ML20034G939
| ML20034G939 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/03/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20034G940 | List: |
| References | |
| NPF-37-A-052, NPF-66-A-052, NPF-72-A-041, NPF-77-A-041 NUDOCS 9303120133 | |
| Download: ML20034G939 (12) | |
Text
<
neuq j9 UNITED STATES
- v g
[
gr g
NUCLEAR REGULATORY COMMISSION
- gh WASHINGTON, D. C. 20555
- 'b y
1 8
9....+9 l
COMMONWEALTH EDISON COMPANY l
t DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. NPF-37 P
1.
The Nuclear Regulatory Commission (the Commission) has found that:
t A.
The application for amendment by Ccmmonwealth Edison Company (the licensee) dated September 16, 1992, 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; r
B.
The facility will operate in conformity with the application, the 4
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 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 Facility Operating License No. NPF-37 is hereby amended to read as follows:
9 9
9303120133 930305 PDR ADOCK 05000454 p
i (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 52 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.
I i
FOR THE NUCLEAR REGULATORY COMMISSION Jak f.l CY l
Dames E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3, 1993 i
i
~
t i
1 b
p s.tr
+#
'o UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION n
a$
WASHINGTON, D. C. 20555 o
5
%, v,/
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 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 September 16, 1992, 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 1; B.
The f acility will operate in confonnity 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 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 Facility Operating License No. NPF-66 is hereby amended to read as follows:
r i
e
. i (2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 52 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.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION rJcf.ht&Y JV
/
James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 3, 1993
[
t e
1 1
f Y
+
r-m m
m
i ATTACHMENT TO LICENSE AMENDMENT NOS. 52 AND 52 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET N05. STN 50-454 AND STN 50-455 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 Paaes Insert Paaes
{
6-6 6-6 i
f I
f i
f f
i t
i 1
}
P i
r a
ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971, except for the Health Physics Supervisor or Lead Health Physicist, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Production Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /
ANS 3.1-1978, and shall include familiarization with relevant industry opera-tional experience from the program managed by Quality Programs and Assessment.
6.5 REVIEW INVESTIGATION AND AUDIT The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below.
OFFSITE 6.5.1 The Superintendent of the Offsite Review and Investigative Function shall be appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS) responsible for nuclear activities.
The corporate audit function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS. The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.
a.
Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Function shall:
(1) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review l
BYRON - UNITS 1 & 2 6-6 AMENDMENT NO. 52
[p neuq Jg UNITED STATES
[
r l 7,
NUCLEAR REGULATORY COMMISSION E
WASHINGTON. D. C. 20555 k....+
r COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. NPF-72 1.
The Nuclear Regulatory Commission (the rommission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 16, 1992, 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; t
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 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 Facility Operating License No. NPF-72 is hereby amended to read as follows:
-2 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 41 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are i
hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
t 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9ht< f h W f
James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation l
Attachment:
f Changes to the Technical Specifications l
Date of Issuance: March 3, 1993 9
f
{
- [p 6.tC
'o UNITED STATES g
y 3
g NUCLEAR REGULATORY COMMISSION g
,y W ASHINGTON, D. C. 20555
%...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 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 September 16, 1992, 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 1; 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 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 2.0.(2) of facility Operating License No. NPF-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 41 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.
L 3.
This license amendment is effective as of the date if its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION thb: f av James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 3, 1993 I
r a
f r
I I
i t.
l
(
m. -
m m
l k
ATTACHMENT TO LICENSE AMENDMENT NOS. 41 AND 41 l
FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457' Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paces Insert Paaqi 6-6 6-6 I
O l
l r
t t
l p
i ADMINISTRATIVE CONTROLS 4
6.2.4 SHIFT TECHNICAL ADVISOR (Continued) l To assure capability for performance of all STA functions:
(1) The shift foreman (SRO) shall participate in the SCRE shift relief i
turnover.
(2) During the shift, the shift engineer and the shift foreman (SRO) shall be made aware of any significant changes in plant status in a timely manner i
by the SCRE.
(3) During the shift, the shift engineer and the shift foreman (SRO) shall remain abreast of the current plant status.
The shift foreman (SRO) shall return to the control room two or three times per shift, where practicable, to confer with the SCRE regarding plant status. Where not practicable to return to the control room, the shift foreman (SRO) shall periodically chet, with the SCRE for a plant status update.
The shift foreman (SRO) shall not abandon duties original to reactor operation, unless specifically ordered by the shift engineer.
- 6. 3 UNIT STAFF QUALIFICATIONS j
6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971, except for the Health Physics Supervisor or Lead Health Physicist, who shall meet or exceed the qualifications ~ of Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Production Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /
ANS 3.1-1978, and shall ir.:1ude familiarization with relevant industry l
operational experience from the program managed by Quality Programs and Assessment.
6.5 REVIEW INVESTIGATION AND AUDIT The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below.
i I
t BRAIDWOOD - UNITS 1 & 2 6-6 AMENDMENT NO. 41 1
6 m..
..