Letter Sequence Other |
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TAC:MF4560, TSTF-2, TSTF-234, TSTF-45, TSTF-46, TSTF-27, TSTF-28, TSTF-87, TSTF-95, TSTF-24, AFW Train Operable When in Service, Administratively Control Containment Penetrations, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B, Add Note to LCO 3.9.5 Allowing Shutdown Cooling Loops Removal from Operation, Increase the Completion Time When the Core Reactivity Balance is Not within Limit, Allow 7 Day Completion Time for a TURBINE-DRIVEN AFW Pump Inoperable, SFDP Clarifications, Add Met Vs. Perform to Specification 1.4, Frequency, Determination of Cumulative and Projected Dose Contributions in Recp, Containment Structural Integrity, Delete SR Frequencies Based on Inoperable Alarms, Provide Separate Condition Entry for Each PORV and Block Valve, Revise Shutdown Margin Definition for Stuck Rod Exception, Eliminate the Remote Shutdown System Table of Instrumentation and Controls, Refueling Boron Concentration Clarification, Require Static and Transient Fq Measurement (Approved, Closed) TAC:MF4561, TSTF-2, TSTF-234, TSTF-45, TSTF-46, TSTF-27, TSTF-28, TSTF-87, TSTF-95, TSTF-24, AFW Train Operable When in Service, Administratively Control Containment Penetrations, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B, Add Note to LCO 3.9.5 Allowing Shutdown Cooling Loops Removal from Operation, Increase the Completion Time When the Core Reactivity Balance is Not within Limit, Allow 7 Day Completion Time for a TURBINE-DRIVEN AFW Pump Inoperable, SFDP Clarifications, Add Met Vs. Perform to Specification 1.4, Frequency, Determination of Cumulative and Projected Dose Contributions in Recp, Containment Structural Integrity, Delete SR Frequencies Based on Inoperable Alarms, Provide Separate Condition Entry for Each PORV and Block Valve, Revise Shutdown Margin Definition for Stuck Rod Exception, Eliminate the Remote Shutdown System Table of Instrumentation and Controls, Refueling Boron Concentration Clarification, Require Static and Transient Fq Measurement (Approved, Closed) TAC:MF5317, Administratively Control Containment Penetrations, Add Note to LCO 3.9.5 Allowing Shutdown Cooling Loops Removal from Operation, Modify Section 3.8 Mode Restriction Notes, Reduce Plant Trips Due to Spurious Signals to the Nis During Physics Testing, Add Met Vs. Perform to Specification 1.4, Frequency, Determination of Cumulative and Projected Dose Contributions in Recp, Containment Structural Integrity, Provide Separate Condition Entry for Each PORV and Block Valve, Nis Power Range Channel Daily SR TS Change to Address LOW Power Decalibration (Withdrawn, Closed) TAC:MF5318, Administratively Control Containment Penetrations, Add Note to LCO 3.9.5 Allowing Shutdown Cooling Loops Removal from Operation, Modify Section 3.8 Mode Restriction Notes, Reduce Plant Trips Due to Spurious Signals to the Nis During Physics Testing, Add Met Vs. Perform to Specification 1.4, Frequency, Determination of Cumulative and Projected Dose Contributions in Recp, Containment Structural Integrity, Provide Separate Condition Entry for Each PORV and Block Valve, Nis Power Range Channel Daily SR TS Change to Address LOW Power Decalibration (Withdrawn, Closed) |
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MONTHYEARML14335A6232014-11-24024 November 2014
Units 1 and 2 - Request for Technical Specification Amendment Adoption of Previously NRC-Approved Generic Technical Specification Changes and Other Changes
Project stage: Request
ML14343A7812015-01-0808 January 2015
Acceptance Review
Project stage: Acceptance Review
ML15195A4682015-08-14014 August 2015
Request for Additional Information
Project stage: RAI
ML16097A6022016-04-0808 April 2016
Audit of Supporting Design, Licensing and Other Documents Related to License Amendment Requests to Support Adoption of Technical Specification Task Force Traveler 312
Project stage: Acceptance Review
ML16138A6512016-06-0202 June 2016
Audit of Supporting Design, Licensing & Other Documents Related to License Amendment Requests to Support the Adoption of Technical Specification Task Force Traveler 312
Project stage: Other
ML15132A5692016-06-0909 June 2016
Issuance of Amendments Regarding Multiple Technical Specification Changes
Project stage: Approval
ML16287A3412016-10-20020 October 2016
Withdrawal of TSTF-312 Amendment Request
Project stage: Withdrawal
2016-10-20
[Table View] |
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Category:Memoranda
MONTHYEARML24199A2072024-07-24024 July 2024
TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter
ML24138A0092024-05-17017 May 2024
Public Meeting Summary - 2023 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50-348, and 50-364 -Meeting Number 20240474
ML24122C6202024-05-0101 May 2024
Public Meeting Summary - 2023 Annual Assessment Meeting Vogtle Electric Generating Plant, Units 1, 2, 3, and 4 Docket Nos.. 50-424, 50-424, 52-025, and 52-026 Meeting Number 20240471
ML23325A2022024-01-16016 January 2024
CFR Part 52 Construction Lessons-Learned Report
ML24004A2192024-01-0808 January 2024
Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023
ML23303A2032023-11-0101 November 2023
October 24, 2023, Summary of Comment Gathering Public Meeting on Lessons Learned from the ITAAC Hearing Process for Vogtle Units 3 and 4
ML22348A0862023-07-25025 July 2023
Finding in Accordance with 10 CFR 52.103(G) That All Acceptance Criteria Are Met for Vogtle Electric Generating Plant, Unit 4
ML23146A1672023-05-31031 May 2023
Public Meeting Summary2022 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50?348, and 50?364 Meeting Number 20230610
ML23115A0382023-05-0909 May 2023
Summary of Readiness Group Public Meeting on April 20, 2023
ML23115A0662023-05-0101 May 2023
Summary of Public Meeting with Southern Nuclear Operating Company to Have Presubmittal Meeting for Vogtle Electric Generating Plant, Unit 4
IR 05000424/20040252023-04-28028 April 2023
Public Meeting Summary - Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 5000424, 5000425, 5200025, 5200026, Meeting Number 20230375
ML22214B4882023-02-0808 February 2023
Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 4
ML22355A0322023-01-0303 January 2023
Revised Charter for the Vogtle Readiness Group to Oversee the Transition to Operations for Vogtle Units 3 and 4
ML22334A0812022-12-0101 December 2022
Update to Targeted Inspections, Tests, Analysis, and Acceptance Criteria for Vogtle Electric Generating Plant Unit 4
ML22322A1672022-11-28028 November 2022
Summary of 11/15/2022 Public Meeting on Lessons Learned
ML22237A0782022-08-0505 August 2022
American Nuclear Insurers, Notification of Change in the Number of Power Reactors in the Secondary Financial Protection (SFP) Program
ML20290A2812022-08-0101 August 2022
103g - Final Memorandum
ML22123A0652022-05-0202 May 2022
Public Meeting Summary Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 50-424, 50-425, 52-025, 52-026, Meeting Number 20220330
ML22108A1382022-04-18018 April 2022
Annual Assessment Public Meeting Summary
ML21337A0032021-12-0707 December 2021
Summary of Vogtle Readiness Group Public Meeting on December 2, 2021
ML21322A1502021-12-0202 December 2021
Summary of November 10, 2021 Public Meeting with Southern Nuclear Operating Company
ML21316A0692021-11-22022 November 2021
November 4, 2021 Summary of Public Meeting with Southern Nuclear Operating Company
ML21280A2962021-10-22022 October 2021
Replacement of Page 2 to Letter Dated June 30, 2020, Titled License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions (EPID L-2020-LLA0150)
ML21230A0102021-08-24024 August 2021
Summary of Public Meeting with Southern Nuclear Operating Company on August 12, 2021
ML21154A2772021-07-20020 July 2021
Summary of a Public Meeting with Southern Nuclear Operating Company on May 27, 2021
ML21194A0402021-07-20020 July 2021
Summary of June 24, 2021 Public Meeting with SNC
ML21190A0622021-07-16016 July 2021
Summary of July 8 2021 Public Meeting to Discuss Late-Filed Allegation Process for Vogtle Electric Generating Plant Units 3 and 4
ML21194A0392021-07-16016 July 2021
July 8, 2021 Summary of Public Meeting with Southern Nuclear Operating Company
ML21124A2032021-05-0606 May 2021
ASME Alternative ALT-16 Pre-submittal Meeting Summary 4-29-21
ML21123A1432021-05-0505 May 2021
April 22, 2021, Summary of a Public Meeting with Southern Nuclear Operating Company
ML21124A1232021-05-0404 May 2021
April 27, 2021, Public Meeting Summary Joseph M. Farley Nuclear Plant Units 1 and 2, Edwin I. Hatch Nuclear Plant Units 1 and 2, Docket No. 50-348, 50-364, 50-321, 50-366, Meeting Number ML21117A030
ML20318A2422020-12-18018 December 2020
.72 50.73 Applicability Memo
ML20351A2822020-12-10010 December 2020
Summary of Public Meeting with Southern Nuclear Operating Co
ML20318A2412020-11-18018 November 2020
Summary of Public Meeting with Southern Nuclear Operating Company, to Discuss Topic Regarding Vogtle Electric Generating Plant, Unit 4: ITAAC Post Closure Notification for ITAAC Index Number 344
ML20303A0422020-11-0505 November 2020
Summary of October 22, 2020 Public Meeting with Southern Nuclear Operating Company
NL-20-1262, Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion2020-10-30030 October 2020
Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion
ML20296A2432020-10-15015 October 2020
Summary of 10-15-20 Public Meeting with Southern Nuclear Operating Company
ML20283A4652020-10-15015 October 2020
Summary of Public Meeting on October 8, 2020 with Southern Nuclear Operating Company
ML20279A5202020-10-0707 October 2020
October 1, 2020, Summary of Public Meeting with Southern Nuclear Operating Company
ML20183A0902020-09-24024 September 2020
Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 3
ML20262G9882020-09-22022 September 2020
September 17, 2020 Summary of Public Meeting with Southern Nuclear Operating Company
ML20248H3292020-09-10010 September 2020
Meeting Summary for September 3, 2020 Public Meeting with Southern Nuclear Operating Company
ML20247J4812020-09-10010 September 2020
Summary for August 27, 2020 Public Meeting with Southern Nuclear Operating Company
ML20191A3832020-08-14014 August 2020
Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4
ML20216A6252020-08-10010 August 2020
Summary of a Public Meeting with Southern Nuclear Operating Company on July 30, 2020
ML20216A6362020-08-10010 August 2020
Summary of a Public Meeting with Southern Nuclear Operating Company on July 23, 2020
ML20205L4312020-07-29029 July 2020
Summary of a Public Meeting with Southern Nuclear Operating Company to Discuss Inspections, Tests, Analyses and Acceptance Criteria Nos. 375 and 216
ML20178A1302020-07-15015 July 2020
Memorandum Transmitting Safety Evaluation Regarding Welded Reinforcement Bar Splices at Vogtle Electric Generating Plant Units 3 and 4
ML20190A0182020-07-0808 July 2020
Summary of Meeting Regarding the Vogtle Readiness Group
ML20168A3352020-06-26026 June 2020
Summary of June 11, 2020 Public Meeting with Southern Nuclear Operating Company
2024-07-24
[Table view] |
Text
June 2, 2016 MEMORANDUM TO: Michael Markley, Chief Plant Licensing Branch II-1 Division of Reactor Licensing Office of Nuclear Reactor Regulation FROM: Undine Shoop, Chief /RA/
Radiation Protection and Consequence Branch Division of Risk Assessment Office of Nuclear Reactor Regulation Robert Dennig, Chief /RA/
Balance of Plant Branch Division of Safety Systems Office of Nuclear Reactor Regulation
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 - AUDIT OF SUPPORTING DESIGN, LICENSING AND OTHER DOCUMENTS RELATED TO LICENSE AMENDMENT REQUESTS TO SUPPORT THE ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER 312 ( TAC NOS. MF5317, ME5318, MF4560 AND 4561)
By letter dated November 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14335A623), the Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a license amendment request (LAR) to revise the Joseph M. Farley Nuclear Plant, Units 1 and 2, Technical Specifications (TS) to adopt various previously approved Technical Specifications Task Force (TSTF) Travelers and two changes not associated with Travelers. In addition, by letter dated July 18, 2014 (ADAMS Accession No. ML14203A124), SNC submitted a LAR to revise the Vogtle Electric Generating Plant Units 1 and 2 TS to adopt various previously approved TSTF Travelers.
The U.S. Nuclear Regulatory Commission, staff determined that additional information is needed related to the requested implementation of TSTF-312-A. The Radiation Protection and Consequence Branch with the support of Balance of Plant Branch staff performed a regulatory CONTACTS: Mark Blumberg, NRR/DRA/ARCB John Parillo, NRR/DRA/ARCB 301-415-1083 301-415-1344
M. Markley 2 audit of the calculations and supporting documents used to justify the LARs in accordance with LIC-111, Regulatory Audits. A summary of the audit performed on May 3, 2016 is attached.
Docket Nos. 50-348, 50-364, 50-424, 50-425
Enclosure:
As stated
ML16138A651
- via email OFFICE DRA/ARCB DRA/ARCB DSS/SBPB DRA/ARCB DSS/SBPB NAME WBlumberg JParillo SJones
- UShoop RDennig DATE 05 / 20 / 16 05 / 20 / 16 05 / 17 / 16 06 / 02 / 16 05 / 26 / 16 JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 - SUPPORTING DESIGN, LICENSING AND OTHER DOCUMENTS RELATED TO LICENSE AMENDMENT REQUESTS TO SUPPORT THE ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER 312 (TAC No. MF5317, ME5318, MF4560 AND 4561)
AUDIT
SUMMARY
BACKGROUND By letter dated November 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14335A623), the Southern Nuclear Operating Company, Inc.
(SNC, the licensee) submitted a request to revise the Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley), Technical Specifications (TS) to adopt various previously approved Technical Specifications Task Force (TSTF) Travelers and two changes not associated with Travelers.
The U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI) on December 30, 2015 and a response from SNC was provided on March 3, 2016 (ADAMS Accession No. ML14335A623).
In addition, by letter dated July 18, 2014 (ADAMS Accession No. ML14203A124), SNC submitted a request to revise the Vogtle Electric Generating Plant Units 1 and 2 (Vogtle) TS to adopt various previously approved TSTF Travelers. The NRC issued RAIs on January 13, 2015 and a response from SNC was provided on February 27, 2015 (ADAMS Accession No. ML15058A91).
In a call with SNC on April 6, 2016, the staff discussed the Farley RAI response and it was decided that an audit of the design, licensing and other document related to the TSTF-312 license amendment request would be held. It was also decided that the audit should include information supporting both the Farley and Vogtle applications to adopt TSTF-312. To supplement the information previously provided by SNC, SNC made available to the NRC staff supporting documents, detailed engineering drawings, analyses and design basis calculations used to justify the requested TSTF-312 changes.
ENCLOSURE
2 AUDIT
SUMMARY
The NRC staff performed this audit at the EXCEL Services Corporation office in Rockville, Maryland on May 3, 2016. The audit team consisted of the NRC staff members and applicants staff identified in the Table below. The regulatory audit was performed in accordance with Office or Nuclear Reactor Regulation procedure, LIC-111, Regulatory Audits.
The audit began with a presentation by SNC staff providing their position regarding implementation of TSTF-312 for Farley and Vogtle. Then SNC provided the supporting documents for the NRC staffs review. As the NRC staff reviewed the supporting documents, SNC provided clarifying information regarding the inputs and assumptions used by SNC. Based upon this review the NRC staff developed an RAI question and SNC developed a draft response to the RAI.
AUDIT PARTICIPANTS The audit was conducted by a team of NRC staff members who are knowledgeable in various aspects of the radiological dose consequences and heating and ventilation system design (HVAC). The following table provides a comprehensive list of the audit participants from the NRC, SNC and Bechtel.
Name Affiliation Mark Blumberg (Farley Reviewer)- Dose) NRC John Parillo (Vogtle Reviewer)- Dose NRC Undine Shoop NRC Bob Martin NRC Mike Markley NRC Steven Jones (HVAC) NRC Jamie Coleman SNC Keith Drudy SNC Ken McElroy SNC William Evans SNC Deep Ghosh (by phone) SNC Ken Jha Bechtel DOCUMENTS REVIEWED BY THE NRC STAFF Farley Drawing D-176005 Farley Drawing D-176006 Farley DOEJ-SM-C060059901-001, Descriptions of Operation for Adjacent HVAC Systems to the Common Control Room Containment Personnel Air Lock Open during Refueling Farley DOEJ-FXCR10185172, Evaluation of Non-Conservatism in Fuel Handling Accident Dose Calc Farley Calculation SM-96-1064-001, Fuel Handling Accident Doses
3 CLOSING BRIEFING At the audit exit, the NRC staff and SNC discussed SNCs proposed RAI responses to the following draft RAl:
Following a fuel handling accident (FHA) there exists a potential for activity to migrate from open containment penetrations into adjacent buildings and eventually into the control room. Please provide additional information describing how this potential contribution to control room dose is accounted for in, or bounded by, the FHA dose consequence analysis of record.
SNCs strategy and content for their response for Farley is provided below:
- Describe via qualitative evaluations, why any build-up of radioactivity around the MCR [Main Control Room] as released from open containment penetrations would be small and take time to accumulate - based on size of and locations of penetrations, driving mechanisms for activity transport, etc. Submit drawings and such as appropriate.
- The SNC Analysis of Record assumes the PAL [Personnel Air Lock] open and 450 CFM [cubic feet per minute] (plus 10 CFM) of unfiltered in-leakage through the MCR HVAC (pressurization mode). SNC had also submitted a documentation of engineering judgment (DOEJ) that added 10 SCFM of unfiltered, not dispersed, but diluted, in-leakage coming from containment into the MCR. This DOEJ will be modified with a 50% dilution factor (containment and aux building volume) and results will be submitted to the NRC. SNC will also provide key inputs and assumptions in the response (DOEJ inputs, assumptions, and justifications for changes if they differ from the current licensing basis). SNC will also include justification for 50% dilution and 10 CFM unfiltered in-leakage.
SNCs strategy and content for their response for Vogtle is provided below:
- Describe, via qualitative evaluations, why the potential for activity to build-up around and infiltrate the MCR is a very low based upon the design features of the plant. Include a discussion on the MCR airlocks and aux building airlocks, locations and size of penetrations, and the paths activity would have to traverse to build up around the MCR. Our conclusion will be there are [no] realistic scenarios for the proposed change to significantly increase dose to the MCR.
- Demonstrate by qualitative arguments that the activity in the vicinity of the MCR when conservatively diluted within the containment volume and a portion of the auxiliary building would be less than that already modeled to transport to the MCR via the dispersion modeled in the analysis of record (AOR) - This will consider existing conservatisms in the FHA analysis such as no credit for containment dilution and direct path dispersion modeled - the key is this will be a comparative evaluation to make the case that the current analysis is bounding. Finally, point to existing margin to the MCR dose.
The staff concluded the audit by informing SNC, per L-101, that all results from the audit are preliminary in nature and are subject to NRC management review.
