ND-19-1460, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.09a (Index Number 41)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.09a (Index Number 41)

ML19336D350
Person / Time
Site:	Vogtle
Issue date:	12/02/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1460
Download: ML19336D350 (6)

Text

C 4-U Kl I MichaelJ. Yox 7825 River Road jOUtnGrn iNUClGdr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel DEC 0 2 2019 Docket Nos.: 52-025 52-026 ND-19-1460 10 CFR 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 2.1.02.09a [Index Number 411 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 2, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.09a

[Index Number 41] 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. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.09a [Index Number 41]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-1460 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. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown 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 M C. Welch M J. Gaslevic M V. Hall M G. Armstrong Ms. T. Lamb M M. Webb M T. Fredette M C. Weber M S. Smith M C. Santos Oolethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1460 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Eiectric Company. LLC Dr. L. OrianI (w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1460 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-1460 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Pian for Uncompieted ITAAC 2.1.02.09a [Index Number 41]

U.S. Nuclear Regulatory Commission ND-19-1460 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 9.a) The PCS provides circulation of coolant to remove heat from the core.

Inspections/Tests/Analvses Testing and analysis to measure PCS flow with four reactor coolant pumps operating at no-load PCS pressure and temperature conditions will be performed. Analyses will be performed to convert the measured pre-fuel load flow to post-fuel load flow with 10-percent steam generator tube plugging.

Acceptance Criteria The calculated post-fuel load PCS flow rate is a 301,670 gpm.

ITAAC Completion Description Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-PCS-ITPP-506 and 4-PCS-ITPP-506(References 1 and 2)to confirm that at no-load Reactor Coolant System (PCS) pressure and temperature conditions, the calculated post-fuel load PCS flow rate is ^ 301,670 gpm with 10-percent steam generator tube plugging.

The testing measures PCS parameters using installed and temporary instrumentation and is trended and recorded using plant computer trends and a high-speed data acquisition system.

When the PCS is at approximately 557°F and 2240 psig with all 4 Reactor Coolant Pumps (PCPs) at 100% speed for a minimum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure thermal stability, the trend data is taken for approximately 10 minutes. This data is analyzed to determine the post-fuel load flow rate with 10-percent steam generator tube plugging. This analysis is documented and attached to References 1 and 2.

The results of the testing and analysis demonstrate that Unit 3 PCS flow rate is XXX,XXX gpm and Unit 4 PCS flow rate is YYY,YYY gpm which confirms the calculated post-fuel load PCS flow rate is ^ 301,670 gpm.

References 1 and 2 are available for NPC inspection as part of Unit 3 and Unit 4 ITAAC 2.1.02.09a Completion Packages(Reference 3 and 4).

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.

U.S. Nuclear Regulatory Commission ND-19-1460 Enclosure Page 3 of 3 References favailable for NRG inspection)

1. 3-RCS-ITPP-506,"Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional"

2. 4-RCS-ITPP-506,"Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional"

3. 2.1.02.09a-U3-CP-Rev0, ITAAC Completion Package

4. 2.1.02.09a-U4-CP-Rev0, ITAAC Completion Package

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