ML082470305
| ML082470305 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Byron, Braidwood, Limerick, Quad Cities, Crane |
| Issue date: | 08/28/2008 |
| From: | Plant Licensing Branch III |
| To: | |
| Gratton C, NRR/DORL, 415-1055 | |
| References | |
| TAC MD6530, TAC MD6531, TAC MD6532, TAC MD6533, TAC MD6534, TAC MD6535, TAC MD6536, TAC MD6537, TAC MD6538, TAC MD6539, TAC MD6540, TAC MD6541, TAC MD6542, TAC MD6543 | |
| Download: ML082470305 (29) | |
Text
(3)
Exelon Generation Company,,pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission 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, suchi 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 to this license shall be completed as specified. is hereby incorporated into this license.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 153, 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, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 153 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 to this license shall be completed as specified. is hereby incorporated into this license.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 153 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)
Emerqency 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. 153
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Inservice Testing Proqram This program provides controls Class 1, 2, and 3 components.
following:
,or inservice testing of ASME Code The program shall include the
- a.
Testing frequencies applicable to the ASME Operation and Maintenance of Nuclear Power Code) and applicable Addenda as follows:
Code for Plants (ASME OM ASME OM Code and applicable Addenda terminology for inservice testing activities I
Requi red Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years At At least once per least once per 7 days 31 days.
At least once per 92 days At At At least least least once once once per 184 days per 276 days per 366 days At least once per 731 days;
- b.
The provisions of SR 3.0.2 are applicable to the above required,Frequencies and to other normal and accelerated Frequencies specified. as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d.
Nothing in the ASME the requirements of OM Code shall be construed to supersede any Technical Specification.
I BPA!DWOOD - UNITS I & 2 5,5-6 Amendment 153 (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 componrents; 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.157 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licen'see 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. 157 (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 1113), as revised through Amendment No. 157, 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.1 57
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Inservice Testina Proaram This program provides controls CIdass 12
, aud 3 components.
following:
for inservice testing of ASME Code The program shall include the
- a.
Testing frequencies applicable to-the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:
ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testinQ activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years At least once per 7 days At least once per 31 days At least once per 92 days At least once At least once M-least once per 184 days per 276 days per 366 days At least once per 731 days;
- b.
The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d.
Nothing in the ASME the requirements of OM Code shall be construed to supersede any Technical Spetification.
BYRON - UNITS 1 & 2 5.5-6 Amendment 157 (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 anybyproduct, 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 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 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 Spe-ifications contained in Appendix A, as revised through Amendment No 229, are hereby incorporated into this renewed operating license. rhe 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. 229 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 MOVDE 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 Technical Srecifications contained in Appendix A, as revised through Amendment No. 2 22, 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. 222
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
I.
For noble gases: a dose rate < 500 mrems/yr to the whole body and a dose rate < 3000 mrems/yr to the skin, and
- 2.
For iodine-131, iodine-133, tritium, and all radionuclides i n particulate form with half-lives greater than 8 days: a dose rate <_ 1500 mrems/yr to any organ;
- h.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 5.0, Appendix I;
- i.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas. beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- i.
Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity'and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of SR 3.0.2 and SR 3.0,.3 are applicable to the Radioactive Effluents Control Program Surveillance Frequencies.
5.5.5 Component Cyclic or Transient Limit
- This program provides controls to track the UFSAR Section 3.9, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.
- a.
Testing Frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME nM Code) and applicable Addenda are as follows:
tcontinued)
Dresden 2 and 3 5.:5-4 Amendment No.229/222
Programs and Manual s 5.5 5.5 Programs and Manuals Inservice Testing Program (continued)
ASME OM Code and applicable Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years Every 48 months Required Frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days At At At least least least once once once per 184 days per 276 days per 366 days At least once per 731 days At least once per 1461 days
- b.
The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d.
Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.
Ventilation Filter Testina Proaram (VFTP) 5.5.
The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems.
Tests described in Specification 5.5.7.a and 5.5.7.b shall be performed once per 24 months; after each complete or partial replacement of the HEPA filter bank or charcoal adsorber bank; after any structural maintenance on the HEPA filter bank or charcoal adsorber bank housing; and, following painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation that could adversely affect the filter bank or charcoal adsorber capability.
(continued)
Oresden 2 and 3 5.5-5 Amendment No.229/222 (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. oossess. and use. in amounts as required any byproduct, source. or special nuclear material without restriction to.chemical orphysicalform, 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.194 ; are hereby incorporated. into this license.
Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 62, 4-06, *1-34, -147
-l, 1 94
APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other specified conditions in the Applicability for individual Limiting Conditions for Operation, unless otherwise stated in the Surveillance Requirement.
Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limiting Condition for Operation.
Failure to perform a Surveillance within the specified Surveillance time interval and allowed extension per Specification 4.0.2, shall be failure to meet the Limiting Condition for Operation except as provided in Specification 4.0.3.
Surveillances do not have to be performed on inoperable equipment or variables outside specified' limits.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance time interval with a maximum allowable extension not to exceed 25%
of the surveillance interval.
4.0.3 If it is discovered that a Surveillance was not performed within its specified Surveillance time interval and allowed extension per Specification 4.0.2, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Surveillance time interval, whichever is greater.
This delay period is permitted to allow performance of the Surveillance.
A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requir~ements must be entered.
When the Surveillance is performed within the delay period and' the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be-entered.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified condition in the Applicability of a Limiting Condition for Operation shall only be made when the Limiting Condition for Operation's Surveillance Requirements have been met within their Surveillance time interval, except as provided in Specification 4.0.3.
When a Limiting Condition for Operation is not met due to its Surveillance Requirements not having been met, entry into an OPERATIONAL CONDITION or other specified condition in the Applicability shall only be made in accordance with Specification 3.0.4.
This provision shall not prevent entry into OPERATIONAL CONDITIONS or other specified conditions in the Applicability that are required to comply with ACTION requirements or that are part of a shutdown of the unit.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:
- a.
Inrservice inspection of ASME Corie C-as.
I, 2, and 3 components shall be performed in a-ordance wilth1 S-ti on
'I of the ASME Boiler and Pressure Ve~ssel COd~v-dli r
Ij i
i'. A l-, 'd a r-_o uire' by [0 CFP Part 50, Section 50.55a.
lnservice te..Stirtg of ASME CoLe Class 1, 2, and 3 pumps and valves sha i be periormep' in 1arccrmance orith theASME Code for Operation arid Mair.tenar ce ho er Pnowr P (ASME OM Code) and applicable Addenda as rc(juir ed b', iO fl FIR Part. 50,
)c-1n 50.55 LIMERICK - UNIT I 3/4 0-2 Amendment No.
44, -3G, 4--u, 4-6-,
4-6q,194
APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)
- b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection activities, and the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda for inservice testing activities, shall be applicable as follows in these Technical Specifications:
Required frequencies ASME Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days
- c.
The provisions of Specification 4.0.2 are applicable to the'above required frequencies for performing inservice inspection and testing activities.
In addition, the provision of Specification 4.0.2 are applicable to other normal and accelerated frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities.
- d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- e.
Nothing in the ASME Code shall be construed to supersede the requirements of any Technical Specification.
- f.
The Inservice Inspection (ISI)
Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion included in the Generic Letter, or in accordance with alternate measures approved by the NRC staff.
Details for implementation of these requirements are included as augmented inspection requirements in the 1SI Program.
LIMERICK - UNIT I 3/4 0-3 Amendment No.
44, 4-9, 4-I-s, 4-74, 194 (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~withoutrestriction to chemical or physical form, for sample analysisý 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, andto 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. 1 55, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with theTechnical 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 parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed-Amendment No. 4-, 27,,&i-i., 689, 1-*,ý
!+-
155
APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS.
or other specified conditions in the Applicability for individual Limiting Conditions for Operation, unless otherwise stated in the Surveillance Requirement.
Failure to meet a Surveill'ance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limiting Condition for Operation.
Failure to perform a Surveillance within the specified Surveillance time interval and allowed extension per Specification 4.0.2, shall be failure to meet the Limiting Condition for Operation except as provided in Specification 4.0.3.
Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.
4.0.3 If it is discovered that a Surveillance was not performed within its specified Surveillance time interval and allowed-extension per Specification 4.0.2, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Surveillance time interval, whichever is greater.
This delay, period is permitted to allow performance of the Surveillance.
A risk evaluation shall be performed for any Surveillance delayed greater. than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the Limiting.
Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be entered.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified condition in the Applicability of a Limiting Condition for Operation shall only be made when the Limiting Condition for Operation's Surveillance Requirements have been met within their Surveillance time interval, except as provided in Specification 4.0.3.
When a Limiting Condition for Operation is not met due to its Surveillance Requirements not having been met, entry into an OPERATIONAL CONDITION or other specified condition in the Applicability shall only be made in accordance with Specification 3.0.4.
This provision shall not prevent entry into OPERATIONAL CONDITIONS or other specified conditions in the Applicability that are required to comply with ACTION requirements or that are part of a shutdown of the unit.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2,
& 3 components shall be applicable as follows:
- a.
Inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Secticn 50.55a.
Inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda required by 10 FR Part 50, Secton 50.55a.
as1,erie bylV CF LIt*n LIMERICK - UNIT 2 3/4 0-2 Amendment No.
-, 89, 4--4, 44-39,155
APPLICABILITY SURVEILLANCE REOUIREMENTS (Continued)
- b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection activities, and the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda for inservice testing a.ctivities, shall be applicable as follows in these Technical Specifications:
Required frequencies ASME Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every(2 years At least once per 731 days
- c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
In addition, the provision of. Specification 4.0.2 are applicable to other normal and accelerated frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities.
- d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- e.
Nothing in the ASME Code shall be construed to supersede the requirements of any Technical Specification.
- f.
The Inservice Inspection (ISI) Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion included in the Generic Letter, or in accordance with alternate measures approved by the NRC staff.
Details for implementation of these requirements are included as augmented inspection requirements in the ISI Program.
LIMERICK - UNIT 2 3/4 0-3 Amendment No, 442, 8-4, 4J*4,l1 5 5 (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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 268, are hereby incorporated in the license. AmerGen Energy Company, LLC shall 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:
AMENDMENT NO. 268
4.3 REACTOR COOLANT Applicability:
Applies to the surveillance requirements for the reactor coolant system.
Obiective:
To determine the condition of the reactor coolant system and the operation of the safety devices related to it.
Specification: A.
Materials surveillance specimens and neutron flux monitors shall be installed in the reactor vessel adjacent to the wall at the'midplane of the active core.
Specimens and monitors shall be periodically removed, tested, and evaluated to determine the effects of neutron fluence on the fracture toughness of the vessel shell materials. The results of these evaluations shall be used to assess the adequacy of the P-T curves A, B, and C in Figures 3.3.1, 3.3.2 and 3.3.3. New curves shall be generated as required.
B.
Inservice inspection of ASME Code Class 1, Class 2 and Class 3 systems and components shall be performed in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a, except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a.
C.
Inservice testing of ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as required by 10 CFR, Section 50.55a, except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a.
D.
A visual examination for leaks shall be made with the reactor coolant system at pressure during, each scheduled refueling outage or after major repairs have been made to the reactor coolant system in accordance with Article 5000, Section X1. The requirements of specification 3.3.A shall be met during the test.
E.
Each replacement safety valve or valve that has been repaired shall be tested in accordance with Specification C above. Setpoints shall be as follows:
Number of Valves 4
5 Set Points (Usia) 1212 +/- 36 1221 -+/-36 F.
A sample of reactor coolant shall be analyzed at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the purpose of determining the content of chloride ion and to check the conductivity.
OYSTER CREEK 4.3-1 Amendment No.: 82., 90. 12,
- 4150, 151,
- 4161, 88, 106, 26---, 268
(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.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 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: "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-Safeg uards-Information-protected-under -1 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, -su bject-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 Amendment No. 26 8 Page 3
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) friservicep Tpqtina Prnciram This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components.
The program shall include the following:
- a.
Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plan-s iASME OM Code) and applicable Addenda are as follows:
ASME OM Code and applicable Addenda terminology for inservice testing antivitipes Required Frequencies for performing inservice testina activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years At least once At least once per 7 days per 31 days At least once per 92 days At At At least least least once once once per i84 days per 276 days per 366 days At least once per 732 days
- b.
The provisions of SR 3.0.2 are applicable to the above required Frequencies and to otner normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d.
Nothing in the ASME OM Code-shall be construed to supersede the requirements of any TS.
Ventilation Filter Testing Program (VFTP)
The VFTP shall establish the required testing of Engineered Safety Feature (ESF). filter ventilation systems.
Tests described in Specifications 5.5.7.a, 5.5.7.b, and 5.5..c shall be performed:
(cnn inuedl 5.5.7 PBAPS UNIT 2 50 -1I1 AmI2nc~ment rjc.268
(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 followinq 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, 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. 272
, 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 plans2, 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 P*cogram, Revision?3. -The-set-
-contai-Saf--afG ifod-rmakion 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
'Licensed power Leyel was revised-by Amendment-No. 250, dated -November 22, 2002, and
-i;H tbe inpiernented following the 14"' 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 Arneni-dment No. 272 Page 3
Programs and Manuals 5.5 Programs and Manuals (continued) 5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code
&lass 1, 2, and 3 components.
The program shall include the following:
- a.
Testing frequencies appl icable ao the ASME Code for Operati on and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda are as follows:
ASME OM Code and applicable Addenda terminology *for inservice testing activities Required Frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years At At At Ieast least least once once once per 184 days per 276 days per 366 days At least once per 732 days
- b.
The provisions of SR 3.0.2 are applicable to the above reLQuired Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d.
Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.
Ventilation Filter Testing Program (VFTP)
I 5.5.7 The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems.
Tests described in Snecifications 5.5.7.a, 5.5.7.b, and 5.5.7.c shall be performed:
-c4ntinued)
P B,", PS' 1jN IT, J 5.0 -!iI Amendment No272 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 241, are hereby incorporated into this renewed operating license. The licensee shalloperate 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. 241 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment'No. 236, are hereby incorporated into this renewed operating license. The licensee shall operate theId.Id.-UIity,,- dauIcud,.-n..
with the Technical Specifications.
C.
The license 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 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', 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 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 236
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
I.
For noble gases: a dose rate
- 500 mrems/yr to the whole body and a dose rate
- 3000 mrems/yr to the skin, and
- 2.
For iodine-i31, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate ! 1500 mrems/yr to any organ;
- h.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix 1;
- i.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and J.
Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluents Control Program Surveillance Frequencies.
5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR Section 3.9, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.
- a.
Testing Frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and app1icabIe Addenda are' as follows; (continued)
Quad Cities I and 2 Amendment No. 241/236
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Inserviri Testina Proaram (continued)
ASME OM Code and applicable Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or, annually Biennially or every 2 years Every 48 months Required Frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least At least At least once once once per 184 days per 276 days per 366 days At least once per 731 days At least once per 1461 days
(
5.5.7
- b.
The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d.
Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.
Ventilation Filter Testing Program (VFTP)
The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems.
Tests described in Specification 5.5.7.a and 5.5.7,b shall be performed once per 24 months; after each complete or partial replacement of the HEPA filter bank or charcoal adsorber bank; after any structural maintenance on the HEPA filter bank or charcoal adsorber bank housing; and, following painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation that could adversely affect the ficter bank or charcoal adsorber capability.
conrti nued)
Quad Cities I and 2 5.5-5 QaC1nmnt No 241/236 (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 cairtoand asfsindetect-ors in. amounts. as aý qU;T'fru MatI O peatioen; cali,,-,tim n fi, ssion rhicrt-,
- I G,....,*
10 lul.l...
- ,,q~
o e ctro e ai n (3)
AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess at either TMI-I or TMI-2, and use in amounts as required for TMI-I any byproduct, 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 TM1-2 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 TM1 Unit I whien 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 the operation 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, and temporary 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 regulations 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.4 1 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 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 No266 are hereby incorporated in the license. The AmcrGen Energy Company. LLC shall operate the facility in accordance with the Technical Specifications.
Amendment *cN. 266
4.2 REACTOR COOLANT SYSTEM INSERVICE AND TESTING Apolicability This technical specification applies to the inservice inspection (ISI) and inservice testing (IST) of the reactor coolant system pressure boundary and portions of other safety oriented system pressure boundaries.
Obiective The objective of the ISI and IST programs is to provide assurance of the continuing integrity of the reactor coolant system while at the same time minimizing radiation exposure to personnel in the performance of inservice inspections and tests.
Specification 4.2.1 ISI of ASME Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code andapplicable Addenda as required by 10 CFR 50, Section 50.55a; except where specific written relief has been granted by the NRC.
4.2.2 IST of ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as required by 10 CFR 50, Section 50.55a, except where specific written relief has been granted by the NRC.
4.2.3 (Deleted) 4.2.4 The accessible portions of one reactor coolant pump motor flywheel assembly will be ultrasonically inspected within the first ISI period, two reactor coolant pump motor flywheel assemblies within the first two ISI periods and all four by the end of the 10 year inspection interval. However, the U.T. procedure is developmental and will be used only to the extend that it is shown to be meaningful. The extent of coverage will be limited to those areas of the flywheel which are accessible without motor disassembly, i.e., can be reached through the access ports. Also, if radiation levels at the lower access ports are prohibitive, only the upper access ports will be used.
4-11 Amendment No. 1-, 29,64, 650, 7., :18, 72, 266
4.9 DECAY HEAT REMOVAL (DHR) CAPABILITY - PERIODIC TESTING Applicability Applies to the periodic testing of systems or components which function to remove decay heat.
Obiective To verify that systems/components required for DHR are capable of performing their design function.
Specification 4.9.1 Reactor Coolant System (RCS) Temperature greater than 250 degrees F.
4.9.1.1 Verify each Emergency Feedwater (EFW) Pump is tested in accordance with the requirements and acceptance criteria of the Inservice Test Program.
Note:
This surveillance is not required to be performed for the turbine-driven EFW Pump (EF-P-1) until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 750 psig.
4.9.1.2 DELETED 4.9.1.3 At least once per 31 days, each EFW System flowpath valve from both Condensate Storage Tanks (CSTs) to the OTSGs via the motor-driven pumps and the turbine-driven pump shall be verified to be in the required status.
4.9.1.4 On a refueling interval basis:
a) Verify that each EFW Pump starts automatically upon receipt of an EFW test signal.
b) Verify that each EFW control valve responds upon receipt of an EFW test signal.
c) Verify that each EFW control valve responds in manual control from the control room and remote shutdown panel.
4.9.1.5 Prior to STARTUP, following a REFUELING SHUTDOWN or a COLD SHUTDOWN greater than 30 days, conduct a test to demonstrate that the motor driven EFW Pumps can pump water from the CSTs to the Steam Generators.
4-52 Amendment No. -7. 119. 124, 172,-242.2Fr,