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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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IUA Tennessee Valley Authortty,1101 Market Street, Chattanooga Tennessee 37402-2801 March 19, 1997 U.S. Nuclear Regulatory Commission ATTN: Chief, Emergency Preparedness Section Region II ,
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Gentlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) - 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS l', 2, AND 3 - GOALS AND OBJECTIVES FOR THE JUNE 1997 RADIOLOGICAL EMERGENCY PLAN (REP) EXERCISE Enclosed are TVA's goals and objectives for the June 1997 BFN REP exercise. These goals and objectives are being submitted in accordance with a July 22, 1994, NRC letter which specified the objectives be submitted 75 days prior to the exercise.
The BFN exercise is currently scheduled for the week of June 2, 1997.
If you have any questions, please telephone Eyerett Whitaker at (423) 751-6369.
Sincerely, l s
/
/ N Raul R. Baron .j General Manager Nuclear Assurance and Licensing Enclosure cc: See page 2 9703250013 970319 o40049 PDR ADOCK 05000259 F PDR lE. IlEE, E!llElElll$lEllE.
. ...... qm Pmend on recycted paper
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Chief, Emergency Preparedness Section
'Page 2 Pbrch 19,.1997 I
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, U.S. Nuclear Regulatory Commission -
ATTN: Document Control Desk Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 ;
l Mr. J. F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike i Rockville, Maryland 20852 -
NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 l l
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ENCLOSURE 4
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2 AND 3 l 1
GOALS AND OBJECTIVES FOR THE JUNE 1997 l RADIOLOGICAL EMERGENCY PLAN EXERCISE '
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. The Radiological Emergency Plan Exercise will be a full scale exercise consisting of the following participation by TVA and State emergency organizations:
. Central Emergency Control Center will fully participate and be evaluated.
. Technical Support Center will fully participate and be evaluated.
. Operations Support Center will fully participate and be evaluated.
. Joint Information Center will fully participate and be evaluated.
. State Emergency Operations Center will fully participate and be evaluated.
. Risk Counties Emergency Operations Centers will fully participate and be evaluated.
. State Field Coordination Center will fully participate and be evaluated.
. State Radiological Monitoring Control Centerwill fully participate and be evaluated.
. State Field Teams will fully participate and be evaluated.
EXERCISE GOALS TVA's goals for the exercise are as follows:
- 1. Allow plant and offsite personnel to demonstrate and test the capabilities of the emergency response organization to protect the health and safety of plant personnel and the general public in accordance with the Nuclear Power- Radiological Emergency Plan (NP-REP), site Emergency Plan Implementing Procedures (EPIPs), and the Central Emergency Control Center (CECC) EPIPs.
- 2. Provide an interactive exercise to ensure proficiency of onsite and offs,ite emergency response capabilities.
3 Provide training for emergency response personnel.
- 4. Identify emergency response capabilities that are in need of improvement or revision.
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- 5. Provide an interactive exercise to allow the State responders to demonstrate their proficiency in 1 emergency response capabilities.
EXERCISE OBJECTIVES l A. Control Room / Simulator
- 1. Demonstrate the ability of the Shift Manager to recognize conditions, classify emergencies, make required notifications in a timely manner, and assume the initial responsibilities of the Site Emergency Director (SED).
- 2. Demonstrate the ability of the Shift Manager to maintain effective command and control of control room activities, perform classification analysis, periodically inform the control room staff of the status of the emergency situation, and provide a precise and clear transfer of responsibilities from the control room to the Technical Support Center (TSC).
- 3. Demonstrate the ability of the control room staff to make timely analysis of the incident, perform mitigating actions, keep onsite personnelinformed of the emergency situation prior to TSC activation.
- 4. Demonstrate the ability of the control room staff to use appropriate radiological emergency procedures, maintain an accurate log of events, and defer problems that cannot be quickly resolved to the TSC for resolution.
- 5. Demonstrate the ability of the control room staff to continuously evaluate information, redefine / confirm conditions and event classifications, and establish an effective flow of information between the Control Room, the TSC, and the Operations Support Center (OSC).
03MS/9710 48 AM Page 1 BFN 1997 Ottectwes
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, B. Technical Support Center (TSC) l
- 1. Demonstrate ability to perform a precise and clear transfer of responsibilities from the control room staff to the TSC staff and assume the primary responsibilities of the Central Emergency Control Center (CECC) until the CECC is activated.
- 2. Demonstrate the SED's ability to provide effective direction, command and control, to manage activities j in a manner that promotes event classification, analysis, or mitigation of an event and to perform periodic briefings forTSC/OSC staff and personnel.
- 3. Demonstrate the ability of the TSC staff to use appropriate procedures, solve problems related to incident identification and mitigation, and maintain an accurate account of events through chronological logs.
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- 4. Demonstrate the TSC's ability to determine the appropriate sampling and monitoring required to support l
accident mitigation, perform timely assessments of onsite redWogic l conditions, and formulate, coordinate, implement, and track on site protective actions.
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- 5. Demonstrate the TSC's ability to maintain effective communication between the OSC, control room, CECC, and various groups within the TSC.
- 6. Demonstrate ability of the TSC to continuously evaluate available information, redefine / confirm plant conditions and event classifications, f.nd if required assemble onsite personnel within the site area.
- 7. Demonstrate the ability of the TSC to effectively communicate with environmental monitoring vans from ,
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the Radcon Lab until the CECC is activated. l 1
C. Operations Support Center (OSC)
Demonstrate the ability of the OSC Manager, through effective command and control, to coordinate and )
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initiate activities in a timely manner, maintain effective communications between various groups with!n the OSC, and use appropriate procedures.
- 2. Demonstrate the ability of the OSC staff to properly plan required tasks and promptly dispatch, track, ,
l and maintain communication with the response teams.
- 3. Demonstrate the ability of the OSC response teams to prepare, respond, make necessary repairs or ,
inspections, and provide an adequate debrief upon retuming to the OSC. l l
- 4. Demonstrate the ability of the OSC staff to maintain accurate status boards, priority boards, team tracking boards, and logs. Also, demonstrate effective transfer of information between the OSC, TSC, Radeon laboratory, and Chemistry laboratory.
- 5. Demonstrate ability of the Radcon personnel to use appropriate procedures and follow Radcon and ALARA practices to ensure adequate worker protection and perform effective inplant surveys.
- 6. Demonstrate ability of the OSC to track changing radiological conditions through survey results and/or inplant monitors, controlintemal and extemal exposures and personnel contamination of onsite emergency workers, and incorporate the information into personnel protective actions and exposure tracking.
D. Central Emergency Control Center (CECC)
- 1. Demonstrate the ability of the Operations Duty Specialist to make initial notifications to State agencies in a timely manner.
- 2. Demonstrate the ability to transfer offsite responsibilities from the TSC to the CECC.
Page 2 03/18/9710 48 AM BFN 1997 objectwes
- 3. Demonstrate the ability of the CECC Director to maintain effective command and control and promote inlemal communications.
- 4. Demonstrate the ability of the CECC to provide emergency classifications, protective action recommendations, plant conditions, and dose assessment information to the State in a timely manner.
- 5. Demonstrate the ability to effectively obtain radiological survey information from the environmental monitoring teams, keep the monitoring teams informed of emergency conditions, and provide them with exposure control.
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- 6. Demonstrate the ability of the CECC staff to use appropriate procedures and equipment, maintain accurate logs, and to periodically evaluate available information and redefine / confirm plant conditions and event classifications.
- 7. Demonstrate the ability of the CECC staff to contact TVA corporate, vendor, or other outside support i resources as appropriate or needed. !
- 8. Demonstrate the ability of the CECC staff to obtain field data needed to develop dose assessments in a ;
timely manner.
- 9. Demonstrate the ability of the CECC staff to establish and maintain effective communication between the various emergency centers.
- 10. Demonstrate the ability of the CECC staff to analyze current plant conditions, identify projected trends, determine the potential consequences, and maintain accurate status board information.
11, Demonstrate the ability to establish and maintain adequate security for the CECC.
E. Exercise Specific
- 1. Demonstrate the ability of the exercise controllers to perform their function without prompting, coaching, or otherwise interfering with the performance of exercise players.
- 2. Demonstrate that personnel participating in the exercise were not pre-positioned prior to commencement.
- 3. Demonstrate that participants did not have undue prior knowledge of scenario details or initiation time.
- 4. The scenario should be technically accurate, anticipate emergency classifications, and be sufficiently difficult to exercise capabilities of the emergency plan.
- 5. Demonstrate the ability to conduct post exercise critiques.
- 6. Demonstrate the adequacy of control room and emergency centers facilities, resources, equipment, and communication systems to support emergency operations.
- 7. Demonstrate the ability to alert and mobilize emergency response center personnel and activation of the emergency centers within approximately one hour.
- 8. Demonstrate the ability to conduct habitability surveys for the TSC, OSC, Control Room / Simulator, and all assembly areas. ,
- 9. Demonstrate the ability to maintain effective communication between the Technical Support Center, Operations Support Center, Central Emergency Control Center, Control Room / Simulator, and NRC.
F. Environmental Monitoring
- 1. Demonstrate the ability of the environmental monitoring teams to effectively utilize procedures to perform dose rate surveys and to collect and analyze radiological samples.
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' 2. Demonstrate the environmental monitoring team's abilities to follow contamination control procedures in field conditions.
- 3. Demonstrate the adequacy of the environmental monitoring vans to support emergency operations.
(monitoring equipment, supplies, communication equipment, etc.)
- 4. Demonstrate the ability of the site to timely and effectively activate and establish communication with environmental monitoring vans.
- 5. Demonstrate ability of the site to timely and effectively transfer control of the environmental monitoring vans to an offsite center.
- 6. Demonstrate ability to effectively dispatch and control radiological / environmental monitoring teams, coordinate with the State when applicable, and obtain, analyze, and utilize meteorological, onsite and offsite radiological conditions, and source term information to develop dose assessments in a timely manner.
- 7. Demonstrate ability of the environmental raonitoring team personnel to monitor their accumulated dose, report their accumulated doses to the Environs Assessor / Field Coordinator, and receive proper authorization for emergency exposures if required.
G. Public Information / Joint Information Center
- 1. Demonstrate the ability of the CECC/ Communications staff to coordingte information with non - TVA agencies prior to the JIC being staffed.
- 2. Demonstrate the ability of the CECC Communications staff to develop timely and accurate news releases.
- 3. Demonstrate the ability of the CECC Information Manager to exercise effective command and control of the overall communications response.
- 4. Demonstrate the ability of the JIC to coordinate public news briefings with State and Federal agencies and provide timely information to the public during periodic JIC briefings.
- 5. Demonstrate the ability of media relations' personnel in the JIC to answer telephone calls from the media professionally and accurately.
- 6. Demonstrate the ability of TVA's public information staff in the JIC to provide timely and accurate information to anyone calling the public information telephone number.
- 7. Demonstrate the ability to provide reasonable media access with minimal impact on emergency response activities.
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- 8. Demonstrate the ability to provide information to the public that is accurate, presented at a meaningful technical level, and take corrective actions for inaccuracies.
- 9. Demonstrate the adequacy of the CECC communication staff facilities, resources, equipment, and communications system to support emergency operations.
H. Fire Emergency Response Team
- 1. Demonstrate that an incident commander is promptly dispatched to the scene of the emergency where he/she demonstrates ability to establish a command post, establish communication with the main control room, and effectively interact with the fire brigade team leader.
- 2. Demonstrate the ability of the fire brigade team to respond to the scene, establish appropriate response sectors / staging areas, and assess the physical situation in a timely manner.
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' 3. The fire brigade team demonstrates adequate fire fighting skills and appropriate use of fire fighting equipment. j l
- 4. The fire brigade leader demonstrates ability to conduct briefings, control the fire scene, and displays i appropriate fire fighting tactics.
- 5. Radeon personnel demonstrates their ability to monitor fire brigade team exposures and provided sufficient radiological information to the incident commander and / or fire brigade team leader, i
- 6. The incident commander and fire brigade team leader demonstrates ability to communicate effectively.
- 7. Security personnel demonstrate their ability to provide sufficient and effective control at the scene of the j fire. I I Post Accident Sampling ]
- 1. Liquid or gaseous samples were collected containing actual or simulated elevated radionuclide levels including the use of the Post Accident Sampling Facility.
- 2. Doses to sampling and analysis personnel do not exceed limits specified in 10CFR20.1201.
- 3. Results of sample analysis are available within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of suspected core damage (given that the reactor and core conditions are such that a representative sample can be taken within that timeframe). i.e.:
sampling is not prudent during the core damage phase orif exercise equipment failures preclude sampling.
J. Termination and Recovery
- 1. If necessary due to the conditions existing at the time of entry into Recovery, a recovery organization l adequate to maintain oversight of remaining activities was designated and a plan was developed on how !
to transition from TSC operations to LRC operations if long term operations are recuired.
- 2. A detailed plan for activities necessary to retum the plant systems to " normal" statur was developed.
- 3. The Control Room, TSC, CECC, NRC, and State were allincluded in discussions ano concurred in the decision to terminate and enter recovery K. NRC Follow-up Items NONE L. The following drills will be conducted during the exercise:
- 1. CECC/ State Communication Drill
- 2. TSC/CECC Communication Drill
- 3. Plant Radeon Drill (In-Plant Radiation Monitoring)
- 4. Plant Radiological Monitoring Drill ( Environs Monitoring )
- 5. Radiological Dose Assessment Drill (CECC)
- 6. Post Accident Sampling Drill 03n8/9710 48 AM BFN 1997 Otyectues Page 5