|
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
Text
F. . -
- o. .
TABI_E OF CONTENTS (Continued)
-I ERRE 2.12 Control Room Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 59 2.13 Nuclear Detector Cooling System . . . . . . . . . . . . . . . . . ... ........ . . . 2-60 .
2.14 Engineered Safety Features System Initiation Instrumentation Settings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 241 '
2.15 Instrununtation and Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 245 Ri ver l. eve l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-71 2.16 2.17 Miscellaneous Radioactive Material Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 72 2.18 Shock Suppressors (Soubbers) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-73 ,
2.19 DELETED l 2.20 Steam Generator Coolant Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-96 2.21 Post-Accident Monitoring Instmmentation . .. .. .. . . . . . . .. . . .. . .. . . . . .. 2-97 2.22 Te-M @ M 9 ............... ...... ....... ......2^^-
DEL.ETED .
3.0 SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-0 3.1 Instrumentation and Control . . . ..... ................. . . ... .... 3-1 3.2 Equipment and Sampimg Tests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 17 3.3 Reactor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance . . . . . . . . . . . . . . . . . . . . . . 3 -21 3.4 Reactor Coolant System Integrity Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 36 3.5 Containment Test ....... .............. ..... ....... . . . . . 3 37 3.6 Safety injection and Containment Cooling Systems Tests . . . . . . . . . . . . . . . . . . . 3 -5 4 3.7 Emergency Power System Periodic Tests . ........................... 3-58 3.8 Main Steam isolation Valves ........................ .......... .341 3.9 Auxiliary Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 342 3.10 Reactor Core Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 63 3.11 DELETED 3 di 3.12 Radioactive Waste Disposal System ....................... ........ 349 3.13 Radioactive Matenal Sources Surveillance ........... ........... . . . . 3 -76 3.14 Shock Suppressors (Snubbers) ............. .. ... . . . . . . . . . . . . . . . 3 -77 3.15 DELETED l 3.16 Residual Heat Removal System Integrity Testing ........................384 3.17 Steam Generatur Tubes . . . . ..................................386 l 4.0 DESIGN FEATURES ........ ............. . . . .. .............41 4.1 Site................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2 Containment Design Features .................. ..................41 4.2.1 Containment Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1 ,
4.2.2 Penetrations . ..... . ... ... ... . .. . . . . ... . . . . .. . .. . . ... . . 4-1 4.2.3 Containment . Structure Cooling Systems .........................42 1
i e
ii Amendment No. 84r8J,03.101.!:2.236.!52360' i i
9501230320 950109 PDR ADOCK 050002B5 P. PDR
1
)
i 1
e TECHNICAL SPECIFICATIONS - TABIFC TABLE OF CONTENTS TABLE DESCRIPTION PAGE 11 R.PS LS S S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 10
................................................. 1.!0s !
2-1 ESFS Initiation Instrumentation Setting Limits . . . . . . . . . . . . . . . . . . . . . . . . . . 244 l i
.......................... 2 44a ;
22 Instrument Operating Requirements for RPS . ......................... 247
................................247a 23 Inrtrument Operating Requirements for Engineered Sa fety Featu res . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 48
..................................248a
........... .... ........ ........ . . . . . . . . . . . 24 8b 24 Instrument Operatmg Con 6tions for Isolation Functions . . .................249
...... . . . . . . . . . . . . . . 2 49a 25 Instrumentation Operating Requirements for Other Safety Feature Functions . . . . . . . 2-70 '
29 RCS Pressure Iv,lation Valves
. . ... . ... .... . ..... . . . .. . . . .. . . .. . 2-2e 2 10 Post. Accident Monitoring. Instrumentation Operating Limits . . . . . . . . . . . . . . . . . 2-98 '
j.
s . . . . . . . . . . . . . . . . . . . . . 2-9 8a
. . . . . . . . . . . . . . . . . . . . . 2 -9 8b
- -. . - .1
-4 um un m e...m. . m_m.. _. ... .. . a.-mu u .
. . ........ , , n_ n_ _
31 Minimum Frequencies for Checks. Cahbrations, and Testing of RPS . . . . . . . .. . ............. .... . . . . . . . . . . . 3-3
.... ................. ... ... .. . . . . . . . . . . 3-4 :
. ..... . ...... . .... . .. .. .. .. . . .. . .. 3-5
...................................... 34 ;
r 32 Minimum Frequencies for Checks. Calibrations and Testing of 1 Engineered Safety Features. Instrumentation and Controls . . . . . . . . . . . . . . . . . . . . 3 7 .
.......................38 :
... ..... ..... .. .. ...... 3-9
.....................310
.......................311 '
....... ....... . . . . . . 3-12 *
.. . ..... ..... .... .. .. 3-12a 1
\
i iv Amendment No. '!5,!?f M i
TECHNICAL SPECIFICATIONS - TABLES TABLE OF CONTENTS (ALPHABETICAL ORDEID Continued TABLE DESCRIPTION PAGE 3-5 Minimum Frequencies for Equipment Tests ...........................320
. . .. . . . . .. .. . .... . . . . .. . . . . .. . .. 3-20s
................................3-20b
. . .. . .. .. . . . ... ... .. . . . . . . . . .... 3-20e
................................320d 3-4 Minimum Frequencies for Sampling Tests ............................3-18
.................................3-19 5.2 1 Minimum Shift Crew Composition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 P
2 10 Post-Accident Monitoring Instrumentation Operating Limits . . . . . . . . . . . . . . . . . 2-9 8
. . . . . . . . . . . . . . . . . . . . . 2-9 8a
. . . . . . . . . . . . . . . . . . . . . 2 -9 8 b l
2-9 RCS Pressure Isolation Valves .... ...............................2-2d 3-6 Reactor Coolant Pump Surveillance ................................327 11 RPS LSSS . . . . . .. . . . ...... .............................110
- . .. . .. . . . .. . . . .. . . . . .. . . . .. .. .. ... . . . . . .. . .. .... 1-10m 3-14 Snubber Visual Inspection Interval . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-79b 3 13 Steam Generator Tube Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-90
+1 ! Tenie-Ge Mc:O: ; Wed; Use ...... .. . . . . . . . . .-- L100--
.(
vii Amendment No. 4M l
- . - . =.- - - - - - -- . . . . .
4
- ) l ihC- gniiii.G C0=!T!0"5 N OPN!0" -
i 2.22 Tuxic GB Mont tors i I
Applicability N I Applies to toxic gas monitors which monitor the fresh air to the ntrol I room. This spe.cificatior, is applicable in all modes. i Objective 2 To assure that redundant toxic gas monitors which are ed for continuous '
r measurement of the fresh air to the control room ar perational. l Specifications 1 Toxic gas monitors shall be operable as p ided in Table 2-11. If t
the required instrumentation is not op ble, then the appropriate action !'
specified in Table 2-11 shall be ta .
Basis {
The redundant toxic gas .
to isolate the control tors were designed to detect toxic gases and or offsite toxic gas ccident.ventilation system in the event of an onsite om ,
If both of the oxic gas detectors are found inoperable, there is no imediate cont inu at to the control room operators and reactor operation may ile repairs are being raade. During this repair, tha control ,
room ! !
o a tiontilation n_ will be switched to internal recirculation mode of l '
N i h
I r
s 2-99 Amendment No.,I k,-
)
ew 4-- ,,- -. , , -
e<~c ' , . - -,
__,,,__ JABL E _2-31 T0XIC GAS MONITORS OPERATING LIMITS Minimum Instrument Operable Cha nnels/ ' Action
- 1. Chlorine Detectors * ,
2 (a) (b) ;
- 2. Hydrochloric Acid, and
. Sulfuric Acid Detectors' 2 (a)(b)
- 3. Hydrazine* Ammonia Det cfors 2 (a)(b)
(a) With one toxic detector inoperable, restore the inoperable detector to OPERABLE sta d's within 7 days, or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain o ration of the control room ventilation system in the recircul ion mode of operation.
(b) Wit oth toxic detectors inoperable, 94 thin I hoer 44ittet'e and maln-t) n operation of the control room ventilation system in the recircula- '
tion mode of operation.
- 0nsite-ChemicaHierares-are-EMerine, Suirurre Ac1a anc riydruine. --
l t
i 2-100 Amendt.sent No. 81/, -0E7-
=
. s,
.ove.= A j
TABLE 3-3 (Continued)
MINIMUM FREQUENCIES F0l1 CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUE NTATION AND CONTROLS Channel Description Survelliance Function Frequency Surveillance Method
- 25. Containment Purge Isolation Check M i
Valves (PCV-742A, 8, C, & D) Verify valve position using control 1 room indication. i
- 26. Containment Hydrogen a. Check M !
Monitors (VA-81A&B) a. Comparison of readings from redun-dant channels.
- b. Test Q b. Calibrate span /zero using sample i'
gas and check flow rates.
o, o' c. Calibrate R
- c. Calibrate using known signals applied to sensors.
- 27. Containment Water Level a. Check Harrow Range (LT-599 & 5 - a. Compare independent level readings.
LT-600) b. Calibrate 3I R b. Known signals applied to sensors.
g Wide Range (LT-387 & a. Check H
! LT-388 a. Observe normal reading and simulate A full scale reading.
- b. Calibrate R
- b. Known signals applied to sensors.
[, 28. Containment Wide Range
?*
- a. Check M Prassure Indicatfor a. Compare independent pressure readings.
?" b. Calibrate R DEM4FDED b. Apply known pressure to sensors.
, 29. T::ic Ge5 SetecToiT:
!* Y;T-0200A;0 (Cig F e Ch;;k gx V17-6200A;0 (:C . -1F' a-en 9mee r - cf 7;;;;;;; 77;_ 7;; ;,_
~ u_m i . dant-chawels f ~* ~9' b+-4(ti'--*- -ft' i
! b. "21fbrat: ; ;;/;ers esir.9 cel;L..iion e
c re !!S :n -R-- e rceel!'tSet= r -f>=ra e*ia- car adi"s * ::t unh sei simida us. 4_. and veri fy usi=0
_ - - - - . _ _ - - - - - - - - - - - - - = - - -
(. . ,l TABLE 3-3 (Continued)
MIfilHUM FREQUENCIES FOR CHECKS, CALIBRATIONS AtfD TESTING OF MISCELLANEOUS INSTRUMENTATIDif AND CONTHDt_s Surveillance Channel Description Function Frequency Surveillance tiethod
,,, -,m ,... i .,
u wcum.. w g ,.4 , ..,.3-4 ,
-. e- -k.a,
- - _g., -
ra-rarison of readings from u Ca l ib ra4+--. 4 4. Ge5 ceifbrat-ien. #
- 30. Core Exit Therruocouple a. Check H a. Con:parf snn of readiiigs fros:
reduno' ant channels,
- b. Calibrate R b. Calibration of A/D converters from known voltage sources.
E
- 31. Heated Junction Thermocouple (YE-116A ar.d YE-1168) a. Check H a .- Comparison readlings frca redundant channels.
- b. Calibrate R b. Ca'11bration of A/D converters from known voltage sources.
2 n
5
( PM - Prior to scheduled cold leg cooldown below 300*F; monthly whtnever tesiperature remains below 300*F and reactor vessel head is installed.
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