ND-19-0332, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.01.03.ii (Index Number 281)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.01.03.ii (Index Number 281)

ML19106A207
Person / Time
Site:	Vogtle
Issue date:	04/16/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0332
Download: ML19106A207 (9)

Text

^ Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel APR 1 6 2019 Docket Nos.: 52-025 52-026 ND-19-0332 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 2.3.01.03.11 (Index Number 2811 Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 1, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.3.01.03.11 [Index Number 281] has not been completed greater than 225-days prior to Initial fuel load. The Enclosure describes the plan for completing ITAAC 2.3.01.03.11[Index Number 281]. 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-19-0332 Page 2 of 4 Respectfully submitted, Micliael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.01.03.ii [Index Number 281]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0332 Page 3of 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 Reoulatorv Commission Mr. W.Jones(w/o enclosures)

Mr. F. D. Brown Ms. J. M. Heisserer Mr. C. P. Patel Mr. G. J. Khourl 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 Oalethorpe 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-19-0332 Page 4 of 4 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. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0332 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-19-0332 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.01.03.11 [Index Number 281]

U.S. Nuclear Regulatory Commission ND-19-0332 Enclosure Page 2of 5 ITAAC Statement Desion Commitment

3. The CCS provides the nonsafety-related functions of transferring heat from the RNS during shutdown and the spent fuel pool cooling system during all modes of operation to the SWS.

4. Controls exist in the MCR to cause the pumps identified in Table 2.3.1-1 to perform the listed functions.

5. Displays of the parameters identified in Table 2.3.1-1 can be retrieved in the MCR.

I nspections/Tests/Analvses ii) Testing will be performed to confirm that the CCS can provide cooling water to the RNS HXs while providing cooling water to the SFS HXs.

Testing will be performed to actuate the pumps identified in Table 2.3.1-1 using controls in the MCR.

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

Acceptance Criteria ii) Each pump of the CCS can provide at least 2685 gpm of cooling water to one RNS HX and at least 1200 gpm of cooling water to one SFS HX while providing at least 4415 gpm to other users of cooling water.

Controls in the MCR operate to cause pumps listed in Table 2.3.1-1 to perform the listed functions.

The displays identified in Table 2.3.1-1 can be retrieved in the MCR.

ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Component Cooling Water System (CCS) provides the nonsafety-related functions of transferring heat from the Normal Residual Heat Removal System (RNS)during shutdown and the Spent Fuel Pool Cooling System (SFS)during all modes of operation to the Service Water System (SWS), that controls exist in the Main Control Room (MCR)to cause the pumps identified in VEGP Combined License(COL)

Appendix C Table 2.3.1-1 to perform the listed function, and displays of the parameters identified in COL Appendix C Table 2.3.1-1 can be retrieved in the MCR. This ITAAC requires testing and inspections to be performed to confirm that the CCS can provide cooling water to the RNS Heat Exchangers(HXs) while providing cooling water to the SFS HXs,that controls in the MCR operate to actuate the pumps in COL Attachment C Table 2.3.1-1, and displays listed in COL Attachment C Table 2.3.1-1 can be retrieved in the MCR.

ii) Each pumo of the CCS can provide at least 2685 com of coolino water to one RNS HX and at least 1200 oom of coolino water to one SFS HX while providing at least 4415 com to other users of coolino water.

U.S. Nuclear Regulatory Commission ND-19-0332 Enclosure Page 3of 5 Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-CCS-ITPP-501 and 4-CCS-ITPP-501 (References 1 and 2)to verify that each COS pump can provide at least 2685 gpm of cooling water to one RNS HX and at least 1200 gpm of cooling water to one BPS HX while providing at least 4415 gpm to other users of cooling water.

The test is conducted by running each COS pump, individually, to supply one RNS HX,one SFS HX and other users of COS in the Auxiliary, Containment, and Turbine buildings. CCS Pump A is placed into service and when steady flow is established to SFS HX A, RNS HX A and the other users of CCS,flow is measured using a combination of permanently installed and temporarily installed flow instrumentation. The flow values are recorded and verified to meet the acceptance criteria. This testing is repeated using the CCS pump B, SFS HX B, RNS HX B, and the same other users of cooling water. The component flows measured during testing are summarized in Attachment A.

The completed preoperational tests confirm that each CCS pump for Unit 3 and Unit 4 can provide at least 2685 gpm of cooling water to one RNS HX and at least 1200 gpm of cooling water to one SFS HX while providing at least 4415 gpm to other users of cooling water.

Controls in the MCR operate to cause pumos listed in Table 2.3.1-1 to perform the listed functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNC290928 and SNCXXXXXX (References 3 and 4)to verify that controls exist in the MCR and the controls operate to cause the pumps listed in Table 2.3.1-1 (Attachment B)to perform the listed functions.

The component test begins with the pumps in Attachment B in the shutdown condition with an operator stationed locally to monitor and verify pump operation. The A CCS pump is started using PLS controls and the pump start is verified locally and in the MCR. The A CCS pump is stopped and this testing is repeated with the B CCS pump.

The test results confirm that controls in Unit 3 and Unit 4 MCR operate to cause the pumps listed in Table 2.3.1-1 to perform the listed functions.

The disolavs identified in Table 2.3.1-1 can be retrieved in the MCR.

The inspection is performed in accordance with Unit 3 and Unit 4 component test procedures SNC290928 and SNCXXXXXX (References 3 and 4)to verify that the displays identified in Table 2.3.1-1 (Attachment C)can be retrieved in the MCR.

Testing is performed at an operator work station in the Unit 3 and Unit 4 MCR. Each display identified in Attachment C is located and verified to be retrievable and displayed on the operator work station.

The test results confirm that the displays identified in Table 2.3.1-1 can be retrieved in the Unit 3 and Unit 4 MCR.

U.S. Nuclear Regulatory Commission ND-19-0332 Enclosure Page 4 of 5 References 1 through 4 are available for NRG inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages(Reference 5 and 6).

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 favailable for NRG inspection)

1. 3-CCS-ITPP-501,"Component Cooling Water System Preoperational Test Procedure"

2. 4-CCS-ITPP-501,"Component Cooling Water System Preoperational Test Procedure"

3. SNC290928,"CCS Component Indication Verifications - ITAAC: SV3-2.3.01.03.11, Items 4, 5"

4. SNCXXXXXX,"CCS Component Indication Verifications- ITAAC: SV4-2.3.01.03.11, Items 4, 5"

5. 2.3.01.03.ii-U3-CP-Rev 0, ITAAC Completion Package

6. 2.3.01.03.ii-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-19-0332 Enclosure Page 5 of 5 Attachment A 008 Oomponent Flow Values 8F8 HX Flow Other 8ystem Flows 008 Pump RN8 HX Flow(gpm)

(gpm) (gpm)

Unit 3 A xxxx XXXX XXXX Unit 3 B xxxx xxxx XXXX Unit 4 A xxxx xxxx XXXX Unit 4 B xxxx xxxx XXXX Attachment B Excerpt from COL Appendix C Table 2.3.1-1 Equipment Name Tag No. Oontrol Function COS Pump A CCS-MP-01A Start COS Pump B CCS-MP-01B Start Attachment 0 Excerpt from COL Appendix C Table 2.3.1-1 Equipment Name Tag No. Display COS Pump A CCS-MP-01A Yes(Run Status)

COS Pump B CCS-MP-01B Yes(Run Status)

COS Discharge Header Flow Sensor CCS-101 Yes COS to Normal Residual Heat Removal System CCS-301 Yes Heat Exchanger(RNS HX)A Flow Sensor COS to RNS HX B Flow Sensor CCS-302 Yes COS to Spent Fuel Pool Cooling System (SFS) CCS-341 Yes HX A Flow Sensor CCS to SFS HX B Flow Sensor CCS-342 Yes CCS Surge Tank Level Sensor A CCS-130 Yes CCS Surge Tank Level Sensor B CCS-131 Yes CCS Heat Exchanger Inlet Temperature Sensor CCS-121 Yes CCS Heat Exchanger Outlet Temperature Sensor CCS-122 Yes CCS Flow to Reactor Coolant Pump(RCP)1A CCS-PL-V256A Yes Valve (Position Indicator)

CCS Flow to RCP 1B Valve (Position Indicator) CCS-PL-V256B Yes CCS Flow to RCP 2A Valve (Position Indicator) CCS-PL-V256C Yes CCS Flow to RCP 2B Valve (Position Indicator) CCS-PL-V256D Yes