ML021640117
| ML021640117 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/12/2002 |
| From: | Jabbour K NRC/NRR/DLPM/LPD2 |
| To: | |
| References | |
| Download: ML021640117 (28) | |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.
Do not include proprietary materials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 06/12/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-259 Plant/Facility Name Browns Ferry Nuclear Plant, Unit 1 TAO Number(s) (if available)
Reference Meeting Notice 05/30/2002 Purpose of Meeting (copy from meeting notice)
Management meeting to discuss an overview of the actions required for Browns Ferry Unit 1 restart NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Kahtan N. Jabbour Senior Project Manager OFFICE Office of Nuclear Reactor Regulation DIVISION Division of Licensing Project Management BRANCH Project Directorate II, Section 2 Distribution of this form and attachments:
Docket File/Central File PUBLIC PRINTED ON RECYCLED PAPER This form was designed using InForms NRC FORM 65B (9-1999)
Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Restart L
TVA/NRC Meeting Nuclear Reactor Regulation - Rockville, MD June 12, 2002 II
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Agenda Introduction/Meeting Objectives Regulatory History Overview and Schedule Methodology for Special Programs Licensing Actions Generic Communications Licensing Actions of Special Interest Commitment Closure Unit 1 Regulatory Framework Summary and Open Discussion
- Jon Rupert
- Tim Abney
- Jon Rupert/Joe Valente
- Joe Valente
- Tim Abney
- Tim Abney
- Tim Abney
- Tim Abney
- Tim Abney
- Jon Rupert I
Unit 1 Restart - Introduction/Meeting Objectives Objectives of this meeting are:
Provide overview of Unit 1 Restart Project Discuss regulatory history of Units 2 and 3 restarts Present licensing actions, and other reviews that will be needed from NRR Initiate dialogue on Regulatory Framework for Unit 1 restart Jon Rupert 2
Regulatory History Unit 2 Restart All 3 BFN units voluntarily shutdown by TVA in March, 1985 because of safety, regulatory and management issues TVA committed to obtain NRC approval prior to restart of any BFN unit NRC issued a "show cause" letter for all TVA nuclear plants in September, 1985, under 10 CFR 50.54 (f), and requested TVA to specify corrective actions TVA submitted the Nuclear Performance Plan, Volume 3, in August, 1986 outlining the steps needed to recover the BFN units, specifically directed to Unit 2 TVA and NRC conducted several meetings and TVA made several submittals to fully define the regulatory actions needed to restart BFN Unit 2 NRC issued NUREG 1232, Volume 3, Supplement 2 in January, 1991, concluding that TVA's actions acceptably addressed deficiencies in BFN NRC approved Unit 2 restart on May 23, 1991 Unit 2 restarted on May 24, 1991 Tim Abney 3
Regulatory History LLAJ Unit 3 Restart TVA proposed regulatory framework for restart of Units 1 and 3 in July, 1991, outlining improvements from the Unit 2 precedent NRC approved framework proposed by TVA in April, 1992 Unit 3 restart effort dealt primarily with resolving Special Programs, as the management issues had been resolved for Unit 2 restart NRC staff issued SECY-95-264 recommending restart of Unit 3 on November 1, 1995 NRC approved Unit 3 restart on November 15, 1995 Unit 3 restarted on November 19, 1995 Tim Abney 4
Regulatory History Unit 1 Based on Energy Vision 2020 recommendations, TVA decided to delay decision on Unit 1 restart Unit 1 was removed from the NRC's problem plant list on June 21,1996 based on commitments from an April 16, 1996 TVA letter to:
"* Implement same special programs on Unit 1 that were done for Unit 3
"* Not restart Unit 1 without prior approval of NRC Tim Abney 5
Overview and Schedule Egg.
Detailed Scoping, Estimate and Planning (DSEP)
Extensive effort to support Unit 1 restart decision Utilized key TVA personnel with both discipline expertise and experience on restart of units 2 and 3 Results in organizational structure and strong team in place for recovery effort
- Unit 1 Restart Principles BFN units will be operationally the same at completion of Unit 1 Restart Unit 1 Restart activities will use plant processes and procedures when available 6
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Overview and Schedule Workscope Required for Unit 1 Restart Special Programs using criteria consistent with Unit 3 Restart Design changes since Units 2/3 restart Future design changes in 5 year BFN Project Plan Corrective/Preventive Maintenance Regulatory Issues Licensing Actions Inservice Inspection Joe Valente 7
Methodology for Special Programs Special Program Differences in Unit 1 vs. Unit 3 Approach Configuration Managenmt None Design Calculations None Equipment Qualification None Seisnic Design None Fire Protection Improvement None Instrnrt Sensing Lines None Wall Thinning None PRA Not Required Compnent & Piece Part Qualification None Electrical Issues None Q-List None MELB None Platfonrm Thermal Growth None IGSCC Complete replacement of recirculation piping Coa*ings None Restart Test None Plant Welding Not Required Heat Code Traceability Not Required 8
Joe Valente
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EPU SUBMITTAL RISK INFORMED ISI SUBMITTAL OPERATOR TRAINING SPAE/SPOC TURNOVER AREA TURNOVER PLANT ACCEPTANCE 5.5'.5..S:.::s.:
OPERATIONAL READINESS REVIEW NRC TESTING NOTIFICATION LICENSING TO NOTIFY NRC OF FUEL LOAD FUEL LOAD TURBINE GENERATOR ON TURNING GEAR NCR APPROVAL FOR RESTART POWER ASCENSION TESTING TVA BFN UNIT-1 MAJOR MILESTONES S© Primavera Systems, Inc.
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Licensing Actions Technical Specifications Changes/License Amendments High Range Primary Containment Radiation Monitors Power Range Neutron Monitor (PRNM) Upgrade With Implementation of Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) TS ARTS/MELLL 14 Day Allowable Outage Time for Emergency Diesel Generators Extended Power Uprate Operation 24 Month Fuel Cycle Crediting of Containment Overpressure for Net Positive Suction Head Calculations for Emergency Core Cooling Pumps Change Setpoint of Scram Discharge Volume PT Curves Safety Limit Minimum Critical Power Ratio (SLMCPR)
Allowable Value for Reactor Vessel Water Level - Low, Level 3 Oscillation Power Range Monitor (OPRM)
Main Steam Isolation Valve (MSIV) Leakage Rate Limits and Exemption from 10 CFR 50 Appendix J Excess Flow Check Valve Surveillance Intervals Containment Air Dilution (CAD) AOT Alternative Source Term Miscellaneous I & C Changes 10 Tim Abney
Licensing Actions Relief Requests Inservice Inspection Program - 11 requests for relief including one which provides for permanent deferral of examinations for circumferential shell welds of the RPV Containment Inspection Program - 5 requests for relief System Pressure Test (SPT) Program - 6 requests for relief Programmatic Relief Requests - 5 requests for relief Risk-Informed ISI Program - 1 request for relief A....,1 11111 /
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Generic Communications L"i Bulletins 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE 88-04 Potential Safety Related Pump Loss 90-01 Loss of Fill Oil in Rosemount Transmitters 93-02 Debris Plugging of Emergency Core Cooling Suction Strainers 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool Cooling Mode 12 Tim Abney
Generic Communications Generic Letters 88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping 88-20, S4 Individual Plant Examination of External Events for Severe Accident Vulnerabilities 89-13 Service Water System Problems Affecting Safety Related Equipment 92-01 Reactor Vessel Structural Integrity 94-02 Long Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs 94-03 Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs 95-07 Pressure Locking and Thermal Binding of Safety Related and Power-Operated Gate Valves 96-06 Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions 97-04 Assurance of Sufficent Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps 98-04 Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss of Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment 13 Tim Abney
Generic Communications
- NUREG-0737 (TMI Action Plan) Action Items I.D.1 I.D.2 II.B. 2 II.B.3 II.E.4.2.1-4 II.F.1.2.C II.F.1.2.D II.F. 1.2.E II.F.2.4 II.K.3.13 II.K.3.18 II.K.3.28 Control Room Design Review Safety Parameter Display Console Plant Shielding Post-Accident Sampling System Containment Isolation Dependability - Implement Diverse Isolation Accident - Monitoring - Containment High Range Radiation Accident - Monitoring - Containment Pressure Accident - Monitoring - Containment Water Level (Generic Letter 84-23) - Instrumentation for Detection of Inadequate Core Cooling HPCI/RCIC Initiation Levels ADS Actuation Modifications Qualification of ADS Accumulators 14 Tim Abney
Licensing Actions of Special Interest Emu License Renewal Extended Power Uprate Unit 1 license condition to provide analysis for Technical Specifications changes since 1985 Tim Abney 15
Commitment Closure 268 total open Unit 1 commitments 68 associated with Generic Communications 70 from LERs, violations and inspections 9
130 from other miscellaneous sources These will be evaluated in accordance with NEI 99-04 for potential decommitments Tim Abney 16
Unit 1 Regulatory Framework "Regulatory Framework will include:
Summary of Special Programs Submittals required Concurrent licensing actions for all 3 units, where applicable Commitment closure process Actions needed for NRC restart approval
"* TVA intends to submit proposed Regulatory Framework document by December 31, 2002 Tim Abney 17
Summary and Conclusions 18 Jon Rupert
BFN UNIT 1 PROJECT PLAN PRIORITY ISSUES...............................................................................................................................................................
2 INSPECTIONS......................................................................................................................................................................
2 M EETINGS IVISITS...............................................................................................................................................................
2 PENDING NRC ACTIONS....................................................................................................................................................
2 TECHNICAL SPECIFICATIONS..........................................................................................................................................
3 SUBMITTALS.......................................................................................................................................................................
4 NRC COMMITMENTS...................................................................................................................................
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BFN UNIT 1 PROJECT PLAN Page 2 PRIORITY ISSUES TVA SUB NRC ISSUE DATE NRC RESP TVA DATE APPROVAL MGR DATE INSPECTIONS INSPECTION INSPECTION NRC CONTACT TVA DATE PROCEDURE CONTACT MEETINGSNISITS MILESTONE DATE CONTACT (NRC, TVA CONTACT INPO, NEIL, ANI)
NRR - Unit 1 Restart Overview @ Rockville 6/12/02 K. Jabbour T. Abney NRR - License Renewal @ Rockville 7/24/02 K. Jabbour M. Morrison 2
Page 3 BFN UNIT 1 PROJECT PLAN TECHNICAL SPECIFICATIONS TVA CONTACT SUBMITTAL FED REG TVA NEED DATE DATE DATE Containment Air Dilution (CAD) AOT 3Q/03 Excess Flow Cljeck Valve Surveillance 3Q/03 Intervals High Range Primary Containment Radiation 4Q/03 Monitors PT Curves 4Q/03 Crediting of Containment Overpressure for Net 1 Q/04 Positive Suction Head Calculations for Emergency Core Cooling Pumps Allowable Value For Reactor Vessel Water 1 Q/04 Level - Low Level 3 Oscillation Power Range Monitor (OPRM) 2Q/04 Main Steam Isolation Valve (MSIV) Leakage 2Q/04 Rate Limits and Exemption From 10 CFR 50 Appendix J SDIV Setpoint Change 2Q/04 14-Day Allowed Outage Time for Emergency 2Q/04 Diesel Generators Power Range Neutron Monitor (PRNM) 3Q/04 Upgrade with Implementation of Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) TS ARTS/MELLL Miscellaneous I & C Changes 3Q/04 24 Month Fuel Cycle 3Q/04 Alternative Source Term 4Q/04 Extended Power Uprate Operation 3Q/05 Safety Limit Minimum Critical Power Ratio 4Q/05 (SLMCPR)
Page 4 BFN UNIT 1 PROJECT PLAN SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE Description Input Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment I ic Due Date to Date to Date to Date to Date Eng Concur Concur Signature Signature 1
Regulatory 4Q/02 Framework 2
GL 88-01 NRC 1 Q/03 Position on IGSCC in BWR Austenitic Stainless Steel Piping 3
GL 94-03 Part 1 Intergranular Stress 1Q/03 Corrosion Cracking Part 2 of Core Shrouds in 3Q/03 BWRs 4
Inservice Inspection 2Q/03 (ISI) Program Relief Requests 5
Containment 3Q/03 Inspection Program Relief Requests 6
System Pressure 3Q/03 Test (SPT) Program Relief Requests 7
Programmatic Relief 4Q/03 Requests 8
BL 93-02 Debris 1 Q/04 Plugging of Emergency Core Cooling Suction Strainers
Page 5 BFN UNIT 1 PROJECT PLAN SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE E
DAT AN INPUT DUE Description Resp Org Input Rec'd Sch'd Date to Concur Actual Date to Concur Sch'd Date to Signature Actual Date to Signature Due Date Comment Lic Eng I _________________
__________________________ £ _________________ J _________________
_____________________ 4. _____________________
BL 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool BL 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE I Q/04
-4 1
I 2Q/04 11 BL 88-04 Potential 2Q/04 Safety Related Pump Loss 12 GL 89-13 Service 2Q/04 Water System Problems Affecting Safety Related Equipment 13 GL 94-02 Long 2Q/04 Term Solutions Thermal-Hydraulic Instabilities in BWRs 14 BL 90-01 Loss of Fill 3Q/04 Oil in Rosemount Transmitters Input Due
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4 4-4
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Page 6 BFN UNIT I PROJECT PLAN SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE Description Input Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment Lic Due Date to Date to Date to Date to Date Eng Concur Concur Signature Signature 15 GL 95-07 Pressure 3Q/04 Locking and Thermal Binding of Safety-Related and Power-Operated Gate Valves 16 GL 96-06 Assurance 3Q/04 of Equipment Operability and Containment Integrity During Design Basis Accident Conditions 17 GL 97-04 Assurance 3Q/04 of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps 18 GL 98-04 Potential 4Q/04 for Degradation of the Emergency Core Cooling Systems Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment
Page 7 BFN UNIT 1 PROJECT PLAN SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE Description Input Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment Lic Due Date to Date to Date to Date to Date Eng Concur Concur Signature Signature 19 Risk-Informed 3Q/05 Inservice Inspection Program 20 GL 88-20, S4 4Q/05 Individual Plant Examination of External Events for Severe Accident Vulnerabilities 21 GL 92-01 Reactor 4Q/05 Vessel Structural Integrity
Page 8
NRC COMMITMENTS - TOTAL OPEN (14) - FOUR-WEEK LOOK AHEAD None CCTS Number Originating Lead Coord.
Closure TVA Due Commitment Description Lic Document Pkg Due to Date Eng.
Lic 1None s:lic/everyone/Project Plan Unit 1/020614 Unit 1.doc