Rev 1 to J-26060A, Critical Safety Function ParametersML20101M459 |
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Site: |
Callaway ![Ameren icon.png](/w/images/0/06/Ameren_icon.png) |
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Issue date: |
06/26/1992 |
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From: |
UNION ELECTRIC CO. |
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To: |
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References |
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J-26060A, NUDOCS 9207080242 |
Download: ML20101M459 (5) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20135E7351996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt One H Replacement Matl ML20135E7431996-12-11011 December 1996 Test to Determine Ampacity Derating Factor for Electrical Conductors Installed in 600mm X 101mm X 3650mm Long Cable Tray Encapsulated by KM1 Darmatt Three H Replacement Matl ML20135E7391996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt Three H Replacement Matl ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS 1999-09-08
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117P2281996-02-26026 February 1996 Rev 10 to Maint Mechanical Procedure MTM-ZZ-QV009, Westinghouse Check Valve Disassembly/Reassembly ML20108E3711996-02-16016 February 1996 Rev 5 to Administrative Procedure APA-ZZ-01003, Odcm ML20117P2371995-11-28028 November 1995 Rev 2 to Callaway Plant Bolting Manual ML20076F9881994-10-12012 October 1994 Rev 0 to Second 10-Yr Interval ISI Plan for Callaway Nuclear Power Plant ML20065N4831993-11-24024 November 1993 Temporary Change Notice 93-0955 to Rev 2 to Off-Normal Operating Procedure OTO-RK-00001, Loss of Control Room Alarms ML20101M4591992-06-26026 June 1992 Rev 1 to J-26060A, Critical Safety Function Parameters ML20069B9661992-03-31031 March 1992 Cultural Resources Mgt Plan for Residual Lands at Union Electric Co Callaway Plant,Callaway,Mo ML20094H2821992-01-28028 January 1992 Rev 2 to Administrative Procedure APA-ZZ-01011, Process Control Program Manual ML20195B5301992-01-14014 January 1992 Rev 2 to Spec A-1003(Q), Surface Preparation & Application of Field Coatings ML20079L5141991-11-0404 November 1991 Rev 13 EPIP EIP-ZZ-00241, Fmt Driver Checklist ML20024H2411991-05-24024 May 1991 Rev 12 to Pump & Valve Inservice Testing Program ML20024G9881991-05-0606 May 1991 Rev 5 to Callaway Records Info Sys General Rules for Records Indexing. ML20070W0021991-04-0101 April 1991 Rev 4 to ARIP2371, General Rules ML20066H2601991-01-31031 January 1991 Rev 2 to A120.0021/S236, Signature/Initials Log ML20067D6541991-01-30030 January 1991 Rev 7 to T210.0002/Q101, Qualification/Certification Documentation ML20066L4881991-01-29029 January 1991 Rev 3 to Callaway Records Info Sys General Rules for Records Indexing ML20067D8191991-01-29029 January 1991 Backfit Change Notice 074 to Rev 6 to T210.0002/R353 ML20066L4561991-01-28028 January 1991 Rev 2 to Callaway Records Info Sys General Rules for Records Indexing ML20081E2111990-07-23023 July 1990 Rev 6 to T210.0002/R353, Required Reading/Personnel Form 2 ML20081E2071990-07-23023 July 1990 Rev 6 to T210.0002/Q101, Qualification/Certification Documentation ML20059G5081990-05-31031 May 1990 Rev 0 to APA-ZZ-01003, Odcm ML20042F2861990-03-30030 March 1990 Rev 11 to Inservice Testing Program. ML20058N2841990-02-0606 February 1990 Rev 4 to T210.0002/D157, Delegation of Authority ML20247D8361989-07-24024 July 1989 Process Control Program Manual ML20247D8291989-07-19019 July 1989 Odcm ML20246L8221989-05-31031 May 1989 Rev 6 to Callaway Plant,Odcm ML20151R2591988-03-31031 March 1988 Rev 10 to Inservice Testing Program Class 1,2 & 3 Pumps ML20154E5101988-02-29029 February 1988 Offsite Dose Calculation Manual ML20236W7151987-11-0303 November 1987 Rev 1 to Nuclear Function Administrative Procedure APA-ZZ-00645, Simulator Configuration Mgt ML20236F7431987-07-31031 July 1987 Rev 9 to Inservice Testing Program,Callaway Nuclear Plant ML20206N4781987-04-0808 April 1987 Rev 8 to Inservice Testing Program,Callaway Nuclear Plant ML20207Q1561987-01-15015 January 1987 Rev 7 to Inservice Testing Program,Callaway Nuclear Plant ML20154J0751986-02-14014 February 1986 Rev 6 to Inservice Testing Program,Callaway Nuclear Plant ML20134D0441985-07-25025 July 1985 Rev 5 to Inservice Testing Program ML20140F5191985-06-28028 June 1985 Rev 4 to, Inservice Testing Program,Callaway Nuclear Plant ML20100E9791985-03-31031 March 1985 Procedure for Performing Task Analysis (& Verification) for Snupps Detailed Control Room Design Review ML20099J0791984-12-31031 December 1984 Corrected Rev 3 to Table, Inservice Testing Program, Inservice Insp Class 1,2 & 3 Pumps ML20093F3491984-10-31031 October 1984 Procedure for Performing Task Analysis & Verification for Detailed Control Room Design Review 1998-07-31
[Table view] |
Text
i DATE: 0'6/26/92 UNION ELECTRIC COMPANY PAGE: 1 TIME: 13:58:47
- DOCUMENT CONTROL SYSTEM ARDC8811 4 DOCUMENT TRANSMITTAL TRANSMITTNL NUMBER: 224352 RETURN ACKNOWLEDGED TRANSMITTAL AND TO CONTROL NUMBER: 338 SUPERSEDED DOCUMENTS (IF APPLICABLE) TO:
TITLE: OTHER ADhfNISTRATION RECORDS DEPT: NUCLEAR REGULATORY COMM. UNION ELECTRIC COMPANY LOCATION: WASHINGTON, DC CALLAWAY PLANT TRANSMITTAL DATE: 920626 P.O. BOX 620 FULTON, MO 65251 a TRAN DOC RET ALT ALT j CODE TYPE DOCUMENT NiTMBER REV REV MED COPY MED COPY AFFECTED DOCUMENT R DRAW J-26060A 001 000 C 1 l
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\0 $8 56 i 9207080242 920626 PDR ADOCK 05000483 6g[
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! REV.! APPR. ? DATE ! REV.! APPR. ! DATE !
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J-26060A CRITICAL SAFETY FUNCTION PARAMETERS COMPUTER PARAMETER PARAMETER DESCRIPTION UNITS POINT REACTIVITY CONTROL NI POWER RNG Nuclear Instruments, Powcr Range % SPDS0059 NI IhTER RNG Nuclear Instruments, Intermediate Range AMPS SPDS0060 NI SOURC RNG Nuclear Instruments, Source Range CPS SPDS0041 >
NL Post Accident Wide Range % SEN0701 NL Post Accident Source Range CPS SEN0702 CORE COOLING i REAC VES LEV Reactor Vessel Water Level % REUO523 TEMP CORE EX Highest Temperature at the Core Exit DEGF AEU0090 SUB MARGIN Saturation Temperature-Highest CET DEGF SPDS0006 CORE FLOW Total Reactor Coolant Flow 4 REUO497 STEAM GENERATORS
( SG LEVEL 1/A SG LEVEL 2/B Steam Generator Steam Generator 2 (or B) Water Level (o A) Water Level %
RELO404A RELO424A SG LEVEL 3/C Steam Generator 3 (or C) Water Level % RELO444A SG LEVEL 4/D Steam Generator 4 (or D) Watcr Level % RELO 4 'J4 A SG PRESS 1/A Steam Genere. tor 1 (or A) Pressure PSIG SPDS0022 SG PRESS 2/B Steam Generator 2 (or B) Pressure PSIG SPDS0023 SG PRESS 3/C Steam Generator 3 (or C) Pressure PSIG SPDS0024 SG PRESS 4/D Steam Generator 4 (or D) Pressure PSIG SPDS0025 MN FD FL 1/A Stm Gen 1 (or A) Main Feedwater Flow KLB/HR SPDS0026 MN FD FL 2/B Stm Gen 2 (or B) Main Feedwater Flow KLB/HR SPDS0027 MN FD FL 3/C Stm Gen 3 (or C) Main Feedwater Flow KLB/HR SPDS0028 MN FD FL 4/D Stm Gen 4 (or D) Main Feedwater Flow KLB/HR SPDS0029 AX FD FL 1/A Stm Gen 1 (or A) Auxillary FW Flow KLB/HR SPDS0054 AX FD FL 2/B Stm Gen 2 (or B) Auxiliary FW Flow "LB/HR SPDS0055 AX FD FL 3/C Stm Gen 3 (or C) Auxiliary FW Flow sB/HR SPDS0056 AX FD FL 4/D Stm Gen 4 (or D) Aux!.li9ry FW Flow KLB/HR SPDS0057 HL TEMP 1/A Stm Gen 1 (or A) Inlet temperature DEGF SPDS0030 HL TEMP 2/B Stm Gen 2 (or B) Inlet Temperature DEGF SPDS0031 HL TEMP 3/C Stm Gen 3 (or C) Inlet Temperature Dr1F SPDS00?2 HL TEMP 4/D Stm Gen 4 (or D) Inlet Temperature DEGF SPDS0033 CL TEMP 1/A Stm Gen 1 (or A) Outlet Temperature DEGF SPDS0034 CL TEMP 2/B Stm Gen 2 (or B) Outlet Temperature DEGF SPDS0035 CL TEMP 3/C Stm Gen 3 (or C) Outlet Temperature DEGF SPDS0036 CL TEMP 4/D Stm Gen 4 (or D) Outlet Temperature DEGF SPDS0037 O
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t - J-26060A '
Rev. 1 1
DATA POINT LIBRARY REFERENCE FILE i i
- Date
- 06/25/92 Reactor Unit: CW1 Data Feeder: N/A 1
NRC ERDS Parameter: NL Point ID: SEN0701
'i POST ACCIDENT WIDE RANGE Plant Spec Point Desc:
, Generic /Cond Desc: POST ACCIDENT WIDE RANGE
- Analog / Digital: A 1 s'ngr Units / Dig States: %
j Engr Units Conversion: N/A Minimum Instr Re'.ge: 1.000E-08 3
Maximum Instr Dange: 2.000E+0?
Zero Point
Reference:
N/A
- Reference Point Notes
- N/A j PROC or SENS: P
- Nunber of Sensors
- 2 i How Processed: AVERAGE Sensor Locations: REACTOR CA7ITY
- Alarm / Trip Set Points: N/A i HI Detector Power Supply Cut-off Power Level N/A
, !!I Detector Power Supply Turn-on Power Level: N/A t Instrument Failure Mode: LOW
', Temperature Compenstdon l
For DP Transmitters: N/A Level Reference Leg: N/A Unique System Dest: MAY FAIL HIGil.
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