Letter Sequence Other |
---|
TAC:MB7498, 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
|
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
[Table View] |
|
---|
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
1.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.3 LimitinQ Safety System Settings. Reactor Protective System Applicability This specification applies to RPS Limiting Safety System settings and bypasses for instrument channels.
Objective To provide for automatic protection action in the event that the principal process variables approach a safety limit.
Specification The reactor protective system trip setting limits and the permissible bypasses for the instrument channels shall be within the Limiting Safety System Setting as stated in Table 1-1.
Basis The reactor protective system consists of four instrument channels to monitor selected plant conditions which will cause a reactor trip if any of these conditions deviate from a preselected operating range to the degree that a safety limit may be reached.
(1) High Power Level - A reactor trip at high power level (neutron flux) is provided to prevent damage to the fuel cladding resulting from some reactivity excursions too rapid to be detected by pressure and temperature measurements (in addition, thermal signals are provided to the high power level trip unit as a backup to the neutron flux signal).
During normal plant operation, with all reactor coolant pumps operating, reactor trip is initiated when the reactor power level reaches 109.0% of indicated full power. Adding to this the possible variation in trip point due to calibration and measurement errors, the maximum actual steady-state power at which a trip would be actuated is 112%, which was used for the purpose of safety analysis.(')
During reactor operation at power levels between 19.1% and 100% of rated power, the Variable High Power Trip (VHPT) will initiate a reactor trip in the event of a reactivity excursion that increases reactor power by 10% or less of rated power. The high power trip setpoint can be set no more than 10% of rated power above the indicated plant power. Operator action is required to increase the set point as plant power is increased. The setpoint is automatically decreased as power decreases.
1-6 Amendment No. ,32,210,218
I- - 1 -. 1-- -- -- . -
2.0 LIMITING CONDITIONS FOR OPERATION 2.7 Electrical Systems Applicability Applies to the availability of electrical power for the operation of plant components.
Objective To define those conditions of electrical power availability necessary to provide for safe reactor operation and the continuing availability of engineered safety features.
Specifications (1) Minimum Requirements The reactor shall not be heated up or maintained at temperatures above 300°F unless the following electrical systems are operable:
- a. Unit auxiliary power transformers T1A-1 or -2 (4,160 V).
- b. House service transformers TlA-3 and 4 (4,160 V).
- c. 4,160 V engineered safety feature buses 1A3 and 1A4.
- d. 4,160 V/480 V Transformers T1 B-3A, T1B-3B, T1B-3C, TlB-4A, T1B-4B, TI B-4C.
- e. 480 V distribution buses I B3A, 1B3A-4A, 1B4A, IB3B, IB3B-4B, IB4B, 1B3C, IB3C-4C, 1B4C.
- f. MCC No. 3A1, 3B1, 3A2,3C1, 3C2,4A1, 4A2,4C1 and 4C2.
- g. 125 V d-c buses No. 1 and 2 (Panels EE-8F and EE-8G).
- h. 125 V d-c distribution panels Al-41A and Al-41B.
- i. 120V a-c instrument buses A, B, C, and D (Panels Al-40-A, B, C and D).
- j. Inverters A, B, C, and D.
- k. Station batteries No. 1 and 2 (EE-8A and EE-8B) including one battery charger on each 125V d-c bus No. 1 and 2 (EE-8F and EE-8G).
- i. Two emergency diesel generators (DG-1 and DG-2).
- -. - One diesel fuel oii storage system containing-a-minimum volume of 16,000 gallons of diesel fuel in FO-1, and a minimum volume of 10,000 gallons of diesel fuel in FO-10.
2-32 Amendment No. 147,162,180,213,218
2.0 LIMITING CONDITIONS FOR OPERATION 2.7 Electrical Systems (Continued) plant shutdown as required by Specification 2.7(2). This period is acceptable based on the remaining capacity (more than 6 days), the fact that procedures are in place to obtain replenishment, and the low probability of an event during this brief period.
Additional supplies of diesel fuel oil are available in the Omaha area and from nearby terminals. Ample facilities exist to assure deliveries to the site within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
One battery charger on each battery shall be operating so that the batteries will always be at full charge; this ensures that adequate d-c power will be available for all emergency uses. Each battery has one battery charger permanently connected with a third charger capable of being connected to either battery bus. The chargers are each rated for 400 amperes at 130 volts. Following a DBA the batteries and the chargers will handle all required loads. Each of the reactor protective channels instrumentation channels is supplied by one of the safety-related a-c instrument buses. The removal of one of the safety-related a-c instrument buses is permitted as the 2-of-4 logic may be manually changed to a 2-of-3 logic without compromising safety.
The engineered safeguards instrument channels use safety-related a-c instrument buses (one redundant bus for each channel) and d-c buses (one redundant bus for each logic circuit). The removal of one of the safety-related a-c instrument buses is permitted as the two of four logic automatically becomes a two of three logic.
Required engineered safeguards components, as described in Specification 2.7(2),
refers to components required to be operable by other Limiting Conditions for Operation within these Technical Specifications. If no other LCO requires a particular ESF component to be operable, then its redundant component is also not required to be operable due to this specification. As an example, Specification 2.3 requires that safety injection pumps be operable prior to the reactor being made critical, and Specification 2.7 applies when the RCS is above 300°F. If the RCS is above 300°F but the reactor is not critical, then no safety injection pumps are required to be operable.
References (1) USAR, Section 8.3.1.2 (2) USAR, Section 8.4.1 (3) USAR, Section 8.2.2 2-36a Amendment No. 147,162,18(,218
3.0 SURVEILLANCE REQUIREMENTS 3.0.1 Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
3.0.2 The surveillance intervals are defined as follows:
Notation Title Frequency S Shift At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days A Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days R Refueling At least once per 18 months P Start up Prior to Reactor Start up, if not completed in the previous week.
Exception to these intervals are stated in the individual Specifications.
3.0.3 The provisions of Specifications 3.0.1 and 3.0.2 are applicable to all codes and standards referenced within the Technical Specifications. The requirements of the Technical Specifications shall have precedence over the requirements of the codes and standards referenced within the Technical Specifications.
3.0.4 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specifications 3.0.1 and 3.0.2, shall constitute noncompliance with the OPERABILITY requirements for the corresponding Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be performed on inoperable equipment.
3-Oa Amendment No. 122,129,157,218
TABLE 3-5 (Continued) U USAR Section Test Freguenc Reference 10c. (continued) 4. Automatic and/or manual initi- R ation of the system shall be demonstrated.
- 11. Containment 1. Demonstrate damper action. 1 year, 2 years, 5 years, and every 5 9.10 Ventilation System years thereafter.
Fusible Linked Dampers 2. Test a spare fusible link.
- 12. Diesel Generator Calibrate R 8.4.3 Under-Voltage Relays
- 13. Motor Operated Verify the contactor pickup value at R Safety Injection <85% of 460 V.
Loop Valve Motor Starters (HCV-311, 314, 317, 320, 327, 329, 331, 333, 312, 315, 318, 321)
- 14. Pressurizer Heaters Verify control circuits operation R for post-accident heater use.
- 15. Spent Fuel Pool Test neutron poison samples for 1, 2, 4, 7, and 10 years after Racks dimensional change, weight, neutron installation, and every 5 years attenuation change and specific thereafter.
gravity change.
- 16. Reactor Coolant 1. Verify all manual isolation During each refueling outage just Gas Vent System valves in each vent path are prior to plant start-up.
in the open position.
- 2. Cycle each automatic valve in the R vent path through at least one complete cycle of full travel from the control room. Verification of valve cycling may be determined by observation of position indicating lights.
- 3. Verify flow through the reactor R coolant vent system vent paths.
3-20d Amendment No. 41,54,60,75,77,80,15,169,102, 218
3.0 SURVEILLANCE REQUIREMENTS 3.5 Containment Test Applicabilitv Applies to containment leakage and structural integrity.
Obiective To verify that the:
(1) Locked closed manual containment isolation valves are closed and locked, (2) potential leakage from containment is within acceptable limits, and (3) structural performance of all important components in the containment prestressing system is acceptable.
Specifications (1) Prior to the reactor going critical after a refueling outage, and at least once per 31 days thereafter, an administrative check will be made to confirm that all "locked closed" manual containment isolation valves, except for valves that are open under administrative control as permitted by Specification 2.6(1)a, are closed and locked. Valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position shall be verified closed during each cold shutdown except that such verification need not be performed more often than once per 92 days.
(2) Containment ntearated Leakaae Rate Test (Tve A Tests)
Perform required visual examinations and leakage rate testing in accordance with the Containment Leakage Rate Testing Program.
(3) Containment Penetrations Leak Rate Tests (Tve B Tests)
Perform required visual examinations and leakage rate testing in accordance with the Containment Leakage Rate Testing Program for the following penetrations:
(i) Equipment Hatch (ii) Personnel Air Lock (iii) Mechanical Penetrations M-1 through M-99 (iv) Fuel Transfer Tube (Mechanical Penetration M-100)
(v) Electrical Penetrations:
A-1 B-9 D-6 F-2 E-HCV-383-3A A-2 B-10 D-7 F-4 E-HCV-383-3B A-4 B-1 1 D-8 F-5 E-HCV-383-4A A-5 C-1 D-9 F-6 E-HCV-383-4B A-6 C-2 D-10 F-7 A-7 C-4 D-11 F-8 A-8 C-5 E-1 F-9
- . - - A-9 C-6 E-2 F-1 - .. -
3-37 Amendment No. 9 5,151,185, 2 18