ML073461180
| ML073461180 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/07/2007 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Gratton C, NRR, DORL, 415-1055 | |
| References | |
| TAC MD5270, TAC MD5271, TAC MD5272, TAC MD5273 | |
| Download: ML073461180 (24) | |
Text
(3) Exelon Generation Company, 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 deteciors in amounts as required; (4) Exelon Generation Company, 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 (5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 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. The 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 is not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified.
Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.1 46 , and the Environmental Protection Plan contained in Appendix B, both ot 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) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No., 1446
(4) Initial Startup Test Program Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Regulatory Guide 1.97, Revision 2 Compliance The licensee shall submit the final report and a schedule for implementation within six months of NRC approval of the DCRDR.
(6) Deleted.
(7) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 146, are hereby incorporated into this license. The' licensee shall operate the facility in accordance with the Additional Conditions.
(8) Exelon Generation Company shall provide to the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company's consolidated net utility plant, as recorded on Exelon Generation Company's books of account.
(9) Exelon Generation Company shall have decommissioning trust funds for Braidwood, Unit 1, in the following minimum amount, when Braidwood, Unit 1, is transferred to Exelon Generation Company:
Braidwood Unit 1 $154,273,345 (10) The decommissioning trust agreement for Braidwood, Unit 1, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:
(a) The decommissioning trust agreement must be in a form acceptable to the NRC.
AMENDMENT NO. 146
ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-72 The licensee shall comply with the following conditions on the schedules noted below:
Amendment Implementation Number Additional Condition Date 146 Upon implementation of Amendment No. 146 adopting With imple-TSTF-448, Revision 3, the determination of control room mentation of the envelope (CRE) unfiltered air inleakage as required by amendment SR 3.7.10.4, in accordance with TS 5.5.18.c.(i), the assessment of CRE habitability as required by Specification 5.5.18.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.18.d, shall be considered met. Following implementation:
(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.18.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from November 7, 2004, the date of the most recent successful tracer gas test, as stated in the February 7, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.18.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from November 7, 2004, the date of the most recent successful tracer gas test, as stated in the February 7, 2005 letter response to Generic Letter 2003-01, or within the next 9 months ifthe time period since-the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.18.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent'successful pressure measurement test, or within 138 days if not performed previously.
AMENDMENT NO. 146
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) Exelon Generation Company, LLC pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts are 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) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 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. The license shall be dsermed 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 is not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified.
Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 146 , and the Environmental Protection Plan contained in Appendix B, both ot which are 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) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No.' 146
(4) Initial Startup Test Program Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Deleted.
(6) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 146, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.
(7) Exelon Generation Company, LLC, shall provide the Director of the Office' of Nuclear Reactor Regulation, a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or'liens) from Exelon Generation Company, LLC to its direct or Indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company, LLC's consolidated net utility plant, as recorded on Exelon Generation Company, LLC's books of account.
(8) Exelon Generation Company, LLC, shall have decommissioning trust funds for Braidwood, Unit 2, in the following minimum amount, when Braidwood, Unit 2, is transferred to Exelon Generation Company, LLC:
Braidwood Unit 2 $154,448,967 (9) The decommissioning trust agreement for Braidwood, Unit 2, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:
(a) The decommissioning trust agreement must be in a form acceptable to the NRC.
(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited.
Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.
AMENDMENT NO. 146
ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-77 The licensee shall comply with the following conditions on the schedules noted below: I I
Amendment Implementation Number Additional Condition Date 146 Upon implementation of Amendment No. 146 adopting With imple-TSTF-448, Revision 3, the determination-oT control room mentation of the envelope (CRE) unfiltered air inleakage as required by amendment SR 3.7.10.4, in accordance with TS 5.5.18.c.(i), the assessment of CRE habitability as required by Specification 5.5.18.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.18.d, shall be considered-met. Following implementation:
(a) The first performance of SR-3.7.10.4, in accordance with Specification 5.5.18.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from November 7, 2004, the date of the most recent successful tracer gas test, as stated in the February 7, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.18.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from November 7, 2004, the date of the most recent successful tracer gas test, as stated in the February 7, 2005 letter response to Generic Letter 2003-01, or within the next 9 months ifthe time period since the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.18-d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.
AMENDMENT NO, 146
V1 Filtraiý-or,
.7.1
- 3. 7 PLANT SYSTEMS 3.7.10 Control Room Ventilation (VC) Filtration System LCO 3.7.10 Two VC Filtration System, tr~ainss sha11l be 01F*,
E,,RABLLE.
NOTE ------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One VC Filtration A.1 Restore VC Filtration 7 days System train System train to inoperable for reasons OPERABLE status.
other than Condition B.
B. One or more VC B.1 Initiate action to Irrmnediately Filtration System implement mitigating trains inoperable due actions.
to inoperable CRE boundary in MODE 1, 2, AND 3, or 4.
B.2 Verify mitigating 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> actions ensure CRE occupant exrosures to radiologica ,
chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary 90 days to OPERABLE status.
(continued) r.~ ~
l rnUN
.r._iI OF"I-iL)v~tuu tTS - C UU)iC I ') 7 .0 -
Am e dMen 146
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION JCOMPLETION TIME
. Required ction and C.I Be i, MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition A or AND B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> D. Required Action and D.i.1 Place OPERABLE VC Inmediately associated Completion Filtration System Time of Condition A train in emergency not met in MODE 5 mode.
or 6, or during movement of irradiated AND fuel assemblies.
D.1.2 Verify OPERABLE VC Immediately Filtration System train is capable of being powered by an OPERABLE emergency power source.
OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND D.2.2 Suspend positive Immediately reactivity additions.
(continued)
BRAIDWOOD - UNITS I & 2 3.7.10 - -2 Amendment 146 1
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
, W O V 1, I I I L L I fL I L .* IU S *p erusd . olv em en t Gf l a n e 4 4- l ,
System trains irradiated fuel inoperable in MODE 5 assemblies.
or 6, or during movement of irradiated AND fuel assemblies.
E.2 Suspend positive Immediately OR reactivity additions.
One or more VC Filtration System trains iToperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
F. Two VC Filtration. F.I Enter LCO 3.0.3. Immediately I System trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.7.10,1 Operate each VC Filtration System train 31 days with:
- a. Flow through the makeup system filters for _>10 continuous hours with the heaters operating; and
- b. Flow through the recirculation charcoal adsorber for >_15 minutes.
(continued)
BRAIDWOOD - UNITS 1 & 2 3.7.10 - 3 Amendment 146 1
VC Filtration System 3.7.10 SURVEILLANCE RFQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.10.2 Perform required VC Filtration System in accordance filter testing in accordance With the with the VFTP Ventilation Filter Testing Program (VFTP).
SR 3.7.10.3 Verify each VC Filtration System train 18 months actuates on an actual or simulated actuation signal.
SR 3.7.10.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habi tabi Ii ty Program.
BRAIDWOOD -- UNITS 1 & 2 3.7.10 - 4 AiTendment 146 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Proaram (continued)
- b. Air lock testing acceptance criteria are:
- i. Overall air lock leakage rate is
- 0.05 L,when tested at > P,; and
- 2. For each door, seal leakage rate is:
- i. < 0.0024 L., when pressurized to 2 3 psig, and ii. < 0.01 L., when pressurized to Ž 10 psig.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
5.5.17 Battery Monitoring and Maintenance Program This program provides for restoration and maintenance, based on the recomnendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries For Stationary Applications," or of the battery manufacturer of the following:
- a. Actions to restore battery cells with float voltage
< 2.13 V, and /
- b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.
5.5.18 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation (VC) Filtration System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
BRAIDWOOD - UNITS 1 & 2 5.5 - 21 Amendment 146
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitability Program (continued)
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (.i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors,"
Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the VC Filtration System, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.- The unfilitered air inleakage limit for radiological challenges, is the inleakage flow rate assumend in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
BRAIDWOOD - UNITS 1 & 2 5.5 - 22 Amendment 146 I I
(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 (5) Pursuant to the Act and 10 CFR Parts 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 regulation 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 3586.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.151 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.
(4) Deleted.
(5) Deleted.
(6) 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 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.
Amendment No.' 151
(7) Deleted (8) Deleted.
(9) Deleted.
(10) Deleted.
(11) Deleted.
(12) Deleted.
(13) Deleted.
(14) Deleted.
(15) Deleted.
(16) Deleted.
(17) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.1 51 , are hereby incorporated Into this license. The licensee shall operate the facility in accordance with the Additional Conditions.
(18) Exelon Generation Company, LLC shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time It is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company, LLC's consolidated net utility plant, as recorded on Exelon Generation Company, LLC's books of account.
(19) Exelon Generation Company, LLC, shall have decommissioning trust funds for Byron, Unit 1, in the following minimum amount, when Byron, Unit 1, is transferred to Exelon Generation Company, LLC:
Byron, Unit 1 $169,659,917 (20) The decommissioning trust agreement for Byron, Unit 1, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:
AMENDMENT NO. 1.51
ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-37 T..e. licensee Shall ccm-ply with the following cc nditions on the schedules noted below:
Amendment Implementation Number Additional Condition Date 151 Upon implementation of Amendment No. 1 51 With imple-adopting TSTF-448, Revision 3, the determination mentation of the of control room envelope (CRE) unfiltered air amendment inleakage as required by SR 3.7.10.4, in accordance with TS 5.5.18.c.(i), the assessment of CRE habitability as required by Specification 5.5.18.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.18.d, shall be considered met. Following implementation:
(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.18.c.(i),
shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from November 1, 2004, the date of the most recent successful tracer gas test, as stated in the January 31, 2005 letter response to Generic Letter 2003-01, or within the next 18 months ifthe time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.18.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from November 1, 2004, the date of the most recent successful tracer gas test, as stated in the January 31, 2005 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.18.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successfiul pressure measurement test, or within 138 days if not performed previously.
AMENDMENT NO. 151
(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 required; (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 (5) Pursuant to the Act and 10 CFR Parts 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 regulation 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 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1 113), as revised through Amendment No. 151, 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.
(3) Deleted.
(4) Deleted.
(5) Deleted.
Amendment No. 151
(6) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 151, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.
(7) Exelon Generation Company, LLC shall provide the Director of the Office of Nuclear Reactor Regulation, a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company, LLC's consolidated net utility plant, as recorded on Exelon Generation Company, LLC's books of account.
(8) Exelon Generation Company, LLC shall have decommissioning trust funds for Byron, Unit 2, in the following minimum amount, when Byron, Unit 2, is transferred to Exelon Generation Company, LLC:
Byron Unit 2 $156,560,489 (9) The decommissioning trust agreement for Byron, Unit 2, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:
(a) The decommissioning trust agreement must be in a form acceptable to the NRC.
(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited.
Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.
AMENDMENT NO. 151
ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-66 The !~censea s,,ll comply "ith the following conditions o, the schedules notted beiw.
Amendment Implementation Number Additional Condition .Date 151 Upon implementation of Amendment No. 151 adopting With imple-TSTF-448, Revision 3, the determination of control room mentation of envelope (CRE) unfiltered air inleakage as required by the amend-SR 3.7.10.4, in accordance with TS 5.5.18.c.(i), the ment assessment of CRE habitability as required by Specification 5.5.18.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.18.d, shall be considered met. Following implementation:
(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.18.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from November 1, 2004, the date of the most recent successful tracer gas test, as stated in the January 31, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.18.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from November 1, 2004, the date of the most recent successful tracer gas test, as stated in the January 31, 2005 letter response to Generic Letter 2003-01, or within the next 9 months ifthe time period since the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.18.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.
AMENDMENT NO. 151
VC Filtration System 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Ventilation (VC) Filtration System LCO 3.7.10 Two VC Filtration System trains shall be OPERABLE.
NOTE----------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative contol.
APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One VC Filtration A.1 Restore VC Filtration 7 days System train System train to inoperable for reasons OPERABLE status.
other than Condition B.
B. One or more VC B.1 Initiate action to Immediately Filtration System implement mitigating trains inoperable due actions.
to inoperable CRE boundary in MODE 1, 2, AND 3, or 4.
B.2 Verify mitigating 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> actions ensure CRE occupant exposures to radiological chemical, and'smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary 90 days to OPERABLE status.
(continued)
D RULJ - I I) j 1 & 3.7.10 - I Amendment 151
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION I COMPiETION TIME C. Required Action and associated Completion C.1 Be in MODE 3. 16 hourS I Time of Condition A or AND B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> D. Required Action and D.1.1 Place OPERABLE VC Immediately associated Completion Filtration System Time of Condition A train in emergency not met in MODE 5 mode.
or 6, or during movement of irradiated AND fuel assemblies.
D.1.2 Verify OPERABLE VC inmediately Filtration System train is capable of being powered by an OPERABLE emergency power source.
OR D.2.1 Suspend movement of Imniediately irradiated fuel assemblies.
AND D.2.2 Suspend positive Imrrediately reactivity additions.
.(continued)
BYRON - UNITS I & 2 3.-7.10 -, 2 151-
VC Filtration Systm 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME "r Fi tai on C_1 0 T......- .
G.
. IU U F41 II I L TL.* I, i Jusp,,d JL[llll movenment giV:ItzIL1ISI 3'1 111,1eulLr-J I U Lt'**I System trains irradiated fuel inoperable in MODE 5 assemblies.
or 6, or during movement of AND irradiated fuel assemblies. E.2 Suspend positive Immediately reactivity additions.
OR One or more VC Filtration System trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
F. Two VC Filtration F.1 Enter LCO 3.0.3. Immediately I System trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
SURVEI LLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each VC Filtration System train 31 days with:
- a. Flow through the makeup system filters for > 10 continuous hours with the heaters operating; and
- b. Flow through the recirculation charcoal adsorber for > 15 minutes.
(continued)
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VC Filtration System 3.7.10 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY
-R -7 1n ) r7-f required
- VC Fil't[ati4 -ay-em In accordance filter testing in accordance with the with the VF-P Ventilation Filter Testing Program (VFTP).
SR 3.7.10.3 Verify each VC Filtration System train 18 months actuates on an actual or simulated actuation signal.
SR 3.7.10.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitaility Program.
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Programs and Manuals 5.5 5.5 Programs anc Manuals 5.5.16 Containment Leakage Rate Testino Program (continued)
- b. Air lock testing acceptance criteria are:
- i. Overall air lock leakaqe rate is
- 0.05 L, when tested at Ž Pa; and
- 2. For each door, seal leakage rate i's:
- i. < 0.0024 L., when pressurized to Ž 3 psig, and ii. < 0.01 L., when pressurized to Ž 10 psig.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
Theprovisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
5.5.17 Battery Monitoring and Maintenance Program This program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Reconinended Practice for Maintenance, Testing, and Replacement of Vented Lead - Acid Batteries For Stationary Applications," or of the battery manufacturer of the following:
A. Actions to restore battery cells with float voltage
< 2.13 V, and B. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.
5.5.18 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation (VC) Filtration System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
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Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitabiiit Program 1,continuea)
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and Jii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designed locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of
'the VC Filtration System, operating at. the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
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