enclosures)

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 Mr. C. Santos Ms. M. Bailey Mr. S. Rose Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Carrington Mr. P. Heher

U.S. Nuclear Regulatory Commission ND-20-0433 Page 3 of 3 Nuclear Regulatory Commission fcon't)

Mr. M. King Mr. E. Davidson Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utiiities Mr. T. Bundros Westinahouse Electric Companv. 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. 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-20-0433 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0433 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC Item 3.3.00.06a [Index No. 787]

U.S. Nuclear Regulatory Commission ND-20-0433 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 6.a) The available room volumes of the radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).

I nspections/Tests/Analvses An inspection will be performed of the as-built radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82'-6" to define volume.

Acceptance Criteria A report exists and concludes that the as-built available room volumes of the radiologically controlled area of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).

ITAAC Determination Basis This ITAAC requires that an inspection be performed of the as-built radiologically controlled area(RCA)of the auxiliary building between floor elevations 66'-6" and 82'-6" to ensure available room volume exceeds the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).

The as-built tank diameters are documented in the as-built information contained in the Quality Assurance Data Package (QADP) provided for the eight liquid radwaste storage tanks. In addition, field measurements were obtained to supplement the Tank's QADP data to obtain the tank parameters necessary to support the tank volume calculations in Reference 2.

Inspections of the RCA portion of the auxiliary building rooms between elevations 66'-6" and 82'-6" were performed to the extent necessary to demonstrate and document that available room volume is more than the as-built tank volumes. Available room volume for this purpose is defined as the total room volume minus the volume of components or commodities within the room. Qnly those RCA auxiliary building rooms needed to provide the available room volume needed to meet the ITAAC acceptance criteria were inspected. Examples of such rooms are defined personnel and/or equipment access corridors, and reserved equipment removal spaces.

Measurements taken to calculate available room volume were taken in accordance with the ITAAC Support Activities procedure (Reference 1), as applicable.

The as-built tank volumes of the liquid radwaste storage tanks are 21,398 ft^ and the available room volume of the RCA in the auxiliary building is 27,228 ft. The inspection plan, results of the visual inspections, available room volume calculation, and as-built tank volumes are documented in Principal Closure Documents(Reference 2)that demonstrate that the as-built available room volumes for the RCA portion of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the as-built volume of the liquid radwaste storage tanks.

U.S. Nuclear Regulatory Commission ND-20-0433 Enclosure Page 3 of 3 The inspection results and calculations conclude that the as-built available room volumes of the RCA of the auxiliary building between floor elevations 66'-6" and 82'-6" exceed the volume of the liquid radwaste storage tanks(WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).

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 these ITAAC. The ITAAC completion review is documented in the ITAAC Completion Packages for ITAAC 3.3.00.06a, Unit 4(Reference 3) and are available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.3.00.06a was performed for VEGP Unit 4 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. NCSP 02-24, Rev. 3,"ITAAC Support Activities (AP1000)"

2. SV4-WLS-ITR-800787, Rev. 0,"Unit 4: ITAAC 787 Auxiliary Building Radiation Area As-Built Available Room Volume (3.3.00.06a)

3. 3.3 00.06a-U4-CP-Rev0, ITAAC Completion Package