ML20094E544
| ML20094E544 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 11/02/1995 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20094E547 | List: |
| References | |
| NPF-37-A-076, NPF-66-A-076, NPF-72-A-086, NPF-77-A-086 NUDOCS 9511070288 | |
| Download: ML20094E544 (16) | |
Text
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UNITED STATES h
., E' NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.o. 2W1
.....p COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 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 May 13, 1993, as supplemented by letters dated August 11 and September 20, 1995, 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;
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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-37 is hereby amended to read as fc? lows:
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Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 76 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are 4
hereby incorporated into this license.
The licensee shall operate i
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 J
/U 46 Geor F. Dick, Sen or Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV I
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical I
Specifications
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Date of Issuance: November 2, 1995 I
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UNITED STATES NUCLEAR REGULATORY COMMISSION e
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%Q..... pl COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 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 May 13, 1993, as supplemented by letters dated August 11 and September 20, 1995, 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; 4
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 i
E.
The issuance of this amendment is in accordance with 10 CFR i
i Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i i
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 i
amended to read as follows:
l l
1 I
l
i i
. (2)
Technical Specifications The Technical Spacifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 76 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 1
hereby incorporated into this license. The licensee shall operate i
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 cf J-u j
Georg
. Dick, Se or Project Manager Project Directorat III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 2, 1995 1
ATTACHMENT TO LICENSE AMENDMENT NOS. 76 AND 76 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 identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 B 3/4 6-3 8 3/4 6-3 I
j
1 I
CONTAINMENT SYSTEMS CONTAINMENT PURGE VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valves shall be OPERABLE and:
a.
Each 48-inch containment shutdown purge supply and exhaust isolation valve shall be closed and power removed, and b.
The 8-inch containment purge supply and exhaust isolation valve (s) shall be closed, except when the associated penetration (s) is(are) permitted to be open for PURGING or VENTING operations under administrative control.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With a 48-inch containment purge supply and/or exhaust isolation valve open and/or powered, close and remove power to isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise be in at least HOT STANDBY withir. 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 SHUTOOWN 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 the 8-inch containment purge supply and/or exhaust isolation i
valve (s) open for reasons other than given in 3.6.1.7b above, close I
the open 8-inch valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 />.
c.
With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifi-cations 4.6.1.7.3 and/or 4.6.1.7.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise 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 />.
I 1
1 BYRON - UNITS 1 & 2 3/4 6-11 AMENDMENT NO. 76 1
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.7.1 Each 48-inch containment purge supply and exhaust isolation valve (s) i shall be verified closed and power removed at least once per 31 days.
4.6.1.7.2 Each 8-inch containment purge supply and exhaust isolation valve shall be verified to be positioned in accordance with Specification 3.6.1.7b at least once per 31 days.
4.6.1.7.3 At least once per 6 months on a STAGGERED TEST BASIS, the inboard and outboard valves with resilient material seals in each closed 48-inch containment purge supply and exhaust penetration shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than 0.05 L, when pressurized to at least P,, 44.4 psig.
4.6.1.7.4 At least once per 3 months, each 8-inch containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than 0.01 L, when j
pressurized to at least P,, 44.4 psig.
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BYRON - UNITS 1 & 2 3/4 6-12 AMENDMENT NO. 76
CONTAINMENT SYSTEMS BASES CONTAINMENT PURGE VENTILATION SYSTEM (Continued) be exceeded in the event of an accident during containment PURGING or VENTING operation. The 8-inch containment purge supply and exhaust isolation valves may be opened under conditions delineated in administrative procedures. These procedures specify those circumstances under which it is acceptable to open the valves; for example, pressure control or establishment of respirable air quality prior to containment entry. The procedures specify that:
(1) the valves must be capable of closing under accident conditions, (2) that the instrumentation for causing isolation of the valves is functioning, and (3) the effluent release will be monitored and that it will be within regulatory limits.
Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust supply valves will provide early indica-tion of resilient material seal degradation and will allow opportunity for repair before gross leakage failures could develop. The 0.60 L leakage limit of Specification 3.6.1.2.b. shall not be exceeded when the leak, age rates i
determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM i
The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or steam line break. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.
The Containment Spray System and the Containment Cooling System are redundant to each other in providing post-accident cooling of the containment atmosphere. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable Spray System to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the Spray Additive System ensures that sufficient Na0H is added to the containment spray in the event of a LOCA.
The limits on NaOH volume and concentration ensure a pH value of between 8.0 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained solution volume limit includes an allowance for solution not usable because of tank discharge line location or other physical characteristics. These assumptions are consistent with the iodine removal efficiency assumed in the safety analyses.
A spray additive tank level of between 78.6% and 90.3% ensures a volume of greater than or equal to 4000 gallons but less than or equal to 4540 gallons.
BYRON - UNITS 1 & 2 B 3/4 6-3 AMENDMENT NO. 76
- g 449 UNITED STATES
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S NUCLEAR REGULATORY COMMISSION E
j WASHINGTON, D.C. 20566-0001
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i COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. NPF-72 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
3 A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 13, 1993, as supplemented by letters dated August 11 and September 20, 1995, 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 facilit; will operate in conformity with the application, the provisions c.' 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:
1
. (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 68 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 Ramin R. Assa, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Srecifications Date of Issuance:
November 2, 1995
/
UNITED STATES
[
S NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D.C. 20swo001 g+
l 1
COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 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 May 13, 1993, as supplemented by letters dated August 11 and September 20, 1995, as 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; i
and 4
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-77 is hereby amended to read as follows:
I
J (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised i
through Amendment No. 68 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License
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No. NPF-72, dated July 2,1987, are hereby incorporated into this d
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.
j FOR THE NUCLEAR REGULATORY COMMISSION
~
Ramin R. Assa, Project Manager Project Directorate III-2 i
Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation l
1
Attachment:
Changes to the Technical Specifications Date of Issuance: November 2, 1995
ATTACHMENT TO LICENSE AMENDMENT NOS. 68 AND 6R 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 Paaes Insert Paaes 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 B 3/4 6-3 B 3/4 6-3
. -.=. _-
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CONTAINMENT SYSTEMS CONTAINMENT PURGE VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valves shall be OPERABLE and:
a.
Each 48-inch containment shutdown purge supply and exhaust isolation valve shall be closed and power removed, and b.
The 8-inch containment purge supply and exhaust isolation valve (s) shall be closed, except when the associated penetration (s) is(are) permitted to be open for PURGING or VENTING operations under j
administrative control.
l APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With a 48-inch containment purge supply and/or exhaust isolation valve open and/or powered, close and remove power to isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 the 8-inch containment purge supply and/or exhaust isolation valve (s) open for reasons other than given in Specification 3.6.1.7b above, close the open 8-inch valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 />.
c.
With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifi-cations 4.6.1.7.3 and/or 4.6.1.7.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise 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 />.
BRAIDWOOD - UNITS 1 & 2 3/4 6-11 AMENDMENT N0. 68
.~.
l CONTAINMENT SYSTEMS SURVElllANCE REQUIREMENTS 4.6.1.7.1 Each 48-inch containment purge supply and exhaust isolation valve (s) shall be verified closed and power removed at least once per 31 days.
4.6.1.7.2 Each 8-inch containment purge supply and exhaust isolation valve shall be verified to be positioned in accordance with Specification 3.6.1.7b at least once per 31 days.
BASIS, the inboard 4.6.1.7.3 At least once per 6 months on a STAGGERE' u o and outboard valves with resilient material seals in eaci closed 48-inch containment purge supply and exhaust penetration shall be demonstrated OPERABLE by verifying tht' the measured leakage rate is less than 0.05 L, when pressurized to at least P,, 44.4 psig.
4.6.1.7.4 At least once per 3 months, each 8-inch containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than 0.01 L, when pressurized to at least P,, 44.4 psig.
l l
't BRAIDWOOD - UNITS 1 & 2 3/4 6-12 AMENDMENT N0. 68 1
CONTAINMENT SYSTEMS BASES CONTAINMENT PURGE VENTILATION SYSTEM (Continued) be exceeded in the event of an accident during containment PURGING or VENTING operation.
The 8-inch containment purge supply and exhaust isolation valves may be opened under conditions delineated in administrative procedures.
These procedures specify those circumstances under which it is acceptable to open the valves; for example, pressure control or establishment of respirable air quality prior to containment entry.
The procedures specify that:
(1) the valves must be capable of closing under accident conditions, (2) that the instrumentation for causing isolation of the valves is functioning, and (3) the effluent release will be monitored and that it will be within regulatory limits.
Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust supply valves will provide early indica-tion of resilient material seal degradation and will allow opportunity for repair before gross leakage failures could develop. The 0.60 L leakage limit of Specification 3.6.1.2.b. shall not be exceeded when the leak, age rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or steam line break.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.
The Containment Spray System and the Containment Cooling System are redundant to each other in providing post-accident cooling of the containment atmosphere. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable Spray System to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the Spray Additive System ensures that sufficient Na0H is added to the containment spray in the event of a LOCA.
The limits on Na0H volume and concentration ensure a pH value of between 8.0 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The contained solution volume limit includes an allowance for solution not usable because of tank discharge line location or other physical characteristics.
These assumptions are consistent with the iodine removal efficiency assumed in the safety analyses.
A spray additive tank level of between 78.6% and 90.3% ensures a volume of greater than or equal to 4000 gallons but less than or equal to 4540 gallons.
BRAIDWOOD - UNITS 1 & 2 B 3/4 6-3 AMENDMENT NO. 68