ND-19-0121, Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.ii (Index Number 181)

Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.ii (Index Number 181)

ML19050A364
Person / Time
Site:	Vogtle
Issue date:	02/19/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.08c.ii, ND-19-0121
Download: ML19050A364 (6)

Text

Michael J. Yox 7825 River Road A Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3& 4 706-848-6459 tei 410-474-8587 cell FEB 1 9 21119 rnyox@southernco.Gom Docket Nos.: 52-025 52-026 ND-19-0121 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 2.2.03.08c.ii [Index Number 1811 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 12, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.ii

[Index Number 181] 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 Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.ii [Index Number 181]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0121 Page 2of 3 To:

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

Mr. D. L. McKinney(w/o enclosures)

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

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

Mr. J. B. Klecha Mr. G. Chick Mr. M. J. Vox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Ms. J. M. Heisserer 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. I. Cozens Mr. J. Gaslevic Mr. V. Hall Oaiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0121 Page 3of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Eiectric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward 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, Balch BIngham

U.S. Nuclear Regulatory Commission ND-19-0121 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0121 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.ii [Index Number 181]

U.S. Nuclear Regulatory Commission ND-19-0121 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Insoections/Tests/Analvses ii) A low-pressure test and analysis will be conducted for each CMT to determine piping flow resistance from the cold leg to the CMT. The test will be performed by filling the CMT via the cold leg balance line by operating the normal residual heat removal pumps.

Acceptance Criteria ii) The flow resistance from the cold leg to the CMT is < 7.21 x 10" ft/gpm^.

ITAAC Completion Description Multiple ITAAC are performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. The subject ITAAC requires a low-pressure injection test and analysis on each Core Makeup Tank(CMT) balance line to the reactor coolant system cold leg to demonstrate that the flow resistance is ^ 7.21 x 10" ft/gpm^.

A preoperational test is conducted in accordance with Unit 3 and Unit 4 preoperational test procedures (References 1 and 2)to determine that the flow resistance from the cold leg to the CMT. Initial conditions are established with the Reactor Coolant System (RCS)filled and the pressurizer is water solid. Temporary flow instruments are installed on the CMT balance line (inlet line), differential pressure instruments are installed between the RCS and the CMT and pressure instruments are installed on the RCS and the CMT. All instruments are connected to a Data Acquisition System (DAQ). Both trains of Normal Residual Heat Removal System (RNS) are in service and the RCS is pressurized to 175 psig.

The test is initiated when the CMT A inlet Motor-Operated Valve(MOV)is opened and the CMT begins to fill. The test is terminated when CMT A upper narrow range instruments are greater than 20% level and the CMT fill is stopped by closing the CMT A inlet MOV,and the RNS is removed from service. The data is collected, and an analysis (Reference 3 and 4)of the data provides a calculation for flow resistance for CMT A. This testing and analysis(Reference 3 and

4) is repeated for CMT B and provides a calculation for flow resistance for CMT B.

The flow resistance for Unit 3 is calculated to be X.XX x 10"*ft/gpm^ for the cold leg to the CMT A and Y.YY x 10"^ ft/gpm^ for the cold leg to the CMT B. The flow resistance for Unit 4 is calculated to be X.XX x 10'* ft/gpm^ for the cold leg to the CMT A and Y.YY x 10"^ ft/gpm^ for the cold leg to CMT B. These results confirm that the calculated flow resistance for each cold leg to the CMT is ^ 7.21 x 10 ft/gpm^.

References 1 through 4 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.08c.ii Completion Packages(References 5 and 6).

U.S. Nuclear Regulatory Commission ND-19-0121 Enclosure Page 3 of 3 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(available for NRC inspection)

1. 3-PXS-ITPP-503,"Passive Core Cooling System Pre-Core Flow Testing with RV Head Installed Preoperational Test Procedure"

2. 4-PXS-ITPP-503,"Passive Core Cooling System Pre-Core Flow Testing with RV Head Installed Preoperational Test Procedure"

3. 3-PXS-XXX,"CMT flow resistance analysis and calculation"

4. 4-PXS-XXX,"CMT flow resistance analysis and calculation"

5. 2.2.03.08c.ii-U3-CP-Rev X, ITAAC Completion Package

6. 2.2.03.08c.ii-U4-CP-Rev X, ITAAC Completion Package

7. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"