ML20149F426
| ML20149F426 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/05/1994 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149F429 | List: |
| References | |
| NPF-37-A-063, NPF-66-A-063 NUDOCS 9408100222 | |
| Download: ML20149F426 (6) | |
Text
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t UNITED STATES E
NUCLEAR REGULATORY COMMISSION
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i COMMONWEALTH EDISON COMPANY j
l DOCKET NO. STN 50-454 f
BYRON STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 63 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
f A.
The application for amendment by Commonwealth Edison Company (the f
licensee) dated August 2,1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the i
Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; i
t B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the Commission; j
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of ti.i 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 amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment, and paragraph 2.C..(2) of Facility Operating License No. NPF-37 is hereby i
amended to read as follows-i l
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9408100222 940805 i
DR ADOCK 05000454 l
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_2_
i (2)
Technical Snecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 63 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.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION John A. Zwolinski, Assistant Director for Region III Reactors Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation 1
Attachment:
l Changes to the Technical Specifications Date of Issuance: August 5, 1994
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y-4 UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D.C. 20555-0001
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COMMONWEALTH EDISON COMPANY i
DOCKET NO. STN 50-455 t
BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 2, 1994, 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; j
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; 1
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 the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facil.ty Operating License No. NPF-66 is hereby amended to read as follrws:
i l
i
~ 8 (2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113),
i as revised through Amendment No.
63 and revised by Attachment 2 i
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 i
license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license.
The licensee shall operate i
the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
John
. Zwolinski, Assistant Director for Region III Reactors Division of Reactor Projects - III/IV l
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: August 5, 1994 l
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I ATTACHMENT T0. LICENSE AMENDMENT NOS. 63 AND 63 FACILITY OPERATING LICENSE N05. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the attached page. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 3-51 3/4 3-51 I
i I
co TABLE 3.3-9 M
e REMOTE SHUTDOWN MONITORING INSTRUMENTATION i
E k
TOTAL NO.
MINIMUM l
READOUT OF CHANNELS INSTRUMENT LOCATION CHANNELS OPERABLE rv 1.
Intermediate Range Neutron Flux PLO6J 2
1 2.
Source Range Neutron Flux PLO6J 2
1 i
3.
Reactor Coolant Temperature -
Wide Range a.
Hot leg PLO5J 1/ loop
- 1/ loop
- l b.
Cold leg PLO5J 1/ loop 1/ loop t'
4.
Pressurizer Pressure PLO6J l
1 i'
t 5.
Pressurizer Level PLO6J 2
1 6.
Steam Generator Pressure PLO4J/PLO5J 1/stm gen 1/stm gen 7.
Steam Generator Level PLO4J 1/stm gen 1/stm gen 8.
RHR Temperature LOCAL 2
1 9.
Auxiliary Feedwater Flow Rate PLO4J/PLO5J 2/stm gen 1/stm gen SE E2 oM "i
5
- None required for Unit I loop B through the end of cycle 6 (i.e., prior to entry into Mode 3 for cycle 7) or until any unscheduled Unit.1 shutdown (entry into Mode 3 on the return to power operation) prior to the end of cycle 6.
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