Letter Sequence Other |
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TAC:MB6469, Missed Surveillance Requirements, Incorporate CEOG Topical Report to Eliminate Pressure Sensor Response Time Testing (Approved, Closed) |
Results
Other: ML021280278, ML022940186, ML030780605, ML031210545, ML031290602, ML031400506, ML031410096, ML031410107, ML031410212, ML031960625, ML032300003, ML032300305, ML032310200, ML032310213, ML032530228, ML032960189
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MONTHYEARML0205206542002-02-25025 February 2002 Order Attachment 1 - Addressee List - Order for Interim Safeguards and Security Compensatory Measures Project stage: Request ML0205002282002-02-25025 February 2002 Issuance of Order for Interim Safeguards and Compensatory Security Measures Project stage: Approval ML0212802782002-05-22022 May 2002 Reply to Response to Order for Interim Safeguards and Security Compensatory Measures Project stage: Other ML0229401862002-10-25025 October 2002 Biweekly Notice Memo, Notice of Consideration, Testing Prestressed Concrete Containment Tendons Project stage: Other ML0302201532003-01-16016 January 2003 Technical Specification Pages for Amendment 215 Missed Surveillances and Adoption of a Technical Specification Bases Control Program Project stage: Acceptance Review ML0229504532003-01-16016 January 2003 Issuance of License Amendment No. 215, Missed Surveillances & Adoption of Technical Specification Bases Control Program Project stage: Approval ML0305902712003-02-26026 February 2003 Technical Specifications, Relocation of TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report Project stage: Acceptance Review ML0306307272003-02-26026 February 2003 Issuance of Amendment No. 216, Relocating TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report Project stage: Approval ML0305803512003-02-27027 February 2003 Correction to Amendment No. 215 to Fort Calhoun, Station No. 1. Page 5-17 of Technical Specifications Omitted Reference to SR 3.0.5. Corrected TS Page Encl Project stage: Acceptance Review ML0307806052003-03-18018 March 2003 Pressure-Temperature Limit Report Submittal Project stage: Other ML0308402732003-03-24024 March 2003 RAI, Related to Integrated Leak Rate Test Surveillance Interval Project stage: RAI LIC-03-0052, Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request2003-04-10010 April 2003 Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request Project stage: Request LIC-03-0055, Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-04-11011 April 2003 Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request Project stage: Response to RAI ML0312004872003-04-29029 April 2003 Issuance of Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days Project stage: Approval ML0312105452003-04-29029 April 2003 Tech Spec Pages for Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days Project stage: Other ML0312906022003-05-0808 May 2003 Tech Spec Pages for Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii Project stage: Other ML0312900812003-05-0808 May 2003 Issuance of Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii Project stage: Approval ML0314102122003-05-20020 May 2003 Thesis (Miscellaneous Report - 134 Pages), Fort Calhoun, S107100 Project stage: Other ML0314005062003-05-20020 May 2003 Ltr RELAP5/MOD3.3 Prediction and Model Simulation Project stage: Other ML0314100962003-05-20020 May 2003 Description/Model Simulation (Technical Paper - 5 Pages), Fort Calhoun, S107101 Project stage: Other ML0314101072003-05-20020 May 2003 Listing (Report, Technical - 3 Pages), Fort Calhoun, S107102 Project stage: Other ML0314103762003-05-21021 May 2003 Request for Additional Information Pressure-Temperature Limit Report Submittal (Tac. MB6468) Project stage: RAI LIC-03-0079, Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-05-21021 May 2003 Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request Project stage: Supplement ML0316800102003-06-17017 June 2003 Request for Additional Information, Use of the Gothic (Version 7.0) Computer Program Project stage: RAI ML0319606252003-07-11011 July 2003 Correction to Amd. 218 for the Fort Calhoun Station, Unit No. 1 (Tac. MB7498) Project stage: Other ML0320202182003-07-18018 July 2003 Ltr Environmental Assessment Relating to Exemption from the Requirements of Appendix G to 10 CFR Part 50 Project stage: Approval ML0320902422003-07-25025 July 2003 Unit 1, License Amendment 219 Modifying Technical Specification 2.1.6 Project stage: Approval ML0321004542003-07-25025 July 2003 Unit 1, Tech Spec Pages for License Amendment 219 Modifying Technical Specification 2.1.6 Project stage: Approval ML0323102002003-08-15015 August 2003 Tech Spec Pages for Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis Project stage: Other ML0323102132003-08-15015 August 2003 Tech Spec Page to License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing Project stage: Other ML0323003052003-08-15015 August 2003 License Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis Project stage: Other ML0323000032003-08-15015 August 2003 License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing Project stage: Other ML0325302282003-09-0404 September 2003 Ft.Calhoun, Closeout Letter - Response to Order for Compensatory Measures Related to Access Authorization Project stage: Other ML0329601892003-10-23023 October 2003 Reply to Response to Order for Fitness-For-Duty Enhancements for Nuclear Security Force Personnel Project stage: Other ML0331002902003-11-0505 November 2003 Unit #1, Issuance of Amendment 222, Authorizing Revisions to the Updated Safety Analysis Report to Incorporate the NRC Approval of the Gothic 7.0 Computer Program for Performing Containment Analysis, (Tac. MB7496) Project stage: Approval 2003-04-10
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Category:Technical Specifications
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors LIC-15-0076, License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2015-09-11011 September 2015 License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. LIC-15-0085, License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item.2015-09-11011 September 2015 License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item. LIC-15-0053, License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes2015-08-20020 August 2015 License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 LIC-14-0128, License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements2014-11-0707 November 2014 License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14115A2972014-04-10010 April 2014 Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML14041A4082014-02-10010 February 2014 License Amendment Request (LAR) 14-01, One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3 ML14108A0442013-12-31031 December 2013 Omaha Public Power District Fort Calhoun Station Unit Radiological Environmental Operating Report for Technical Specification Section 5.94.b January 1, 2013 to December 31, 2013 ML14108A0422013-12-31031 December 2013 Omaha Public Power District Fort Calhoun Station Unit No. 1 - Annual Report for Technical Specification Section 5.94.a January 1, 2013 to December 31, 2013 ML12128A1702012-04-12012 April 2012 Technical Specification (TS) Basis Change Index, Page 2 of 2 and TS 2.10 - Page 18 LIC-12-0006, License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)2012-02-10010 February 2012 License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO) LIC-12-0052, Annual Report for Technical Specification Section 5.9.4a2011-12-31031 December 2011 Annual Report for Technical Specification Section 5.9.4a LIC-10-0034, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.2010-07-12012 July 2010 License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c. LIC-10-0043, Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication2010-06-0101 June 2010 Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication ML0935611192010-01-22022 January 2010 Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications ML0925405912009-10-0909 October 2009 License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip ML0912502752009-05-0505 May 2009 Replacement Page TS 2.1 - Page 8, License Amendment Request for Administrative Revisions ML0907108912009-03-27027 March 2009 License Amendment, Issuance of Amendment No. 258, Revise Limiting Condition for Operation 2.7(2)j in TS 2.7, Electrical Systems, to Clarify Allowed Outage Time for Emergency Diesel Generators ML0911703682009-02-18018 February 2009 Updated Tech Spec Pages, from Licensee, License Amendment Request Lic 08-0078, Administrative Revisions to the Technical Specifications to Correct Typographical Errors and Provide Clarification LIC-09-0008, License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-01-30030 January 2009 License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. LIC-08-0074, License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)2008-07-31031 July 2008 License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT) LIC-08-0049, License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time2008-04-22022 April 2008 License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time LIC-08-0008, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System.2008-02-0505 February 2008 License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System. LIC-07-0084, License Amendment Request, Change to Diesel Generator Surveillance Testing.2007-10-0505 October 2007 License Amendment Request, Change to Diesel Generator Surveillance Testing. LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent.2007-09-11011 September 2007 License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent. LIC-07-0046, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-05-16016 May 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707100982007-04-0303 April 2007 Technical Specifications, Editorial Changes to Apply Certain Limiting Conditions for Operation Requirements ML0705905082007-02-28028 February 2007 License and Technical Specification Pages - Amendment No. 248 to Facility Operating License Relocation of T.S. 2.22, Toxic Gas Monitors, and T.S. Table 3-3, Item 29 to Updated Safety Analysis Report LIC-06-0146, License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process.2006-12-20020 December 2006 License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process. LIC-06-0147, License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications2006-12-20020 December 2006 License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications ML0631105582006-11-0707 November 2006 Technical Specifications, Revising TS Steam Generator Tube Suveillance Program ML0631202592006-10-27027 October 2006 Tech Spec Pages for Amendment 244 Modifications to Technical Specification 2.4, Containment Cooling to Reduce Operable Containment Spray Pumps ML0628604282006-10-10010 October 2006 Response to Request for Additional Information (RAI) Related to the Replacement of Trisodium Phosphate ML0624201602006-08-30030 August 2006 Tech Spec Pages for Amendment 241 Regarding Use of M5 Fuel Cladding ML0624304022006-08-30030 August 2006 Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a Steam Generator.. ML0624301302006-06-27027 June 2006 Tech Spec Pages for Amendment 240 Deletion of Design Features in Technical Specifications 4.3.1.2b and 4.3.1.2c LIC-06-0063, Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements.2006-06-0202 June 2006 Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements. 2024-01-31
[Table view] |
Text
2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System Applicability Applies to the operating status of the emergency core cooling system.
Objective To assure operability of equipment required to remove decay heat from the core.
Specifications (1) Minimum Requirements The reactor shall not be made critical unless all of the following conditions are met:
- a. The SIRW tank contains not less than 283,000 gallons of water with a boron concentration of at least the refueling boron concentration at a temperature not less than 50 0F.
- b. One means of temperature indication (local) of the SIRW tank is operable.
- c. All four safety injection tanks are operable and pressurized to at least 240 psig with a tank level of at least 116.2 inches (67%) and a maximum level of 128.1 inches (74%) with refueling boron concentration.
- d. One level and one pressure instrument is operable on each safety injection tank.
- e. One low-pressure safety injection train is operable on each associated 4,160 V engineered safety feature bus.
- f. One high-pressure safety injection pump is operable on each associated 4,160 V engineered safety feature bus.
- g. Both shutdown heat exchangers are operable.
- h. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the reactor coolant system.
- i. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable. HCV-2914, 2934, 2974, and 2954 shall have power removed from the motor operators by locking open the circuit breakers in the power supply lines to the valve motor operators FCV-326 shall be locked open.
2-20 Amendment No. 17,32,43,103,117, 4 493 3AA4AA5 7A1t75, 217
2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)
(2) Modification of Minimum Requirements During power operation, the Minimum Requirements may be modified to allow one of the following conditions to be true at any one time. If the system is not restored to meet the minimum requirements within the time period specified below, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the minimum requirements are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- a. One low-pressure safety injection train may be inoperable provided the train is restored to operable status within seven (7) days.
- b. One high-pressure safety injection pump may be inoperable provided the pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. One shutdown heat exchanger may be inoperable for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Any valves, interlocks or piping directly associated with one of the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as listed for that component.
- e. Any valve, interlock or piping associated with the safety injection and shutdown cooling system which is not covered under d. above but which is required to function during accident conditions may be inoperable for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- f. One safety injection tank may be inoperable for reasons other than g. or h. below for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- g. Level and/or pressure instrumentation on one safety injection tank may be inoperable for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- h. One safety injection tank may be inoperable due to boron concentration not within limits for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- i. Components in excess of those allowed by Conditions a, b, d, and e may be inoperable provided they are returned to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> when performing the quarterly recirculation actuation logic channel functional test (Table 3-2 item 20) under administrative controls. This allowance applies only to the remaining portion of Cycle 20 and all of Cycle 21.
2-21 Amendment No. 49,171,175,186, 208,217
2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)
The USAR Loss of Coolant Accident analysis assumes a minimum SIRW tank inventory of 250,000 gallons has been pumped from the SIRW tank when recirculation begins. Technical Specification 2.3(1) requires that the SIRW tank contains a minimum of 283,000 gallons of usable water. This additional volume over that assumed in the USAR analysis provides sufficient margin to account for instrument uncertainty. The SIRW tank contains water containing a boron concentration of at least the refueling boron concentration. This is sufficient boron concentration to provide a shutdown margin of 5%, including allowances for uncertainties, with all control rods withdrawn and a new core at a temperature of 68'F.(2 )
The limits for the safety injection tank pressure and volume assure the required amount of water injection during an accident and are based on values used for the accident analyses. The minimum 116.2 inch level corresponds to a volume of 825 ft3 and the maximum 128.1 inch level corresponds to a volume of 895.5 ft3. Prior to the time the reactor is brought critical, the valving of the safety injection system must be checked for correct alignment and appropriate valves locked. Since the system is used for shutdown cooling, the valving will be changed and must be properly aligned prior to start-up of the reactor.
The operable status of the various systems and components is to be demonstrated by periodic tests. A large fraction of these tests will be performed while the reactor is operating in the power range.
If a component is found to be inoperable, it will be possible in most cases to effect repairs and restore the system to full operability within a relatively short time. For a single component to be inoperable does not negate the ability of the system to perform its function. If it develops that the inoperable component is not repaired within the specified allowable time period, or a second component in the same or related system is found to be inoperable, the reactor will initially be put in the hot shutdown condition to provide for reduction of cooling requirements after a postulated loss-of-coolant accident. This will also permit improved access for repairs in some cases. After a limited time in hot shutdown, if the malfunction(s) is not corrected, the reactor will be placed in the cold shutdown condition utilizing normal shutdown and cooldown procedures. In the cold shutdown condition, release of fission products or damage of the fuel elements is not considered possible.
The plant operating procedures will require immediate action to effect repairs of an inoperable component and therefore in most cases repairs will be completed in less than the specified allowable repair times. The limiting times to repair are intended to assure that operability of the component will be restored promptly and yet allow sufficient time to effect repairs using safe and proper procedures.
The time allowed to repair a safety injection tank is based on the deterministic and probabilistic analyses of Reference (8). The time allowed to repair a LPSI train is based on the deterministic and probabilistic analyses of Reference (9). These analyses concluded that the overall risk impact of the completion times are either risk-beneficial or risk neutral.
The requirement for core cooling in case of postulated loss-of-coolant accident while in the hot shutdown condition is significantly reduced below the requirements for a postulated loss-of-coolant accident during power operation. Putting the reactor in the hot shutdown condition reduces the consequences of a loss-of-coolant accident and also allows more free access to some of the engineered safeguards components in order to effect repairs.
Failure to complete repairs within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of going to the hot shutdown condition is considered indicative of a requirement for major maintenance and, therefore, in such a case, the reactor is to be put into the cold shutdown condition.
2-23 Amendment No. 32,39,47,49,74,179,186,217 July 15, 1999
2.0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)
Components in excess of those allowed by Conditions a, b, d, and e may be inoperable provided they are returned to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> when performing the quarterly recirculation actuation logic channel functional test (Table 3-2 item 20) under administrative controls. This allowance applies only to the remaining portion of Cycle 20 and all of Cycle 21. This prevents violating Technical Specifications or necessitating a unit shutdown due to inability to perform the quarterly recirculation actuation logic channel functional test. These administrative controls consist of stationing three dedicated operators at the Engineered Safeguards Features (ESF) panel controls in the control room. In this way, the following conditions are maintained and actions can be rapidly performed should a valid ESF actuation occur:
- the appropriate Safety Injection Refueling Water Tank (SIRWT) to Safety Injection (SI) and Containment Spray (CS) pumps suction valve control switch is maintained in the OPEN position (spring-return switch),
- the appropriate SI and CS pumps to SIRWT recirculation minimum flow valve control switch is maintained in the OPEN position (spring-return switch),
- the appropriate Recirculation Actuation Signal (RAS) lockout relays and initiating signal can be rapidly reset,
- the appropriate SI and CS pumps to SIRWT recirculation minimum flow valve control switch can be rapidly returned to the AUTO position,
- the appropriate SIRWT to SI and CS pumps suction valve control switch can be rapidly returned to the AUTO position, and
- the appropriate Containment Sump to SI and CS pumps suction valve control switch can be rapidly returned to the AUTO position.
The appropriate SI and CS pumps to SIRWT recirculation minimum flow valve control switch and the appropriate SIRWT to SI and CS pumps suction valve control switch are held in the OPEN position during the test to enhance the reliability of the appropriate SI and CS pumps by maintaining the associated valves open.
References (1) USAR, Section 14.15.1 (2) USAR, Section 6.2.3.1 (3) USAR, Section 14.15.3 (4) USAR, Appendix K (5) Omaha Public Power District's Submittal, December 1, 1976 (6) Technical Specification 2.1.2, Figure 2-1B (7) USAR, Section 4.4.3 (8) CE NPSD-994, "CEOG Joint Applications Report for Safety Injection Tank AOT/SIT Extension," May 1995.
(9) CE NPSD-995, "CEOG Joint Applications Report for Low Pressure Safety Injection System AOT Extension," May 1995.
2-23b Amendment No. 47,64,74,179,206,217