ML20078Q332: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:(..
{{#Wiki_filter:(..
L N Commonw2 lth Edison                                                                               .
N Commonw2 lth Edison L
                  ~                                                                                                    l C., .,} Brtidwood   Nucbtr Routs #1, Box 84 Powsr Station                                                                ;
C.,.,} Brtidwood Nucbtr Powsr Station l
V ~J Braceville, Illinois 60407                                                                         i
~
            \             Telephone 815/458-2801
Routs #1, Box 84 V ~J Braceville, Illinois 60407 i
\\
Telephone 815/458-2801
{
{
)         February 9,1995 BW/95-0018 i
)
Office of Resource Management                                                                               ;
February 9,1995 BW/95-0018 i
U.S. Nuclear Regulatory Commission                                                                           r
Office of Resource Management U.S. Nuclear Regulatory Commission r
) .-       Washington, D.C. 20555                                                                                       !
).-
Attention:       Document Control Desk
Washington, D.C. 20555 Attention:
Document Control Desk


==Subject:==
==Subject:==
Braidwood Station's Unit 2 Reactor Containment                                             !
Braidwood Station's Unit 2 Reactor Containment
)                           Type A Integrated Leakage Rate Test                                                         j NRC Docket Nos. 50-456 and 50-457                                                           ,
)
Enclosed is Comed's report for the " Reactor Containment Building Integrated Leak Rate Test,"                 j conducted from October 27 through November 9,1994, for Braidwood Unit 2. This report is to                   !
Type A Integrated Leakage Rate Test j
3        be submitted to the NRC approximately three months after conducting the test in accordance with               i 10 CFR 50, Appendix J, Section V.                                                                           '
NRC Docket Nos. 50-456 and 50-457 Enclosed is Comed's report for the " Reactor Containment Building Integrated Leak Rate Test,"
l The report describes the second Unit 2 Type A containment leakage rate test performed using .               f Braidwood Technical Surveillance 2BwVS 6.1.2.a-1, " Unit 2 Primary Containment Type A Integrated Leakage Rate Test (ILRT)," in accordance with the requirements of 10 CFR 50,
j conducted from October 27 through November 9,1994, for Braidwood Unit 2. This report is to 3
).        Appendix J, Section III.A.
be submitted to the NRC approximately three months after conducting the test in accordance with i
10 CFR 50, Appendix J, Section V.
l The report describes the second Unit 2 Type A containment leakage rate test performed using.
f Braidwood Technical Surveillance 2BwVS 6.1.2.a-1, " Unit 2 Primary Containment Type A
).
Integrated Leakage Rate Test (ILRT)," in accordance with the requirements of 10 CFR 50, Appendix J, Section III.A.
Should you have any questions, contact Allen Checca, Braidwood Systems Engineering Supervisor, at (815) 458-2801, extension 2243.
Should you have any questions, contact Allen Checca, Braidwood Systems Engineering Supervisor, at (815) 458-2801, extension 2243.
)        Yours truly, l
M            b        u K.L. Kofron                                                                                                    '
)        Station Manager                                                                                                <
Braidwood Nuclear Station                                                                                    j KLK/AC/dia
)        Attachment ec:      J.B. Martin, NRC Regional Administrator, Rill R.R. Assa, Project Manager, NRR S.G. DuPont, Sr. Resident Inspector
)
)
9502210209 950209                                                             o'I   i
Yours truly, b
)                           PDR     ADOCK 05000457                                                         I P                   PDR
M u
                                                                                                          #      I
K.L. Kofron
                                                                                    .--- - -- ..- --          -    .-}}
)
Station Manager Braidwood Nuclear Station j
KLK/AC/dia
)
Attachment ec:
J.B. Martin, NRC Regional Administrator, Rill R.R. Assa, Project Manager, NRR S.G. DuPont, Sr. Resident Inspector
)
9502210209 950209 o'I i
)
PDR ADOCK 05000457 I
I P
PDR
.}}

Latest revision as of 01:14, 15 December 2024

Forwards Braidwood Unit 2 Reactor Containment Bldg Type a ILRT Final Rept,Conducted from 941027-1109.Rept Describes Second Unit 2 Type a Containment Leakage Rate Test Performed Using Braidwood Technical Surveillance 2BwVS 6.1.2.a-1
ML20078Q332
Person / Time
Site: Braidwood 
Issue date: 02/09/1995
From: Kofron K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20078Q335 List:
References
BW-95-0018, BW-95-18, NUDOCS 9502210209
Download: ML20078Q332 (1)


Text

(..

N Commonw2 lth Edison L

C.,.,} Brtidwood Nucbtr Powsr Station l

~

Routs #1, Box 84 V ~J Braceville, Illinois 60407 i

\\

Telephone 815/458-2801

{

)

February 9,1995 BW/95-0018 i

Office of Resource Management U.S. Nuclear Regulatory Commission r

).-

Washington, D.C. 20555 Attention:

Document Control Desk

Subject:

Braidwood Station's Unit 2 Reactor Containment

)

Type A Integrated Leakage Rate Test j

NRC Docket Nos. 50-456 and 50-457 Enclosed is Comed's report for the " Reactor Containment Building Integrated Leak Rate Test,"

j conducted from October 27 through November 9,1994, for Braidwood Unit 2. This report is to 3

be submitted to the NRC approximately three months after conducting the test in accordance with i

10 CFR 50, Appendix J,Section V.

l The report describes the second Unit 2 Type A containment leakage rate test performed using.

f Braidwood Technical Surveillance 2BwVS 6.1.2.a-1, " Unit 2 Primary Containment Type A

).

Integrated Leakage Rate Test (ILRT)," in accordance with the requirements of 10 CFR 50, Appendix J,Section III.A.

Should you have any questions, contact Allen Checca, Braidwood Systems Engineering Supervisor, at (815) 458-2801, extension 2243.

)

Yours truly, b

M u

K.L. Kofron

)

Station Manager Braidwood Nuclear Station j

KLK/AC/dia

)

Attachment ec:

J.B. Martin, NRC Regional Administrator, Rill R.R. Assa, Project Manager, NRR S.G. DuPont, Sr. Resident Inspector

)

9502210209 950209 o'I i

)

PDR ADOCK 05000457 I

I P

PDR

.