ML021720680

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Enclosure 2 (License Handout) (Paper Copy) Re Browns Ferry Nuclear Plant, Unit 1 Restart
ML021720680
Person / Time
Site: Browns Ferry 
Issue date: 06/12/2002
From:
NRC/NRR/DLPM/LPD2
To:
NRC/NRR/DLPM/LPD2
References
Download: ML021720680 (27)
v • d • e


Text

Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Restart TVA/NRC Meeting-.

Nuclear Reýa.qto ulolifi fi`- Rockville, MD June 12 2002 S. "'**""i

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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 I 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 Regulator3 Framework for Unit I restart Jon Rupert 2

Regulatory History

  • Unit 2 Restart All 3 BFN units voluntarily shatdown 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 P1 n, Volume 3, in August, 1986 outlining the steps needed to recover the BFtN 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 3

Tim Abney

Regulatory History U-,.

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 prin

.ly 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 4

Tim Abney

Regulatory History EnW 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 Ao 1-5 Tim Abney

Overview and Schedule MA 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

Jon Rupert

Overview and Schedule LL[

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 7

Joe Valente

Methodology for Special Programs Special Program Configuration Mana it Design Calculations Equipmnmt Qualification Seismnic Design Fire Protection Improvement Instumunt Sensing Lines Wall Thinning PRA Compoent &PiecePart Qualification Electrical Issues Q-List MEfLB Platform Thermal Growth IGSCC Coatings Restart Test Plant Weldin Heat Code Traceability Differences in Unit 1 vs. Unit 3 Approach None None None None None None None Not Reuired None None None None None Complete replacenmmt of recirculation pipinn None None Not Required Not Required 8

Joe Valente

2M2.

2003 SO RD APPROVAL N RD MAJOR CONTRACTS EN NEERING PROGRAMS REQD FOR MODS

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INEERING ISSUE DRYWELL DCWS NR BRIEF OBILIUE MODIFICATIONS SUPPORT TEAM NG LEAD MATERIAL-ORDER MODIFCATIONS - DEMOLITION & NON DCN ACTIVITIES PREPARE & ISSUE BULK MATERIAL ORDER LONG LEAD MATERIAL - DELIVER ENGINEERING ISSUE REACTOR BUILDING OCN'S DESIGN ENGINEERING SUPPORT ENGINEERING ISSUE CONTROL BUILDING DCN'S MODIFICATIONS IMPLEMENT DRYWELL DCN'S CRD:

=70 AL READINESS REVIEW 4IRC TESTING N071FICATION LICENSING TO NOTIFY NRC OF FUEL LOAD FUEL LOAD TURBINE GENERATOR ON TURNING GEAR NCR APPROVAL FOR RESTART POWER ASCENSION TESTING BREAKER CLOSURE

@6 Primuavra2 s~utems Inc F...

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Licensing Actions Technical Specifications Changes/ cense 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 Atbney

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 re( iests for relief Programmatic Relief Request, 5 requests for relief Risk-Informed ISI Program - 1 request for relief 11 Tim Abney

Generic Communications

-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 S1111 M-AVo1y

Generic Communications

  • NUREG-0737 (TMI Action Plan) Action Items LD.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 1.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 Tim Abney 14

Licensing Actions of Special Interest License Renewal

° Extended Power Uprate

° Unit 1 license condition to provide analysis for Technical Specifications changes since 1985 Tim Abney 15

Commitment Closure 0 268 total open Unit 1 commitments 68 associated with Generic Communications 0

70 from LERs, violations and inspections 130 from other miscellaneous sources These will be evaluated in accordance with NEI 99-04 for potential decommitments 16 Tim Abney

Unit 1 Regulatory Framework Eu".

Regulatory Framework will includ(.

Summary of Special Programs Submittals required Concurrent licensing actions for all 3 units, where applicable Commitment closure process Actions needed for NRC restart approval 0

TVA intends to submit proposed Regulatory Framework document by December 31, 2002

-F; A17 I IM 11A111y

Summary and Conclusions Jon Rupert 18

BFN UNIT I PROJECT PLAN PRIORITY ISSUES...............................................................................................................................................................

2 INSPECTIONS......................................................................................................................................................................2 MEETINGSN ISITS...............................................................................................................................................................

2 PENDING NRC ACTIONS....................................................................................................................................................

2 TECHNICAL SPECIFICATIONS..........................................................................................................................................

3 SUBMITTALS.......................................................................................................................................................................

NRC COMMITMENTS...................................................................................................................................

8

2 BFN UNIT 1 PROJECT PLAN Page 2 MEETINGSNISITS

-NRR - Unit 1 Restart Overview @ Rockville NRR - License Renewal @ Rockville CONTACT (NRC, TVA CONTACT INPO, NEIL, ANI)

K. Jabbour T. Abney K. Jabbour M. Morrison MILESTONE DATE 6/12/02 7/24/02 I

Page 3 BFN UNIT I PROJECT PLAN TECHNICAL SPECIFICATIONS TVA CONTACT SUBMITTAL SUBMITTAL DATE FED REG DATE L ________

I ________

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t Containment Air Dilution (CAD) AOT Excess Flow CQeck Valve Surveillance Intervals High Range Primary Containment Radiation Monitors PT Curves Crediting of Containment Overpressure for Ne Positive Suction Head Calculations for Emergency Core Cooling Pumps Allowable Value For Reactor Vessel Water Level - Low Level 3 Oscillation Power Range Monitor (OPRM) 3Q103 L

4 4Q/03 I

v TVA NEED DATE I

I 1Q/04 I

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20/04 4-1 1

2Q04 Main Steam Isolation Valve (MSIV) Leakage Rate Limits and Exemption From 10 CFR 50 Appendix J SDIV Setpoint Change 14-Day Allowed Outage Time for Emergency Diesel Generators Power Range Neutron Monitor (PRNM)

Upgrade with Implementation of Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) TS ARTS/MELLL Miscellaneous I & C Changes 24 Month Fuel Cycle Alternative Source Term Extended Power Uprate Operation FSafety Limit Minimum Critical Power Rýa-tio f

20/04 4

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I 3Q104 3Q1r 30/04 3Q/04 3Q/05 4Q/05

_________________________________I

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3Q/03 3Q/03 4Q/03 4Q/03 1 Q/04 1 Q/04 2Q/04 2Q '04 2Q/04 2Q/04 3Q/04 3Q/04 4Q/05

Page 4 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 IJic ConcuriCocurnSignaure Signaure Due DDate to [Date to Date to Date Eng Due Concur Concur Signature Signature De Regulatory Framework GL 88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping GL 94-03 Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs inservice Inspection (ISI) Program Relief Requests Containment Inspection Program Relief Requests System Pressure Test (SPT) Program Relief Requests Programmatic Relief Requests BL 93-02 Debris Plugging of Emergency Core Cooling Suction Strainers i

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4-II 4-T 1 Q/03 Part 1 1Q/03 Part 2 3Q/03 2Q/03 3Q/03 3Q/03 4Q/03 1 Q104 I

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Page 5 BFN UNIT 1 PROJECT PLAN SUBMITTALS - LOOK AHEAD nI r-nATl Amnl NIDI IT flD IF In ut Re m I r-AN I

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1 ue Li Description Input Due Resp Org Scn'd Date to Concur

/Actual Date to Concur Date to Signature Date to Signature Date Eng

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BL 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool 0 BL 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE I1 BL 88-04 Potential Safety Related Pump Loss 12 GL 89-13 Service Water System Problems Affecting Safety Related Equipment 13 GL 94-02 Long Term Solutions Thermal-Hydraulic Instabilities in BWRs 14 BL 90-01 Loss of Fill Oil in Rosemount Transmitters

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2Q/04 2Q/04 2Q/04 2Q/04 3Q/04 I _____

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Page 6 BFN UNIT I PROJECT PLAN 1=

SUBMITTALS - LOOK AHEAD nl Ir-nATP Amn I IPOI TntFlI rI U1t1,./

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.AUI Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment Lic Oate to Date to Date to Date to Date Eng Concur Concur Signature Signature T

1 12/0ý4 Description Input Due 157GL 95-07 Pressure Locking and Thermal Binding of Safety-Related and power-Operated Gate Valves 19 GL 96-06 Assurance of Equipment Operability and Containmeni Integrity During Design Basis Accident Conditions 17 GL 97-04 Assurance of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps 18 GL 98-04 Potential for Degradation of the Emergency Core Cooling Systems Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment

__ 4.1 tI II 3Q/04 3Q/04 4Q/04 I

______________________ I ______________ I _____________

__________________ j _________________

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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 tojDateEm Due Dte t Dat to ate o Dae toDate E

Concur Concur Signature Signature 19 Risk-Informed 3Q/05 Inservice Inspection Program GL 88-20, S4 Individual Plant Examination of External Events for Severe Accident Vulnerabilities

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GL 92-01 Reactor Vessel Structural Integrity 20 Page

,-21 1 4Q/05 4Q/05 I - - - - -

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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 Eng.

None s:lic/everyone/Project Plan Unit 1/020614 Unit 1.doc

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