ML033520072

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Senior Management Status Meeting Between Nrc/Bwr Owners Group
ML033520072
Person / Time
Site: Boiling Water Reactor Owners Group
Issue date: 12/10/2003
From: Wang A
NRC/NRR/DLPM/LPD4
To:
References
Download: ML033520072 (23)
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Text

NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION 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 121I1 b3 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)

(- e I

Plant/Facility Name d< n e L/

IS rout TAC Number(s) (if available)

Reference Meeting Notice l0 f3 37 Purpose of Meeting (copy from meeting notice)

C e 7CfO\\

5 itvkCa NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE OFFICE DIVISION BRANCH Distribution of this form and attachments:

Docket File/Central File PUBLIC NRIC FORM 658 (9-1999)

PRINTED ON RECYCLED PAPER This loffn was designed using InFoffns

NRC/BWR Owners' Group Management Meeting - December 10, 2003 Agenda 8:30 Opening Remarks BWROG/NRC Joint Submittal Planning Review NRC/B WROG submittal integrated schedule TSTFs affecting BWRs Bank Position Withdrawal Sequence Decoupling of LOOP/LOCA-Option 3 Stability / Detect and Suppress Status presentation--an overview of recent meetings and happenings Steam Dryer Integrity Status presentation--an overview of recent meetings and happenings Generic Safety Issue - 189 Station Black Out Hydrogen Igniter Operability Alternative Source Terms Use of Standby. Liquid Control BWROG/NRC NRC STATUS BWROGJNRC BWROG BWROG BWROG BWROG OTHER BWROG/NRC STATUS ISSUES

  • NRC issues affecting BWRs.

Use of Standby Liquid Control in Alternate Source Term applications GSI-80, Pipe Break Effects on CRD Hydraulic Line GSI-193, ECCS Pump Gas Entrainment Others BWROG/NRC 11:30 Adjourn

BWR Owners' Group Licensing Topical Report / Other Submittals of BWROG Interest

=

INTEGRATED BWROG SUBMITTAL -NRC REVIEW SCHEDULE OGj Document LTR Traveller RAI

Response

TSTF TSTF TO NRC APPROVAL ISSUE NTech Specr I

RAWPI CLT C

N umber Tidle to NRC N umber Date Due Date N umber NRC TOPICALJTSTf CLIIP DATE COMMENTS

_SF-4 j Cotimn Stutua Inert (Al Ower...

I A

Ie I1-IYEI TSTF-343 ontainment Structural Integrity (All Owners TSTF-343 YES TD4-S 9....

,-} WQG i TST t~~~~~~~~~~~~~~*

1

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  • StX~ii,*j#

4

  • t 7: w.*<.-. S b.4' 4'.
114, TSTF-448 Control Room Habitability (All Owners Groups)

BWOG-TSTF-448 8119103 1Q04 E YES 1Q04 E I11 TSTF-459 Eliminate the requirement to have one RHR BWROG-TSTF-459 9/19/03 3QS4 E YES Shutdown Cooling System in operation R7 RI TSTF-460 Control Rod Scram Time Frequency (120 days -

BWROG-TSTF460 90103 3Q04 E YES

> 200 days) 90, RI TSTF-465 Addition of Time performance Surveillance BWROG-TSTF-465 9/18/03 3Q04 E Requirement (SR) note to Source Range Monitor 81, RI (SRM)SRs Joint Owners' Group MOV Response to GL 2128/04 E NA NIA N/A 8/04(TOPICAL)E NO NIA 96-05 (Final Report)

Containment Atmospheric Control Valves 1Q04 E NO NEDOb::33091 ~p,.W6W~cntFi RodIin-serto PWroc

-'%H.q.-CiQ04Ft2404EViV7C%

OVeaN&t NEDO 53D9 X:E E

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~S fi m 20S Suppression Pool Cooling / RHR Operable 2Q04 E Initiative Alternate Source Term -generic gap release 1Q04 E fraction for high-bumup fuel Risk Informed Tech Specs (RITS)

Initiative - I Modified End States 115101: NEDC BWROG-TSTF423 8112103 9/27/02 (Topical-SER)

YES 2Q04 E CEOG TSTF-422 BWROG 32988, R2 87 A 2/03 (NEDC 32988-TSTF-423 I_

I L

I I

IA) 2004 (TSTF) 2 Initiative - 4a CIV AOT Extention BWROG LTR BWROG-4I23/03A 3003 A TSTF454 9/5/03 2003 (Topical SER)

YES 2004 E 2J21102A XX 2Q04 (TSTF) E initiative-4b Risk Informed AOTs with Backstop Position paper On Hold for NA for BWROG 10/12/01A, revised BWR's No pilot white paper 12/27102A F

Page 1 of 2 E-Expected or target date WVA-Not Applicable Updated 12110/03

!t. Fe~~~~~~~I

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BWR Owners' Group Licensing Topical Report / Other Submittals of BWROG Interest INTEGRATED BWROG SUBMITTAL -NRC REVIEW SCHEDULE I

OG Tech Spec RAI CLIIP Document LTR Traveller RAI

Response

TSTF TSTF TO NRC APPROVAL ISSUE Number Title to NRC Number Date Due Date Number NRC -

TOPICAI/TSTF CLIIP DATE COMMENTS Initiative - 5b Relocate Surveillance Test Interval to Ucensee Position paper 6/01 BWROG-Comment TSTF-425 2Q04 E 4Q04 (TSTF) E YES 1Q05 E BWROG lead. Exelon LAR Control A, revised position 88 s on 4Q04 (SER) E submittal to NRC scheduled for paper IQ04E position 2104.

paper

__ _ _ 2004 E_

Initiative - 6a Modify LCO 3.0.3 to 24 Hours On Hold for N/A On Hold for resolution of BWR`s Initiative 6b and 6c to determine if Initiative Is required.

Initiative -6b Provide Conditions In the LCOs for those levels On Hold for Based on CEOG work, may of degradation where no condition currently BWR's consider 6b approach using exists to preclude entry Into LCO3.0.3.

(A)(4) to minimize use of LCO 3.0.3.

Initiative -6c Provide specific times In the LCO for those On Hold for TSTF-426 4Q03 E 2004 (TSTF) E TSTF to submit TSTF to NRC conditions that require entry Into LCO 3.0.3 BWR's after receipt of NRC SER and immediately.

receipt of Information from CEOG.

Initiative - 7a Snubbers WOG-150 TSTF-372, 11/17/03 YES R3 Initiative -7a Allowance for Non-Technical SpecificationBarrier TSTF-427 3/4/03 YES Degradation on Supported System OPERABILITY Initiative-7b Define Not Operable/Functional NEI revised position NA YES paper to NRC 2Q03 Initiative -8 Eliminate TS-Not Meet Criteria 2005E White paper YES Low Priority on method Risk Informed Activities Option 3, Elimination of LOOP Requirements 1004 E Exemption may be required.

1with LB LOCA E-Expected or target date N/AuNotAppflcable Updated 12/10/03 Page 2 of 2

Stability Detect and Suppress Methodology Presentation For BWROG/NRC Management Meeting Rockville, MD December 10, 2003 Ken Putnam (NMC)

BWROGINRC Management December 10, 2003 Meeting I

Purpose of Presentation

- Communicate BWROG actions and positions

- Discuss OPRM Technical Specification December 10, 2003 SWROG/NRC Management Meeting 2

1

August 15, 2003 NRC -Meeting

  • NRC agreed with plant specific approach
  • NRC wanted:

- Letter closing the Part 21 DIVOM issue

- Letter recommending arming of OPRMs

  • Both letters reviewed by Executives, Primary Representatives and Committee
  • Both letters were transmitted to the NRC on September 30, 2003 BWROGINRC Management December 10. 2003 Meeting 3

Future Committee Actions

  • Develop plant-specific DIVOM procedure
  • Support plant-specific DIVOM development for non-GE fuel vendors
  • Plant-specific schedules to be developed and submitted to NRC BWROGINRC Management December 10. 2003 Meeting 4

2

OPRM Technical Specifications

  • Some plants may operate indefinitely with "Alternate Method"
  • Some plants must restore operability within 120 days
  • NRC Staff not granting current requests for use of alternate method beyond 120 days
  • BWROG considering generic traveller to resolve issue BWROG/NRC Management December 10. 2003 Meeting 5

3

Steam Dryer Integrity Committee Presentation for BWROG/NRC Management Meeting December 10, 2003

.-Rockville, MD Joe Conen (DTE Energy)

December10. 2003 BWROGINRC Manaaement Meegna Steam Dryer Integrity A Repairs to steam dryers is not a new BWR issue A Dryer failures at Quad Cities (BWR 3) subsequent, to extended poWer uprates

  • XE gX GE SIL 644.and 644 supplement 1-provides inspection recommendations based on relative susceptibility of dryers December 10, 2003

. BWROGINRC Management MeeUng 2

1

Steam Dryer Integrity A In June 2003, BWROG Executive Oversight Committee (EOC) directed that workscope be appropriately shared among BWROG, BWRVIP, and General Electric A EOC directed that workscope cover broad dryer reliability and performance issues Not limited to issues related to dryer damage experienced at QC2 0

a' BWRVIP assigned lead responsibility 2

December 10. 2003 BWROGINRC Management Meeting 3

Steam Dryer Integrity Summary of Key Design Factors

~A BWR 3; square hood and internal braces

  • -o, High stresses where braces attach to hood
  • Some BWR 3 dryers do not have internal braces Add* BWR 4; slanted hoods, internal braces replaced with plates that reduce the maximum stress Ng

>>* BWR 5 and later; curved hoods to optimize steam flow, retained the internal plates; even lower maximum stress A Higher MSL velocities increase the amplitude of flow induced and acoustic load forcing functions that lead to high cycle fatigue

.~1 December 10. 2003 BWROGINRC Management Meeting 4

2

3

I GE Steam Dryer Screening Matrix 8 Steam Velocity (Main Steam Lines)

  • Pressure based on square of velocity
  • Highest =10
  • Other plants square of velocity normalized to Quad Cities square of velocity
  • Based on uniform unit pressure loading
  • Square = 10
  • Square (Wao struts) = 5
  • Slanted =3
  • Curved = 2 hi~t&

December 10. 2003 BWROGINRC Management Meetina 7

4g GE Steam Dryer Screening Matrix m

Example Results Average Pressure Flow Vel. I Load Hood Stress Relative g

Plant Line (ftlsec)

Score Type Score Score

{oPlant 4 202 10.00 Flat 10 100 Plant 5 168 6.90 Flat 10 69

~i Plant 17 141 4.87 Slanted 3

15 Plant 20 134 4.43 Slanted 3

13 g0;Plant 22 172 7.23 Cured 2

14 Xj Plant 14 181 8.03 Cured 2

16 December 10, 2003 BWROG/NRC Management Meeting 8

4

SCREENING MATRIX RESULTS so.

so 1

640 C

I-30 20 -nf

10.

Uprat*d BWRs (US and IntenaUonal) 75% of uprated U.S. BWR dryer failure probabilities are less than 20% of highest screening matrix results Steam Dryer Integrity Recent / Current'Activities

-VNRC questions summarized in letter to B WROG dated September 26, 2003 N

A, BWRVIP/BWROG workscope discussed with -NRC during November 4-5, 2003

4VNI, BVWRVIP meetings

-',,Formal BWROG response in preparation II~~

December 10. 2003 BWROGINRC Management Meeting 10 5

BWR Extended Power Uprate Issues BWROG/NRC Management Meeting December 10, 2003 Rockville, MD BWROG/NRC Management Meeting December 10, 2003 I

Meeting 1

Extended Power Uprates

  • EPUs Implemented at 11 l EPUs Anticipated at 6 E the near term I +AoDroximatelv 100 uorat Ii iI BWRs 3WRs in

.es L

have been implemented in the industry

+Roughly 5% of nuclear capacity December 10, 2003 BWROG/NRC Management Meeting

Implementation Challenges

  • Steam Dryers l
  • Flow Induced Vibration December 10, 2003 BWROG/NRC Management Meeting 3

Metn Plant Safety

+7Safety systems remain highly reliable

  • Technical Specification Surveillances and LCOs continue to be Met
  • Principal safety barriers have not been challenged
  • Maintenance Rule continues to manage risk
  • While challenges have occurred, uprates are a proportionally small contributoJWRWRj4qpgtry events December 10, 2003 Meeting 4

Learning From Experience ii I

I I

i i

+BWRVIP Steam Dryer Program

+INPO Workshops on power uprate

+Monthly utility EPU project manager conference calls to share lessons learned

+GE Self Assessment of EPU experience

+BWROG evaluating additional involvement 5s BWROG/NRC Management Meeting December 10, 2003

BWROG GSI-189 COMMITTEE BACKGROUND

  • Committee Formed to Address'G S

Impact on BWR Mark,ii, in~ pent Owners.

  • Focus of Effort is on Pant Differences which impact Benefinis and Cost

/

  • Reviewed NRC Ben it\\ a\\d Cos t*Aalysis
  • Results of Review16 ocumctentea Letter i

(BWROG - 03053).

e December 10, 2003 2BW R

[

2 1

BWROG LETTER CONCLUSIONS

  • Present Worth Calculated Benefitsvfoj7 Mean NUREG 1150 CaseWfEAi III Containment is $10k.
  • Total Benefits do notlSupport Pr eedingi with Plant Modifications for BWR:; wners/

December 10, 2003 SWRoG-MI 3

BWROG LETTER (CONT)

  • BWR Emergency Operating Procedures (EQR)

Restrict use of Hydrogen 1gntersW

> Hydrogen Analyzers neededfTo assure hyjrgen concentration is within limits

> Hydrogen Analyzers will require support Euipment /

o Scope of Backup Power Mddification n eds to include Hydrogen Analy zers or BWR o Cost Estimate of $320k based on SmaI Generator with no Suppqrt EquipmentI o Cost of Modification will far exceed'$3 OT Estimate.

December 10, 2003 4 4 2

BWROG LETTER (CONT)

  • Increase in Plant Defense in Depth..fro Backup Power for. Igniters-Is-norted by the Cost.

9.

  • Early Plant Emergen 1 Responseo SBO /

events needs to concentrate on

,wer restoration and Core' Cooling. jl I

  • Power restoration f 6r, ydrogep terse will be Assessed as part of.EmgE hncy I

Response.

December 10, 2003 BWR X

BWROG GSI-1 89

SUMMARY

  • Request a. review of the needft rule-making for Mark IHISi-iI Benefits identified Ftrp ark III (

not support Modificati ns

  • Is there a role for BV(' OG, in the resolution of issue.?/

December 10, 2003 BWROG/NRCJU i

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X 9ALTERNATIVE SOURCE TERMS (AST)

-W t59PRESENTATION FOR 4)zZ BWROG/NRC Management Meeting December 10, 2003 Rockville, MD JOE CONEN (DTE)

Vice Chairman, BWROG December120, 2003 BWROG/NRC Management MedingI i> ~ ~

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24 Recent AST Issue

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Issue: Crediting use of Standby Liquid Control S*~- 3~

(SLC) for Suppression Pool pH Control.

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Background:

- Suppression Pool credited to maintain iodine source terms in solution, reducing dose consequences. Pool pH of 7 or greater is needed to maintain iodine in solution.

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- Post-LOCA radiolysis of chloride-bearing materials (cable jacketing, shielding, etc) can' generate acids that

- reduce suppression pool pH over time.

- BWVR SLC injection into pool can counteract this effect to maintain the necessary pH levels for iodine retention.

,,F; December 10,2003 BWROG/NRC Management Mceting 2

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Recent AST Issue

i S1m /Potential NRC Issues

Ad~k SLC "credited" as containment atmosphere cleanup (GDC4 1)

GDC41 requires that system have "suitable redundancy";

accomplish safety function assuming "single failure" SLC systems generally not single failure proof

- Injection check valves, initiation switch SLC systems are generally not safety-related or subject to j 0. At environmental qualification.

NRC staff is working to consolidate its position regarding this SLC application.,,.

S 4

December 10,2003 BWROG/NRC Management Meeting 3

BVWROG Interest I SLC system is common to B Rs-I SLC reliability is recognized

- Credited for ATWS mitigation [10 CFR 50.62 (c)(4)]

X

- SLC is included in Standard Technical Specifications 7 BWRs currently have AST Applications in NRC review Several applicants informed of NRC considerations regarding SLC

.t.

One BWR has submitted Exemption Request for GDC4 I Several earlier AST applications crediting SLC were approved X

0 1 AST application supports resolution of Control Room

,fi, Habitability Issues and Power Uprate applications X: Ha Is there a role for BWROG in the resolution of issue?

December 10, 2003 BWROGINRC Management Meeting 4

2

Separation of LOOP and LOCA Presentation For BWROG/NRC Management Meeting December 10, 2003 Rockville, MD BWROGINRC Management December 10. 2003 Meeting 1

Separation of LOOP/LOCA The probability of a Loss of Offsite Power concurrent with a large break Loss of Coolant Accident is sufficiently remote to be treated as a severe accident BWROGINRC Management December 10, 2003 Meeting 2

1

Separation of LOOP/LOCA Scope of BWROG Topical Report reduces burden while maintaining or enhancing safety

- Allow Warm-up of diesel prior to loading

- Optimize Electrical Load Sequence

- Start Diesel only when needed

- Simplify Testing

- MOV stroke times relaxed

- Improve Suppression Pool Cooling

  • - Eliminate Complex Loop select BWROGINRC Management December 10. 2003 Meeting 3

Separation of LOOP/LOCA

  • Issues

- Use of generic PRA model with site confirmation of applicability

- Defense in depth confirmation using simplified code (MAAP) with confirmatory analysis (TRACG)

BWROG1NRC Management December 10. 2003 Meeting 4

2

Separation of LOOP/LOCA

  • Projected Schedule

- BWROG Submittal

- NRC Acceptance Review

- Lead plant exemption request NRC RAI's

- BWROG response to RAI's Draft SE completed Final SE issued January 2004 February 2004 March 2004 April 2004 May 2004 July 2004 August 2004 December 10, 2003 BWROG/NRC Management Meeting S

3

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