Letter Sequence Other |
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MONTHYEARML20127E7021985-06-0606 June 1985 Requests Review of Tech Spec Requirements to Confirm That Response Time Surveillance Requirement Appropriate & Consistant W/Definition of Reactor Trip Sys Response Time. License Amend Needed If Response Time Incorrect Project stage: Approval ML20133B2541985-09-23023 September 1985 Proposed Tech Specs,Rectifying Inconsistencies W/Installed Instrumentation Not in Agreement W/Rev 4 to NUREG-0452 & Removing Unnecessary Numerals from Spec Numbers Project stage: Other ML20133B2491985-09-23023 September 1985 Rev 1 to License Change Application 117,modifying Tech Specs to Rectify Inconsistencies W/Installed Instrumentation Not in Agreement W/Rev 4 to NUREG-0452 & to Remove Unnecessary Numerals from Spec Numbers Project stage: Other ML20133B2331985-09-23023 September 1985 Forwards Rev 1 to License Change Application 117,requesting Amend to License NPF-1,modifying Tech Specs to Revise Reactor Trip Sys & ESFAS Instrumentation Requirements. Certificate of Svc Encl Project stage: Other ML20207B8141986-07-0303 July 1986 Proposed Tech Specs,Incorporating License Change Application 117 Re Reactor Trip Sys & ESFAS Instrumentation to Incorporate Revised WCAP-10271 & Westinghouse STS Project stage: Other ML20207B8041986-07-0303 July 1986 Revised Application to Amend License NPF-1,incorporating License Change Application 117,changing Tech Specs Re Reactor Trip Sys & ESFAS Instrumentation to Incorporate Revised WCAP-10271 & Westinghouse STS Project stage: Request ML20207B7961986-07-0303 July 1986 Forwards Revised Application to Amend License NPF-1, Incorporating License Change Application 117,changing Tech Specs Re Reactor Trip Sys & ESFAS Instrumentation to Incorporate Revised WCAP-10271 & Westinghouse STS Project stage: Request ML20212M3981986-08-22022 August 1986 Proposed Tech Specs Re Table 3.3-1, Reactor Trip Sys Instrumentation, Action 19 of Table 3.3-3 & Protective & ESF Instrumentation Bases Project stage: Other ML20212M3511986-08-22022 August 1986 Revised Application for Amend to License NPF-1,incorporating Rev 2 to License Change Application 117,changing Tech Specs Re Table 3.3-1, Turbine Trip & Expansion of Reactor Protection Bases Per Change in Surveillance Interval Project stage: Request ML20211C8821986-10-17017 October 1986 Proposed Tech Specs Re Reactor Trip Sys & ESF Actuation Sys Instrumentation & Surveillance Requirements Project stage: Other ML20211C7901986-10-17017 October 1986 Revised Application to Amend License NPF-1,consisting of Changes to Rev 2 to License Change Application 117,revising Tech Spec Tables 3.3-1 Re Reactor Trip Sys Instrumentation & 4.3-1 Re ESF Sys Instrumentation Surveillance Requirements Project stage: Request ML20205F9111987-03-23023 March 1987 Withdraws Requested Change D.14.b of License Change Application 117 for License NPF-1 Re Reactor Protection Sys Instrumentation.Revised Page 15 Reflecting Withdrawal of Proposed Change Encl Project stage: Withdrawal ML20209D9081987-04-22022 April 1987 Forwards Amend 131 to License NPF-1 & Safety Evaluation. Amend Provides Changes to Reactor Trip Sys & ESFAS Instrumentation Requirements Project stage: Approval 1986-07-03
[Table View] |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint ML20151T5951988-08-12012 August 1988 Proposed Tech Specs,Revising Surveillance Requirements for ECCS Check Valves ML20151A0381988-07-0808 July 1988 Proposed Tech Specs Re Radioactive Gaseous Effluents & Radioactive Liquid Waste Sampling & Analysis Program ML20151U7171988-04-14014 April 1988 Revised Proposed Tech Specs Re Plant Sys,As Part of Rev 1 to License Change Application 142 ML20148K5971988-03-23023 March 1988 Proposed Revised Tech Specs Re RCS ML20148C2101988-03-18018 March 1988 Proposed Tech Specs,Reflecting Revised Offsite & Facility Organization Charts ML20196J9031988-03-0101 March 1988 Proposed Tech Specs Modifying OL NPF-1,removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5%.Certificate of Svc Encl ML20147E7371988-03-0101 March 1988 Proposed Tech Specs Re Containment Isolation Valves ML20149K1901988-02-17017 February 1988 Proposed Tech Specs,Adding New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity ML20149L6981988-02-15015 February 1988 Proposed Tech Specs Re Offsite & Facility Organization Charts.Util Certificate of Svc Encl ML20149H1121988-02-0404 February 1988 Proposed Tech Specs Revising Operability & Surveillance Requirements for Component Cooling Water Sys ML20147D4561988-01-15015 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organization Charts ML20195H8971987-12-24024 December 1987 Proposed Tech Specs Deleting Sections Re Fire Protection ML20237D6971987-12-18018 December 1987 Proposed Tech Specs,Requiring Measurement of Initial Discriminator Bias Curve for Each Detector & Subsequent Discrimination Bias Curves Obtained,Evaluated & Compared to Initial Curves ML20237D6551987-12-16016 December 1987 Proposed Tech Specs Deleting Provision for Continued Plant Operation in Section 3/4.4.6.2 & Requiring Prompt Unit Placement in Cold Shutdown After Pressure Boundary Leakage Occurrence ML20236W7611987-11-20020 November 1987 Proposed Tech Specs Including Effects of Nuclear Fuel Design Changes ML20236Q2271987-11-16016 November 1987 Proposed Tech Specs,Resolving Control Room Habitability Issues ML20236P4391987-11-13013 November 1987 Proposed Tech Specs,Extending Surveillance Time Period for Verifying Control Rod Insertability During Control Rod Worth & Shutdown Margin Tests to 7 Days.Certificate of Svc Encl ML20236N3861987-11-0909 November 1987 Proposed Tech Spec,Revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs.W/Certificate of Svc ML20236N5881987-08-0606 August 1987 Proposed Tech Spec Section, Bases Correcting Section for Agreement W/Definition of Pressure Boundary Leakage ML20235W5571987-07-14014 July 1987 Proposed Tech Specs Re Solid Radwaste Sys ML20215K8381987-06-22022 June 1987 Proposed Tech Spec Table 3.3-1,revising Operability Requirements for Reactor Trip Breakers & 4.3-1,revising Surveillance Requirements for Manual Reactor Trip,Reactor Trip Breakers & Bypass Breakers ML20210B6241987-04-29029 April 1987 Proposed Tech Specs Revising Typos & Clarifying Appropriate Process to Be Used for Review & Approval of Temporary Changes to Procedures.Certificate of Svc Encl ML20209D0251987-04-20020 April 1987 Proposed Tech Specs Re RCS Surveillance Requirements ML20206D9261987-04-0303 April 1987 Revised Tech Spec Pages 3/4 8-6 & 3/4 8-7 Re Onsite Power Distribution Sys,Per License Change Application 128 ML20206A6221987-04-0303 April 1987 Revised Tech Spec Page 7,clarifying License Change Application 124 Re power-operated Valves ML20245A2631987-02-26026 February 1987 Proposed Tech Specs,Consisting of Revised Pages for License Change Application 124 & License Change Application 135, Adding Steamline Isolation Valves & Valve CV-8825 Back Onto Table 3.6-1 & Excluding Containment Airlocks from Criteria ML20211P0031987-02-20020 February 1987 Proposed Tech Specs Re Steam Generator Tube Plugging Criteria in Tube Sheet Region ML20211H4021987-02-11011 February 1987 Proposed Tech Specs Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2% ML20207Q5371987-01-20020 January 1987 Proposed Tech Specs,Revising Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves 1999-03-18
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M7291999-08-0505 August 1999 Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units ML20207D3951999-06-0101 June 1999 Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J3911999-03-10010 March 1999 Trojan Nuclear Plant License Termination Plan ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20153D3081998-09-21021 September 1998 Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20196J5131997-07-29029 July 1997 Rev 0 to Trojan Second Integrated Test Rept,Filter Media Processing Sys Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20196J5241997-07-29029 July 1997 Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20137T9361997-04-0808 April 1997 Rev 1 to Trojan Proof of Principle Test Summary ML20137G1731997-03-20020 March 1997 Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program ML20137K5151997-03-0404 March 1997 Rev 0 to Trojan Proof of Principle Test Summary ML20138L1901997-01-30030 January 1997 Reactor Vessel & Internals Removal Plan ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059L1721993-11-30030 November 1993 Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20057D9131993-09-30030 September 1993 Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings ML20057F1631993-09-30030 September 1993 Updated Trojan Nuclear Div Manual ML20056F9971993-08-26026 August 1993 Rev 9 to Odcm ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20126B7231992-12-0303 December 1992 Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20126B7601992-09-25025 September 1992 Rev 18 to Emergency Instruction EI-3, SG Tube Rupture ML20126B7451992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill ML20126B7491992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump ML20126B7411992-09-25025 September 1992 Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown ML20126B7331992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control ML20126B7061992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired ML20126B7181992-09-23023 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired ML20126B7141992-08-20020 August 1992 Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring ML20210D5281992-06-0808 June 1992 Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20126B7201992-01-24024 January 1992 Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak ML20062F7391990-11-15015 November 1990 Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996 ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247E5331989-03-29029 March 1989 Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure ML20248D3271989-03-27027 March 1989 Rev 0 to QAP-VT-108, Visual Exam ML20247E5491989-03-0202 March 1989 Rev 0 to Procedure TNP-QAP-VT108, Visual Exam ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint 1999-08-05
[Table view] |
Text
.
TABLE 3.3-1 (Continued) own .y ..
Oo 5 - REACTOR TRIP SYSTEM INSTRUMENTATION 2# .
i MINIMUM
~ N.i! ~ TOTAL NO. CHANNELS CHANNELS APPLICABLE ,
om FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION '
u o- -
'$8 18. Turbine Trip 3 ]l.,,!,j A. Low Hydraulic . Control 3 2 2 19 6#
- L 011 Pressure B. Turbine Stop. Valve Closure 4-1/ valve 4-1/ valve 4-1/ valve 1 $. 78 l~
.19. Auto Safety Injection Input 2 1 2 1, 2 1,
~
- 20. . Reactor Coolant Pump Breaker 4-1/ breaker. 2 1/ breaker 19 98 Position Trip' per oper-ating loop
@ a
- 21. Reactor Trip Breakers 2 1 2 1, 2 l'
' 2 1 2 3 *, 4 *, 5* 10 O - -
oO 22. -Automatic Trip Log'ic~
2 1 2 1, 2 1
% 2 1 2 3*, 4*, S* 10 ca o . .
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..~. t LCA 117, Rev. 2 '
Attachment 1 .
Page 15 of 42 .
TABLE 3.3-1 -(Continued) -
- l M a ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement a'nd with the THERMAL POWER level:
- a. Below P-6, restore the inoperabli channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.
- b. Above P-6, operation may continue, provided th'at THERMAL POWER is expeditiously placed within the range of the Soprce Range or Power Range. Instrumentation.
ACTION 4 - With the number of OPERABLE channels one less than the Mini-mum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. -
(- ACTION 5 - With the' number of channels OPERABLE one less than the Mini-mum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may pro
- ceed provided both of the following conditions are satisfied:
j a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. The Minimum Channels OPERABLE requirement is met; how-ever, the inoperable channel may be bypassed for up to l 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.
ACTION 7 - With the number of OPERABLE . channels one less than the Total Number of Channels, place the inoperable channel in the l tripped condition'within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Operation may continue until performance of the next required CHANNEL FUNCTIONAL -
TEST.
ACTION. 8 - With a channel associated with an operating _ loop inoperable, restore the inoperable channel to OPERABLE status. within 2 -
. hours or be in at least HOT' STANDBY within.the ne' x t 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
One channel associated with an operating loop ma~y be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1. .
I
- . TROJAN-UNIT 1 3/4-3-6 . Amendment No. 33, I
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' a e 1
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LCA 117, RIv. 2 *
. Attachment 1 Page 30 of 42 TABLE 3.3-3 (Continued)
ACTION STATEMENTS ACTION 19 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. One channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specifi- l cation 4.3.2.1 provided the other channel is OPERABLE.
ACTION 20 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associa'ted valve inoperable and take the ACTION required by -
Specification 3.7.1.6.
ACTION 21 - With the number of OPERABLE Channels one less than the Total s f- Number of Channels, declare the associated auxiliary
, (- feedwater pump inoperable and apply the requirements of Specification 3.7.1.2. -
ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer Prevents or defeats pressure channels > 1925 manual block of safety psig. injection actuation on low pressurizer pressure.
P-12 With 2 of 4 T avg channels Allows manual block of
< 553*F safety injection actua-tion on high steam line
( flow and low steam line pressure. Causes steam line isolation on high steam flow. Affects steam dump blocks.
P-4 With both reactor trip Allows manual block of breakers open. safety injection actua-tion. .Causes turbine trip. Closes feedwater-valves on low Tavg and prevents their reopening ;
if closed by safety )
injection or high steam generator water level.
P-14 With 2 of 3 steam generator Causes turbine trip and level channels >75% of narrow trips both feedwater range instrument span. pumps. Closes feedwater ,
isolation, bypass, and t!
regulating valves.
. ,. .f JTrojan-Unit 1 - '
3/4 3 Amendment No. 47, h'" :
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LCA 117., Rev. 2
. Attachment 1 Page 42a of 42 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combina-tion thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundaricy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining ~
an appropriate level of reliability of the Reactor Protection and ESF instrumentation.
The OPERABILITY of these systems is required to provide the overall -
(( reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protec-tion Instrumentation System", and supplements to that report as approved by the NRC and documented in the SER (letter to J. J. Sheppard from Cecil 0. Thomas dated February 21,1985).
The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, over-lapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verfication may be demonstrated by either 1) in place, onsite or offsite test measurements o:- 2) utilizing replacement sensors with certified response times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERASILITY of the radiation monitoring channels ensures that
- 1) the radiation levels are continually measured in the areas served TROJAN-UN.IT 1 B 3/4 3-1
.m;
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