ND-19-0949, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.03.041 (Index Number 609)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.03.041 (Index Number 609)

ML19234A217
Person / Time
Site:	Vogtle
Issue date:	08/22/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0949
Download: ML19234A217 (10)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 Southern Nuclear 706-848-6459 tel AllG 2 2 2019 Docket Nos.: 52-025 52-026 ND-19-0949 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 2.6.03.041 [Index Number 6091 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 21, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) 2.6.03.041 [Index Number 609] 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. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.6.03.041 [Index Number 609]

MJY/KM/sfr

U.S. Nuclear Regulatory Commission ND-19-0949 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (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. G. Chick 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 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 Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber OalethorDe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0949 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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 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 Sen/Ice Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-19-0949 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.6.03.041 [Index Number 609]

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 2 of 7 ITAAC Statement Desion Commitment:

4.i) The IDS supplies an operating voltage at the terminals of the Class 1E motor operated valves identified in subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3, 2.2.4, 2.3.2, 2.3.6, and 2.7.1 that is greater than or equal to the minimum design voltage.

Inspection. Tests. Analvses:

Testing will be performed by measuring the voltage during motor starting at both the IDS battery and motor-operated valve motor terminals while each motor-operated valve is stroked. Analyses will be performed to verify that the voltage at the motor-operated valve motor terminals is greater than or equal to the minimum design voltage of each motor-operated valve with an IDS battery terminal voltage of 210 Vdc.

Acceptance Criteria:

A report exists and concludes that IDS can provide a voltage greater than or equal to each valve's minimum design voltage to the motor terminals of each motor-operated valve when power is supplied under design conditions from IDS batteries with battery terminal voltage at 210 Vdc while each motor-operated valve is stroked.

ITAAC Completion Description Testing is performed by measuring the voltage during motor starting at both the Class 1E do and uninterruptible power supply system (IDS) battery and motor-operated valve(MOV) motor terminals while each MOV is stroked. Analyses are performed to verify that the voltage at the MOV motor terminals is greater than or equal to the minimum design voltage of each MOV with an IDS battery terminal voltage of 210 Vdc.

Analyses are performed in accordance with SV3-IDS-E0C-004 and SV4-IDS-E0C-004 (References 1 and 2)to determine the voltage drop on each power circuit at a battery voltage of 210 Vdc and the resulting voltage at the MOV terminals during normal operating conditions, and accident conditions. References 1 and 2 are the basis of analyses performed in accordance with SV3-1DS-E0C-018 and SV4-IDS-E0C-018(References 3 and 4). The analyses determine the expected voltage at the MOV terminals and define the method for the determination of the minimum acceptance voltage for each MOV during preoperational testing.

Each MOV identified in COL Appendix C subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3, 2.2.4, 2.3.2, 2.3.6, and 2.7.1 (Attachment A)is stroked individually in accordance with References 5 and 6.

The voltage at the battery disconnect switch and at the MOV terminals is recorded during MOV operation using installed maintenance and test equipment. The recorded voltage at the MOV terminals is analyzed in accordance with the method described in References 3 and 4, to compare proportional values when the tested battery voltage is higher or lower than the nominal voltage assumed in the analyses of References 3 and 4, to determine the minimum acceptance voltage for each MOV. A resulting proportional voltage that is greater than or equal to the minimum design voltage of each MOV confirms the tested voltage is bounded by the analyses in References 3 and 4.

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 3 of 7 The analyses and preoperational test results(References 1 through 6)confirm that IDS can provide a voltage greater than or equal to each MOV's minimum design voltage to the terminals of each MOV,as specified in reference 3and 4, when power is supplied under design conditions from IDS batteries with battery terminal voltage at 210 Vdc while each MOV is stroked.

References 1 through 6 are available for NRG inspection as part of Unit 3 and Unit 4ITAAC Completion Packages(Reference 7 and 8).

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(available for NRG inspection)

1. SV3-IDS-E0C-004,"IDS Power Cable Sizing and Voltage Drop Analysis"

2. SV4-IDS-E0C-004,"IDS Power Cable Sizing and Voltage Drop Analysis"

3. SV3-IDS-E0C-018,"MOV Acceptance Voltage During Safety Related DC MOV Testing"

4. SV4-IDS-E0C-018,"MOV Acceptance Voltage During Safety Related DC MOV Testing"

5. 3-IDS-ITPP-503,"Class 1E DC and UPS System MOV Voltage Tesf

6. 4-IDS-ITPP-503,"Class 1E DC and UPS System MOV Voltage Tesf

7. 2.6.03.04i-U3-CP-Rev0, ITAAC Completion Package

8. 2.6.03.04i-U4-CP-Rev0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 4 of 7 Attachment A*

Table 2.1.2-1 Equipment Name Tag No.

First-stage ADS Motor-operated Valve(MOV) RCS-PL-V001A First-stage ADS MOV RCS-PL-V001B Second-stage ADS MOV RCS-PL-V002A Second-stage ADS MOV RCS-PL-V002B Third-stage ADS MOV RCS-PL-V003A Third-stage ADS MOV RCS-PL-V003B First-stage ADS Isolation MOV RCS-PL-V011A First-stage ADS Isolation MOV RCS-PL-V011B Second-stage ADS Isolation MOV RCS-PL-V012A Second-stage ADS Isolation MOV RCS-PL-V012B Third-stage ADS Isolation MOV RCS-PL-V013A Third-stage ADS Isolation MOV RCS-PL-V013B Fourth-stage ADS MOV RCS-PL-V014A Fourth-stage ADS MOV RCS-PL-V014B Fourth-stage ADS MOV RCS-PL-V014C Fourth-stage ADS MOV RCS-PL-V014D Table 2.2.1-1 Equipment Name Tag No.

Component Cooling Water System (CCS) CCS-PL-V200 Containment Isolation Motor-operated Valve (MOV)- Inlet Line Outside Reactor Containment(ORC)

CCS Containment Isolation MOV - Outlet CCS-PL-V207 Line IRC CCS Containment Isolation MOV - Outlet CCS-PL-V208 Line ORC" SFS Discharge Line Containment Isolation SFS-PL-V038 MOV - ORC SFS Suction Line Containment Isolation MOV SFS-PL-V034

-IRC SFS Suction Line Containment Isolation MOV SFS-PL-V035

-ORC Vacuum Relief Containment Isolation A MOV VFS-PL-V800A

-ORC Vacuum Relief Containment Isolation B MOV VFS-PL-V800B

-ORC Excerpt from COL Tables 2.1.2-1 and 2.2.1-1, pages C-48, C-88

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 5 of 7 Attachment A (Cent.)*

Table 2.2.2-1 Equipment Name Tag No.

PCCWST Isolation Valve MOV PCS-PL-V001C PCCWST Isolation Block MOV PCS-PL-V002A PCCWST Isolation Block MOV PCS-PL-V002B PCCWST Isolation Block MOV PCS-PL-V002C Table 2.2.3-1 Equipment Name Tag No.

CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B PRHR HX Inlet Isolation Motor-operated PXS-PL-V101 Valve Containment Recirculation A isolation Motor- PXS-PL-V117A operated Valve Containment Recirculation B Isolation Motor- PXS-PL-V117B operated Vaive Table 2.2.4-1 Equipment Name Tag No.

Power-operated Relief Valve Block Motor- SGS-PL-V027A operated Valve Steam Generator 01 Power-operated Relief Valve Block Motor- SGS-PL-V027B operated Valve Steam Generator 02 Startup Feedwater Isolation Motor-operated SGS-PL-V067A Valve Startup Feedwater Isolation Motor-operated SGS-PL-V067B Valve Excerpt from COL Tables 2.2.2-1, 2.2.3-1, 2.2.4-1, pages C-111 b. C-117, C-147

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 6 of 7 Attachment A (Cont.)*

Table 2.3.2-1 Equipment Name Tag No.

RCS Purification Motor-operated Isolation CVS-PL-V001 Valve RCS Purification Motor-operated Isolation CVS-PL-V002 Valve RCS Purification Motor-operated Isolation CVS-PL-V003 Valve CVS Makeup Line Containment Isolation CVS-PL-V090 Motor-operated Valve CVS Makeup Line Containment Isolation CVS-PL-V091 Motor-operated Valve Table 2.3.6-1 Equipment Name Tag No.

RCS Inner Hot Leg Suction Motor-operated RNS-PL-V001A Isolation Valve RCS Inner Hot Leg Suction Motor-operated RNS-PL-V001B Isolation Valve RCS Outer Hot Leg Suction Motor-operated RNS-PL-V002A Isolation Valve RCS Outer Hot Leg Suction Motor-operated RNS-PL-V002B Isolation Valve RNS Discharge Motor-operated Containment RNS-PL-V011 Isolation Valve RNS Suction Header Motor-operated RNS-PL-V022 Containment Isolation Valve RNS Suction from IRWST Motor-operated RNS-PL-V023 Isolation Valve RNS Discharge to IRWST Motor-operated RNS-PL-V024 Isolation Valve RNS Suction from Cask Loading Pit Motor- RNS-PL-V055 operated Isolation Valve Excerpt from COL Tables 2.3.2-1 and 2.3.6-1, pages C-188, C-216

U.S. Nuclear Regulatory Commission ND-19-0949 Enclosure Page 7 of 7 Attachment A(Cent.)*

Table 2.7.1-1 Equipment Name Tag No.

All valves Identified in COL table 2.7.1-1 are N/A air operated valves.

Excerpt from COL Table 2.7.1-1, C-369