Letter Sequence RAI |
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MONTHYEARCNL-13-126, Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-4852013-11-22022 November 2013 Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-485 Project stage: Other ML14017A0782013-12-24024 December 2013 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 Acceptance of Requested Licensing Action Amendment (TAC Nos. MF3124, M3125, and MF3126) Project stage: Acceptance Review CNL-14-037, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Leakage Rate Through Main Steam Isolation Valves - TS-4852014-04-0404 April 2014 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Leakage Rate Through Main Steam Isolation Valves - TS-485 Project stage: Response to RAI ML14171A2882014-06-19019 June 2014 NRR E-mail Capture - RAIs Regarding Proposed Technical Specification Change to Revise the Leakage Rate Through Msivs TS-485, TAC Nos. MF3124, MF3125, and MF3126 Project stage: RAI ML14183A0082014-07-0101 July 2014 NRR E-mail Capture - RAI for TACs MF8124, MF8125, and MF8126 for Browns Ferry Project stage: RAI CNL-14-106, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-4852014-08-15015 August 2014 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-485 Project stage: Response to RAI 2014-04-04
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Category:E-Mail
MONTHYEARML24170A6392024-06-17017 June 2024 Notification of Inspection and Request for Information ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML23355A2202023-12-21021 December 2023 Radiation Protection Inspection - Inspection Report 2024-01 ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23208A0872023-07-26026 July 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry 1, 2, and 3, Alternative Request 0-ISI-47 to Use an Alternative to ASME Code, Section XI, Examination Requirements for Examination Categories B-N-1 and B-N-2 ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23117A0702023-04-26026 April 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, 1, 2, and 3, License Amendment Request to Revise Tech Specs Surveillance Requirements 3.4.3.2 and 3.5.1.11 Safety Relief Valves (BFN TS-540) ML23097A0172023-04-0606 April 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-566-A and TSTF-580-A, Revision 1 ML23073A2072023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message - NRC Acknowledgement ML23075A0502023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message and TVA Intentions on EA-22-122 - Choice Letter Response Email Message -- NRC Acknowledgement ML23073A2082023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML23013A1512023-01-13013 January 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Use Later ASME OM Code Edition and Alternative Requests BFN-IST-01 Through BFN-IST-05 ML23017A0062023-01-12012 January 2023 Initial Information Request Inspection Report: 2023001 ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23004A0352023-01-0404 January 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Delete TS 3.6.3.1 by Adopting TSTF-478 ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22304A1852022-10-31031 October 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Remove Site Acreage Description from TS 4.1 ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22265A1492022-09-21021 September 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Alternative Request BFN-0-ISI-32 ML22259A0392022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 5 ML22259A0382022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 4 ML22259A0372022-09-13013 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 3 ML22238A0672022-08-24024 August 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 2 ML22238A0652022-08-19019 August 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A1682022-06-21021 June 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Relief Request BFN-2-ISI-003 ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22131A1692022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-505 and TSTF-439 ML22091A1942022-03-0808 March 2022 2022 BFN POV Inspection Information Request ML22055A0772022-02-22022 February 2022 NRR E-mail Capture - Results of NRC SUNSI Review of Browns Ferry Nuclear Plant, Units 1, 2, and 3, Updated Final Safety Analysis Report, Amendment 29 ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22032A0322022-01-27027 January 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Alternative Request BFN-21-ISI-02 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl 2024-06-17
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NRR-PMDAPEm Resource From: Saba, Farideh Sent: Thursday, June 19, 2014 5:18 PM To: Williams, Gordon Robert (grwilliams1@tva.gov)
Cc: Schrull, Edward Dustin (edschrull@tva.gov); Hess, Thomas A (tahess@tva.gov)
Subject:
RAIs REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGE TO REVISE THE LEAKAGE RATE THROUGH MSIVS - TS-485, TAC Nos. MF3124, MF3125, and MF3126 Attachments: MF3124-6_BFN1-3 SBPB RAIs REVISE THE LEAKAGE RATE THROUGH MSIVS TS-485-FES.docx Importance: High
- Gordon, Please see the request for additional information (RAIs) in the attached document from the technical reviewer in the Balance of Plant Branch (SBPB). I had sent you these RAIs as draft RAIs on 06/05/14 and had a clarification call on 06/17/14. As we discussed during this call, you understand the questions. Referring to your email dated 06/19/14, you will respond to these RAIs by 07/18/14.
- 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 1
Hearing Identifier: NRR_PMDA Email Number: 1391 Mail Envelope Properties (Farideh.Saba@nrc.gov20140619171800)
Subject:
RAIs REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGE TO REVISE THE LEAKAGE RATE THROUGH MSIVS - TS-485, TAC Nos. MF3124, MF3125, and MF3126 Sent Date: 6/19/2014 5:18:26 PM Received Date: 6/19/2014 5:18:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients:
"Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov>
Tracking Status: None "Hess, Thomas A (tahess@tva.gov)" <tahess@tva.gov>
Tracking Status: None "Williams, Gordon Robert (grwilliams1@tva.gov)" <grwilliams1@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 616 6/19/2014 5:18:00 PM MF3124-6_BFN1-3 SBPB RAIs REVISE THE LEAKAGE RATE THROUGH MSIVS TS-485- FES.docx 32964 Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ
REQUEST FOR ADDITIONAL INFORMATION (RAI)
PROPOSED TECHNICAL SPECIFICATION CHANGE TO REVISE THE LEAKAGE RATE THROUGH MSIVS - TS-485 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated November 22, 2013, Tennessee Valley Authority (TVA), the licensee, requested a change to the Technical Specifications (TS) to Browns Ferry Nuclear Plant Units 1, 2, and 3 (BFN). The amendment proposes to change TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs), specifically for decreasing the allowable leakage rate of each of the mainsteam isolation valves (MSIV) and decreasing the combined leakage rate of all four MSIV.
The Nuclear Regulatory Commission (NRC) staff has performed a review of BFNs license amendment request (LAR) for modifying TS 3.6.1.3 (TS-485). The review resulted in the following request for additional information (RAI). The requested information is necessary for the NRC staff to complete the evaluation of this amendment request.
SBPB RAI-1 BFN Updated Final Safety Analysis Report (FSAR), Section 4.11.4 states that the outside mainsteam drain lines on the four mainsteam headers are used to allow continuous draining to the condenser through the orifice. In addition the outside steam line drains are capable of being utilized to equalize pressure across the main steam isolation valves prior to restart following steam line isolation. Also the main steam drain lines are used to warm up and pressurize the outside steam lines.
However, in the LAR, the licensee states:
In the unlikely event the primary flow path is not available, and consistent with the guidance provided in NEDC-31858P, a secondary flow path is provided (although not with orifice flow). The secondary flow path is through normally open valves FCV-1-168, FCV-1-169, FCV-1-170, and FCV-1-171, and continues through valves FCV-1-57, FCV-1-58, and FCV-1-59 to the main condenser.
Descriptions of drain pathways appear to be different between the FSAR reference and the statement in the LAR. Additionally, the licensee implies that some operator actions may be necessary for secondary drain flow path alignment.
- a. Clarify any differences in how the primary and secondary ALT pathway is operated post-accident versus the mainstream line drains systems while at power, startup, or Enclosure
shutdown. Consider revising the UFSAR by adding the two ALT pathway descriptions to the UFSAR.
- b. Explain how main control room (MCR) operators know when or how the primary flow path, which is passive, is unavailable in order to line-up the secondary path. Provide drawings and/or describe the instruments that are available to the MCR staff in order to make such an assessment.
SBPB RAI-2 In the LAR, the licensee states:
One of the valves (FCV-1-59) has a four-inch bypass containing no valves or orifices. Therefore, there is no concern associated with FCV-1-59 with respect to ALT Pathway availability.
Also, in the LAR, the licensee states:
The secondary ALT Pathway (Figure 2) has now been defined as the pathway through the main steam drain lines and through open valves FCV-1-57, FCV 58, and FCV-1-59 to the condenser.
Descriptions of drain pathways appear to be different between the UFSAR reference and the licensee statements in the LAR.
Confirm that there are no restrictions in the bypass line around FCV-1-59 and provide explanation of the system configuration and why the valve is closed and why the valve is necessary. If FCV-1-59 is truly a full bypass, describe why FCV-1-59 exists and why it needed to be open in the secondary ALT Pathway.
SBPB RAI-3 In the LAR, the licensee states:
That all the valves in the ALT pathway, and any boundary valves required to close, are included in the IST or augmented IST programs. The IST program and will test the power operated valves on an appropriate periodic basis.
In addition, the licensee states that the primary ALT Pathway is through this 0.1875-inch orifice with valve FCV-1-58 closed. To ensure the flow through the 0.1875-inch orifice is not obstructed, periodic radiography inspection of the 0.1875 inch orifice will be performed during refueling outages. Also four two-inch bypass lines, that contain 0.25 inch orifices (around valves FCV-1-168, FCV-1-169, FCV-1-170 and FCV-1-171), connecting to a three-inch header.
Inspection methodology for all orifices in the flow path, to verify there is no flow blockage, is not described in the LAR.
- a. Describe why a radiography (RT) inspection of the 0.1875 inch orifice around FCV-1-58 is preferred over a visual inspection. Also, describe why radiography was selected to verify an open flow path versus other means such as a visual inspection.
- b. Provide an explanation of how a RT would provide assurance on an open pathway through on orifice plate. Describe the acceptance criteria of the RT for the 0.1875 inch orifice.
- c. Identify the procedures/methodology that ensures that inspections are performed during refueling outages, including the frequency (i.e., every refueling outage) that the inspection is performed.
- d. Discuss the rational for not performing a periodic radiography inspection or visual inspection of the 0.25 inch orifices around FCV-1-168, FCV-1-169, FCV-1-170 and FCV-1-171.