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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to ABB C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20134H3771996-11-0606 November 1996 Proposed Tech Specs of Appendix a Re Cooling Water Sys ML20134E4551996-10-25025 October 1996 Proposed Tech Specs Changing TS 4.4.A, Containment Leakage Tests, Bases to TS Section B.4.4, Containment Sys Tests & Adding TS.6.5.J, Containment Leakage Rate Testing Program ML20129E2591996-09-24024 September 1996 Proposed Tech Specs,Changing TS 4.12 to Incorporate Revised Acceptance Criteria for SG Tubes W/Degradation in Tubesheet Region ML20117P4311996-09-11011 September 1996 Proposed Tech Specs,Revising Plant TS Governing Cw Sys ML20117B2381996-08-15015 August 1996 Proposed Tech Specs 3.3.B.2 Re Containment Cooling Sys & Bases to Conform to Supporting Analyses ML20115G8121996-07-15015 July 1996 Proposed Tech Specs Re Moveable Incore Detector Thimble Reduction ML20095J7951995-12-14014 December 1995 Proposed Tech Specs for Conformance of Administrative Controls Section 6 to Guidance of STS ML20094S2791995-11-28028 November 1995 Proposed Tech Specs Re Radiological Effluent TS Conformance ML20087F3571995-08-0909 August 1995 Proposed Tech Specs Table TS 3.15-1,Pages 1 & 2 & Bases Page B.3.15-1 Marked Up to Implement License Amend Request 1999-08-31
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to ABB C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20195F1391998-10-0808 October 1998 Non-proprietary Version of Rev 1 to NSPNAD-97002, Steam Line Break Methodology ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20151Z9181998-08-0303 August 1998 Rev 0 to 5AWI 6.1.2, Design Outputs,Review & Verification ML20151Z9011998-08-0303 August 1998 Rev 2 to 5AWI 6.1.0, Design Change General ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20248M1421998-04-0606 April 1998 Draft NRC Insp Manual Temporary Instruction 2515/XXX Fire Protection Functional Insp (Fpfi) ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20151Z9561998-01-0505 January 1998 Rev 0 to 5AWI 6.1.7, Design Change Work Orders ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20151Z9441997-10-20020 October 1997 Rev 0 to 5AWI 6.1.6, Design Review & Approval ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20136H0101997-01-29029 January 1997 Rev 12 to Abnormal Procedure AB-3, Earthquakes ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20138G8751996-11-0808 November 1996 Rev 2 to TN-40 Cask Unloading Procedure 1999-08-31
[Table view] |
Text
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l LICENSE AMENDMENT REQUEST DATED August 15,1996 Amendment of Containment Cooling Systems Technical Specifications to Conform to Their Supportina Analyses j
EXHIBIT B i
l Appendix A, Technical Specification Pages Marked Up Pages I
TS.3.3-4 B.3.3-3 B.3.3-3 Overflow i
i 9608260439 960815 ADOCK0500g2 PDR P
j
i l
TS.3.3-4 RE" ?! 10/27/??
3.3.B.
Containment Cooline Systems l
l
- 1. A reactor shall not be made or maintained critical nor shall reactor coolant system average temperature exceed 200*F unless the
{
l following conditions are satisfied (except as specified in 3.3.5.2 l
below).
a.
Two containment spray pumps are OPERABLE.
b.
Four containment fan cooler units are OPERABLE.
- c. The spray additive tank is OPERABLE with not less than 2590 gallons of solution with a sodium hydroxide concentration of 94 to lit by weight inclusive.
- d. Manual valves in the above systems that could (if improperly positioned) reduce spray flow below that assumed for accident analysis, shall be blocked and tagged in the proper position.
During POWER OPERATION, changes in valve position will be under direct administrative control.
- e. The containment spray system motor operated valves MV-32096 and MV-32097 (Unit 2 valves: MV-32108 and MV-32109) shall be closed and shall have the motor control center supply breakers in the off position.
- 2. During STARTUP OPERATION or POWER OPERATION, any one of the fol-i lowing conditions of inoperability may exist provided STARTUP OPERATION is discontinued until OPERABILITY is restored. If.
OPERABILITY is not restored within the time specified, 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- a. One containment fan cooler gjihunk may be inoperable for 7 daysy previded brth centninrent : prey ;" ;c cre OPERABLE.
- b. One containment spray g iiHpump may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, previded et leret tre centninrent fn :: ler unite er: OPERABLE.
- c. Tre centrinrent f n :: ler unit
- y be in:per ble fer 72 heure, previded et 1:2t en centninnent : prey p1 ; i OPERABLE.
- d. Tu centninnent spr y ;" ;
- y he ineperchic fer 72 heurs,
pr:vided frar centninrent fan :::ler unit cre OPERABLE.
e,- The spray additive tank may be inoperable for 2473 hours0.0286 days <br />0.687 hours <br />0.00409 weeks <br />9.409765e-4 months <br />.
x
_..m m.
t B.3.3-3 om
,m s o n, me 3.3 ENGINEERED SAFETY FEATURES i
l i
13331 continued The containment cooling function is provided by two independent systems:
containment fan cooler um&se and containment spraye. g CF),r.'
%NNY M@L@N 1hp%NM N paits. Tip e6a es** % @864 4 $ 9 05 0;sprey$sta 1L MPMI *_
s spfayJ 31g A g GDuring normal operation,
- t t ---t f:n :::1:: m64e are utilized to remove heat lost from equipment and piping within the containment. In the event of the Design Basis Accident, gg
)]$
g-y ::: ef ^-
j fellerin;; :: iin-tir-will provide sufficient cooling to reduce l
containment pressure 6 M M ) M g g l
Qg^ij[s g 3 8 M g : ferr : rtei--^rt fer :::ler rite, t:: : ntei-- nt :;rry p- : er tre : rtei--
t ft: :: ler rit: plu: ::: certrirr t :;rry ;--
t (Reference 4). $ : ef - fe r g : rtei----a ft: :: ler g[1^jrit:
Qase permitted to be inoperable during POWER OPERATION This is an abnormal operating situation, in that plant operating procedures require that inoperable g rtei----2 fer :::ler units be repaired as soon as practical. However, because of the difficulty of access to make repairs, it is important on occasion to be able to operate temporarily with only gjewe g *: rtei r:rt fen :::ler p. ggl3we g : tri----! fer :::ler gr*f-it: can provide adequate cooling for normal operation when the-
'i M:::tci-:t f n :::1:s units are cooled by the' chilled water system (Reference 3). Compensation for this mode of operation is provided by the j
high degree of redundancy of containment cooling systems during a Design l
Basis Accident.
One component cooling water pump together with one component cooling heat exchanger can accommodate the heat removal load on one unit, either following a loss-of-coolant accident or during normal plant shutdown. The four pumps of the two-unit facility can be cross connected as necessary to accommodate temporary outage of.the pump. If, during the post-accident phase, the component cooling watar supply were lost, core and containment cooling could be maintained until repairs were effected (Reference 5).
Cooling water can be supplied by either of the two horizontal motor-driven pumps, by a safeguards motor-driven pump or by either of two safeguards diesel-driven pumps. (Reference 6). Operation of a single cooling water pump provides sufficient cooling in one unit during the injection and recirculation phases of a postulated loss-of coolant accident plus sufficient cooling to maintain the second unit in a hot standby condition.
TS.3.3.D.1.a assures that an automatic Safety Injection signal to the cooling water header isolation valves will not align both OPERABLE safe-guards pumps to the same safeguards train, j
TS.3.3.D.1.a also assures that 121 cooling water pump is aligned to provide i
cooling water to the same train as the train from which it is being powered (e.g., if 121 cooling wager pump is aligned to Train B cooling water header, it needs to be powered from Bus 26 and, ultimately, Diesel Generator D6 in the event of a loss of offsite power). Otherwise, the i
single failure of a diesel generator could leave one train of engineered safety features without power and the other train without cooling water.
i A
5/43T4 4
The minimum fuel supply of 19,000 gallons wil supply one diesel-driven cooling water pump for 14 days. Note that the 19,000 gallon requirement is included in the 70,000 gallon total diesel fuel oil requirement of Specification 3.7.A.5 for Unit 1.
4 l
i i
i 1
O LICENSE AMENDMENT REQUEST DATED August 15,1996 Amendment of Containment Cooling Systems Technical Specifications to Conform to Their Suocortina Analyses EXHIBIT C Appendix A, Technical Specification Pages Revised Pages TS.3.3-4 l
B.3.3-3 i
i I
l
.. -. -~--.-- =.
TS.3.3-4 3.3.B.
Containment Cooling Systems
- 1. A reactor shall not be made or maintained critical nor shall I
reactor coolant system average temperature exceed 200*F unless the following conditions are satisfied (except as specified in 3.3.B.2 below):
a.
Two containment spray pumps are OPERABLE.
b.
Four containment fan cooler units are OPERABLE.
- c. The spray additive tank is OPERABLE with not less than 2590 gallons of solution with a sodium hydroxide concentration of 94 to j
lit by weight inclusive.
{
- d. M nual valves in the above systems that could (if improperly
. positioned) reduce spray flow below that assumed for accident analysis, shall be blocked and tagged in the proper position.
During POWER OPERATION, changes in valve position will be under i
direct administrative control.
j i
- e. The containment spray system motor operated valves MV-32096 and MV-32097 (Unit 2 valves: MV-32108 and MV-32109) shall be closed and shall have the motor control center supply breakers j
in the off position.
j
- 2. During STARTUP OPERATION or POWER OPERATION, any one of the fol-loving conditions of inoperability may exist provided STARTUP OPERATION is discontinued until OPERABILITY is restored. If OPERABILITY is not restored within the time specified, 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, j
- a. One containment fan cooler train may be inoperable for 7 days
- b. One containment spray train may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
c.
The spray additive tank may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
O c
B.3.3-3 3.3 ENGINEERED SAFETY FEATURES Bases continued The containment cooling function is provided by two independent systems:
containment fan cooler (CFC) and containment spray. The CFC system consists of two separate trains with each train consisting of two fan coil units.
The containment spray system consists of two independent trains, except that each train is supplied sodium hydroxide from a single, common spray additive tank. During normal operation, two CFC trains are utilized to remove heat lost from equipment and piping within the containment. In the event of the Design Basis Accident, one containment fan cooler unit plus one containment spray pump will provide sufficient cooling to reduce containment pressure and maintain off-site and control room doses within regulatory limits (Reference 4). One CFC train is permitted to be inoperable during POWER OPERATION. This is an abnormal operating situation, in that plant operating procedures require that inoperable CFC units be repaired as soon as practical. However, because of the difficulty of access to make repairs, it is important on occasion to be able to operate temporarily with only one CFC train. One CFC train can provide adequate cooling for normal operation when the CFC units are cooled by the chilled water system (Reference 3). Compensation for this mode of operation is provided by the high degree of redundancy of containment cooling systems during a Design Basis Accident.
One component cooling water pump together with one component cooling heat exchanger can accommodate the heat removal load on one unit, either following a loss-of-coolant accident or during normal plant shutdown. The four pumps of the two-unit facility can be cross connected as necessary to accommodate temporary outage of the pump. If, during the post-accident phase, the component cooling water supply were lost, core and containment cooling could be maintained until repairs were effected (Reference 5).
Cooling water can be supplied by either of the two horizontal motor-driven pumps, by a safeguards motor-driven pump or by either of two safeguards diesel-driven pumps. (Reference 6). Operation of a single cooling water pump provides sufficient cooling in one unit during the injection and recirculation phases of a postulated loss-of coolant accident plus sufficient cooling to maintain the second unit in a hot standby condition.
TS.3.3.D.1.a assures that an automatic Safety Injection signal to the cooling water header isolation valves will not align both OPERABLE safe-guards pumps to the same safeguards train.
TS.3.3.D.1.a also assures that 121 cooling water pump is aligned to provide cooling water to the same train as the train from which it is being powered (e.g., if 121 cooling wager pump is aligned to Train B cooling water header, it needs to be powered from Bus 26 and, ultimately, Diesel Generator D6 in the event of a loss of offsite power). Otherwise, the single failure of a diesel generator could leave one train of engineered safety features without power and the other train without cooling water.
The minimum fuel supply of 19,000 gallons wil supply one diesel-driven cooling water pump for 14 days. Note that the 19,000 gallon requirement is included in the 70,000 gallon total diesel fuel oil requirement of Specification 3.7.A.5 for Unit 1.