ML20236L106

Summary of 980204 Meeting W/Util in Rockville,Md Re Methodologies Being Implemented by Ies Utilities,Inc to Resolve Issued Identified by NRC Bulletin 96-003.List of Meeting Participants & Handouts Encl

ML20236L106
Person / Time
Site:	Duane Arnold
Issue date:	06/29/1998
From:	Richard Laufer NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
IEB-96-003, IEB-96-3, NUDOCS 9807100225
Download: ML20236L106 (64)

Text

_

June 29, 1998

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LICENSEE: IES Utilities Inc.

FACILITY: Duane Amold Energy Center

SUMMARY

OF FEBRUARY 4,1998, MEETING TO DISCUSS THE RESOLUTION OF NRC BULLETIN 96-03 ISSUES AT THE DUANE ARNOLD ENERGY CENTER On February 4,1998, NRC staff met in Rockville, Maryland, with representatives of IES Utilities Inc. The purpose of the meeting was to discuss the methodologies being implemented by IES Utilities Inc. at the Duane Amold Energy Center to resolve issues identified by NRC Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors." A list of the meeting participants is included as Enclosure 1, and a copy of the meeting handouts is provided as Enclosure 2.

The licensee presented information on the design of their emergent:y core cooling system (ECCS) suction strainers. The licensee's presentation included discussions of the net positive suction head (NPSH) analysis, debris generation, structural analysis of the strainers, and licensing considerations. The NRC staff raised several questions during the licensee's discussion. The staff's questions included concems regarding the testing of the strainer and the potential for an increased reliance on containment overpressure. No issues were resolved as a result of this meeting.

Original signed by:

Richard J. Laufer, Project Manager Project Directorate 111-3 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosures:

1. List of Meeting Participants

2. Meeting Handouts __ .g cc w/encis: See next page M Ed "" #

DISTRIBUTION Hard Copy w/encls [/

Docket File E-mail w/ Encl 1 //

SCollins (SJC1) JKudrick (JAK1)

PD lil-3 Reading FMiraglia (FJM) TD'Angelo (TXD)

PUBLIC THiltz (TGH) KKavanagh (KAK)

GGrant, Rlli BBoger (BAB2) RElliot (RBE) f)g RLaufer DSkay (DMS6)

EAdensam (EGA1)

RBellamy (RRB1) RLobel (RML)

/// d[

Hard Coov w/Enct 1 Pray (PMR)

OGC ACRS DOCUMENT NAME: G:\DUANEARN\DA96144.MTS OFFICE PD3-3:PM lC PD3-3:LA O NAME RLaufer EA- EBamhill (' W DATE 6/F[/98 M f98 OFFICIAL RECORD COPY q

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9807kb05!25980629 PDR ADOCK 05000331 G PDR 2

l June 29, 1998 LICENSEE: IES Utilitias Inc.

FACILITY: Duane Amold Energy Center

SUMMARY

OF FEBRUARY 4,1998, MEETING TO DISCUSS THE RESOLUTION OF NRC BULLETIN 96-03 ISSUES AT THE DUANE ARNOLD ENERGY CENTER l On February 4,1998, NRC staff met in Rockville, Maryland, with representatives of IES Utilities  !

l Inc. The purpose of the meeting was to discuss the methodologies being implemented by lES 1 l

Utilities Inc. at the Duane Amold Energy Center to resolve issues identified by NRC Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors." A list of the meeting participants is included as Enclosure 1, and a copy of the meeting handouts is provided as Enclosure 2.

The licensee presented information on the design of their emergency core cooling system (ECCS) suction strainers. The licensee's presentation included discussions of the net positive suction head (NPSH) analysis, debris generation, structural analysis of the strainers, and licensing considerations. The NRC staff raised several questions during the licensee's discussion. The staff's questions included concems regarding the testing of the strainer and the i potential for an increased reliance on containment overpressure. No issues were resolved as a l result of this meeting.

Original signed by:

Richard J. Laufer, Project Manager I Project Directorate 111-3 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation l Docket No. 50-331

Enclosures:

1. List of Meeting Participants

2. Meeting Handouts cc w/encis: See next page DISTRIBUTION Hard Coov w/encis E-mail w/ Encl 1 Docket File SCollins (SJC1) JKudrick (JAK1) .

PD 111-3 Reading FMiraglia (FJM) TD'Angelo (TXD)

PUBLIC THiltz (TGH) KKavanagh (KAK)

GGrant, Rlli BBoger (BAB2) RElliot (RBE)

RLaufer EAdensam (EGA1) DSkay (DMS6) i RBellamy (RRB1) RLobel(RML) ,

Hard Copy w/Enci 1 Pray (PMR)  !

OGC l ACRS DOCUMENT NAME: G:\DUANEARN\DA96144.MTS l OFFICE PD3-3:PM C PD3-3:LA Q, RLaufer P.-

! NAME EBamhill V W DATE f/#f/98 k/#98 OFFICIAL RECORD COPY l

u________________________ _

p ter ug g t,-

UNITED STATES j

i g NUCLEAR REfiULATORY COMMISSION e WASHINGTON, D.C. 30666 0001 o% ***/ June 29, 1998 LICENSEE: lES Utilities Inc.

FACILITY: Duane Amold Energy Center

SUMMARY

OF FEBRUARY 4,1998, MEETING TO DISCUSS THE RESOLUTION OF NRC BULLETIN 96-03 ISSUES AT THE DUANE ARNOLD ENERGY CENTER l On February 4,1998, NRC staff met in Rockville, Maryland, with representatives of IES Utilities Inc. The purpose of the meeting was to discuss the methodologies being implemented by IES Utilities Inc. at the Duane Amold Energy Center to resolve issues identified by NRC Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors." A list of the meeting participants is included as Enclosure 1, and a copy of the meeting handouts is provided as Enclosure 2.

The licensee presented information on the design of their emergency core cooling system (ECCS) suction strainers. The licensee's presentation included discussions of the net positive suction head (NPSH) analysis, debris generation, structural analysis of the strainers, and licensing considerations. The NRC staff raised several questions during the licensee's discussion. The staff's questions included concems regarding the testing of the strainer and the potential for an increased reliance on containment overpressure. No issues were resolved as a result of this meeting.

Richard J. Laufer, Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosures:

1. List of Meeting Participants l

2. Meeting Handouts I cc w/encis: See next page i

i p

l

t ,

' Lee Liu Duane Arnold Energy Center

.lES Utilities Inc.

cc:

Jack Newman, Esquire Al Gutterman, Esquire Morgan, Lewis, & Bockius 1800 M Street, NW.

Washington, DC 20036-5869 Chairman, Linn County Board of Supervisors Cedar Rapids,IA 52406 l IES Utilities Inc.

I ATTN: Gary Van Middlesworth Plant Superintendent, Nuclear 3277 DAEC Road Palo,IA 52324 l John F. Franz, Jr.

l Vice President, Nuclear Duane Arnold Energy Center 3277 DAEC Road Palo,IA 52324 l Ken Peveler Manager of Regulatory Performance Duane Arnold Energy Center 3277 DAEC Road Palo,IA 52324 U.S. Nuclear Regulatory Commission Resident inspector's Office Rural Route #1 Palo,lA 52324 1

Regional Administrator, Rlli U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4531 Parween Baig Utilities Divis~ ion ,

Iowa Department of Commerce Lucas Office Building,5th floor Des Moines,IA 50319  ;

I l

1 l

i

s- ,

[ --

MEETING ATTENDEES NRC AND lES UTILITIES INC.

DISCUSSION OF RESOLUTION OF BULLETIN 96-03 FEBRUARY 4,1998 NAME AFFILIATION P.' Ray NRC R. Lobel NRC J. Kudrick NRC T. D'Angelo NRC K Kavanagh NRC R. Elliott NRC D. Skay NRC R. Laufer NRC J. Johnson IES Utilities Inc.

M. McDermott IES Utilities Inc.

S. Huebsch IES Utilities Inc.

K. Peveler IES Utiiities Inc.

C. Rushworth IES Utilities Inc.

J. Azmeh IES Utilities Inc.

D. Lemm lES Utilities Inc.

T. Vogel Duke Engineering & Services J. Attwood Duke Engineering & Services J. Lynch General Electric 1

i Enclosure 1

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1 AGENDA 1/29/98  ;

1 Resolution of NRC Bulletin 96-03 by Duane Arnold Energy Center

Purpose:

l The goal of this meeting is to facilitate open discussion between the DAEC Project Team j and the NRC. We should expect to discuss the methodologies being implemented by the

~DAEC team to resolve issues identified by NRC Bulletin 96-03. Identification of concerns and open issues will be paramount to the success of the discussion.

1 Morning Session - 10:00AM i

• Introduction Steve Huebsch Project Manager e introduction of team IES Utilities e general plant parameters of significance e methodologies used l

• NPSH Analysis John Johnson IES e containment analysis Steve Huebsch IES e strainer headloss GE method John Lynch GE

. NPSH calculations 1 1

• Debris Generation

. URG Methodology Steve Huebsch IES I

Afternoon Session i 1

i

• Structural Analysis Jamal Azmeh IES I e strainer sizing John Lynch GE I

. MARKI analysis Tom Vogel DE&S Joe Attwood DE&S l = development ofload factors John Lynch GE l

• Licensing considerations Clara Rushworth IES e SER on GE LTR L e SER on BWROG Utility Resolution Guide

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, APPENDIX-A Rev.C l DATA SHEET:

STRAINER ASSEMBLIES Performance Characteristic Design Limit (s)

Screen Opemng Size 1/8" diameter (Nommal)

Design Temperature 40-205 'F Normal Operating Temperature 85-100 *F RHR Min. Flow / Strainer 500 gpm Maximum RHR Flow Rate per Strainer Assembly 13,000 gpm (first 10 minutes) l Maximum CS Flow Rate per Strainer Assembly 4,500 gpm (first 10 minutes) -

Maximum time period prior to a reduction in flow rate 10 minutes (RHR) i l through the RHR and CS Strainer Assemblies 10 minutes (CS)

Rated Flow Rate thmugh the RHR Stramer Assemblies after 9,600 gpm i 10 minutes Rated Flow Rate through the CS Strainer Assemblies after 3,100 gpm 10 minutes Minimum Required Toms Water Volume 440,600 Gallons Maximum Allowable Head Loss through Debris Covered 16 A at 202.4 'F and 9,600 gpm RHR Strainers Assemblies Maximum Allowable Head Loss through Debris Covered 13.4 A water at 202.4 *F and 3100 gpm CS Strainers Assemblies RHR Connecting Flanges 24" diameter ANSI B16.5,150# Flange I CS Connecting Flanges 24" diameter ANSI B16.5,150# Flange RHR Torus Penetrations (2 Pumps per each Penetration) N225A N225B CS Torus Penetrations N227A

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Design Life 40 years Debris Leading at Strainer ,

e Fiber 150 A' e Sludge 500lbs e Dirt / Dust 150 lbs

• Rust 50lbs e Paint Chips- quali6ed 71lbs e unqualified 71lbs e Zinc Dust ,

47 lbs.

e equipment Tag (2.5" X 4.5"), and tape pieces 50ea.

• RMI 308 A2(SeeNote 1)

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Notes: 1. Mirror Insulation encased between outer reactor and bioshield wall is ignored. The identified RMI is located on a 4" RCIC line in the zone ofinfluence. DAEC is a 100%

fiberinsulation plant.

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