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Category:- No Document Type Applies
MONTHYEARML23165A2492023-06-14014 June 2023
4Q 2022 Performance Summary U4
ML22334A0832022-12-0101 December 2022
Attachment 1 - Targeted ITAAC Listing VEGP Unit 4
ML22334A0842022-12-0101 December 2022
Attachment 2 - ITAAC Family Listing VEGP Unit 4
ML21278A3552021-10-0505 October 2021
Enclosure 2: Safety Determination Input for IEEE 384 Separation Issues and Safety Determination Input for IEEE 384 Separation Issues within IDS Enclosures
ML21278A3562021-10-0505 October 2021
Enclosure 3: AP1000 Plant At-Power Internal Events PRA Risk Assessment for Spatial Separation Criteria Nonconformances
ML21277A0212021-10-0404 October 2021
2021 Q2 Cross Cutting Page
ML20358A1802020-12-23023 December 2020
(VEGP) Units 3 and 4 - Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) - Alternative Requirements for A8ME Section XI Examination Coverage of Weldolet Branch Connection Welds (VEGP 3&4-PSI/ISI-ALT-15)
ML20343A0432020-12-0808 December 2020
Construction Reactor Oversight Process Resources December 2020
ML20022A0602020-01-20020 January 2020
Assessment of Communications in Response Request for Information for Vogtle Electric Generating Plant Units 3 and 4
ML19325C6722019-11-21021 November 2019
Staff Bullets for October 21, 2019 Public Meeting, Vogtle Electric Generating Plant Units 3 and 4, LAR-19-017, Request for License Amendment: Removal of the PRHR-HX Natural Circulation Test
ML19233A0072019-08-22022 August 2019
NRC Contacts for New Power Reactors
ML19113A0922019-04-23023 April 2019
Functional Arrangement ITAAC Acceptance Criteria R1
ML17235B1482017-08-23023 August 2017
U.S. Nuclear Regulatory Commission - Tornado Missile Risk Evaluator (TMRE) Methodology Topics and Methodology Feedback
ML14141A6272014-05-20020 May 2014
LTR-14-0288-Ticket - Senator Edward J. Markey Ltr. Information About NRC-Sanctioned Job Shadow Program with China
ML14094A3582014-04-0808 April 2014
Enclosure - PWROG Peer Review Form 4-03-14, Table 1
ML14078A6212014-04-0101 April 2014
Enclosure 3 - RASCAL 4.3 Inputs for Site Boundary Dose Projections
ML14072A4542014-03-0606 March 2014
Response to NRC Request for Additional Information Site Plan, 2-1, Sheet 1 of 1
ML14072A4632014-03-0606 March 2014
Response to NRC Request for Additional Information 2-1, Sheet 3 of 10
ML12056A0522012-03-12012 March 2012
Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
ML1135406252012-02-10010 February 2012
Amendment to Indemnity Agreement No. B-107 - Amendment No. 6
ML12010A0342011-12-28028 December 2011
Onsite Ground/Surface Water Questionnaire, Onsite Radiological Effluent/Remp Monitoring Program
ML1122005052011-08-0404 August 2011
Crop Tabletop Example Findings
ML1132604282011-01-0303 January 2011
NRC 2011 Vogtle
ML1019301932010-06-0909 June 2010
Undated Onsite Ground/Surface Water Monitoring Questionnaire 4 for Vogtle
ML1019304602010-03-25025 March 2010
List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants
NL-08-0869, Enclosure 11, List of Regulatory Commitments2008-06-27027 June 2008
Enclosure 11, List of Regulatory Commitments
ML0811902022008-04-24024 April 2008
End of Cycle Public Meeting Attendee List
ML0808000362008-03-13013 March 2008
List of Attendees, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors
ML0806704192008-03-0707 March 2008
CDBI Findings
ML0732407642007-11-0505 November 2007
Vogtle - FSAR-2, Calculation Package
ML0732407472007-11-0505 November 2007
Electrical Design Parameters of Typical 230kv and 500kv Transmission Lines Terminating Into Plant Vogtle
ML0732407112007-11-0505 November 2007
Project Wings (Wildlife Incentives for Nongame and Game Species)
ML0732400242007-10-25025 October 2007
Examples of Max Thermal Power License Conditions
ML0726301142007-09-14014 September 2007
/ P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170
ML0732407042007-06-27027 June 2007
Cooperative Safe Harbor Management Agreement (2005 Updated Version) No. 28 for Red-Cockaded Woodpeckers (Picoides Borealis) and Their Habitat on Private Land in Georgia
ML0714103852007-05-17017 May 2007
Enclosure 1 - Attendee List for 05/17/2007 Vogtle Public Meeting
ML0713402122007-05-10010 May 2007
Log of Congressional Correspondence for January 16, 2007 - February 28, 2007
ML0634705992006-12-14014 December 2006
Plant Service List
ML0619203352006-04-14014 April 2006
Attachment 3 - List of Attendees for April 14, 2006 Public Meeting to Discuss Vogtle Early Site Permit Seismic Activities
ML0609006412005-10-11011 October 2005
Spent Fuel Pool Action Plan, from Entergy
ML0732407432005-08-22022 August 2005
Submittal of Photocopies of the Highway Capacity Manual 2000
ML0732407362005-02-21021 February 2005
Safe Drinking Water Information System
ML0404104922004-02-20020 February 2004
Order EA-03-009 Service List
ML0732407172003-07-24024 July 2003
Movement and Population Size of American Shad Near a Low-Head Lock and Dam
ML0732407292000-01-31031 January 2000
Habitat Utilization and Biological Characteristics of Adult Atlantic Sturgeon in Two South Carolina Rivers
ML0732407661999-07-31031 July 1999
Savannah River Basin Comprehensive Reconnaissance Study
ML0732407411999-06-0606 June 1999
State of Georgia, Permit No. GA0026786, Authorization to Discharge Under the National Pollutant Discharge Elimination System
ML0732406901998-04-0101 April 1998
State of Georgia, Permit to Operate a Public Water System Issued on 04/01/1998 to Vogtle Plant
ML0732407461997-05-0808 May 1997
Georgia Power Transmission Bulletin, Maintenance of Plant Vogtle Transmission Line Corridors
ML0630002251997-05-0808 May 1997
Georgia Power Transmission Bulletin No. 6-10: Maintenance of Plant Vogtle Transmission Line Corridors. Revised
2023-06-14
[Table view] |
Text
April 23, 2019 Proposed Acceptance Criteria for SNCs Draft License Amendment Request (LAR) on Functional Arrangement ITAAC Acceptance Criteria:
For acceptance of a License Amendment Request (LAR) requesting deletion of specific Functional Arrangement ITAAC, the NRC staff considers that the licensee should provide the following information:
- 1. The LAR should (a) describe what the Functional Arrangement ITAAC verifies (including the method of verification), (b) describe the extent to which the remaining ITAAC duplicate the Functional Arrangement ITAAC verifications, and (c) to the extent that the Functional Arrangement ITAAC verifications are not duplicated by the remaining ITAAC, explain why it is acceptable for these matters not to be verified by ITAAC.
- 2. In describing what the Functional Arrangement ITAAC verify (including the method of verification), the LAR should be consistent with NRC-approved Uncompleted ITAAC Notifications (UINs) and the following discussion from Section 10.5 of NEI 08-01,1 or the LAR should provide justification for an alternative approach:
The purpose of the system Functional Arrangement ITAAC, and the associated ITAAC Closure Notification, is to verify and document that the as-built system components conform to the Tier 1 Design Description, that is, (1) that components are physically arranged as shown in any referenced figure, and located as identified in any referenced table; and (2) that system components identified in the Tier 1 Design Descriptions are physically arranged as specified by the design. The capability to perform required system safety functions described in the Tier 1 Design Description is verified by other ITAAC, which are the subject of separate ITAAC Closure Notifications. It is expected that licensees will use detailed construction drawings during walkdown inspections to verify the functional arrangement of specified as-built components. These inspections may be performed any time after construction is completed to the extent that all Tier 1 components within the scope of the ITAAC are installed.
In particular, the LAR should address the physical arrangement of all system components identified in the Tier 1 design description to provide the service for which the system is intended, as described in the system design description.
- 3. For the most safety significant systems, for example, the Reactor Coolant System (RCS),
Containment System (CNS), Passive Containment Cooling System (PCS), and Passive Core Cooling System (PXS), the LAR should describe how the remaining ITAAC will include a walkdown to verify the following functional arrangement attributes:
1 The NRC staff accepted Nuclear Energy Institute (NEI) Report 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, to provide a generic streamlined process for completion of ITAAC.
1
- a. Appropriate component tag numbers to ensure that the functional arrangement of the system is correct.
- b. Components and piping located in the flow path consistent with the construction drawing.
- c. Component installation consistent with the construction drawing (including orientation, type, and mounting).
- d. Piping installation consistent with construction drawing (including ASME class, size, slope, and supports).
- e. No significant adverse arrangement of components or piping that could impact function.
- f. Verification of adequate access for inservice inspection (ISI) and inservice testing (IST) activities, and confirmation that interferences are avoided.
2
