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MONTHYEAR3F0304-09, Proposed License Condition for License Amendment Request 280, Revision 0, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System2004-03-25025 March 2004 Proposed License Condition for License Amendment Request #280, Revision 0, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System Project stage: Request 3F0404-11, Modified Proposed License Condition, License Amendment Request 280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System2004-04-27027 April 2004 Modified Proposed License Condition, License Amendment Request #280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System Project stage: Request ML0414101442004-05-18018 May 2004 Tech Spec Pages for Amendment 212 Regarding the Nuclear Services Seawater System Project stage: Other ML0414101392004-05-18018 May 2004 Tech Spec Pages Amendment 212 Regarding the Nuclear Services Seawater System Project stage: Other ML0414002822004-05-18018 May 2004 License Amendment 212 Regarding the Nuclear Services Seawater System Project stage: Approval 2004-04-27
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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
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-5a-2.C.(13) During the one-time extended allowed outage time for work on Nuclear Services Seawater System Emergency Pump RWP-2B, authorized in Improved Technical Specification (ITS) 3.7.9, CR-3 will implement the following compensatory measures:
(a) No elective maintenance will be scheduled on other related risk sensitive equipment beyond that required for the refurbishment activity of RWP-2B that could degrade the risk profile of the plant. For these purposes, the systems are: Nuclear Services and Decay Heat Seawater System, Decay Heat System, Decay Heat Closed Cycle Cooling Water System, Nuclear Services Closed Cycle Cooling Water (SW), Emergency Diesel Generators, Chilled Water, Emergency Feedwater System, Emergency Feedwater Initiation and Controls System (EFIC) Auxiliary Feedwater Pump and Makeup System.
(b) Makeup Pump configurations will be selected to minimize risk.
(c) Increased operator attention will be focused on loss/restoration of RW/SW/ redundant train and the Appendix R Chiller. This will be accomplished by on shift operating crew review of Abnormal Procedure (AP)-330, Loss of Nuclear Service Cooling.
(d) Operator attention will be focused on potential use of non-safety grade Feedwater Pump FWP-7 and its dedicated Diesel Generator (MTDG-1).
This will be accomplished by on shift operating crew review of Emergency Operating Procedure (EOP)-14, Enclosure 7, Emergency Feedwater Pump (EFWP) Management.
(e) Daily operator walkdowns of the redundant train of RW/SW/Pumps and associated power supply switchgear will be conducted.
(f) No elective maintenance to be scheduled in the switchyard that would challenge the availability of offsite power to the ES Buses or to the Bus for RWP-1.
(g) Hourly roving fire watches will be established in fire zones identified as containing circuits required for RWP-1 or RWP-2A to minimize fire risk in these areas. Those fire zones are: AB-95-3AA, AB-95-3B, AB-95-3E, AB-95-3F, AB-95-3G, AB-95-3K, AB-95-3T, AB-95-3U, AB-95-3W, AB 3X, AB-95-3Z, CC-108-102, CC-108-104, CC-108-105, CC-108-106, CC-108-108, CC-1 08-109, CC-1 08-110, CC-1 24-111, CC-1 24-116, CC-1 24-i1 7, CC-1 34-118A, IB-95-200C, lB-1 19-201 B, TB-i 19-400E, TB-1 19-403, TB-95-400A, TB-95-401, AB-1 19-6 and AB-1 19-6A.
(h) Prior to entering the Allowed Outage Time for rebuild of RWP-2B, fire zones containing circuits for either RWP-1 or RWP-2A will be walked down to identify and minimize transient combustibles not related to ongoing approved work. Hourly roving fire watches will be charged with continuing to monitor for the presence of transient combustible materials until RWP-2B is returned to service.
Amendment No. 212
- 5b -
(i) For the risk significant fire zones containing circuits for both RWP-1 and RWP-2A, the following additional compensatory measures will be established which address the specific risk factors in each zone. No additional compensatory measures beyond roving fire watches will be established for fire zones that contain circuits for all three pumps (RWP-1, RWP-2A and RWP-2B).
Fire Zone CC-108-108 A continuous Fire Brigade Qualified fire watch will be stationed in the fire area except while 41 60V breaker manipulations are being performed. The individual's turnout gear will be available in the adjacent area where a fire hose station is also located equipped with an electrically safe fog nozzle.
Fire Zone AB-95-3W The Waste Transfer Pumps will only be operated when there is a qualified fire watch in the immediate vicinity of the operating pump equipped with a radio and fire extinguisher. No hot or spark producing work will be conducted. A roving hourly fire watch will observe this zone.
Fire Zone AB-95-3E The operating makeup pump will be selected based on minimizing the risk from internal events as a result of redundancy in its cooling water source.
No hot or spark producing work will be conducted. Roving hourly fire watches will be conducted.
Fire Zone AB-95-3AA The operating makeup pump will be selected based on minimizing the risk from internal events as a result of redundancy in its cooling water source.
No hot or spark producing work will be conducted. Roving hourly fire watches will be conducted.
Fire Zone AB-95-3F The operating makeup pump will be selected based on minimizing the risk from internal events as a result of redundancy in its cooling water source.
No hot or spark producing work will be conducted. Roving hourly fire watches will be conducted.
Fire Zone AB-95-3T The portion of the fire zone that can be locked will be locked and the keys will be administratively controlled. Entries will be limited to only operationally necessary activities and require inspection for transient combustible materials upon exit. The portion of the zone that cannot be locked will be observed by the roving fire watch. No hot or spark producing work will be conducted.
Fire Zone AB-95-3U The portion of the fire zone that can be locked will be locked and the keys will be administratively controlled. Entries will be limited to only operationally necessary activities and require inspection for transient combustible materials upon exit. The portion of the zone that cannot be locked will be observed by the roving fire watch. No hot or spark producing work will be conducted.
Amendment No. 212
- 5c - I 2.D Physical Protection.
The licensee shall fully implement and maintain in effect all
- provisions of the Commission-approved physical security, guard 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 plans, which contain
'- Safeguards Information protected under 10 CFR 73.21, are entitled:
0 co 1T.
"Crystal River Nuclear Power Plant, Unit 3, Modified Amended Security Plan," with revisions submitted through April 14, 1988; 'Crystal River Nuclear Power Plant, Unit 3, Security Training and Quali-fication Plan," with revisions submitted through July.29, 1987; and "Crystal River Nuclear Power Plant, Unit 3, Safeguards Contingency Plan," with revisions submitted through July 23, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
a.D.(')"Crystal River Nuclear Plant Unit 3 Security Training1981, and sub-Qualification Plan", Revision 3, dated Deceirber 30, mitted by letter dated March 19, 1982, and consisting of all previous revisions. This plan shall be followed in accordance with 10 CFR 73.55(b)(4), 60 days after approval by the Commission. Of d0IR
'Arnd 4' All security personnel, as required in the above plans, shall be qualified within two years of this approval. The licensee may make changes to this plan without prior Commission approval if the changes do not decrease the safeguards effectiveness of the plan.
The licensee shall maintain records of and submit reports concerning such changes in the same manner as required for changes made to the
Ah hitr lb. -f4, 212