ML030550790

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2/13/03, BWROG Meeting Handouts
ML030550790
Person / Time
Site: Boiling Water Reactor Owners Group
Issue date: 02/13/2003
From:
Office of Nuclear Reactor Regulation
To:
Wang A, NRR/DLPM, 415-1445
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ML030210358 List:
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Download: ML030550790 (19)
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Stability Detect and Suppress Methodology Presentation for BWROG/NRC Management Meeting February 13, 2003 Mike May Feruary13,2003 BWROG/NRC Management Meeting

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2 D & S Program Phases

  • Phase 1: Identify methodology success path
  • Phase 2: Define new stability limit to show compliance to fuel design criteria
  • Phase 3: Develop the technical bases for new stability limit and develop the framework for licensing submittal 4,
  • Phase 4: Perform all analyses, submit LTR, and obtain NRC approval February 13, 2003 BWROG/NRC Management Meeting "Background

- Phase 1

  • Committee re-established to resolve Part 21 issue of non-conservative DIVOM curves

- DIVOM relates change in CPR to oscillation magnitude

  • Committee determined that generic DIVOM correlation not feasible

- Requires setpoints too low for effective o eration at some plants February 13, 003 BWROG/NRC Management Meeting 4

L 3

3 Background - Phase 1

--(Continued)

  • Committee pursued new approach

- Establishes generic setpoints and uses TRACG to calculate best-estimate CPR response to oscillations and initiating events o?..

- Received favorable response from NRC at 5/1 meeting, but NRC cautioned uncertainties must be quantified

  • Searched for more robust alternative

- Committee decided to pursue new stability limit

" *instead of SLMCPR

- Requires licensing basis change for stability February 13, 2003 BWROG/NRC Management Meeting 5

New Stability Limit - Phase 2

  • More realistic characterization of oscillation event
  • Approach permits oscillations that take fuel into and out of boiling transition

- Evaluate fuel response relative to applicable fuel design limits appropriate for stability

- Define new stability limit to ensure negligible impact on fuel February 13, 2003 BWROG/NRC Management Meeting 6

8 Summary of Feasibility Study

'~Phase 2 (Continued)

A,,,

  • Results indicate negligible impact on fuel

- Preliminary TRACG analysis shows acceptable temperature oscillation

- Limiting issue is annealing of irradiation "hardening

"- Need to establish oscillation temperature limit that ensures negligible annealing February 13, 2003 BWROG/NRC Management Meeting 7

I.

NRC Nov 2002 Meeting Summary

,4.

  • Meeting was positive
  • Solution based on fundamental fuel parameters
  • Program is right way to go
  • Ambitious - Need to qualify fuel performance methods for oscillation events February 13,2003 EWROG!NRC Management Meeting I

5

.,*;*Present Activities - Phase 3

"* Developing licensing framework document

- Defines all necessary licensing elements t,;-*

- Establishes work scope

- Provides roadmap

., *Technical discussion with NRC Staff set

- for February 2 0th Febnrary 13, 2003 BWROG/NRC Management Meeting 9

Major Milestones

"* Analysis to confirm assumptions, 2Q 2003

- ?

analysis scope, and schedule

  • Complete engineering analysis 4Q 2004 x1,-,
  • . Submit Licensing Topic Reports 1Q 2005
  • Receive NRC approval 1Q 2006 February 13.2003 BWROGINRC Management Meeting to

0 1

Risk Informed Part 50 Option 3

,. BWROG/NRC Management Meeting Rockville, MD February 13, 2003 Lewis Sumner (SNC)

BWROG/NRC February 13 2003 Management Meeting Purpose of Committee &

Presentation

  • Purpose of the committee

- Original: Develop RIP-50 Option 3 programs (SECY-2001-133) - focus on

§50.46 and App. K.

- Current: Pursue LOCA/LOOP and monitor the others

  • Purpose of the presentation

- Review results of last meeting with the Staff

- Ensure agreement on expected results from the next meeting.

NRMVWROG 2

Ma agemizen W e

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Next NRC Meeting

  • Scheduled for February 27, 2003

- BWROG outline has been transmitted to the Staff for review

- BWROG expectation is that meeting will have a positive impact on the LTR content

- Minimize Requests for Additional Information

- BWROG requests confirmation from NRC management regarding success path NRC/BWROG Manaeement Meetine SNovember 2002 NRC Meeting

-z,.,

  • BWROG presented its "safety case"

- Substantial reduction in complexity

- Separating LOCA from LOOP is expected to

. improve safety NRC commented favorably p.I

  • Discussed need for near-term progress

- Staff suggested LTR as basis for §50.12 exemption to §50.46

  • BWROG has outlined specific information

-C for the LTR NRCI/BWROG February 13, 2003 Management Meeting

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  • R Summary
  • LOCA/LOOP is important

- It is a cornerstone for risk-informed regulations

  • BWROG has struggled to identify a "success path

- Lead plant exemption request has potential

- BWROG prefers rulemaking, if timely

  • Continued BWROG efforts are based upon "milestone accomplishments

?XnRCBWO 5mn~ef February 13, 2003 4

3 5

NRC/BWROG

Removal of Safety Limit MCPR From Tech. Specs.

4 Large Number of SLMCPR Changes Results in Significant Industry / NRC Burden.

Objective: Relocate SLMCPR Value to the COLR.

February 13, 2003 BWROG-NRC Management Meeting Reduction of-Unnecessary Regulatory Burden:

Removal of Safety Limit MCPR From Tech. Specs.

Presentation for BWROG/NRC Management Meeting February 13, 2003 Tom Silko (Entergy VY)

February 13, 2003 BWROG-NRC Management Meeting 2

I

Removal of Safety Limit MCPR From Tech. Specs.

  • Advent of Advanced Core Design Methods Has Resulted in SLMCPR Values Routinely Changing.
  • 1999 - TSTF-357 Proposed to Relocate Numeric Value to the COLR.

"* Fall 2002 - Exelon/AmerGen Submit Exemption Request to Relocate SLMCPR.

"4 Fall 2002 - Draft TSTF-357, Revision 1 Placed on Hold Pending Exemption Disposition.

BWROG-NRC Management Meeting Removal of Safety Limit MCPR From Tech. Specs.

+ Original BWR Tech Specs Contained Numeric Values of ore Thermal Limits - Caused Frequent Tech Spec Changes.

+ GL 88-16 Allowed Removal of Core Thermal Limits Numeric Values from Tech Specs to the COLR.

+ SLMCPR Numeric Value is in Safety Limits Section of Tech Specs and was Not Relocated. At the Time, SLMCPR did not Routinely Change Cycle-to-Cycle.

February 13, 2003 BWROG-NRC Management Meeting 3

t I

February 13, 2003

3 Removal of Safety Limit MCPR From Tech. Specs.

+ Closure Options

February 13, 2003 BWROG-NRC Management Meeting

1 Joint Owners' Group (JOG)

Motor-Operated Valve (MOV)

Periodic Verification (PV)

PRESENTATION FOR BWR OWNERS' GROUPINRC Management Meeting February13,2003 Tom Green (GENE) for Glenn Warren (SNC)

February 13, 2003 BWROG-NRC MANAGEMENT MEETING JOG MOV Periodic Verificaton OBJECTIVES PARTICIPATION B&WOG, BWROG, CEOG & WOG

- 62 plants; 98 units w OBJECTIVES

  • Brief NRC Management on JOG Program Status February 13, 2003 BWROG-NRC MANAGEMENT 2

MEETING

February 13, 2003 JOG MOV Periodic Verificabon PROGRAM

SUMMARY

STATUS

-190 MOVs assigned for testing S3-Phase JOG MOV PV Program:

"* Interim (static testing while dynamic testing conducted)

"* Dynamic testing (3 consecutive tests per assigned MOV)

"* Individual plant Implementation (i.e.,

recommendations)

S5-yr testing program (Phase 2) ended-October 2002 with - 570 dynamic tests conducted w Final report in preparation (age-related degradation conclusions and recommendations from testing)

February 13, 2003 BWROG-NRC MANAGEMENT 3

MEETING JOG MOV Periodic Verification JOG COMMUNICATIONS WITH INDUSTRY w JOG has presented a status update at annual MUG (MOV Users' Groupi meetings since 1997 w JOG has presented a status update at NRCIASME Valve Symposiums since 1998 SJOG Feedback Notices have shared relevant dynamic testing information with participating utilities from program start (NRC has reviewed)

BWROG-NRC MANAGEMENT MEETING

3 JOG MOV Periodic Verificabon PROGRAM SCHEDULE SOCT 02: Dynamic testing completed 2 DEC 02: All test results to MPR Associates for evaluation w APR 03: Draft report for JOG Core Group review w JUL 03: Status meeting with NRC Staff w JUL 03: Draft report to utilities for review SNOV 03: Final Report issued to OGs for approval SDEC 03: Final report submitted to NRC JUN 04: Expected NRC SER February 13,2003 BWROG-NRC MANAGEMENT 5

MEETING JOG MOV Periodic Verification NRC INTERACTION 2-10 JOG status meetings have occurred with NRC since program start in 1997; meetings have been amiable and constructive z-NRC has Indicated acceptance of JOG program schedule for final report submittal SNRC GL 96-05 SER Issues and related open Items will be addressed in JOG Final Report Expectation of both JOG and NRC is for "clean" JOG MOV PV SER to facilitate ease of utility Implementation SJUL 17-18, 2003 meetingjAiarmo JOG to discuss preliminary test results with NRC Staff SJOG will seek waiver for "NRC Review Fees" consistent with current NRC guidelines February 13, 2003 BWROG-NRC MANAGEMENT 6

MEETING

4 JOG MOV Pedodic Verification UTILITY IMPLEMENTATION JOG to most likely recommend a utility implementation schedule similar to that endorsed by NRC for the BWROG DC Motor Methodology implementation

"* "Clock-start" upon SER issue

"* Plant-specific MOV PV program response within "X" years or "Y" Refueling Outages February 13, 2003 BWROG-NRC MANAGEMENT 7

MEETING

Page 1 0

9 Hydrogen Accumulation Committee Status Presentation For BWROG/NRC Management Meeting February 13, 2003 Rockville, MD Jack Gray (Entergy NE)

February 13, 2003 BWROG/NRC I

l Manacement Meeting L-V H2 Accumulation co

Background

Two hydrogen detonation events

- RHR/SCM Rupture - November 2001

- Head Spray Rupture - December 2001

  • GE "Blue Ribbon" task force defined potential risk
  • Hydrogen Accumulation committee developed managed approach to address this risk February 13, 2003 BWROGMNRC 2

@3 Management Meetniz

Page 2 c

1H2 Accumulation Background (Continued)

BWROG communicated with Japanese and European utilities that experienced detonation events Extensive discussion with affected European utility at October 2002 BWROG European Conference Multiple discussions with affected Japanese utility at BWROG General Meetings February 13, 2003 BWROG/NRC 3M i

Manazernnt Meeting L

H2 Accumulation Committee Accomplishments Reviewed GE task force report and key technical references Benchmarked Japanese utility screening methods Studied mitigation methods to reduce potential for hydrogen accumulation GE provided "tool chest" to BWROG

"* GE hydrogen design methods

"* Detonation pressure information February 13,2003 BWROM e

NRC 4

Page 3 H2 Accumulation Committee Accomplishments (Continued)

Issued Guidance Document BWR Piping and Component Susceptibility to Hydrogen Detonation"

"* Management logic chart for evaluating system susceptibility

"* Generic "susceptibility" classifications ("bins") as part of screening criteria

"* Identified 2 high priority piping runs for evaluation and potential action during upcoming refueling and maintenance outages RHR Steam Condensing Mode

- Head Spray System February 13,2003 WRaa NRC 5e Mana=emn Meeting LIý Information Made Available to the CT Nuclear Industry

" Distributed Guidance Document to the BWROG Executives and Primary Representatives in December 2002

- Lewis Sumner letter requesting action

"* Sent Guidance Document (Proprietary and Non Proprietary versions) and Steam Condensing Mode survey results to NRC December 2002

"* Guidance Document is being provided to INPO

"* Survey is in progress to determine plant specific actions taken to date February 13,2003 ManaBenent Meeting

____________________~~~~~

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%II" fltII re Tech Spec Open RAI NEI CLIIP Document LTR Traveller Open RAI

Response

TSTF TSTF TO NRC APPROVAL ISSUE Number Title (to NRC)

No.

Date Due Date Number NRC TOPICALrTSTF CLIIP DATE COMMENTS NEDO-33003 Regulatory Relaxation for the H2/02 Monitors and BWROG-01036 NO BWROG requested NRC to Combustible Gas Control System 6/22/01 A suspend review In Jan 02 NEDC-31951P Implementation of IWC and Technical Basis for BWROG-98037 NA NONE 11/08/01 (letter) A NO COMPLETE Revised Piping Inspection Schedules 4/8198 A Joint Owners' Group MOV Response to GL 96-05 12131/03 E NA NONE 6104(TOPICAL)E NO (Final Report)

YES Containment Atmospheric Control Valves 2003 E RITS-1 Risk Informed Tech spec (RITS) -1 Modified End E-mail to NEI and NEI CEOG-152, 71/31/01 A 10102 A TSTF-422 422 6/02A 9102 (SER) A YES 3Q03E BWROG and CEOG TSTFs States Itr to NRC. 115/01:

BWROG-87 TSTF-423 423 1003E 2003 (TSTF) E bundled. Approved report NEDC 32988, R2 submitted to NRC 1103 RITS-2 Missed Surveillances Developed by NEI CEOG-140, NA NA TSTF-358 9/14/00, R5 6/01 (TSTF)A YES 9/28/01 A 90% of plants have or will RITSTF and submitted R3 apply for it RITS-3 Flexible Mode Restraints OGOO-0443-236. GE-CEOG-141, 8114/01A TSTF-359 2/4/02 A 3Q02(TSTF)'A YES 3002 A Late comments being NE A13-00464-002.

R3 R8 FRN addressed In CLIIP FRN 12/00, R2 1003 Notice of availabliti RITS-4a CIV AOT Extention BWROG LTR CEOG-160 4002A 1Q03E Not 2Q03E 2Q03 (SER)E YES 1003E BWROG submittal, will 2/21/02A Assigned 4003 (TSTF) E require review fees RITS-4b Risk Informed AOTs with Backstop NEI position paper NAforBWROG 10/12/10A, revised No pilot white paper 2/27/02A RITS-5b Transfer SRs/Optimize STIs NEI position paper BWROG-88 Comments 5/31102 A TSTF-425 2Q03E 3Q03(TSTF) E YES 1Q04 E BWROG lead. Next 8/01 A, revised on position revision of method estimated position paper 4/03E paper for 1Q03 9/21/01 A_____

RITS-6 Modify LCO 3 0 3 to 24 Hours 2003 E CEOG-373 Based on CEOG work. may consider 6a approach using (A)(4) to have a floating LCO 3 0 3 action statement RITS-7a Barriers White paper TSTF-372 to be submitted to NRC 1003 RITS-7b Define Not Operable/Functional NEI revised position NA YES naper to NRC 2003 YES RITS-8 Eliminate TS-Not Meet Cnteria 2003E White paper on method NO Draft report transmittedfor NEDC-33030 Option 2 Pilot Program for Quad Cities OG 01-0241-244 NO Draft report trnsmitted for 7/27/01 A

_____________________information...

7/2701 APotential petition for rule Option 3, Elimination of LOOP Requirements with LB 12/03 E ima l ng LOCA NOCOMak ETE Pipe Break Inside Containment for SEP III Plants (GSI 11/15/01A N

156 6 1) NEDC-33054P NEDC-XXXXX Revised Detect and Suppress Methodology 1Q05E N/A NIA NIA 1Q06 (Topical) E NO A=Actual Date

.~xectd o taget date NA=Not Applicable Updated 2/111=003

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