ND-19-0208, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.08.02.1 (Index Number 415)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.08.02.1 (Index Number 415)

ML19066A215
Person / Time
Site:	Vogtle
Issue date:	03/07/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0208
Download: ML19066A215 (9)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tei MAR 0 7 2019 Docket Nos.: 52-025 52-026 ND-19-0208 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.08.02.1 [Index Number 415]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 25, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.3.08.02.1

[Index Number 415] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.3.08.02.1[Index Number 415]. 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-19-0208 Page 2 of 4 Respectfully submitted, Michael J. Yo:j Regulatory Affaii^ Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.08.02.1 [Index Number 415]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0208 Page 3of 4 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. Yox 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 Qqiethorpe 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-19-0208 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinahouse Electric 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. 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 Sen/ice 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-19-0208 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-0208 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.08.02.1 [Index Number 415]

U.S. Nuclear Regulatory Commission ND-19-0208 Enclosure Page 2of 5 ITAAC Statement Design Commitment

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

3. Controls exist in the MCR to cause the components identified in Table 2.3.8-1 to perform the listed function.

4. Displays of the parameters identified in Table 2.3.8-1 can be retrieved in the MCR.

Inspections/Tests/Analvses i) Testing will be performed to confirm that the SWS can provide cooling water to the CCS heat exchangers.

Testing will be performed on the components in Table 2.3.8-1 using controls in the MCR.

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

Acceptance Criteria i) Each SWS pump can provide at least 10,000 gpm of cooling water through its CCS heat exchanger.

Controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions.

The displays identified in Tabie 2.3.8-1 can be retrieved in the MCR.

ITAAC Completion Description This ITAAC requires testing and inspections be performed to demonstrate that the Service Water System(SWS)provides the nonsafety-related function of transferring heat from the Component Cooling Water System (CCS)to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling, ensure controls in the Main Control Room (MCR)operate to cause the components listed in Table 2.3.8-1 to perform the listed function, and ensure the displays of parameters identified in Table 2.3.8-1 can be retrieved in the MCR.

if Each SWS pumo can provide at least 10.000 gpm of cooling water through its CCS heat exchanger.

Multiple ITAAC are performed to demonstrate the SWS provides the nonsafety-related function of transferring heat from the component cooling water system to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling. Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-SWS-ITPP-501 and 4-SWS-ITPP-501 (References 1 and 2)to verify that each SWS pump can provide at least 10,000 gpm of cooling water through its CCS heat exchanger.

U.S. Nuclear Regulatory Commission ND-19-0208 Enclosure Page 3of 5 Initial conditions are established with the SWS train B pump in service with a temporary flow instrument installed upstream of the COS B heat exchanger. The temporary flow instrument is monitored for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 6 minute intervals and the flow value is determined and verified to be greater than 10,000 gpm. This testing is repeated with the SWS pump A and the A COS heat exchanger. The test results show that the Unit 3 B SWS pump provides XX,XXX gpm through Unit 3 B COS heat exchanger, the Unit 3 A SWS pump provides XX,XXX gpm through Unit 3 A COS heat exchanger. The Unit 4 B SWS pump provides XX,XXX gpm through Unit 4 B COS heat exchanger and the Unit 4 A SWS pump provides XX,XXX gpm through Unit 4 A COS heat exchanger. These test results confirm that each SWS pump can provide at least 10,000 gpm of cooling water through its COS heat exchanger Controls in the MGR operate to cause the components listed in Table 2.3.8-1 to oerform the listed functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNC922111 and SNCXXXXXX (References 3 and 4)to verify that controls exist in the MCR and the controls operate to cause the components listed in COL Appendix C Table 2.3.8-1 (Attachment A)for each Unit to perform the listed functions.

The component tests are conducted using controls at an operator work station in the MCR with the A SWS pump in service. SWS cooling tower fan A is started using its temperature controller from the operator work station. The B SWS pump is then started, its discharge valve is verified to open, and the A SWS pump is removed from service. The SWS cooling tower cells are then aligned to place the B cooling tower cell and the B cooling tower fan in service. SWS cooling tower fan B is started using its temperature controller from the operator work station. The SWS pumps are then realigned to place A SWS pump in service and the A SWS pump discharge valve is verified to open. These test results confirm that controls in Unit 3 and Unit 4 MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions.

The disolavs identified in Table 2.3.8-1 can be retrieved in the MCR.

The inspection is performed in accordance with Unit 3 and Unit 4 component test procedures SNC922111 and SNCXXXXXX (References 3 and 4)to verify that the displays identified in COL Appendix C Table 2.3.8-1 (Attachment B)can be retrieved in the MCR.

Testing is conducted 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 2.3.8-1 can be retrieved in the Unit 3 and Unit 4 MCR.

The completed test results(References 1 through 4), confirm that for Unit 3 and Unit 4, each SWS pump can provide at least 10,000 gpm of cooling water through its CCS heat exchanger, that the controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions, and that the displays identified in Table 2.3.8-1 can be retrieved in the MCR.

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

U.S. Nuclear Regulatory Commission ND-19-0208 Enclosure Page 4 of 5 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 favailabie for NRC inspection)

1. 3-SWS-ITPP-501,"Service Water System Preoperational Test"

2. 4-SWS-ITPP-501,"Service Water System Preoperational Test"

3. SNC922111,"Service Water Indication and Control Function Verifications- ITAAC: SV3-2.3.08.02.1, Items 3 and 4"

4. SNCXXXXXX,"Service Water Indication and Control Function Verifications - ITAAC: SV4-2.3.08.02.1, Items 3 and 4"

5. 2.3.08.02.i-U3-CP-Rev 0, ITAAC Completion Package

6. 2.3.08.02.i-U4-CP-Rev 0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0208 Enclosure Page 5 of 5 Attachment A Excerpt from COL Appendix C Table 2.3.8-1 Equipment Name Tag No. Control Function Service Water Pump A (Motor) SWS-MP-01A Start Service Water Pump B (Motor) SWS-MP-01B Start Service Water Cooling Tower Fan A SWS-MA-01A Start (Motor)

Service Water Cooling Tower Fan B SWS-MA-01B Start (Motor)

Service Water Pump A Discharge SWS-PL-V002A Open Valve Service Water Pump B Discharge SWS-PL-V002B Open Valve Attachment B Excerpt from COL Appendix C Table 2.3.8-1 Equipment Name Tag No. Display Service Water Pump A (Motor) SWS-MP-01A Yes(Run Status)

Service Water Pump B (Motor) SWS-MP-01B Yes(Run Status)

Service Water Cooling Tower Fan A SWS-MA-01A Yes(Run Status)

(Motor)

Service Water Cooling Tower Fan B SWS-MA-01B Yes(Run Status)

(Motor)

Service Water Pump 1A Flow Sensor SWS-004A Yes Service Water Pump 1B Flow Sensor SWS-004B Yes Service Water Pump A Discharge SWS-PL-V002A Yes(valve position)

Valve Service Water Pump B Discharge SWS-PL-V002B Yes(valve position)

Valve Service Water Pump A Discharge SWS-005A Yes Temperature Sensor Service Water Pump B Discharge SWS-005B Yes Temperature Sensor Service Water Cooling Tower Basin SWS-009 Yes Level