CNL-15-260, Commitments to Maintain Severe Accident Management Guidelines

Commitments to Maintain Severe Accident Management Guidelines

ML15365A398
Person / Time
Site:	Browns Ferry, Watts Bar, Sequoyah
Issue date:	12/30/2015
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-15-260
Download: ML15365A398 (3)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-260 December 30, 2015 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating Licenses Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating Licenses Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391

Subject:

Tennessee Valley Authority (TVA) - Commitments to Maintain Severe Accident Management Guidelines for Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for TVAs Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants. These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures (EOPs). The SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.

The new SAMG commitments are listed in the Enclosure.

It is expected that NRC staff will conduct periodic inspection of the sites SAMGs; and performance deficiencies, if any are identified, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to NRC review and approval of SAMG strategies, or the use of equipment described in SAMGs.

U.S. Nuclear Regulatory Commission CNL-15-260 Page 2 December 30, 2015 If additional information is needed regarding this submittal, please contact Russell Thompson at (423) 751-2567 .

. Shea Vice President, Nuclear Licensing Enclosure SAMG Industry Initiative Commitments cc (Enclosure):

NRR Director - NRC Headquarters NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Senior Resident Inspector-Watts Bar Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRR Project Manager - Sequoyah Nuclear Plant NRR Project Manager -Watts Bar Nuclear Plant

ENCLOSURE SAMG Industry Initiative Commitments Commitment Scheduled Completion Date TVA Fleet administrative controls for SAMGs June 30, 2016 will be updated by June 30, 2016 to reflect that the site SAMGs are within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.

Browns Ferry Nuclear Plant will update the June 30, 2017 site SAMGs to Revision 3 of the BWROG generic severe accident guidelines (published February 2013) by June 30, 2017.

TVA Fleet administrative controls for SAMGs June 30, 2016 will be updated by June 30, 2016 to reflect that the site SAMGs will be updated to future revisions of the respective Owners Group generic severe accident technical guidelines, and the future revisions of the SAMGs will be integrated with other emergency response guideline sets and symptom-based Emergency Operating Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents1 within 2 refueling outages or 3 years of the publication date of the guidelines, whichever is greater.

1 Use of NEI 14-01 guidance for Browns Ferry Nuclear Plant begins with the update to Revision 4 of the BWROG generic severe accident guidelines.

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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-260 December 30, 2015 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating Licenses Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating Licenses Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391

Subject:

Tennessee Valley Authority (TVA) - Commitments to Maintain Severe Accident Management Guidelines for Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for TVAs Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants. These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures (EOPs). The SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.

The new SAMG commitments are listed in the Enclosure.

It is expected that NRC staff will conduct periodic inspection of the sites SAMGs; and performance deficiencies, if any are identified, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to NRC review and approval of SAMG strategies, or the use of equipment described in SAMGs.

U.S. Nuclear Regulatory Commission CNL-15-260 Page 2 December 30, 2015 If additional information is needed regarding this submittal, please contact Russell Thompson at (423) 751-2567 .

. Shea Vice President, Nuclear Licensing Enclosure SAMG Industry Initiative Commitments cc (Enclosure):

NRR Director - NRC Headquarters NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Senior Resident Inspector-Watts Bar Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRR Project Manager - Sequoyah Nuclear Plant NRR Project Manager -Watts Bar Nuclear Plant

ENCLOSURE SAMG Industry Initiative Commitments Commitment Scheduled Completion Date TVA Fleet administrative controls for SAMGs June 30, 2016 will be updated by June 30, 2016 to reflect that the site SAMGs are within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.

Browns Ferry Nuclear Plant will update the June 30, 2017 site SAMGs to Revision 3 of the BWROG generic severe accident guidelines (published February 2013) by June 30, 2017.

TVA Fleet administrative controls for SAMGs June 30, 2016 will be updated by June 30, 2016 to reflect that the site SAMGs will be updated to future revisions of the respective Owners Group generic severe accident technical guidelines, and the future revisions of the SAMGs will be integrated with other emergency response guideline sets and symptom-based Emergency Operating Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents1 within 2 refueling outages or 3 years of the publication date of the guidelines, whichever is greater.

1 Use of NEI 14-01 guidance for Browns Ferry Nuclear Plant begins with the update to Revision 4 of the BWROG generic severe accident guidelines.

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