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Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 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 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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 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 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter 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 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 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 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24151A6322024-05-30030 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 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 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
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NRC FoRM 195 U.S, NUCLEAR REGULATORY C EMISSION DOCKET NUMBEA I2.70) gOy r 50-259It~
FI LE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO Mr ' C; Rusche FROM: TVA DATE OF DOCUMENT Chanttanogga, Tenn. 37401 6<<15-76 J, E, Gilleland DATE RECEIVED 18-76 6
%LETTER QNOTOA IZE 0 PROP INPUT FOAM NUMBER OF COPIES RECEIVED J'
GkoR IGINAL Im UN C LASS I F I E D OCOP Y .signed DEscRIPTION Ltr trans the following: ENcLOBURE /!"44th Revision to "plan for Evalua>>
tion,'Repair, & Return to Service of Browns
'Perry 1 & 2(March 22, 1975) Fire" ~ ~ ~ ~
(45 cys encl record)
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PLANT NAME: Browns Ferry 1 & 2 IIo~~
ASST' kI:me!4M'AFETY FOR ACTION/INFO RMATI ON ASSIGNED AD: ASSI ~liED AD BRANCH CIIXEF:
PROJECT HANAGER: PRO C SNA LXC '.
INTERNAL D ISTR I BUTION G SYSTEMS SAFETY SITE S NRC PDR'&E HEINEIIAN ENV RO ANA S SCHROEDER BENAROYA N OELD GOSSICK & STAFF ENGINEERING IPPOLITO ENV MIPC MACCARRY KIRKMOOD CASE KNXGIlT SIWEXL OPERAT N REAC ORS HA ES PAWLXCKX ROJECT IIANA DIEN REACTOR SAFEXY OPERATIN CH BOYD ROSS EISENH P COLLINS NOVAK SHAO HOUSTON ROSZTOCZY BAER PETERSON CHECK BUTLER 1IELTZ GRII IES HELTEMES AT&X SKOVHOLT SALTZHAN OLL RUTAERG EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: NAT LAB: BROOKIIAVEN N+
TXC: REG; VIE ULRIKSON ORNL N$.ZC. ~ LA PDR 6197 .
ASLB CONSUL'I'ANTS ACRS CYS EN ~ ~
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OgUTIOy 830 Power Building Qgf
,TENNESSEE VALLEY AUTHORITY 0 m CHATTANOOGA. TENNESSEE 37401 cf. Z ,
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JUN 15 >976 I'tie
,R,@tetgy Docket Mr. Benard C. Rusche, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
'~f.4'g) "
Washington, DC, 20555 Ju Nl8>676 ~
Near rector co roraArortr
Dear Mr. Rusche:
r>roe r socrr~
I In the Hatter af the ) Docket Nos. 5 Tennessee Valley Authority ) 0-2 Enclosed are 45 copies of the 44th revision to a document previously submitted on April li, 1975, entitled "Plan for Evaluation, Repair, and Return 'to Service of Browns Ferry Units 1 and 2 (March 22, 1975, Fire)." The gevision consists of the following:
1 Evaluation Plan Materi'al Revised Part Program for Sampling, Analysis, and Cleanup',of Residue on Affected Structures, Systems, and Components This revision includes additional information regarding the surveillance program for electrical cables that have been coated with flame retardant material (Flamemastic 71A).
Instructions. for entering the 44th revision are also included.
C I
Very truly yours, ggCL L L' J. E. Gilleland /
Assistant Manager of Power
~'t t~g Enclosures CC: See page 2 An Equal Opportunity Employer
JUN 15]976 Mr. Benard C. Rusche CC (Enclosures):
Mr. Frank Long Regional Office
'U.S. Nuclear Regulatory Commission 230 Peachtree Street, NM., Suite 818 Atlanta, Georgia 30303 Mr. Norman C. Moseley, Director (3)
Regional Office U.S. Nuclear Regulatory Commission 230 Peachtree Street, %f., Suite 818 Atlanta, Georgia 30303 Mr. Co E. MurPhy Regional Office U.S. Nuclear Regulatory Commission 230 Peachtree Street, NWo, Suite 818 Atlanta, Georgia 30303
. ~ g8gU18tog 'Dock83 FJts PLAN FOR EVALUATION, REPAIR, AND RETURN TO SERVICE OF BROHNS FERRY UNITS 1 AN@ 2 0fARCH 22, 1975, PIRE)
Piling instructions for June 14, 1976, Revision.
Insert Part V, section B, page 37, attachment 5A,, dated 6/9/76
e V ~
Section B Page 37 Attachment 5A Recovery Plan BrÃlP 6/9/76 H. J. Green, Power Plant Superintendent, Browns Perry Nuclear Plant J. B. Calhoun,'hief, Huclear Generation Branch, 702 EB-C BROHi> EL~CTR1CAL CABTZ SUIVTr:ZEJAIiCE PROGRAM w
This memorandum,'~ucplments my memorandum to you dated April 27, 1976, and modifies the test inter'.s sp cificd, 1n that memorandum.
Because of concern of the LtRC that cocooning of the.electrics cables with Planunstic may cause heating and degradation of the cable, TA'<
has coded.tted to.".inspect and test certain celected cable )ac':ets periodic~. An insp ction and test should be cade at the fi"'stand unit 3. refueling outag , at the second uMt 1 refueling outage, thereafter at a~roxhmte3y, 3-year intervals at the nearest unit 1 x'efue31ng outace';
A lcm-voltage ~r'ex cable was selected for sampling since it would continuous3y cary curr"nt of sufficient mgni.udo to produce lo.~-
level heating,'if any. Contro3. and simal cables carry only sms11 intermittent currents which would produce no, or little, heat.
The cable packet~ was selected as the primary indicator of cable degradation. 'Cables PLL1 are s~e conductor, 400-IXM cour, with cross-linseed polyethylene insulation and a pol>-A.nyl chloride 1aczet.
The temperatuxe ratir.-. of the insulat1on is 90' and the tmnerature rating of the,]ac'.sc" is 75 C. Calc~tions baced on the thermal resistance of .t'ice'nsulation, "acket, and appro:M~tcly 100 p rcent of normal current flo;z show that th tern crature differential bet;;con the conductor "nd:~~he'utside of the insu'"ticn is 3.47', and bebreen the conc'uctor'nd the,out"'dc of the gacI:et is 4.73'.
Since the temoeraturc it rath'f the insulation is 15' 1- evident that a~ thex~ degradation,
@eater than if any, of the gacI et, the cable xrl33. be detected first in thc )acket.
J. R. Calhoun, CCF;FVH;C JC
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