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{{#Wiki_filter:_______ _ _____
{{#Wiki_filter:_______ _ _____
  ,/         %o~
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UNITED STATES                                             l
%o UNITED STATES l
!',              c              NUCLEAR REGULATORY COMMISSION                                             I
NUCLEAR REGULATORY COMMISSION I
'g               .E                           - WASHINGTON, D. C. 20656
~
    % ,,,, .                                        JllN 2 4 tgg7 Paul G. Kuhel Supervisor of Station Support Services                                                               j Nuclear Services Technical                                                                           l Commonwealth Edison Company 72 West Adams, Room 1248E Chicago, IL 60690-0767
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- WASHINGTON, D. C. 20656 JllN 2 4 tgg7 Paul G. Kuhel Supervisor of Station Support Services j
Nuclear Services Technical l
Commonwealth Edison Company 72 West Adams, Room 1248E Chicago, IL 60690-0767


==Dear Mr. Kuhel:==
==Dear Mr. Kuhel:==
==Subject:==
==Subject:==
COMMENTS ON PROPOSED VALVE FAILURE REPORTING CRITERIA - NPRDS USERS GROUP (NUG)MEETINGNO.12 ACTION 4.5 In our previous NUG meeting, you led a discussion and provided recommendations for improved guidance on identifying and reporting valve failures. All NUG members were asked to provide comments, from a user's point of view, on the proposed valve failure reporting criteria. Therefore, we have enclosed the attached markup which incorporates our comments. We have also enclosed an example of one plant's local leak rate acceptance criteria upon which operabi-                       l is d
COMMENTS ON PROPOSED VALVE FAILURE REPORTING CRITERIA - NPRDS USERS GROUP (NUG)MEETINGNO.12 ACTION 4.5 In our previous NUG meeting, you led a discussion and provided recommendations for improved guidance on identifying and reporting valve failures. All NUG members were asked to provide comments, from a user's point of view, on the proposed valve failure reporting criteria. Therefore, we have enclosed the attached markup which incorporates our comments. We have also enclosed an example of one plant's local leak rate acceptance criteria upon which operabi-l lity of a specific valve (e.g., MSIV) fio~s etermjA is d d.
: d. As indicated in the lity of a specific valve (e.g., MSIV) ntgehsent.                                      fio~s etermjA ethat~l       eTalves'                         a ocaT" WaTFf8 e"                       'W11Ts7iFYtttegratot7 shevWhidered2as:vepensable.~as As users of the NPRDS in reliability studies (e.g., NPRDS Trends and Patterns Program), we would appreciate your consideration of the enclosed comments dur-                       ,
As indicated in the ntgehsent.
ing development of the revised criteria for the next meeting. Please direct                         '
ethat~l eTalves' a
any questions that you may have regarding this subject to Mr. G.L. Plumlee (301-492-4492).                                                                                      .
' ocaT" WaTFf8 e"
'W11Ts7iFYtttegratot7 shevWhidered2as:vepensable.~as As users of the NPRDS in reliability studies (e.g., NPRDS Trends and Patterns Program), we would appreciate your consideration of the enclosed comments dur-ing development of the revised criteria for the next meeting. Please direct any questions that you may have regarding this subject to Mr. G.L. Plumlee (301-492-4492).
1 i
1 i
Sincerely                                               )
Sincerely
R. L. Dennig, Member p
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NPRDS Users Group I
p R. L. Dennig, Member NPRDS Users Group I
cc: P. Lyons, INPO W. Conway, INPO R. Simard, INPO J. Crooks Fo*L 4-8 7-(/6{
cc: P. Lyons, INPO W. Conway, INPO R. Simard, INPO J. Crooks Fo*L 4-8 7-(/6{
M. Williams G//3 1
M. Williams G//3 1
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8709150099 870911 DO 465 PDR I


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                                                                                    !)                                           :r Mr. Paul G. Kuhel                       .4                                         -2 I'       t ei     ;
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As users of the NPRDS/in reliability studies (e.g., NPRDS Trends and Patterns Program), we would appreciate your consideration of the enclosed comments dur-ing development of the rq9 sed criteria for the next me? ting. Please direct
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                          -any' questions that;.,(ou rrzy have regarding this subject to Mr. G.L. Plumlee (301-4924492),                                   '
! )
                                                                                ,                e
:r Mr. Paul G. Kuhel
                                                        >                                        l J                                                                                                       1
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                                                                                                  . Sincere 1y, t
-2 I'
R. L. Dennig, Member NPRDS Users Group cc: P. Lyons, 7/iPO                                       ,
t ei As users of the NPRDS/in reliability studies (e.g., NPRDS Trends and Patterns Program), we would appreciate your consideration of the enclosed comments dur-ing development of the rq9 sed criteria for the next me? ting.
W. Conway, INP0                                                                           ,
Please direct
R. Simard, INPO
-any' questions that;.,(ou rrzy have regarding this subject to Mr. G.L. Plumlee (301-4924492),
                                                                                                                            ~
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J. Vora.g .ESP J. Crooks               .'                        ,
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B. Brady e E. Boyle                                                                                                   ,
. Sincere 1y, t
J. Taylor;,                           '
R. L. Dennig, Member NPRDS Users Group cc: P. Lyons, 7/iPO W. Conway, INP0
~
R. Simard, INPO J. Vora.g.ES P
J. Crooks B. Brady e E. Boyle J. Taylor;,
M. Williams Distribution:
M. Williams Distribution:
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WpRDS VALVE FAILURE REPORTING CRITERIA
,u, WpRDS VALVE FAILURE REPORTING CRITERIA
        -h MMf U.8/ DRAFY FRC$t COPMOWEALTH EDISON of '
-h MMf U.8/ DRAFY FRC$t COPMOWEALTH EDISON of '
I A failurs ty21!!Tc if:
I A failurs ty21!!Tc if:
                                                                                    ..q
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: i.       The valve can th I i
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                                                                                                              /
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of @p9nscy, of" Q,9er perform its primary intended function at the time
i.
                                                "                            .f 9                         ,i 2..
The valve can th I of @p9nscy, of" Q,9er perform its primary intended function at the time
9          The valve is out of savvice or inoperable by Technical specifications due to failure which is discovered prior to start of repair work
.f 9
                                                                        ^                                                                               y gp r 3.
,i 2.. The valve is out of savvice or inoperable by Technical specifications due 9
to failure which is discovered prior to start of repair worky gp r
^
3.
The repair (Work Reg!ast) is high priority.
The repair (Work Reg!ast) is high priority.
repait initiation tins)or                                          It cannot wait for convenient A failure exit.ts d,Lue_gg,,1gkage if:
It cannot wait for convenient repait initiation tins or
: 4.       The rep; air atJ rxmdiscretionary.
)
curtai2ingiUperationn                        er        The leak out of or through the valve is j
A failure exit.ts d,Lue_gg,,1gkage if:
a                                                                                         ~
4.
The rep; air atJ rxmdiscretionary.
The leak out of or through the valve is curtai2ingiUperationn er j
a
~
1.
1.
The valve does still perform its primary intended function at the discovery,                                                                                       of 2.
The valve does still perform its primary intended function at the discovery, of 2.
The repdr werk itself is the only reason to take the or to render it inoperable. The valve remains in                                     out of service discovery until P.he time that repair is init                                   ce from the time of
The repdr werk itself is the only reason to take the out of service or to render it inoperable. The valve remains in discovery until P.he time that repair is init ce from the time of 3.
: 3.       The repait'can be'made without taki 5                                                                         e valve out of service.
The repait'can be'made without taki 5
A failure due to leakaoe does
e valve out of service.
: 4.       The repairs are n xistif:}
A failure due to leakaoe does xistif:}
only to pass L           ILRT test. The valve functiono bu                         not seal t
4.
      , e                                                                              .
The repairs are n only to pass L ILRT test.
ILRT desired conditions.
The valve functiono bu not seal t ILRT desired conditions.
        'j
e
        '.                                            5.       The or b discretionary. The work may be cancelled or rescheduled at
'j 5.
                                                                                %c cotidition that. caused the repair work request to be written does not cuWail operatiorjs.
The or b discretionary. The work may be cancelled or rescheduled at
1                                       +                                .
%c cotidition that. caused the repair work request to be written does not cuWail operatiorjs.
v
1 v
                                                                                                                                                                      )
)
MM
+
                                                            ,s </                 r, .
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1N5ERT                                       ,
1N5ERT NPRDS VALVE FAILURE REPORTING CRITERIA (cont.)
NPRDS VALVE FAILURE REPORTING CRITERIA (cont.)                                                                                                                                                       l l
l l
: 5. The leakage contributed to a challenge to the Technical Specification limit such that a decision was made to repair the valve prior to exceeding the limit. or
: 5. The leakage contributed to a challenge to the Technical Specification limit such that a decision was made to repair the
}
}
: 6. The repair was necessary to pass the LLRT (i.e.. either the site specific Technical Specification local leak rate acceptance criteria or the 10 CFR 50. Appendix J combined leak rate acceptance criteria could not be achieved without the repair). or
valve prior to exceeding the limit. or
: 7. The leakage was judged to be a significant fraction of the ILRT limit.
: 6. The repair was necessary to pass the LLRT (i.e..
either the site specific Technical Specification local leak rate acceptance criteria or the 10 CFR 50. Appendix J combined leak rate acceptance criteria could not be achieved without the repair). or 7.
The leakage was judged to be a significant fraction of the ILRT limit.
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l l
l l
l
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atd5E .< =W,>                                                                         !
 
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==.y A. DOCUEENT BNFOR!AATION licens=""#
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'"'T as acTsens INFORMATION
: 7. .                                                                                         '"'T -
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as acTsens INFORMATION                                                                                                                       !
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    ~
PDBLICCITIZEN
PDBLICCITIZEN Buyers Up a Congress Watch D Critical Mass :Heahh Research Group : Litigation Group C Tan Gro July 20, 1987 Don Grimsley Diractor, Division of Rules & Records Nuclear Regulatory Commission                                               TREEDOM 0F INFORMA Washington, DC       20555                                                     ACT REQUEST MNBB 4210 bYIv3 Attn. Freedom of Information Act Request                                    M 'd 7-ny)
~
Mr. Grimsley Pursuant to the Freedom of Information Act, as amended, 5 U.S.C.
Buyers Up a Congress Watch D Critical Mass :Heahh Research Group : Litigation Group C Tan Gro July 20, 1987 Don Grimsley Diractor, Division of Rules & Records TREEDOM 0F INFORMA Nuclear Regulatory Commission Washington, DC 20555 ACT REQUEST bYIv3 MNBB 4210 M 'd 7-ny)
S 552, Public Citizen's Critical Hass Energy Project hereby requests copies of the following records:
Attn. Freedom of Information Act Request Mr. Grimsley Pursuant to the Freedom of Information Act, as amended, 5 U.S.C. S 552, Public Citizen's Critical Hass Energy Project hereby requests copies of the following records:
1.
1.
A complete listing of all conditions, situations, mishaps, accidents, or any kind of event included in the Nuclear Plant IXsliability Data System (NPRDS), including, but not limited to individual component failures and records of all other events it collects.
A complete listing of all conditions, situations, mishaps, accidents, or any kind of event included in the Nuclear Plant IXsliability Data System (NPRDS), including, but not limited to individual component failures and records of all other events it collects.
  *    '                  In addition, records explicitly defining what kind or type of events are reported to the NPRDS would also be appreciated.
In addition, records explicitly defining what kind or type of events are reported to the NPRDS would also be appreciated.
2.
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Any and ali analyses of nuclear power plant operating experience which use the NPRDS or any of the information contained therein.
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Such analyses may include, but are not limited to, analyses of aging of plant systems or components: recurring problems or deficiencies in plant systems or components; assessments of particular systems or compenents; precursors to major events; or any other type of analysis that may have been performed using the NPRDS.
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Any and all assessments or evaluations of the performance of the NPRDS system done since the system's inception including, but not limited to, the criteria against which the performance of the system is measured and the methodology used for assesoment and evaluation, the assessments or evaluations themselves, and correspondence related to or j         concerning the performance of the system.
Any and all assessments or evaluations of the performance of the NPRDS system done since the system's inception including, but not limited to, the criteria against which the performance of the system is measured and the methodology used for assesoment and evaluation, the assessments or evaluations themselves, and correspondence related to or j
concerning the performance of the system.
This request pertains to all records in the posession of the Nuclear Regulatory Commission (NRC), its licensees, or in the possession of contractors or subcontractors of the NRC or its licensees.
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                                                                                                                  \
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q               ns Pennsylvania An. se a washington. oc 20003 o po2n4sa988
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Latest revision as of 05:30, 2 December 2024

Forwards Comments Re Proposed Valve Failure Reporting Criteria,Per NPRDS Users Group Meeting 12,Action 4.5
ML20238E610
Person / Time
Issue date: 06/24/1987
From: Dennig R
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Kuhel P
COMMONWEALTH EDISON CO.
Shared Package
ML20238E398 List:
References
FOIA-87-465 NUDOCS 8709150099
Download: ML20238E610 (5)


Text

_______ _ _____

,/

%o UNITED STATES l

NUCLEAR REGULATORY COMMISSION I

~

c

'g

.E

- WASHINGTON, D. C. 20656 JllN 2 4 tgg7 Paul G. Kuhel Supervisor of Station Support Services j

Nuclear Services Technical l

Commonwealth Edison Company 72 West Adams, Room 1248E Chicago, IL 60690-0767

Dear Mr. Kuhel:

Subject:

COMMENTS ON PROPOSED VALVE FAILURE REPORTING CRITERIA - NPRDS USERS GROUP (NUG)MEETINGNO.12 ACTION 4.5 In our previous NUG meeting, you led a discussion and provided recommendations for improved guidance on identifying and reporting valve failures. All NUG members were asked to provide comments, from a user's point of view, on the proposed valve failure reporting criteria. Therefore, we have enclosed the attached markup which incorporates our comments. We have also enclosed an example of one plant's local leak rate acceptance criteria upon which operabi-l lity of a specific valve (e.g., MSIV) fio~s etermjA is d d.

As indicated in the ntgehsent.

ethat~l eTalves' a

' ocaT" WaTFf8 e"

'W11Ts7iFYtttegratot7 shevWhidered2as:vepensable.~as As users of the NPRDS in reliability studies (e.g., NPRDS Trends and Patterns Program), we would appreciate your consideration of the enclosed comments dur-ing development of the revised criteria for the next meeting. Please direct any questions that you may have regarding this subject to Mr. G.L. Plumlee (301-492-4492).

1 i

Sincerely

)

p R. L. Dennig, Member NPRDS Users Group I

cc: P. Lyons, INPO W. Conway, INPO R. Simard, INPO J. Crooks Fo*L 4-8 7-(/6{

M. Williams G//3 1

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t ei As users of the NPRDS/in reliability studies (e.g., NPRDS Trends and Patterns Program), we would appreciate your consideration of the enclosed comments dur-ing development of the rq9 sed criteria for the next me? ting.

Please direct

-any' questions that;.,(ou rrzy have regarding this subject to Mr. G.L. Plumlee (301-4924492),

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. Sincere 1y, t

R. L. Dennig, Member NPRDS Users Group cc: P. Lyons, 7/iPO W. Conway, INP0

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R. Simard, INPO J. Vora.g.ES P

J. Crooks B. Brady e E. Boyle J. Taylor;,

M. Williams Distribution:

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,u, WpRDS VALVE FAILURE REPORTING CRITERIA

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The valve can th I of @p9nscy, of" Q,9er perform its primary intended function at the time

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,i 2.. The valve is out of savvice or inoperable by Technical specifications due 9

to failure which is discovered prior to start of repair worky gp r

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The repair (Work Reg!ast) is high priority.

It cannot wait for convenient repait initiation tins or

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A failure exit.ts d,Lue_gg,,1gkage if:

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The rep; air atJ rxmdiscretionary.

The leak out of or through the valve is curtai2ingiUperationn er j

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The valve does still perform its primary intended function at the discovery, of 2.

The repdr werk itself is the only reason to take the out of service or to render it inoperable. The valve remains in discovery until P.he time that repair is init ce from the time of 3.

The repait'can be'made without taki 5

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A failure due to leakaoe does xistif:}

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The repairs are n only to pass L ILRT test.

The valve functiono bu not seal t ILRT desired conditions.

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The or b discretionary. The work may be cancelled or rescheduled at

%c cotidition that. caused the repair work request to be written does not cuWail operatiorjs.

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5. The leakage contributed to a challenge to the Technical Specification limit such that a decision was made to repair the

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6. The repair was necessary to pass the LLRT (i.e..

either the site specific Technical Specification local leak rate acceptance criteria or the 10 CFR 50. Appendix J combined leak rate acceptance criteria could not be achieved without the repair). or 7.

The leakage was judged to be a significant fraction of the ILRT limit.

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Buyers Up a Congress Watch D Critical Mass :Heahh Research Group : Litigation Group C Tan Gro July 20, 1987 Don Grimsley Diractor, Division of Rules & Records TREEDOM 0F INFORMA Nuclear Regulatory Commission Washington, DC 20555 ACT REQUEST bYIv3 MNBB 4210 M 'd 7-ny)

Attn. Freedom of Information Act Request Mr. Grimsley Pursuant to the Freedom of Information Act, as amended, 5 U.S.C. S 552, Public Citizen's Critical Hass Energy Project hereby requests copies of the following records:

1.

A complete listing of all conditions, situations, mishaps, accidents, or any kind of event included in the Nuclear Plant IXsliability Data System (NPRDS), including, but not limited to individual component failures and records of all other events it collects.

In addition, records explicitly defining what kind or type of events are reported to the NPRDS would also be appreciated.

2.

Any and ali analyses of nuclear power plant operating experience which use the NPRDS or any of the information contained therein.

Such analyses may include, but are not limited to, analyses of aging of plant systems or components: recurring problems or deficiencies in plant systems or components; assessments of particular systems or compenents; precursors to major events; or any other type of analysis that may have been performed using the NPRDS.

3.

Any and all assessments or evaluations of the performance of the NPRDS system done since the system's inception including, but not limited to, the criteria against which the performance of the system is measured and the methodology used for assesoment and evaluation, the assessments or evaluations themselves, and correspondence related to or j

concerning the performance of the system.

This request pertains to all records in the posession of the Nuclear Regulatory Commission (NRC), its licensees, or in the possession of contractors or subcontractors of the NRC or its licensees.

In this request, " record" includes, but is not limited to, any memoranda, formal or informal correspondence, reports, studies, reviews, letters, computer memories and printouts, information transfer systems, audio and video tapes, movies and any other form of communication, in the possession of any individual or office in the NRC, whether generated by the NRC, its contractors, the nuclear industry or any other source.

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q ns Pennsylvania An. se a washington. oc 20003 o po2n4sa988

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L Publid ditizon's Critical Mass Energy Project non-profit public interest organization founded in is a nationally known 1974.

We will use these documents in our studies of nuclear power safety, and we will disseminate and distribute the information contained therein to the press and public.

I and its numerous other publications,Public Citizen's annual Nuclear Power Safety Re attract wide attention in the national, local, and trade media.

Thousands of copies of Public Citizen's reports have been sold or distributed to members of the public, industry, government and citizen groups.

Since furnishing these documents "can be considered as primarily benefitting the public," we request a complete waiver of any costs you might incur in processing these records or making copies for us under the provisions of 10 C.F.R. S 9 and 14(a).

please notify us before filling the request. If you rule otherwise, Nothing in this request should be considered a request for the private records of any specific individual.

l Hence, no provisions of the Privacy Act should be deemed applicable.

1 If ell or any parts of this request are denied, please cite the specific exemptions (s) on which you rely in refusing to release the i

documents.

Further, since the Freedom of Information Act provides that if only portions of a file are exempt from release, the remainder must be released, we request that we be provided with all non-exempt portions which are reasonably segregable.

Of course, we reserve our right to appeal the withholding or deletion of any information.

As provided in the Freedom of Information Act, we will expect to receive the requested records or a final determination within ten working days.

If your office is unable to fully respond to this request in that time, please send us a written estimate of when the response will be completed.

If you have any questions about this request, please telephone me (202) 546-4996.

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Thank you for your help.

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I Sinc}fely,

^w oshua Gordon Nuclear Analyst j

Public Citizen's Critical j

Mass Energy Project

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