Letter Sequence Response to RAI |
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TAC:MB9776, Control Room Habitability (Approved, Closed) TAC:MB9777, Control Room Habitability (Approved, Closed) TAC:MB9778, Control Room Habitability (Approved, Closed) |
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MONTHYEARML0635500492007-01-0909 January 2007 RAI, Generic Letter 2003-01, Control Room Habitability Project stage: RAI ML0704005662007-02-0808 February 2007 Response to Request for Additional Information Regarding Generic Letter 2003-01, Control Room Habitability. Project stage: Response to RAI ML0705804112007-03-0808 March 2007 Review of Response to Generic Letter 2003-01, TAC MB9776, MB9777, MB9778 Project stage: Approval ML0806001672008-02-27027 February 2008 Response to Generic Letter (GL) 2003-01- Control Room Habitability Request for Commitment Extension Project stage: Request 2007-02-08
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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February 8, 2007 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D. C. 20555-0001 Gentlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2003-01, "CONTROL ROOM HABITABILITY" (TAC NOS. MB9776, MB9777, AND MB9778) This letter is in response to NRC's January 9, 2007, Request for Additional Information (ADAMS Accession No. ML063550049) regarding Generic Letter (GL) 2003-01, Control Room Habitability. TVA's original response to GL 2003-01 was submitted on December 8, 2003 (ML033430322).
NRC RAI In a December 8, 2003, letter, Tennessee Valley Authority (TVA) responded to questions concerning Generic Letter (GL) 2003-01, Control Room Habitability. TVA stated that Technical Specification (TS) surveillance requirement (SR) 3.7.3.4 calls for periodic testing of each Control Room Emergency Ventilation subsystem to verify that a Control Room Habitability Zone (CRHZ) pressure of greater than 0.125 inch
water gauge can be maintained. TVA stated that this SR quantifies the CRHZ unfiltered in-leakage, that this testing has been performed on a periodic basis since 1991, and that
U.S. Nuclear Regulatory Commission Page 2 February 8, 2007 the testing is adequate to demonstrate CRHZ integrity such that no TS changes are required.
Additional information concerning the complex testing/
in-leakage quantification testing is required in order for the staff to complete its review of GL 2003-01 Item 1c.
Provide information about this testing in sufficient detail
such that the Nuclear Regulatory Commission staff is able to evaluate and determine if it is an acceptable method to demonstrate control room envelope integrity as described in Regulatory Guide 1.197 "Demonstrating Control Room Envelope Integrity At Nuclear Power Reactors" and Nuclear Energy Institute document, NEI 99-03 "Control Room Habitability Assessment Guidance."
TVA Response In the original submittal letter, TVA indicated that the periodic testing of each Control Room Emergency Ventilation subsystem, which verifies that a CRHZ pressure of greater than 0.125 inch water gauge can be maintained, satisfactorily quantified the CRHZ unfiltered inleakage. In light of subsequent industry efforts on the development of Technical
Specifications Task Force (TSTF) Traveler 448, which provides model TS for an acceptable method to demonstrate control room envelope integrity as described in Regulatory Guide 1.197 "Demonstrating Control Room Envelope Integrity At Nuclear Power Reactors" and Nuclear Energy Institute (NEI) document, NEI 99-03 "Control Room Habitability Assessment Guidance", TVA will evaluate the testing elements recommended in
TSTF-448 and will submit a proposed license amendment request based on TSTF-448 by March 1, 2008. The Notice of Availability of TSTF-448 Revision 3 was posted in the Federal Register on January 17, 2007, under the Consolidated Line Item Improvement Program.
TVA does not consider this a high priority activity in that tracer gas testing on the BFN CRHZ shows significant unfiltered inleakage margin (measured value of 600 cubic feet
per minute (CFM)) to the analysis value assumed in the BFN Alternate Source Term design and licensing basis of 3717 CFM.
U.S. Nuclear Regulatory Commission Page 3 February 8, 2007 If you have any questions about this submittal, please contact me at (256) 729-2636.
Sincerely, Original signed by:
William D. Crouch Manager of Licensing and Industry Affairs
Enclosure:
List of Regulatory Commitments cc: See page 3 U.S. Nuclear Regulatory Commission Page 4 February 8, 2007 Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415
NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Margaret Chernoff, Project Manager
U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 U.S. Nuclear Regulatory Commission Page 5 February 8, 2007 DTL:BCM:BAB Enclosure cc (Enclosure):
M. Bajestani, NAB 1A-BFN A. S. Bhatnagar, LP 6A-C R. H. Bryan, BR 4X-C R. G. Jones, POB 2C-BFN
G. V. Little, NAB 1D-BFN R. A. DeLong, SAB 1A-BFN B. J. O'Grady, PAB 1E-BFN K. W. Singer, LP 6A-C P. D. Swafford, LP 6A-C E. J. Vigluicci, WT 6A-K NSRB Support, LP 5M-C
EDMS WT CA - K s:lic/submit/subs/GL 2003-01.doc
Enclosure Browns Ferry Nuclear Plant (BFN)
Units 1, 2, and 3 Request For Additional Information Regarding Generic Letter 2003-01 Control Room Habitability List of Regulatory Commitments
- 1. TVA will evaluate the testing elements recommended in TSTF-448 and will submit a proposed license amendment request based on TSTF-448 by March 1, 2008.