ML20138K029
| ML20138K029 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 05/06/1997 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138K032 | List: |
| References | |
| NPF-37-A-089, NPF-66-A-089, NPF-72-A-081, NPF-77-A-081 NUDOCS 9705120026 | |
| Download: ML20138K029 (15) | |
Text
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UNITED STATES p
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WASHINGTON, D.C. 2054 6 0001
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-454 BYR0N STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 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 November 4,1996, as supplemented on December 4, 1996, and March 20, 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 (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 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:
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97o5120026 970506 PDR ADOCK 0500o454 P
1 (2)
Technical Specifications
-The Technical Specifications contained in Appendix A as revised 4
through Amendment No. 89 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.
t 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 Georg
. Dick, Senior Project Manager Project Directorate III-2 Di'/ision of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1997 T
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i UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION 4"
WASHINGTON, D.C. 20066 4 001 o%...../
COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 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 November 4, 1996, as supplemented on December 4, 1996, and March 20, 1997, 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; 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 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.
l 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 1
amended to read as follows:
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i
(2)
Technical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 89 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. Attachrent 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 4Acd J4 George F. Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications' Date of Issuance: May 6, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT NOS. 89 AND 89 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. 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 l
identified by the captioned amendment number and contain marginal lines indicating the area of change.
Pages indicated by an asterisk (*) are proviaed for convenience only.
Remove Paaes Insert Paaes
- 3/4 6-7
- 3/4 6-7 3/4 6-8 3/4 6-8 l
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T i
CONTAINMENT SYSTEMS i
AIR TEMPERATURE LIMITING CONDITION FOR OPERATION I
j 3.6.1.5 Primary containment average air temperature shall not exceed 120*F.
i APPLICABILITY: MODES 1, 2, 3 and 4.
i ACTION:
l With the containment average air temperature greater than 120*F, reduce the 3
average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures of the running fans at the i
following locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
i Location A RCFC Dry Bulb Inlet Temperature 8 RCFC Dry Bulb Inlet Temperature C RCFC Dry Bulb Inlet Temperature i
D RCFC Dry Bulb Inlet Temperature I
3 1
4 j
BYRON - UNITS 1 & 2 3/4 6-7 Amendment No. 2
. -... - ~ -.. -.. - - - -.. -. - - -.. - -. -. -. - -. -
i CONTAINMENT SYSTEMS l
CONTAINMENT VESSEL STRUCTURAL INTEGRITY i.
1 LIMITING CONDITION FOR OPERATION i
3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in t
l Specifications 4.6.1.6.1*,. 4.6.1.6.2, and 4.6.1.6.3.
1 APPLICABILITY: MODES 1, 2, 3, and 4.
.[
ACTION:
l a.
With more than one tendon with an observed lift-off force between l-the predicted lower limit and 90% of the predicted lower limit or with one tendon below 90% of the predicted lower limit, restore the j
i tendon (s).to the required level of integrity within 15 days and j
j perform an engineering evaluation of the containment and provide a
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Special Report to the Commission within 30 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next l
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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b.
With any abnormal degradation of the structural integrity other than i
i ACTION a. at a level below the acceptance criteria of Specifications i
4.6.1.6.1, 4.6.1.6.2, and 4.6.1.6.3, restore the containment vessel I
to the required level of integrity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and perform an i
engineering evaluation of the containment and provide a Special l
Report to the Commission within 15 days in accordance with l
1 Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS l
l-i 4.6.1.6.1 Containment Vessel Tendons. The containment vessel tendons' struc-i tural integrity shall be demonstrated at the end of 1, 3, and 5 years following the initial containment vessel structural integrity test and at i
j 5-year. intervals thereafter.
The tendons' structural integrity shall be demonstrated by:
t Determining'that a random but representative sample of at least a.
19 tendons (5 dome, 6 vertical, and 8 hoop) each have an observed j
lift-off force within predicted limits for each.
For each-subsequent inspection one tendon from each group may be kept i
unchanged to develop a history and to correlate the observed data.
If the observed lift-off force of any one tendon in the original sample population lies between the predicted lower limit and 90% of the predicted lower limit, two tendons, one on each side of this 1
tendon should be checked for their lift-off forces.
If both of i
i these adjacent tendons are found to be within their predicted l
limits, all three tendons should be restored to the required level of integrity. This single deficiency may be considered unique and acceptable. Unless there is abnormal degradation of the containment i
vessel during the first three inspections, the sample population for subsequent inspections shall include at least 10 tendons (3 dome, i
3 vertical, and 4 hoop);
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- Unit 1 may have sheathing filler grease voids in excess of 5% of the net duct volume for up to 35 tendons until the end of BIR08.
j BYRON --UNITS 1 & 2 3/4 6-8 AMENDMENT NO. 89 i
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UNITED STATES
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,j NUCLEAR REGULATORY COMMISSION 4
t WASHINGTON, D.C. 20666 0001 49.....,o COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 4,1996, as supplemented on December 4, 1996, and March 20, 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 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:
I
(2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 81 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'and sha'.1 be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
Ge
. Dick, Sen or Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV i
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1997 i
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'4 UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION o
' 4' WASHINGTON, D.C. 30666 4001 k9.....,d COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 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 November 4,1996, as supplemented on December 4, 1996, and March 20, 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 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 El of the Commission's reaulations 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-77 is hereby amended to read as follows:
4
. (2)
Technical Specific ;' ani The Technical Specifications contained in Appendix A as revised through Amendment No. 81 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.
3.
This license amendment is effective as of the date if its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMIS3 ION h
4 George Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1997 l
1
ATTACHMENT TO LICENSE AMENDMENT NOS. 81 AND 81 i
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.
Pages indicated by an asterisk (*) are provided for convenience only.
Remove Paaes Insert Paaes
- 3/4 6-7
- 3/4 6-7 3/4 6-8 3/4 6-8 4
J J
1 a
l i
4 1
A 1
9 1
1 CONTAINMENT SYSTEMS AIR TEMPERATURE i
LIMITING CONDITION FOR OPERATION i
j 3.6.1.5 Primary containment average air temperature shall not exceed 120'F.
APPLICABILITY: MDDES 1, 2, 3, and 4.
ACTION:
l With the containment average air temperature greater than 120'F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS i
4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures of the running fans at the following, locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Location A RCFC Dry Bulb Inlet Temperature B RCFC Dry Bulb Inlet Temperature C RCFC Dry Bulb Inlet Temperature D RCFC Dry Bulb Inlet Temperature.
j BRAIDWOOD - UNITS 1 & 2 3/4 6-7
CONTAINMENT SYSTEMS ^
CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specifications 4.6.1.6.1*, 4.6.1.6.2, and 4.6.1.6.3.
l APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
i a.
With more than one tendon with an observed lift-off force between the predicted lower limit and 90% of the predicted lower limit or with one tendon below 90% of the predicted lower limit,-restore the tendon (s) to the required level of integrity within 15 days and i
perform an engineering evaluation of the containment and provide a Special Report to the Commission within 30 days in accordance with i
Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any abnormal degradation of the structural integrity other than ACTION a. at a level below the acceptance criteria of Specifications 4.6.1.6.1, 4.6.1.6.2, and 4.6.1.6.3, restore the containment vessel to the required level of integrity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and perform an engineering evaluation of the containment and provide a Special Report to the Commission within 15 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMENTS 4.6.1.6.1 Containment Vessel Tendons. The containment vessel tendons' struc-tural integrity shall be demonstrated at the end of 1, 3, and 5 years following the initial containment vessel structural integrity test and at 5-year intervals thereafter. The tendons' structural integrity shall be demonstrated by:
a.
Determining that a random but representative sample of at least 19 tendons (5 dome, 6 vertical, and 8 hoop) each have an observed lift-off force within predicted limits for each.
For each subsequent inspection one tendon from each group may be kept unchanged to develop a history and to correlate the observed data.
i If the observed lift-off force of any one tendon in the original sample population lies between the predicted lower limit and 90% of the predicted lower limit, two tendons, one on each side of this tendon should be checked for their lift-off forces.
If both of i
l these adjacent tendons are found to be within their predicted limits, all three tendons should be restored to the required level t
of integrity. This single deficiency may be considered unique and i;
' acceptable. Unless there is abnorma1' degradation of the containment t
vessel during the first three inspections, the sarple population for l'
subsequent inspections shall include at least 10 tendons (3 dome, 3 vertical, and 4 hoop);
' Unit 1 may have sheathing filler grease voids in excess of 5% of the net duct j
volume for up to 35 tendons from May 1, 1998, until the end of AIR 07.
I BRAIDWOOD - UNITS 1 & 2 3/4 6-8 AMENDMENT NO. 81 i
ADMINISTRATIVE CONTROLS
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REPORTING REQUIREMENTS (Continued)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
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6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental a
Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT **
6.9.1.7 A Radioactive Effluent Release Report covering the operation of the facility during the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of i
Appendix I to 10 CFR Part 50.
i MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or RCS safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
OPERATING LIMITS REPORT
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6.9.1.9 Operating limits shall be established and documented in the OPERATING LIMITS REPORT (0LR) before each reload cycle or any remaining part of a reload 4
cycle for the following:
1.
Moderator Temperature Coefficient for Specification 3.1.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3.1.3.5, 3.
Control Bank Insertion Limit for Specification 3.1.3.6, 4.
Axial Flux Difference Limits, Target Band for Specification 3.2.1, 5.
Heat Flux Hot Channel Factor and K(Z) for Specification 3.2.2, 6.
Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier for Specification 3.2.3, and 1
7.
F Radial Peaking Factor for Specification 4.2.2.2.
y i
- A single submittal may be made for a multi-unit station.
,,A single submittal may be made for a multi unit station The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
BRAIDWOOD - UNITS 1 & 2 6-22 AMENDMENT NO. 80
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