ML20248L686
| ML20248L686 | |
| Person / Time | |
|---|---|
| Issue date: | 03/18/1998 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9803240047 | |
| Download: ML20248L686 (31) | |
Text
_ -__ _____ _ _____ - _ _ -
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- g UNITED STATES E
NUCLEAR REGULATORY COMMISSION N
\\ * * * * *,o[f WASHINGTON, D.C. 20666-0001 March 18, 1998
SUMMARY
OF MEETING WITH THE BOILING WATER REACTOR OWNERS GROUP
SUBJECT:
DISCUSS ISSUES RELATED TO THE POTENTIAL LOSS OF EMERGENCY CORE COOLING SYSTEM CAPABILITY DUE TO CLOGGING OF THE SUCTION STRAINERS BY DEBRIS GENERATED DURING A POSTULATED LOSS-OF-COOLANT ACCIDENT On February 6,1998, the staff met with members of the Boiling Water Reactor Owners Group (BWROG) strainer subcommittee to discuss issues related to the potentialloss of emergency core coolant system (ECCS) capability due to clogging of the suction strainers by debris generated during a loss-of-coolant accident (LOCA). A list of the meeting attendees is provided as Attachment 1. Attachment 2 is a copy of the handouts provided by the BWROG.
The purpose of the meeting was to discuss the open items identified by the NRC in its review of the Utility Resolution Guidance (URG) submitted by the BWROG on November 20,1996 (General Electric (GE) Topical Report NEDO-32686, Revision 0, " Utility Resolution Guidance for ECCS Suction Stainer Blockage"). The staff's evaluation was provided to the BWROG in a draft safety evaluation report (SER) dated December 31,1997, in its December 31,1997 letter, the staff requested f"at the BWROG provide its response to the open items by March 2,1998. The purpose of the F "ruary 6,1998, meeting was for the BWROG to provide comments verbally and discuss potenf
.3 solution with the staff prior to its formal written submittal. The BWROG noted that less signi66.1t comments would not be discussed in the meeting, but would be provided in its written sul mittal. The BWROG had 13 specific comments on the SER open items. The following decisions were made conceming resolution of these comments:
1.
In the draft SER, the staff disagreed with URG conclusions related to mixed beds and concluded that the bounding head loss should be determined by summing the values of head loss for fibrous debris / corrosion products and reflective metallic insulation (RMI) debris. The BWROG presented test data that indicated that head loss for a mixed bed decreased when RMIis included. The staff stated that the BWROG should determine whether RMI or fibrous debris is bounding. The BWROG agreed to clarify the URG.
I 2.
The draft SER stated that insufficient information on the use of Jacketing was provided in the URG to determine the acceptability. The BWROG indicated where additionalinformation.,_
could be found in the URG. In addition, the BWROG requested that the use of banding and i
Jacketing be approved generically.
3.
The draft SER concluded that the generic applicability of the URG head loss correlation is not acceptable. The BWROG presented information demonstrating that the maximum head loss occurs at the highest fiber loading. The staff disagreed with the position. It was agreed j
that the BWROG would need to provide additionalinformation to the staff.
4.
The draft SER states that the staff believes that target areas averaged pressure (TAAP)is a g.q more technically correct bases for assessing potential damage from a jet nozzle than the URG's proposal of jet centerline pressure. The BWROG indicated that it has performed an
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additional evaluation to support its position and that this information will be included in its formal response to the draft SER.
5.
The draft SER concluded that the URG's method of defining the zone of influence is unsubstantiated. it was agreed that the URG requires a stronger technical basis.
6.
The draft SER states that damage to calcium silicate should be treated as erosion. The staff expressed concem that the BWROG did not test aged calcium silicate. The BWROG stated that utilities will need to look at the specific calcium silicate application at their plants.
7.
The draft SER states that large debris generated above the lowest grating should not be discounted if the lowest floor grating has substantial openings. The BWROG stated that it believes its approach to be conservative and that it is awaiting issuance of NUREG/CR-6369, "Drywell Debris Transport Study," to complete its evaluation. The staff indicated that the NUREG would be going to the publisher shortly and would be ready for
. issuance after 6 weeks. The staff will determine if a final, unpublished report can be made available to the BWROG sooner.
8.
The draft SER concluded that the URG guidance related to transport fractions for Mark ll containments is non-conservative. The BWROG noted that the draft SER only addresses fibrous debris. The BWROG stated that it will need to evaluate NUREG/CR-6369 to address this item.
9.
The draft SER states that insufficient technical justification was provided for assuming a transport fraction of less than 100 percent for large debris generated below the lowest drywell grating. The BWROG presented additionalinformation and the staff agreed that the BWROG's position is conservative. The staff requested that the BWROG clarify its position in its written response.
- 10. The draft SER concluded that the URG guidance for assuming erosion of large fibrous debris is adequate provided unthrottled ECCS flow does not continue for more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
The BWROG stated that it does not want time-dependent operator actions. The staff will address this comment following receipt of the formal response.
- 11. The draft SER concluded that the destruction factors for some types of insulation were based on a very limited set of experimentation data. The BWROG provided information to support the destruction factors. The staff requested that this additional analysis be documented in the written response.
- 12. The BWROG questioned a statement in the draft SER that temperature correction is unacceptable. The staff stated that this comment only applies to RMI. The BWROG agreed with the staff's response. The SER will be clarified.
- 13. The staff commented that the URG didn't account for particulate mass in debris / head loss calculations. The BWROG stated that it has data which indicates that debris concentration doesn't change. The staff requested that the BWROG reference this test data in its response.
, The meeting also included a discussion of the planned closeout of NRC Bulletin (BL) 96-03. The staff indicated that it expects all hardware modifications to be completed by the end of 1998, but that final closure of BL 96-03 would require resolution of the'open items identified in the staff's draft SER. The staff also indicated that the reviews of Generic Letter (GL) 97-04 responses will be conducted concurrently with closeout of BL 96-03 issues. The BWROG requested that guidance, potentially in the form of a supplement to BL 96-03, be issued that would address the relationship between BL 96-03 and the other outstanding or planned generic communications related to ECCS strainers, the plan for long-term closure, and 10 CFR 50.59 applicability. The staff discussed its proposed plan for on-site review of BL 96-03 implementation. The on-site reviews will begin in spring 1998 with four to six plants. The staff expects to prepare an inspection plan prior to the on-site reviews and to share these plans with each affected utility. If significant findings are identified, additional on-site reviews or inspections may be necessary and a temporary instruction may be prepared. The BWROG indicated that it would appreciate an opportunity to provide comments on any temporary instructions that are developed.
The BWROG had several questions on the applicability of 10 CFR 50.59 for the strainer installations, particularly conceming the number of open items identified by the staff in its review of the URG. The staff stated that its approval or disapproval of specific aspects of the generic URG should not be a factor in determining whether the proposed design constitutes an unreviewed safety question. Additional guidance would be needed from the NRR staff to answer l
specific questions on 10 CFR 50.59 applicability.
in addition to the discussion on the URG, the staff provided the following update on related generic issues:
Responses to GL 97-04 have been received from all BWRs. The staff is evaluating to identify significant issues.
The staff would like to meet with the BWROG to discuss resolution of the issue on containment coatings after the URG SER comments are finalized.
1 The GL on coatings was sent to CRGR last week.
The staff met with GE recently on its topical report and is working with GE to resolve issues l
that were identified.
& W Donna M. Skay, Project Ma er Project Directorate lil-2 l
Division of Reactor Projects Office of Nuclear Reactor Regulation Attachments:
- 1. List of Attendees
- 2. Handouts cc w/att: See next page
.f
-3 March.18, 1998 The meeting also included a dis ssion of the planned closeout of NRC Bulletin (BL) 96-03. The staff indicated that it expects all hardware modifications to be completed by the end of 1998, but
- that final closure of BL 96-03 would require resolution of the open items identified in the staff's draft SER. The staff also indicated that the reviews of Generic Letter (GL) 97-04 responses will s be conducted concurrently with closeout of BL 96-03 issues. The BWROG requested that guidance, potentially in the form of a supplement to BL 96-03, be issued that would address the relationship between BL 96-03 and the other outstanding or planned generic communications related to ECCS strainers, the plan forlong-term closure, and 10 CFR 50.59 applicability. The staff discussed its proposed plan for on-site review of BL 96-03 implementation. The on-site reviews will begin in spring 1998 with four to six plants. The staff expects to prepare an inspection plan prior to the on-site reviews and to share these plans with each affected utility, if significant findings are identified, additional on-site reviews or inspections may be necessary and a temporary instruction may be prepared. The BWROG indicated that it would appreciate an opportunity to provide comments on any temporary instructions that are developed.'
The BWROG had several questions on the applicability of 10 CFR 50.59 for the strainer installations, particularly corcoming the number of open ite'ms identified by the staff in its review of the URG.L The staff stated that its approval or disapproval of specific aspects of the generic -
URG should not be a factor in determining whether the proposed design constitutes an unreviewed safety question. Additional guidance would be needed from the NRR staff to answer specific questions on 10 CFR 50.59 applicability.
In addition to the discussion on the URG, the staff provided the following update on related generic issues:
Responses to GL 97-04 have been received from all BWRs. The staff is evaluating to identify significant issues.
The staff would like to meet with the BWROG to discuss resolution of the issue on containment coatings after the URG SER comments are finalized.
The GL on coatings was sent to CRGR last week.
The staff met with GE recently on its topical report and is working with GE to resolve issues that were identified.
Orig. signed by Donna M. Skay, Project Manager Project Directorate ill-2 Division of Reactor Projects Office of Nuclear Reactor Regulation Attachments:
- 1. List of Attendees
- 2. Handouts See next oaoe for distribution cc w/att: See next page DOCUMENT NAME: G:\\CMNTSP\\SKAY\\020698. SUM See Previous Concurrence
- To RECEIVE A COPY oF THis DOCUMENT, INDICATE IN THE DoX:"C" = COPY WITHouT ENCLOSURES "E" = COPY WITH ENCLOSURES "N" e
OFFICE PM:PD3/2 J.,.
LA:Pp3[2 f [
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OFFICIAL RECORD COPY
.. March 18,1998 The meeting also included a discussion of the planned closeout of NRC Bulletin (BL) 96-03. The staff indicated that it expects all hardware modifications to be completed by the end of 1998, but that final closure of BL 96-03 would require resolution of the open items identified in the staffs draft SER. The staff also indicated that the reviews of Generic Letter (GL) 97-04 responses will be conducted concurrently with closeout of BL 96-03 issues. The BWROG requested that guidance, potentially in the form of a supplement to BL 96-03, be issued that would address the relationship between BL 96-03 and the other outstanding or planned generic communications related to ECCS strainers, the plan for long-term closure, and 10 CFR 50.59 applicability. The staff discussed its proposed plan for on-site review of BL 96-03 implementation. The on-site reviews will begin in spring 1998 with four to six plants. The staff expects to prepare an inspection plan prior to the on-site reviews and to share these plans with each affected utility. If significant findings are identified, additional on-site reviews or inspections may be necessary and a temporary instruction may be prepared. The BWROG indicated that it would appreciate an opportunity to provide comments on any temporary instructions that are developed.
The BWROG had several questions on the applicability of 10 CFR 50.59 for the strainer installations, particularly concoming the number of open items identified by the staff in its review l
of the URG. The staff stated that its approval or disapproval of specific aspects of the generic l
URG should not be a factor in determining whether the proposed design constitutes an l
unreviewed safety question. Additional guidance would be needed from the NRR staff to answer specific questions on 10 CFR 50.59 applicability.
In addition to the discussion on the URG, the staff provided the following update on related generic issues:
)
Responses to GL 97-04 have been received from all BWRs. The staff is evaluating to identify significant issues.
The staff would like to meet with the BWROG to discuss resolution of the issue on containment coatings after the URG SER comments are finalized.
The GL on coatings was sent to CRGR last week.
i The staff met with GE recently on its topical report and is working with GE to resolve issues j
that were identified.
Orig. signed by Donna M. Skay, Project Manager Project Directorate lil-2 Division of Reactor Projects Office of Nuclear Reactor Regulation Attachments:
I
- 1. List of Attendees
(.
- 2. Handouts See next omae for distribution DOCUMENT NAME: G:\\CMNTSPtSKAY\\020698. SUM See Previous Concurrence
- T@ RECElvE A COPY of THis DOCUMENT, INDICATE IN THE box:"C" = COPY WITHouT ENCLOSURES "E" = copy WITH ENCLOSURES "N" i
OFFICE PM.PDW2 b
[Ahh O AiRR:SCS8 D:PDy2 G
DsMAY:sp h 1/4hE RELuo?
RCAPRA M NAME DATE y 6 se wG me st2ms y tS se OFFICIAL RECORD COPY
The meeting also included a discussion of the planned closeout of NRC Bulletin (BL) 96-03. The staff indicated that it expects all hardware modifications to be completed by the end of 1998, but that final closure of BL 96-03 would require resolution of the'open items identified in the staff's draft SER. The staff also indicated that the reviews of Generic Letter (GL) 97-04 responses will be conducted concurrently with closeout of BL 96-03 issues. The BWROG requested that guidance, potentially in the form of a supplement to BL 96-03, be issued that would address the relationship between BL 96-03 and the other outstanding or planned generic communications related to ECCS strainers, the plan for long-term closure, and 10 CFR 50.59 applicability. The staff discussed its proposed plan for on-site review of BL 96-03 implementation. The on-site reviews will begin in spring 1998 with four to six plants. The staff expects to prepare an inspection plan prior to the on-site reviews and to share these plans with each affected utility. If significant findings are identified, additional on-site reviews or inspections may be necessary and a temporary instruction may be prepared. The BWROG indicated that it would appreciate an opportunity to provide comments on any temporary instructions that are developed.
I The BWROG had several questions on the applicability of 10 CFR 50.59 for the strainer l
installations, particularly concoming the number of open items identified by the staff in its review of the URG. The staff stated that its approval or disapproval of specific aspects of the generic URG should not be a factor in determining whether the proposed design constitutes an unresolved safety question. The staff stated that it would need additional guidance from the l
NRR staff to answer specific questions on 10 CFR 50.59 applicability.
In addition to the discussion on the URG, the staff provided the following update on relatsd generic issues:
Responses to GL 97-04 have been received from all BWRs. The staff is evaluating to identify significant issues.
j 1
l The staff would like to meet with the BWROG to discuss resolution of the issue on 1
l-containment coatings after the URG SER comments are finalized.
The GL on coatings was sent to CRGR last week.
(
l The staff met with GE recently on its topical report and is working with GE to resolve issues i
l l
that were identified.
/
f.
Donna M. Skay, Project Manager l
/
Project Directorate lil-2 l
Division of Reactor Projects Office of Nuclear Reactor Regulation j
Attachments:
/
- 1. List of Attendees
- 2. Handouts See next Daoe for distribution DOCUMENT NAME: G:\\CMNTSP\\SKAY\\020698. SUM T3 RECEIVE A COPY oF THis DOCUMENT, INotCATE IN THE aox:"C" = COPY WITHouT ENCLOSURES *E" = COPY WITH ENCLOSURES "N" OFFICE PM.PD3/2
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NRR:SCSB 6
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OFFICIAL RECORD COPY
l l
DISTRIBUTION FOR
SUMMARY
OF MEETING HELD FEBRUARY 6,1998, WlTH IHE BGiLING l
WATER REACTOR OWNERS GROUP i
DISTRIBUTION:
Hard Copy w/ encl 1 and 2:
Central Files PUBLIC PD 111/2 r/f D. Skay OGC i
ACRS E-MAIL w/end 1 only:
S. Collins /F. Miraglia (SJC1/FJM)
B. Boger (BAB2)
E. Adensam (EGA1)
R. Capra (RAC1)
C. Moore (ACM)
T. Martin (SLM3)
T. Hiltz (TGH)
' C. Berlin 0er (CHB)
J. Kudrick (JAK1)
A. Serkiz (AWS)
M. Marshall (MXM2)
K. Kavanaugh (KAK)
R. Elliot (RBE)
R. Lobel (RML)
L-_-___----___-.__
Rocky Sgarro, Chairman BWR Owners' Group ECCS Suction Strainer Committee clo Pennsylvania Power & Light 2 North Ninth Street, Mail Code GENA 61 Allsiltown, PA Thomas A. Green, Technical Project Manager General Electric Company 175 Curtner Avenue, Mail Code 182 San Jose, CA 95125 Thomas J. Rausch, Chairman BWR Owners' Group c/o Commonwealth Edison Nuclear Fuel Services 1400 Opus Place Downers Grove, IL 60515 s
l l
)
BWR OWNERS GROUP MEETING ATTENDANCE LIST FEBRUARY 5-6,1998 NAME UTILITY / PLANT Tom Green GE Dan Marot Sequoia Consulting Bill Houston Sequoia Consulting Jeff Brauwn Southem Nuclear Barry Barkley PSE&G/ Hope Creek Tom Morales WPPSS'WNP-2 Jim Brower Supply System /WNP-2 Girija Shukla DECO / Fermi 2 Bob Bryer Detroit Edison /Formi 2 Steven P. Brown Comed /LaSalle County Gilbert Ziglor ITS Corp Jeff Drowley Commonwealth Edison John Eglaston Comed
' Pasquale Bartolini Niagara Mohawk /NMP-1 Dana Smith EOl/GGNS Paula B. Politzi NMPC/NMP-1 Patrick A. Tobin NSP/Monticello Alan Bilanin Continuum Dynamics Steve Hufbech IES Utilities /DAEC
' Theodore Hilston First Energy / Perry Rick Ingram Entergy/ Grand Gulf John C. Pulford Vermont Yankee Greg Ashlem Duke Engineering Michael Jones NMPC/NMP 2 Richard Tripp CP&UBrunswick Boyd Stanley CP&UBrunswick Jon Arterbum DE&S Ronnie Cole Entergy/Riverbend John Lynch GE Bob Rybak Comed Rick Pistolas PP&USusquehanna Tom Oldennabe PP&USUSQ Mark Mjaatvedt PP&USusquehanna Rocky Sgarro PP&L Susquehanna Ed Hoslerman PECO/ Limerick / Peach Bottom Norm Hoy NYPA/JAFNPP Joan Butler NEl Jan Lefter JAF/NYPA Gordon Hart PCI John C. Pulford VY Chris Slongo Ontario Hydro Tom O'Reilly NUS/LIS Tom Rausch Comed /BWROG Al Serkiz USNRC D. V. Rao SEA, Inc.
Michael Marshall USNRC Donna Skay USNRC Kerri Kavanagh USRC Rob Elliott USNRC Caroline Schlaseman MPR Associates Richard Lobel USNRC Dave Modeon NEl ATTACHMENT 1 l
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