ML14296A770

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2014/10/23 NRR E-mail Capture - RAIs Regarding Browns Ferry Nuclear Plant, Unit 2, Pressure Temperature Limits Amendment Docket No. 50-260 (TAC No. MF4304)
ML14296A770
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 10/23/2014
From: Saba F E
Division of Operating Reactor Licensing
To: Gordon D
Tennessee Valley Authority
References
MF4304
Download: ML14296A770 (2)


Text

1NRR-PMDAPEm ResourceFrom:Saba, FaridehSent:Thursday, October 23, 2014 12:19 PMTo:Gordon, DennisCc:Widrevitz, Dan

Subject:

RAIs REGARDING BROWNS FERRY NUCLEAR PLANT, UNIT 2, PRESSURE TEMPERATURE LIMITS AMENDMENT DOCKET NO. 50-260 (TAC NO. MF4304)Importance:HighGordon, By letter dated June 19, 2014, Tennessee Valley Authority, the licensee for Browns Ferry Nuclear Plant, Unit No. 2, submitted for staff review and approval of a license amendment request to implement new Pressure Temperature (P/T) Limits. In order to complete its review of the licensee's submittal, the Nuclear Regulatory Commission (NRC) staff requires additional information to complete its review. The NRC staff draft request for additional information (RAIs) are as follows. As we agreed during the clarification call today, please respond to these request for additional information (RAIs) by December 2, 2014. RAI 1 Clarify why the modified P/T limits curves required Note 1 of TS SR 3.4.9.1 and associated values to cite >313 psig rather than >312 psig.

RAI 2 The staff requests that sample calculations for Curves A, B, and C be provided for the 48 Effective Full-Power Year P/T limits curves representing the 313 psig "notch" in said curves. Specifically clarify the relationship between the notches and the controlling material property from which the notches are derived. RAI 3 represents a Pressure and Temperature Limits Report (PTLR), including text such as, Changes to the curves, limits, or parameters within this PTLR, based upon new irradiation fluence data of the reactor pressure vessel, or other plant design assumptions in the Updated Final Safety Analysis Report, can be made pursuant to Section 50.59 of Title 10 of Code of Federal Regulations, provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance.

However, the application does not request implementation of a PTLR. Confirm that it is not the intent of the application to implement a PTLR.

Thanks,

Farideh Farideh E. Saba, P.E. Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV Hearing Identifier: NRR_PMDA Email Number: 1660 Mail Envelope Properties (Farideh.Saba@nrc.gov20141023121800)

Subject:

RAIs REGARDING BROWNS FERRY NUCLEAR PLANT, UNIT 2, PRESSURE TEMPERATURE LIMITS AMENDMENT DOCKET NO. 50-260 (TAC NO. MF4304) Sent Date: 10/23/2014 12:18:57 PM Received Date: 10/23/2014 12:18:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients: "Widrevitz, Dan" <Dan.Widrevitz@nrc.gov> Tracking Status: None "Gordon, Dennis" <Dennis.Gordon@nrc.gov> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 2031 10/23/2014 12:18:00 PM Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received: