ND-21-1095, Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.1 (Index Number 75)

Resubmittal of Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.06.1 (Index Number 75)

ML21355A357
Person / Time
Site:	Vogtle
Issue date:	12/21/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-1095
Download: ML21355A357 (14)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 A Southern Nuclear Vogtle 3 & 4 706-848-6459 tel DEC 2 1 2021 Docket Nos.: 52-025 52-026 ND-21-1095 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 Resubmittal of Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.03.06.1 [Index Number 751 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 20, 2021, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.03.06.1 [Index Number 75] has not been completed greater than 225-days prior to initial fuel load for Unit 4.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.1.03.06.1 [Index Number75] ND-19-1333

[ML19305A429] dated October 31, 2019. This resubmittal addresses changes made to ITAAC by Amendment 188 and Amendment 186 to the Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Combined Licenses and supersedes ND-19-1333 in its entirety.

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 Kelli Roberts at 706-848-6991.

U.S. Nuclear Regulatory Commission ND-21-1095 Page 2 of 4 Respectfully submitted, Michael J.

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.03.06.1 [Index Number 75]

MJY/BSZ/sfr

U.S. Nuclear Regulatory Commission ND-21-1095 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Regulatory Commission Ms. M. Bailey M . M. King M . G. Bowman Ms. A. Veil M . C. P. Patel M . G. J. Khouri M . C. J. Even M . B. J. Kemker Ms. N. C. Coovert M C. Welch M J. Gaslevic M O. Lopez-Santiago M G. Armstrong M M. Webb M T. Fredette M C. Santos M B. Davis M J. Vasquez M J. Eargle M T. Fanelli Ms. K. McCurry M J. Parent M B. Griman M V. Hall

U.S. Nuclear Regulatory Commission ND-21-1095 Page 4 of 4 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen 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 Mr. D. 0. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-21-1095 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.03.06.1 [Index Number 75]

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 2 of 10 ITAAC Statement Design Commitment:

6. The seismic Category I equipment identified in Table 2.1.3-1 can withstand seismic design basis loads without loss of safety function.

9.a) The Class 1E equipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

Inspections. Tests. Analvses:

i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.1.3-1 (except fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies) is located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type tests and analyses of seismic Category I equipment will be performed.

ill) Inspection will be performed for the existence of a report verifying that the equipment including anchorage is seismically bounded by the tested or analyzed conditions. This inspection must be performed on the as-built equipment except for the fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies.

i) Type tests, analysis, or a combination of type tests and analysis will be performed on Class 1E equipment located in a harsh environment.

ii) Inspection will be performed of the as-built Class IE equipment and the associated wiring, cables, and terminations located in a harsh environment.

Acceptance Criteria:

i) The seismic Category I equipment identified in Table 2.1.3-1 (except fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies) is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

iii) A report exists and concludes that the equipment including anchorage is seismically bounded by the tested or analyzed conditions.

i) A report exists and concludes that the Class 1E equipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 3 of 10

11) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.1.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Reactor System (RXS)components identified as seismic Category I or Class 1E in the Combined License(COL)Appendix C, Table 2.1.3-1 (the Table) are designed and constructed in accordance with applicable requirements.

i) The seismic Cateaorv I equipment identified in Table 2.1.3-1 (except fuel assemblies, rod cluster control assemblies, orav rod cluster assemblies, and incore instrument QuickLoc assemblies) is located on the Nuclear Island.

To assure that seismic Category I components can withstand seismic design basis loads without loss of safety function, all the components in the Table are designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EG)

Walkdown ITAAC Guideline and EG ITAAC As-built Installation Documentation Guideline (References 1 & 2), an inspection is conducted of the RXS to confirm the satisfactory installation of the seismically qualified components. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room).

Fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies are not installed in their final location until after the 10 CFR 52.103(g)finding has been made as part of initial fuel load. Per item ii below, the assemblies are seismically qualified when located on the nuclear island. Inspections of these assemblies are performed but not in the final installed location, since that is not allowed by 52.103(g). The EG As-Built Reconciliation Reports(EQRR)(Reference 7) identified in Attachment A document the results of the inspection and conclude that the seismic Category I components are located on the Nuclear Island except for the fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies.

ii) A report exists and concludes that the seismic Cateaorv I eouioment can withstand seismic design basis loads without loss of safetv function.

Seismic Category I components in the Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the passive seismic Category I mechanical equipment is demonstrated by analysis in accordance with American Society of Mechanical Engineers(ASME)Code Section III (Reference 8).

Safety-related (Class 1E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987(Reference 9). The specific qualification method (i.e.,

type testing, analysis, or combination) used for each component in the Table is identified in Attachment A. Additional information about the methods used to qualify API000 safety-related equipment is provided in the Updated Final Safety Analysis Report(UFSAR) Appendix 3D (Reference 10). The EG Reports (Reference 11) identified in Attachment A contain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 4 of 10 ill) A report exists and concludes that the equipment includina anchorage is seismicallv bounded by the tested or analyzed conditions.

To the extent that the installation prior to fuel load is possible, an inspection (References 1 & 2) is conducted to confirm the satisfactory installation of the seismically qualified components in the Table. The inspection yerifies the equipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and other interfaces.

For components not installed prior to fuel load, the inspection is accomplished by yerifying a quality assurance data package (Reference 6 (i.e. fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies)) exists that concludes that the equipment was constructed as per design.

The inspection conducted for each component in the table will consider the critical seismic attributes identified in the associated EQ Report for that component. The inspection will confirm that the equipment, including anchorage, is seismically bounded by the tested or analyzed conditions.

Attachment A identifies the EQRR (Reference 7) completed to yerify that the seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987(Reference 9) and NRG Regulatory Guide (RG) 1.100 (Reference 12).

i) A report exists and concludes that the Class 1E equipment identified in Table 2.1.3-1 as being qualified for a harsh enyironment can withstand the enyironmental conditions that would exist before, durino. and following a desian basis accident without loss of safety function for the time required to perform the safety function.

The harsh enyironment Class IE components in the Table are qualified by type testing and/or analyses. Class 1E electrical component type testing is performed in accordance with IEEE Standard 323-1974(Reference 13) and RG 1.89 (Reference 3)to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment A identifies the EQ program and specific qualification method for each safety-related mechanical or Class 1E electrical component located in a harsh enyironment. Additional information about the methods used to qualify API000 safety-related equipment is proyided in the UFSAR Appendix 3D (Reference 10). EQ Reports (Reference 11) identified in Attachment A contain applicable test reports and associated documentation and conclude that the equipment can withstand the enyironmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.1.3-1 as being qualified for a harsh enyironment are bounded by type tests, analyses, or a combination of tyoe tests and analyses.

An inspection is conducted to confirm the satisfactory installation of the harsh qualified as-built components in the Table. The inspection yerifies the equipment location, make/model/serial number, as-designed equipment mounting, wiring, cables, and terminations and confirms that the enyironmental conditions for the zone in which the component is mounted are bounded by the tested and/or analyzed conditions.

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 5 of 10 The EQRR (Reference 7) identified in Attachment A document this inspection and conclude that the harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974(Reference 13).

Together, these reports (References 7 and 11) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2.1.3-1 (except fuel assemblies, rod cluster control assemblies, gray rod cluster assemblies, and incore instrument QuickLoc assemblies) is located on the Nuclear Island;

• A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; A report exists and concludes that the equipment including anchorage is seismically bounded by the tested or analyzed conditions;

• A report exists and concludes that the Class 1E equipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and

• A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 2.1.3-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

References 7 and 11 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.1.03.06.1 Completion Packages(References 4 and 5, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company(SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Indexes 76, 77, 81, and 82,found no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission N D-21-1095 Enclosu re Page 6 of 10 References ^available for NRG inspection)

1. ND-RA-001-014,"EQ ITAAC As-built Waikdown Guideline", Version 3.1

2. ND-RA-001-016,"EQ ITAAC As-bulit installation Documentation Guideline", Version 1.0

3. Regulatory Guide 1.89, Rev 1,"Environmental Qualification of Certain Electric Equipment important to Safety for Nuclear Power Plants"

4. 2.1.03.06.i-U3-CP-Rev X, ITAAC Completion Package

5. 2.1.03.06.i-U4-CP-Rev X, ITAAC Completion Package

6. APP-XXX-VQQ-XXX, Rev. X,"Quality Assurance Data Package"

7. EQ Reconciliation Reports as identified in Attachment A for Units 3 and 4

8. American Society of Mechanical Engineers(ASME) Boiler and Pressure Vessel(B&PV)

Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda

9. IEEE Standard 344-1987,"IEEE Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations"

10. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D,"Methodology for Qualifying API000 Safety-Related Electrical and Mechanical Equipment"

11. Equipment Qualification Reports as identified in Attachment A

12. Regulatory Guide 1.100, Rev. 2,"Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

13. IEEE Standard 323-1974,"IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations"

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

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 7 of 10 Attachment A System: Reactor System (RXS)

Class 1E/ Envir Equipment Seismic Qual. For Envir. Qual Type of Tag No/ EQ Reports EQRR" Name^ Cat. 1 + Harsh Zone ^ Program Qual.

2 Envir.*

APP- 2.1.03.06.1-RV (Reactor RXS-MV-01 Yes N/A N/A Analysis MV01- U3/4-EQRR-Vessel)

ZOR-101 PCDXXX Reactor 2.1.03.06.1-Upper APP-MI01-RXS-MI-01 Yes - N/A N/A Analysis U3/4-EQRR-Internals S3R-002 PCDXXX Assembly Reactor 2.1.03.06.1-Lower APP-MI01-RXS-MI-02 Yes - N/A N/A Analysis U3/4-EQRR-Internals S3R-002 PCDXXX Assembly

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 8 of 10 Class 1E/ Envir Equipment Seismic Qual. For Envir. Quai Type of Tag No.^ EG Reports EQRR" Name'*' Cat. I ^ Harsh Zone Program Qual.

2 Envir.*

RXS-FA-A07/ AOS/ A09/ 605/ 806/ 607/ 608/

609/ 610/ 611/ 004/ 005/ 006/ 007/ 008/ 009/

010/ 011/ 012/ D03/ D04/ D05/ 006/ D07/ D08/

09/ D10/ D11/ 012/ D13/ E02/ E03/ E04/ E05/

E06/ E07/ E08/ E09/ E10/ El 1/ El 2/ El 3/ El 4/

F02/ F03/ F04/ F05/ F06/ F07/ F08/ F09/ F10/

F11/ F12/ F13/ F14/ G01/ G02/ G03/ G04/ G05/

ON-NRFE-Fuel G06/ G07/ G08/ G09/ G10/ G11/ G12/ G13/

10-21 2.1.03.06.i-Assemblies G14/ G15/ HOI/ H02/ H03/ H04/ H05/ H06/ H07/

Yes N/A N/A Analysis U3/4-EQRR-(157 H08/ H09/ H10/ Nil/ HI2/ HI3/ HI4/ H15/J01/

ON-NRFE- PODXXX locations) J02/ J03/ J04/ J05/ J06/ J07/ J08/ J09/ J10/ J11/

13-1 J12/ J13/ J14/ J15/ K02/ K03/ K04/ K05/ K06/

K07/ K08/ K09/ K10/ K11/ K12/ K13/ K14/ L02/

L03/ L04/ L05/ L06/ L07/ L08/ L09/ LI 0/ L11/

LI 2/ LI 3/ LI 4/ M03/ M04/ M05/ M06/ M07/ M08/

M09/ M10/ Ml 1/ Ml2/ Ml3/ N04/ N05/ N06/

N07/ N08/ N09/ N10/ N11/ N12/ P05/ P06/ P07/

P08/ P09/ P10/ P11/ R07/ R08/ R09 RXS-FR-606/ 610/ 005/ 007/ 009/ 011/ 006/

Rod Cluster 08/ I 0/ E03/ E05/ E07/ E09/ El 1/ El 3/ F02/

Control F04/ F12/ F14/ G03/ G05/ G07/ G09/ G11/ G13/ 2.1.03.06.i-Assemblies H04/ H08/ HI2/ J03/ J05/ J07/ J09/ J11/ J13/ Yes N/A N/A Analysis NRFE-14-1 U3/4-EQRR-(ROOAs)

K02/ K04/ K12/ K14/ L03/ L05/ L07/ L09/ L11/ PO^XXX (minimum 53 LI3/ M06/ M08/ M10/ N05/ N07/ N09/ Nil/ P06/

locations)

P10 Gray Rod Cluster 2.1.03.06.i-RXS-FG-608/ 004/ 012/ F06/ F08/ F10/ H02/

Assemblies Yes N/A N/A Analysis NRFE-14-1 U3/4-EQRR-H06/ H10/ H14/ K06/ K08/ K10/ M04/ M12/ P08 (GROAs) (16 POOXXX locations)

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 9 of 10 Class 1E/ Envir Equipment Seismic Quai. For Envir. Qua! Type of Tag No/ EQ Reports EQRR" Name^ Cat. I + Harsh Zone ^ Program Quai.

2 Envir.* ^

RXS-MV-11 BOG/ 11 BOB/ 11B10/ 11 COS/ 11C07/

11C09/ 11C11/ 11D04/ 11 DOG/ 11 DOB/ 11D10/

11D12/ 11E03/11E05/11E07/ 11E09/11E11/

11E13/ 11F02/ 11F04/11F0G/ 11F0B/ 11F10/

Control Rod 11F12/ 11F14/ 11G03/ 11G05/ 11G07/ 11G09/

Drive APP- 2.1.03.0G.i-11G11/11G13/11H02/11H04/11 HOG/11 HOB/

Mechanisms Yes No/No N/A N/A Analysis MV11- U3/4-EQRR-11H10/ 11H12/ 11H14/ 11J03/ 11 JOS/ 11J07/

(CRDMs)(69 S3R-002 PCDXXX 11J09/ 11J11/ 11J13/ 11K02/ 11K04/ 11KOG/

Locations) 11K0B/11K10/11K12/11K14/11L03/11L0S/

11L07/11L09/11L11/11L13/11M04/11M0G/

11M0B/11M10/11M12/11N0S/11N07/11N09/

11N11/11P0G/11P0B/11P10 incore instrument APP- 2.1.03.0G.i-QuickLoc RXS-MY-Y11 through Y1B Yes -

N/A N/A Analysis MV01- U3/4-EQRR-Assemblies S3R-002 PCDXXX (8 Locations)

Source Type APP-JE92-2.1.03.0G.i-Range Testing VBR-001 /

RXS-JE-NE001A/ NE001B/ NE001C/ NE001D Yes Yes/ Yes 1 E* U3/4-EQRR-

& APP-JE92-Detectors (4) PCDXXX Analysis VBR-002 intermediate Type APP-JE92-2.1.03.0G.i-Range RXS-JE-NE002A/ NE002B/ NE002C/ NE002D Testing VBR-001 /

Yes Yes/ Yes 1 E*S U3/4-EQRR-

& APP-JE92-Detectors (4) PCDXXX Analysis VBR-002 Power Range Type APP-JE92-2.1.03.0G.i-Detectors - RXS-JE-NE003A/ NE003B/ NE003C/ NE003D Testing VBR-001 /

Yes Yes/ Yes 1 E*S U3/4-EQRR-

& APP-JE92-Lower (4) PCDXXX Analysis VBR-002

U.S. Nuclear Regulatory Commission ND-21-1095 Enclosure Page 10 of 10 Class 1E/ Envir Equipment Seismic Qua!. For Envir. Qual Type of Tag No.+ EQ Reports EQRR" Name^ Cat. 1 + Harsh Zone ^ Program Qual.

Envir.+ 3 2 Power Range Type APP-JE92-2.1.03.06.1-Detectors - RXS-JE-NE004A/ NE004B/ NE004C/ NE004D Testing VBR-001 /

Yes Yes/ Yes 1 E*S U3/4-EQRR-

& APP-JE92-Upper (4) PCDXXX Analysis VBR-002 Notes:

^ Excerpt from COL Appendix C Table 2.1.3-1

1. See Table 3D.5-1 of UFSAR

2. E = Electrical Equipment Program (limit switch and the motor operator, squib operator, solenoid operator)

S = Qualified for submergence or operation with spray

• = Harsh Environment

3. Dash (-) Indicates not applicable

4. The Unit 3/4 EQRR are numbered "2.1.03.06.I-U3/4-EQRR-PCDXXX"