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{{#Wiki_filter:Official Transcript of Proceedings  
{{#Wiki_filter:United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.
 
In the Matter of:
NUCLEAR REGULATORY COMMISSION  
(Indian Point Nuclear Generating Units 2 and 3)
 
ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000561-00-BD01                  Identified: 10/15/2012 Admitted: 10/15/2012                        Withdrawn:
Title:   Advisory Committee on Reactor Safeguards     Plant License Renewal Subcommittee Docket Number: (n/a) Location:   Rockville, Maryland Date:   Wednesday, August 18, 2010 Work Order No.: NRC-387 Pages 1-147 NEAL R. GROSS AND CO., INC.
Rejected:                                      Stricken:
Other:                                                                                ENT000561 Submitted: August 20, 2012 Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title:                       Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Docket Number:                         (n/a)
Location:                               Rockville, Maryland Date:                                   Wednesday, August 18, 2010 Work Order No.:                         NRC-387                             Pages 1-147 NEAL R. GROSS AND CO., INC.
Court Reporters and Transcribers 1323 Rhode Island Avenue, N.W.
Court Reporters and Transcribers 1323 Rhode Island Avenue, N.W.
Washington, D.C. 20005 (202) 234-4433 ENT000561 Submitted: August 20, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of
Washington, D.C. 20005 (202) 234-4433
: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)
ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:
Identified:
Admitted: Withdrawn:
Rejected: Stricken: Other: ENT000561-00-BD01 10/15/2012 10/15/2012 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 1 1 DISCLAIMER 2 3 4
5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22  UNITED STATES NUCLEAR REGULATORY COMMISSIONS ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
 
The contents of this transcript of the
 
proceeding of the United States Nuclear Regulatory
 
Commission Advisory Committee on Reactor Safeguards, as reported herein, is a record of the discussions
 
recorded at the meeting. 
 
This transcript has not been reviewed, corrected, and edited, and it may contain
 
inaccuracies. 
 
NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 2 UNITED STATES OF AMERICA 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 NUCLEAR REGULATORY COMMISSION
+ + + + +  ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) PLANT LICENSE RENEWAL SUBCOMMITTEE KEWAUNEE POWER STATION
+ + + + +
WEDNESDAY, AUGUST 18, 2010
+ + + + +  ROCKVILLE, MARYLAND
+ + + + +  The Subcommittee met at the Nuclear
 
Regulatory Commission, Two White Flint North, Room
 
T2B1, 11545 Rockville Pike, at 8:30 a.m., Mario
 
Bonanca, Chairman, presiding.
 
SUBCOMMITTEE MEMBERS:
MARIO V. BONACA, Chairman J. SAM ARMIJO, Member CHARLES H. BROWN, Member WILLIAM J. SHACK, Member JOHN W. STETKAR, Member NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 3 DESIGNATED FEDERAL OFFICIAL:
1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25  GIRIJA S. SHUKLA
 
CONSULTANT:
JOHN J. BARTON
 
NRC STAFF:
BRIAN HOLIAN, NRR JOHN DAILY, NRR DAVID PELTON, NRR BILL ROGERS CAROLINE TILTON, Region III
 
DOMINION ENERGY KEWAUNEE:
PAUL AITKEN PHIL BUKES MIKE HALE MARK HOTCHKISS JIM RUSCH BEN RODILL STEVE SCASE CHARLIE SORRELL BILL WEBSTER MICHAEL WILSON DAVID WOOTEN STEW YUEN NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 4 C-O-N-T-E-N-T-S 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 AGENDA ITEM                            PAGE
 
Opening Remarks                            4
 
Staff Introduction                        5
 
Dominion Energy/Kewaunee Presentation      8
 
NRC Staff Presentation                    86 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 68 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25  MR. SCACE:  But I think what Paul
 
indicated is, we are using that experience and demonstrating the opportunistic if you would views. 
 
And those are conditioned based on experience as you'd
 
expect over 40 years. So some inspection frequencies
 
we do more often, and will continue to do that. They
 
will now be documented under this new program, but we
 
are not going to start at ground zero because we have
 
a new program. So a major part of this other than
 
those we determine we haven't had sufficient
 
opportunistic opportunities, that program and that
 
experience will continue with our inspection.
MEMBER STETKAR:  Okay, thanks, that helps
 
a little bit, thanks.
MR. AITKEN:  Next slide.
So the third open item relates to steam
 
generator divider plate cracking. On this item the
 
staff requested additional information from Kewaunee
 
related to the materials of construction  of the steam
 
generator divider blade, and the weather cracks in the
 
alloy 600 divider plate could propagate into the base
 
material of the channel head or into the tube sheet
 
platen.
If we determined that this condition was
 
likely then the staff requested that the details of an NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 69 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 inspection be provided for review. As Brian mentioned
 
the request was based in part on I believe French OE
 
with the divider plate cracking.
MEMBER STETKAR:  Paul, before you go back
 
to the other slide, the last bullet on there, it says
 
recent - oh recent foreign operating experience. I'll
 
ask you now before you get into the materials things
 
that I don't understand anything about, you replaced
 
the steam generators in 2001. In 2006 apparently you
 
discovered a number of foreign objects in both your
 
steam generators. All I know is what I read in the
 
reports. Five foreign objects in steam generator A
 
and nine foreign objects in steam generator B.
This has nothing to do with the topic of
 
what you are talking about here as far as primary
 
water stress corrosion cracking, but at least the
 
steam generators - and I was going to ask you later
 
anyway so I might as well do it now. What were they?
Where did they come from?  And do you have a loose
 
parts monitoring system?
MR. HANNA:  Tim Hanna for the applicant. 
 
We do have a loose parts monitoring system. All of
 
the parts that you are referring to were on the
 
secondary side of the steam generators, and they were
 
very small remnants for manufacturing such as weld VBs NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 70 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 or very small machine turnings. And they were either
 
removed from the steam generators or evaluated as
 
acceptable for continued service, due to the very
 
small volume of the material.
MEMBER STETKAR:  So they were - you
 
actually determined that they had been in there since
 
the original installation?
MR. HANNA:  That is correct.
MEMBER STETKAR:  Okay.
CONSULTANT BARTON:  Do they have a loose
 
parts monitoring system?
MEMBER STETKAR:  It's not really a part.
Loose parts monitoring typically picks up more stuff
 
on the primary site. It's pretty messy out on the
 
secondary side.
MR. AITKEN:  Okay, so this issue remains
 
under review by the various experts and technical
 
groups in the industry along with the NRC staff. A
 
meeting was conducted just last week between the NRC
 
and the industry where several people were trying to
 
understand the concern and ascertain what is the best
 
path to resolve this item not only for Kewaunee, but
 
for the other affected plants in the United States.
Dominion remains active in these forums, and if there are any new requirements promulgated to NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 71 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 the industry, then Dominion will evaluate the industry
 
recommendation like the other affected plants and do
 
the right thing.
In response to this open item we concluded
 
that the condition described by the staff is unlikely
 
for Kewaunee for the following reasons. First, the
 
steam generators are relatively new, they're not quite
 
10 years old as Stew had mentioned. They are not
 
likely to experience cracking with this limited
 
service life.
Next, although the divider plates are
 
alloy 600, the divided plate assembly welds are made
 
from alloy 52/152 weld metal which is inherently
 
resistant to cracking caused by PWSCC.
Also we believe there is sufficient data
 
from the industry resource to support the conclusion
 
that PWSCC cracking stops when nonsusceptible
 
materials are encountered.
There is no U.S. or international OEs that
 
Dominion, EPRI or Westinghouse is aware of indicated
 
that cracking of the divider plates has ever
 
propagated into adjacent tube sheets of channel heads.
So based on the above Kewaunee concluded
 
in its response to this open item that an inspection
 
program is not warranted at this time. And that NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W. (202) 234-4433 WASHINGTON, D.C. 20005-3701 www.nealrgross.com 72 1 2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 response has been provided to the staff as of July
 
22 nd , 2010, and is currently under review. And our last open item, relates to the
 
ongoing issue related to buried piping and underground
 
components. First the staff requested that Kewaunee
 
identify systems with components that are in a buried
 
or an underground environment. The staff also
 
requested that we provide any updates related to
 
operating experience with the buried piping that was
 
not included in our application submittal.
First I'd like to address the equipment
 
located in an underground environment, which could be
 
within vaults or chases, and exposed to air on the
 
external surfaces. Kewaunee has very limited


equipment in this category, just a few feet of fuel
1 1
2                                DISCLAIMER 3
4 5  UNITED STATES NUCLEAR REGULATORY COMMISSIONS 6        ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 7
8 9            The contents of this transcript of the 10 proceeding of the United States Nuclear Regulatory 11 Commission Advisory Committee on Reactor Safeguards, 12 as reported herein, is a record of the discussions 13 recorded at the meeting.
14 15            This transcript has not been reviewed, 16 corrected, and edited, and it may contain 17 inaccuracies.
18 19 20 21 22 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433              WASHINGTON, D.C. 20005-3701  www.nealrgross.com


oil transfer piping for our diesel fuel oil system, and a couple of fuel oil transfer pumps. This
2 1                        UNITED STATES OF AMERICA 2                      NUCLEAR REGULATORY COMMISSION 3                                    + + + + +
4                ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 5                                      (ACRS) 6                  PLANT LICENSE RENEWAL SUBCOMMITTEE 7                          KEWAUNEE POWER STATION 8                                    + + + + +
9                                    WEDNESDAY, 10                              AUGUST 18, 2010 11                                    + + + + +
12                            ROCKVILLE, MARYLAND 13                                    + + + + +
14                      The    Subcommittee                met  at  the    Nuclear 15 Regulatory          Commission,        Two      White      Flint  North,        Room 16 T2B1,          11545  Rockville        Pike,          at 8:30  a.m.,        Mario 17 Bonanca, Chairman, presiding.
18 SUBCOMMITTEE MEMBERS:
19              MARIO V. BONACA, Chairman 20              J. SAM ARMIJO, Member 21              CHARLES H. BROWN, Member 22              WILLIAM J. SHACK, Member 23              JOHN W. STETKAR, Member 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433                WASHINGTON, D.C. 20005-3701          www.nealrgross.com


equipment is managed for the effects of aging by the
3 1 DESIGNATED FEDERAL OFFICIAL:
2              GIRIJA S. SHUKLA 3 CONSULTANT:
4              JOHN J. BARTON 5 NRC STAFF:
6              BRIAN HOLIAN, NRR 7              JOHN DAILY, NRR 8              DAVID PELTON, NRR 9              BILL ROGERS 10              CAROLINE TILTON, Region III 11 DOMINION ENERGY KEWAUNEE:
12              PAUL AITKEN 13              PHIL BUKES 14              MIKE HALE 15              MARK HOTCHKISS 16              JIM RUSCH 17              BEN RODILL 18              STEVE SCASE 19              CHARLIE SORRELL 20              BILL WEBSTER 21              MICHAEL WILSON 22              DAVID WOOTEN 23              STEW YUEN 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433                WASHINGTON, D.C. 20005-3701  www.nealrgross.com


visual inspections performed in accordance with the
4 1                    C-O-N-T-E-N-T-S 2 AGENDA ITEM                                      PAGE 3 Opening Remarks                                      4 4 Staff Introduction                                  5 5 Dominion Energy/Kewaunee Presentation                8 6 NRC Staff Presentation                              86 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433      WASHINGTON, D.C. 20005-3701      www.nealrgross.com


external surfaces monitoring program on a period
68 1                    MR. SCACE:              But          I think    what        Paul 2 indicated        is,  we    are      using          that    experience          and 3 demonstrating the opportunistic if you would views.
4 And those are conditioned based on experience as you'd 5 expect over 40 years.                So some inspection frequencies 6 we do more often, and will continue to do that.                                  They 7 will now be documented under this new program, but we 8 are not going to start at ground zero because we have 9 a new program.            So a major part of this other than 10 those          we  determine        we        haven't        had  sufficient 11 opportunistic        opportunities,              that      program   and        that 12 experience will continue with our inspection.
13                    MEMBER STETKAR:              Okay, thanks, that helps 14 a little bit, thanks.
15                    MR. AITKEN:        Next slide.
16                    So the third open item relates to steam 17 generator divider plate cracking.                            On this item the 18 staff requested additional information from Kewaunee 19 related to the materials of construction                          of the steam 20 generator divider blade, and the weather cracks in the 21 alloy 600 divider plate could propagate into the base 22 material of the channel head or into the tube sheet 23 platen.
24                    If we determined that this condition was 25 likely then the staff requested that the details of an NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433              WASHINGTON, D.C. 20005-3701              www.nealrgross.com


frequency.
69 1 inspection be provided for review.                        As Brian mentioned 2 the request was based in part on I believe French OE 3 with the divider plate cracking.
The remaining components that are in a  
4                      MEMBER STETKAR:            Paul, before you go back 5 to the other slide, the last bullet on there, it says 6 recent - oh recent foreign operating experience.                                I'll 7 ask you now before you get into the materials things 8 that I don't understand anything about, you replaced 9 the steam generators in 2001.                          In 2006 apparently you 10 discovered a number of foreign objects in both your 11 steam generators.            All I know is what I read in the 12 reports.          Five foreign objects in steam generator A 13 and nine foreign objects in steam generator B.
14                      This has nothing to do with the topic of 15 what you are talking about here as far as primary 16 water          stress  corrosion        cracking,        but  at  least          the 17 steam generators - and I was going to ask you later 18 anyway so I might as well do it now.                          What were they?
19  Where did they come from?                      And do you have a loose 20 parts monitoring system?
21                      MR. HANNA:        Tim Hanna for the applicant.
22 We do have a loose parts monitoring system.                                All of 23 the        parts    that  you      are      referring      to  were    on        the 24 secondary side of the steam generators, and they were 25 very small remnants for manufacturing such as weld VBs NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433                WASHINGTON, D.C. 20005-3701            www.nealrgross.com


soil environment are managed for the effects of aging
70 1 or very small machine turnings.                            And they were either 2 removed          from  the  steam        generators          or  evaluated          as 3 acceptable          for continued          service,        due  to  the       very 4 small volume of the material.
5                    MEMBER    STETKAR:                So  they  were    -      you 6 actually determined that they had been in there since 7 the original installation?
8                    MR. HANNA:        That is correct.
9                    MEMBER STETKAR:            Okay.
10                      CONSULTANT BARTON:                  Do they have a loose 11 parts monitoring system?
12                      MEMBER STETKAR:              It's not really a part.
13  Loose parts monitoring typically picks up more stuff 14 on the primary site.                  It's pretty messy out on the 15 secondary side.
16                      MR. AITKEN:          Okay, so this issue remains 17 under          review  by  the      various          experts    and  technical 18 groups in the industry along with the NRC staff.                                        A 19 meeting was conducted just last week between the NRC 20 and the industry where several people were trying to 21 understand the concern and ascertain what is the best 22 path to resolve this item not only for Kewaunee, but 23 for the other affected plants in the United States.
24                    Dominion remains active in these forums, 25 and if there are any new requirements promulgated to NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433                WASHINGTON, D.C. 20005-3701            www.nealrgross.com


by the buried piping and tank inspection program which
71 1 the industry, then Dominion will evaluate the industry 2 recommendation like the other affected plants and do 3 the right thing.
4                      In response to this open item we concluded 5 that the condition described by the staff is unlikely 6 for Kewaunee for the following reasons.                                First, the 7 steam generators are relatively new, they're not quite 8 10 years old as Stew had mentioned.                                  They are not 9 likely          to  experience        cracking              with  this    limited 10 service life.
11                      Next,    although            the        divider  plates          are 12 alloy 600, the divided plate assembly welds are made 13 from          alloy  52/152    weld        metal          which  is  inherently 14 resistant to cracking caused by PWSCC.
15                      Also we believe there is sufficient data 16 from the industry resource to support the conclusion 17 that          PWSCC    cracking          stops            when    nonsusceptible 18 materials are encountered.
19                      There is no U.S. or international OEs that 20 Dominion, EPRI or Westinghouse is aware of indicated 21 that          cracking  of      the      divider            plates  has        ever 22 propagated into adjacent tube sheets of channel heads.
23                      So based on the above Kewaunee concluded 24 in its response to this open item that an inspection 25 program         is  not  warranted            at      this      time. And        that NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433                WASHINGTON, D.C. 20005-3701              www.nealrgross.com


I will discuss here in the next few slides.}}
72 1 response has been provided to the staff as of July 2 22nd, 2010, and is currently under review.
3                      And our last open item, relates to the 4 ongoing issue related to buried piping and underground 5 components.          First the staff requested that Kewaunee 6 identify systems with components that are in a buried 7 or        an    underground      environment.                The  staff        also 8 requested          that  we    provide          any      updates    related          to 9 operating experience with the buried piping that was 10 not included in our application submittal.
11                      First I'd like to address the equipment 12 located in an underground environment, which could be 13 within vaults or chases, and exposed to air on the 14 external          surfaces.          Kewaunee            has  very      limited 15 equipment in this category, just a few feet of fuel 16 oil transfer piping for our diesel fuel oil system, 17 and        a  couple    of  fuel        oil      transfer      pumps.          This 18 equipment is managed for the effects of aging by the 19 visual inspections performed in accordance with the 20 external          surfaces    monitoring              program    on  a    period 21 frequency.
22                      The remaining components that are in a 23 soil environment are managed for the effects of aging 24 by the buried piping and tank inspection program which 25 I will discuss here in the next few slides.
NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.
(202) 234-4433                WASHINGTON, D.C. 20005-3701              www.nealrgross.com}}

Latest revision as of 19:21, 11 November 2019

Official Exhibit - ENT000561-00-BD01 - Kewaunee Tr., Advisory Comm. on Reactor Safeguards, Plant License Renewal Subcomm. (Aug. 18, 2010)
ML12340A726
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 08/20/2012
From:
Entergy Nuclear Operations
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 23331, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12340A726 (10)


Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: ENT000561-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:

Rejected: Stricken:

Other: ENT000561 Submitted: August 20, 2012 Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Docket Number: (n/a)

Location: Rockville, Maryland Date: Wednesday, August 18, 2010 Work Order No.: NRC-387 Pages 1-147 NEAL R. GROSS AND CO., INC.

Court Reporters and Transcribers 1323 Rhode Island Avenue, N.W.

Washington, D.C. 20005 (202) 234-4433

1 1

2 DISCLAIMER 3

4 5 UNITED STATES NUCLEAR REGULATORY COMMISSIONS 6 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 7

8 9 The contents of this transcript of the 10 proceeding of the United States Nuclear Regulatory 11 Commission Advisory Committee on Reactor Safeguards, 12 as reported herein, is a record of the discussions 13 recorded at the meeting.

14 15 This transcript has not been reviewed, 16 corrected, and edited, and it may contain 17 inaccuracies.

18 19 20 21 22 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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2 1 UNITED STATES OF AMERICA 2 NUCLEAR REGULATORY COMMISSION 3 + + + + +

4 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 5 (ACRS) 6 PLANT LICENSE RENEWAL SUBCOMMITTEE 7 KEWAUNEE POWER STATION 8 + + + + +

9 WEDNESDAY, 10 AUGUST 18, 2010 11 + + + + +

12 ROCKVILLE, MARYLAND 13 + + + + +

14 The Subcommittee met at the Nuclear 15 Regulatory Commission, Two White Flint North, Room 16 T2B1, 11545 Rockville Pike, at 8:30 a.m., Mario 17 Bonanca, Chairman, presiding.

18 SUBCOMMITTEE MEMBERS:

19 MARIO V. BONACA, Chairman 20 J. SAM ARMIJO, Member 21 CHARLES H. BROWN, Member 22 WILLIAM J. SHACK, Member 23 JOHN W. STETKAR, Member 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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3 1 DESIGNATED FEDERAL OFFICIAL:

2 GIRIJA S. SHUKLA 3 CONSULTANT:

4 JOHN J. BARTON 5 NRC STAFF:

6 BRIAN HOLIAN, NRR 7 JOHN DAILY, NRR 8 DAVID PELTON, NRR 9 BILL ROGERS 10 CAROLINE TILTON, Region III 11 DOMINION ENERGY KEWAUNEE:

12 PAUL AITKEN 13 PHIL BUKES 14 MIKE HALE 15 MARK HOTCHKISS 16 JIM RUSCH 17 BEN RODILL 18 STEVE SCASE 19 CHARLIE SORRELL 20 BILL WEBSTER 21 MICHAEL WILSON 22 DAVID WOOTEN 23 STEW YUEN 24 25 NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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4 1 C-O-N-T-E-N-T-S 2 AGENDA ITEM PAGE 3 Opening Remarks 4 4 Staff Introduction 5 5 Dominion Energy/Kewaunee Presentation 8 6 NRC Staff Presentation 86 7

8 9

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68 1 MR. SCACE: But I think what Paul 2 indicated is, we are using that experience and 3 demonstrating the opportunistic if you would views.

4 And those are conditioned based on experience as you'd 5 expect over 40 years. So some inspection frequencies 6 we do more often, and will continue to do that. They 7 will now be documented under this new program, but we 8 are not going to start at ground zero because we have 9 a new program. So a major part of this other than 10 those we determine we haven't had sufficient 11 opportunistic opportunities, that program and that 12 experience will continue with our inspection.

13 MEMBER STETKAR: Okay, thanks, that helps 14 a little bit, thanks.

15 MR. AITKEN: Next slide.

16 So the third open item relates to steam 17 generator divider plate cracking. On this item the 18 staff requested additional information from Kewaunee 19 related to the materials of construction of the steam 20 generator divider blade, and the weather cracks in the 21 alloy 600 divider plate could propagate into the base 22 material of the channel head or into the tube sheet 23 platen.

24 If we determined that this condition was 25 likely then the staff requested that the details of an NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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69 1 inspection be provided for review. As Brian mentioned 2 the request was based in part on I believe French OE 3 with the divider plate cracking.

4 MEMBER STETKAR: Paul, before you go back 5 to the other slide, the last bullet on there, it says 6 recent - oh recent foreign operating experience. I'll 7 ask you now before you get into the materials things 8 that I don't understand anything about, you replaced 9 the steam generators in 2001. In 2006 apparently you 10 discovered a number of foreign objects in both your 11 steam generators. All I know is what I read in the 12 reports. Five foreign objects in steam generator A 13 and nine foreign objects in steam generator B.

14 This has nothing to do with the topic of 15 what you are talking about here as far as primary 16 water stress corrosion cracking, but at least the 17 steam generators - and I was going to ask you later 18 anyway so I might as well do it now. What were they?

19 Where did they come from? And do you have a loose 20 parts monitoring system?

21 MR. HANNA: Tim Hanna for the applicant.

22 We do have a loose parts monitoring system. All of 23 the parts that you are referring to were on the 24 secondary side of the steam generators, and they were 25 very small remnants for manufacturing such as weld VBs NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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70 1 or very small machine turnings. And they were either 2 removed from the steam generators or evaluated as 3 acceptable for continued service, due to the very 4 small volume of the material.

5 MEMBER STETKAR: So they were - you 6 actually determined that they had been in there since 7 the original installation?

8 MR. HANNA: That is correct.

9 MEMBER STETKAR: Okay.

10 CONSULTANT BARTON: Do they have a loose 11 parts monitoring system?

12 MEMBER STETKAR: It's not really a part.

13 Loose parts monitoring typically picks up more stuff 14 on the primary site. It's pretty messy out on the 15 secondary side.

16 MR. AITKEN: Okay, so this issue remains 17 under review by the various experts and technical 18 groups in the industry along with the NRC staff. A 19 meeting was conducted just last week between the NRC 20 and the industry where several people were trying to 21 understand the concern and ascertain what is the best 22 path to resolve this item not only for Kewaunee, but 23 for the other affected plants in the United States.

24 Dominion remains active in these forums, 25 and if there are any new requirements promulgated to NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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71 1 the industry, then Dominion will evaluate the industry 2 recommendation like the other affected plants and do 3 the right thing.

4 In response to this open item we concluded 5 that the condition described by the staff is unlikely 6 for Kewaunee for the following reasons. First, the 7 steam generators are relatively new, they're not quite 8 10 years old as Stew had mentioned. They are not 9 likely to experience cracking with this limited 10 service life.

11 Next, although the divider plates are 12 alloy 600, the divided plate assembly welds are made 13 from alloy 52/152 weld metal which is inherently 14 resistant to cracking caused by PWSCC.

15 Also we believe there is sufficient data 16 from the industry resource to support the conclusion 17 that PWSCC cracking stops when nonsusceptible 18 materials are encountered.

19 There is no U.S. or international OEs that 20 Dominion, EPRI or Westinghouse is aware of indicated 21 that cracking of the divider plates has ever 22 propagated into adjacent tube sheets of channel heads.

23 So based on the above Kewaunee concluded 24 in its response to this open item that an inspection 25 program is not warranted at this time. And that NEAL R. GROSS COURT REPORTERS AND TRANSCRIBERS 1323 RHODE ISLAND AVE., N.W.

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72 1 response has been provided to the staff as of July 2 22nd, 2010, and is currently under review.

3 And our last open item, relates to the 4 ongoing issue related to buried piping and underground 5 components. First the staff requested that Kewaunee 6 identify systems with components that are in a buried 7 or an underground environment. The staff also 8 requested that we provide any updates related to 9 operating experience with the buried piping that was 10 not included in our application submittal.

11 First I'd like to address the equipment 12 located in an underground environment, which could be 13 within vaults or chases, and exposed to air on the 14 external surfaces. Kewaunee has very limited 15 equipment in this category, just a few feet of fuel 16 oil transfer piping for our diesel fuel oil system, 17 and a couple of fuel oil transfer pumps. This 18 equipment is managed for the effects of aging by the 19 visual inspections performed in accordance with the 20 external surfaces monitoring program on a period 21 frequency.

22 The remaining components that are in a 23 soil environment are managed for the effects of aging 24 by the buried piping and tank inspection program which 25 I will discuss here in the next few slides.

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