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UNITED STATES j
NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION
      $                                              WASHINGTON, D.C. 20666-0001
~
        'g *** * /                                                                                                       1 l
g WASHINGTON, D.C. 20666-0001
COMONWEALTH EDISON COMPANY DOCKET NO. 50-295 l                                             ZION NUCLEAR POWER STATION. UNIT 1 l
'g *** * /
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174             l
COMONWEALTH EDISON COMPANY DOCKET NO. 50-295 l
,                                                                                            License No. DPR-39
ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. DPR-39 1.
;          1. The Nuclear Regulatory Commission (the Commission) has found that:
The Nuclear Regulatory Commission (the Commission) has found that:
A.             The application for ameadment by Commonwealth Edison Company (the i                                 licensee) dated August 16, 1996, as supplemented by letter dated
A.
,                                 October 4,1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the i                                 Commission's rules and regulations set forth in 10 CFR Chapter I;                       l 1
The application for ameadment by Commonwealth Edison Company (the i
B.             The facility will operate in conformity with the application, the                       l
licensee) dated August 16, 1996, as supplemented by {{letter dated|date=October 4, 1996|text=letter dated October 4,1996}}, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the i
,                                provisions of the Act, and the rules and regulations of the                             1 4
Commission's rules and regulations set forth in 10 CFR Chapter I; B.
Commission; i                 C.             There is reasonable assurance (i) that the activities authorized
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 1
;                                by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be a                                conducted in compliance with the Commission's regulations;                               l 3
Commission; 4
D.             The issuance of this amendment will not be inimical to the common                       l defense and security or to the health and safety of the public; and                                                                                     i E.             The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable                             ;
i C.
requirements have been satisfied.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; a
: 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
3 D.
t 9611080220 961106 PDR   ADOCK 05000295 P                             PDR
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
t 9611080220 961106 PDR ADOCK 05000295 P
PDR


__.      . = .         _-        .. -        .    ._. _ .          _ _ _ . - - -
. =.
l I
" (2)
(2)       Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174
: 3.     This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
FOR THE NUCLEAR REGULATORY COMMISSION l
l                                                Cly e Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV                 l Office of Nuclear Reactor Regulation
Cly e Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation


==Attachment:==
==Attachment:==
 
Changes to the Technical Specifications Date of Issuance:
Changes to the Technical Specifications Date of Issuance: November 6, 1996 i
November 6, 1996 i
I I
I I
I I
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I


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[,*         4                             UNITED STATES
[,*
    ,  y              g           NUCLEAR REGULATORY COMMISSION
4 UNITED STATES y
* WASHINGTON, D.C. 20666 4001 4, .....,o 1
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001 4,.....,o 1
COMONWEALTH EDISON COMPRI                                         !
COMONWEALTH EDISON COMPRI l
l                                                DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2
DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
,                                    AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 161 License No. DPR-48 1.
Amendment No. 161 License No. DPR-48
The Nuclear Regulatory Commission (the Commission) has found that A.
: 1. The Nuclear Regulatory Commission (the Commission) has found that l
The application for amendment by Comonwealth Edison Company (the licensee) dated August 16, 1996, as supplemented by {{letter dated|date=October 4, 1996|text=letter dated October 4, 1996}}, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
A. The application for amendment by Comonwealth Edison Company (the licensee) dated August 16, 1996, as supplemented by letter dated October 4, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the                 l provisions of the Act, and the rules and regulations of the                       !
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; j
Comission;                                                                         j C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
C.
: 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby                 '
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
amended to read as follows:
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:


                          ._.          ..              . - . =
. -. =
~
~
(2)   Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.161 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(2)
: 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.161
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COM41SSION Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
FOR THE NUCLEAR REGULATORY COM41SSION Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation


==Attachment:==
==Attachment:==
Changes to the Technical Specifications Date of Issuance: November 6, 1996
Changes to the Technical Specifications Date of Issuance: November 6, 1996


ATTACHMENT TO LICENSE AMENDMENT NOS.174       AND 161 4
ATTACHMENT TO LICENSE AMENDMENT NOS.174 AND 161 FACILITY OPERATING LICENSE NOS. DPR-39 AND DPR-48 4
FACILITY OPERATING LICENSE NOS. DPR-39 AND DPR-48 1
1 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paoes Insert Paaes 74f3 74f3 78c 76c
Remove Paoes                           Insert Paaes 74f3                                   74f3 78c                                   76c l


LIMITING CONDITION FOR OPERATION                           SURVEILLANCE REQUIRENENT
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIRENENT
: 10. Repaired Tube means a tube that has undemone a process that re-establishes its serviceability.
: 10. Repaired Tube means a tube that has undemone a process that re-establishes its serviceability.
The sleeving process utilized shall be one of the following:
The sleeving process utilized shall be one of the following:
: a. The Combustion Engineering welded sleeve process as descri M in Report CEM-331-P, Revision 1-P.**
a.
: b. The Westinghouse Electric Corporation mechanical sleeve process as described in Report WCAP-Il669.
The Combustion Engineering welded sleeve process as descri M in Report CEM-331-P, Revision 1-P.**
: c. The Bechtel-KWU Alliance welded sleeve process as described in Report BKAT-01-P, Revision 1.
b.
: 11. F* Distance is the length of undgraded tube required to resist pullout. This distance is measured from the bottom of the upper hard roll transition toward the bottom of the tubesheet and has been conservatively determined to be 1.05 inches. The determination of the F*
The Westinghouse Electric Corporation mechanical sleeve process as described in Report WCAP-Il669.
c.
The Bechtel-KWU Alliance welded sleeve process as described in Report BKAT-01-P, Revision 1.
: 11. F* Distance is the length of undgraded tube required to resist pullout. This distance is i
measured from the bottom of the upper hard roll transition toward the bottom of the tubesheet and has been conservatively determined to be 1.05 inches. The determination of the F*
Distance is satisfied by the mechanical tool (rolling pin) used to install the joint having an effective length of greater than or equal to 1.05 inches. The F* Distance is applicable only to tubes that are rerolled below the mid-plane of the tubesheet and have no degradation in the rerolled expansion joints.
Distance is satisfied by the mechanical tool (rolling pin) used to install the joint having an effective length of greater than or equal to 1.05 inches. The F* Distance is applicable only to tubes that are rerolled below the mid-plane of the tubesheet and have no degradation in the rerolled expansion joints.
: 12. F* Tube is a tube with indications below the F*
: 12. F* Tube is a tube with indications below the F*
Distance, equal to or grpater than 40%, and no indications within the F Distance.
Distance, equal to or grpater than 40%, and no indications within the F Distance.
                                      **The following sections of AB8/CE Report CEN-629-P Revision 00 shall be implemented in conjunction with Report CEN-331-P, Revision 1-P:
**The following sections of AB8/CE Report CEN-629-P Revision 00 shall be implemented in conjunction with Report CEN-331-P, Revision 1-P:
Section 4.5.3 - Tube Brushing-Cleaning Equipment Section 4.5.7 - Nondestructive Examination Section 5.0 - Sleeve Examination Program Section 9.3.1 - Cleaning Qualification i
Section 4.5.3 - Tube Brushing-Cleaning Equipment Section 4.5.7 - Nondestructive Examination Section 5.0
t 74f3                                   Amendment Nos. 174 and 161 t
- Sleeve Examination Program Section 9.3.1 - Cleaning Qualification i
t 74f3 Amendment Nos. 174 and 161 t


8:s:s:
8:s:s:
3.3.1 Steam Generators 4.3.1 The F* Distance will be controlled by process control. For a new additional roll expansion,                             -
3.3.1 Steam Generators 4.3.1 The F* Distance will be controlled by process control. For a new additional roll expansion, the requirement will be at least 1.05 inches of new hard roll. This is controlled by the length of the rolling pin used during the mechanical installation of the new hard roll joint. The distance from the original roll transition zone is also controlled by the process in that the lower end of the new roll expansion is located approximately one inch above the original factory hard roll expansion.
the requirement will be at least 1.05 inches of new hard roll. This is controlled by the length of the rolling pin used during the mechanical installation of the new hard roll joint. The distance from the original roll transition zone is also controlled by the process in that the lower end of the new roll expansion is located approximately one inch above the original factory hard roll expansion. In the case of the new roll, eddy current examination will confirm that there are no indications in the new roll regior and that there is a new roll region with well defined upper and lower expansion transitions. The F* Distance is not applicable to the original factory hard roll.
In the case of the new roll, eddy current examination will confirm that there are no indications in the new roll regior and that there is a new roll region with well defined upper and lower expansion transitions. The F* Distance is not applicable to the original factory hard roll.
78c                                                                                                                                 Amendment Nos. 174 and 161
78c Amendment Nos. 174 and 161
_ _ - _ _ _ _ - _ _ - _ _ _ - _ _ _      _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ -                      - _ _ -}}
-}}

Latest revision as of 04:36, 12 December 2024

Amends 174 & 161 to Licenses DPR-39 & DPR-48,respectively, Revising Definition of F* Distance by Removing Uncertainty Term from Specified Distance & Removing Footnote Which Specifies Time Frame Applicable
ML20134F977
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 11/06/1996
From: Shiraki C
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20134F952 List:
References
NUDOCS 9611080220
Download: ML20134F977 (7)


Text

_

m _. _

yy ye l'.

UNITED STATES j

NUCLEAR REGULATORY COMMISSION

~

g WASHINGTON, D.C. 20666-0001

'g *** * /

COMONWEALTH EDISON COMPANY DOCKET NO. 50-295 l

ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. DPR-39 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for ameadment by Commonwealth Edison Company (the i

licensee) dated August 16, 1996, as supplemented by letter dated October 4,1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the i

Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 1

Commission; 4

i C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; a

3 D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

t 9611080220 961106 PDR ADOCK 05000295 P

PDR

. =.

" (2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174

, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION l

Cly e Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 6, 1996 i

I I

I

pn neau

[,*

4 UNITED STATES y

g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001 4,.....,o 1

COMONWEALTH EDISON COMPRI l

DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 161 License No. DPR-48 1.

The Nuclear Regulatory Commission (the Commission) has found that A.

The application for amendment by Comonwealth Edison Company (the licensee) dated August 16, 1996, as supplemented by letter dated October 4, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; j

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:

. -. =

~

(2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.161

, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COM41SSION Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 6, 1996

ATTACHMENT TO LICENSE AMENDMENT NOS.174 AND 161 FACILITY OPERATING LICENSE NOS. DPR-39 AND DPR-48 4

1 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Remove Paoes Insert Paaes 74f3 74f3 78c 76c

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIRENENT

10. Repaired Tube means a tube that has undemone a process that re-establishes its serviceability.

The sleeving process utilized shall be one of the following:

a.

The Combustion Engineering welded sleeve process as descri M in Report CEM-331-P, Revision 1-P.**

b.

The Westinghouse Electric Corporation mechanical sleeve process as described in Report WCAP-Il669.

c.

The Bechtel-KWU Alliance welded sleeve process as described in Report BKAT-01-P, Revision 1.

11. F* Distance is the length of undgraded tube required to resist pullout. This distance is i

measured from the bottom of the upper hard roll transition toward the bottom of the tubesheet and has been conservatively determined to be 1.05 inches. The determination of the F*

Distance is satisfied by the mechanical tool (rolling pin) used to install the joint having an effective length of greater than or equal to 1.05 inches. The F* Distance is applicable only to tubes that are rerolled below the mid-plane of the tubesheet and have no degradation in the rerolled expansion joints.

12. F* Tube is a tube with indications below the F*

Distance, equal to or grpater than 40%, and no indications within the F Distance.

    • The following sections of AB8/CE Report CEN-629-P Revision 00 shall be implemented in conjunction with Report CEN-331-P, Revision 1-P:

Section 4.5.3 - Tube Brushing-Cleaning Equipment Section 4.5.7 - Nondestructive Examination Section 5.0

- Sleeve Examination Program Section 9.3.1 - Cleaning Qualification i

t 74f3 Amendment Nos. 174 and 161 t

8:s:s:

3.3.1 Steam Generators 4.3.1 The F* Distance will be controlled by process control. For a new additional roll expansion, the requirement will be at least 1.05 inches of new hard roll. This is controlled by the length of the rolling pin used during the mechanical installation of the new hard roll joint. The distance from the original roll transition zone is also controlled by the process in that the lower end of the new roll expansion is located approximately one inch above the original factory hard roll expansion.

In the case of the new roll, eddy current examination will confirm that there are no indications in the new roll regior and that there is a new roll region with well defined upper and lower expansion transitions. The F* Distance is not applicable to the original factory hard roll.

78c Amendment Nos. 174 and 161

-