Letter Sequence Other |
|---|
|
|
MONTHYEARML0508705402005-03-25025 March 2005
Technical Specification Change Request No. 332 - Upgrade of 69 Kv Offsite Power Transmission Line
Project stage: Other
ML0513001002005-04-26026 April 2005
Draft RAI on Your Proposed Amendment Re. Offsite Power Line Upgrade
Project stage: Draft RAI
ML0516601332005-06-10010 June 2005
Response to Request for Additional Information Concerning Technical Specification Change Request on Upgrade of 69kV Offsite Power Transmission Line
Project stage: Response to RAI
ML0520000612005-07-14014 July 2005
Tech Spec Pages for Amendment 256 Capability Upgrade of a 69-KV Offsite Power Line to 230-KV
Project stage: Other
ML0517502482005-07-14014 July 2005
Issuance of License Amendment 256 Capability Upgrade of a 69-KV Offsite Power Line to 230-KV
Project stage: Approval
2005-04-26
[Table View] |
|
|---|
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
[Table view] |
Text
Bases:
The general objective is to assure an adequate supply of power with at least one active and one standby source of power available for operation of equipment required for a safe plant shutdown, to maintain the plant in a safe shutdown condition and to operate the required engineered safety feature equipment following an accident.
AC power for shutdown and operation of engineered safety feature equipment can be provided by any of three active (one or two 230 KV lines: N-line or 0-line, the 230 KV S-line, and one of two 34.5 KV lines is active) and either of two standby (two diesel generators) sources of power.
In applying the minimum requirement of one active and one standby source of AC power, since two 230 KV lines are on the same set of towers, either one or both of the 230 KV lines (N-line or O-Line) are considered as a single active source. Normally all six sources are available.
However, to provide for maintenance and repair of equipment and still have redundancy of power sources the requirement of one active and one standby source of power was established. The plant's main generator is not given credit as a source since it is not available during shutdown.
The plant 125V DC system consists of three batteries and associated distribution system.
Batteries B and C are designated as the safety related subsystems while battery A is designated as a non-safety related subsystem. Safety related loads are supplied by batteries B and C, each with two associated full capacity chargers. One charger on each battery Is in service at all times with the second charger available in the event of charger failure. These chargers are active sources and supply the normal 125V DC requirements with the batteries and standby sources. (1)
Action 3.7.D.1 is for one required safety related battery B or battery C charger (i.e., no station battery charger operable for the associated battery) inoperable (e.g., the battery float voltage limit of 4.7.C.1.a is not maintained for battery B or battery C). These Actions provide a tiered response that focuses on returning the battery to the fully charged state and restoring a fully qualified charger to OPERABLE status in a reasonable time period. Action 3.7.D.1.a requires that the battery terminal voltage be restored to greater than or equal to the minimum established float voltage within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This time provides for returning the inoperable charger to OPERABLE status or providing an alternate means of restoring battery terminal voltage to greater than or equal to the minimum established float voltage. Restoring the battery terminal voltage to greater than or equal to the minimum established float voltage provides good' assurance that, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the associated battery will be restored to its fully charged condition (as verified by Action 3.7.tD.1 .b) from any discharge that might have occurred due to the charger inoperability.
A discharged battery having terminal voltage of at least the minimum established float voltage indicates that the battery is on the exponential charging current portion (the second part) of its recharge cycle. The time to return a battery to its fully charged state under this condition is simply a function of the amount of the previous discharge and the recharge characteristic of the battery. Thus, there is good assurance of fully recharging the battery within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, avoiding a premature shutdown with its own attendant risk.
If established battery terminal float voltage cannot be restored to greater than or equal to the minimum established float voltage within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and the charger is not operating in the current-limiting mode, a faulty charger is indicated. A faulty charger that is incapable of maintaining established battery terminal float voltage does not provide assurance that it can revert to and operate properly in the current limit mode that is necessary during the recovery period following a battery discharge event that the DC system is designed for.
OYSTER CREEK 3.7-4 Amendment No.: ,6 , 99, 13G6,448-,222-,245, 256 rofted by -o151201
3.7 AUXILIARY ELECTRICAL POWER Applicability: Applies to the OPERATING status of the auxiliary electrical power supply.
Obiective: To assure the OPERABILITY of the auxiliary electrical power supply.
Specification:
NOTE: LCO 3.0.C.2 is not applicable to Auxiliary Electrical Power.
A. The reactor shall not be made critical unless all of the following requirements are satisfied:
- 1. The following buses or panels energized.
- a. 4160 volt buses 1C and 1D in the Turbine Building Switchgear Room.
- b. 460 volt buses:
USS 1A2, USS 1B2, MCC 1A21, MCC 1821, Vital MCC 1A2, and Vital MCC 1B2 in the Reactor Building 480 V Switchgear Room.
USS 1A3 and USS 1B3 in the Intake Structure.
MCC 1A21A, MCC 1A21B, MCC IB21A, MCC 1B21B, and Vital MCC 1AB2 on Reactor Building Elevation 23' 6".
MCC 1A24 and 1B24 in the Boiler House.
- c. 208/120 volt panels CIP-3, IP-4, IP-4A, IP-4B, IP-4C and VACP-1 in the Reactor Building Switchgear Room.
- d. 120 volt protection panels PSP-1 and PSP-2 in the Lower Cable Spreading Room.
- e. 125 VDC Distribution Centers DC-B and DC-C.
125 VDC Power Panels DC-D and DC-F.
125 VDC MCCs DC-1 and DC-2
- f. 24 volt DC power panels DC-A and DC-B in the Lower Cable Spreading Room.
- 2. One 230 KV line (N-line or O-line) is fully operational and switch gear and both I startup transformers are energized to carry power to the station 4160 volt AC buses and carry power to or away from the plant.
- 3. An additional source of power consisting of one of the following is in service connected to feed the appropriate plant 4160 V bus or buses:
- a. 230 KV S-line fully operational. I
- b. A 34.5 KV line fully operational.
OYSTER CREEK 3.7-1 Amendment No.: 11, 55, 80,4419, 136, 211,222,211,215,256 Corrected by lctter of 1/15/201