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| | number = ML070400566 | | | number = ML070400566 |
| | issue date = 02/08/2007 | | | issue date = 02/08/2007 |
| | title = Browns Ferry, Units 1, 2, and 3 - Response to Request for Additional Information Regarding Generic Letter 2003-01, Control Room Habitability. | | | title = Response to Request for Additional Information Regarding Generic Letter 2003-01, Control Room Habitability. |
| | author name = Crouch W D | | | author name = Crouch W D |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
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
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - 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Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - 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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.