Text

Technical Specifications, Changes Resulting from the Incorporation of TSTF-448, Control Room Habitability.
	ML073100389
Person / Time
Site:	Peach Bottom, Byron, Braidwood, Limerick, Clinton, LaSalle
Issue date:	10/31/2007
From:	; NRC/NRR/ADRO/DORL/LPLIII-2
To:	;
	Gratton C, NRR, DORL, 415-1055
Shared Package
ML072550382	List: ML072550393; ML073100389;
References
	TAC MD5270, TAC MD5271, TAC MD5272, TAC MD5273, TAC MD5274, TAC MD5277, TAC MD5278, TAC MD5279, TAC MD5280, TAC MD5282, TAC MD5283
	Download: ML073100389 (77)
	v • d • e

(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. 150 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. 150

ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO.: NPF-37 The licensee shall comply with the following conditions on the schedules noted below:

Amendment Implementation Number Additional Condition Date Upon implementation of Amendment No. 1 50 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 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 sincethe 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 bySR_ _

3.0.2, as measured from the date of the most recent successful pressure measurement fest, brwithin- 138 days if niot p-eformed previ6usly.

AMENDMENT NO. 150

(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, 150 , 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. 150

ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-66 The licensee shall comply with the following conditions on the schedules noted below:

Amendment Implementation Number Additional Condition Date Upon implementation of Amendment No. 150 adopting With imple-TSTF-448, Revision 3, the determination of control room mentation of envelope (CRE) unfiltered air inleakage as required by the amend-ment 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 5.5.184d, 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 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 1.38 days if not performed previously.... . .... ...

AMENDMENT NO.150

VC Filtration System 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control RoomVentilation (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 0.143 weeks 0.0329 months 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)

BYRON - UNITS 1 & 2 3.7.10 - 1 Amendment 150 1

VC Filtration System 3.7.10 ACTIONS (continued)

CONDITION REOUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months 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 0.214 weeks 0.0493 months D. Required Action and D.1.1 Place OPERABLE VC Immnediately 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 Imnmediately Filtration System train is capable of being powered by an OPERABLE emergency power source.

OR D.2.1 Suspend movement of' Imnediately irradiated fuel assemblies.

AND D.2.2 Suspend positive Immediately reactivity additions.

(continued)

BYRON - UNITS I & 2 3.7.10 - 2 Amendment150

VC Filtration System 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two VC Filtration E.1 Suspend movement of Immediately System trains irradiated fuel inoperable in MODE 5 assemblies.

or 6, or during movement of AND irradiated fuel assemblies. E.2 Suspend positive Inmediately 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.

SURVEILLANCE 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)

BYRON - UNITS 1 & 2 3.7.10 - 3 Amendment1 5P

VC Filtration System 3.7.10 SURVEILLANCE REQUIREMENTS (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 Habitability Program.

BYRON - UNITS 1 & 2 3.7.10 - 4 Amendment 150

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakaae Rate TestinQ Program (continued)

b. Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is

0.05 L,when tested at > Pa; and

2. For each door, seal leakage rate is:

i. < 0.0024 La, when pressurized to Ž3 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 recommendations 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. Theprogram 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 shail-include the-following-elements: ..-. - - .......

BYRON - UNITS 1& 2 /1 5.5 - 21 Amendment 150 1

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitability Program (continued)

a. The definition of the CRE and the CRE boundary.

b. Requirements fbr 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, 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.

BYRON - UNITS I & 2 5.5 - 22 Amendmentirnl I

............... IJUI

(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 detectors 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 4 5 , 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) 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,4he provisions-of 10-CFR Section 50.54(s)(2-) will apply.

Amendment No. 145

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 Upon implementation of Amendment No. 145 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. 145

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 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. 145, and the Environmental Protection Plan contained in Appendix B, both o1 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-1i0-CFR-Section.50_-54(s)(2)-will-apply -.--.....

Amendment No 145

ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-77 The licensee shall comply with the following conditions on the schedules noted below:

Amendment Implementation Number Additional Condition Date Upon implementation of Amendment No.1 4adopting 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 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 successful pressure measurement test, or within 138 days if not performed previously.

AMENDMENT NO. 145

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 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 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 0.143 weeks 0.0329 months 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)

BRAIDWOOD - UNITS 1 & 2 3. 7.10 - 1 Amendment 145 1

VC Filtration System 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months 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 0.214 weeks 0.0493 months 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. I1 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 Inmnediately reactivity additions.

(continued)

BRAIDWOOD - UNITS 1 & 2 3.7.10 - 2 Amendment 145

VC Filtration System 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two VC Filtration E.1 Suspend movement of Immediately 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 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 System trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition Bý.

SURVEILLANCE 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 Ž 10 continuous hours with the heaters operating; and

b. Flow through the recirculation charcoal adsorber for Ž 15 minutes.

. ..... (continued)

BRAIDWOOD - UNITS I & 2 3.7.10 - 3 Amendment 1451

VC Filtration System 3.7.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.10.2 Perform required VC Filtration System In accordance filter testing in accordance with the with the VFTP I 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 Habitability Program.

BRAIDWOOD - UNITS 1 & 2 1.7.10 - 4 Amendment 1451

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued)

b. Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is

0.05 L,when tested at Ž P,; and

2. For each door, seal leakage rate is:

i. < 0.0024 La, when pressurized to Ž3 psig, and ii. < 0.01 La, 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 Pronram This program provides for restoration and maintenance, based on the recommendations 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- incl-ude--the fol-lowingelements: . . . .. ..

BRAIDWOOD - UNITS 1 & 2 5.5 - 21 AmendmentlAr I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitability Program (continued)

a. The definition of the CRE and CRE boundary.

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 IRE boundary as required by paragraphs c and d, respectively.

BRAIDWOOD - UNITS 1 & 2 5.5 - 22 Amendment 145 1

(4) AmerGen Energy Company, LLC, pursuant to the Act and to 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; (5) AmerGen Energy Company, LLC, 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 (6) AmerGen Energy 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. 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 AmerGen Energy Company, LLC is authorized to operate the facility at reactor core power levels not in excess of 3473 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 and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 178 are hereby incorporated into this license.

AmerGen Energy Company, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment-No. 1 -78

(22) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the follow key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (23) Upon implementation of Amendment No. 178 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.3.5, in accordance with TS 5.5.15.c.(i), the assessment of CRE habitability as required by Specification 5.5.15.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.15.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.3.5, in accordance with Specification 5.5.15.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 16, 2004, the date of the most recent successful tracer gas test, as stated in the February 8, 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 5.5.15.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from November 16, 2004, the date of the most recent successful tracer gas test, as stated in the February 8, 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.

Amendment No.1 78 1

-7a-(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.15.d, shall be within 24 months, plus the 6 months allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 6 months if not performed previously.

D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include: (a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirement of 10 CFR Part 50, Appendix J - Option B, paragraph Ill.B, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for local leak rate tests (Section 6.2.6 of SSER 6); and (c) an exemption from the requirements of paragraph 1II.B of Option B of 10 CFR Part 50, Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve 1E51-F374 associated with containment penetration 1 MC-44 from inclusion in the combined leakage rate for penetrations and valves subject to Type B and C tests (SER supporting Amendment 62 to Facility Operating License No. NPF-62). The special circumstances regarding each exemption, except for item (a) above, are identified in the referenced section of the safety evaluation report and the supplements thereto.

Amendment No.1 7 8

Control Room Ventilation System 3.7.3 3.7 PLANT SYSTEM 3.7.3 Control Room Ventilation System LCO 3.7.3 Two Control Room Ventilation subsystems shall be OPERABLE.

- - -NOTE-------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the primary or secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Control Room A.1 Restore Control Room 7 days Ventilation subsystem Ventilation subsystem inoperable for reasons to OPERABLE status.

other than Condition B.

B. One or more Control B.1 Initiate action to Immediately Room Ventilation implement mitigating subsystems inoperable actions.

due to inoperable CRE boundary in MODE 1, 2,or 3. AND Verify mitigating 24 hours1 days 0.143 weeks 0.0329 months B.2 actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND 90 days B.3 Restore'CRE boundary

.toOPERABLEstatus.-

(continued)

CLINTON 3.7-4 Amendment No. 1 78

Control.Room Ventilation System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Associated Completion Time of Condition A or AND B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months D. Required Action and ------------ NOTE-------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated D.1 Place OPERABLE Immediately fuel assemblies in the Control Room primary or secondary Ventilation subsystem containment, during in high radiation CORE ALTERATIONS, or mode.

during OPDRVs.

OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the primary and secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E. Two Control Room E.1 Enter LCO 3.0.3. Immediately Ventilation subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

CLINTON 3.7-5 Amendment No. 178

Control Room Ventilation System 3.7.3 ACTIONS (continued) ........ ..

CONDITION REQUIRED ACTION COMPLETION TIME F. Two Control Room F.1 Suspend movement of Immediately Ventilation subsystems irradiated fuel inoperable during assemblies in the movement of irradiated primary and secondary fuel assemblies in the containment.

primary or secondary containment, during AND CORE ALTERATIONS, or during OPDRVs. F.2 Suspend CORE Immediately ALTERATIONS.

OR AND One or more Control Room Ventilation F.3 Initiate action to Immediately subsystems inoperable suspend OPDRVs.

due to inoperable CRE boundary during movement of irradiated

,fuel assemblies in the primary or secondary containment, during CORE ALTERATIONS, or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each Control Room Ventilation 31 days subsystem with flow through the makeup filter for Ž 10 continuous hours with the heaters operating.

SR 3.7.3.2 Operate each Control Room. Ventilation 31 days subsystem with flow through the recirculation filter for Ž 15 minutes.

(continued)

CLINTON 3.7-6 Amendment No. 178 I

Control Room Ventilation System 3.7.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required Control Room Ventilation In accordance filter testing in accordance with the with the VFTP Ventilation Filter Testing Program (VFTP).

SR 3.7.3.4 Verify each Control Room Ventilation 24 months subsystem actuates on an actual or simulated initiation signal.

SR 3.7.3.5 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitability Program CLINTON 3.7-7 Amendment No 1 7 8

Programs and Manuals 5.5 5.5 Program and Manuals 5.5.14 Battery Monitoring and Maintenance Program This program provides for battery restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing and Replacement of Vented Lead-Acid Batteries for Stationary Applications,"

including 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.

5.5.15 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 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:

a. The definition of the CRE and the CRE boundary.

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 Section C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Evelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Section C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

(continued)

CLINTON 5.0-16b Amendment No.

178

Programs and Manuals 5.5 5.5 Program and Manuals 5.5.15 Control Room Envelope Habitability Program (continued)

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the Control Room Ventilation System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 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 paragraph c and d, respectively.

CLINTON 5. 0-16c Amendment No. 178

(4) Exelon Generation Company, LLC, 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, 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 LaSalle County Station, Units 1 and 2.

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 full power (3489 megawatts thermal).

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 186' and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Conduct of Work Activities Durinq Fuel Load and Initial Startup The licensee shall review by committee all Unit 1 Preoperational Testing and System Demonstration activities performed concurrently with Unit 1 initial fuel loading or with the Unit 1 Startup Test Program to assure that the activity will not affect the safe performance of the Unit 1 fuel loading or the portion of the Unit 1 Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security and health physics, with respect to-performance of the activity concurrently with the Unit 1 fuel loading or the portion of the Unit 1 Startup Program being performed. The committee for the review shall be composed of at least three members, knowledgeable in the above areas, and who meet the qualifications for professional-technical personnel specified by Amendment-No. 1-86

- 16a2 -

Am. (45) Upon implementation of Amendment No.1 86 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.4.5, in accordance with TS 5.5.15.c.(i), the assessment of CRE habitability as required by Specification 5.5.15.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.15.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.4.5, in accordance with Specification 5.5.15.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from 1998, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 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 5.5.15.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from 1998, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 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 5.5.15.d, shall be within 24 months, plus 6 months allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 6 months if not performed previously.

D. The facility requires exemptions from certain requirements of 10 CFR Part 50, 10 CFR Part 70, and 10 CFR Part 73. These include:

(a) Exemptions from certain requirements of Appendices G, H and J and 10 CFR Part 73 are described in the Safety Evaluation Report and Supplement No. 1, No. 2, No. 3 to the Safety Evaluation Report.

(b) An exemption was requested until completion of the first refueling from the requirements of 10 CFR 70.24.

(c) An exemption from 10 CFR Part 50, Appendix E from performing a full scale exercise within one year before issuance of an operating license, both exemptions (b) and (c) are described in Supplement No. 2 of the Safety Evaluation Report.

(5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station Units 1 and 2.

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 full power (3489 megawatts thermal). Items in Attachment 1 shall be completed as specified. Attachment 1 is hereby incorporated .into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.1 73 , and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection .Plan.

(3) Conduct of Work Activities During Fuel Load and Initial Startup The licensee shall review by committee all Unit 2 Preoperational Testing and System Demonstration activities performed concurrently with Unit 2 initial fuel loading or with the Unit 2 Startup Test Program to assure that the activity will not affect the safe performance of the Unit 2 fuel loading or the portion of the Unit 2 Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security and health physics, with respect to performance of the activity concurrently with the Unit 2 fuel loading or the portion of the Unit 2 Startup Program being performed. The committee for the review shall be composed of at least three members, knowledgeable in the above areas, and who meet the qualifications for professional-technical personnel specified by section 4.4 of ANSI N18.7-1971. At least one of these three shall be a senior member of the Assistant Superintendent of Operation's staff.

Amendment No. 173

- 9d -

(28) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordination fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged

6. Training or integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (29) Upon implementation of Amendment No. 173 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.4.5, in accordance with TS 5.5.15.c.(i), the assessment of CRE habitability as required by Specification 5.5.15.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.15.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.4.5, in accordance with Specification 5.5.15.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from 1998, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 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 5.5.15.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from 1998, the date of the most

-recent-successful-tracergas-testas-stated in-the December 97-2003 letter response to Generic Letter 2003-01, or within the next 9 months if the-timeF-p-enrid sinc-et h-e-mcgt-re-e-nts[-C*:-es-ful tracei gas test is greater than 3 years.

10-(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.15.d, shall be within 24 months, plus the 6 months allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 6 months if not performed previously.

D. The facility requires exemptions from certain requirements of 10 CFR Part 50, 10 CFR Part 70, and 10 CFR Part 73. These include:

(a) Exemptions from certain requirements of Appendices G, H and J to 10 CFR Part 50, and to 10 CFR Part 73 are described in the Safety Evaluation Report and Supplement Numbers 1, 2, 3, and 5 to the Safety Evaluation Report.

(b) An exemption was requested until completion of the first refueling from the requirements of 10 CFR 70.24.

(c) An exemption from the requirement of paragraph III.D of Appendix J to conduct the third Type A test of each ten-year service period when the plant is shutdown for the 10-year plant inservice inspections.

(d) A one-time exemption from the requirement of paragraph III.A.6(b) of Appendix J to resume a Type A test scheduleof three times in ten years.

Exemptions (c) and (d) are described in the Safety Evaluation accompanying Amendment No. 87 to this license.

(e) An exemption was granted to remove the Main Steam Isolation Valves (MSIVs) from the acceptance criteria for the combined local leak rate test (Type B and C), as defined in the regulations of 10 CFR Part 50, Appendix J, Option B, Paragraph III.B. Exemption (e) is described in the safety evaluation accompanying Amendment No. 97 to this License.

These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.

Therefore, these exemptions are hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, and the rules and regulations of the Commission (except as hereinafter exempted therefrom), and the provisions of the Act.

E. Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evaluated in the Final Environmental

ý-Statement-and its-Addendum, -the licensee-shall-provide-a-written-notification-to-the Director of the Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with-siUchc-ativitie-S..

CRAF System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Area Filtration (CRAF) System LCO 3.7.4 Two CRAF subsystems shall be OPERABLE.

-NOTE --------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAF subsystem A.1 Restore CRAF 7 days inoperable for reasons subsystem to OPERABLE other than Condition status.

B.

B. One or more CRAF B.1 Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.

boundary in MODE 1, 2, or 3. AND B.2 Verify mitigating 24 hours1 days 0.143 weeks 0.0329 months actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 RestoreCRE--bound-a-ry-- -days-to OPERABLE status.

(continued)

LaSalle I and 2 3.7.4-1 Amendment No186/171

CRAF System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

D. Required Action and ------------- NOTE----------- I associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated 0.1 Place OPERABLE C'RAF Immediately fuel assemblies in the subsystem in secondary containment, pressurization mode.

during CORE ALTERATIONS, or during OR OPDRVs.

D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E. Two CRAF subsystems E.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

LaSalle I and 2 3. 7.4-2 Amendment No. 186/ 173 I

CRAF System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Two CRAF subsystems ------------- NOTE -------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated -----------------------------

fuel assemblies in the secondary containment, F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during a'ssemblies in the OPDRVs. secondary containment.

OR AND One or more CRAF subsystems inoperable F.2 Suspend CORE Immediately due to inoperable CRE ALTERATIONS.

boundary during movement of irradiated AND fuel assemblies in the secondary containment, F.3 Initiate action to Immediately during CORE suspend OPDRVs.

ALTERATIONS, or during OPDRVS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CRAF subsystem for 31 days

Ž 10 continuous hours with the heaters operating.

(continued)

LaSalle I and 2 3.7.4-3 Amendment No. 186/1'73 1

CRAF System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.2 Manually initiate flow through the CRAF 31 days recirculation filters for 2 10 hours0.417 days 0.0595 weeks 0.0137 months .

SR 3.7.4.3, Perform required CRAF filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.4.4 Verify each CRAF subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.7.4.5 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitability Program LaSalle'l and 2 3.7.4-4 Amendment No. 186/173 I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, which includes the following:

a. Actions to restore battery cells with float voltage < 2.1.3 V; and

b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates; and

c. Actions to verify that the remaining cells are Ž 2.07 V when a cell or cells have been found to be < 2.13 V.

5.5.15 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 Area Filtration (CRAF) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiologic'al 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 whole body or its equivalent to any part of the body. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

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, at designated locations, of the CRE pressure re-l-at-ive toi-al1--ex-ternal *area-s-- adjacent-to-the -C-RE boundary during the pressurization mode of operation by one train of LaSalle 1 and 2 5.5-14 Amendment No.186/173 I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Control Room Envelope Habitability Program (continued) the CRAF System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS.

The results shall be trended and used. as part of the 24 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.

LaSalle 1 arnd 2 5.5-15 Amendment No. 186 / 173

(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, 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, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

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 (except as exempted from compliance in Section 2.D. below) 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal (100% rated power) in accordance with the conditions specified herein and 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 and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 188 , are hereby incorporated into this license.

Exelon Generation Company shall operate the facility in accordance with the

I Technical Specifications and the Environmental Protection Plan.

Amrn-endm-nt No. 6 a 1-47-1 88.

(22) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(23) Upon implementation of Amendment No. 188 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 4.7.2.2.a, in accordance with TS 6.16.c.(i), the assessment of CRE habitability as required by Specification 6.16.c.(ii), and the measurement of CRE pressure as required by Specification 6.16.d, shall be considered met. Following implementation:

(a) The first performance of SR 4.7.2.2.a, in accordance with Specification 6,16.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 4.0.2, as measured from September 16, 2004, the date of the most recent successful tracer gas test, as stated in the December 10, 2004 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 6.16.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 4.0.2, as measured from September 16, 2004, the date of the most recent successful tracer gas test, as stated in the December 10, 2004 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 6.16.d, shall be within 24 months, plus the 180 days allowed by SR 4.0.2, as measured from September 16, 2004, the date of the most recent successful pressure measurement test, or within 180 days if not performed previously.

D. The facility requires exemptions from certain requirements of '10CFR Part 50.

These include (a) exemption from the requirement of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3), (b) exemption from the requirements' of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemption from the requirements of Appendix J that the measured MSIV leak rates be included in the summation for the local leak rate test (Section 6.2.6 of SSER-3), (c) exemption from the requirement of Appendix J, the local leak rate testing of the Traversing Incore Probe Shear Valves (Section 6.2.6 of the SER and SSER-3).

These exemptions are authorized by law and will not endanger Amendment NQ. ,43.-141 .188 Revised by letter dated October 28, 2004 Revised by letter dated December 10, 2004 Revised by letter dated May 31, 2007 Revised by letter dated August 9, 2007

9 life or property or the common defense and security and are otherwise in the public interest. Therefore these exemptions are hereby granted pursuant to 10 CFR 50.12 and 50.47(c). With the granting of these exemptions the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provision of the Act, and the rules and regulations of the Commission.

E. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans', submitted by letter. dated May 17, 2006, is entitled:

"Limerick Generating Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2." The set contains Safeguards Information protected under 10 CFR 73.21.

F. Deleted G. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance 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 on October 26, 2024.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by Darrell Eisenhut for Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments/Appendices:

1. Attachments 1-2

2. Appendix A - Technical Specifications (NUREG-1 149)

3. Appendix B - Environmental Protection Plan

4. Appendix C - Additional Conditions Date of Issuance: August 8, 1985 -The-Training-and-Qualification Plan and Safeguards Contingency Plan are Appe*ndics to the Security Plan.

Amendment No. 9- 4-28, 43-1-44., 188 Revised by letter dated October 28, 2004 Revised by letter dated December 10, 2004 Revised by letter dated May 31, 2007

BASES SECT ION ................................................................. PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES ................ B 3/4 6-4 3/4.6.4 VACUUM RELIEF ........................................ B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT .............................. B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL .............. B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS - COMMON SYSTEMS .............. B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM -

COMMON SYSTEM ........................................ B 3/4 7-1 a 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM ................ B 3/4 7-1 cl 3/4.7.4 SNUBBERS ............................................. B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION ......................... B 3/4 7-3 3/4.7.6 (Deleted) .................................. ......... B 3/4 7-4 3/4.7.7 (Deleted) ........................................ B 3/4 7-4 3/4.7.8 MAIN TURBINE BYPASS SYSTEM ........................... B 3/4 7-5 3/4.8 ELECTRI CAL POWER SYSTEM 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER DISTRIBUTION SYSTEMS ................................. B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES .............. B 3/4 8-3

.3/4.9 REFUELI NG OPERATIONS 3/4.9.1 REACTOR MODE SWITCH .................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION .............. ........................ B 3/4 9-1 3/4.9.3 CONTROL ROD POSITION ................................. B 3/4 9-1 3/4.9.4 DECAY TIME ........................................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS ............ ....................... B 3/4 9-1

.LIMERICK - UNITI1 xxi Amendment No.' 2-, 4.9, 4, 4-94,188

ADMINISTRATIVE CONTROLS SECTION PAGE 6.13 PROCESS CONTROL PROGRAM (PCP) ..................................... 6-21 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) ............................. 6-22 6 .15 (Deleted ) .................................... .................... 6 -22 6.16 CONTROL ROOM ENVELOPE HABITABILITY PROGRAM ........................ 6-22 LIMERICK - UNIT I xxvii i Amendment No. 49, 188

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - COMMON SYSTEM LIMITING 'CONDITION FOR OPERATION 3.7.2 Two independent control room emergency fresh air supply system subsystems shall be OPERABLE.

NOTE: The main control room envelope (CRE) boundary may be opened intermittently under administrative control APPLICABILITY: All, OPERATIONAL CONDITIONS and when RECENTLY IRRADIATED FUEL is being handled in the secondary containment, or during operations with a potential for draining the reactor vessel.

ACTION:

a. In OPERATIONAL CONDITION 1, 2, or 3:

1. With one control room emergency fresh air supply subsystem inoperable for reasons other than Condition a.2, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

2. With one or more control room emergency fresh air supply subsystems inoperable due to an inoperable CRE boundary,

a. Initiate action to implement mitigating actions immediately or be in HOT SHUTDOWN within 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months ; and

b. Within 24 hours1 days 0.143 weeks 0.0329 months , verify mitigating actions ensure CRE occupant exposures to radiological and chemical hazards will not exceed limits and actions to mitigate exposure to smoke hazards are taken or be in HOT SHUTDOWN within 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months ; and

c. Restore CRE boundary to operable' status within 90 days or be in HOT SHUTDOWN within 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

b. In OPERATIONAL CONDITION 4, 5, or when RECENTLY IRRADIATED FUEL is being handled in the secondary containment, or during operations with a potential for draining the reactor vessel:

1. With one control room emergency fresh air supply subsystems inoperable for reasons other than Condition b.3, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the radiation isolation mode of operation.

2. With both control room emergency fresh air supply subsystems inoperable for reasons other thanCondition b.3, immediately

-.--.-...-suspend-handl-ing-of-RECENTLY-iRRADlATED-FUE h-i-the s -condary-containment and operations with a potential for draining the reactor vesse-l-.-- The-- prov-i-s-ions-- of--Spec-i-i cat-ion --3T-O. 3 are--not-applicable.

LIMERICK - UNIT I 3/4 7-6 Amendment No. 4J1,-9,,4- g,44ý6, 18 8

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

3. With one or more control room emergency fresh air subsystems inoperable due to an inoperable CRE boundary, immediately suspend handling of RECENTLY IRRADIATED FUEL in the secondary containment and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.2.1 Each control room emergency fresh air supply subsystem shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by verifying the control room air temperature to be less than or equal to 85 0 F effective temperature.

b. In accordance with the Surveillance Frequency Control Program on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates with the heaters OPERABLE.

c. In accordance with the Surveillance Frequency Control Program or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the subsystem by:

1. Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 3000 cfm +/- 10%.

2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration of less than 2.5%

when tested in accordance with ASTM D3803-1989 at a temperature of 30 0 C (86 0 F) and a relative humidity of 70%.

3. Verifying a subsystem flow rate of 3000 cfm +/- 10% during subsystem operation when tested in accordance with ANSI N510-1980.

d. After every 720 hours30 days 4.286 weeks 0.986 months of charcoal adsorber operation by'verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration of less than 2.5%

when tested in accordance with ASTM D3803-1989 at a temperature of 30 0 C (860F) and a Ylati -Tuhidtf-70%.

LIMERICK - UNIT 1 3/4 7-7 Amendment No. 6,9,ý-4O,-4-44,'4.,188

-!-8,

PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

e. In accordance with the Surveillance Frequency Control Program by:

1. Verifying that the pressure drop across the combined prefilter, upstream and downstream HEPA filters, and charcoal adsorber banks is less than 6 inches water gauge while operating the subsystem at a flow rate of 3000 cfm +/- 10%; verifying that the prefilter pressure drop is less than 0.8 inch water gauge and that the pressure drop across each HEPA is less than 2 inches water gauge.

2. Verifying that on each of the below chlorine isolation mode actuation test signals, the subsystem automatically switches to the chlorine isolation mode of operation and the isolation valves close within 5 seconds:

a) Outside air intake high chlorine, and b) Manual initiation from the control room.

3. Verifying that on each of the below radiation isolation mode actuation test signals, the subsystem automatically switches to the radiation isolation mode of operation:

a) Outside air intake high radiation, and b) Manual initiation from control room.

f. -After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetra-tion and bypass leakage testing acceptance criteria of less than 0.05%

in accordance with ANSI N510-1980 while operating the system at a flow rate of 3000 cfm +/- 10%.

q. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 3000 cfm +/- 10%.

4.7.2.2 The control room envelope boundary shall be demonstrated OPERABLE:

a. At a frequency in accordance with the Control Room Envelope Habitability Program by performance of control room envelope unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

LIMERICK - UNIT 1 3/4 7-8 Amendment No. B,4O,.-4,-1-&* ,

4-9&6,188

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2. A determination that the change did not reduce the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

a. Shall be documented with the following information:

1. Sufficient information to support the change together with the appropriate analyses or. evaluations justifying the change(,s) and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective upon review and acceptance by the RORC and the approval of the Plant Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report .in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) -INFORMATION FROM THIS SECTION RELOCATED TO THE OCM.

6.16 CONTROL ROOM ENVELOPE HABITABILITY PROGRAM A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE h'abitability is maintained such that, with an OPERABLE Control Room Emergency Fresh Air Supply (CREFAS) 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 protectfon is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions withoutpersonnel 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:

a.-__ Thhe-de.fini-t.i-on .o*__the --CRE--and the--CRE boundary.

.... ..... . Req iemen.ts for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

LIMERICK - UNIT I 6-22 Amendment No. 49,49,-74,4-6,-71-9-7, 188

ADMINISTRATIVE CONTROLS CONTROL ROOM ENVELOPE HABITABILITY PROGRAM (Continued)

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, at designated 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 CREFAS, operating at the flow rate required by SR 4.7.2.1.c.1, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of-the 24 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 Specification 4.0.2 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.

LIMERICK - UNIT 1 6-23 Amendment No.188

(4) Pursuant to the Act and 10 CFR Parts 30, 40, 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, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

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 (except as exempted from compliance in Section 2.D. below) 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels of 3458 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 149 , are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fire Protection (Section 9.5, SSER-2, -4)*

Exelon Generation Company shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report dated August 1983 through Supplement 9, dated August 1989, and Safety Evaluation dated November 20, 1995, 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.

The parenti-eti&cal-no-tationfollowi-ng-thetitle-of licensecondion--do-te-th-es denotes-the section of the Safety Evaluation Report and/or its supplements wherein the license condition is .

discu-ssed. .. .......... ........... . . ........ .. . . .. . ... .. . . ... .

Amendment No. , 27, 8-1-, 68, 9,1._-08 .149

(10) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(11) Upon implementation of Amendment No.149 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 4.7.2.2.a, in accordance with TS 6.16.c.(i), the assessment of CRE habitability as required by Specification 6.16.c.(ii), and the measurement of CRE pressure as required by Specification 6.16.d, shall be considered met.

Following implementation:

(a) The first performance of SR 4.7.2.2.a, in accordance with Specification 6.16.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 4.0.2, as measured from September 16, 2004, the date of the most recent successful tracer gas test, as stated in the December 10, 2004 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 6.16.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 4.0.2, as measured from September 16, 2004, the date of the most recent successful tracer gas test, as stated in the December 10, 2004 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 6.16.d, shall be within 24 months, plus the 180 days allowed by SR 4.0.2, as measured from September 16, 2004, the date of the most recent successful pressure measurement test, or within 180 days if not performed previously.

D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) exemption from the requirement of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3), (b) exemption from the requirements of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemption from the requirements of Appendix J that the measured MSIV leak' rates be included in the summation for the local leak rate test (Section 6.2.6.1 of SSER-3), (c) exemption from the requirement of Appendix J, the local leak rate testing of the Traversing Incore Probe Shear Valves (Section 6.26.1 of the SER and SSER-3), and (d) an exemption Amendment No. 92, 4-8, 44,3,149 Revised by letter dated August 9, 2007

- 5a -

from the schedule requirements of 10 CFR 50.33(k)(I) related to availability of funds for decommissioning the facility (Section 22.1, SSER 8). The special circumstances regarding exemptions (a), (b) and (c) are identified in Sections 6.2.6.1 of the SER and SSER 3. An exemption from the criticality monitoring requirements of 10 CFR 70.24 was previously granted with NRC materials license No. SNM-1977 issued November 22, 1988. The licensee is hereby exempted from the requirements of 10 CFR 70.24 insofar as this requirement applies to the handling and storage of fuel assemblies held under this license.

These exemptions, are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items a, b, c, and d above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. Deleted F. 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.

Amendment No. .92,408, 14,,149 Revised by letter dated August 9, 2007

INDEX BASFS SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES ................. B 3/4 6-4 3/4.6.4 VACUUM RELIEF ........................................ B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT ................................ B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL ............... B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS - COMMON SYSTEMS ............... B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM -

COMMON SYSTEM ......................................... B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM ............... B 3/4 7-1 c 3/4.7.4 SNUBBERS .............................................. B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION .......................... B 3/4 7-3 3/4.7.6 (Deleted) ............................................ B 3/4 7-4 3/4.7.7 (Deleted) ............................................. B 3/4 7-4 3/4.7.8 MAIN TURBINE BYPASS SYSTEM ........................... B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEM 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER DISTRIBUTION SYSTEMS ..................................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES .............. B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH .................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION ....................................... B 3/4 9-1 3/4.9.3 CONTROL ROD POSITION ................................. B 3/4 9-1 3/4.9.4 DECAY TIME ........................................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS ............. ........................ . B- 3/,4 9-1 LIMERICK - UNIT 2 xxi Amendment No. 4-6, 68, 149

INDE X ADMINISTRATIVE CONTROLS C TT CI J. id uIu PAGE 6.13 PROCESS CONTROL PROGRAM (PCP) ................................. 6-21 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM ......................... 6-22 6.15 (Deleted) ................................................... 6-22 6.16 CONTROL ROOM ENVELOPE HABITABILITY PROGRAM ...................... 6-22 LIMERICK - UNIT 2 xxvii i Amendment No. 44, 149

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - COMMON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency fresh air supply system subsystems shall be OPERABLE.

NOTE: The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: All OPERATIONAL CONDITIONS and when RECENTLY IRRADIATED FUEL is being handled in the secondary containment, or during operations with a potential for draining the reactor vessel.

ACTION:

a. In OPERATIONAL CONDITION 1, 2, or 3:

1. With the Unit 1 diesel generator for one control room emergency fresh air supply subsystem inoperable for more than 30 days, be in at least HOT SHUTDOWN within the'next 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

2. With one control r oom emergency fresh air supply subsystem inoperable for reasons other than Condition a.5, restore the inoperable subsystem to OPERABLE status within .7days, or be in at least HOT SHUTDOWN within the next 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

3. With one control room emergency fresh air supply subsystem inoperable for reasons other than Condition a.5, and the other control room emergency fresh air supply subsystem with an inoperable Unit 1 diesel generator, restore the inoperable subsystem to OPERABLE status or restore the Unit 1 diesel generator to OPERABLE status within 72 hours3 days 0.429 weeks 0.0986 months , or be in at least HOT SHUTDOWN within the next 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

4. With the Unit I diesel generators for both control room emergency fresh air supply subsystems inoperable for more than 72 hours3 days 0.429 weeks 0.0986 months , be in at least HOT SHUTDOWN within the next 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

5. With one or more control room emergency fresh air supply subsystems inoperable due to an inoperable CRE boundary,

a. Initiate action to implement mitigating actions immediately or be in HOT SHUTDOWN within 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the followirg 24 hours1 days 0.143 weeks 0.0329 months ; and

b. Within 24 hours1 days 0.143 weeks 0.0329 months , verify mitigating actions ensure CRE occupant exposures to radiological and chemical hazards IWw _n ot e x.ce ed- in-i _t s-a-n d--ac-t-i-o n-s--to-m-i-t-i-g ate- -e x-p os-u-re - -to m-i smoke hazards are taken or be in HOT SHUTDOWN within 12 hour-s ..and i-n COLD- SHUTDOWN- w-i-th-i-n -the -fol l-owi-ng 24- hours; and LIMERICK - UNIT 2 3/4 7-6 Amendment No. 44A, 46,149

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

c. Restore CRE boundary to operable status within 90 days or be in HOT SHUTDOWN within 12 hours0.5 days 0.0714 weeks 0.0164 months and in COLD SHUTDOWN within the following 24 hours1 days 0.143 weeks 0.0329 months .

b. In OPERATIONAL CONDITION 4, 5 or when RECENTLY IRRADIATED FUEL is being handled in the secondary containment, or during operations with a potential for draining the reactor vessel:

1. With one control room emergency fresh air supply subsystem inoperable for reasons other than Condition b.3, restore the inoperable subsystem to OPERABLE status within 7 days, or initiate and maintain operation of the OPERABLE subsystem in the radiation isolation mode of operation.

2. With both both control room emergency fresh air supply subsystem inoperable for reasons other than Condition b.3, immediately suspend handling of RECENTLY IRRADIATED FUEL in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.

3. With one or more control room emergency fresh air subsystems inoperable due to an inoperable CRE boundary, immediately suspend'handling of-RECENTLY IRRADIATED FUEL in the secondary containment and operations with a potential for-draining the reactor vessel. The provisions of Specification. 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.2.1 Each control room emergency fresh air supply subsystem shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by verifying the control room air temperature to be less than or equal to 85.°F effective temperature.

b. In accordance with the Surveillance Frequency Control Program on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates with the heaters OPERABLE.

c. In accordance with'the Surveillance Frequency Control Program or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the subsystem by:

1. Verifying that the subsystem satisfies the in-place penetration

-.-- and- bypass- 1eakage-te-sti-ng c-le s{-than 0.05% and uses the test procedure guidance in Regulatory Positions C '5 '-a-, C.5,.c, and- CT5-d- -of---Regul-ato ry-G id--1 52---Re-vi-si-6 -2, March 1978, and the system flow rate is 3000 cfm +/- 10%.

LIMERICK - UNIT 2 3/4 7-6a Amendment No. -4, 4-4-;,149

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration of less than 2.5%

when tested in accordance with ASTM D3803-1989 at a temperature of 30'C (86°F) and a relative humidity of 70%.

3. Verifying a subsystem flow rate of 3000 cfm +/- 10% during subsystem operation when tested in accordance with ANSI N510-1980.

d. After every 720 hours30 days 4.286 weeks 0.986 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration Pf less than 2.5% when tested in accordance with ASTM D3803-1989 at a temperature of 30 0 C (86 0 F) and a relative humidity of 70%.

e. In accordance with the Surveillance Frequency Control Program by:

1. Verifying that the pressure drop across the combined prefilter, upstream and downstream HEPA filters, and charcoal adsorber banks is less than 6 inches water gauge while operating the subsystem at a flow rate of 3000 cfm +/- 10%; verifying that the prefilter pressure drop is less than 0.8 inch water gauge and that the pressure drop across each HEPA is less than 2 inches water gauge.

2. Verifying that on each. of the below chlorine isolation mode actuation test signals, the subsystem automatically switches to the chlorine isolation mode of operation and the isolation valves close within 5 seconds:

a) Outside air intake high chlorine, and b) Manual initiation from the control room.

3. Verifying that on each of thebelow radiation isolation mode actuation test signals, the subsystem automatically switches to the radiation isolation mode of operation:

a) Outside air intake high radiation, and b) Manual initiation from control room.

LIMERICK - UNIT 2 3/4 7-7 Amendment No. -34, 4*4*,4-4-7, 149

PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

f. After each-complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetra-tion and bypass leakage testing acceptance criteria of less than 0.05%

in accordance with ANSI N510-1980 while operating the system at a flow rate of 3000 cfm +/- 10%.

g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 3000 cfm +/- 10%.

4.7.2.2 The control room envelope boundary shall be demonstrated OPERABLE:

a. At a frequency in accordance with the Control Room Envelope Habitability Program by performance of control room envelope unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

LIMERICK - UNIT 2 3/4 7-8 Amendment No. 149

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2. A determination' that the change did not reduce the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:

a. Shall be documented with the following information:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose,. or setpoint calculations.

b. Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager..

c. Shall be submitted-to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 (Deleted) -. INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

6.16 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 Emergency Fresh Air Supply (CREFAS) 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:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining including configuration the and control CRE preventive boundary inmaintenance its design condition LIMERICK - UNIT 2 6-22 Amendment No. 2,4-1-,*,338,,448,149

ADMIOSISRATIVE CONTROL~S CONTROL ROOM ENVELOPE HABITABILITY PROGRAM (Continued)

c. Requirements for (M) 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, at designated 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 CREFAS, operating at the flow rate required by SR 4.7.2.1 c.1, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and.

used as part of the 24 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 Specification 4.0.2 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.

LIMERICK - UNIT 2 6-23 Amendment No.149

(5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 2 6 4 , are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, 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 the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1 , submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

(4) Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report (SER) dated May 23, 1979, and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC.SERs dated September 16, 1993, and August 24, 1994, subject to the following provision:

The Exelon Generation Company may make changes to the approved 1The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to-the Security- Plan.

Renewed License No. DPR-44 Revised by letter dated October 28, 2004 Revised by letter dated May 29, 2007 Page 3

(11) Mitigation Strategqy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (12) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-1 37, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(13) Upon implementation of Amendment No. 264 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.4.4, in accordance with TS 5.5.13.c(i),

the assessment of ORE habitability as required by Specification 5.5.13.c(ii), and the measurement of GRE pressure as required by

.Specification 5.5.13.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.4.4, in accordance with Specification 5.5.13.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from October 25, 2004, the date of the most recent successful tracer gas test, as stated in the January 21, 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.

Renewed License No. DPR-44 Revised by letter dated August 9, 2007 Page 7

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.13.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from October 25, 2004, the date of the most recent successful tracer gas test, as stated in the January 21, 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 5.5.13.d, shall be within 24 months, plus the 180 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 180 days if not performed previously.

3. This renewed license is subject to the following conditions for the protection of the environment:

A. To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station Unit No. 2 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended. Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as appropriate.

B. In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to Section 316 of the Federal Water Pollution Control Act, the Exelon Generation Company shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom. If such change would entail any modification to this license, or any Technical Specifications which are part of this license, or require NRC approval pursuant to 10 CFR 50.59 or involve an environmental impact different than analyzed in the Final Environmental Statement, the Exelon Generation Company shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safety, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for Renewed License No. DPR-44 Revised by letter dated August 9, 2007 Page 7a

MCREV System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Emergency Ventilation (MCREV) System LCO 3.7.4 Two MCREV subsystems shall be OPERABLE.

NOTE -------------------------------

The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES. 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREV subsystem A.1 Restore MCREV 7 days inoperable for reasons subsystem to OPERABLE other than Condition status.

B.

B. One or more MCREV B.1 Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.

boundary in MODE 1, 2 or 3. AND B.2 Verify mitigating 24 hours1 days 0.143 weeks 0.0329 months actions ensure CRE occupant exposures to radiological/chemical hazards will not exceed limits and mitigating actions for smoke hazards are taken as required.

AND B.3 Restore CRE boundary 90 days to OPERABLE status.

PBAPS UNIT 2 3. 7-7 Amendment No. 264

MCREV System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

D. Required Action and. ------------- NOTE-------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A -----------------------------

not met during movement of irradiated D.1 Place OPERABLE MCREV Immediately fuel assemblies in the subsystem in secondary containment, operation.

during CORE ALTERATIONS, or during OR

'OPDRVs.

D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E. Two MCREV subsystems E.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

PBAPS UNIT 2, 3.7-8 Amendment No. 264

MCREV System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREV subsystems -------------NOTE------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the

-,OPDRVs. secondary containment.

OR AND One or more MCREV subsystems inoperable F.2 Suspend CORE Immediately due to an inoperable ALTERATIONS.

CRE Boundary during movement of irradiated AND fuel assemblies in the secondary containment, F.3 Initiate action to Immediately during CORE suspend OPDRVs.

ALTERATIONS or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREV subsystem for 31 days 15 minutes.

SR 3.7.4.2 Perform required MCREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.4.3 Verify each MCREV subsystem actuates on an 24 months actual or simulated initiation signal.

. SR

-. 3 ..7-.4-.4-----. -Per-f-orm -r-equ r-ed--CRE--unf i-1tered -ai-r-inleakage testing in accordance with the In accordance with the i1 Co ntrol Ro.Qm ._EnvelQpe Habitability Program. Control Room Envelope Habitability Program.

PBAPS UNIT 2 3.7-9 Amendment No. 264

Programs and Manuals 5.5 5.5 Programs .and Manuals 5.5.12' Primary Containment Leakage Rate Testing Program (continued)

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is

9000 scc/min when tested at 2 P,

c. MSIV leakage acceptance criteria are as specified in SR 3.6.1.3.14.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 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 Main Control Room Emergency Ventilation (MCREV)

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 as applicable, 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 whole body dose or its equivalent to any part of the body for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventative maintenance.

c. Requirements of (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 Section 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

...... sp*fied in Section C.I and C.2 of Regulatory Guide 1.197, Revision 0.

(continued)

PBAPS UNIT 2 5.0-18 Amendment No.264

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Control Room Envelope Habitability Program (continued)

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the MCREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a -STAGGERED TEST BASIS.

The results shall be trended and used as part of the 24 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.

PBAPS UNIT 2 5.0-18a Amendment No. 264

(5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.268 , are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.'

(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, 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 combined set of plans 2, submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

(4) Fire Protection The Exelon Generation Company shall irnplement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in 1Licensed power level was revised by Amendment No. 250, dated November 22, 2002, and will be implemented following the 1 4 t' refueling outage currently scheduled for Fall 2003.

2The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-56 Revised-by letter-dated October-28,-2004 Revised by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Page 3

plant-specific program. Before July 2, 2014, the licensee will notify the NRC of its decision to implement the core shroud inspection and evaluation guidelines program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary descriptions of the core shroud inspection and evaluation guidelines program.

(11 ) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (12) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(13) Upon implementation of Amendment No. 268 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.4.4, in accordance with TS 5.5.13.c(i),

the assessment of CRE habitability as required by Specification 5.5.13.c(ii); and the measurement of CRE pressure as required by Specification 5.5.13.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.4.4, in accordance with Specification 5.5.13.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from October-25-,-2004,-the date-of-the-most-recent successful --

Renewed License No. DPR-56 Revised by letter dated August 9, 2007 Page 7

tracer gas test, as stated in the January 21, 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 5.5.13.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from October 25, 2004, the date of the most recent successful tracer gas test, as stated in the January 21, 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 5.5.13.d, shall be within 24 months, plus the 180 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 180 days if not performed previously.

3. This renewed license is subject to the following conditions for the protection of the environment:

A. To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station, Unit No. 3, will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended. Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as,appropriate.

B. In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to Section 316 of the Federal Water Pollution Control Act, the Exelon Generation Company shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom. If such change would entail any modification to Renewed License No. DPR-56 Revised by letter dated August 9, 2007 Page 7a

MCREV System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Emergency Ventilation (MCREV) System LCO 3.7.4 Two MCREV subsystems shall be OPERABLE.

NOTE-----------------------------

The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREV subsystem A.1 Restore MCREV 7 days inoperable for reasons- subsystem to OPERABLE other than Condition status.

B.

B. One or more MCREV B.1 Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.

boundary in MODE 1, 2 or 3. AND B.2 Verify mitigating 24 hours1 days 0.143 weeks 0.0329 months actions ensure CRE occupant exposures to radiological/chemical hazards w4ill not exceed limits and mitigating actions for smoke-hazards are taken as required.

AND B.3 Restore CRE boundary 90 days to OPERABLE status.

'PBAPS UNIT 3 3. 7-7 Amendment No.268

MCREV System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

D. Required Action and ------------- NOTE------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A -----------------------------

not met during movement of irradiated D.1 Place OPERABLE MCREV Immediately fuel assemblies in the subsystem in secondary containment, operation.

during CORE ALTERATIONS, or during OR OPDRVs.

D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary "containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E. Two MCREV subsystems E.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months inoperable in MODE 1, 2, or-3 for reasons other than Condition B.

PBAPS UNIT 3 3.7-8 Amendment No.268

MCREV System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREV subsystems ------------- NOTE------------ I inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the OPDRVs. secondary containment.

OR AND One or more MCREV subsystems inoperable F.2 Suspend CORE Immediately due to an inoperable ALTERATIONS.

CRE boundary during movement of irradiated AND fuel assemblies in the secondary containment, F.3 Initiate action to Immediately during CORE ALTERATIONS suspend OPDRVs.

or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREV subsystem for 31 days 15 minutes.

SR 3.7.4.2 Perform required MCREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.4.3 Verify each MCREV subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.7.4.4 Perform required CRE unfiltered air In accordance

...... .... ___--- . ....in-l-ea-k-age--t-esti-ng-in-accord-an-ce--wi-th--t-he - -... with--t-he-...

Control Room Envelope Habitability Program. Control Room

... E-nv-e-lope Habitability Program.

PBAPS UNIT 3 3.7--9 Amendment No. 268

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is 5 9000 scc/min when tested at Ž Pa.

c. MSIV leakage acceptance criteria are as *specified in SR 3.6.1.3.14.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 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 Main Control Room Emergency Ventilation (MCREV)

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 as applicable, 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 whole body dose or its equivalent to any part of the body for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventative ma-intenance.

c. Requirements of (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 Section 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 speci-fjtd--in-.-Secti-on_.[,l-a-n d_*.-2_* _-e~gL .t-o_ Gutd 1 1 . .

Revision 0.

(continued)

PBAPS UNIT 3 5.0-18 Amendment No. 268

Programs andManuals 5.5 5.5 Programs and Manuals 5.5.13 Control Room Envelope Habitability Program (continued)

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the MCREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months ion a STAGGERED TEST BASIS.

The results shall be trended and used as part of the 24 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.

PBAPS UNIT 3 5 .0- 18a Amendment.No.268

v t e Letter Sequence Acceptance Review
TAC:MD5270, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5271, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5272, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5273, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5274, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5277, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5278, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5279, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5280, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5282, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open) TAC:MD5283, Control Room Habitability, Ventilation System Envelope Allowed Outage Time (Open)
Initiation Request Acceptance, Acceptance Administration Questions Answers Results Approval... Other: ML072550393, ML073390056
MONTHYEAR2007-12-07 [Table View]

ML073100389

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