ML24228A265: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:August 20, 2024
{{#Wiki_filter:August 20, 2024 LICENSEE:
 
Tennessee Valley Authority FACILITY:
LICENSEE: Tennessee Valley Authority
Sequoyah Nuclear Plant, Units 1 and 2 Watts Bar Nuclear Plant, Units 1 and 2  
 
FACILITY: Sequoyah Nuclear Plant, Units 1 and 2 Watts Bar Nuclear Plant, Units 1 and 2


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF AUGUST 14, 2024, PUBLIC PRE-SUBMITTAL MEETING WITH TENNESSEE VALLEY AUTHORITY REGARDING A FUTURE SEQUOYAH NUCLEAR PLANT AND WATTS BAR NUCLEAR PLANT LICENSE AMENDMENT REQUEST RELATED TO TE CHNICAL SPECIFICATION 3.5.2.,
OF AUGUST 14, 2024, PUBLIC PRE-SUBMITTAL MEETING WITH TENNESSEE VALLEY AUTHORITY REGARDING A FUTURE SEQUOYAH NUCLEAR PLANT AND WATTS BAR NUCLEAR PLANT LICENSE AMENDMENT REQUEST RELATED TO TECHNICAL SPECIFICATION 3.5.2.,
ECCS - OPERATING (EPID L-2024-LRM-0090)
ECCS - OPERATING (EPID L-2024-LRM-0090)
 
On August 14, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff held a pre-submittal meeting with representatives from Tennessee Valley Authority (TVA). The purpose of the meeting was to discuss the licensees plans to submit a license amendment request (LAR) related to the emergency core cooling system (ECCS) at Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah) and Watts Bar Nuclear Plant, Units 1 and 2 (Watts Bar), which would revise Note 1 of Technical Specification (TS) 3.5.2, ECCS - Operating, to add isolation of residual heat removal (RHR) flow paths for pressure isolation valve testing. The meeting notice and agenda, dated July 30, 2024, are available in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession No. ML24226A432. A list of attendees is provided in the enclosure.
On August 14, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff held a pre-submittal meeting with representatives from Tennessee Valley Authority (TVA). The purpose of the meeting was to discuss the licensees plans to submit a license amendment request (LAR) related to the emergency core cooling system (ECCS) at Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah) and Watts Bar Nuclear Plant, Units 1 and 2 (Watts Bar), which would revise Note 1 of Technical Specification (TS) 3.5.2, ECCS - Operating, to add isolation of residual heat removal (RHR) flow paths for pressure isolat ion valve testing. The meeting notice and agenda, dated July 30, 2024, are available in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession No. ML24226A432. A list of attendees is provided in the enclosure.
 
During the meeting, the licensee presented information (ML24225A254) regarding the proposed TS changes including an EECS description, reasons for the proposed change, technical background, precedent LARs and the submittal timeframe.
During the meeting, the licensee presented information (ML24225A254) regarding the proposed TS changes including an EECS description, reasons for the proposed change, technical background, precedent LARs and the submittal timeframe.
Below is a summary of the key comments and discussions:
Below is a summary of the key comments and discussions:
: 1. Any changes to related in-service testing requirements would be included in the LAR.
: 1. Any changes to related in-service testing requirements would be included in the LAR.
: 2. TS 3.5.2, Note 1, does not specify when the RHR flow path can be isolated, other than it is in Mode 3.
: 2. TS 3.5.2, Note 1, does not specify when the RHR flow path can be isolated, other than it is in Mode 3.
The NRC staff did not make any regulatory decisions or commitments at the meeting. There were no members of the public in attendance.


The NRC staff did not make any regulatory decisions or commitments at the meeting. There were no members of the public in attendance.
Please direct any inquiries to me at 301-415-1383 or by e-mail to Perry.Buckberg@nrc.gov.  
 
/RA/
Please direct any inquiries to me at 301-415-1383 or by e-mail to Perry.Buckberg@nrc.gov.
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, 50-390 and 50-391  
 
/RA/
 
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
 
Docket Nos. 50-327, 50-328, 50-390 and 50-391


==Enclosure:==
==Enclosure:==
List of Attendees
List of Attendees cc: Listserv  
 
cc: Listserv
 
LIST OF ATTENDEES
 
AUGIST 14, 2024, VIRTUAL PUBLIC MEETING
 
WITH TENNESSEE VALLEY AUTHORITY, ET AL.
 
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2
 
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2
 
PRE-APPLICATION MEETING REGARDING
 
TECHNICAL SPECIFICATION 3.5.2, NOTE 1
 
U.S. Nuclear Regulatory Commission Branch Perry Buckberg - NRR1/DORL2/LPLII-23 Jo Ambrosini - NRR/DSS/SNSB4 Steve Smith - NRR/DSS/STSB5
 
Tennessee Valley Authority Jesse Baron Andrew Taylor Chris Carey Paul Parashak Stuart Rymer Shawna Hughes Kasey Decker Dustin Martin
 
1 Office of Nuclear Reactor Regulation 2 Division of Operating Reactor Licensing 3 Plant Licensing Branch II-2 4 Nuclear Systems Performance Branch 5 Technical Specifications Branch


Enclosure
Enclosure LIST OF ATTENDEES AUGIST 14, 2024, VIRTUAL PUBLIC MEETING WITH TENNESSEE VALLEY AUTHORITY, ET AL.
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 PRE-APPLICATION MEETING REGARDING TECHNICAL SPECIFICATION 3.5.2, NOTE 1 U.S. Nuclear Regulatory Commission Branch Perry Buckberg -
NRR1/DORL2/LPLII-23 Jo Ambrosini -
NRR/DSS/SNSB4 Steve Smith -
NRR/DSS/STSB5 Tennessee Valley Authority Jesse Baron Andrew Taylor Chris Carey Paul Parashak Stuart Rymer Shawna Hughes Kasey Decker Dustin Martin 1 Office of Nuclear Reactor Regulation 2 Division of Operating Reactor Licensing 3 Plant Licensing Branch II-2 4 Nuclear Systems Performance Branch 5 Technical Specifications Branch


ML24228A268 (Package)
ML24228A268 (Package)

Latest revision as of 13:30, 24 November 2024

Summary of Public Pre-Submittal Meeting with Tennessee Valley Authority Regarding a Future Sequoyah Nuclear Plant and Watts Bar Nuclear Plant LAR Related to TS 3.5.2. ECCS - Operating
ML24228A265
Person / Time
Site: Sequoyah, Watts Bar  Tennessee Valley Authority icon.png
Issue date: 08/20/2024
From: Perry Buckberg
Plant Licensing Branch II
To:
Tennessee Valley Authority
Green K
Shared Package
ML24228A268 List:
References
EPID L-2024-LRM-0090
Download: ML24228A265 (4)


Text

August 20, 2024 LICENSEE:

Tennessee Valley Authority FACILITY:

Sequoyah Nuclear Plant, Units 1 and 2 Watts Bar Nuclear Plant, Units 1 and 2

SUBJECT:

SUMMARY

OF AUGUST 14, 2024, PUBLIC PRE-SUBMITTAL MEETING WITH TENNESSEE VALLEY AUTHORITY REGARDING A FUTURE SEQUOYAH NUCLEAR PLANT AND WATTS BAR NUCLEAR PLANT LICENSE AMENDMENT REQUEST RELATED TO TECHNICAL SPECIFICATION 3.5.2.,

ECCS - OPERATING (EPID L-2024-LRM-0090)

On August 14, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff held a pre-submittal meeting with representatives from Tennessee Valley Authority (TVA). The purpose of the meeting was to discuss the licensees plans to submit a license amendment request (LAR) related to the emergency core cooling system (ECCS) at Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah) and Watts Bar Nuclear Plant, Units 1 and 2 (Watts Bar), which would revise Note 1 of Technical Specification (TS) 3.5.2, ECCS - Operating, to add isolation of residual heat removal (RHR) flow paths for pressure isolation valve testing. The meeting notice and agenda, dated July 30, 2024, are available in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession No. ML24226A432. A list of attendees is provided in the enclosure.

During the meeting, the licensee presented information (ML24225A254) regarding the proposed TS changes including an EECS description, reasons for the proposed change, technical background, precedent LARs and the submittal timeframe.

Below is a summary of the key comments and discussions:

1. Any changes to related in-service testing requirements would be included in the LAR.
2. TS 3.5.2, Note 1, does not specify when the RHR flow path can be isolated, other than it is in Mode 3.

The NRC staff did not make any regulatory decisions or commitments at the meeting. There were no members of the public in attendance.

Please direct any inquiries to me at 301-415-1383 or by e-mail to Perry.Buckberg@nrc.gov.

/RA/

Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, 50-390 and 50-391

Enclosure:

List of Attendees cc: Listserv

Enclosure LIST OF ATTENDEES AUGIST 14, 2024, VIRTUAL PUBLIC MEETING WITH TENNESSEE VALLEY AUTHORITY, ET AL.

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 PRE-APPLICATION MEETING REGARDING TECHNICAL SPECIFICATION 3.5.2, NOTE 1 U.S. Nuclear Regulatory Commission Branch Perry Buckberg -

NRR1/DORL2/LPLII-23 Jo Ambrosini -

NRR/DSS/SNSB4 Steve Smith -

NRR/DSS/STSB5 Tennessee Valley Authority Jesse Baron Andrew Taylor Chris Carey Paul Parashak Stuart Rymer Shawna Hughes Kasey Decker Dustin Martin 1 Office of Nuclear Reactor Regulation 2 Division of Operating Reactor Licensing 3 Plant Licensing Branch II-2 4 Nuclear Systems Performance Branch 5 Technical Specifications Branch

ML24228A268 (Package)

ML24228A265 (Summary)

ML24226A432 (Meeting Notice)

ML24225A254 (Meeting Slides)

OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SNSB/BC NRR/DSS/STSB/BC NAME PBuckberg ABaxter PSahd SMehta (RElliott for)

DATE 08/15/2024 08/19/2024 08/19/2024 08/19/2024 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona PBuckberg DATE 08/20/2024 08/20/2024