Letter Sequence Approval |
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TAC:MB7497, 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
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Text
2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (continued) 2.1.6 Pressurizer and Main Steam Safety Valves Applicability Applies to the status of the pressurizer and main steam safety valves.
Objective To specify minimum requirements pertaining to the pressurizer and main steam safety valves.
Specifications To provide adequate overpressure protection for the reactor coolant system and steam system, the following safety valve requirements shall be met:
(1) Two pressurizer safety valves shall be OPERABLE in MODES 1 and 2, with lift settings of 2485 psig +1%I-3% and 2530 psig +1%I-3% respectively.
(2) Whenever there is fuel in the reactor, and the reactor vessel head is installed, a minimum of one OPERABLE safety valve shall be installed on the pressurizer. However, when in at least the COLD SHUTDOWN condition, safety valve nozzles may be open to containment atmosphere during performance of safety valve tests or maintenance to satisfy this specification.
(3) At least four of the five Main Steam Safety Valves (MSSVs) associated with each steam generator shall be OPERABLE in MODES I and 2. Lift settings shall be at 985 psig +3/-2%,
1000 psig +3/-2%, 1010 psig +3/-2%, 1025 psig +31-2%, and 1035 psig +31-2%.t"
- a. With less than four of the five MSSVs associated with each steam generator OPERABLE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(4) Two power-operated relief valves (PORVs) shall be OPERABLE during heatups and cooldowns when the RCS temperature is less than 515 0F, and in MODES 4 and 5 whenever the head is on the reactor vessel and the RCS is not vented through a 0.94 square inch or larger vent, to prevent violation of the pressure-temperature limits designated by Figure 2-1.
- a. With one PORV inoperable during heatups and cooldowns when the RCS temperature is less than 515 0 F, restore the Inoperable PORV to OPERABLE within 7 days or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and depressurize and vent the RCS through at least a 0.94 square inch or larger vent within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- b. With both PORVs inoperable during heatups and cooldowns when the RCS temperature is less than 515"F, be In COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and depressurize and vent the RCS through at least a 0.94 square inch or larger vent within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- c. With one PORV Inoperable in MODES 4 or 5, within one hour ensure the pressurizer steam space is greater than 53% volume (50.6% or less actual level) and restore the inoperable PORV to OPERABLE within 7 days. If adequate steam space cannot be established within one hour, then restore the inoperable PORV to OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the PORV cannot be restored in the required time, depressurize and vent the RCS through at least a 0.94 square inch or larger vent within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
2-15 Amendment No. 39,47,54,146,161, 189,-67, 219
2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (continued) 2.1.6 Pressurizer and Main Steam Safety Valves (continued)
- d. With both PORVs inoperable in Modes 4 or 5 depressurize and vent the RCS through at least a 0.94 square inch or larger vent within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
(5) Two power-operated relief valves (PORVs) and their associated block valves shall be operable in Modes 1, 2, and 3.
- a. With one or both PORV(s) inoperable because of excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to operable status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- b. With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore PORV to operable status or close its associated block valve and remove power from the block valve; restore the PORV to operable status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN with the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- c. With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to operable status or close both block valves, remove power from the block valves, and be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- d. With one or both block valve(s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve(s) to operable status or place the associated PORV(s) in the closed position. Restore at least one block valve to operable status within the next hour if both block valves are inoperable; restore the remaining inoperable block valve to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Otherwise, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Basis The purpose of the two spring-loaded Pressurizer Safety Valves (PSV's) is to provide Reactor Coolant System (RCS) overpressure protection and thereby ensure that the Safety Limit for RCS pressure (i.e., 2750 psia) is not exceeded for analyzed accidents. The maximum RCS pressure transient for an analyzed accident is associated with a Loss of Load event(2 ).
The TS 2.1.6(1) lift settings are determined during Surveillance Testing in accordance with ASME Code test methods. The ASME Code requires that valves in steam service use steam as the test medium for establishing the setpoint. The +1%/-3% tolerance range specified in TS 2.1.6(1) applies to opening pressures determined during Surveillance Testing. When the valves are installed in the system, the presence of a water-filled loop seal at the valve inlets may result in in-situ actuation at a pressure that differs from the actuation pressure with steam at the inlet.
Comparative testing and analysis indicates that with a loop seal present, the opening pressure of these valves may be up to 1% lower than the opening pressure under normal test conditions.
Opening pressures below the specified setpoints are not a concern with respect to the safety limit for RCS pressure. Analysis of a loss of load case involving elevated PSV opening pressures indicated that RCS pressures remained below the 2750 psia Safety Limit with PSV opening pressures upon to 6% above the nominal setpoints. The valves are set to a tolerance of +/-1% of setpoint using ASME Code test methods before being returned to service after testing. This allows for some setpoint variance over the surveillance interval.
The power-operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency power source to ensure the ability to seal this possible RCS leakage path.
2-15a Amendment No. 54,%65,16+1,j69,219
TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Feguncy Reference
- 1. Control Element Drop times of all full-length CEA's Prior to reactor criticality after each 7.5.3 Assemblies removal of the reactor vessel closure head
- 2. Control Element Partial movement of all CEA's Q 7 Assemblies (Minimum of 6 in)
- 3. Pressurizer Safety Verify each pressurizer safety valve R 7 I Valves is OPERABLE in accordance with I the Inservice Testing Program. I Following testing, lift settings shall I be 2485 psig *1% and 2530 psig i1% I respectively. I
- 4. Main Steam Safety Set Point R 4 Valves
- 5. DELETED
- 6. DELETED
- 7. DELETED
- 8. Reactor Coolant Evaluate D* 4 System Leakage
- 9. Diesel Fuel Supply Fuel Inventory D 8.4 1Oa. Charcoal and HEPA 1. In-Place Testing" 9.10 Filters for Control Charcoal adsorbers and HEPA On a rel lueling frequency or every 720 Room filter banks shall be leak hours ol fsystem operation or after each tested and show >99.95% complet e or partial replacement of the Freon (R-1 I or R-1 12) and charcoa I adsorber/HEPA filter banks, or cold DOP particulates after an) Vmajor structural maintenance on removal, respectively. the systie-m housing or following significant painting , fire or chemical releases in a ventilatiNion zone communicating with the system.
- Whenever the system is at or above operating temperature and pressure.
Tests shall be performed in accordance with applicable section(s) of ANSI N510-1980.
3-20 Amendment No. 15,24,128,16O,166,169,171,219
5.0 ADMINISTRATIVE CONTROLS 5.9 Reportina Requirements (Continued)
- b. Annual Occupational Exposure Report. An annual occupational exposure report shall be submitted on or before April 30 of each year. The report shall consist of a tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functionsF e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling outages. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
- c. Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, with a copy to the appropriate Regional Office, no later than the fifteenth of each month following the calendar month covered by the report.
5.9.2 ReDortable Event A Licensee Event Report (LER) shall be submitted to the U.S. Nuclear Regulatory Commission for any event meeting the requirements of 10 CFR Part 50.73.
5.9.3 Soecial Reports Special reports shall be submitted to the appropriate NRC Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification where appropriate:
- a. In-service inspection report, reference 3.3.
- b. Tendon surveillance, reference 5.21.
- c. Containment structural tests, reference 3.5.
- d. DELETED
- e. DELETED
- f. DELETED
- g. Materials radiation surveillance specimens reports, reference 3.3.
- h. DELETED
- i. Post-accident monitoring instrumentation, reference 2.21
- j. Electrical systems, reference 2.7(2).
2I This tabulation supplements the requirements of § 20.2206 of 10 CFR Part 20.
5-7 Amendment No. 9,24,35,26,46,7S,66,86,99,
-;'~~~~~~~~~~~~~~~ i 0, 1 , 19, 'I33, i4:7, i 2,i 57,160,164,185,202-,21,21 9