Byron, Units 1 and 2, Braidwood, Units 1 and 2, Dresden ... · analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act

-3-

(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 nuclearmaterial without restriction to chemical or physical form, for sampleanalysis or instrument calibration or associated with radioactiveapparatus or components; and

(5) Pursuant to the Act and 10 CER Parts 30, 40 and 70, to possess, but notseparate, such byproduct and special nuclear materials as may beproduced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specifiedin the Commission's regulation set forth in 10 CFR Chapter I and is subject to allapplicable provisions of the Act and to the rules, regulations, and orders of theCommission 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 powerlevels not in excess of 3586.6 megawatts thermal (100 percent power) inaccordance with the conditions specified herein.

(2) Technical Specifications

The Technical Specifications contained in Appendix A as revised throughAmendment No. 1 52 And the Environmental Protection Plan contained inAppendix B, both of which .are attached hereto, are hereby incorporatedinto this license. The licensee shall operate the facility in accordance withthe 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 theapproved fire protection program as described in the licensee's FireProtection Report, and as approved in the SER dated February 1987through Supplement No. 8, subject to the following provision:

. "The licensee may make changes to the approved fire protectionprogram without prior approval of the Commission only if thosechanges would not adversely affect the ability to achieve and

* . maintain safe shutdown in the event of a fire.

Amendment No. 152

I't

-4-

(6) Additional Conditions

The Additional Conditions contained in Appendix C, as revised throughAmendment No. 1152, are hereby incorporated into this license. Thelicensee shall operate the facility in accordance with the AdditionalConditions.

(7) Exelon Generation Company, LLC shall provide the Director of the Officeof Nuclear Reactor Regulation, a copy of any application, at the time it isfiled, to transfer (excluding grants of security interests or liens) fromExelon Generation Company, LLC to its direct or indirect parent, or to anyother affiliated company, facilities for the production, transmission, ordistribution of electric energy having a depreciated book value exceedingten percent (10%) of Exelon Generation Company, LLC's consolidatednet utility plant, as recorded on Exelon Generation Company, LLC'sbooks of account.

(8) Exelon Generation Company, LLC shall have decommissioning trustfunds for Byron, Unit 2, in the following minimum amount, when Byron,Unit 2, is transferred to Exelon Generation Company, LLC:

Byron Unit 2 $156,560,489

(9) The decommissioning trust agreement for Byron, Unit 2, at the time thetransfer of the unit to Exelon Generation Company, LLC is effected andthereafter, is subject to the following:

(a) The decommissioning trust agreement must be in a formacceptable to the NRC.

(b) With respect to the decommissioning trust fund, investments inthe securities or other obligations of Exelon Corporation oraffiliates thereof, or their successors or assigns are prohibited.Except for'investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning oneor more nuclear power plants are prohibited.

J.,

AMENDMENT NO. 152

Organization5.2

5.0 ADMINISTRATIVE CONTROLS

5.2 Organization

* 21 Onsite and Offsite OrQanizations

Onsite and offsite organizations shall be established for facilityoperation and corporate management, respectively. The onsite andoffsite organizations shall include the positions for activitiesaffecting safety of the nuclear power -plant.

a. Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organization,positions. These relationships shall be documented andupdated, as appropriate, in organization charts,' functionaldescriptions of departmental responsibilities andrelationships, and job descriptions for key personnelpositions, or in equivalent forms of documentation. Theserequirements, including the generic titles of thosepersonnel fulfilling the responsibilities of the positionsdelineated in these Technical Specifications, shal bedocumented in the Quality Assurance Program;-.

b. The station manager shall be responsible for overall safeoperation of the plant and shall have control over thoseonsite activities necessary• for. safe operation andmaintenance of the plant;' ,

c. The Chief Nuclear Officer shall be responsible for overallplant nuclear safety and shall, take any measures needed. toensure acceptable performance of the staff in operating,maintaining, and providing technical support to the plant toensure nuclear safety; and ' -

d. The individuals who train the operating staff, or' performhealth physics or quality assurance. functions, may report tothe appropriate onsite manager; however, these individualsshall have sufficient organizational freedomt6 ensure theirindependence from operating pressures.,.

I

BYRON - UNITS 1 & 2 5.2 - .. A~1 mendment

~4,152

-4-

(4) Initial Startup Test Program

Any changes to the Initial Test Program described in Section 14 of theFSAR made in accordance with the provisions of 10 CFR 50.59 shall bereported in accordance with 50.59(b) within one month of such change.

(5) Regulatory Guide 1.97, Revision 2 Compliance

The licensee shall submit the final report and a schedule forimplementation within six months of NRC approval of the DCRDR.

(6) Deleted.


The Additional Conditions contained in Appendix C, as revised throughAmendment No. 147 are hereby incorporated into this license. Thelicensee shall operate the facility in accordance with the AdditionalConditions.

(8) Exelon Generation Company shall provide to theDirector of the Office ofNuclear Reactor Regulation a copy of any application, at the time it isfiled, to transfer (excluding grants of security interests or liens) fromExelon Generation Company to its direct or indirect parent, or to anyother affiliated company, facilities for the production, transmission, ordistribution of electric energy having a depreciated book value exceedingten percent (10%) of Exelon Generation Company's consolidated netutility plant, as recorded on Exelon Generation Company's books ofaccount.

(9) Exelon Generation Company shall have decommissioning trust funds forBraidwood, Unit 1, in the following minimum amount, when Braidwood,Unit 1, is transferred to Exelon Generation Company:

I

Braidwood Unit 1 $154,273,345

(10) The decommissioning trust agreement for Braidwood, Unit 1, at the timethe transfer of the unit to Exelon Generation Company is effected andthereafter, is subject to the following:


AMENDMENT NO.147

-4-

(4) Initial Startup Test Program

Any changes to the Initial Test Program described in Section 14 of theFSAR made in accordance with the provisions of 10 CFR 50.59 shall bereported in accordance with 50.59(b) within one month of such change.

(5) Deleted.


The Additional Conditions contained in Appendix C, as revised throughAmendment No. 147, are hereby incorporated into this license. Thelicensee shall operate the facility in accordance with the AdditionalConditions.

(7) Exelon Generation Company, LLC, shall provide the Director of the Officeof Nuclear Reactor Regulation, a copy of any application, at the time it is.filed, to transfer (excluding grants of security interests or liens) fromExelon Generation Company, LLC to its direct or indirect parent, or to anyother affiliated company, facilities for the production, transmission, ordistribution of electric energy having a depreciated book value exceedingten percent (10%) of Exelon Generation Company, LLC's consolidatednet utility plant, as recorded on Exelon Generation Company, LLC'sbooks of account.

(8) Exelon Generation Company, LLC, shall have decommissioning trustfunds for Braidwood, Unit 2, in the following minimum amount, whenBraidwood, Unit 2, is transferred to Exelon Generation Company, LLC:

Braidwood Unit 2 $154,448,967

(9) The decommissioning trust agreement for Braidwood, Unit 2, at the timethe transfer of the unit to Exelon Generation Company, LLC is effectedand thereafter, is subject to the following:


(b) With respect to the decommissioning trust fund, investments inthe securities or other obligations of Exelon Corporation oraffiliates thereof, or their successors or assigns are prohibited.Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning oneor more nuclear power plants are prohibited.

AMENDMENT NO. 147

Organization5.2

5X 0-ADMINISTRATIVE-CONTROLS

5.2 Organization"

5.2.1 Onsite and Offsite Organizations

Onsite and offsite organizations shall be established for facilityoperation and corporate management, respectively. The onsite andoffsite, organizations shall include the-positions for activitiesaffecting safety of the nuclear power plant.

Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organizationpositions. These relationships shall be documented andupdated, as appropriate, in organization charts, functionaldescriptions-of departmental responsibilities andela a ,ionships, and job descri ptions for key personnel

positions, or in equivalent forms of documentation. Theserequirements, including the generic titles of thosepersonnel fulfilling the responsibilities of the positionsdelineated in these Technical Specifications, shall bedocumented in the Quality Assurance Program;

b. The station manager shall be responsible for overall safeoperationof the plant and shall have control over thoseonsite activities necessary for safe operation andmaintenanceof the plant;

C. The Chief Nuclear Officer shall be responsible for overallplant nuclear safety and shall take any measures needed toensure acceptable performance of the staff in operating,maintaining, and providing technical support to the plant toensure nuclear safety; and

d'. * The individuals who train the operating staff, or performhealth physics or quality assurance functions, may report totheappropriate onsite manager; however, these individuals

. shall have sufficient organizational freedom to ensure theirindependence from operating pressures.

BRAIWOOD UN ITS 1. & 2. 5.2 - 1 Amendment 147

-3-

(2) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Part70, to receive, possess and use at any time special nuclear materials asreactor fuel, in accordance with the limitations for storage and amountsrequired for reactor operation, as described in the Updated Final SafetyAnalysis Report, as supplemented and amended;

(3) Exelon Generation Company, LLC,. pursuant to the Act and 10 CFR Parts30, 40 and 70, to receive, possess and use at any time any byproduct, ,source -and special-nuclear material- as sealed neutron-sources for -reactorstartup, sealed sources for reactor instrumentation and radiationmonitoring equipment calibration, and as fission detectors in amounts asrequired;

(4) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts30, 40 and 70, to receive, possess and use in amounts as required anybyproduct, source or special nuclear material without restriction tochemical or physical form, for sample analysis or instrument calibration orassociated with radioactive apparatus or components; and

(5) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts30, 40 and 70, to possess, but not separate, such byproduct specialnuclear materials as may be produced by the Operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the.conditions specified in the Commission's regulations set forth in 10 CFRChapter I; 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 issubject to the additional conditions specified or incorporated below:


The licensee is authorized to operate the facility at steady state reactorcore power levels not in excess of 2957 megawatts thermal (100 percentrated power) in accordance with the conditions specified herein.


The Technical Specifications contained in Appendix' A, as revised throughAmendment No. 225 are hereby incorporated intothis renewed *operating license. The licensee shall operate the facility in accordancewith the Technical Specifications. , •

(3) Operation in the coastdown mode is permitted to04% power.

Renewed -License No. DPR-1 9

Amendment No. 2"2

' " - " 'C ' • " :... : I

-4-

f. Surveillance Requirement 4.9.A. 10 - Diesel Storage Tank Cleaning(Unit 3 and Unit 2/3 only)

Each of the above Surveillance Requirements shall be successfullydemonstrated prior to entering into MODE 2 on the first plant star:tup followingthe fourteenth refueling outage (D3R14).

3. This renewed operating license shall be deemed to contain and is subject to theconditions specified in the following Commission-re-g-lations- I0 CFR Part20, Section .30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of10 CFR Part 50, and Section 70.32 of 10.CFR Part 70; is subject to all applicableprovisions of the Act and to the rules, regulations, and orders of the Commission now orhereafter in effect; and is subject to the additional conditions specified or incorporatedbelow:

A. Maximum Power Level

The licensee is authorized to operate the facility at steady state power levels notin excess of 2957 megawatts (thermal), except that the licensee shall notoperate the facility at power levels in excess of five (5) megawatts (thermal), untilsatisfactory completion of modifications and final testing of the station outputtransformer, the auto-depressurization interlock, and the feedwater system, asdescribed in the licensee's telegrams; dated February 26, 1971, have beenverified in writing by the Commission.

B. Technical Specifications

The Technical Specifications contained in Appendix A, as revised throughAmendment No. 2t7 are hereby incorporated into this renewed operatinglicense. The licensee shall operate the facility in accordance with the TechnicalSpecifications.

C. Reports

The licensee shall.make certain reports in accordance with the requirements ofthe Technical Specifications.

D. Records

The licensee shall keep facility operating records in accordance with therequirements of the Technical Specifications.

E. Restrictions

Operation in the coastdown mode is permitted to 40% power.

Renewed License No. DPR-25Amendment NO., 217 :,

• , , " % . :: ,,;- '. ., . ,

Organization5.2


5.2- Organization


Onsite and offsite organizations shall be established for unitoperation and corporate management, respectivel-. T-he onsi-te -andoffsite organizations shall include the positions for activitiesaffecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organizationpositions. These relationships shall be documented andupdated, as appropriate, in organiz*ation charts, functionaldescriptions of departmental responsibilities andrelationships, and job descriptions for key personnelpositions, or in equivalent forms.of documentation. Theserequirements, including the generic titles of thosepersonnel fulfilling the responsibilities of the positionsdelineated in these Technical Specifications, shall bedocumented in the Quality Assurance Manual.

b. The station manager shall be responsible for overall safeoperation of the plant and shall have control over thoseonsite activities necessary for safe operation andmaintenance of the plant.

c. A corporate officer shall have corporate responsibility foroverall plant nuclear safety and shall take any measuresneeded to ensure acceptable performance of the staff inoperating, maintaining, and providing technical support tothe plant to ensure nuclear safety.

d. The individuals who train the operating staff, or performradiation protection or quality assurance functions, mayreport to the appropriate onsite manager; however, theseindividuals shall have sufficient organizational freedom toensure their independence from operating pressures.

5.2.2 Unit Staff

The unit staff organization shall include the following:

(continued)

Dresden 2 and 3 5.2-1 Amendment No. 225/217

-3-

(4) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts30, 40, and 70, to receive, possess, and use in amounts as required anybyproduct, source or special nuclear material without restriction tochemical or physical form, for sample analysis or instrument calibration orassociated with radioactive apparatus or components; and

(5) Exelon Generation Company, LLC, pursuant to the Act and 10 CFRParts 30, 40, and 70, to possess, but not separate, such byproduct andspecial nuclear materials as may be produced by the operationcof LaSalleCounty Station, Units 1 and 2.

C. This license shall be deemed to contain and is subject to the conditions specifiedin the Commission's regulations set forth in 10 CFR Chapter I and is subject toall applicable provisions of the Act and to the rules, regulations, and orders of theCommission now or hereafter in effect; and is subject to the additional conditionsspecified or incorporated below:


The licensee is authorized to operate the facility at reactor core powerlevels 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 throughAmendment No. 187 and the Environmental Protection Plan contained inAppendix B, are hereby incorporated in the license. The licensee shalloperate the facility in accordance with the Technical Specifications andthe Environmental Protection Plan.

(3) Conduct of Work Activities During Fuel Load and Initial Startup

The licensee shall review by committee all Unit 1 PreoperationalTesting and System Demonstration activities performed concurrentlywith Unit 1 initial fuel loading or with the Unit 1 Startup Test Programto assure that the activity will not affect the safe performance of theUnit 1 fuel loading or the portion of the Unit 1 Startup Program beingperformed. The review shall address, as a minimum, systeminteraction, span of control, staffing, security and health physics,with respect to performance of the activity concurrently with theUnit 1 fuel loading or the portion of the Unit 1 Startup Program beingperformed. The committee for the review shall be composed of atleast three members, knowledgeable in the above areas, and who meetthe qualifications for professional-technical personnel specified by

Amendment No. 187

-3-

(5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 possess, but notseparate, such byproduct and special nuclear materials as may beproduced 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 specifiedin the Commission's regulations set forth in 10 CFR Chapter I and is subject toall applicable provisions of the Act and to the rules, regulations, and orders of theCommission now or hereafter in effect; and is subject to the additional conditionsspecified or incorporated below:


The licensee is authorized to operate the facility at reactor core powerlevels not in excess of full power (3489 megawatts thermal). Items inAttachment 1 shall be completed as specified. Attachment 1 is herebyincorporated into this license.,

(2) Technical Specifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A, as revised throughAmendment No. 174 and the Environmental Protection Plan contained inAppendix B, are hereby incorporated in the license. The licensee shalloperate the facility in accordance with the Technical Specifications andthe Environmental Protection Plan.

(3) Conduct of Work Activities Durinq Fuel Load and Initial Startup

The licensee shall review by committee all Unit 2 Preoperational Testingand System Demonstration activities performed concurrently with Unit 2initial fuel loading or with the Unit 2 Startup Test Program to assure thatthe activity will not affect the safe performance of the Unit 2 fuel loadingor the portion of the Unit 2 Startup Program being performed. The reviewshall address, as a minimum, system interaction, span of control, staffing,security and health physics, with respect to performance of the activityconcurrently with the Unit 2 fuel loading or the portion of the Unit 2Startup Program being performed. The committee for the review shallbe composed of at least three members, knowledgeable in the aboveareas, and who meet the qualifications for professional-technicalpersonnel specified by section 4.4 of ANSI N18.7-1971. At least one ofthese three shall be a senior member of the Assistant Superintendent ofOperation's staff.

Amendment No. 174

Organization5.2


5.2 Organization

5.2.1 Onsite and Offsite Oraanizations

K

Onsite and offsite organizations shall be established for unitoperation-and corporate--management,; respectivel-y.- The -onsite andoffsite. organizations shall include the positions for activitiesaffecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organizationpositions. These relationships shall be documented andupdated, as appropriate, in organization charts, functionaldescriptions of departmental responsibilities andrelationships, and job descriptions for key personnelpositions, or in equivalent forms of documentation. Theserequirements, including the generic titles of thosepersonnel fulfilling the responsibilities of the positionsdelineated in these Technical Specifications, shall bedocumented in the Quality Assurance Manual.

b. The station manager shall be responsible for overall safeoperation of the plant and shall have control over thoseonsite activities necessary for safe operation andmaintenance of the plant.

c. A corporate officer shall have corporate responsibility foroverall plant nuclear safety and shall take any measuresneeded to ensure acceptable performance of the staff inoperating, maintaining, and providing technical support tothe plant to'ensure nuclear safety.

d. The individuals who train the operating staff, or performradiation protection or quality assurance functions, mayreport to the appropriate onsite manager; however, theseindividuals shall have sufficient organizational freedom toensure- their independence from operating pressures.

Unit Staff

.. The unit. staff organization shall include the following:

5.2.2

a. At•otal of three'required in all c(

La SaIIe. l and '2'

• ,;} ; "

non-licensed operators for the two units is

)nditions. At least one of the required

(continued)

5.2-1 Amendment No. 187/174

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

C. This renewed license shall be deemed to contain and is subject to the conditionsspecified in the following Commission regulations in 10 CFR Chapter 1: Part 20,Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, andSection 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 issubject to the additional conditions specified below:


Exelon Generation Company is authorized to operate the Peach BottomAtomic Power Station, Unit 2, at steady state reactor core power levelsnot in excess of 3514 megawatts thermal.


The Technical Specifications cor-fained In Appendices A and B, asrevised through Amendment No, 265. are hereby incorporated in thelicense. Exelon Generation Comrny shall operate the facility Inaccordance with the Technical Specifications.

(3) Physical Protection

Exelon Generation Company shall fully implement and maintain in effectall provisions of the Commission-approved physical security, training andqualification, and safeguards contingency plans including amendmentsmade pursuant to provisions of the Miscellaneous Amendments andSearch Requirements revisions to 10 CFR 73.55 (51 FR 27817 and27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). Thecombined set of plans1, which contain Safeguards Information protectedunder 10 CFR 73.21, is entitled: "Peach Bottom Atomic Power StationSecurity Plan, Training and Qualification Plan, Safeguards ContingencyPlan, and Independent Spent Fuel Storage Installation Security Program,Revision 0," submitted by letter dated October 21, 2004.

(4) Fire Protection

The Exelon Generation Company shall implement and maintain in effectall provisions of the approved fire protection program as described in theUpdated Final Safety Analysis Report for the facility, and as approved inthe NRC Safety Evaluation Report (SER) dated May 23, 1979, andSupplements dated August 14, September 15, October 10 and November24, 1980, and in the NRC SERs dated September 16, 1993, and August24, 1994, subject to the following provision:

The Exelon Generation Company may-make changes to the approved

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the

Security Plan:Renewed License No. DPR-44

Pageised by letter datedi Oeteber 2, 2004

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

C. This renewed license shall be deemed to contain and is subject to the conditionsspecified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32of Part 70; all applicable provisions of the Act and the rules, regulations, and orders ofthe Commission now or hereafter in effect; and is subject to the additional conditionsspecified below:


Exelon Generation Company is authorized to operate the Peach BottomAtomic Power Station, Unit No. 3, at steady state reactor core powerlevels not in excess of 3514 megawatts thermal.


The Technical Specifications contained in Appendices A and B, asrevised through Amendment No 269 are hereby incorporated in thelicense. Exelon Generation Corm'pany shal! operate the facility inaccordance with the Technical Specifications.'

(3) Physical Protection

Exelon Generation Company shall fully implement and maintain in effectall provisions of the Commission-approved physical security, training andqualification, and safeguards contingency plans including amendmentsmade pursuant to provisions of the Miscellaneous Amendments andSearch Requirements revisions to 10 CFR 73.55 (51 FR 27817 and27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). Thecombined set of plansw, which contain Safeguards Information protectedunder 10 CFR 73.21, is entitled: "Peach Bottom Atomic Power StationSecurity Plan, Training and Qualification Plan, Safeguards ContingencyPlan, and Independent Spent Fuel Storage Installation Security Program,Revision 0," submitted by letter dated October 21, 2004.

(4) Fire Protection

The Exelon Generation Company shall implement and maintain in effectall provisions of the approved fire protection program as described in theUpdated Final Safety Analysis Report for the facility, and as approved in

,Licensed power level was revised by Amendment No. 250, dated November 22, 2002,and will be implemented following the 141h refueling outage currently scheduled for Fall 2003.

2The training and Qualification Plan and Safeguards Contingency Plan and Appendices

to the Security Plan.

Page 3

Renewed License No. DPR-56Revise by lttte. datedJ f. tobL 20, 2004

Revise by let.dated Novmbe 5 , 2004

Organization5.2


5.2 Organization


Onsite and offsite organizations shall be established for unitoperation and corporate management, respectively. The onsite andoffsite organizations shall include the positions for activitiesaffecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organizationpositions. .These relationships shall be documented andupdated, as appropriate, in organization ch.arts, functionaldescriptions of departmental responsibili-ties andrelationships, and job descriptions for key personnelpositions, or in equivalent forms of documentation. Theserequirements, including the generic titles of those personnelfulfilling the responsibilities of the positions delineatedin these Technical Specifications, shall be documented in theQATR; .

b. The plant manager shall be responsible for overall safeoperation of the plant and shall have control over thoseonsite activities necessary for safe operation andmaintenance of the plant;

c. The specified corporate officer shall have corporateresponsibility for overall plant nuclear ýafety and shalltake any measures needed to ensure acceptable performance ofthe staff. in operating, maintaining, and providing technicalsupport to the plantto ensure nuclear safety; and

d. The individuals who train the operating staff, carry outhealth physics, or perform quality assurance functions mayreport to the appropriate onsite manager; however, theseindividuals shall have sufficient organizational freedom toensure their independence from operating pressures.

5.2.2 Unit Staff

The unit staff organization shall also include the following:

(continued)

PBAPS UNIT 2 .O-2ý Amendment No.265

Organization5.2

5.0 ADMINISTRATIVECONTROLS

5.2 Organization


Onsite and offsite organizations shall be established for unitoperation and corporate management, respectively. The onsite andoff si te organi zatibns- sha-l" fi-ncl-ude- the p'osi t-fon s f"or -act'tvi tiesaffecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organizationpositions. These relationships shall be documented andupdated, as appropriate, in organization charts, functionaldescriptions of departmental responsibilities andrelationships, and job descriptions for key personnelpositions,or in equivalent forms ofdocumentation. Theserequirements, including the generic titles of those personnelfulfilling the responsibilities of the positions delineatedin these Technical .Spelcifications, shall be documented in theQATR;

b. The plant manager shall be responsible *for overall safeoperation of the plant and shall have control over thoseonsite activities necessary for safe operation andmaintenance of the plant;

c. The specified corporate officer shall have corporateresponsibi-lity for overall plant nuclear safety and shalltake any measures needed.to ensure acceptable performance ofthe staff in operating, maintaining, and providing technicalsupport to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry outhealth physics, or perform quality assurance functions mayreport to the appropriate onsite manager; however, theseindividuals shall have sufficient organizational freedom toensure their independence from operating pressures.

5.2.2 Unit Staff

The unit staff organization shall also include the following:

(continued)

. ... • . .. - Am n m n .No.

PBAPS UNIT 3.$.O. . Amenment No.269

" IL ! ... ii i . ..

-4-


The Technical Specifications contained in Appendix A, as revised throughAmendment No. 236. are hereby incorporated into this renewed operatinglicense. The licensee shall operate the facility in accordance with the TechnicalSpecifications.

C. The licensee shall maintain the commitments made in response to theMarch. 14, 1983, NUREG-0737 Order, subject to the-following-provision:

The licensee may make changes to commitments made in response to theMarch 14, 1983, NUREG-0737 Oder without prior approval of the Commissionas long as the change would be permitted. without NRC approval, pursuant to therequirements of 10 CFR 50.59. Consistent with this regulation, if the changeresults in an Unreviewed Safety Question, a license amendment shall besubmitted to the NRC staff for review and approval prior to implementation of thechange.,

D. Equalizer Valve Restriction

Three of the four valves in the equalizer piping between the recirculationloops shall be closed at all times during reactor operation with one bypass valveopen to allow for thermal expansion of water.

E; The licensee shall fully implement and maintain in effect all, provisions of theCommission-approved physical security, training and qualification, andsafeguards contingency plans including amendments made pursuant toprovisions of the Miscellaneous Amendments and Search Requirementsrevisions to. 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans', which containSafeguards Information protected under 10 CFR 73.21, is entitled: "Quad CitiesNuclear Power Station Security Plan, Training and Qualification Plan, andSafeguards Contingency Plan, Revision 0," submitted by letter datedOctober 21, 2004.

F. The licensee shall implement and maintain in effect all provisions of theapproved fire protection program as described in the Updated Final SafetyAnalysis Report for the facility and as approved in the Safety Evaluation Reportsdated July 27, 1979 with supplements dated November 5, 1980, and

The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to theSecurity Plan.

Renewed License No. DPR-2Amendment No. 236

-S.

SI -I : , , -.

9

-4-


The Technical Specifications contained in Appendix A, as revised throughAmendment No. 231 are hereby incorporated into this renewedoperating license. i ne licensee shall operate the facility in accordancewith the Technical Specifications.

C. The license shall maintain the commitments made in response to the-March 14, 1 983,N U REG;O737 Order, subject-to-the following-provision:

The licensee may make changes to commitments made inresponse to the March 14, 1983, NUREG-0737 Order withoutprior approval of the Commission as long as the change would bepermitted without NRC approval, pursuant to the requirements of10 CFR 50.59. Consistent with this regulation, if the changeresults. in ari, Unreviewed Safety. Question, a.license amendmentshall be submitted to the NRC staff for rev'iew and approval priorto implementation of the change..

D. Equalizer Valve Restriction

Three of the four valves in the equalizer piping between the recirculationloops shall be closed at all times during reactor operation with onebypass valve open to allow for thermal expansion of water.

E. The licensee shall fully implement and maintain in effect all provisions ofthe Commission-approved physical security, training and qualification,and safeguards contingency plans including amendments made pursuantto provisions of the Miscellaneous Amendments and SearchRequirements, revisions to 10 CFR.73.55 (51 FR 27817 and 27822), andthe authority of 10 CFR 50.90 and 10CFR 50.54(p). The combined setof plans', which contain Safeguards information protected under1.0 CFR 73.2 1jis entitled: "Quad ,ities Nuclear Power Station SecurityPlan, Training and Qualification Plan, and Safeguards Contingency Plan,Revision 0," submitted by ietter dated October 21, 2004.

F. The licensee shall implement and maintain in effect all provisions of theapproved fire protection program as described in the Updated FinalSafety•Analysis Report for the facility and as approved in the SafetyEvaluation Reports dated July 27, 1979 with supplements dated

The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to theSecurity Plan.

Renewed License No. DPR-30Amendment No. 231

r .,. ,.

N . • .. , ~ . • ., , . ' • (.. • .•• .. . , ,.

Organization5.2


5.2 Organization

5.2..1 Onsite and Offsite Organizations

Onsite and offsite organizations shall be established for unitoperation and-corporat-e--management-,--respectively.- --The onsite and-offsite organizations shall include the positions for activitiesaffecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shallbe defined and established throughout highest managementlevels, intermediate levels, and all operating organizationpositions. These relationships shallbe documented andupdated, as appropriate, in organization charts., functionaldescriptions of departmental responsibilities and.relationships, and job descriptio.ns for key personnelpositions, or in equivalent forms of documentation. Theserequirements, including the generic titles of thosepersonnel fulfilling the responsibilities of the positionsdelineated in these Technical Specifications, shall bedocumented in the. Quality Assurance Manual.

b. The station manager shall be responsibie for-overall safeoperation of the plant and shall have control .over thoseonsite activities necessary for safe operatibn anndmaintenance of the plant. - -

c. A corporate officer'shall have corporate respoinsibi~ity foroverall plant nuclear safety and-shall take'any measuresneeded to ensure acceptable performance of the staff inoperating, maintaining, and providing technical support tothe plant to ensure nuclear safety. -

d. The individuals who train the Operating staff, or..performradiation protection or quality'assuranrce functfons, may.report to the appropriate onsite manager; however, theseindividuals shall have sufficient organizational freedom toensure their independence from operating-pressures.

5.2.2 Unit Staff

The unit staff organization shall includethe :following:4':

(•continued)

Quad Cities 1 and 2 5.2-1 Amendment., No 236/231

Documents

Byron, Units 1 and 2, Braidwood, Units 1 and 2, Dresden ... · analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act