ND-18-1542, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.11c.i (Index Number 212): Difference between revisions

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{{#Wiki_filter:^ Southern Nuclear                                     Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4                706-848-6459 tel 410-474-8587 cell myox@southernco.conn DEC 1 9 2018 Docket Nos.:    52-025 52-026 ND-18-1542 10CFR 52.99(c)(3)
{{#Wiki_filter:^
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 2.2.03.11c.i [Index Number 2121 Ladies and Gentlemen:
Southern Nuclear DEC 1 9 2018 Docket Nos.:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 17, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.Ilc.i
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.conn ND-18-1542 10CFR 52.99(c)(3)
[Index Number 212] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.03.1 Ic.i[Index Number 212]. 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.
Southern Nuclear Operating Company Vogtle ElectricGenerating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.11c.i [Index Number 2121 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 17, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analyses, andAcceptance Criteria (ITAAC) Item 2.2.03.Ilc.i
[Index Number 212] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.03.1 Ic.i[Index Number 212]. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days priorto initial fuel load.
Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.03.1 Ic.i [Index Number 212] ND-17-1127
Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.03.1 Ic.i [Index Number 212] ND-17-1127
[ML17186A038] dated June 30, 2017. This resubmittal supersedes ND-17-1127 in its entirety.
[ML17186A038] dated June 30, 2017. This resubmittal supersedes ND-17-1127 in its entirety.
This notification is informed bythe 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, oranalyses have not been performed orhave been only partially completed.
This notification is informed bythe 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, oranalyses have not been performed orhave 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).
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 thatall acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).
This letter contains no new NRC regulatory commitments.
This letter contains no new NRC regulatory commitments.
If there are any questions, please contact Tom Petrak at 706-848-1575.
If there are any questions, please contact Tom Petrak at 706-848-1575.
Respectfullysubmitted Michael J.
Respectfullysubmitted Michael J.
Regulatory Affairs Director Vogtle 3 & 4
Regulatory Affairs Director Vogtle 3 &4


U.S. Nuclear Regulatory Commission ND-18-1542 Page 2 of 4
U.S. Nuclear Regulatory Commission ND-18-1542 Page 2 of 4


==Enclosure:==
==Enclosure:==
Vogtle ElectricGenerating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.11c.i [Index Number 212]
Vogtle ElectricGenerating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.11c.i[Index Number212]
MJY/DLW/sfr
MJY/DLW/sfr


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U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1542 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.1Ic.l [Index Number 212]
U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1542 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.1Ic.l [Index Number 212]


U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 11 .c) The valves identified in Table 2.2.3-1 as having DAS control perform their active function after receiving a signal from the DAS.
U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 11.c)The valves identified inTable 2.2.3-1 as having DAS control perform theiractivefunction after receiving a signal from the DAS.
Insoections/Tests/Analvses i) Testing will be performed on the squib valves identified inTable 2.2.3-1 using real or simulated signals into the DAS without stroking the valve.
Insoections/Tests/Analvses i) Testing will be performed on the squibvalvesidentified inTable2.2.3-1 using realor simulated signals intothe DASwithout stroking the valve.
Acceotance Criteria i) Squib valves receive an electrical signal at the valve electrical leadsthat is capable of actuating the valve after a signal is input to the DAS.
Acceotance Criteria i) Squib valves receive an electrical signal at thevalve electrical leadsthatiscapable of actuating the valve after a signal is inputto the DAS.
ITAAC ComDietion Description Multiple ITAAC are performed toverify that the valves identified in Combined License (COL)
ITAAC ComDietion Description Multiple ITAAC are performed toverify that thevalves identified in Combined License (COL)
Appendix C Table 2.2.3-1 (Attachment A) as having Diverse Actuation System (DAS) control perform an active function after receiving a signal from DAS. The subject ITAAC performs testing on the squib valves listed in Attachment A.
Appendix CTable 2.2.3-1 (Attachment A) as having Diverse Actuation System (DAS) control perform an active function after receiving a signal from DAS. The subject ITAAC performs testing on the squib valves listed inAttachmentA.
Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-DAS-ITPP-501 and 4-DAS-ITPP-501 (References 1 and 2) to verify that the valves identified in Attachment Aas having DAS control perform an active function after receiving a signal from DAS. Testing is performed on the squib valves using real signals into the DAS without stroking the valve and ensuring the squib valves receive an electrical signal at the valve electrical leads that is capable of actuating the valve.
Testing isperformed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-DAS-ITPP-501 and 4-DAS-ITPP-501 (References 1 and 2) to verify that the valves identified in Attachment Aas having DAS control perform an active function after receiving a signal from DAS. Testing isperformed onthesquib valves using real signals into the DAS without stroking the valve andensuring thesquib valves receive an electrical signal at the valve electrical leads that is capable of actuating the valve.
The squib valves are armed using the manual controls on the DAS panel and then actuated with the DAS actuation controls. During testing each squib valve identified in Attachment Ahas the squib valve igniters replaced with test resistor fixtures. Test resistance is corrected to the maximum resistance expected during accident conditions. A multimeter along with a Data Acquisition (DAQ) system is used to measure both firing current and voltage.
The squib valves arearmed using the manual controls on the DAS panel and then actuated with the DAS actuation controls. During testing each squib valve identified in Attachment Ahas the squib valve igniters replaced with test resistor fixtures. Testresistance iscorrected tothe maximum resistanceexpectedduring accident conditions. Amultimeter along with a Data Acquisition (DAQ) system is usedto measure both firing current and voltage.
Circuit resistance is measured and inside and outside containment temperatures are measured at multiple locations andare used to calculate the circuit resistance expected during accident conditions and at the minimum ambient temperature. The calculated circuit resistances are verified to meet the minimum and maximum allowable resistances.
Circuit resistance is measured and inside and outside containment temperatures are measured at multiple locations andare used tocalculate thecircuit resistance expected during accident conditions and at the minimumambient temperature. The calculated circuitresistances are verified to meet the minimum and maximum allowable resistances.
The minimum signal necessary to actuate the squib valves is specified in valve design information as at least 3.7 amperes for 10 milliseconds. The information recorded during testing of voltage and firing current is utilized to confirm that a sufficient test signal is received at each of the squib valves.
The minimum signal necessary to actuate the squib valves is specified in valve design information as at least3.7 amperes for 10 milliseconds. The information recorded during testing of voltage and firing current isutilized toconfirm that a sufficient testsignal is received at each of the squib valves.
The completed test results (References 1 and 2), confirm that each squib valve, identified in the Attachment A, receives an electrical signal at the valve electrical leads that is capable of actuating the squib valve after a signal is input to the DAS.
The completed test results (References 1and 2), confirm that each squib valve, identified in the Attachment A, receives an electrical signal at the valve electrical leadsthatiscapable of actuatingthe squib valve after a signal is input to the DAS.


U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 3 of 4 References 1 and 2 are available for NRG inspection as part of the Unit 3 and Unit 4ITAAC Completion Packages (Reference 3 and 4, respectively).
U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 3 of 4 References 1 and 2 are available for NRG inspection as part of the Unit3 and Unit4ITAAC Completion Packages (Reference 3 and 4, respectively).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertainingto the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings associated with this ITAAC.
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performeda review of allfindings pertainingto the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings associated with this ITAAC.
References favailable for NRG inspection)
References favailable for NRG inspection)
: 1. 3-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure"
: 1. 3-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure" 2.
: 2. 4-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure"
4-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure" 3.
: 3. 2.2.03.11 c.i-U3-CP-Rev 0, ITAAC Completion Package
2.2.03.11 c.i-U3-CP-Rev 0, ITAAC Completion Package 4.
: 4. 2.2.03.11 c.i-U4-CP-Rev 0, ITAAC Completion Package
2.2.03.11 c.i-U4-CP-Rev 0, ITAAC Completion Package 5.
: 5. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"


U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 4 of 4 Attachment A Excerpt from COL Appendix 0 Table 2.2.3-1 Equipment Name                     Tag No.               Control RMS/ DAS Containment Recirculation A PXS-PL-V118A                   YesA'es Squib Valve Containment Recirculation B PXS-PL-V118B                   YesA'es Squib Valve Containment Recirculation A PXS-PL-V120A                   YesA'es Squib Valve Containment Recirculation B PXS-PL-V120B                   YesA'es Squib Valve IRWST Injection A Squib           PXS-PL-V123A                   Yes/Yes Valve IRWST Injection B Squib           PXS-PL-V123B                   YesA^es Valve IRWST Injection A Squib           PXS-PL-V125A                   YesAes Vaive IRWST Injection B Squib           PXS-PL-V125B                   YesAes Valve}}
U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 4 of 4 Attachment A Excerpt from COL Appendix 0 Table 2.2.3-1 Equipment Name Tag No.
Control RMS/ DAS Containment Recirculation A Squib Valve PXS-PL-V118A YesA'es Containment Recirculation B Squib Valve PXS-PL-V118B YesA'es Containment Recirculation A Squib Valve PXS-PL-V120A YesA'es Containment Recirculation B Squib Valve PXS-PL-V120B YesA'es IRWST Injection A Squib Valve PXS-PL-V123A Yes/Yes IRWST Injection B Squib Valve PXS-PL-V123B YesA^es IRWST Injection A Squib Vaive PXS-PL-V125A YesAes IRWST Injection B Squib Valve PXS-PL-V125B YesAes}}

Latest revision as of 07:42, 5 January 2025

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.11c.i (Index Number 212)
ML18353B211
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 12/19/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.11c.i, ND-18-1542
Download: ML18353B211 (8)
v • d • e


Text

^

Southern Nuclear DEC 1 9 2018 Docket Nos.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.conn ND-18-1542 10CFR 52.99(c)(3)

Southern Nuclear Operating Company Vogtle ElectricGenerating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.11c.i [Index Number 2121 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 17, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspection, Test, Analyses, andAcceptance Criteria (ITAAC) Item 2.2.03.Ilc.i

[Index Number 212] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.03.1 Ic.i[Index Number 212]. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days priorto initial fuel load.

Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.03.1 Ic.i [Index Number 212] ND-17-1127

[ML17186A038] dated June 30, 2017. This resubmittal supersedes ND-17-1127 in its entirety.

This notification is informed bythe 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, oranalyses have not been performed orhave 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 thatall 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.

Respectfullysubmitted Michael J.

Regulatory Affairs Director Vogtle 3 &4

U.S. Nuclear Regulatory Commission ND-18-1542 Page 2 of 4

Enclosure:

Vogtle ElectricGenerating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.11c.i[Index Number212]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-18-1542 Page 3 of 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. A. L. Pugh 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-1542 Page 4 of 4 Daiton Utilities Mr. T. Bundros WECTEC Mr. 0. A. Castell Westinqhouse 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., CDS 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-18-1542 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1542 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.1Ic.l [Index Number 212]

U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 11.c)The valves identified inTable 2.2.3-1 as having DAS control perform theiractivefunction after receiving a signal from the DAS.

Insoections/Tests/Analvses i) Testing will be performed on the squibvalvesidentified inTable2.2.3-1 using realor simulated signals intothe DASwithout stroking the valve.

Acceotance Criteria i) Squib valves receive an electrical signal at thevalve electrical leadsthatiscapable of actuating the valve after a signal is inputto the DAS.

ITAAC ComDietion Description Multiple ITAAC are performed toverify that thevalves identified in Combined License (COL)

Appendix CTable 2.2.3-1 (Attachment A) as having Diverse Actuation System (DAS) control perform an active function after receiving a signal from DAS. The subject ITAAC performs testing on the squib valves listed inAttachmentA.

Testing isperformed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-DAS-ITPP-501 and 4-DAS-ITPP-501 (References 1 and 2) to verify that the valves identified in Attachment Aas having DAS control perform an active function after receiving a signal from DAS. Testing isperformed onthesquib valves using real signals into the DAS without stroking the valve andensuring thesquib valves receive an electrical signal at the valve electrical leads that is capable of actuating the valve.

The squib valves arearmed using the manual controls on the DAS panel and then actuated with the DAS actuation controls. During testing each squib valve identified in Attachment Ahas the squib valve igniters replaced with test resistor fixtures. Testresistance iscorrected tothe maximum resistanceexpectedduring accident conditions. Amultimeter along with a Data Acquisition (DAQ) system is usedto measure both firing current and voltage.

Circuit resistance is measured and inside and outside containment temperatures are measured at multiple locations andare used tocalculate thecircuit resistance expected during accident conditions and at the minimumambient temperature. The calculated circuitresistances are verified to meet the minimum and maximum allowable resistances.

The minimum signal necessary to actuate the squib valves is specified in valve design information as at least3.7 amperes for 10 milliseconds. The information recorded during testing of voltage and firing current isutilized toconfirm that a sufficient testsignal is received at each of the squib valves.

The completed test results (References 1and 2), confirm that each squib valve, identified in the Attachment A, receives an electrical signal at the valve electrical leadsthatiscapable of actuatingthe squib valve after a signal is input to the DAS.

U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 3 of 4 References 1 and 2 are available for NRG inspection as part of the Unit3 and Unit4ITAAC Completion Packages (Reference 3 and 4, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performeda review of allfindings pertainingto the subject ITAAC and associated corrective actions. This review found there are no relevant ITAACfindings associated with this ITAAC.

References favailable for NRG inspection)

1. 3-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure" 2.

4-DAS-ITPP-501, "Diverse Actuation System Preoperational Test Procedure" 3.

2.2.03.11 c.i-U3-CP-Rev 0, ITAAC Completion Package 4.

2.2.03.11 c.i-U4-CP-Rev 0, ITAAC Completion Package 5.

NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-1542 Enclosure Page 4 of 4 Attachment A Excerpt from COL Appendix 0 Table 2.2.3-1 Equipment Name Tag No.

Control RMS/ DAS Containment Recirculation A Squib Valve PXS-PL-V118A YesA'es Containment Recirculation B Squib Valve PXS-PL-V118B YesA'es Containment Recirculation A Squib Valve PXS-PL-V120A YesA'es Containment Recirculation B Squib Valve PXS-PL-V120B YesA'es IRWST Injection A Squib Valve PXS-PL-V123A Yes/Yes IRWST Injection B Squib Valve PXS-PL-V123B YesA^es IRWST Injection A Squib Vaive PXS-PL-V125A YesAes IRWST Injection B Squib Valve PXS-PL-V125B YesAes

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