ML082130136
| ML082130136 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Clinton, Quad Cities, LaSalle |
| Issue date: | 07/25/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | |
| Gratton C, NRR/DORL/LPL3-2, 415-1055 | |
| Shared Package | |
| ML080860679 | List: |
| References | |
| TAC MD6364, TAC MD6365, TAC MD6366, TAC MD6367, TAC MD6368, TAC MD6369, TAC MD6370, TAC MD6371, TAC MD6372, TAC MD6373, TAC MD6374, TAC MD6375, TAC MD6376, TAC MD6377, TAC MD6378 | |
| Download: ML082130136 (26) | |
Text
(3) Exelon Generation Company,.pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any timeany 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 not in excess of 3586.6 megawatts thermal (100 percent rated power) in-accordance with'the-conditions-specifiedherein and other items identified in Attachment 1 to this license. The iteins ideiitified 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.152, and theEnvironmental 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, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 152
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 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.
-Attachthentt 1rish*- reby incorporated .into-this-liý-ens-e-.-.----- 7 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No 152 and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 152
Facility Staff Qual i fi cations 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the .facility staff shall, meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
- 1) either the senior health physics supervisor or lead health physicist, shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and
- 2) the education and experience eligi bi 1i ty requirements for operator license applicants, (described in Exelon letter RS 078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
BRAIEAKOD - UNITS 1 & 2 .5.3-1 Amendment 15 2
(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 tochemical 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. 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 not in excess of 3586.6 megawatts thermal (100 percent power) in accordance with the. conditions specified herein.
(2) Technical Specifications The Technical Snp.r.ifications contained in Appendix A as revised through Amendment No.4_156, 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. 156
.(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 instrumentationand 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 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) 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 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 1113), as revised through Amendment No..156 , and the Environmental Protection Plan contained in Appendix B, both of which are 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. 156
Facility Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
- 1) either the senior health'physics supervisor or lead health physicist, shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and
- 2) the education and experience eli gi bi l i ty requirements for operator license applicants, (described in Exelon letter RS 078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
Amendment 156
& 22 5.3-1 BYRON - UNITS 11 &
- 5.3-1 Amendment 156
(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. 180., 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. 180
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978, with the following exception:
the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, .2007), and changes thereto, shall be approved by the NRC and described in an applicable station training, procedure.
CLINTON -5.0-5 Amendment No. 180
(2) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear materials as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented .and amended; (3) Exelon Generation Company, LLC, 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, 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 special nuclear 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 CFR Chapter I; is subject to all applicable provisions of the Act and to the rules,
...---regulations, and orders -ofthe Commission now or hereafter'ineffect, and is subject-to-th-additioial--onditi*hn speifiT-orcorpS~atedb~l-. .
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2957 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 228 , are hereby incorporated into this renewed operating license. -I ne licensee shall operate the facility in accordance with the Technical Specifications.
(3) Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-19 Amendment No- 228
- 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 successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fourteenth refueling outage (D3R14).
- 3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections. 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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:
A. Maximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 2957 megawatts (thermal), except that the licensee shall not operate the facility at power levels in excess of five (5) megawatts (thermal), until satisfactory completion of modifications and final testing of the station output transformer, the auto-depressurization interlock, and the feedwater system, as described in the licensee's telegrams; dated February 26, 1971, have been verified in writing by the Commission.
B. Technical Specifications
- "'The._TechnicalSpecifications-contained-in-Appendlix-ATas-revised through - - ......
Amendment No. 220, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. Reports The-licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D. Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E. Restrictions Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-25 Amendment No. 220
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-197.1, with the following exceptions:
- 1) the radiation protection manager shall meet or exceed the qualifications for "Radiation Protection Manager" in.Regulatory Gu.ide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in Exelon letter RS-07-078, dated July 19., 2007), and changes thereto, shall be approved by the NRC and described in an applicable station-training procedure..
Dresden 2 and 3 5.3-1 Amendment No 228/ 220
(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 spiecial nuclear materialsT 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 additionalconditions 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 thrc " Inh Amendment No. 189 and the Environmental Protection Plan containe n Appendix B, are hereby incorporated in the license. The licensee sha dll ld operate the facility in accordance with the Technical Specifications an the Environmental Protection Plan.
(3) Conduct of Work Activities During 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. 189
(5)ý 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. 176. 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. 176
.. I " . .. .
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS.
5.3 Unit Staff Qualifications 5.3.1 Each memberof the unit staff shall meet or. exceed the minimum qualifications of ANSI N18.1-1971, with. the following exceptions:
1). the radiation protection manager shall meet the requirements of "radiation protection manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in Exelon letterRS-07-078, dated July 19., 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure. Also, the ANSI N18.1-1971 qualification requirements for "radiation protection technician" may. be met by either of the following alternatives:
a .. Individuals who have completed the radiation protection technician training program and have accrued one year of working experience in the specialty; or
- b. Individuals who have completed the radiation protection technician training program,.but have -not yet accrued one year of working experience in the specialty, who are
-supervised by on-shift radiation protection supervision who meet the requirements of ANSI N18.1-1971, Section 4.3.2 or Section 4.4.4.
LaSalle 1 and 2 5.3-1 Amendment No.189 / 176
(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, or special nuclear materials 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 materials 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, source, or 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 1 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 steady-state power levels not in excess of 1930 megawatts (thermal) (100 percent rated power) in accordance with the conditions specified herein.
(2) . Technical SpDecifications The Technical Specifications contained .in Appendices A and B, as revised through Amendment No. 265, are hereby incorporated in the license. AmerGen Energy Company, LLC small operate the facility in accordance with the Technical Specifications.
(3) Fire Protection AmerGen Energy Company, LLC 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 Safety Evaluation Report dated March 3, 1978, and supplements thereto, subject to the following provision:
- Implemented AMENDMENT NO. 265
- c. A break of at least eight hours.should be allowed between work period, including shift turnover time.
- d. In a, b, and c above, the time.required to complete shift turnover is
- to be counted as breaktime and is not to be counted as work time.
- e. Except during extended shutdown periods,the use of overtime,
- . should be considered on an individual basis and not for the entire
. staff on a shift.
Any deviation from the above guidelines shall be authorized by the Department Managers; or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
- j. The Senior Manager - Operations or an Operations Manager, and the Shift Manager require Senior Reactor Operators licenses.. The licensed Nuclear Plant Operators require a Reactor Operators license.
6.2.2.3 individuals who train the operating staff and those who carry out the health physics and quality assurance function shall have sufficient organizational freedom to be independent of operational pressures, however, they may report to the appropriate.
manager on site.
6.3 Facility Staff Qualifications 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSi/ANS 3.1 of 1978 for-comparable positions unless otherwise noted in the Technical Specifications, with the following exceptions: 1.) the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure, and 2) technicians and maintenance personnel who do not meet ANSI/ANS 3.1 of 1978, Section 4.5, are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet or exceed the, qualifications, of Regulatory Guide 1.8 (Rev. 1-R, 9/75). Each other member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971 shall meet or exceed the minimum qualifications specified therein, or in the case of radiation protection technicians, they shall have at least one year's continuous experience in applied radiation protection work in a nuclear facility dealing with radiological problems similar to thoseencountered in nuclear power, stations and shall have been certified by the management position responsible for radiological controls as qualified to perform assigned functions. This certification must be based on an NRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible supervision that the individual has demonstrated his ability to perform each specified procedure and assigned function with an understanding of its basis and purpose.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, response and analysis of the plant for transients and accidents.
OYSTER CREEK 6-2a Amendment No.: 134,203,220,226i232, 265
(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 reactorcore 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. 267 , 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 plans1 , 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-underi 0-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;--1-994,-subject-to-the -following.-provision:.-
The Exelon Generation Company may make changes to the approved "The Training and Qualification Plan and Safeguards Contingency Plan- are Appendices to the Security tRenewedPlan, License No. DPR-44 Revised by letter dated October 28, 2004 Revised. by letter dated May 29, 2007 Amendment No 267 Page 3
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions described in the UFSAR, with the following exceptions: 1). the Manager-Radiation Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).
PBAPS UNIT 2 5.0-5 Amendment No. 267
(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 deemedto 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. 267 , 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.PrQgrar,.Revision-3.' -.The-set-
-contain'sSafe-g-aThuidi-fformation protected under 10 CFR 73.21.
(4) Fire Protection The ExelonGeneration 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
'Licensed power level was revised by Amendment-No- 250, dated -November 22, 2002, and V4,b-e implemented foilowing the 14t" 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, 20Q4 Revised.by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Amendment No.; 267 Page 3
Unit Staff Qualifications
- *. 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 *Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualif ications of ANSI N1.8.1-1971 for comparable positions described in the UF.SAR, with the following exceptions:. 1) the Manager-Radiation Protection shal.] meet or exceed the qualifications of Regulatory Guide 1.8, September 1.975, and 2) the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the.NRC and described in an applicable station training procedure.
5.3.2 For the purpose of 1O.CFR 55.4, a.licensed Senior Reactor Operator (SRO) and a licensed Reactor. Operator (RO) are those individuals who, in.addition to meeting the requirements of TS 5.3.1, perform.
the functions described in 10 CFR 50.54(m).
PBAPS UNIT 3 5.0-5 Amendment No. 271
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2/40 are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Oder without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D. Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E. The licensee 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 sets of plans 1 , which contain Safeguards Information protected under. 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
F. The licensee 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 Safety Evaluation Reports dated July 27, 1979 with supplements dated November 5, 1980, and
'The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-29 Amendment No.' 240
Unit Staff Qualifications.
.5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-.1971, with the following exceptions:
- 1) the radiation protection manager or lead radiation protection technician who shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experienceeligibility requirements for operator license applicants, (described in.Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and. described in an applicable station training procedure.
Quad Cities 1 and 2 5.3-1 Amendment No 240 /235
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 235 are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. The license shall maintain the commitments made in response to the March. 14, 1983, NUREG-0737 Order, subjectto the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be.
permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D. Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E. The licensee 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 , which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
F. The licensee 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 Safety Evaluation Reports dated July 27, 1979 with supplements dated The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 235
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or.exceed the minimum qualifications of ANSI N1.8.1-1971, with the following exceptions:
- 1) the radiation protection manager or lead radiation protection technician who shall meet or exceed the qualifications for "Radiation Protection Manager" in.Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described i.n an applicable station training procedure.
Quad Cities 1 and 2 5.3-1 Amendment No.240/235
- (2) AmerGen Energy Company. LLC, 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 reactor fuel, sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation. monitoring equipment calibration,. and as fission detectors in amounts as required for reactor operation; (3) AmerGen Energy Company. LLC, pursuant to the Act and 10 CFR Parts 30. 40 and 70to receive, possess at either TMI-1 or TMI-2, and use in amounts as required for TMI-1 anybyproduct,source or special.
nuclear material without restriction to chemical or physical form, for sample analysis, testing, instrument calibration, or associated with radioactive apparatus or components. Other than radioactive apparatus and components to be used at TMI Unit 2 in accordance with the TMI-2 License, the radioactive apparatus and components that may be moved from TMI Unit I to TMI Unit 2 under this provision shall, be limited to: (1) outage-related items (such as contaminated scaffolding, tools, protective clothing, portable shielding and decontamination equipment); and (2) other equipment belonging to TMI Unit I when storage of such equipment at TMI-2 is deemed necessary for load handling or contamination control considerations; (4) AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess at the TMI Unit I or Unit 2 site, but not separate,:such byproduct and special nuclear materials as may be produced by theoperation of either unit. Radioactive waste may be moved from TMI Unit.2 to TMI Unit I under-this provision for collection, processing (including decontamination), packaging, andtemporary storage prior to disposal. Radioactive waste that may be moved from TMI Unit I to TMI Unit 2 under this provision shall be limited to: (1) dry active waste (DAW) temporarily moved to TMI Unit 2 during waste collection activities, and (2) contaminated liquid contained in shared system piping and tanks. Radioactive waste that may be moved from TMI Unit I to TMI Unit 2 under this provision shall not include spent fuel, spent resins, filter sludge, evaporator bottoms, contaminated oil. or contaminated liquid filters.
The storage of radioactive materials or radwaste generated at TMI Unit 2 and stored at TMI Unit I shall not result in a source term that, if released, would exceed that previously analyzed in the UFSAR in terms of offsite dose consequences.
The storage of radioactive materials or radwaste generated at TMI Unit I and stored at TMI Unit 2 shall not result in a source term that, if released, would exceed that previously analyzed in the PDMS SAR for TMI Unit 2 in terms of off-site dose consequences.
- c. .This license shall be deemed to contain and is subject to the conditions specified.in the following Commission regulations10 CFR Chapter L: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part.50, andSection 70.32 of Part 70; 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 steady state reactor core power levels not in excess of 2568 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No 265 are hereby incorporated in the license. The AmerGen Energy Company, LLC shall operate the facility in accordance with the Technical Specifications.
Amendment No.: "1265
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications. of ANSI/ANS 3:1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications, with the following exceptions: 1) the education and experience, eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure, and 2) individuals who do not meet ANSI/ANS 3.1 of 1978, Section 4.5, are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977. Each radiological controls technician/supervisor shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-I Radiation Controls training program. All radiological controls technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents.
6.4 TRAINING 6.4.1 A training program for the Fire Brigade shall be maintained and shall meet or exceed the requirements of Section 600 of the NFPA Code.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The director of each department shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the Review and Approval Matrix. Implementing.
- approvals shall be performed at the cognizant manager level or above.
6-3 Amendment Nos. 11,32 , 77, 92,129,*31,132,139 17*1*207, 212, 218, 241, 265