ND-21-0168, ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.iii (Index Number 417)

From kanterella
(Redirected from ML21061A104)
Jump to navigation Jump to search
ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.iii (Index Number 417)
ML21061A104
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/02/2021
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0168
Download: ML21061A104 (6)


Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel Docket No.: 52-025 MAR 0 2 2021 ND-21-0168 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 2.3.08.02.i [Index Number 4171 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 2.3.08.02.iii [Index Number 417], for verifying the SWS tower basin volume. 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 Kelli Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox /

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Completion of ITAAC 2.3.08.02.iii [Index Number 417]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-21-0168 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 Reaulatorv Commission Ms. M. Bailey (w/o enclosures)

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

U.S. Nuclear Regulatory Commission ND-21-0168 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse 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. Matis, Tetra Tech NU8, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GD8 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0168 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0168 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.08.02.iii [Index Number 417]

U.S. Nuclear Regulatory Commission ND-21-0168 Enciosure Page 2 of 3 ITAAC Statement Design Commitment

2. The SWS provides the nonsafety-reiated function of transferring heat from the component cooling water system to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling.

I nspections/Tests/Analvses ill) Testing will be performed to confirm that the SWS cooling tower basin has adequate reserve volume.

Acceptance Criteria ill) The SWS tower basin contains a usable volume of at least 230,000 gallons at the basin low level alarm setpoint.

ITAAC Determination Basis Multiple ITAAC are performed to verify that the Service Water System (SWS) provides the nonsafety-reiated function of transferring heat from the Component Cooling Water System (CCS)to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling.

The subject ITAAC requires testing be performed to confirm that the SWS cooling tower basin contains useabie volume of at least 230,000 gallons at the basin low level alarm setpoint.

This ICN differs from the UIN due to a design change that was incorporated into the SWS cooling tower basin instrumentation. The iow-2 condition was changed from being the low level alarm to being a warning that the low level is being approached. The new low level condition is the low-3 alarm and the low-1 condition remained unchanged. Low-3 is equivalent to Low-2 described in the UIN.

Testing was performed in accordance with Unit 3 preoperational test procedure 3-SWS-ITPP-501 (Reference 1) and confirmed that the SWS pumps will operate to provide required flow and pressure at the low-3 alarm setpoint in the SWS cooling tower basin. The usable volume is defined as the volume contained between the low level alarm setpoint (iow-1) and the lowest usable level alarm setpoint (low-3). As part of the test procedure, the as-built dimensions of the basin and all structural components that reduce the useabie volume, were measured. The as-built dimensions along with the appropriate measurement uncertainty were used to determine the basin volume.

The preoperational test which was performed using Work Order 1051753(Reference 2) ensured the SWS was in a normal system alignment with the cooling tower basin divider open and makeup water isolated. The cooling tower basin level was lowered to the low-3 setpoint and both SWS pumps were verified to provide the proper pressure and flow. The usable volume of the basin was calculated by measuring the as-buiit dimensions of the basin between the iow-1 and iow-3 setpoints and subtracting the as-buiit volume of the structural components inside the basin. The results of the volume calculation and the SWS pump testing demonstrated the Unit 3 SWS cooling tower basin contains 239,541 usable gallons at the Iow-1 setpoint.

U.S. Nuclear Regulatory Commission ND-21-0168 Enclosure Page 3 of 3 The Unit 3 preoperational test results (Reference 1) confirmed that the SWS cooling tower basin contains a usable volume of at least 230,000 gallons at the basin low level alarm setpolnt. This was documented In References 1 and 3.

References 1 through 3 are available for NRG Inspection as well as Unit 3 ITAAC 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 there were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review Is documented In the ITAAC Completion Package for ITAAC 2.3.08.02.III (Reference 4) and Is available for NRC review.

ITAAC Completion Statement Based on the above Information, SNC hereby notifies the NRC that ITAAC 2.3.08.02.III 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.

References(available for NRC inspection)

1. 3-SWS-ITPP-501, Rev 3.0,"Service Water System Preoperational Tesf
2. Work Order 1051753,"(ITAAC) 3-SWS-ITPP-501 Preoperational Tesf
3. SV3-SWS-ITR-801417, Rev. 0,"Unit 3 Recorded Results of Service Water System Tower Basin Volume: ITAAC 2.3.08.02.111"
4. 2.3.08.02.lll-U3-CP-Rev0, ITAAC Completion Package