Letter Sequence Other |
|---|
|
|
MONTHYEARML0314907222003-05-29029 May 2003
Request for Additional Information, New Departure from Nucleate Boiling Correlation
Project stage: RAI
3F0703-08, Response to Request for Additional Information Regarding Technical Specification Change Request for New Departure from Nucleate Boiling Correlation2003-07-15015 July 2003
Response to Request for Additional Information Regarding Technical Specification Change Request for New Departure from Nucleate Boiling Correlation
Project stage: Response to RAI
3F0703-14, Non-Proprietary Version to Response to Request for Additional Information Regarding Technical Specification Changes Request for New Departure from Nuclear Boiling Correlation2003-07-31031 July 2003
Non-Proprietary Version to Response to Request for Additional Information Regarding Technical Specification Changes Request for New Departure from Nuclear Boiling Correlation
Project stage: Response to RAI
3F1003-05, Supplemental Information and Proposed License Condition for License Amendment Request No. 277, Revision 0, Bhtp Departure from Nucleate Boiling Correlation.2003-10-0101 October 2003
Supplemental Information and Proposed License Condition for License Amendment Request No. 277, Revision 0, Bhtp Departure from Nucleate Boiling Correlation.
Project stage: Supplement
ML0329304352003-10-16016 October 2003
Issuance of Amendment No. 211, Revising Improved Technical Specification 2.1.1 Which Provides Departure from Nucleate Boiling Safety Limits
Project stage: Approval
ML0329503392003-10-16016 October 2003
Technical Specification for Crystal River, Unit 3, Amendment No. 211
Project stage: Other
ML0330700492003-11-0303 November 2003
Framatome Anp, Inc. Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
2003-11-03
[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
2.C.(6) Deleted per Amendment No. 21, 7-3-79 2.C.(7) Prior to startup following the first regularly scheduled refueling outage, Florida Power Corporation shall modify to the satisfaction of the Commission, the reactor coolant system flow indication to meet the single failure criterion with regard to pressure sensing lines to the flow differential pressure transmitters.
2.C.(8) Within three months of issuance of this license, Florida Power Corporation shall submit to the Commission a proposed surveillance program for monitoring the containment for the purpose of determining any future delamination of the dome.
2.C.(9) Fire Protection Florida Power Corporation shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27,1979, January 22,1981, January 6,1983, July 18, 1985 and March 16, 1988, subject to the following provisions:
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.
2.C.(10) The design of the reactor coolant pump supports need not include consideration of the effects of postulated ruptures of the primary reactor coolant loop piping and may be revised in accordance with Florida Power Corporation's amendment request of April 24,1986.
2.C.(11) A system of thermocouples added to the decay heat (DH) drop and Auxiliary Pressurizer Spray (APS) lines, capable of detecting flow initiation, shall be operable for Modes 4 through 1. Channel checks of the thermocouples shall be performed on a monthly basis to demonstrate operability. If either the DH or APS system thermocouples become inoperable, operability shall be restored within 30 days or the NRC shall be informed, in a Special Report within the following fourteen (14) days, of the inoperability and the plans to restore operability.
2.C.(12) Florida Power Corporation shall assure that the Cycle 14 core for CR-3 is designed using the methods specified in and operated within the Core Operating Limits Report limits developed from Topical Reports BAW-1 01 64P-A, Revision 4, and BAW-1 0241 P.
Revision 0, in addition to those methods allowed by Improved Technical Specification 5.6.2.18.
Amendment No. 211
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1. Reactor Core SLs 2.1.1.1 In MODES 1 and 2, the maximum local fuel pin centerline temperature shall be 5080 - (6.5 E-3) X (Burnup MWD/MTU)OF. Operation within this limit is ensured by compliance with the AXIAL POWER IMBALANCE protective limits preserved by the Reactor Protection System setpoints in LCO 3.3.1, "Reactor Protection System (RPS)
Instrumentation," as specified in the COLR.
2.1.1.2 In MODES 1 and 2, the departure from nucleate boiling ratio DNBR) shall be maintained greater than the limits of 1.3 for the BAW-2 correlation, 1.18 for the BWC correlation and 1.132 for the BHTP correlation.
Operation within this limit is ensured by compliance with SL 2.1.1.3 and with the AXIAL POWER IMBALANCE protective limits preserved by the RPS setpoints in LCO 3.3.1, as specified in the COLR.
2.1.1.3 In MODES 1 and 2, Reactor Coolant System (RCS) core outlet temperature and pressure shall be maintained above and to the left of the SL shown in Figure 2.1.1-1.
2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained
2.2 SL Violations The following actions shall be completed:
2.2.1 In MODE 1 or 2, if SL 2.1.1.1, SL 2.1.1.2 or SL 2.1.1.3 is violated, be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 In MODE 1 or 2, if SL 2.1.2 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Crystal River Unit 3 2.0-1 Amendment No. 211
