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 Tennessee Valley Authority icon.png
Issue date: 06/12/2002
From:
NRC/NRR/DLPM/LPD2
To:
NRC/NRR/DLPM/LPD2
References
Download: ML021720680 (27)
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Text

Tennessee Valley Authority Browns Ferry Nuclear Plant I Unit 1 Restart 7

z TVA/NRC Meeting-.

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

-1*

Enclosure 2

Agenda

"* Introduction/Meeting Objectives - Jon Rupert

- Tim Abney

"* Regulatory History

- Jon Rupert/Joe Valente

"* Overview and Schedule

- Joe Valente

"* Methodology for Special Programs

- Tim Abney

  • Licensing Actions - Tim Abney

° Generic Communications - Tim Abney

  • Licensing Actions of Special Interest - Tim Abney
  • Commitment Closure - Tim Abney
  • Unit I Regulatory Framework - Jon Rupert Summary and Open Discussion 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 2

Jon Rupert

Regulatory History

  • Unit 2 Restart of safety, All 3 BFN units voluntarily shatdown by TVA in March, 1985 because regulatory and management issues TVA committed to obtain NRC approval prior to restart of any BFN unit 1985, NRC issued a "show cause" letter for all TVA nuclear plants in September, under 10 CFR 50.54 (f), and requested TVA to specify corrective actions 1986 TVA submitted the Nuclear Performance P1 n, Volume 3, in August, to Unit 2 outlining the steps needed to recover the BFtN units, specifically directed to TVA and NRC conducted several meetings and TVA made several submittals 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 and 3 in July, 1991, TVA proposed regulatory framework for restart of Units 1 outlining improvements from the Unit 2 precedent

- NRC approved framework proposed by TVA in April, 1992 Programs, as the Unit 3 restart effort dealt prin .ly with resolving Special management issues had been resolved for Unit 2 restart of Unit 3 on November 1, NRC staff issued SECY-95-264 recommending restart 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 on Based on Energy Vision 2020 recommendations, TVA decided to delay decision 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 on restart

- Utilized key TVA personnel with both discipline expertise and experience of units 2 and 3 effort Results in organizational structure and strong team in place for recovery Unit 1 Restart Principles BFN units will be operationally the same at completion of Unit 1 Restart available Unit 1 Restart activities will use plant processes and procedures when 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 Differences in Unit 1 vs. Unit 3 Approach None Configuration Mana it None Design Calculations None Equipmnmt Qualification None Seismnic Design None Fire Protection Improvement None Instumunt Sensing Lines None Wall Thinning Not Reuired PRA None Compoent &PiecePart Qualification None Electrical Issues None Q-List None MEfLB None Platform Thermal Growth Complete replacenmmt of recirculation pipinn IGSCC None Coatings None Restart Test Not Required Plant Weldin Not Required Heat Code Traceability 8

Joe Valente

2M2.. . 2003 ..

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

%*0.\  :

.3...........3...  :

' . *........................\3 ~:

INEERING ISSUE DRYWELL DCWS NR BRIEF OBILIUEMODIFICATIONS 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 ALREADINESS REVIEW 4IRCTESTING N071FICATION LICENSING TO NOTIFY NRC OF FUEL LOAD FUEL LOAD TURBINE GENERATOR ON TURNING GEAR NCR APPROVAL FOR RESTART POWER ASCENSION TESTING BREAKER CLOSURE

+ , ,,,,,*.+,* +I+ ...... , .....

@6 Primuavra2

..- s~utems .Inc F... . . J_______

Licensing Actions Technical Specifications Changes/ cense Amendments High Range Primary Containment Radiation Monitors Monitor Power Range Neutron Monitor (PRNM) Upgrade With Implementation of Average Power Range (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 for Emergency Core Crediting of Containment Overpressure for Net Positive Suction Head Calculations 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) 50 Appendix J Main Steam Isolation Valve (MSIV) Leakage Rate Limits and Exemption from 10 CFR 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 of the RPV for permanent deferral of examinations for circumferential shell welds 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 GE 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by 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 Suppression Pool Cooling Mode 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in 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 Control Room Design Review I.D.2 Safety Parameter Display Console II.B.2 Plant Shielding II.B.3 Post-Accident Sampling System II.E.4.2. 1-4 Containment Isolation Dependability - Implement Diverse Isolation II.F. 1.2.C Accident - Monitoring - Containment High Range Radiation II. F.1.2.D Accident - Monitoring - Containment Pressure 1.F. 1.2.E Accident - Monitoring - Containment Water Level II.F.2.4 (Generic Letter 84-23) - Instrumentation for Detection of Inadequate Core Cooling II.K.3.13 HPCI/RCIC Initiation Levels II.K.3.18 ADS Actuation Modifications II.K.3.28 Qualification of ADS Accumulators Tim Abney 14

Licensing Actions of Special Interest

° 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 Tim Abney 16

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 2

PRIORITY ISSUES ...............................................................................................................................................................

INSPECTIONS......................................................................................................................................................................2 2

MEETINGSN ISITS ...............................................................................................................................................................

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

3 TECHNICAL SPECIFICATIONS ..........................................................................................................................................

SUBMITTALS .......................................................................................................................................................................

8 NRC COMMITMENTS ...................................................................................................................................

2 BFN UNIT 1 PROJECT PLAN Page 2 I CONTACT (NRC, TVA CONTACT MILESTONE DATE INPO, NEIL, ANI)

MEETINGSNISITS K. Jabbour T. Abney 6/12/02 M. Morrison K. Jabbour

-NRR - Unit 1 Restart Overview @ Rockville 7/24/02 NRR - License Renewal @ Rockville

Page 3 BFN UNIT I PROJECT PLAN SUBMITTAL --- r- FED REG TVA NEED TVA CONTACT SUBMITTAL DATE DATE TECHNICAL SPECIFICATIONS DATE

_________ L ________ 3UIUi I ________

t 4 3Q/03 Containment Air Dilution (CAD) AOT ______________

3Q103 3Q/03 Excess Flow CQeck Valve Surveillance Intervals _________ L 4Q/03 4 4Q/03 High Range Primary Containment Radiation Monitors I v 4Q/03 PT Curves 11Q/04

__________ I I ___

Q/04 Crediting of Containment Overpressure for Ne Positive Suction Head Calculations for Emergency Core Cooling Pumps I -i I-t -

1 Q/04 Allowable Value For Reactor Vessel Water Level - Low Level 3 ___________________ 4 20/04 2Q/04 Oscillation Power Range Monitor (OPRM)

___________ 4- 2Q04 1 1 2Q '04 Main Steam Isolation Valve (MSIV) Leakage Rate Limits and Exemption From 10 CFR 50 Appendix J 20/04 f 4

2Q/04 SDIV Setpoint Change 20104 2Q/04 14-Day Allowed Outage Time for Emergency Diesel Generators 3Q104 I I 3Q/04 Power Range Neutron Monitor (PRNM)

Upgrade with Implementation of Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) TS ARTS/MELLL 3Q1r -

3Q/04 Miscellaneous I & C Changes 30/04 3Q/04 24 Month Fuel Cycle t-Alternative Source Term 3Q/05 Extended Power Uprate Operation 4Q/05 FSafety Limit Minimum Critical Power Rýa-tio 4Q/05

_________________________________I

Page 4 BFN UNIT I PROJECT PLAN SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE _ _ _ _

Input Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment IJic Description Due

  • ConcuriCocurnSignaure DDate to [Date to Signature Signaure Date to Signature Date De Eng Due Concur Concur ____

-t %.41v d-Regulatory 1 Framework 1Q/03 GL 88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Part 1 Piping I I I I 1Q/03 GL 94-03 Intergranular Stress Part 2 Corrosion Cracking 3Q/03 of Core Shrouds in BWRs 2Q/03 inservice Inspection (ISI) Program Relief Requests 3Q/03 Containment Inspection Program Relief Requests ________________ -t r 3Q/03 16 System Pressure Test (SPT) Program Relief Requests _____

____ ____ 4- - II 4Q/03 L

Programmatic Relief Requests _______ 4- T 1 Q104 BL 93-02 Debris Plugging of Emergency Core Cooling Suction I Strainers i 1 I _____ _____ I _________

Page 5 BFN UNIT 1 PROJECT PLAN SUBMITTALS - LOOK AHEAD nI r-nATl Amnl NIDI IT flD IF In ut Re - A U m I- r-1-1AN I 9 1L14 -4.

Aa-% .-I 1 Uf~ A,4..d I ue mm nt LiLi Resp Org /Actual Date to Date to V Vlgl .......

Input Input Rec'd Scn'dto Date to Eng Description Date Date Due Signature Signature I Concur Concur

=I1'0I0A I I r- I I I I I ikýuu-+

1 1.41 --

I 9 BL 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool _ _ __ _ _ _ -I-2Q/04 0 BL 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE ___________ I 4- t -T 2Q/04 I1 BL 88-04 Potential Safety Related Pump Loss 2Q/04 12 GL 89-13 Service Water System Problems Affecting Safety Related Equipment I 1 T 2Q/04 13 GL 94-02 Long Term Solutions Thermal-Hydraulic Instabilities in BWRs I 3Q/04 14 BL 90-01 Loss of Fill Oil in Rosemount Transmitters I _____ _______ ______________ I _____ _______ - _______ -

Page 6 BFN UNIT I PROJECT PLAN SUBMITTALSAmn - LOOK AHEAD nl Ir- nATP I IPOI TntFlI U1t1,./ li lt .AUI i rI .. IU 1= Sch'd Actualto Due Comment Lic Eng Input Resp Org Input Rec'd Sch'd Actual Date to Date Date Description Oate to Date to Due Signature Concur Concur Signature T 1 12/0ý4 Owl U-T 157GL 95-07 Pressure Locking and Thermal Binding of Safety-Related and power-Operated Gate Valves _ I I__ 1 3Q/04 19 GL 96-06 Assurance of Equipment Operability and Containmeni Integrity During Design Basis Accident Conditions _________ __ 4.1 tI 3Q/04 17 GL 97-04 Assurance of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps ________ ___ - II 4Q/04 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 I ______________________ I ______________ I _____________ __________________ j _________________ __________________ ___________________ --

BFN UNIT I PROJECT PLAN Page 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 Due Date Dte to t Date Dat to to Date ate to o Date Dae tojDateEm toDate E 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

-I I T T r t I 4 I L 21

,-21 1 GL 92-01 Reactor 4Q/05 Vessel Structural Integrity

- - I - - - - - I

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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