ML15323A006

NRR E-mail Capture - (External_Sender) Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, for Browns Ferry Units 1, 2, and 3

ML15323A006
Person / Time
Site:	Browns Ferry
Issue date:	11/18/2015
From:	Walter D State of AL, Dept of Public Health, Office of Radiation Control
To:	Farideh Saba Plant Licensing Branch II
References
Download: ML15323A006 (3)

Text

NRR-PMDAPEm Resource From: David.Walter@adph.state.al.us Sent: Wednesday, November 18, 2015 5:20 PM To: Saba, Farideh

Subject:

[External_Sender] Issuance of Amendments to Revise Technical Specification 2.1.1, "Reactor core Safety Limits, " for Browns Ferry Units 1, 2, and 3

Farideh, I have no comments.

Thanks.

David Walter, Director Alabama Office of Radiation Control Phone: (334)206-5391 Fax: (334)206-5387 Visit our web site at www.adph.org/radiation From: "Saba, Farideh" To: "'David.Walter@adph.state.al.us'"

Cc: "Clayton, Beverly" , "Pfefferkorn, Candace" Date: 11/18/2015 03:16 PM

Subject:

Issuance of Amendments to Revise Technical Specification 2.1.1, "Reactor core Safety Limits," for Browns Ferry Units 1, 2, and 3

Dear Mr. Walter,

The U.S. Nuclear Regulatory Commission (NRC) is about to issue amendments to the Browns Ferry Units 1, 2, and 3 licenses. In accordance with Title 10 of the Code of Federal Regulations, Section 50.91(b), I am notifying you of the proposed issuance of this amendment.

These amendments are in response to the Tennessee Valley Authoritys (TVAs) application dated December 11, 2014, as supplemented by letters dated June 3 and July 30, 2015. These amendments revise Section 2.1.1, Reactor Core SLs

[Safety Limits], of the Technical Specifications (TSs) for all three units, to lower the value of the reactor steam dome pressure safety limit from the current 785 pounds per square inch gauge (psig) to 585 psig. The revised value of 585 psig is consistent with the lower range of the critical power correlations currently in use at the units. The revised value will also adequately bound a pressure regulator failure open transient event. This change resolves a Title 10 of the Code of Federal Regulation (10 CFR), Part 21 condition concerning a potential to momentarily violate Reactor Core Safety Limit 2.1.1.1 and 2.1.1.2 during a Pressure Regulator Failure Maximum Demand (Open) transient.

Attached is the associated proposed no significant hazards consideration for the amendment request that was published in the Federal Register on May 5, 2015 (80 FR 25721).

Please let us know if you have any comments on behalf of the State of Alabama for the above amendments.

Regards, Farideh 1

Farideh E. Saba, P.E.

Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV

[attachment "80 FR 25721 5-15.pdf" deleted by David Walter/RAD/ADPH]

Confidentiality Notice - This e-Mail message, including any attachments, is for the sole use of the intended recipient(s) and may contain confidential or privileged information. If this message concerns a lawsuit, it may be considered a privileged communication. Any unauthorized review, use, disclosure, or distribution is prohibited. If you are not the intended recipient, please contact the sender by reply e-mail and destroy all copies of the original message.

2

Hearing Identifier: NRR_PMDA Email Number: 2501 Mail Envelope Properties (OF8E0F42EA.293312D6-ON86257F01.007A9D35-86257F01.007AACCD)

Subject:

[External_Sender] Issuance of Amendments to Revise Technical Specification 2.1.1, "Reactor core Safety Limits, " for Browns Ferry Units 1, 2, and 3 Sent Date: 11/18/2015 5:19:56 PM Received Date: 11/18/2015 5:20:58 PM From: David.Walter@adph.state.al.us Created By: David.Walter@adph.state.al.us Recipients:

"Saba, Farideh" <Farideh.Saba@nrc.gov>

Tracking Status: None Post Office: LocalDomain Files Size Date & Time MESSAGE 2752 11/18/2015 5:20:58 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

NRR-PMDAPEm Resource From: David.Walter@adph.state.al.us Sent: Wednesday, November 18, 2015 5:20 PM To: Saba, Farideh

Subject:

[External_Sender] Issuance of Amendments to Revise Technical Specification 2.1.1, "Reactor core Safety Limits, " for Browns Ferry Units 1, 2, and 3

Farideh, I have no comments.

Thanks.

David Walter, Director Alabama Office of Radiation Control Phone: (334)206-5391 Fax: (334)206-5387 Visit our web site at www.adph.org/radiation From: "Saba, Farideh" To: "'David.Walter@adph.state.al.us'"

Cc: "Clayton, Beverly" , "Pfefferkorn, Candace" Date: 11/18/2015 03:16 PM

Subject:

Issuance of Amendments to Revise Technical Specification 2.1.1, "Reactor core Safety Limits," for Browns Ferry Units 1, 2, and 3

Dear Mr. Walter,

The U.S. Nuclear Regulatory Commission (NRC) is about to issue amendments to the Browns Ferry Units 1, 2, and 3 licenses. In accordance with Title 10 of the Code of Federal Regulations, Section 50.91(b), I am notifying you of the proposed issuance of this amendment.

These amendments are in response to the Tennessee Valley Authoritys (TVAs) application dated December 11, 2014, as supplemented by letters dated June 3 and July 30, 2015. These amendments revise Section 2.1.1, Reactor Core SLs

[Safety Limits], of the Technical Specifications (TSs) for all three units, to lower the value of the reactor steam dome pressure safety limit from the current 785 pounds per square inch gauge (psig) to 585 psig. The revised value of 585 psig is consistent with the lower range of the critical power correlations currently in use at the units. The revised value will also adequately bound a pressure regulator failure open transient event. This change resolves a Title 10 of the Code of Federal Regulation (10 CFR), Part 21 condition concerning a potential to momentarily violate Reactor Core Safety Limit 2.1.1.1 and 2.1.1.2 during a Pressure Regulator Failure Maximum Demand (Open) transient.

Attached is the associated proposed no significant hazards consideration for the amendment request that was published in the Federal Register on May 5, 2015 (80 FR 25721).

Please let us know if you have any comments on behalf of the State of Alabama for the above amendments.

Regards, Farideh 1

Farideh E. Saba, P.E.

Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV

[attachment "80 FR 25721 5-15.pdf" deleted by David Walter/RAD/ADPH]

Confidentiality Notice - This e-Mail message, including any attachments, is for the sole use of the intended recipient(s) and may contain confidential or privileged information. If this message concerns a lawsuit, it may be considered a privileged communication. Any unauthorized review, use, disclosure, or distribution is prohibited. If you are not the intended recipient, please contact the sender by reply e-mail and destroy all copies of the original message.

2

Hearing Identifier: NRR_PMDA Email Number: 2501 Mail Envelope Properties (OF8E0F42EA.293312D6-ON86257F01.007A9D35-86257F01.007AACCD)

Subject:

[External_Sender] Issuance of Amendments to Revise Technical Specification 2.1.1, "Reactor core Safety Limits, " for Browns Ferry Units 1, 2, and 3 Sent Date: 11/18/2015 5:19:56 PM Received Date: 11/18/2015 5:20:58 PM From: David.Walter@adph.state.al.us Created By: David.Walter@adph.state.al.us Recipients:

"Saba, Farideh" <Farideh.Saba@nrc.gov>

Tracking Status: None Post Office: LocalDomain Files Size Date & Time MESSAGE 2752 11/18/2015 5:20:58 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: