ML20153B168
| ML20153B168 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/01/1988 |
| From: | Norrholm L Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20153B172 | List: |
| References | |
| NPF-37-A-019, NPF-66-A-019 NUDOCS 8807130002 | |
| Download: ML20153B168 (6) | |
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UNITED STATES 8
i NUCLEAR REGULATORY COMMISSION g
l WASHINGTON, D. C. 20655
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COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSJ Amendment No. 19 License No. NPF-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated March 10, 1988, supplemented April 21, 1988, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re 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; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering tte 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is he"eby amended to read as follows:
8807130002 880701 PDR ADOCK 05000454 P
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(2). Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.19 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 NUC EAR,RFAULATORY COMMISSION D /
J) d ( A Proje$.Pprrho
, Acting D rector ct Liirectorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical
-Specifications Date of Issuance:
July 1, 1988
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UNITED STATES NUCLEAR REGULATORY COMMISSION 5
g WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET N0. STN 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 19 License No. NPF-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 10, 1988, supplemented April 21, 1988, 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 l
Comission; 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 regula?. ions; l
0.
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 Specifica-i tions as indicated in the attachment to this license amendment, and l
paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby i
amended to read as follows:
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2 (2) Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.19 and revised by Attachamnt 2 to NPF-60, an. the Environmental Protection Plan contained in Appendix B, both of wl.ich are 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.
3.
This license amendment is effective as of the da.t of its issuance.
FOR THE NUCLEA(R REGULATORY COMMISSION i
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i Nb GA Leif /Nr olm, Acting D rector Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 1, 1988
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4 ATTACHMENT TO LICENSE AMENDMENT NOS. 19 AND 19 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS.,}TN-5_0-454 AND STN 50-455 Revise Appendix A as follows:
Remove Page Insert Page 6-2 6-2 i
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ADMINISTRATIVE CONTROLS o
UNIT STAFF (Continued) e.
Administrative procedures shall be developed and implemented to liiiiit the working hours of unit staff who perform safety-related functions; e.g.,
licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.
The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
6.2.3 ONSITE NUCLEAR SAFETY GROUP (0NSG)
FUNCTION 6.2.3.1 The 0NSG serves as an independent safety engineering group and shall function to examine plant operating characteristics, NRC issuances, industry advisories, REPORTABLE EVENTS and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
The ONSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, opera-tions activities or other means of improving plant safety to the Manager of Nuclear Safety, and the Station Manager, Byron Station.
COMPOSITION 6.2.3.2 The 0NSG shall be composed of at least three, dedicated, full-time l
engineers located on site.
RESPONSIBILITIES 6.2.3.3 The ONSG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the 0NSG shall be prepared, main-tained, and forwarded each calendar month to the Manager of Nuclear Safety, and the Station Manager, Byron Station.
6.2.4 SHIFT TECHNICAL ADVISOR The Station Control Room Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal opera. ting or accident conditions.
During these conditions the SCRE or other on duty STA shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.
- Not responsible for sign-off function.
BYRON - UNITS 1 & 2 6-2 AMENDMENT NO. 19
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