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MONTHYEARML0525601182005-08-26026 August 2005 Draft RAI Re. Proposed Amendment on Alternative Source Term Project stage: Draft RAI ML0531203762005-11-0202 November 2005 Response to Request for Additional Information - License Amendment Request No. 315, Application of Alternative Source Term. (Non-Proprietary Version) Project stage: Response to RAI ML0531203242005-12-0505 December 2005 Amergen Energy Company LLC, Request for Withholding Information from Public Disclosure for Oyster Creek Generating Station Project stage: Withholding Request Acceptance ML0633204782006-11-28028 November 2006 E-mail, Miller, NRR, to Distel, Exelon, Draft Request for Additional Information, Oyster Creek AST LAR Project stage: Draft RAI ML0633302152006-12-19019 December 2006 RAI, License Amendment Request for Application of the Alternate Source Term Methodology Project stage: RAI ML0634501852006-12-21021 December 2006 Summary of Meeting with Amergen Energy Company, LL, to Discuss Alternative Source Term License Amendment Request Project stage: Meeting ML0703101012007-01-24024 January 2007 Response to Request for Additional Information - License Amendment Request No. 315, Application of Alternative Source Term Project stage: Response to RAI ML0703603302007-02-0202 February 2007 Response to Request for Additional Information - License Amendment Request No. 315, Application of Alternative Source Term. Project stage: Response to RAI ML0705204592007-02-0909 February 2007 E-mail, Miller, NRR, to Distel, Exelon, Oyster Creek AST Project stage: Other ML0708508202007-03-15015 March 2007 Calculation No. C-1302-826-E310-018, Revision 0, Oyster Creek Offsite Atmospheric Dispersion (X/Q) for Alternative Source Terms (Ast). Project stage: Other ML0708508162007-03-16016 March 2007 Additional Information - License Amendment Request No. 315, Application of Alternative Source Term Project stage: Request ML0706505142007-03-21021 March 2007 Clarification of Response to Request for Additional Information Regarding License Amendment Request for Application of the Alternate Source Term Methodology Project stage: RAI ML0709200672007-03-23023 March 2007 Additional Information - License Amendment Request No. 315, Application of Alternative Source Term Project stage: Request ML0708803932007-03-28028 March 2007 Additional Information - License Amendment Request No. 315, Application of Alternative Source Term. Project stage: Request ML0710800192007-04-26026 April 2007 License Amendment Application of Alternate Source Term Methodology Project stage: Acceptance Review ML0711703892007-04-26026 April 2007 Technical Specifications Application of Alternate Source Term Methodology Project stage: Other ML0713102132007-05-0404 May 2007 Additional Information - License Amendment Request No. 315, Application of Alternative Source Term. Project stage: Request 2007-02-02
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Category:Technical Specifications
MONTHYEARML21119A0642021-06-25025 June 2021 License Amendment 299 ML18221A4002018-10-17017 October 2018 Issuance of Amendment No. 294, Revise the Site Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MG0160; L-2017-LLA-0307) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) RA-15-030, Submittal of Changes to Technical Specifications Bases2015-04-14014 April 2015 Submittal of Changes to Technical Specifications Bases ML14329A6252015-03-30030 March 2015 Issuance of Amendment Regarding Reactor Building Vital Area Access Control ML1019301722010-09-27027 September 2010 Issuance of Amendment Relocation of Surveillance Requirement Frequencies to a Licensee Controlled Document Based on TSTF-425, Revision 3 RA-10-028, Response to Request for Additional Information, License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document2010-04-16016 April 2010 Response to Request for Additional Information, License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document RA-09-029, Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of A..2009-03-30030 March 2009 Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of A.. RA-08-100, Special Report for Inoperability of Turbine Building High Range Radioactive Noble Gas Monitor2008-11-18018 November 2008 Special Report for Inoperability of Turbine Building High Range Radioactive Noble Gas Monitor ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0812303462008-05-30030 May 2008 Tec Specs to Amd 266/License DPF-16/Oyster Creek ML0810505452008-04-30030 April 2008 Technical Specification Pages for License Amendment No. 265 the Incorporation of TSTF-448, Revision 3, Control Room Habitability. (Tac MD5281) RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. RA-08-004, Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)2008-03-10010 March 2008 Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0802901792008-02-0101 February 2008 Oyster Creek,Technical Specifications, Corrected, Revised Pages of Facility Operating License No. DPR-16 RA-08-011, Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement..2008-01-23023 January 2008 Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement.. ML0729202902007-10-18018 October 2007 Technical Specification Change Request No. 374 - Revision to Mechanical Snubber Functional Testing Requirements ML0722501972007-08-0808 August 2007 Technical Specifications Pages Re Annual Radioactive Effluent Release Report Submittal Date ML0721302932007-07-27027 July 2007 Technical Specifications, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0713603392007-05-16016 May 2007 Technical Specification Change Request No. 327 - Modify Technical Specifications for Primary Containment Oxygen Concentration ML0711703892007-04-26026 April 2007 Technical Specifications Application of Alternate Source Term Methodology ML0633201962006-11-27027 November 2006 Technical Specification Change Request No. 341 - Revision to Required Submittal Date for Annual Radioactive Effluent Release Report ML0626101962006-09-13013 September 2006 Technical Specification Pages Re Increase Safety Valve As-Found Setpoint Tolerance from 1 Percent to 3 Percent ML0624404112006-09-0101 September 2006 Tech Spec Pages for Amendment 260 Regarding Revision to Electromatic Relief Valve Surveillance Requirement ML0623704752006-08-25025 August 2006 Technical Specifications - Deletion of Reporting Requirement in Facility Operating License ML0605500582006-02-22022 February 2006 Tech Spec Page for Amendment 258 Regarding Deletion of Reporting Requirement in Facility Operating License ML0600600152006-01-0404 January 2006 Technical Specifications, 1.0 Environmental Monitoring ML0529701902005-10-18018 October 2005 Technical Specification Change Request No. 328 - Modify Surveillance Requirements for Testing of Main Steam Line Electromatic Relief Valves ML0520000612005-07-14014 July 2005 Tech Spec Pages for Amendment 256 Capability Upgrade of a 69-KV Offsite Power Line to 230-KV ML0517802562005-06-23023 June 2005 Tech Spec Pages for Amendment, Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions ML0516002532005-06-0808 June 2005 Tech Spec Page for Amendment 254 Delete the TS Requirements to Submit Monthly Operating Reports and Annual Occupational Radiation Exposure Reports RS-05-006, Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License2005-02-25025 February 2005 Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License ML0505900852005-02-24024 February 2005 Technical Specification Change Request No. 319 - Revision to Table 3.1.1 Notes Aa and Bb Regarding Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions RS-04-157, Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License2004-12-17017 December 2004 Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License ML0430803562004-11-0202 November 2004 Tech Spec Pages for Amendment 250 Main Steam Line Isolation Valve Leakage Testing ML0433100362004-10-20020 October 2004 Technical Specification, Control Rod Scram Time Testing Requirements ML0429203072004-10-13013 October 2004 Table, Run or Startup Mode (Except for Low Power Physics Testing) ML0427902182004-10-0404 October 2004 Technical Specifications, Modify Control Rod Scram Time Testing Surveillance Requirements ML0425301502004-08-27027 August 2004 Station,Technical Specification Change Request No. 331 - Safety Limit Minimum Critical Power Ratio ML0423604742004-08-19019 August 2004 Technical Specification for Oyster Creek ML0422301962004-08-0909 August 2004 Tech Spec for Oyster Creek, License Amendment No. 246, Elimination of Requirements for Hydrogen Monitors ML0421703712004-07-30030 July 2004 Technical Specifications, Sections 3.7 and 4.7, Auxiliary Electrical Power, and Added a New Section 6.8.5, Station Battery Monitoring and Maintenance Program ML0415600412004-07-13013 July 2004 Unit, 1, License Amendments 244 and 250 Re.: Amendments to Delete a License Condition Regarding the Long Range Planning Program ML0415305902004-05-27027 May 2004 Unit 1, Technical Specifications, Reflect Ownership Change ML0409002892004-03-29029 March 2004 Tech Spec Pages for Amendment 241 Regarding Increasing Flexibility in Mode Restraints ML0333201312003-11-24024 November 2003 Tech Spec Pages for Amendment 239 Regarding Startup Transformer and Emergency Diesel Generator Unavailability 2021-06-25
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(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 (themal) (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. , 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:
- implemented1 AINVII-M.IIvIEINTII41O0. 262
The average of the scram insertion times for the three fastest control rods of all groups of four control rods in a two-by-two array shall be no greater than:
Rod Length Insertion Time Inserted (%) (Seconds) 5 0.398 20 0.954 50 2.120 90 5.300 Any four rod group may contain a control rod which is valved out of service provided the above requirements and Specification 3.2.A are met. Time zero shall be taken as the de-energization of the pilot scram valve solenoids.
- 4. In service control rods which cannot be moved with control rod drive pressure shall be considered inoperable. If a partially or fully withdrawn control rod drive cannot be moved with drive or scram pressure, the reactor shall be brought to a shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless investigation demonstrates that the cause of the failure is not due to a failed control rod drive mechanism collet housing. Inoperable control rods shall be valved out of service, in such positions that Specification 3.2.A is met. In no case shall the number of inoperable control rods valved out of service be greater than six during the power operation. If this specification is not met, the reactor shall be placed in the shutdown condition.
- 5. Control Rods shall not be withdrawn for approach to criticality unless at least two source range channels have an observed count rate equal to or greater than 3 counts per second.
C. Standby Liquid Control System
- 1. The standby liquid control system shall be operable at all times under the following conditions:
(a) when the reactor is not shut down by the control rods such that Specification 3.2.A is met, except as provided in Specification 3.2.C.3, and (b) when the reactor is >212 0 F, except during REACTOR VESSEL PRESSURE TESTING.
- 2. The standby liquid control solution shall have a Boron-10 isotopic enrichment equal to or greater than 35 atom %, be maintained within the cross-hatched volume-concentration requirement area in Figure 3.2-1 and at a temperature not less than the temperature presented in Figure 3.2-2 at all times when the standby liquid control system is required to be operable.
- 3. (a) If one standby liquid control system pumping circuit becomes inoperable during the RUN mode and Specification 3.2.A is met, the reactor may remain in operation for a period not to exceed 7 days, provided the pump in the other circuit is verified daily to be operable, otherwise be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
OYSTER CREEK 3.2-3 Amendment No: 76,124, 167,178, 253, Amendment No. 262