|
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| Line 46: |
Line 46: |
| .. ..... ....... .. sleci fi e-d-c ndi ti hW -hI- i-~ il -t -hy *n* b 7 made: | | .. ..... ....... .. sleci fi e-d-c ndi ti hW -hI- i-~ il -t -hy *n* b 7 made: |
| : a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; or | | : a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; or |
| .. . . ... . . -----------
| |
| . --------
| |
| . . -(continued)' | | . . -(continued)' |
| Crystal River Unit 3 3.0-1 Amendment No.224 | | Crystal River Unit 3 3.0-1 Amendment No.224 |
Letter Sequence Approval |
|---|
TAC:MD4057, Addition of LCO 3.0.8, Inoperability of Snubbers (Approved, Closed) |
|
MONTHYEAR3F1206-05, License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-14014 December 2006
License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process
Project stage: Request
3F0307-08, License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process2007-03-14014 March 2007
License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process
Project stage: Request
ML0716904912007-06-15015 June 2007
Technical Specifications, Issuance of Amendment to Adopt TSTF-372
Project stage: Approval
ML0715004662007-06-15015 June 2007
License Amendment, Issuance of Amendment to Adopt TSTF-372
Project stage: Approval
2007-03-14
[Table View] |
|
|---|
Category:Technical Specifications
MONTHYEARML21238A0952021-10-13013 October 2021
Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a
ML15261A4522015-11-27027 November 2015
Nuclear Generating Plant - Issuance of Amendment No. 249 Regarding Technical Specification Change of Management Titles to General Manager Decommissioning
ML15224B2862015-09-0404 September 2015
Nuclear Generating Plant - Issuance of Amendment for Operating License and Technical Specification Based on Permanently Shutdown and Defueled Status
ML15121A5702015-05-29029 May 2015
Letter, Safety Evaluation for Order Approving Transfer of Licenses and Conforming Amendments
ML14097A1452014-07-11011 July 2014
Nuclear Generating Plant - Issuance of Amendment No. 244, Revise Technical Specifications to Remove Certain Requirements from Section 5, Administrative Controls
3F0514-01, Response to Requests for Additional Information and Supplement 1 to License Amendment Request 316, Revision 02014-05-0707 May 2014
Response to Requests for Additional Information and Supplement 1 to License Amendment Request #316, Revision 0
3F0413-01, License Amendment Request 313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions2013-04-25025 April 2013
License Amendment Request #313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions
3F1212-06, CR-3 Extended Power Uprate LAR Supplement to Support NRC Accident Dose Branch (Aadb) Technical Review2012-12-18018 December 2012
CR-3 Extended Power Uprate LAR Supplement to Support NRC Accident Dose Branch (Aadb) Technical Review
ML12339A0672012-12-18018 December 2012
Issuance of License Amendments Regarding Cyber Security
3F0811-01, Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-18018 August 2011
Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
3F0209-06, License Amendment Request 310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification2009-02-26026 February 2009
License Amendment Request #310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification
3F0608-08, License Amendment Request 299, Revision 1: Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process..2008-06-19019 June 2008
License Amendment Request #299, Revision 1: Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process..
ML0730300752007-10-25025 October 2007
Tech Spec Pages for Amendment 227 Fuel Storage Patterns in the Spent Fuel Pool
ML0730303862007-10-23023 October 2007
Tech Spec Pages for Amendment 225 Regarding Nuclear Services Closed Cycle Cooling Water System
3F0707-03, License Amendment Request No. 299, Revision 0, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement..2007-07-12012 July 2007
License Amendment Request No. 299, Revision 0, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement..
ML0716904912007-06-15015 June 2007
Technical Specifications, Issuance of Amendment to Adopt TSTF-372
ML0714101022007-05-16016 May 2007
Tech Spec Pages for Amendment 223 Regarding Steam Generator Tube Inspection Program
3F0307-11, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction2007-03-30030 March 2007
License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information2007-03-14014 March 2007
License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information2006-12-21021 December 2006
License Amendment Request #264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F1206-05, License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-14014 December 2006
License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process
3F1006-01, License Amendment Request 292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B2006-10-0505 October 2006
License Amendment Request #292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B
ML0530503972005-10-31031 October 2005
TS for License Amendment, Probabilistic Methodology for Tube End Crack Alternate Repair Criteria, TAC No. MC5813
3F0905-06, License Amendment Request 290, Revision 2 Re Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria2005-09-0909 September 2005
License Amendment Request #290, Revision 2 Re Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria
ML0525004302005-09-0606 September 2005
Tech Spec Pages for Amendment No. 220 Regarding Removal of Obsolete Footnotes from the Technical Specifications
ML0521603482005-08-0404 August 2005
Technical Specifications, Reactor Building Spray Nozzle Surveillance Requirements
ML0521001812005-07-27027 July 2005
Technical Specifications, Amendment 218 on Surveillance Requirements for RCP Flywheel Inspection
ML0511102352005-04-19019 April 2005
Tech Spec Pages for Amendment No. 217, Revision to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Reports Requirements
3F0105-03, License Amendment Request 290, Revision 0, Probabilistic Methodology to Determine the Contribution to Main Stream Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria2005-01-27027 January 2005
License Amendment Request #290, Revision 0, Probabilistic Methodology to Determine the Contribution to Main Stream Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria
ML0501204702005-01-11011 January 2005
License Amendment, Mode Change Limitations (Tac No. MC1861)
ML0501300522005-01-11011 January 2005
Technical Specification Pages Re Mode Change Limitations
ML0429602092004-10-21021 October 2004
Amendment, Tech Spec, One-Time Extension of an Emergency Feedwater System Train Completion Time
ML0414101392004-05-18018 May 2004
Tech Spec Pages Amendment 212 Regarding the Nuclear Services Seawater System
ML0414101442004-05-18018 May 2004
Tech Spec Pages for Amendment 212 Regarding the Nuclear Services Seawater System
ML0336001152003-12-19019 December 2003
Application for Technical Specification Change Re Mode Change Limitations Using Consolidated Line Item Improvement Process
ML0329503392003-10-16016 October 2003
Technical Specification for Crystal River, Unit 3, Amendment No. 211
ML0327905482003-10-0101 October 2003
Tech Spec for Crystal River, Unit 3 - Issuance of Amendment Regarding TS Change Request for the Use of M5 Advanced Alloy Fuel Cladding
ML0325412262003-09-0808 September 2003
Technical Specification Change Request for Containment Isolation Valves 3.6.3
ML0319604892003-07-14014 July 2003
Tech Spec Pages for Amendment 208 Regarding TS Change Request for Containment Requirements During Irradiated Fuel Handling and Core Alterations
ML0316713192003-06-13013 June 2003
Tech Spec Pages for Amendment 207 Technical Specification Change Request for Emergency Diesel Generator Allowed Outage Time Extension
3F0403-04, TS Bases Control Program2003-04-10010 April 2003
TS Bases Control Program
3F0303-03, Response to Request for Additional Information & Revision 1 to Proposed License Amendment Request 257, Emergency Diesel Generator Allowed Outage Time Extension2003-03-20020 March 2003
Response to Request for Additional Information & Revision 1 to Proposed License Amendment Request #257, Emergency Diesel Generator Allowed Outage Time Extension
3F0203-05, License Amendment Request 274, Revision 0, Containment Isolation Valves2003-02-17017 February 2003
License Amendment Request #274, Revision 0, Containment Isolation Valves
ML0304400642003-02-11011 February 2003
Technical Specification Pages for Amendment No. 206 Proposed Change to Loss-of-Power Instrumentation Technical Specifications (Tac No. MB5384)
ML0234300622002-12-0404 December 2002
Technical Specifications, Increase Maximum Steady-state Core Power Level from 2544 Megawatts Thermal (Mwt) to 2568 Mwt
ML0220302412002-07-16016 July 2002
Technical Specification Pages, Amendment No. 204 Re Table 3.3.1-1 (Page 1 of 1), Reactor Protection System Instrumentation
3F0602-01, License Amendment Request 273, Revision 0 - Emergency Diesel Generator Diesel (EDG) Loss of Power Start.2002-06-13013 June 2002
License Amendment Request #273, Revision 0 - Emergency Diesel Generator Diesel (EDG) Loss of Power Start.
2021-10-13
[Table view] |
Text
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:
2.C.(1) Maximum Power Level Florida Power Corporation is authorized to operate the facility at a steady state reactor core power level not in excess of 2568 Megawatts (100 percent of rated -core power level).
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 224, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment 149. The Surveillance Requirements shall be successfully demonstrated prior to the time and condition specified below for each.
a) SR 3.3.8.2.b shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.
b) SR 3.3.11.2, Function 2, shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.
c) SR3.3.17.1, Functions 1, 2, 6, 10, 14, & 17 shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.
d) SR3.3.17.2, Function 10 shall be successfully demonstrated prior to entering MODE 3 on the first plant start-up following Refuel Outage 9.
e) SR 3.6.1.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.
f) SR 3.7.12.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.
g) SR 3.8.1.10 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.
h) SR 3.8.3.3 shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.
Amendment No. 3, 41, 149, 205, 223 224
LCO Applicability LCO 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7 and LCO 3.0.8.
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
LCO 3.0.3 When an LCO is not met, except as provided in the associated ACTIONS, and an associated ACTION is not met or provided, the unit shall be placed in a MODE or other specified condition in which the Specification is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a. MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;
- b. MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and
- c. MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.
LCO 3.0.4 When an LCO is not met, entry into a MODE or other
.. ..... ....... .. sleci fi e-d-c ndi ti hW -hI- i-~ il -t -hy *n* b 7 made:
- a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; or
. . -(continued)'
Crystal River Unit 3 3.0-1 Amendment No.224
LCO Applicability LCO 3.0 3.0 LCO APPLICABILITY LCO 3.0.6 When a support system's Required Action directs a supported (continued) system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.
LCO 3.0.7 PHYSICS TESTS Exception LCOs (Specification 3.1.8 and 3.1.9) allow specified Technical Specifications (TS) requirements to be suspended to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with PHYSICS TESTS Exception LCOs is optional. When a PHYSICS TEST Exception LCO is desired to be met but is not met, the ACTIONS of the PHYSICS TESTS Exception LCO shall be met.
When a PHYSICS TEST Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with other applicable Specifications.
LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:
- a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.
Crystal River Unit 3 3.0-3 Amendment No.224
