ML20197G263

Summary of 971202 Meeting W/Bwrog in Washington,Dc Re Work That BWROG Proposes to Do Related to Behavior of Protective Coatings Inside Containment During Loca.W/List of Attendees

ML20197G263
Person / Time
Issue date:	12/22/1997
From:	Joshua Wilson NRC (Affiliation Not Assigned)
To:	Essig T NRC (Affiliation Not Assigned)
References
PROJECT-691 NUDOCS 9712300406
Download: ML20197G263 (30)

Text

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• • • * }2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20046-0001

%, ,,,,,*f December _ 22, 1997 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: James H. Wilson, Senior Project Manager Standardization Project Directorate g

Division of Reactor Program Management Office of Nuclear Reactor Regulation SUBJECT;

SUMMARY

OF PUBLIC MEETING HELD ON DECEMBER 2,1997, WITH THE BOILING WATER REACTOR OWNERS' GROUP (BWROG)

TO DISCUSS CONTAINMENT COATINGS PERFORMANCE At the request of the BWROG, staff from the Materials and Chemical Engineering Branch and the Containment Systems and Severe Accident Branch, in the Office of Nuclear Reactor Regula1on, met with the BWROG during one of the BWROG'? regularly scheduled meetings in Washington, DC to discuss work that the BWROG proposes to do related to the behavior of protective coatinga inside containment during a loss of-coolant accident (LOCA). A list of attendees and their affiliations is provided as Attachment 1.

Mr. Jeff Branum of Sodhem Company and Mr. Don Hill of Washington Public Power Supply System briefed the staff, using the viewgraphs provided as Attachment 2 (notes appearing on these viewgraphs represent danges made by the speakers to the prepared viewgraphs used in the presentations). The program described by the BWROG addresses several issues which are

-important, from a safety perspective, to an understanding of post LOCA coatings performance.

These include the timing of the coating failures and the size and shape of the paint particles after failure. Currently, the BWROG intends to parform some additional transport experiments after this program is completed.

The staff commented that the program proposed by the BWROG was very similar in its general outline to experimental work that the staff has considered performing. Mr. Tom Green of General Electric Company offered the staff an opportunity to discuss the BWROG's proposed program in more detail after the NRC staff has an opportunity to study it.

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. LIST OF ATTENDEES AT MEETING W/ BWROG ON CONTAIMENT

. .; COATINGS PERFORMANCE HELD IN WASHINGTON, DC ON DECEMBER 2,1997 1 NAME AEElLIATION R. Lobel- NRC J. Medoff NRC J. Branum Southem Nuclear D. Hill WPPSS J.Dayman Poco Energy T. Green GE T. Hilston '

CEl/ Perry W. Maher Sequoia Consulting

.i R.Janov&te GE R. Phillips . TVA R. Howard TVA J. Adrian SCS D. Zabala SNC A. Bilanin Continuum Dyn R. Bryer Detroit Edison / Fermi 2 L. Holden Com Ed G. Ashley Duke Engineering W. WMmor Vermont Yankee C. Sewetzke Niagara Mohawk S.Saha GPU/ Oyster Creek G. Hart PCI M. Crapps SGPAl/UESI A. Ricker NU/ Millstone 1 G. Comelius NU/ Millstone 1 4

i Attachment 1 p 4- wy 4 ie r e a e, a, #.,4 ?h' a--e .mg- h-,, es ...w.w,= &

4 CONTAINMENTCOA TINGS COMMITTEE  !

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BWR Owners'Grou)6 \

l Containment Coating Committee Meeting l with NRC Staff i

! I December 2,1997 l Washington, DC JeffBranum Southern Nuclear l l

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TAG 97105 I l

Attachment 2  ;

l

CONTAINMENTCOA TINGS Committee . Lead the US nuclear industry in Objectivet resolution of the containment coating issue

- Potentially impacts ECCS pump suction strainer performance and final resolution of the suction strainer plugging issue Presentat/on . Update NRC Staff regarding BWR Objective; Owners' Group Resolution actions Background . NRC has expressed concern regarding performance of non-qualified and indeterminate containment coatings with respect to ECCS suction strainer plugging

. Draft Generic Letter (TAC No.

M97146) issued on May 13,1997 for 45 day comment

- NEl coordinated industry response

- Affects BWRs andPWRs

- Expected to be issued 4Q 1997 at the earliest TAG 9710$

CONTAINMENTCOA TINGS Background (Continued)

BWROG authorized Ad Hoc Containment Coating Committee to:

Ensure consistent industry response to Generic Letter

. Integrate BWRIPWRIEPRI efforts into unified approach under BWROG leadership Conduct BWROG Ad Hoc meeting to develop a containment coating resolution plan, define work scope, select subcontractors, and estimate cost for initial work scope Establish generic criteria to assess potential impact of unqualified and/ot degraded coatings on ECCS strainers Employ expertise from ECCS Suction Strainer Committee ASTM D-33 Subcommittee, and Nuclear Utility Coating Council, to lead s project TAG 97105

' ~ '

CONTAINMENTCOATINGS AdHoc Meeting Summary:

2 day Chicago meeting well attended 39 participants 14 utilities 4 consultants l NRC, EPRI, NEl, BWROG Management, GE

. Initial workscope developed e Source Term Working Group Formed

- Data acquisition to document: <

>*- Particle size atfailure

'a Timing of release

>= Quantity released

- Conference calls initiated on September 3rd

>*- Includes participation from coating suppliers and industry consultants

~~

BWR Owners' Group Executives authorized full generic committee in late October 1997 8

TAG 97105

... CONTAINMENTCOA TINGS issue Resolution Strategy:

. Review available test data to develop defendable containment coating source terms Supplement with autoclave testing

. Use transport, settling, and strainer head loss methodology developed by ECCS Suction Strainer Committee Supplement test data where required

. Determine timing for coating debris release from substrate Delayed release facilitates increased settling in suppression pool

. Develop Containment Coating Utility Resolution Guidance (CCURG) similar to what was developed by ECCS Suction Strainer Committee (URG)

==-

TAG 97105 l

. .g CONTAiHMENTCOA TINGS 3

Approved Work Scope:

• Program Overview 1

- Interim safety assessment (ifI aquired)-

- Interim guidance

- Information meeting with NRC

- Industry /EPRl/PWR interface

- Response shell for GL

- Data compilation Source Term andDebris Characterization

- Data acquisition and analysis (particle size at failure, timing of release from substrate, quantity released)

! - Autoclave testing of coupons engineered to fall under LOCA conditions 1 - Key input for other committee tasks e Transport Guideline

- Review, modify, validate transport settling methodology for Mark I, ll, lll (DBA, IBA)

- Particle characteristics sensitivity o - Timing sensitivity HeadLoss Guidelines Function of paint, fiber and slue.ge characteristics l and quantities-L

- Effect of temperature TA097105

1

.w CONTAINMENTCOA TINGS l

)

-I CurrentActions:

. Containment Coating survey in process L

• Working Group completed plan for autoclave tests in support of source term and debris characterization -

6 coatings systems engineered to fail Obtained proposals from Carboline for test

~

coupon preparation and autoclave testing; and

.from University of Massachusetts for radiation aging of test coupons p

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, TA097105 i

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. y CONTAINMENTCOA TINGS Autoclave TestPlan:

Preparation of 2" X 4" X 1/4" thick test coupons Coating systems designed to induce failure

\0g

. N)ne (9) test coupons for each coating system

1. Carbon steel panels, sweep blasted per SSPC-GP-7 (1-2 mil profile), coated with Carboline 890 (5.0-7.0 mils)/ Carboline 890 (5.0-7.0 mils).

2. Smooth galvanized panels, solvent wiped, coated with Carboline 890 (5.0-7.0 mils)/

Carboline 890 (5.0-7.0 mils).

3. Carbon steel panels, wire wheel cleaned to produce a 0.5-1.0 mil profile, coated with 5.0-7.0 mils of Carbonzine 11SG.

4. Carbon steel panels, blasted per SP-10, coated with Carbozinc 11SG (5.0-7.0 mils)/Carbozinc ,

11SG (5.0-7.0 mils)/ Carboline 890 (5.0-7.0 mils).

5. Alkyd / Alkyd System, equal to Valspar 13R28 Primer and 19 Series Topcoat applied to carbon steel panels, prepared per SSPC-SP-7.

6. Red Oxide Primer, equal to Valspar 13R28 applied to carbon steel panels prepared per SSPC-SP-7 9

TAG 97105

- ~., _ __,,...-___ _____--- _ _ _ _ , _ _ _ _,

CONTAINMENTCOA TINGS v

Autoclave TestPlan(Continued):

On ks\f tho

e Test coupons irradiated to 5 X 10s rads max 1mUnTdoshpproximatsiy 304toum l Maximum dose at approximately 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> is i 1 X 10' rads l

i

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. LOCA test conditions ( wdl x clo (tradia&) -

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L 1. ASTM D 3911/340 F for 30 minutes, terminating i test with slow decrease in temperature and pressure.

2. ASTM D 3911/340 F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, terminating test with slow decrease in temperature and pressure.

3. ASTM D 3911/340 F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, terminating after typical, rapid decrease in temperature and i pressure. (Spray solution)

TAG 97-105

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• y Project No. 691 Boiling Water Rouer Owners Group.

cc: Thomas J. Rausch, Chairman Boiling Water Reactor Owners' Group Commonwealth Edison Company Nuclear FuelEervices 1400 Opus Place 4th Floor ETWill Downers Grove,IL 60515 Carl D. Terry _

Vice President, Nuclear Engineering Niagara Mohawk Power Corporation Nine Mile Point-2 PO Box 63 Lycoming, NY 13093 Drew B. Fetters PECO Energy Nuclear Group Headquarters MC 62C-3 965 Chesterbrook Blvd.-

Wayne, PA 19087 John Hosner Commonwealth Edison Executive Towers,4th Floor 1400 Opus Place Downers Grove,IL 60515 George T. Jones

. Pennsylvania Power & Light MC A6-1 Two North Ninth Street Allentown, PA 18101 Lewis H. Sumner Southem Nue'rar/ Georgia Power E.1. Hatch Nuclear Power Plant U.S. Route 1 North, Box 439 Baxley,GA 31513 L. A. England Entergy Operations Inc.

PO Box 31995 Jackson,' MS 39286 K. K. Sedney GE Nuclear Energy

' 175 Curtner Ave, M/C 182 San Jose, CA 95125

en *84g p- 4 UNITO STATES s* ' NUCLEAR REGULATORY COMMISSION

• WASHINGTON, D.C. am g ,,' ,,, December 22, 1997 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic lesues and Environmental Projects Branch Division of Reactor Program Management ONMe of Nuclear Reactor Regulation FROM: James H. Wilson, Senior Project Manager c'andardization Project Directorate O g

Division of Reactor Program Management ONice of Nuclear Reactor Regulation

SUMMARY

OF PUBLIC MEETING HELD ON DECEMBER 2,1997, WITH THE BOILING WATER REACTOR OWNERS' GROUP (BWROG)

TO DISCUSS CONTAINMENT COATINGS PERFORMANCE At t le request of the BWROG, staff from the Materials and Chemical Engineering Branch and the Containment Systems and Severe f.ccident Branch, in the Office of Nuclear Reactor Regulation, met with the BWROG during one of the BWROG's regu!=rly-scheduled meetings in Washington, DC to discuss work that the BWROG proposes to do related to the behavior of protective coatings inside containment during a loss-of coolant accident (LOCA). A list of attendees and their affiliations is prosided as Attachment 1.

Mr. Jeff Branum of Southern Company and Mr. Don Hill of Washington Public Power Supply System briefed the staff, using the viewgraphs provided as Attachment 2 (notes appearing on these viewgraphs a .present changes made by the tpeakeN to the prepared viewgraphs usea in the presentations). The program described by the BWROG addresses severalissues which are important, from a safety perspective, to an understanding of post-LOCA coatings performance.

Thase include the timing of the coating failures and the size and shape of the paint particles after failure. Currently, the BWROG intends to perform some additional transport experiments after this program le completed.

The staff commented that the program proposed by the BWROG was very similar in its general outline to experimental work that the staff has considered performing. Mr. Tom Green of v

General Ele .ic Company offered the staff an opportunity to discuss the BWROG's proposed program k. .nore detall alter the NRC staff has an opportunity to study it.

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es December 22. 1997 !

4 Conclud.ng these piesentations to the staff, the BWROG su$oumed the public portion of its  ;

meeting Project No. 691 j

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.o T. Essig 2 December 22. 1997 Concluding these presentations to the staff, the BWROG adjoumed the public portion of its meeting.

Project No. 691 Attachments: As stated cc w/ stts: See next page DISTRIBUTION: See attach page Document Name: MEETSUM.D02

• See Previous Concurrences /

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LIST OF ATTENDEES AT MEETING W/ BWROG ON CONTAIMENT COATINGS PERFORMANCE HELD IN

.. WASHINGTON, DC ON DECEMBER 2,1997 NALM' AEE1LIATJON R. Lobel NRC J. Medon NRC J. Branum Southem Nuclear D. Hill WPPSS J. Dayman Poco finergy T. Green GE T. Hilston ~

CEl/Porry W. Maher Sequoia Consulting R.Janowlac GE R. Phlilips TVA R. Howard TVA J.Addan SCS D. Zabala SNC A. Bilanin Continuum Dyn R. Bryor Detroit Edison / Fermi 2 L. Holden Com Ed G. Ashley Duke Engineering W. Wittmer Vermont Yankee C. Sawatzke NiaDara Mohawk S.Saha GPU/ Oyster Creek G. Hart PCI M. Crapps SGPAl/UESI A. Ricker NU/ Millstone 1 G. Cornelius NU/ Millstone 1

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! CONTAINMENTCOA TINGS i

COMMITTEE 4

BWR Owners' Group Containment Coating Committee Meeting with NRC Staff December 2,1997

Washington, DC 1

4 JeffBranum i Southern Nuclear -

TA007106 Attachment ?

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CONTAINMENTCOATINGS Comm/ttee . Lead the US nuclear industry in Object / vet resolution of the containment coating issue

- Potentially impacts ECOS pump suction strainer performance and final resolution of the suction strainer plugging issue Presentat/on . Update NRC Staff regarding BWR 4

Object / vet Owners' Group Resolution actions Background . NRC has expressed concern regarding performan?,e of non-qualified and indeterminate l containment coatings with respect to ECCS suction strainer plugging Draft Generic Letter (TAC No.

M97146) issued on May 13,1997 for 45 day comment

- NEl coordinated industry response Affects BWRs andPWRs Expected to be issued 4Q '1997 at the earliest TAG 9M05

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,- CONTAINMENTCOA TINGS

\ .

Background (Continued) 1 l BWROG authorized Ad Hoc Containment Coating l Committ= , to:

Ensure consistent industry response to Generic Letter i

1

. Integrate BWR/PWR/EPRI efforts into unified approach under BWROG leadership l

\

Conduct BWROG Ad Hoc meeting to develop a i containment coating resolution plan, define work l

scope, select subcontractors, and estimate cost for initial work scope l

Establish generlocriteria to assess potential  !

impact of unqualified and/or degraded i coatings on ECCS strainers i -

Employ expertise from ECCS Suction Strainer

Committee ASTM D-33 Subcommittee, and Nuclear Utility Coating Council, to lead project l-

~

TAG 97106

. . . - .. . . _ . _ _ . . . . _ . . _ _ , . , _ . . (( .. [ . _ _ _._.__I i. _ _ __ _-.,.-. ..- .._.. _ _ _ _

CONTAINMENTCOA TINGS AdHoc Meeting Summary:

2 day Chicago meeting well attended --

- 39 participants  !

- 14 utilities i

- 4 consultants  ;

- NRC, EPRI, NEl, BWROG Management, GE l

. Initial workscope developed

• Source Term Working Group Formed

- Data acquisition to document:

• Particle size atfailure

• Timing of release

- Quantity released l

- Conference calls initiated on September 3rd  :

~

Includes participation from coating suppliers and l Industry consultants '

BWR Owners' Group Executives authorized full generic committee in late October 1997 l

l l TAG 97106 l

._.___.._..._._--....___.7....____ _ _ . . . . . . .

CONTAINMENTCOA TINGS Issue Resolution Strategy:

e Review available test data to develop defendable containment coating source terms Supplement with autoclave testing

. Use transport, settling, and strainer head loss methodology developed by ECCS Suction Strainer l Committee '

Supplement test data where required l l

. Determine timing for coating debris release from l substrate Delayed release facilitates increased settling in l suppression pool Develop Containment Coating Utility Resolution Guidance (CCURG) similar to what was developed by ECOS Suction Strainer Committes (URG)

I TAO 9MD$

l ..

CONTAINMENTCOA TINGS j Approved Work Scope:

• Program Overview

- Interim safety assessment (if required)

- Interim guidance -

t

- Information meeting with NRC

- Industry /EPRl/PWR interface

- Response shell for GL

- Data compilation e

Source Term andDebris Characterizailon

- Data acquisition and analysis (particle size at failure, timing of release from substrate, quantity released)

- Autoclave testing of coupons engineered to fall under LOCA conditions

- Key input for other committee tasks '

• Transport Guldeline

- Review, modify, validate transport settling methodology for Mark I, ll, lll (DBA, IBA)

- Particle characteristics sensitivity

- Timing sensitivity e

HeadLoss Guidelines

- Function of paint, fiber and sludge characteristics and quantities

- Effect of temperature l

TAG 97106

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CONTAINMENTCOATINGS \

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CurrentActions:

l

• Containment Coating survey in process ,

i e Working Group completed plan for autoclave tests ,

in aupport of source term and debris

characterization -

6 coatings systems engineered to fail ,

Obtained proposals from Carboline for test '

l l coup'on preparation and autoclave testing; and l from University of Massachusetts for radiation aging of test coupons ,

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, CONTAINMENTCOA TINGS I

Autoclave TestPlan

=

Preparation of 2" X 4" X 1/4" thick test coupons

- Coating systems designed to induce failure

% l pine (9) test coupons for each coating system l

i

1. Carbon steel panels, sweep blasted per SSPC-SP-7 (1-2 mil profile), coated with Carboline 890 (5.0-7.0 mils)/ Carboline 890

' (5.0-7.0 mils).

2. Smooth galvanized panels, solvent wiped, i

coated with Carboline 890 (5.0-7.0 mils)/

Carbo!ine 890 (5.0-7.0 mils).

i

3. Carbon steel panels, wire

• wheel cleaned to produce a 0.5-1.0 mil profile, coated with 5.0-7.0 mils of Carbonzinc 11SG.

4. Carbon steel panels, blasted per SP-10, coated with Carbozinc 11SG (5.0-7.0 mils)/Carbozino 11SG (5.0-7.0 mils)lCarboline 890 (5.0-7.0 mils).

5. Alkyd / Alkyd System, equal to Valspar 13R28 Primer and 19 Series Topcoat applied to carbon steel panels, prepared per SSPC-SP-7.

6. Red Oxide Primer, equal to ValspEr 13R28 applied to carbon steel panels prepared per i SSPC-SP-7 "

l l

l TAO 9M06 l

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CONTAINMENTCOA TINGS

't l

Autoclave TestPlan(Continued):

i Om ka.lf Igo l

• Test coupons irradiated to 5 X 10' rads Maximum doswatrpproximately-SC heure -

1 -

Maximum dose at approximately 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> is

1 X 10' rads l

LOCA test conditions (utL x do ar>dsdO -

/

1. ASTM D 3911/340 F for 30 minutes, terminating i

test with slow decrease in temperature and pressure.

2. ASTM D 3911/340 F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, terminating test with slow decrease in temperature and pressure.

2 l

3. ASTM D 3911/340 F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, terminating after typical, rapid decrease in temperature and pressure. (Spray solution)

TA007106

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4

- , i Project No. 091 Boiling Water Reactor Owners Group i

oc: Thomas J. Rausch, Chairman Bothng Water Rowtor owners' Oroup <

Commonwealth Edison Company i i Nuclear Fuel Services  !

1400 Opus Place,4th Floor ETWill -

Downers Grove,IL 00515 i

(

Cart D. Terry Niagara Mohawk Power Corponrtion i

Nine Mile Point-2

- PO Box 83 Lycoming, NY 13093 4

, Drew 9.' Fetters PECO Energy .

t Nuclear Group Headquerters MC 62C-3 -

965 Chesterbrook Blvd- -

Wayne, PA 19087 '

. John Hosner Commonwealth Edison Executive Towers,4th Floor i

1400 Opus Place Downers Grove,IL 60515 George T. Jones Pennsylvania Power & Light f' MC A6-1 Two North Ninth Street

• Allentown, PA 18101 -

Lewis H. Sumner ,

Southem Nuclear / Georgia Power E.1. Hatch Nuclear Power Plant U.S. Route 1 North, Box 439 Baxley, GA 31513 i-i L. A. England _ i Entergy Operations Inc. -

PO Box 31995

Jackson, MS 39286

• K.K.Sedney GE Nuclear Energy **

175 Curtner Ave, M/C 182 -

San Jose, CA 95125 uen e . m 4 -

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