ML20134K797
| ML20134K797 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood |
| Issue date: | 02/12/1997 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134K801 | List: |
| References | |
| NPF-37-A-085, NPF-66-A-085, NPF-72-A-077, NPF-77-A-077 NUDOCS 9702140235 | |
| Download: ML20134K797 (12) | |
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WASHINGTON, D.C. 30ss&4001
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COPMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. I AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison company (the licensee) dated August 2, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the 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 Commission; 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; 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 ampnded by changes to paragraph 2.C.(2) and by deleting paragraph 2.C.(16) of Facility Operating License No.
NPF-37 and is hereby amended to read as follows:
l I
- Page 7 is attached, for convenience, for the composite license to reflect this change.
9702140235 970212 PDR ADOCK 05000454 P
h (2)
Technical Snecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 85 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(16) 6el'eted.
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 k-l Ge F. Dick, Se or Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
License page 7 Date of Issuance:
February 12, 1997 i
i f
L (16) Deleted.
i D.
The facility requires exemptions from certain requirements of Appendices A, E and J to 10 CFR Part 50. These include (a) an exemption from the requirements of Paragraph III.D.2(b)(11) of i
Appendix J, the testing of containment air locks at times when containment integrity is not required (Section 6.2.6 of the SER), (b) an exemption from GDC-2 of Appendix A, the requirement that structures, systems and components important to safety be i
designed to withstand the effects of natural phenomena such as earthquakes (Section 3.10 of SSER #5), (c) an exemption from.
GDC-13 and GDC-17 of Appendix A, the requirement that instrumentation be provided to monitor variables and systems over their anticipated ranges, and the requirement that provisions be included to minimize the probability of losing electric power (Section 9.5.4.1 of SSER #5), (d) an exemption from GDC-19 of Appendix A, the requirement that the control room have adequate radiation protection to permit access and i
occupancy under accident conditions (Section 6.5.1 of SSER #6),
and (e) an exemption from the requirement of Section IV.F of Appendix E that a full participation emergency planning exercise be conducted within one year before issuance of the first operating license for full power and prior to operation above 5%
of rated power (Section 13.3 of SSER #6). These exemptions are authorized by law and will not endanger life or property or the i
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AMENDMENT NO. $), 85 l
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NUCLEAR REGULATORY COMMISSION I
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COMONWEALTH EDISON CONPANY i
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DOCKET NO. STN 50-455 i
j BYRON STATION. UNIT ND. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. NPF-66 j
1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Commonwealth Edison Company (the licensee) dated August 2, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in
)
l 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 Commission; C.
There is reasonable assurance (1) 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; 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 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 ayended by changes to paragraph 2.C.(2) and by deleting paragraph 2.C.(5) of Facility Operating License No. NPF-66 and is hereby amended to read as follows:
- Page 3a is attached, for convenience, for the composite license to reflect this change.
__ (2)
Technical Snecifications The Technical Specifications contained in Appendix A (NUREG-Ill3),
as revised through Amendment No. 85 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(5)
Deleted.
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 v
Ce F. Dick Jr., Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
License page 3a
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Date of Issuance:
February 12, 1997 i
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- 3a -
i (3)
Initial Test Proaram Any changes to the Initial Startup Test Program described in Chapter 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(4)
Reaulatory Guide 1.97. Revision 2 Como11ance The licensee shall submit by March 1, 1987, a preliminary report describing how the requirements of Regulatory Guide 1.97, Revision 2 have been or will be met. The licensee shall submit by September 1,1987, the final report and a schedule for implementation (assuming the NRC approves the DCRDR by March 1, 198'/).
(5)
Deleted.
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l AMELDMENT NO. S), 85
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@U% k UNITED STATES I
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WASHINGTON, D.C. soseH001
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f COMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.77 License No. NPF-72 I
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consenwealth Edison Company (the 3
licensee) dated August 2, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the j
Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; d
B.
The facility will operate in confonnity with the application, the l
provisions of the Act, and the rules and regulations of the
?
Commission; i
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 i
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is ayended by changes to paragraph 2.C.(2) and by deleting paragraph 2.C.(6) of Facility Operating License No. NPF-72 4
and is hereby amended to read as follows:
)
l
- Page 4 is attached, for convenience, for the composite license to reflect this change.
l 4
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(2)
Jechnical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 77 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(6)
Deleted.
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 kg 04]
Georgr F.
ick, Sen or Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
License page 4 -
Date of Issuance:
February 12, 1997
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i J
(4)
Initial Startuo Test Proaram Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 4
l 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
i i
i (5) Reaulatory Guide 1.97. Revision 2 Compliance
?
- The licensee shall-submit the final report and a schedule for implementation within six months of NRC approval of the DCRDR.
(6) Deleted.
D.
The facility requires an exemption from the requirements of Appendix J to 10 CFR Part 50, Paragraph III.D.2(b)(ii), the testing of containment air locks at times when containment integrity is not i
required (SER Section 6.2.6).
This exemption is authorized by law, j
will not present an undue risk to the public health and safety, and is consistent with the common defense and security. This exemption is hereby granted. The special circumstances regarding this exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. This exemption is granted pursuant to 10 CFR 50.12. With this exemption, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and j
regulations of the Commission.
l An exemption was previously granted pursuant to 10 CFR 70.24.
The exemption was granted with NRC materials license No. SNM-1938, issued October 8, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is a
i exempted from the criticality alarm system provision of 10 CFR 70.24 l
so far as this section applies to the storage of fuel assemblies held j
under this license.
1 E.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as supplemented and amended, and as approved in the J
SER dated November 1983 and its supplements, subject to the following 4
provision:
~
The licensee may make changes to the approved fire protection program j
without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown 4
in the event of a fire.
1 AMENDMENT NO. 75, 77
en UNITED STATES O
~ j NUCLEAR REGULATORY COMMISSION l
j WASHINGTON, D.C. sce6Hooi
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COPMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 2, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; t
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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; I
D.
The issuance of this amendment will not be inimical to the common i
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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to paragraph 2.C.(2) and by deleting paragraph 2.C.(5) of Facility Operating License No. NPF-77 and is hereby amended to read as follows:
- Page 4 is attached, for convenience, for the composite license to reflect this change.
l i,
(2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 77 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2,1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(5)
Deleted.
3.
This license amendment is effective as of the date if its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
L-George Dick, Seni r Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
License page 4 Date of Issuance:
February 12, 1997
(4)
Initial Startuo Test Proaram Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Deleted.
D.
The facility requires an exemption from the requirements of Appendix J t
to 10 CFR Part 50, Paragraph III.D.2(b)(ii), the testing of containment air locks at times when containment integrity is not required (SER Section 6.2.6).
This exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. The staff's environmental assessment was published on May 19, 1988 (53 FR 17995).
This exemption was granted in the low power license and is continued for the full power license. The special circumstances regarding this exemption are identified in the referenced section of the Safety Evaluation Report and the supplements thereto.
This exemption is granted pursuant to 10 CFR 50.12. With this exemption, the facility i
will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
An exemption was previously granted pursuant to 10 CFR 70.24.
The
]
exemption was granted with NRC materials license No. SNM-1938, issued October 8,1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is 4
exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
AMENDMENT N0 75,77 4
, _