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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
[Table view] |
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CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM {RIDS)
ACCESSION NBR:9810080119 DOC.DATE: 98/09/30 NOTARIZED: NO FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee DOCKET 05000259 I
50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E.
RECIP NAME Tennessee Valley Authority RECIPIENT AFFILIATION a2 r Records Management Branch (Document Control Desk)
SUBJECT:
Forwards listed revised EPIPs IAW 10CFR50,App E,Section V for Browns Ferry Nuclear Plant.Rev date for changes is 980924.
T DISTRXBUTION CODE: A045D COPXES RECEXVED:LTR ENCL SIZE: Q TITLE: OR Submittal: Emergency Preparedness Plans, Implement ' Procedures, NOTES: G RECIPIENT COPIES RECIPIENT COPIES XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3-PD 1 1 DEAGAZIO,A 1 1
'NTERNAL: AEOD/HAGAN,D 1 1 LE CENTER 0 2 2 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRA'CT'RC 1 1 EXTERNAL: NOAC. 1 1 PDR 1 1 E
N NOTE TO ALL "RIDS" RECIPIENTS:
EAS HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9
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Tennessee Valley Authority, Post Office Sox 2000, Decatur, Alabama 36609-2000 September 30, 1998 10 CFR 50 Appendix E U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentleman:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR'PLANT (BFN) UNITS 1, 2, and 3 EMERGENCY PLAN. IMPLEMENTING PROCEDURE (EPIP) REVISIONS TVA is submitting this notification in accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, to provide NRC with the following EPIP revisions: (1) EPIP Index, (2) EPIP 1 Revision 23, and (3) EPIP 5 Revision 25.
The revision date for the changes is September 24, 1998. TVA requests that your controlled copies be updated within 30 days of the revision dates as noted on the transmittal/receipt acknowledgment sheet.
The enclosed information is being sent by certified mail. The
. signed receipt signifies that you have received this information and will be taken's verification that the NRC copy of the procedures have been updated, and the superseded material has been destroyed.
98i0080ii9 980930 05000259; PDR ADQCK F ca@ g.
U.S. Nuclear Regulatory Commission Page 2 September 30, 1998 If you have any questions, please telephone me at (256) 729-2636.
cerely ney Manager of 'cens'ng and Ind stry Af irs
'I, Enclosures cc (Enclosures):
NRC Resident Inspector (Enclosures provided by BFN Browns Ferry Nuclear Plant Document Control Unit) 10833 Shaw Road Athens, Alabama 35611 Mr. H. O..Christensen, Branch Chief (2 copies)
U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street S.W.
Suite 23T85 Atlanta, Georgia 30303 Mr. A. W.,DeAgazio, Project Manager (w/o Enclosures)
U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
GENERAL REVISIONS GENERIC FILING INSTRUCTIONS FILE DOCUMENTS AS FOLLOWS:
PAGES TO BE REMOVED PAGES TO BE INSERTED EPIP INDEX (ALL) EPIP INDEX (ALL)
EPIP -1 REVISION 22 (ALL) EPIP -1 REVISION 23 (ALL)
EPIP -5 REVISION 24 (ALL) EPIP -5 REVISION 25 (ALL)
Browns g'erry Nuclear Plant Page 1 Curator Procedu Folder Screen status~ACTIVE ProcTyp P Doc Type~PROCEDURE 0 /98 Sorted Type Eff Dt Group Unit Proc Type Proc Number Doc Type Title Doc Stat Section REV 0 EPIP EPIP-1 PROCEDURE EMERGENCY PION CLASSIFICATION 07/27/1998 OTHER 022 LOGIC ACTIVE REP ACTIVE 0 EPIP EPIP.-10 PROCEDURE MEDICAL EMERGENCY PROCEDURE 07/09/1998 OTHE 019 ACTIVE RE ACTIVE 0 EPIP EPIP-11 PROCEDURE SECURITY AND ACCESS CONTROL 09/15/199 OTHER 007 ACTIVE REP ACTI 0 EPIP EPIP-13 PROCEDURE RADIOCHEMICAL LABORATORY 09 5/1995 OTHER 006 PROCEDURE CTIVE REP ACTIVE 0 EPIP - EPIP-14 PROCEDURE RADIOLOGICAL CONTROL PRO 11/17/1997 OTHER 013 ACTIVE REP ACTIVE 0 EPIP EPIP-15 PROCEDURE EMERGENCY EXPO URE 06/26/1996 OTHER 005 ACTIVE REP ACTIVE 0 EPIP EPZP-16 PROCEDURE TERMI ON AND RECOVERY 11/01/1995 OTHER ~ 003 PROC URE ACTIVE REP ACTIVE 0 EPZP EPZP-17 PROCEDURE RGENCY EQUIP ?g AND SUPPLIES 07/14/1998 OTHER 022 (INVENTORY AND OPERABILITY ACTIVE REP PROCEDURE) ACTIVE 0 EPZP EPIP-2 PROCE RE NOTIFICATION OF UNUSUAL EVE 05/12/1997 OTHER 020 ACTIVE REP ACTIVE 0 EPZP EPIP-20 PROCEDURE PLANT DATA 06/14/1996 OTHER 009 ACTIVE'EP ACTIVE 0 EPIP EPIP-21 PROCEDURE FIRE EMERGENCY PROCEDURE 06/25/1997 OTHER 002 ACTIVE REP ACTIVE 0 EPIP EPIP-3 PROCEDURE ALERT 05/12/1997 OTHER 023 ACTIVE REP ACTIVE 0 EPZP PZP-4 PROCEDURE SITE AREA EMERGENCY 05/12/1997 OTHER 022 ACTIVE REP ACTIVE
Brows Ferry Nuclear Plant Page 2 Curator Procedures Folder Screen pg10lcc status~ACTIVE ProcType~EPIP Doc Type=PROCEDURE 07/27/98 Sorted hy Type Eff Dt Group Unit Proc Type Proc Number Doc Type Title Doc Stat Section i REV 0 EPIP EPIP-5 PROCEDURE GENERAL EMERGENCY 05/12/1997 OTHER 024 ACTIVE REP ACTIVE 0 EPIP EPIP-6 , PROCEDURE ACTIVATION AND OPERATION OF THE 11/20/1996 OTHER 017 TECHNICAL SUPPORT CENTER (TSC) ACTIVE REP ACTIVE 0 EPIP E PIP-7 PROCEDURE ACTIVATION AND OPERATION OF THE 11/20/1996 OTHER 017 OPERATIONS SUPPORT CENTER (OSC) ACTIVE REP ACTIVE 0 EPIP EPIP-8 PROCEDURE PERSONNEL ACCOUNTABILITYAND 11/17/1997 OTHER 010 EVACUATION ACTIVE REP ACTIVE
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TENNESSEE VALLEYAUTHORITY 4
BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTINGPROCEDURE EPIP-5 GENERAL EMERGENCY REVISION 24 PREPARED BY: A. H. FELTMAN PHONE: 3666 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: MASOUD BAJESTANI DATE: 04/17/97 EFFECTIVE DATE: 05/12/97 LEVEL OF USE: REFERENCE USE VALIDATIONDATE: NOT REQUIRED QUALITY-RELATED 0733104394 BFNP EPIP EPIP" 5 051297 24
REVISION LOG Procedure Number: EPIP-5 Revision Number: 24 Pages Affected: 1-4, 7, 8, 9 Description of Change:
IC-29 THIS PROCEDURE REVISION ZS BEING CONDUCTED TO UPDATE TELEPHONE NUMBERS, PROVIDE CLARIFING INFORMATION REGARDING THE NOTIFICATION OF THE ODS AND STATE OFFICIALS, CLARIFY INFORMATION REGARDING PERIODIC EVALUATIONS, HUMAN FACTOR THE NOTIFICATION ZNFORMATIN REGARDING THE ACTION OF PORTECTIVE ACTION RECOMENDATIONS.
GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT
'l.0 PURPosE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as a GENERAL EMERGENCY (GE).
1.2 Provide for periodic evaluation'of the current situation by the Shift Manager/SED to determine whether the GE should be terminated, or continued.
2.0 ScoPE This procedure applies to emergency events that are classified as General Emergency by EPIP-1, Emergency Classification Procedure.
PAGE 1 OF 11 REVISION 24
GENERAL BROWNS FLURRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INsTRUcTioNs NoTE: IF ALL EMERGENGY CENTERs ARE STAFFED STEPs 3.'I THRU 3.2 Do NoT APPLY. (NIA STEPs IF NQT APPLIGABLE) 3.1 Notification of the 0 erations Dut S ecialist ODS & Emer enc Res onders Note: The ODS should be notified within 5 minutes after the emergency event is declared.
Date:
3.1.1 ~Com tete Attachment A (Notification Information).
INITIALS TIME 3.1.2 Direct the Unit 1, Unit Operator to make notifications from Attachment 8 (Unit 1, Unit iNITIALS TIME Operator Notification) 3.1.3 ~Motif the ODS and Provide the information from INITIALS TIME Attachment A.
Note: Utilize the direct ring-down ODS phone when making this notiTication or as applicable dial direct.
ODS Telephone Numbers 5-751-1700, 2495 If the ODS cannot be reached within 10 minutes, Then contact the following and Provide the information from Attachment A:
- 1. Limestone County: 9-232-0111 INITIALS TIME
- 2. Nlorgan County: 9-1-205-353-2515 INITIALS TIME
- 3. Lawrence County: 9-1-205-974-7641 INITIALS
- 4. Lauderdale County: 9-1-205-760-9117 INITIALS TIME
- 5. State of Alabama Rad Health Duty Officer: INITIALS TIME Day Shift 8 a.m. - 5 p.m.
9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 PAGE 2 OF ll REVISION 24
.GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INsTRUGTIQNs (CoNTINUED) 3.1.4 Fax a copy of Attachment A to the ODS for INITIALS TIME confirmation of information or the state if contacted directly.
ODS Fax AL Rad Health 5-751-8620 9-1-334-206-5387 3.1.6 Receive confirmation call from the ODS (to verify TIME notification of the State of Alabama), (N/A this step if the State was contacted directly).
3.2 NoTIFIcATIQN oF SITE PERsoNNEL 3.2.1 Make the following plant P.A. announcement:
INITIALS TIME THIS IS (NAME), SHIFT MANAGER. A GENERAL EMERGENCY HAS BEEN DECLARED ON UNIT
. I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME!
3.3 AccoUNTABILITYAND EVAcUATIoNoF NQN-EMERGENGY RESPONDERS Note: Prior to sounding the Evacuation Alarm notify Nuclear Security. If the TSC is staffed notify the TSC Security Manager. If the TSC is not staffed or the TSC Security Manager position has not been filled then call 3629 or 7830.
3.3.1 Activate the Accountability Alarm, if not previously sounded. (Reference EPIP-8) (N/A STEP IF NQT iNITIALS TIME APPLICABLE) 3.3.2 When accountability is complete, Conduct evacuation of non-emergency responders by iNITIALS TIME activating the Evacuation Alarm, if not previously sounded. (N/A STEP IF NQT APPLIGABLE)
PAGE 3 OF 11 REVISION 24
GENERAL BROWNS FLURRY EPIP-5
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EMERGENCY NUCLEAR PLANT 3.0 INsTRUcTIoNs (CoNTINUED) 3.4 DosE AssEssMENT 3.4.1 Evaluate the need for offsite dose assessment.
(NIA STEP IF NQT APPLIGABLE) INITIALS TIME 3.4.1.1 When offsite dose assessment is required Obtain the information from the CECC when operational.
3.4.1.2 If the CECC is not operational, Contact the TSC, when staffed or the RADCON Shift Supervisor and ~Re uest the implementation of EPIP 14, for dose assessment.
3.5 NQTIFIGATIQN oF THE NRC 3.5.1 ~Motif the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if requested by the NRC maintain an open and INITIALS TIME continuous communications channel.
Note; Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, using all 10 digits. If the number is busy, Then select in order, the alternate numbers until a connection is achieved.
Note: If the ENS phones are out-of-service, Then dial direct utilizing the TVA phone system by dialing 9-1-the number listed on the ENS telephones.
No access codes are required.
PAGE 4 OF 11 REVISION 24
GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INsTRUcTioNs (CoNTINUED) 3.6 PRoTEGTIvE AGTIQN REcoMMENDATIQN 3.6.1 If the CECC is not staffed Then make a Protective Action Recommendation (PAR) using INITIALS TIME Attachment D. (This PAR shall be made only by the SED.) (N/A STEP IF NQT APPLIGABLE) 3.7 EMERGENGY REsPoNsE TEAM NoTIFIGATIQNs 3.7.1 If the following emergency centers are staffed, Then notify the following of the current emergency INITIALS TIME classification and plant conditions.
(N/A STEP IF NQT APPLIGABLE)
~ CECC ~ OSC
~ TSC ~ CONTROL ROOMS
~ PLANT PA ANNQUNGEMENT 3.8 PERIQDIc EUALUATIQNoF THE EvENT 3.8.1 Continue to Evaluate the event using EPIP-1 as conditions warrant.
Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred.
3.8.2 If the CECC is not staffed, Then notify the ODS and provide the current plant status. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8 a.m. - 5 p.m. Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 PAGE 5 OF 11 REVISION 24
GENERAL BROWNS FERRY EPIP-5
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EMERGENCY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 PERIQDIG EvALUATIQNoF THE EvENT(CQNTINUED) 3.8.3 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure.
3.8.4 After the evaluation has been completed, if staffed ~Nottf the following of the status:
~ CECC ~ OSC
~ NRC (ENS) ~ CQNTRQL RooMs
~ TSC ~ PLANT PA ANNQUNGEMENT 3.8.5 Document the completion of the evaluation by log entry.
3.8.6 Re-enter this procedural section as conditions warrant at step 3.8.1 or until directed to exit this procedure by steps 3.8.3.
3.9 CLosURE oF THE GENERAL EMERGENGY 3.9.1 ~Uon termination of the General Emergency Send the completed EPIP-5 and all attachments to Emergency Preparedness (EP).
3.9.2 EP shall Forward to the PORC Secretary the completed EPIP and all attachments for review by TIME PORC.
3.9.3 PORC Review Completed.
PORC Chairman DATE
[NRC/C85/28].
3.9.4 After PORC review is completed the PORC secretary shall Forward the signed EPIP-5 with all INITIALs TIME attachments to EP for documentation storage.
PAGE 6 OF 11 REVISION 24
GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 4.0 ATTACHMENTS Attachment A - Notification Information Attachment B - Unit 1, Unit Operator Notification Attachment C - Protective Action Recommendations PAGE 7 OF 11 REVISION 24
GENERAL BROWSES FLURRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENTA (Page 1 of 1)
NOTIFICATION INFORIVIATION Q THIS IS A REAL EVENT THIS IS A DRILL This is at Browns Ferry.
Name There has been a GENERAL EMERGENCY declared at Browns Ferry affecting:
Q Unit1 Unit 2 Unit 3 Q Common EAL Designator:
Brief Description of the Event:
Plant Conditions:
Q Stable Deteriorating Radiological Conditions:
Q No Abnormal Releases Offsite Q Airborne Release Offsite Q Liquid Release Offsite Q Release Information Not Known Event Declared: Time: Date:
Event Terminated: Time: Date:
The following Protective Action Recommendation (PAR) is provided (PAR Required for General Emergency).
Q Recommendation 1 - Evacuate 2 mile radius and 10 miles downwind and shelter remainder of 10 mile EPZ.
Q Recommendation 2 - Evacuate 2 mile radius and 5 miles downwind and shelter remainder of 10 mile EPZ.
Q Recommendation 3 - Evacuate 2 mile radius and shelter remainder of 10 mile EPZ.
Q Recommendation 4- Shelter 2 mile radius and shelter 5 miles downwind.
The Meteorological Conditions are:
Wind Speed: Wind Direction From:
Please re eat the information ou have received to ensure accurac PAGES OF 11 REVISION 24
BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENTB (Page 1 of 2)
Unit 1, Unit Operator NOTIFICATION Date: I I
- 1. 'Activate the Automatic Paging System (APS).
INITIALS TIME Note: See Instructions in EPIP-6 Callout List (List will be maintained by the EP Manager)
Important: If the APS does NOT activate, Call the ODS (5-751-1700 or 5-751-2495) to activate and notify the SED immediately.
- 2. ~Notif the Unit Supervisor's on shift.
INmALS TIME
- 3. ~Notif Nuclear Security Shift Supervisor and state "A GENERAL EMERGENCY HAS BEEN INITIALS TIME DECLARED," and direct to activate EPIP-11, Security and Access Control.
Plant Extension 3629 or 7830
- 4. ~Notif the Chemistry Lab Supervisor and state "A INITIALS TIME GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-13, Radiochemical Laboratory Procedure.
~ Plant Extension 2367 or 2368
- 5. ~Notif the RADCON Shift Supervisor and state "A INITIALS GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 2300 or 3104 PAGE 9 OF 11 REVISION 24
+ s GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENTB (Page 2 of 2)
Unit 1, Unit Operator NOTIFICATION Date: I I
- 6. '~Motif the "On-Call" MRC Resident and state "A GENERAL EMERGENCY HAS BEEN INITIALS TIME DECLARED," per BFN-EPIP-05.
~ Plant Extension 2572 [Secretary]
or from weekly duty list
- 7. IF the APS did not operate properly, Make notifications from the current duty list. If the IH<TNLS TIME individuals on the duty list cannot be contacted, INake notifications from the EPIP-6 Call Out List.
~Motif the SED of the condition.
PAGE 10 OF 11 REVISION 24
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GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENTC (Page 1 of 1)
PROTECTIVE ACTION RECOMMENDATIONS General Emergency Dcclarod NOTES Projected IF Conditions Are not known, or Measured Dose YES Qt Greater Than or Equal
'Ihcn Answer No. to the Table I Limits at ot beyond Qr CONIINUB ASSBSSMBNT. S htILES RECOMMENDATIONI Modifyprotective actions based EVACUATE2 Mila radar on available plant and field and to Miles downw/nd monitoring infomaiion. Locate NO and and evacuate addluonal Iocahzcd SIIELTER taualnder ef hot spots. IO Mile EPZ Indications of Severe Core YBS (Q When Dose Asscssmcnt Projections Damage Greater Than OR or equal to the Actual Measured Exposures Values in are not known, a stack release rate Table 2 of> 1.3 El I uCi/ace noble gas can be utilized to mcct the condition of I Rcrn/hr External Dose at the site NO boundary.
Is there loss of YBS Physical Control of the Facility TABLE I NO RA D IOA CTI VITY RELEASE DOSE TYPE I IMIT Projeoted or hteasured Dose YBS 3i9 B-6 uCI/cc OreaterThan or Equal of Iodine 131 to thc Table I Limits Measured at or beyond I REM/hr Bxtcrnal Dose 2 hllLES RECOhlhIENDATION Projected 5
IRBM TBDB RBM Thyroid CDB O's NO Prcjeoted or Measured Dose Oroaier Than or Equal YBS EVACUATE 2 mile radius and 5 Mila doanwind and SIIELTER rauainder of IO Mile EPZ to the Tabt ~ I Limits at or beyond SITE BOUNDARY RECOMhIENDATION EVACUATE2 Mde rad/us TABLE 2 and SI tEL'IERrenudnda of INDICATIONS NO 10 htile EPZ
- 1. Fuel Not Covered And Stcam Cooling Entcrcd (BOI~) or Primar Containm<<nt Flooding Entered (BOIH).
RECOMh'IENDATION
- 2. Unit 2- cll Radiation Exceeds 270 R/hr on 2- 272 or 2-EM*90-273.
Unit 3 Drywcll Radiation Excccds 90 R/hr on SIIELTER2 Mileradius and 3-RM-90.272 or 3-RM-90-273. SIIELTER 5 hQa downviind
- 3. EquiTibrium Reactor Coolant Acthlty of
> 300 uCi/ Dose uivslcnt Iodine.
LAST PAGE PAGE 11 OF 11 REVISION 24
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