ML20127K182: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:_         . _                            ._ .
{{#Wiki_filter:_
I   i             - Commenwealth Edison
I i
      '     f 1400 opus Place
- Commenwealth Edison f
            'y A
'y A 1400 opus Place
            , Q)< oowners Grove, minois 60515 g
, Q)< oowners Grove, minois 60515 g
November 23,1992
November 23,1992
                                                                                                  \
\\
A i
A i
Dr.-Thomas E. Murley, Director                                                                       i Office Of Nuclear Reactor Regulation                                                             M U.S. Nuclear Regulatory Commission Washington, DC 20555                                                                         .
Dr.-Thomas E. Murley, Director M
3 Attn: Document Control Desk
Office Of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 3
Attn: Document Control Desk


==Subject:==
==Subject:==
Line 34: Line 35:


==References:==
==References:==
a)   Letter from T. Simpkin to Dr. T. Murley dated April 15,1992.
a)
Letter from T. Simpkin to Dr. T. Murley dated April 15,1992.


==Dear Dr. Murley:==
==Dear Dr. Murley:==
With reference (a), Commonwealth Edison Company (CECO) proposed to amend Appendix A, Technical Specification for Facility Operating License NPF 37, NPF-66, N PF-72 and NPF-77. The proposed amendment involves a revision to Technical Specifications 2.2.1, Table 2.2-1,3.3.2, Table 3.3 4 and their associated bases. The proposed amendment request provides the changes that have resulted from the Setpoint Reconciliation Program.
With reference (a), Commonwealth Edison Company (CECO) proposed to amend Appendix A, Technical Specification for Facility Operating License NPF 37, NPF-66, N PF-72 and NPF-77. The proposed amendment involves a revision to Technical Specifications 2.2.1, Table 2.2-1,3.3.2, Table 3.3 4 and their associated bases. The proposed amendment request provides the changes that have resulted from the Setpoint Reconciliation Program.
Due to a transcription error, the revised setpoint for the Emergency Trip Header Pressure, Functional Unit 16a on page 2-5, was omitted from the Byron mark-up. Please find a corrected page 2-5 for the Byron Technical Specifications attached.
Due to a transcription error, the revised setpoint for the Emergency Trip Header Pressure, Functional Unit 16a on page 2-5, was omitted from the Byron mark-up. Please find a corrected page 2-5 for the Byron Technical Specifications attached.
250035 e
250035 e
9301260065 DR            921323                                                             6 p       ADOCK 05000454 PDR                                                         "l
9301260065 921323 6
        / sci:lD615:21                                                                             I
DR p
ADOCK 05000454 PDR "l
I
/ sci:lD615:21


Dr. Thomas E. Murley                                           November 23,1992 CECO is notifying the State of Illinois by transmitting a copy of this letter and its attachments to the designated State Official.
Dr. Thomas E. Murley November 23,1992 CECO is notifying the State of Illinois by transmitting a copy of this letter and its attachments to the designated State Official.
Please direct any questions regarding this matter to this office.
Please direct any questions regarding this matter to this office.
l Respectfully,
l Respectfully,
                                                    %%A Terrence W. Simpkin
% % A
                                                                                '~                        J Nuclear Licensing Administrator cc: R. Elliott, Project Manager - NRR J. Hickman, Project Manager - NRR S. DuPont, Resident inspector - Braidwood W. Kropp, Resident inspector - Byron Document Control Desk - NRR Region 111 Office Office of Nuclear Facility Safety -IDNS
'~
              / sci:lD615:22                                                                                 ,
J Terrence W. Simpkin Nuclear Licensing Administrator cc: R. Elliott, Project Manager - NRR J. Hickman, Project Manager - NRR S. DuPont, Resident inspector - Braidwood W. Kropp, Resident inspector - Byron Document Control Desk - NRR Region 111 Office Office of Nuclear Facility Safety -IDNS
    .}}
/ sci:lD615:22
.}}

Latest revision as of 16:08, 12 December 2024

Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 2.2.1,Table 2.2-1,3.3.2,Table 3.3-4 & Associated Bases,Providing Changes That Have Resulted from Setpoint Reconciliation Program
ML20127K182
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 11/23/1992
From: Simpkin T
COMMONWEALTH EDISON CO.
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20127K185 List:
References
NUDOCS 9301260065
Download: ML20127K182 (2)


Text

_

I i

- Commenwealth Edison f

'y A 1400 opus Place

, Q)< oowners Grove, minois 60515 g

November 23,1992

\\

A i

Dr.-Thomas E. Murley, Director M

Office Of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 3

Attn: Document Control Desk

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 A plication for Amendment to Facility rating Licanse NPF-37, NPF 66, NPF-72, and NPF-77 t1 C_DockeiBos5014E4L455.A56_and_45Z

References:

a)

Letter from T. Simpkin to Dr. T. Murley dated April 15,1992.

Dear Dr. Murley:

With reference (a), Commonwealth Edison Company (CECO) proposed to amend Appendix A, Technical Specification for Facility Operating License NPF 37, NPF-66, N PF-72 and NPF-77. The proposed amendment involves a revision to Technical Specifications 2.2.1, Table 2.2-1,3.3.2, Table 3.3 4 and their associated bases. The proposed amendment request provides the changes that have resulted from the Setpoint Reconciliation Program.

Due to a transcription error, the revised setpoint for the Emergency Trip Header Pressure, Functional Unit 16a on page 2-5, was omitted from the Byron mark-up. Please find a corrected page 2-5 for the Byron Technical Specifications attached.

250035 e

9301260065 921323 6

DR p

ADOCK 05000454 PDR "l

I

/ sci:lD615:21

Dr. Thomas E. Murley November 23,1992 CECO is notifying the State of Illinois by transmitting a copy of this letter and its attachments to the designated State Official.

Please direct any questions regarding this matter to this office.

l Respectfully,

% % A

'~

J Terrence W. Simpkin Nuclear Licensing Administrator cc: R. Elliott, Project Manager - NRR J. Hickman, Project Manager - NRR S. DuPont, Resident inspector - Braidwood W. Kropp, Resident inspector - Byron Document Control Desk - NRR Region 111 Office Office of Nuclear Facility Safety -IDNS

/ sci:lD615:22

.