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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 - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - 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 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 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 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 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual 2024-09-03
[Table view] Category:Operating Plan
MONTHYEARML13063A4372013-02-28028 February 2013 Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order # EA-12-051) ML13063A4362013-02-28028 February 2013 Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Reliable Hardened Containment Vents (Order Number EA-12-050) ML12240A1062012-08-23023 August 2012 Integrated Improvement Plan Summary ML0810104512008-04-0404 April 2008 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) BFN Steam Monitoring Plan ML18283B6911976-09-20020 September 1976 Superseded Pages Per 50th Revision, Dated 9/20/1976 ML18283B0431976-06-16016 June 1976 Submits 45th Revision to Document Previously Submitted on 4/12/1975, Entitled Plan for Evaluation, Repair, and Return to Service of Browns Ferry Units 1 and 2 (March 22, 1975, Fire). ML18283B0441976-06-15015 June 1976 44th Revision to Document Previously Submitted on 4/16/1975, Entitled Plan for Evaluation, Repair, and Return to Service of Browns Ferry Units 1 and 2 (March 22, 1975, Fire). 2013-02-28
[Table view] |
Text
NRC FORM 195 I2.78)
NRC DISTRIBUTION Fon PART 50 DOCKET MATERIAL U.S. NUCLL'AR REGULATORY C ISSION DOCKET NUMBER 50-259 FILE NUMBER
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TP>> Mr. B,C. Rusche FROM: TVA DATE OF DOCUMENT Chattanooga, Tenn 37401 6-16-76 J E Gilleland DATE RECEIVED 6-18-76 .
I7IL ET TE R 0 NOTOR Z E 0 I PROP INPUT FORM NUMBER OF COPIES RECEIVED 5toRIGINAL IRUNC LASS I PIE 0 '
QCOP Y 1 signed DEscRIPTIDN Ltr trans the following: ENGLosURE /5th Revison to "Plan for Evalaution, Repair & Return to Service of Browns Ferry 1
& 2 Plant(March 22, 1975 Fire)" ~ ~ ~ ~
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. PLANT NAME: Browns Ferry 1 & 2 Mttlatt/Lip@
os SAFETY FOR ACTION/INFORMATION DHL 6 ASSIGNED AD: ASSX NED AD BRANCH CHIEF:
PROJECT MANAGER: P O.a A' a LICo ASST INTERNAL 0 ISTRI BUTION RED FILE SYSTEMS SAFETY SITE SA NRC PDR'&E HEINEMAN'CHROEDER ENVIRO NA S BENAROYA OELD GOSSXCK & STAFF ENGINEERING IPPOLITO MIPC 'ACCARRY KIRK'OD CASE KNIGHT HANAUER SI1WEIL OPE'RATING REACTORS PAMLICKI PROJECT MANA EMEN RFACTOR SAFE'IIY OPERAT N BOYD ROSS EISENH P COLLINS NOVAK SHAD HOUSTON ROSZTOCZY BAER PETERSON CHECK BUTLER MELTZ GRIMES HELTEMES AT& I SKOVHOLT SALTZMAN RUTBERG EXTERNAL DISTRIBUTION CONTROI NUMBER LPDR: Athens NAT LAB: BROOK11AVEN N TIC: REG VIE ULRIKSON ORNL N$+ ~ LA PDR 6198 >>
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F76 1916 rt yQ JUN 16 >g76 Itegoleto Docile, lie gp Mr, Benard CD Rusche, Director Office of Nuclear Reactor Regulation U.S; Nuclear Regulatory Commission sb Washington, DC 20555
Dear Mr,
Rusche:
JOIg8>9>
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In the Matter of the ) Docket Nos ~ 50-259, Tennessee Valley Authority )
Enclosed are 45 of the 45th revision to a docume'nt previousl submitted on 'April 13, 1975, entitled "Plan for Evaluation, Repair, and Return to Service of Browns Ferry Units 1 and 2 (March 22, 1975, Fire) ~
"'he revision consists of the following:
Evaluation Plan
Material:Revised. ' 'Par't for'ampling, Analysis, and V 'rogram, Cleanup of Residue on Affected Structures, Systems, and Components.
This revision"includes additional information regarding the frequency at which the condition of electrical cables that have been'oated with flame retardant material (Flamemast:ic 71A) will be inspected.
Instructions for entering the 45th revision are also included.
Very truly yours,"
J. E, Gilleland Assistant Manager of Power Enclosures CC: See page 2-An Equal Opportunity Employer
Mr.. Benard C. Rusche JUIII 1.6 1976 CC (E'nclosures):
Mr', Frank Long Regional Office U.S Nuclear Regulatory Commission 230'eachtree Street,.NN,, 'Suite 818 Atlanta, Georgia 30303 Mr. Norman C. Moseley, Director Office (3)'egional U~S ~ Nuclear Regulatory Commission 230'eachtree Street, HM., Suite 818 Atlanta, Georgia 30303 Mrs- C+ H+ Murphy Regional Office U.S; Nuclear Regulatory, Commission 230'eachtree Street, NW , Suite818 Atlanta, Georgia 30303 '
Qgulatory Docket fight Page 15 Part V Section 3 Page 3.5 Recovery Plan BFNP Revised. 6/9/76 Particular attention should be given to cleaning uninsulated terminals.
,6.9.4.1 The transformer shall be reassembled and. each winding given a meggar test with the other windings grounded.
, 6.9.4.2 If the transformer is of the voltage-regulating type with moving parts and electrical contacts, it shall be cleaned, and. treated, as specified in applicable paragraphs of 6.2 (motors) and 6.3 (switchboards). It shall be reassembled, relubricated, and retested in accordance with applicable manufacturer's instructions.
6.9.5 The transformers shall be reinstalled and returned to normal status.
6.10 Reinspection 6.10.1 All electrical equipment, except totally enclosed. motors and.
other sealed. electrical equipment, shall be given a visual inspection, approximate3y six months after the equipment has been cleaned. Particular attention should. be given to the presence of corrosion'products. If any products are noted.,
the equipment shall be recleaned.
6.10.2 A11 cable trays in the units 1 and 2 reactor building shall be
.inspected annually for 5 years for indications of degradation of the cable tray system. If degraded. trays or supports are
'found., they should be replaced as soon as possib3.e. No wholesale degradation and. replacement of cable tray systems
'are expected to occur.
6.10.3 .In response to an ACRS concern that the Flamemastic cocooning of electrical cables changes the working environment, at the first unit 1 refueling outage, at the second. unit 1 refueling outage, and thereafter at approximately every 3 years during the nearest unit 3. refueling outage, a nondivisional low-voltage power cable tray on unit 1 (floor elevation 593) shall have a portion of the Flamemastic cocoon opened., the cables inspected, and a sample of the cable jacketing removed.. The
'acket sample shall be given an ASTM D412 physical and dimensional test for elongation and tensile strength. The test values shall be compared. to previously obtained values to detexmine the aging of the cable materials.
Repairs to the cable jacket shall be made with a cable jacket repair kit, and the open area shall be recoated with Flamemastic.
(see attachments 5 and 5a, memorandums dated April 27, 3.976, and June 9, 3.976, from J. R. Calhoun to H. J, Green, subject; "Browns Ferry Nuclear Plant Units 1 and. 2 - Electrical Cable Surveillance Program" ).
E le~
PLAN FOR EVALUATION, REPAIR~ AND RETURN TO SERVICE OF BROWNS FERRY UNITS 1 AND 2 (MARCH 22, 1975, FIRE)
Filing instructions for June 16, 1976, Revision.
Remove Zesett Part V, section B", page 15, Part V, section B, page 15, Revised 4/30'/76, Revised 6/9/76