ND-18-0980, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.080 (Index Number 40): Difference between revisions

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{{#Wiki_filter:iVIictiael J. Yox             7825 River Road hk. Southern Nuclear                                Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 708-848-6459 tei 410-474-8587 cell JUL 3 0 20)8                                                                  myox@souttiernco.com Docket Nos.:   52-025 52-026 ND-18-0980 10CFR 52.99(c)(3)
{{#Wiki_filter:hk. Southern Nuclear JUL 3 0 20)8 iVIictiael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 708-848-6459 tei 410-474-8587 cell myox@souttiernco.com Docket Nos.:
52-025 52-026 ND-18-0980 10CFR 52.99(c)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.080 (Index Number 401 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 10, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.08e [Index Number 40]
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.080 (Index Number 401 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 10, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.08e [Index Number 40]
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.
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 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 performedor 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 priorto 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.
Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4
Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtie 3 &4


==Enclosure:==
==Enclosure:==
Line 43: Line 44:
Mr. 8. Roetger, Georgia Public Sen/ice Commission Ms. 8. W. Kernlzan, Georgia Public Sen/ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
Mr. 8. Roetger, Georgia Public Sen/ice Commission Ms. 8. W. Kernlzan, Georgia Public Sen/ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham


U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0980 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.08e [Index Number 40]
U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0980 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC2.1.02.08e [Index Number 40]


U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 2 of 3 ITAAC Statement Design Commitment:
U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 2 of 3 ITAAC Statement Design Commitment:
8.e) The RCS provides emergency letdown during design basis events.
8.e) The RCS provides emergency letdown during design basis events.
Inspections. Tests. Analvses:
Inspections. Tests. Analvses:
Inspections of the reactor vessel head vent valves and Inlet and outlet piping will be conducted.
Inspections ofthe reactor vessel head vent valves and Inlet and outlet piping will be conducted.
Acceptance Criteria:
Acceptance Criteria:
A report exists and concludes that the capacity of the reactor vessel head vent Is sufficient to pass not less than 9.0 Ibm/sec at 2500 psia In the RCS.
Areportexists and concludes that the capacityofthe reactor vessel head vent Issufficient to pass not less than 9.0 Ibm/sec at 2500 psia In the RCS.
ITAAC Completion Description The Reactor Coolant System (RCS) provides emergency letdown during design basis events.
ITAAC Completion Description The Reactor CoolantSystem (RCS) provides emergency letdown duringdesign basis events.
This ITAAC performs Inspections of the reactor vessel head vent valves and Inlet and outlet piping to verify that the capacity of the reactor vessel head vent Is sufficient to pass not less than 9.0 Ibm/sec at 2500 psIa In the RCS.
This ITAAC performs Inspections ofthe reactor vessel head vent valves and Inlet and outlet piping to verify thatthe capacity ofthe reactor vessel head vent Is sufficient to pass not less than 9.0 Ibm/sec at 2500 psIa Inthe RCS.
Aflow capacity of the Reactor Vessel (RV) head vent pipe routing Is restricted (choked) up to the orifice downstream of the RV head vent valves RCS-PL-V150C and -D. The flow resistance of the RV head vent valves and Inlet and outlet piping Is calculated with Darcy's formula using line routing Information (I.e., pipe length, pipe diameter, number and type of pipe fittings, entrance/exit losses and valves) (Reference 1). Following Installation, Inspections of construction records are performed to verify the line routing Information of the RV head vent Inlet and outlet piping Including valves up to the downstream orifice Is consistent with the Information In the flow capacitydesign calculation. The results are used to calculate the as-bullt flow capacity for each RV head vent flow path using the same methodology used In the flow capacity design calculation (References 2 and 3) and compared to the ITAAC acceptance criteria. The capacity ofthe RV head vent Is sufficient to pass x.x Ibm/sec at 2500 psIa In the RCS which Is not less than 9.0 Ibm/sec at 2500 psIa.
Aflow capacity ofthe Reactor Vessel (RV) head ventpiperouting Isrestricted (choked) upto the orifice downstream of the RV head vent valves RCS-PL-V150C and -D. The flow resistance of the RV head vent valves and Inletand outlet piping Is calculated with Darcy's formula using line routing Information (I.e., pipe length, pipe diameter, number and typeofpipe fittings, entrance/exit losses and valves) (Reference 1). Following Installation, Inspectionsof construction records are performedto verify the line routing Information of the RV head vent Inlet and outlet piping Including valves up to the downstream orifice Isconsistentwith the Information In the flow capacitydesigncalculation. The resultsare used to calculatethe as-bullt flow capacity for each RV head vent flow pathusing the same methodology used In the flow capacity designcalculation (References 2 and 3) and compared to the ITAAC acceptance criteria. Thecapacity ofthe RV head vent Is sufficient to pass x.x Ibm/sec at 2500 psIa In the RCS which Is not less than 9.0 Ibm/sec at 2500 psIa.
The results are documented Inthe Unit 3 and Unit 4 Principal Closure Document (Reference 2 and 3, respectively) and demonstrates the IT/\AC acceptance criteria Is met.
The results are documented Inthe Unit 3 and Unit 4 Principal Closure Document (Reference 2 and 3, respectively) and demonstrates the IT/\\AC acceptance criteriaIs met.
References 1 thru 3 are available for NRC Inspection as part of the Unit 3 and Unit 4 ITAAC 2.1.02.08e Completion Packages (Reference 4 and 5, respectively).
References 1 thru 3 are availablefor NRC Inspection as part of the Unit 3 and Unit 4 ITAAC 2.1.02.08e Completion Packages (Reference 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 findings pertaining to the subject IT/\AC and associated corrective actions. This review found there are no relevant IT/WC findings associated with this ITAAC.
List of ITAAC Findings In accordance with plantprocedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review ofall findings pertaining tothe subject IT/\\AC and associated corrective actions. This review found there are no relevant IT/WC findings associated with this ITAAC.


U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 3 of 3 References favailable for NRC inspection)
U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 3 of 3 References favailable for NRC inspection)
: 1. APP-RCS-M3C-067, Rev 4, "Orifice Functional Requirements for RGB Reactor Vessel Head Vent Flow Orifices (APP-RCS-PY-R01A/B)"
: 1. APP-RCS-M3C-067, Rev 4, "Orifice Functional Requirements for RGB Reactor Vessel Head Vent Flow Orifices (APP-RCS-PY-R01A/B)"
: 2. Principal Closure Document (Unit 3)
2.
: 3. Principal Closure Document (Unit 4)
Principal Closure Document (Unit3) 3.
: 4. 2.1.02.08e-U3-CP-Rev0, ITAAC Completion Package
Principal Closure Document (Unit 4) 4.
: 5. 2.1.02.08e-U4-CP-Rev0, ITAAC Completion Package
2.1.02.08e-U3-CP-Rev0, ITAAC Completion Package 5.
: 6. NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52"}}
2.1.02.08e-U4-CP-Rev0, ITAAC Completion Package 6.
NEI 08-01, "Industry Guideline forthe ITAAC Closure Process under 10 CFR Part 52"}}

Latest revision as of 16:07, 5 January 2025

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.080 (Index Number 40)
ML18211A636
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/30/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-18-0980
Download: ML18211A636 (6)
v • d • e


Text

hk. Southern Nuclear JUL 3 0 20)8 iVIictiael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 708-848-6459 tei 410-474-8587 cell myox@souttiernco.com Docket Nos.:

52-025 52-026 ND-18-0980 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.080 (Index Number 401 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 10, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.08e [Index Number 40]

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 performedor 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 priorto 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 Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.08e [Index Number 40]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0980 Page 2 of 3 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. Vox 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 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 Ms. A. E. Rivera-Varona Mr. M. E. Ernstes Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-0980 Page 3 of 3 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 Sen/ice Commission Ms. 8. W. Kernlzan, Georgia Public Sen/ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0980 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC2.1.02.08e [Index Number 40]

U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 2 of 3 ITAAC Statement Design Commitment:

8.e) The RCS provides emergency letdown during design basis events.

Inspections. Tests. Analvses:

Inspections ofthe reactor vessel head vent valves and Inlet and outlet piping will be conducted.

Acceptance Criteria:

Areportexists and concludes that the capacityofthe reactor vessel head vent Issufficient to pass not less than 9.0 Ibm/sec at 2500 psia In the RCS.

ITAAC Completion Description The Reactor CoolantSystem (RCS) provides emergency letdown duringdesign basis events.

This ITAAC performs Inspections ofthe reactor vessel head vent valves and Inlet and outlet piping to verify thatthe capacity ofthe reactor vessel head vent Is sufficient to pass not less than 9.0 Ibm/sec at 2500 psIa Inthe RCS.

Aflow capacity ofthe Reactor Vessel (RV) head ventpiperouting Isrestricted (choked) upto the orifice downstream of the RV head vent valves RCS-PL-V150C and -D. The flow resistance of the RV head vent valves and Inletand outlet piping Is calculated with Darcy's formula using line routing Information (I.e., pipe length, pipe diameter, number and typeofpipe fittings, entrance/exit losses and valves) (Reference 1). Following Installation, Inspectionsof construction records are performedto verify the line routing Information of the RV head vent Inlet and outlet piping Including valves up to the downstream orifice Isconsistentwith the Information In the flow capacitydesigncalculation. The resultsare used to calculatethe as-bullt flow capacity for each RV head vent flow pathusing the same methodology used In the flow capacity designcalculation (References 2 and 3) and compared to the ITAAC acceptance criteria. Thecapacity ofthe RV head vent Is sufficient to pass x.x Ibm/sec at 2500 psIa In the RCS which Is not less than 9.0 Ibm/sec at 2500 psIa.

The results are documented Inthe Unit 3 and Unit 4 Principal Closure Document (Reference 2 and 3, respectively) and demonstrates the IT/\\AC acceptance criteriaIs met.

References 1 thru 3 are availablefor NRC Inspection as part of the Unit 3 and Unit 4 ITAAC 2.1.02.08e Completion Packages (Reference 4 and 5, respectively).

List of ITAAC Findings In accordance with plantprocedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review ofall findings pertaining tothe subject IT/\\AC and associated corrective actions. This review found there are no relevant IT/WC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-18-0980 Enclosure Page 3 of 3 References favailable for NRC inspection)

1. APP-RCS-M3C-067, Rev 4, "Orifice Functional Requirements for RGB Reactor Vessel Head Vent Flow Orifices (APP-RCS-PY-R01A/B)"

2.

Principal Closure Document (Unit3) 3.

Principal Closure Document (Unit 4) 4.

2.1.02.08e-U3-CP-Rev0, ITAAC Completion Package 5.

2.1.02.08e-U4-CP-Rev0, ITAAC Completion Package 6.

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

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