ND-19-0261, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.4.01.02 (Index Number 493)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.4.01.02 (Index Number 493)

ML19085A399
Person / Time
Site:	Vogtle
Issue date:	03/25/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0261
Download: ML19085A399 (9)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel MAR 2 5 2019 Docket Nos.: 52-025 52-026 ND-19-0261 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 2.4.01.02 findex Number 4931 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 23, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.4.01.02

[Index Number 493] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.4.01.02[Index Number 493]. 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)(3) 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

U.S. Nuclear Regulatory Commission ND-19-0261 Page 2 of 4 Respectfuliy submitted, Michael J. Yo>

Regulatory Affairs'Director Vogtle 3 & 4 Enclosure; Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.4.01.02 [Index Number 493]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0261 Page 3 of 4 To:

Southern Nuclear Operating Companv/ 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 Reaulatorv 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 Qqiethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-0261 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Orlani(w/o enclosures)

Mr. D. C. 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., GDS Associates, inc.

Mr. 8. Roetger, Georgia Pubiic Service Commission Ms. 8. W. Kemizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0261 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-0261 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.4.01.02[Index Number 493]

U.S. Nuclear Regulatory Commission ND-19-0261 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment

2. The FWS provides startup feedwater flow from the CST to the SGS for heat removal from the RCS.

3. Controls exist in the MCR to cause the components identified in Table 2.4.1-1 to perform the listed function.

4. Displays of the parameters identified in Table 2.4.1-1 can be retrieved in the MCR.

I nsoections/Tests/Analvses Testing will be performed to confirm that each of the startup feedwater pumps can provide water from the CST to both steam generators.

Testing will be performed on the components in Table 2.4.1-1 using controls in the MCR.

Inspection will be performed for retrievability of parameters in the MCR.

Acceptance Criteria Each FWS startup feedwater pump provides a flow rate greater than or equal to 260 gpm to each steam generator system at a steam generator secondary side pressure of at least 1106 psia.

Controls in the MCR operate to cause the components listed in Table 2.4.1-1 to perform the listed functions.

The displays identified in Table 2.4.1-1 can be retrieved in the MCR.

ITAAC Completion Description This ITAAC requires testing and inspections be performed to verify that the Main and Startup Feedwater System (FWS) provides 260 gpm of startup feedwater flow from the Condensate Storage Tank(CST)to the Steam Generator System (SGS)for Reactor Coolant System (RCS) heat removal, that controls exist in the Main Control Room (MCR)and operate to cause the components listed in the VEGP Unit 3 and Unit 4 Combined Operating License COL Appendix C Table 2.4.1-1 (Attachment A)to perform the listed function, and that the displays of parameters identified in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.4.1-1 (Attachment B) can be retrieved in the Main Control Room (MCR).

Each FWS startup feedwater oumo provides a flow rate Greater than or equal to 260 com to each steam generator svstem at a steam Generator secondary side pressure of at least 1106 Dsia.

Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-FWS-ITPP-502 and 4-FWS-ITPP-502(References 1 and 2)to verify that each Startup

U.S. Nuclear Regulatory Commission ND-19-0261 Enclosure Page 3 of 5 Feedwater pump can provide greater than or equal to 260 gpm to each steam generator system at a secondary side pressure of at least 1106 psia.

Initial conditions are established with the plant at Normal Operating Pressure(NOP)and Normal Operating Temperature(NOT)utilizing the plant general operating procedure. Steam Generator pressure control is placed into Automatic to maintain secondary pressure at 1125 psia and temporary flow instruments are installed on the startup feedwater lines to each steam generator.

Main Feedwater flow is stopped and Startup Feedwater flow is initiated using the A Startup Feedwater pump. Flow is recorded and verified to be greater than or equal to 260 gpm to each steam generator system. This testing is repeated using the B Startup Feedwater pump.

The results of the testing show that the Unit 3 A startup feedwater pump provides XXX gpm to the A steam generator and YYY gpm to the B steam generator and the B startup feedwater pump provides XXX gpm to the A steam generator and YYY gpm to the B steam generator. The Unit 4 A startup feedwater pump provides XXX gpm to the A steam generator and YYY gpm to the B steam generator and the B startup feedwater pump provides XXX gpm to the A steam generator and YYY gpm to the B steam generator.

This testing confirms that for Unit 3 and Unit 4 each FWS startup feedwater pump provides a flow rate greater than or equal to 260 gpm to each steam generator system at a steam generator secondary side pressure of at least 1106 psia.

Controls in the MGR operate to cause the components listed in Table 2.4.1-1 to perform the listed functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNCXXXXXX and SNCYYYYYY (References 3 and 4)to verify that controls exist in the MCR and the controls operate to cause the components listed in Table 2.4.1-1 (Attachment A)to perform the listed functions.

The component test begins with the components in Attachment A in the closed position or shutdown condition. An operator is stationed locally to monitor and verify component actuations.

The A startup feedwater pump is started using PLS controls and the pump isolation valve is verified to open. The A startup feedwater pump is stopped and this testing is repeated for the B startup feedwater pump. The test results confirm that controls in Unit 3 and Unit 4 MCR operate to cause the components listed in Table 2.4.1-1 to perform the listed functions.

The disolavs identified in Table 2.4.1-1 can be retrieved in the MCR.

The inspection is performed in accordance with Unit 3 and Unit 4 component test procedures SNCXXXXXX and SNCYYYYYY (References 3 and 4)to verify that the displays identified in Table 2.4.1-1 (Attachment B)can be retrieved in the MCR.

Testing begins at an operator work station in the Unit 3 and Unit 4 MCR and verifies all the displays identified in Attachment B can be retrieved. This confirms that the displays identified in Table 2.4.1-1 can be retrieved in the Unit 3 and Unit 4 MCR.

The completed test results(References 1 through 4), confirm that each of the startup feedwater pumps provide the required flow to each steam generator system, that the controls in the MCR

U.S. Nuclear Regulatory Commission ND-19-0261 Enclosure Page 4 of 5 operate to cause the components listed in Table 2.4.1-1 to perform the listed functions, and that the displays identified in Table 2.4.1-1 can be retrieved in the MGR.

References 1 through 4 are available for NRG inspection as part of Unit 3 and Unit 4ITAAG Completion Packages(Reference 5 and 6).

List of ITAAC Findings In accordance with plant procedures for ITAAG completion, Southern Nuclear Operating Company(SNG) performed a review of all findings pertaining to the subject ITAAG and associated corrective actions. This review found there are no relevant ITAAG findings associated with this ITAAG.

References favaiiabie for NRC inspection^

1. 3-FWS-ITPP-502,"Main and Startup Feedwater System (FWS) Hot Functional Test Procedure"

2. 4-FWS-ITPP-502,"Main and Startup Feedwater System (FWS) Hot Functional Test Procedure"

3. SNGXXXXXX,"SFW Pump Start and Discharge Valve Verification Test- ITAAG: SV3-2.4.01.02, Items 3 and 4"

4. SNGYYYYYY,"SFW Pump Start and Discharge Valve Verification Test- ITAAG: SV4-2.4.01.02, Items 3 and 4"

5. 2.4.01.02-U3-GP-Rev 0, ITAAG Completion Package

6. 2.4.01.02-U4-GP-Rev 0, ITAAG Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0261 Enclosure Page 5 of 5 Attachment A Excerpt from COL Appendix C Table 2.4.1-1 Equipment Name Tag No. Control Function Startup Feedwater Pump A (Motor) FWS-MP-03A Start Startup Feedwater Pump B (Motor) FWS-MP-03B Start Startup Feedwater Pump A Isolation Valve FWS-PL-V013A Open Startup Feedwater Pump B Isolation Valve FWS-PL-V013B Open Attachment B Excerpt from COL Appendix C Table 2.4.1-1 Equipment Name Taq No. Display Startup Feedwater Pump A (Motor) FWS-MP-03A Yes(Run Status)

Startup Feedwater Pump B (Motor) FWS-MP-03B Yes(Run Status)

Startup Feedwater Pump A Isolation Valve FWS-PL-V013A Yes(Valve Position)

Startup Feedwater Pump B Isolation Valve FWS-PL-V013B Yes(Valve Position)