ML20211A807
| ML20211A807 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/10/1999 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20211A811 | List: |
| References | |
| NPF-37-A-110, NPF-66-A-110 NUDOCS 9908240145 | |
| Download: ML20211A807 (15) | |
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION o
2 WASHINGTON, D.C. 2006H001
...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 I
BYRON STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. NPF-37 1.
The Nuclear Regulatory Commissh' (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 14,1997, 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 reguiations of the Commission; i
C.
There is reasonable assurance (l) 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 paragraphs 2.A.,2.B.(2),2.C.(1),
2.C.(2),2.C.(6),2.D. and 2.E.; and by deletbg paragraphs 2.C.(3),2.C.(4),2.C.(5),
2.C.(7), 2.C.(8), 2.C.(9), 2.C.(10), 2.C.(11), 2.C.(12), 2.C.(13), 2.C.(14), 2.C.(15) and Attachments 1 and 2 of Facility Operating License No. NPF-37* and is hereby amended to read as follows:
'Pages 2 through 5 are attached, for convenience, for the composite license to reflect these changes.
9908240145 990810 PDR ADOCK 05000454 p
2-2.
A.
The license applies to the Byron Station, Unit No.1, a pressurized water nuclear reactor and associated equipment (the facility), owned by Commonwealth Edison Company. The facility is located in north central Illinois within Rockvale Township,
. Ogle County, lilinois and is described in the licensee's " Updated Final Safety Analysis Report," as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B.
(2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; C.
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No.110 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)
The licensee shall implement and m' intain in effect all provisions of the a
approved fire protection program as described in the licensee's Fire Protection Report, and as approved in the SER dated February 1987,
- through Supplement No. 8, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
D.
The facility requires no exemptions from the requirements of 10 CFR Part 50.
E.
Commonwealth Edison shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions
- of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and l
r.
]
b 1'
l 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Byron Nuclear Power Station Security Plan,"
with revisions submitted through January 14,1988; " Byron Nuclear Power Station Security Personnel Training and Qualification Plan *," with revisions submitted through September 26,1986; and " Byron Nuclear Power Station Safeguards Contingency Plan *," with revisions submitted through July 30,1985.
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 i
J4 m4 Suzanne. Black, Acting Director Project Directorate lli j
Division of Licensing Project Management 1
Office of Nuclear Reactor Regulation
Attachment:
License Pages 2 through 5 Date of issuance: August 10, 1999 l
i
7; j
H.
After weighing the environmental, economic, technical and other benefds of the facility against environmental and other costs and considering available i
attematives, the issuance of this Facility Operating License No. NPF-37, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of l
the Commission's regulations and all applicable requirements have been satisfied; and l
l 1.'
The receipt, possession, and use of source, byproduct and speval nuclear
-l l
material as authorized by this license will be in accordance with the I
Commission's regulations in 10 CFR Parts 30,40 and 70.
i j
2.
Pursuant to approval by the Nuclear Regulatory Commission at a meeting on February 12,1985, the License for Fuel Loading and Low Power Testing, License No.
NPF-23, issued on October 31,1984, is superseded by Facility Operating License No.
NPF-37 hereby issued to Commonwealth Edison Company (the licensee) to read as l
follows:
A.
The license applies to the Byron Station, Unit No.1, a pressurized water nuclear reactor and associated equipment (the facility), owned by Commonwealth Edison Company. The facility is located in north central lilinois within Rockvale l
Township, Ogle County, Illinois and is described in the licensee's " Updated Final l
Safety Analysis Report," as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Commonwealth Edison Company:
(1)
Pursuant to Section 103 of the Act and 10 CFR Part 50 to possess, use and operate the facildy at the designated location in accordance with the procedures and limdations set forth in this license; (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at I
any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented l
l and amended; 1
l (3)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material l
as sealed neutron sources for reactor startup, sealsd sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; l.
AMENDMENT NO.110 l
y l,
(4)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample arealysis or instrument calibration or associated with radioactive
. apparatus or components; and 4
(5)
- Pursuant to the Act and 10 CFR Patts 30,40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to
{
all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified orincorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% power)in accordance with the conditions specif'ed herein.
(2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No.110 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)
Deleted.
N t
(4)
Deleted.
I (5)
Deleted.
(6)
The licensee shallimplement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report, and as approved in the SER dated February 1987
)
through Supplement No. 8, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior apprr., val of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
L AMENDMENT NO.110
]
r'
, (7)
Deleted.
i (8).
Deleted.
(9)
Deleted.
(10)
Deleted.
t
. (11)
Deleted.
l (12)
Deleted.
)
(13)
Deleted.
(14)
Deleted.
(15)
Deleted.
(16)
Deleted.
i l
(17)
Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 100, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.
D.
The facility requires no exemptions from the requirements of 10 CFR Part 50.
l E.
Commonwealth Edison shall fully implement and maintain in effect all provisions l
of the Commission approved physical security, guard training and qualification,
[
and safeguards contingency plans including amendments made pursuant to '.
i provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 anff 10 CFR 50.54(p). The plans, which contain Safeguards i
information protected under 10 CFR 73.21, are entitled: " Byron Nuclear Power Station Security Plan," with revisions submitted through January 14,1988; l-
" Byron Nuclear Power Station Security Personnel Training and Qualification Plan *," with revisions submitted through September 26,1986; and " Byron i
Nuclear Power Station Safeguards Contingency Plan *," with revisions submitted through July 30,1985.
l I
- The Security Personnel Training and Qualification Plan and the Safeguards Contingency Plan are Appendices to the Security Plan.
AMENDMENT NO.110 e
o 9 F.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c) and (e).
G.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
This license is effective as of the date of issuance and shall expire at midnight October 31,2024.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by:
Harold R. Denton, Director Office of Nuclear Recctor Regulation Appendices:
- 1. Appendix A - Technical Specifications (NUREG-1113)
- 2. Appendix B - Environmental Protection Plan
- 3. Appendix C - Additional Conditions Date of issuance: February 14,1985 AMENDMENT NO.110 I
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UNITED STATES
- r g
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. M1 49.....,o COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company ('he licensee) dated March 14,1997, 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 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 paragraphs 2.A.,2.B.,2.B.(1),
2.B.(2),2.B.(3),2.B.(4),2.B.(5),2.C.(1),2.C.(2),2.D.,2.E., and 2.F., and by deleting paragraphs 2.C.(3),2.C.(4), and Attachment 1 of Facility Operating License No.
NPF-66* and is hereby amended to read as follows:
- Pages 2 through 5 are attached, for convenience, for the composite license to reflect these changes.
e
-, 2.
A.
The license applies to the Byron Station, Unit No. 2, a pressurized water reactor, and associated equipment (the facility) owned by Commonwealth Edison Company. The facility is located in north central Illinois within Rockvale l
Township, Ogle County, Illinois and is described in the licensee's Updated Final Safety Analysis Report, as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
l B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Commonwealth Edison Company (Comed):
(1)
Pursuant to Section 103 of the AS and 10 CFR Part 50 to possess, use and operate the facility at the designated location in Ogle County, Illinois, in accordance with the procedures and limitations set forth in this license; (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess,-
and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as aquired; (4)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear -
material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and i
(5)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to posses, but ot i
separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
I
r (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.110 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. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
D.
The facility requires no exemptions from the requirements of 10 CFR Part 50.
An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1916, issued March 4,1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is 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.
E.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report and the licensee's letters dated September 23,1986, October 23,1986, November 3,1986, December 12 and 15,1986, and January 21,1987, and as approved in the SER dated February 1982 through Supplement No. 8, subject to the following provision:
The licensee may make changes to the approved fire protection program i
without prior approval of the Commission only if those changes would not i
adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
F.
Comed shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements i
revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Byron Nuclear Power Station Security Plan," with revisions submitted through January 14,1988; j
- Byron Nuclear Power Station Security Personnel Training and Qualification Plan," with revisions submitted through September 26,1986; and " Byron Nuclear Power Station Safeguards Contingency Plan, with revisions submitted through July 30,1985.
l l
l
c 4
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 A
M
^
Suzan
. Black, Acting Director Project Directorate til Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
License Pages 2 through 5 Date of issuance: August 10, 1999 1
4
. F.
Commonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and indemnity Agreements," of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available 4
altamatives, the issuance of Facility Operating License No. NPF-66, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B to License No. NPF-37, issued February 14,1985, is in accordance with 10 CFR Part 51 of the Commission's regulatione and all applicable requirements have been satisfied; and 1.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30,40 and 70.
I 2.
Based on the foregoing findings regarding this facility, Facility Operating License No.
NPF-66 hereby issued to Commonwealth Edison Company (the licensee) to read as follows:
A.
The license applies to the Byron Station, Unit No. 2, a pressurized water reactor, and associated equipment (the facility) owned by Commonwealth Edison Company. The facility is located in north central lilinois within Rockvale Township, Ogle County,~ HlinW and is described in the licensee's Updated Final l
Safety Analysis Report, as supr.:amented and amended, and in the licensee's Environmental Report, as supplemented and amended.
I B.
Subject to the conditions and requirements incorporated herein, the Commission l
hereby licenses Commonwealth Edison Company (Comed):
(1)
Pursuant to Section 103 of the Act and 10 CFR Part 50 to possess, use l
and operate the facility at the designated location in Ogle County, Illinois, in accordance with the procedures and limitations set forth in this license; (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at l
any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented l
and amended; 1
AMENDMENT NO.110 i
r-i (3)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, l
and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, l
and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30,40 and 70, to posses, but not l
separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level.
The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.110 and the Environmental Protection l
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. The licensee shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
(3).
Deleted.
(4)
Deleted.
(5)
Deleted.
AMENDMENT NO.110
D J. (6).
Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.100, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.
D.
The facility requires no exemptions from the requirements of 10 CFR Pert 50.
An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1916, issued March 4,1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is 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.
E.
The licensee shall implement and maintain in effect all provisions of the approved fire protection prgraom as described in the licensee's Fire Protection Report and the licensee's letters dated September 23,' 1986, October 23,1986, November 3,1986, December 12 and 15,1986, and January 21,1987, and as approved in the SER dated February 1982 through Supplement No. 8, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior apporval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
F.
Comed shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Byron Nuclear Power Station Security Plan," with revisions submitted through January 14,1988; i
" Byron Nuclear Power Station Security Personnel Training and Qualification Plan," with revisions submitted through September 26,1986; and " Byron Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through July 30,1985.
G.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements AMENDMENT NO.110 I
I
e l
l l
)
5-contained in Section 2.C of this license in the following manner; initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
H.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
I.
This license is effective as of the date of issuance and shall expire at midnight on November 6,2026.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Revision to Appendix A-Technical Specifications (NUREG-1113)
]
- 2. Appendix C - Additional Conditions Date of issuance: January 30,1987 9
AMENDMENT NO.110
- _ - _ _ _ _ _ _