ND-19-0198, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.02.03a (Index Number 703)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.02.03a (Index Number 703)

ML19064A410
Person / Time
Site:	Vogtle
Issue date:	03/05/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0198
Download: ML19064A410 (10)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel MAR 0 5 2019 Docket Nos.: 52-025 52-026 ND-19-0198 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 2.7.02.03a [Index Number 7031 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, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.7.02.03a

[Index Number 703] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.7.02.03a [Index Number 703]. 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-19-0198 Page 2 of 4 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 2.7.02.03a [Index Number 703]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0198 Page 3of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost(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. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Ration 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 Municioai Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-0198 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani(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. 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 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-19-0198 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-19-0198 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.02.03a [Index Number 703]

U.S. Nuclear Regulatory Commission ND-19-0198 Enclosure Page 2of 6 ITAAC Statement Desion Commitment 3.a)The VWS provides chilled water to the supply air handling units serving the MCR,the Class 1E electrical rooms, and the unit coolers serving the RNS and CVS pump rooms.

4. Controls exist in the MCR to cause the components identified in Table 2.7.2-1 to perform the listed function.

5. Displays of the parameters identified in Table 2.7.2-1 can be retrieved in the MCR.

I nsoections/Tests/Analvses Testing will be performed by measuring the flow rates to the chilled water cooling coils.

Testing will be performed on the components in Table 2.7.2-1 using controls in the MCR.

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

Acceptance Criteria The water flow to each cooling coil equals or exceeds the following:

Coil Flow (coml VBSMYC01A/B 96 VBS MY C02A/C 97 VBS MY C02B/D 52 VASMYC07A/B 12.3 VASMYC12A/B 8.2 VAS MY C06A/B 8.2 Controls in the MCR operate to cause the components listed in Table 2.7.2-1 to perform the listed functions.

The displays identified in Table 2.7.2-1 can be retrieved in the MCR.

ITAAC Completion Description This ITAAC requires testing and inspections to be performed to verify that the Central Chilled Water System (VWS)provides the required chilled water flows to the air handling units for the Main Control Room (MCR), the class IE electrical rooms, and the Normal Residual Heat Removal System (RNS) pump room coolers and Chemical and Volume Control System (CVS) pump room coolers. Testing also verifies controls in the Main Control Room(MCR)operate to cause components listed in COL Appendix C Table 2.7.2-1 (Attachment B)to perform their listed function and an inspection is performed to verify the displays identified in COL Appendix C Table 2.7.2-1 can be retrieved in the MCR.

U.S. Nuclear Regulatory Commission ND-19-0198 Enclosure Page 3of 6 The water flow to each cooling coll equals or exceeds the followino:

Coil Flow faoml VBS MY C01A/B 96 VBS MY C02A/C 97 VBS MY C02B/D 52 VAS MY C07A/B 12.3 VAS MYC12A/B 8.2 VAS MY C06A/B 8.2 Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-VWS-ITPP-501 and 4-VWS-ITPP-501 (References 1 and 2)to verify that the cooling water flow to each cooling coil equals or exceeds the required flow rates.

Initial conditions are established with Low Capacity Chiller MS-02 in service and temporary flow instruments installed on the outlet line from each of the coolers tested. The flow control valves are manually opened to ensure full flow through the affected 6 coolers. When the chilled water flow stabilizes, 10 flow readings are taken at 3 minute intervals. The flow value for each cooler is verified to be above the required values, and the system is restored to normal. This testing is then repeated with the Low Capacity Chiller MS-03 and the remaining 6 cooler units. This testing shows that the flows obtained (Attachment A)are greater than or equai to the ITAAC acceptance criteria required flows.

Controls in the MCR operate to cause the components listed in Table 2.7.2-1 to perform the listed functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNC922140 and SNCXXXXXX (References 3 and 4)to verify that controis exist in the MCR and the controls operate to cause the components listed in Table 2.7.2-1 (Attachment B)to perform the listed functions.

The component test begins with the components in Attachment B in the closed position or shutdown condition. The valves are stroked to the open position using controis in the MCR, locally verified to be in the correct position and documented in the test. The ventilation components are started using controls in the MCR, locally verified to have started and documented in the test. The test results confirm that controis in Unit 3 and Unit 4 MCR operate to cause the components iisted in Table 2.7.2-1 to perform the listed functions.

The displavs identified in Table 2.7.2-1 can be retrieved in the MCR.

The inspection is performed in accordance with Unit 3 and Unit 4 component test procedures SNC922140 and SNCXXXXXX (References 3 and 4)to verify that the displays identified in Table 2.7.2-1 (Attachment C)can be retrieved in the MCR.

Testing begins at an operator work station in the Unit 3 and Unit 4 MCR and verifies all of the displays identified in Attachment B can be retrieved. This confirms that the displays identified in Table 2.7.2-1 can be retrieved in the Unit 3 and Unit 4 MCR.

U.S. Nuclear Regulatory Commission ND-19-0198 Enclosure Page 4 of 6 The completed test results (References 1 through 4), confirm that the low capacity chillers provide the required flow to the listed components, that the controls in the MCR operate to cause the components listed in Table 2.7.2-1 to perform the listed functions, and that the displays identified in Table 2.7.2-1 can be retrieved in the MCR.

References 1 through 4 are available for NRC inspection as part of Unit 3and 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 NRC inspection)

1. 3-VWS-ITPP-501,"Central Chilled Water System Preoperational Test"

2. 4-VWS-ITPP-501,"Central Chilled Water System Preoperational Test"

3. SNC922140,"Central Chilled Water System Controls ITAAC: SV3-2.7.02.03a Items 4 and 5"

4. SNCXXXXXX,"Central Chilled Water System Controls ITAAC: SV4-2.7.02.03a Items 4 and 5"

5. 2.7.02.03a-U3-CP-Rev 0, ITAAC Completion Package

6. 2.7.02.03a-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-19-0198 Enclosure Page 5 of 6 Attachment A Chiller Unit Unit Coii Number ITAAC Required Actual Flow Flow(gpm) (gpm) 3 VBS MY 001A 96 XX 3 VBS MY C02A 97 XX MS-02 3 VBS MY C02D 52 XX 3 VAS MY C06A 8.2 X.X 3 VASMYC07A 12.3 XX.X 3 VAS MY C012B 8.2 X.X 3 VBS MY C01B 96 XX 3 VBS MY C02B 52 XX MS-03 3 VBS MY C02C 97 XX 3 VAS MY C06B 8.2 X.X 3 VAS MY C07B 12.3 XX.X 3 VAS MY C012A 8.2 X.X 4 VBS MY 001A 96 XX 4 VBS MY 002A 97 XX MS-02 4 VBS MY 002D 52 XX 4 VAS MY 006A 8.2 X.X 4 VAS MY 007A 12.3 XX.X 4 VAS MY 0012B 8.2 X.X 4 VBS MY 001B 96 XX 4 VBS MY 002B 52 XX MS-03 4 VBS MY 0020 97 XX 4 VAS MY 006B 8.2 X.X 4 VAS MY 007B 12.3 XX.X 4 VAS MY 0012A 8.2 X.X

U.S. Nuclear Regulatory Commission ND-19-0198 Enclosure Page6(rf 6 Attachment B Excerpt from COL Appendix C Table 2.7.2-1 Equipment Name Tag No. Control Function Air-cooled Chiller VWS-MS-02 Start Air-cooled Chiller VWS-MS-03 Start Air-cooled Chiller Pump VWS-MP-02 Start Air-cooled Chiller Pump VWS-MP-03 Start CVS Pump Room Unit Cooler Fan A VAS-MA-07A Start CVS Pump Room Unit Cooler Fan B VAS-MA-07B Start RNS Pump Room Unit Cooler Fan A VAS-MA-08A Start RNS Pump Room Unit Cooler Fan B VAS-MA-08B Start Air-cooled Chiller Water Valve VWS-PL-V210 Open Air-cooled Chiller Water Valve VW8-PL-V253 Open Attachment C Excerpt from COL Appendix C Table 2.7.2-1 Equipment Name Tag No. Display Air-cooled Chiller VWS-MS-02 Yes (Run Status)

Air-cooled Chiller VWS-MS-03 Yes (Run Status)

Air-cooled Chiller Pump VWS-MP-02 Yes (Run Status)

Air-cooled Chiller Pump VWS-MP-03 Yes (Run Status)

CVS Pump Room Unit Cooler Fan A VAS-MA-07A Yes (Run Status)

CVS Pump Room Unit Cooler Fan B VAS-MA-07B Yes (Run Status)

RNS Pump Room Unit Cooler Fan A VAS-MA-08A Yes (Run Status)

RNS Pump Room Unit Cooler Fan B VAS-MA-08B Yes (Run Status)

Air-cooled Chiller Water Valve VWS-PL-V210 Yes (Position Status)

Air-cooled Chiller Water Valve VWS-PL-V253 Yes (Position Status)