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Category:Technical Specification
MONTHYEARML22081A0402022-03-10010 March 2022 Independent Spent Fuel Storage Installation, 10 CFR 50.59 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review LIC-20-0005, Independent Spent Fuel Storage Installation, Technical Specification Basis2020-04-30030 April 2020 Independent Spent Fuel Storage Installation, Technical Specification Basis LIC-15-0014, License Amendment Request (Laa) 15-01; Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using the Consolidated Line Item...2015-07-24024 July 2015 License Amendment Request (Laa) 15-01; Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using the Consolidated Line Item... LIC-15-0018, Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-52015-01-27027 January 2015 Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-5 LIC-14-0135, Supplement to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements2014-12-10010 December 2014 Supplement to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements LIC-14-0122, License Amendment Request (LAR) 14-09; Application to Revise Technical Specification 3.1, Table 3-3, to Correct an Administrative Error in the Surveillance Method for the Containment Wide Range Radiation Monitors2014-11-0707 November 2014 License Amendment Request (LAR) 14-09; Application to Revise Technical Specification 3.1, Table 3-3, to Correct an Administrative Error in the Surveillance Method for the Containment Wide Range Radiation Monitors ML12226A1712012-06-18018 June 2012 Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, and Updated Safety Analysis Report (USAR) Revision ML12128A1702012-04-12012 April 2012 Technical Specification (TS) Basis Change Index, Page 2 of 2 and TS 2.10 - Page 18 LIC-12-0027, License Amendment Request (LAR) 12-02, Proposed Change to Relocate Operating and Surveillance Requirements for Technical Specifications 217 and 3.13 Concerning Miscellaneous Radioactive Material Sources2012-03-0909 March 2012 License Amendment Request (LAR) 12-02, Proposed Change to Relocate Operating and Surveillance Requirements for Technical Specifications 217 and 3.13 Concerning Miscellaneous Radioactive Material Sources ML11257A0392011-08-25025 August 2011 08/25/2011 Issues #1 ML0924303932009-09-28028 September 2009 Correction to Amendment No. 260 Modification of Surveillance Requirements for Containment Air Cooling and Filtering System and Removal of License Conditions 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-07-0043, License Amendment Request, Addition of Swing Inverters to 120-Volt Alternating Current Instrument Buses2007-07-31031 July 2007 License Amendment Request, Addition of Swing Inverters to 120-Volt Alternating Current Instrument Buses ML0706102732007-06-0606 June 2007 Technical Specification Pages - Amendment No. 250 Adoption of TSTF-447 to Delete Requirements for Hydrogen Purge System - CLIIP ML0631805462006-11-13013 November 2006 Technical Specification Pages - Issuance of Amendment 247 Change of Containment Building Sump Buffering Agent from Trisodium Phosphate to Sodium Tetraborate ML0630003122006-10-27027 October 2006 Issuance of Amendment Modifications to TS, Containment Cooling to Reduce Operable Containment Spray Pumps (MC9297) LIC-06-0087, 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 SGT Repair Method.2006-08-30030 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 SGT Repair Method. LIC-05-0137, Revised License Amendment Request, Deletion of Sleeving as a Steam Generator Tube Repair Method2005-12-19019 December 2005 Revised License Amendment Request, Deletion of Sleeving as a Steam Generator Tube Repair Method ML0530501552005-11-0101 November 2005 Technical Specifications for Fort Calhoun, Corrections to Amendment Number 226. TAC Mc 0194 ML0508404912005-03-22022 March 2005 2 Pages Fort Calhoun - for Amd. 234. Elimination of Requirements for Hydrogen Monitors Using the Consolidated Line Item Improvement Process (Tac. MC4305) ML0507500592005-03-11011 March 2005 Tech Spec Pages for Amendment 233 Revising TS 5.9.5 to Be Consistent with Specification 5.6.5 of NUREG-1432 ML0505300112005-02-18018 February 2005 Tech Spec Page for Amendment 231 Elimination of Requirements to Provide Monthly Operating/Annual Occupational Radiation Exposure Reports LIC-04-0117, License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0.2004-11-23023 November 2004 License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0. ML0433501352004-10-21021 October 2004 Tech Spec Pages for Amendment No. 229, Changing TS 2.7, TS Table 3-5 and TS 5.0 to Modify Requirements for the Diesel Generator Fuel Oil for Consistency with Improved Standard TS ML0411901872003-12-31031 December 2003 Omaha Public Power District Fort Calhoun Station Unit 1, Annual Report for Technical Specification Section 5.9.4.a, January 1, 2003 to December 31, 2003. ML0331604192003-11-10010 November 2003 TS Pages (2), Fort Calhoun Station, Unit 1, Issuance of Amendment No. 223, Deleting TS 2.3(2)i and the Corresponding Bases That Allows the Performance of the Surveillance Test of Table 3.2, Item 20 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 LIC-02-0105, License Amendment Request, Various Administrative and Editorial Changes.2003-01-27027 January 2003 License Amendment Request, Various Administrative and Editorial Changes. ML0302201532003-01-16016 January 2003 Technical Specification Pages for Amendment 215 Missed Surveillances and Adoption of a Technical Specification Bases Control Program ML0233106842002-11-26026 November 2002 Ft. Calhoun Station, Unit 1, Technical Specification Pages for Amendment 212, Steam and Feedwater Systems LIC-02-0065, License Amendment Request, Steam and Feedwater Systems.2002-07-23023 July 2002 License Amendment Request, Steam and Feedwater Systems. LIC-02-0066, License Amendment Request Re Technical Specification Change Regarding Missed Surveillance and Adoption of a Technical Specification Bases Control Program for Fort Calhoun Unit 12002-07-22022 July 2002 License Amendment Request Re Technical Specification Change Regarding Missed Surveillance and Adoption of a Technical Specification Bases Control Program for Fort Calhoun Unit 1 ML0208701962002-03-26026 March 2002 Tech Spec Pages for Amendment No. 204 Dated March 26, 2002 ML0208701892002-03-26026 March 2002 Tech Spec Pages Amendment No. 205 Tac No. MB3652 Dated March 26, 2002 2022-03-10
[Table view] Category:Amendment
MONTHYEARLIC-15-0018, Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-52015-01-27027 January 2015 Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-5 LIC-14-0135, Supplement to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements2014-12-10010 December 2014 Supplement to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements LIC-14-0122, License Amendment Request (LAR) 14-09; Application to Revise Technical Specification 3.1, Table 3-3, to Correct an Administrative Error in the Surveillance Method for the Containment Wide Range Radiation Monitors2014-11-0707 November 2014 License Amendment Request (LAR) 14-09; Application to Revise Technical Specification 3.1, Table 3-3, to Correct an Administrative Error in the Surveillance Method for the Containment Wide Range Radiation Monitors LIC-12-0027, License Amendment Request (LAR) 12-02, Proposed Change to Relocate Operating and Surveillance Requirements for Technical Specifications 217 and 3.13 Concerning Miscellaneous Radioactive Material Sources2012-03-0909 March 2012 License Amendment Request (LAR) 12-02, Proposed Change to Relocate Operating and Surveillance Requirements for Technical Specifications 217 and 3.13 Concerning Miscellaneous Radioactive Material Sources ML11257A0392011-08-25025 August 2011 08/25/2011 Issues #1 ML0924303932009-09-28028 September 2009 Correction to Amendment No. 260 Modification of Surveillance Requirements for Containment Air Cooling and Filtering System and Removal of License Conditions LIC-07-0043, License Amendment Request, Addition of Swing Inverters to 120-Volt Alternating Current Instrument Buses2007-07-31031 July 2007 License Amendment Request, Addition of Swing Inverters to 120-Volt Alternating Current Instrument Buses ML0706102732007-06-0606 June 2007 Technical Specification Pages - Amendment No. 250 Adoption of TSTF-447 to Delete Requirements for Hydrogen Purge System - CLIIP ML0631805462006-11-13013 November 2006 Technical Specification Pages - Issuance of Amendment 247 Change of Containment Building Sump Buffering Agent from Trisodium Phosphate to Sodium Tetraborate ML0630003122006-10-27027 October 2006 Issuance of Amendment Modifications to TS, Containment Cooling to Reduce Operable Containment Spray Pumps (MC9297) LIC-06-0087, 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 SGT Repair Method.2006-08-30030 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 SGT Repair Method. ML0530501552005-11-0101 November 2005 Technical Specifications for Fort Calhoun, Corrections to Amendment Number 226. TAC Mc 0194 ML0508404912005-03-22022 March 2005 2 Pages Fort Calhoun - for Amd. 234. Elimination of Requirements for Hydrogen Monitors Using the Consolidated Line Item Improvement Process (Tac. MC4305) ML0507500592005-03-11011 March 2005 Tech Spec Pages for Amendment 233 Revising TS 5.9.5 to Be Consistent with Specification 5.6.5 of NUREG-1432 ML0505300112005-02-18018 February 2005 Tech Spec Page for Amendment 231 Elimination of Requirements to Provide Monthly Operating/Annual Occupational Radiation Exposure Reports ML0433501352004-10-21021 October 2004 Tech Spec Pages for Amendment No. 229, Changing TS 2.7, TS Table 3-5 and TS 5.0 to Modify Requirements for the Diesel Generator Fuel Oil for Consistency with Improved Standard TS ML0411901872003-12-31031 December 2003 Omaha Public Power District Fort Calhoun Station Unit 1, Annual Report for Technical Specification Section 5.9.4.a, January 1, 2003 to December 31, 2003. ML0331604192003-11-10010 November 2003 TS Pages (2), Fort Calhoun Station, Unit 1, Issuance of Amendment No. 223, Deleting TS 2.3(2)i and the Corresponding Bases That Allows the Performance of the Surveillance Test of Table 3.2, Item 20 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 LIC-02-0105, License Amendment Request, Various Administrative and Editorial Changes.2003-01-27027 January 2003 License Amendment Request, Various Administrative and Editorial Changes. ML0302201532003-01-16016 January 2003 Technical Specification Pages for Amendment 215 Missed Surveillances and Adoption of a Technical Specification Bases Control Program ML0233106842002-11-26026 November 2002 Ft. Calhoun Station, Unit 1, Technical Specification Pages for Amendment 212, Steam and Feedwater Systems LIC-02-0065, License Amendment Request, Steam and Feedwater Systems.2002-07-23023 July 2002 License Amendment Request, Steam and Feedwater Systems. LIC-02-0066, License Amendment Request Re Technical Specification Change Regarding Missed Surveillance and Adoption of a Technical Specification Bases Control Program for Fort Calhoun Unit 12002-07-22022 July 2002 License Amendment Request Re Technical Specification Change Regarding Missed Surveillance and Adoption of a Technical Specification Bases Control Program for Fort Calhoun Unit 1 ML0208701962002-03-26026 March 2002 Tech Spec Pages for Amendment No. 204 Dated March 26, 2002 ML0208701892002-03-26026 March 2002 Tech Spec Pages Amendment No. 205 Tac No. MB3652 Dated March 26, 2002 2015-01-27
[Table view] |
Text
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.4 Containment Cooling Applicability Applies to the operating status of the containment cooling systems.
Objective To assure operability of equipment required to remove heat from the containment during normal operating and emergency situations.
Specifications (1) Minimum Requirements
- a. The reactor shall not be made critical, except for low-temperature physics tests, unless all the following are met:
- i. The following equipment normally associated with diesel-generator DG-1 (4.16-kV bus 1A3 and associated non-automatically transferring 480-Volt bus sections) is operable, except as noted:(1)
Raw water pump AC-10A Raw water pump AC-10C Component cooling water pump AC-3A Component cooling water pump AC-3C Containment spray pump SI-3A Containment air cooling and filtering unit VA-3A Containment air cooling unit VA-7C ii. The following equipment normally associated with diesel-generator DG-2 (4.16-kV 1A4 and associated non-automatically transferable 480 Volt bus sections) is operable, except as noted.(1)
Raw water pump AC-10B Raw water pump AC-10D Component cooling water pump AC-3B Containment spray pump SI-3B Containment air cooling and filtering unit VA-3B Containment air cooling unit VA-7D iii. Four component cooling heat exchangers shall be operable.
iv. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable.
(1)
Reactor may be made critical with one inoperable raw water pump. LCO action statements shall apply.
2.4 - Page 1 Amendment No. 120,175, 244
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.4 Containment Cooling (Continued)
- b. During power operation one of the components listed in (1)a.i. and ii. may be inoperable. If the inoperable component is not restored to operability within seven days, the reactor shall be placed in 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 inoperable component is not restored to operability 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 />.
- c. For cases involving Raw Water pump inoperability, if the river water temperature is below 60 degrees Fahrenheit, one Raw Water pump may be inoperable indefinitely without applying any LCO action statement. When the river water temperature is greater than 60 degrees Fahrenheit, an inoperable Raw Water pump shall be restored to operability within 7 days or 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 inoperable Raw Water pump is not restored to operability 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 />.
(2) Modification of Minimum Requirements
- a. During power operation, the minimum requirements may be modified to allow a total of two of the components listed in (1)a.i. and ii. to be inoperable at any one time. (This does not include: 1) One Raw Water pump which may be inoperable as described above if the river water temperature is below 60 degrees Fahrenheit or, 2) SI-3A and SI-3B being simultaneously inoperable.
Only two raw water pumps may be out of service during power operations.
Either containment spray pump, SI-3A or SI-3B, must be operable during power operations.) If the operability of one of the two components is not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 />. LCO 2.4(1)b. shall be applied if one of the inoperable components is restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the operability of both components is not restored 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 />.
- b. During power operation one component cooling heat exchanger may be inoperable. If the operability of the heat exchanger is not restored within 14 days, 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 two component cooling heat exchangers are inoperable, the reactor shall be placed in 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 inoperable heat exchanger(s) is not restored to operability 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 />.
- c. Any valves, interlocks and 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 for that component.
- d. Any valve, interlock or piping associated with the containment cooling system which is not included in the above paragraph and which is required 2.4 - Page 2 Amendment No. 49,111,120,175, 244
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.4 Containment Cooling (Continued) 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 />. If operability is not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 />.
Basis A full capacity diesel-generator is connected to each of the two engineered safeguards 4.16-kV buses. Three engineered safeguards 480-Volt double-ended load centers are provided; of the six transformers, three are connected to each of the two 4.16-kV buses.
Two load centers are operated as two-bus-section units; the third is provided with a center bus manually transferable to either associated end section. The center bus section supplies HPSI Pump SI-2C, CS Pump SI-3C and Charging Pump CH-1C any of which can thus be supplied from either 4.16-kV bus if required (note that CS pump SI-3C is connected to the center bus, however, this pump is available for manual operation only). The containment spray pumps initially take coolant from the safety injection and refueling water (SIRW) tank. Before this supply of water is exhausted (at least 24 minutes)(2) the spray system is transferred to the recirculation mode and the pumps take suction from the containment sump. One shutdown cooling heat exchanger is sufficient to satisfy the spray system requirements during the long-term containment cooling period.(3) In addition, in the unlikely event of the component cooling water supply being lost, raw water can be utilized for direct cooling of certain engineered safeguard components.(4)
The containment spray system is independant from the containment air cooling and filtering unit for the containment cooling function.(5) For the limiting Loss of Coolant Accident (LOCA ) scenario, one of the two spray pumps would limit the containment pressure to below the design value without taking credit for the air coolers or the cooling capacity of the safety injection system.(6) (7) For the limiting Main Steam Line Break (MSLB) scenario, a heat removal contribution is credited from the air coolers in the mitigation of containment peak pressure.(7) Credit is taken for iodine removal by the containment spray system.
The cooling equipment provided to limit the containment pressure following a DBA is divided between the independent power supply systems. The raw water and component cooling water pumps are similarly distributed on the 4.16-kV and 480 Volt buses. In the event of a DBA, loss of normal power sources and failure of one diesel-generator to operate, a minimum of one spray pump, and two air coolers would be connected to the available diesel-generator. This would provide adequate containment cooling equipment to limit the containment pressure below the design value for the limiting one pump, one spray header LOCA event. The limiting MSLB event in which off site power is available, is not affected by the loss of one diesel generator.
2.4 - Page 3 Amendment No. 111,166,175,198, 244
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.7 Electrical Systems (Continued)
Basis The electrical system equipment is arranged so that no single failure can inactivate enough engineered safeguards to jeopardize the plant safety. The 480 V safeguards are arranged on nine bus sections. The 4.16 kV safeguards are supplied from two buses.
The normal source of auxiliary power with the plant at power for the safeguards buses is from the house service power transformers being fed from the 161 Kv incoming line with on-site emergency power from either one of two diesel generators and off-site standby power via the unit auxiliary transformers.(1) The loss of the 161kV incoming line renders the house service transformers (T1A-3 and T1A-4) inoperable in that the transformers cannot supply power to the 4.16kV safeguards buses 1A3 and 1A4. Inoperability of the house service transformer(s) or loss of the 161kV incoming line is not reportable pursuant to 10 CFR 50.72 criteria; however, the NRC will be promptly notified of these events via the NRC Operations Center.
The two emergency diesel generators on site do not require offsite power for start up or operation.
Upon loss of normal and standby power sources, the 4.16 Kv buses 1A3 and 1A4 are energized from the diesel generators. Bus load shedding, transfer to the diesel generator and pickup of critical loads are carried out automatically.(2)
When the turbine generator is out of service for an extended period, the generator can be isolated by opening motor operated disconnect switch DS-T1 in the bus between the generator and the main transformer, allowing the main transformer and the unit auxiliary power transformers (T1A-1 and T1A-2) to be returned to service.(3) The auxiliary power transformers are not considered inoperable during these normal plant startup/shutdown realignments.
Minimum requirements are implemented prior to raising the RCS temperature above 300EF to assure availability of engineered safety features.
The time allowed to repair an inoperable inverter is based upon engineering judgement, taking into consideration the time required to repair an inverter and the additional risk to which the unit is exposed because of the inverter inoperability. In the event of inverter failure, the load on the inverter is automatically transferred to its safety related bypass source. The associated 120 V a-c instrument bus is considered OPERABLE when it is being powered from its bypass source and during the short time it takes to manually or automatically transfer between sources.
Equipment served by 4.16 kV and 480 V auxiliary buses and MCC's is arranged so that loss of an entire 4.16 kV bus does not compromise safety of the plant during DBA conditions. For example, if 4.16 kV bus 1A3 is lost, two raw water pumps, one low pressure safety injection pump, two high pressure safety injection pumps, one auxiliary feedwater pump, two component cooling water pumps, one containment spray pump and two containment air fans are lost. This leaves two raw water pumps, one low pressure safety injection pump, one high pressure safety injection pump, one component cooling water pump, one containment spray pumps and two containment air fans which is more than sufficient to control containment pressure below the design value during the DBA.
2.7 - Page 5 Amendment No. 147,162,180,213, 229, 244