ML18051B460: Difference between revisions

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===4.2 PLANT===
===4.2 PLANT===
SAFETY ENGINEERING (PSE) Proc No 4.08 Revision 0 Page 2 of 9 PSE shall perform an assessment of every inadvertant plant trip and provide the results of such assessment to the Plant General Manager in accordance with Reference 3.7. 4.3 OPERATIONS SUPERINTENDENT For a Condition II event, as determined by Step 5.3.4, the Operations Superintendent or his designated alternate shall: a. Report to the Plant site to assist in the further investigation of the trip and to determine necessary corrective action before restart. b. Analyze the event reconstruction and supply information*per Step 5.4.2 to the Plant General Manager. 4.4 LEAD SHIFT ENGINEER The Lead Shift Engineer shall review all completed Reactor Trip Reports. 4.5 DUTY SHIFT ENGINEER The Shift Engineer (SE) on duty shall: a. Complete offsite personnel and agency notification in accordance with Reference 3.6 and 3.8 as apprpriate.  
SAFETY ENGINEERING (PSE) Proc No 4.08 Revision 0 Page 2 of 9 PSE shall perform an assessment of every inadvertant plant trip and provide the results of such assessment to the Plant General Manager in accordance with Reference 3.7. 4.3 OPERATIONS SUPERINTENDENT For a Condition II event, as determined by Step 5.3.4, the Operations Superintendent or his designated alternate shall: a. Report to the Plant site to assist in the further investigation of the trip and to determine necessary corrective action before restart. b. Analyze the event reconstruction and supply information*per Step 5.4.2 to the Plant General Manager. 4.4 LEAD SHIFT ENGINEER The Lead Shift Engineer shall review all completed Reactor Trip Reports. 4.5 DUTY SHIFT ENGINEER The Shift Engineer (SE) on duty shall: a. Complete offsite personnel and agency notification in accordance with Reference 3.6 and 3.8 as apprpriate.
: b. Interview plant personnel involved in the trip. c. Collect data for inclusion in trip report. d. Make recommendations to Plant General Manager on reactor startup. e. Prepare Trip Report. 4.6 SHIFT SUPERVISOR/OPERATIONS The Shift Supervisor/Operations (SS) shall: a. Assist the SE with data collection as Plant conditions allow. b. Make recommendation to Plant General Manager on reactor startup. c. Assure Plant shutdown actions are completed after the reactor trip. d. Maintain the Plant in a safe condition.
: b. Interview plant personnel involved in the trip. c. Collect data for inclusion in trip report. d. Make recommendations to Plant General Manager on reactor startup. e. Prepare Trip Report. 4.6 SHIFT SUPERVISOR/OPERATIONS The Shift Supervisor/Operations (SS) shall: a. Assist the SE with data collection as Plant conditions allow. b. Make recommendation to Plant General Manager on reactor startup. c. Assure Plant shutdown actions are completed after the reactor trip. d. Maintain the Plant in a safe condition.
ad0285-0014a-93-154 INFORMATION COPY   
ad0285-0014a-93-154 INFORMATION COPY   
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Strip chart recordings must accurately reflect real time to have meaningful information.
Strip chart recordings must accurately reflect real time to have meaningful information.
If this is not the case, the SE should ensure the chart paper is annotated with a time mark, chart speed (chart speed may change during the transient), and time scale. Operator Statements After the plant is in a safe, stable condition, the SE should ensure each individual involved in the trip (eg, reactor operator, man/technician, Maintenance Supervisor, etc) provides a statement concerning his/her involvement in the reactor trip. These statements may be obtained in one of the following ways: ad0285-0014a-93-154 iNFORMATION COPY   
If this is not the case, the SE should ensure the chart paper is annotated with a time mark, chart speed (chart speed may change during the transient), and time scale. Operator Statements After the plant is in a safe, stable condition, the SE should ensure each individual involved in the trip (eg, reactor operator, man/technician, Maintenance Supervisor, etc) provides a statement concerning his/her involvement in the reactor trip. These statements may be obtained in one of the following ways: ad0285-0014a-93-154 iNFORMATION COPY   
*, .. 5.2.3 5.2.4 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS  
*, .. 5.2.3 5.2.4 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS
: a. Written operator statements (use Attachment 2). Proc No 4.08 Revision 0 Page 4 of 9 b. SS/SE interviews with personnel involved in the reactor trip. c. Critique with all involved personnel.
: a. Written operator statements (use Attachment 2). Proc No 4.08 Revision 0 Page 4 of 9 b. SS/SE interviews with personnel involved in the reactor trip. c. Critique with all involved personnel.
If either of the last two techniques are used, the information should be recorded to ensure future availability of the information.
If either of the last two techniques are used, the information should be recorded to ensure future availability of the information.
The operator statements should be restricted to facts concerning the event, and the facts should be stated chronologically, if possible.
The operator statements should be restricted to facts concerning the event, and the facts should be stated chronologically, if possible.
The statement should include the following:  
The statement should include the following:
: a. Plant conditions prior to the trip (for maintenance personnel, this will include the status of maintenance or testing).  
: a. Plant conditions prior to the trip (for maintenance personnel, this will include the status of maintenance or testing).
: b. First indication that a problem existed. c. Individual's actions as a result of the indications.  
: b. First indication that a problem existed. c. Individual's actions as a result of the indications.
: d. Subsequent indications and plant response, including manual actions. e. Noted equipment malfunctions or inadequacies.  
: d. Subsequent indications and plant response, including manual actions. e. Noted equipment malfunctions or inadequacies.
: f. Procedure deficiencies identified during the situation.  
: f. Procedure deficiencies identified during the situation.
: g. Recommendations to prevent recurrence.
: g. Recommendations to prevent recurrence.
The written statements or tape recordings shall be included in the reactor trip data package to assist in the event reconstruction.
The written statements or tape recordings shall be included in the reactor trip data package to assist in the event reconstruction.
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The SE will reconstruct the transient in Part 3 of the Post-Trip Review Report, Attachment 1, using the collected data. A chronological description of the event will be developed, using all available data. Pertinent alarms, trips, actuations, and isolations will be listed or marked on the of-events or Feedwater Purity Data Logger printout.
The SE will reconstruct the transient in Part 3 of the Post-Trip Review Report, Attachment 1, using the collected data. A chronological description of the event will be developed, using all available data. Pertinent alarms, trips, actuations, and isolations will be listed or marked on the of-events or Feedwater Purity Data Logger printout.
Pertinent plant parameters should be incorporated into the chronological list of events during the reconstruction.
Pertinent plant parameters should be incorporated into the chronological list of events during the reconstruction.
Analysis and Evaluation The Shift Supervisor, and the Shift Engineer shall analyze and evaluate the event reconstruction to determine the cause of the trip and the following:  
Analysis and Evaluation The Shift Supervisor, and the Shift Engineer shall analyze and evaluate the event reconstruction to determine the cause of the trip and the following:
: a. If all major safety-related and other important equipment involved in the trip operated as anticipated or expected.  
: a. If all major safety-related and other important equipment involved in the trip operated as anticipated or expected.
: b. If the trip/transient caused any detrimental effects on plant equipment.  
: b. If the trip/transient caused any detrimental effects on plant equipment.
: c. If it is acceptable to restart the reactor. The Shift Supervisor and the Shift Engineer should look beyond the obvious indications to diagnose the cause of the trip and evaluate the plant response.
: c. If it is acceptable to restart the reactor. The Shift Supervisor and the Shift Engineer should look beyond the obvious indications to diagnose the cause of the trip and evaluate the plant response.
They should review the available information thoroughly, looking for: a. abnormal indications or degraded trends in equipment performance, b. events occurring out of the normal or anticipated sequence, c. failed or degraded response of equipment to control signals, d. . unusual chemistry results or radiation readings, and e. unanticipated alarms. The actual or suspected cause of the trip and any abnormal or degraded indication identified during the transient shall be documented in Parts 4 through 6 of the Post-Trip Review Report. ad0285-0014a-93-154 INFORMATION COPY 5.3.3 5.3.4 5.3.5 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS Preliminary Safety Assessment Proc No 4.08 Revision 0 Page 6 of 9 A preliminary safety assessment of the trip and subsequent plant response shall be performed by the Shift Supervisor and the Shift Engineer.
They should review the available information thoroughly, looking for: a. abnormal indications or degraded trends in equipment performance, b. events occurring out of the normal or anticipated sequence, c. failed or degraded response of equipment to control signals, d. . unusual chemistry results or radiation readings, and e. unanticipated alarms. The actual or suspected cause of the trip and any abnormal or degraded indication identified during the transient shall be documented in Parts 4 through 6 of the Post-Trip Review Report. ad0285-0014a-93-154 INFORMATION COPY 5.3.3 5.3.4 5.3.5 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS Preliminary Safety Assessment Proc No 4.08 Revision 0 Page 6 of 9 A preliminary safety assessment of the trip and subsequent plant response shall be performed by the Shift Supervisor and the Shift Engineer.
The maximum and minimum values of selected parameters shall be compared with their established limits in the Technical Specifications.
The maximum and minimum values of selected parameters shall be compared with their established limits in the Technical Specifications.
Parts 7 and & of the Post-Trip Review Report will document this safety assessment.
Parts 7 and & of the Post-Trip Review Report will document this safety assessment.
Trip Classification Based on the results of the analysis and evaluation of the plant trip and subsequent response, the Shift Supervisor and the Shift Engineer shall classify the event as one of the following conditions:  
Trip Classification Based on the results of the analysis and evaluation of the plant trip and subsequent response, the Shift Supervisor and the Shift Engineer shall classify the event as one of the following conditions:
: a. Condition I The cause of the trip is positively known and has been corrected; all safety-related and other important equipment functioned properly during the trip, or if not, the malfunction has either been corrected or redundant equipment is available for reactor start-up.  
: a. Condition I The cause of the trip is positively known and has been corrected; all safety-related and other important equipment functioned properly during the trip, or if not, the malfunction has either been corrected or redundant equipment is available for reactor start-up.
: b. Condition II 1. The cause of the trip is not positively known. Or 2. Safety related equipment or other equipment functioned in an abnormal or degraded manner during the trip and the malfunction has not been corrected.
: b. Condition II 1. The cause of the trip is not positively known. Or 2. Safety related equipment or other equipment functioned in an abnormal or degraded manner during the trip and the malfunction has not been corrected.
Or 3. Safety related equipment or other equipment functioned in an abnormal or degraded manner during the trip and redundant equipment is not available for startup. If the Shift Supervisor and Shift Engineer cannot agree on tion of the transient, the event will be referred to the Plant General Manager for re-evaluation and classification.
Or 3. Safety related equipment or other equipment functioned in an abnormal or degraded manner during the trip and redundant equipment is not available for startup. If the Shift Supervisor and Shift Engineer cannot agree on tion of the transient, the event will be referred to the Plant General Manager for re-evaluation and classification.
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Sources of expertise that should be considered include nuclear steam supply vendors, vendor engineers, onsite engineering staff and other experienced operations and.maintenance personnel.
Sources of expertise that should be considered include nuclear steam supply vendors, vendor engineers, onsite engineering staff and other experienced operations and.maintenance personnel.
The Operations Superintendent should supply the following information to the Plant Manager:
The Operations Superintendent should supply the following information to the Plant Manager:
* a. The actual or most probable cause of the trip. b. The maintenance and testing necessary before reactor restart including additional measures to verify the most probable cause. c. Additional monitoring or trending required during and/or after reactor restart. d. Necessary briefings to operations and/or maintenance personnel concerning specific equipment indications or possible malfunctions.  
* a. The actual or most probable cause of the trip. b. The maintenance and testing necessary before reactor restart including additional measures to verify the most probable cause. c. Additional monitoring or trending required during and/or after reactor restart. d. Necessary briefings to operations and/or maintenance personnel concerning specific equipment indications or possible malfunctions.
: e. The conditions necesary for a reactor restart. Plant General Manager Evaluation and Decision The Plant General Manager should evaluate the recommendation made by the personnel performing the trip investigation.
: e. The conditions necesary for a reactor restart. Plant General Manager Evaluation and Decision The Plant General Manager should evaluate the recommendation made by the personnel performing the trip investigation.
The Plant General Manager should consider convening the PRC to review the trip investigation prior to reactor restart for Condition II events. The ad0285-0014a-93-154 INFORMATION COPY   
The Plant General Manager should consider convening the PRC to review the trip investigation prior to reactor restart for Condition II events. The ad0285-0014a-93-154 INFORMATION COPY   
*, 5.5 5.5.1 5.5.2 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS PRC can advise the Plant General Manager on the thoroughness, technical accuracy and consistency of the trip investigation.
*, 5.5 5.5.1 5.5.2 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS PRC can advise the Plant General Manager on the thoroughness, technical accuracy and consistency of the trip investigation.
Proc No 4.08 Revision 0 Page 8 of 9 The Plant General Manager's decision to restart the reactor shall include the following considerations:  
Proc No 4.08 Revision 0 Page 8 of 9 The Plant General Manager's decision to restart the reactor shall include the following considerations:
: a. The most probable cause of the trip is known and corrected.  
: a. The most probable cause of the trip is known and corrected.
: b. Major safety-related and other important equipment functioned properly during the transient, or corrective maintenance and satisfactory testing has been performed or will be completed when plant conditions permit. c. The plant response during the event has been analyzed and the plant responded as anticipated, or all abnormalties are understood and corrected as required by Technical Specifications.
: b. Major safety-related and other important equipment functioned properly during the transient, or corrective maintenance and satisfactory testing has been performed or will be completed when plant conditions permit. c. The plant response during the event has been analyzed and the plant responded as anticipated, or all abnormalties are understood and corrected as required by Technical Specifications.
If the cause of the trip has not been positively identified, the Plant General Manager shall determine if the cause and the circumstances surrounding the cause have been analyzed adequately.
If the cause of the trip has not been positively identified, the Plant General Manager shall determine if the cause and the circumstances surrounding the cause have been analyzed adequately.
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* POST-TRIP REVIEW REPORT Date of Occurrence:
* POST-TRIP REVIEW REPORT Date of Occurrence:
Time of Occurrence:
Time of Occurrence:
PART 1: INITIAL CONDITIONS  
PART 1: INITIAL CONDITIONS
: a. Reactor Power % b. Reactor Coolant Pumps Operating (circle) A B c. Hain Feed Pump(s) Operating (circle) A B d. Status of Control Stations (circle) 1. Turbine Control Han 2. A Feedpump Control Han B Feedpump Control Han 3. A Hain Feedwater Reg Valve Han B Hain Feedwater Reg Valve Man 4. Turbine Bypass Valve (-l.--i-CV-0511)
: a. Reactor Power % b. Reactor Coolant Pumps Operating (circle) A B c. Hain Feed Pump(s) Operating (circle) A B d. Status of Control Stations (circle) 1. Turbine Control Han 2. A Feedpump Control Han B Feedpump Control Han 3. A Hain Feedwater Reg Valve Han B Hain Feedwater Reg Valve Man 4. Turbine Bypass Valve (-l.--i-CV-0511)
Man s. Pressurizer Level Control Channel A/B Han 6. Pressurizer Pressure Control Channel A/B Man e. PORV Block Valves (circle) OPEN f. Off-normal Status (of any trains/portions of safety systems) Proc No 4.08 Attachment 1 Revision 0 Page 1 of 12 c D Oper Auto Imp In/Imp Out Auto Auto Auto Auto Auto Auto Auto CLOSED DETAILS 1. Reactor Protection System 2. Safety Injection Actuation.
Man s. Pressurizer Level Control Channel A/B Han 6. Pressurizer Pressure Control Channel A/B Man e. PORV Block Valves (circle) OPEN f. Off-normal Status (of any trains/portions of safety systems) Proc No 4.08 Attachment 1 Revision 0 Page 1 of 12 c D Oper Auto Imp In/Imp Out Auto Auto Auto Auto Auto Auto Auto CLOSED DETAILS 1. Reactor Protection System 2. Safety Injection Actuation.
System ad0285-0014b-93-154 fNFORMATION COPY
System ad0285-0014b-93-154 fNFORMATION COPY
* POST-TRIP REVIEW REPORT 3. Containment Cooling & Spray 4. Auxiliary Feedwater  
* POST-TRIP REVIEW REPORT 3. Containment Cooling & Spray 4. Auxiliary Feedwater
: g. Testing/Surveillances in progress:
: g. Testing/Surveillances in progress:
ad0285-0014b-93-154 Test Ii Proc No 4.08 Attachment 1 Revision 0 Page 2 of 12 Status/Step fNFORMATION COPY r   
ad0285-0014b-93-154 Test Ii Proc No 4.08 Attachment 1 Revision 0 Page 2 of 12 Status/Step fNFORMATION COPY r   
.. -POST-TRIP REVIEW REPORT PART 2: PLANT RESPONSE a. Obtain a copy of the applicable parameter Check If Included Parameter  
.. -POST-TRIP REVIEW REPORT PART 2: PLANT RESPONSE a. Obtain a copy of the applicable parameter Check If Included Parameter
: 1. Rx Power 2. Pzr Level 3. Pzr Pressure 4. T ave s. Tc WR 6. SG Levels b. Obtain a Printout from: 1. Tennecomp Data Logger 2. Event Recorder 3. Critical Function Monitor plots given below: Proc No 4.08 Attachment 1 Revision 0 Page 3 of 12 c. Obtain pertinent logs from past 24 hours (Chemistry, Control Room, Auxiliary Operator, etc). d. Safety System Actuation and Performance  
: 1. Rx Power 2. Pzr Level 3. Pzr Pressure 4. T ave s. Tc WR 6. SG Levels b. Obtain a Printout from: 1. Tennecomp Data Logger 2. Event Recorder 3. Critical Function Monitor plots given below: Proc No 4.08 Attachment 1 Revision 0 Page 3 of 12 c. Obtain pertinent logs from past 24 hours (Chemistry, Control Room, Auxiliary Operator, etc). d. Safety System Actuation and Performance
: 1. Reactor Protection System Type of Trip: Time of Trip: 2. Safety Injection Actuation System Actuation Signal/ Actuation Time Number of Trains HPSI I LPSI I 3. Containment Isolation I ad0285-0014b-93-154 INFORMATION COPY   
: 1. Reactor Protection System Type of Trip: Time of Trip: 2. Safety Injection Actuation System Actuation Signal/ Actuation Time Number of Trains HPSI I LPSI I 3. Containment Isolation I ad0285-0014b-93-154 INFORMATION COPY   
.. POST-TRIP REVIEW REPORT 4. PZR Code Safety Valves Lifted Did they reseat properly?
.. POST-TRIP REVIEW REPORT 4. PZR Code Safety Valves Lifted Did they reseat properly?
How Confirmed?  
How Confirmed?
: 5. Main Steam Relief Valves Lifted Did they reseat properly?
: 5. Main Steam Relief Valves Lifted Did they reseat properly?
How confirmed?  
How confirmed?
: e. Control System Actions 1. Turbine Trip 2. PCS Pressure Control Did PORV lift? Was PZR heater response normal? Was PZR spray response normal? Was PZR level control normal? 3. Were additional HPSI pumps started? Auto Start Manual Start f. Manual Actions Were any control stations taken from Auto to Manual? ad0285-0014b-93-154 Trip Time Trip Signal Signal Time Start Time Stop Proc No 4.08 Attachment 1 Revision 0 Page 4 of 12 YES NO YES NO YES NO YES NO (circle) YES NO YES NO YES NO YES NO YES NO YES NO INFORMATION COPY   
: e. Control System Actions 1. Turbine Trip 2. PCS Pressure Control Did PORV lift? Was PZR heater response normal? Was PZR spray response normal? Was PZR level control normal? 3. Were additional HPSI pumps started? Auto Start Manual Start f. Manual Actions Were any control stations taken from Auto to Manual? ad0285-0014b-93-154 Trip Time Trip Signal Signal Time Start Time Stop Proc No 4.08 Attachment 1 Revision 0 Page 4 of 12 YES NO YES NO YES NO YES NO (circle) YES NO YES NO YES NO YES NO YES NO YES NO INFORMATION COPY   
' . Proc No 4.08 Attachment 1 Revision 0 Page 5 of 12 POST-TRIP REVIEW REPORT Specify Station Time/Sequence:
' . Proc No 4.08 Attachment 1 Revision 0 Page 5 of 12 POST-TRIP REVIEW REPORT Specify Station Time/Sequence:
Other Manual Actions: g. Radiological response:  
Other Manual Actions: g. Radiological response:
: h. Chemistry conditions:
: h. Chemistry conditions:
Comments:
Comments:
ad0285-0014b-93-154 (in.elude abnormal area tion monitor, process tion monitor, or environmental monitoring indication)  
ad0285-0014b-93-154 (in.elude abnormal area tion monitor, process tion monitor, or environmental monitoring indication)
: 2. Secondary fNFORMATION COPY   
: 2. Secondary fNFORMATION COPY   
' . PART 3: SEQUENCE OF EVENT TIME: ad0285-0014b-93-154 POST-TRIP REVIEW REPORT Shift Supervisor:
' . PART 3: SEQUENCE OF EVENT TIME: ad0285-0014b-93-154 POST-TRIP REVIEW REPORT Shift Supervisor:
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If handwritten statements are prepared., include the Plant conditions prior to the tip, your indications that a problem existed, your action as a result of those indications, noted equipment malfunctions 6r inadequacies and any identified procedure deficiencies.
If handwritten statements are prepared., include the Plant conditions prior to the tip, your indications that a problem existed, your action as a result of those indications, noted equipment malfunctions 6r inadequacies and any identified procedure deficiencies.
Also, include any information you consider important to review this unscheduled reactor trip and actions to prevent recurrence. (Use additional sheets if necessary) ad0285-0014c-93-154 INFORMATION COP't IC0685-0236-NL04 ATTACHMENT II Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Datalogger Digital Inputs "Information Copy" July 1, 1985 (11 Pages)
Also, include any information you consider important to review this unscheduled reactor trip and actions to prevent recurrence. (Use additional sheets if necessary) ad0285-0014c-93-154 INFORMATION COP't IC0685-0236-NL04 ATTACHMENT II Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Datalogger Digital Inputs "Information Copy" July 1, 1985 (11 Pages)
DATALOGCER flELD REMOTE STATION l STATUS lNPlfIS DLS Conaole O\annel Device Channel Dcscriecion  
DATALOGCER flELD REMOTE STATION l STATUS lNPlfIS DLS Conaole O\annel Device Channel Dcscriecion
:fne Siti!!al Scheme* Schematic Dwl No Section l Connector AW9J26 IU:actor Core Neutron Flux Channd-A lligh Digital 0-125 V DC lCOl C06 2 Connector AW9J26 keactor Power Rate Change Channel-A High Digitd 0-125 V DC lCOl C06 3 Connector AW9J26 Presi;urizer T-72 Presi;ure Olannel-A High Digital 0-125 V DC ICOl C06 4 Connector AW9J26 Thermal Margin or Coolant Preas Olannel*A Low Digital 0-125 V DC lCOl C06 5 Connector AW9J26 Steam E*50A Presaure Olannel-A Low Digit1tl 0-125 V DC ICOl C06 6 Connector AW9J26 Stea111 E-508.Prelisure Olannel-A Low Digital 0-125 V DC IGOl C06 1 Connector AW9J26 Primuy Coolant loop l Flow Channel-A Low Digital O-U5 V DC lCOl C06 8 Connector AW9J26 Steam Generator E-50A Water Level Ch1tn-A Low Digital 0-125 V DC lGOl C06 9 Connector AW9J26 Steam Generator E-50B Water level Chan-A Low Digital 0*125 V DC lGOl C06 10 Connector AW9J26 Reactor load (Turbine Trip) Channel-A Lost Digital 0-125 V DC lGOl C06 11 l-1 Reactor Control Rod Drive Clutch A Relay K*l Digital 0*125 V DC lCOl C06 l2 42-737 Priwary Sylitem Drain Tank Pump P*7lA Start Digital 0-125 V DC IGOl E-260 807 u 42-ti43 Primary System Drain Tank Pump P-71B Start Digital 0*125 V DC IGOl E-260 808 e 14 lIAX Dirty Waste Drain Tank T-60 Level Digital 0*125 V DC IGOl E-267 C40 15 LIAX Dirty Waste Drain Tank T-60 Level Digital 0*125 V DC IGOl E-267 C40 16 Spare IGOl 17 42-761 llrain Tank Pump P*75A Start *Digital 0-125 V DC IGOl E-264 807 l8 42-831. Equipment Drain tank Pump P-758 Start Digital 0*125 V DC lGOl E-264 808 19 Spare IGOl 20 252-103 Primary Coolant Pump P*50A Digital 0-125 V DC ICOl E-183 A2l 21 252-203 Priwary Coolant Pump P-50B Digital 0*125 V DC IGOl E-183 A2l 2l 252-104 Primary Coolant Pwap P*50C Digital 0-125 V DC ICOl E-183 All 23 252-204 Primary Coolant Pump P-50D Digital 0-125 V DC IGOl E-183 All 24 POS*l042B Prelisurizer Power lllelief Valve Digital 0*125 V DC SoO/ICOl E-256 JJ07 25 POS-l0lf3B Pressurizer Power Relief Valve Digital 0*125 V DC S6l/IG01 E-256 JJ07 26 POS-10578 Pre&liurizer  
:fne Siti!!al Scheme* Schematic Dwl No Section l Connector AW9J26 IU:actor Core Neutron Flux Channd-A lligh Digital 0-125 V DC lCOl C06 2 Connector AW9J26 keactor Power Rate Change Channel-A High Digitd 0-125 V DC lCOl C06 3 Connector AW9J26 Presi;urizer T-72 Presi;ure Olannel-A High Digital 0-125 V DC ICOl C06 4 Connector AW9J26 Thermal Margin or Coolant Preas Olannel*A Low Digital 0-125 V DC lCOl C06 5 Connector AW9J26 Steam E*50A Presaure Olannel-A Low Digit1tl 0-125 V DC ICOl C06 6 Connector AW9J26 Stea111 E-508.Prelisure Olannel-A Low Digital 0-125 V DC IGOl C06 1 Connector AW9J26 Primuy Coolant loop l Flow Channel-A Low Digital O-U5 V DC lCOl C06 8 Connector AW9J26 Steam Generator E-50A Water Level Ch1tn-A Low Digital 0-125 V DC lGOl C06 9 Connector AW9J26 Steam Generator E-50B Water level Chan-A Low Digital 0*125 V DC lGOl C06 10 Connector AW9J26 Reactor load (Turbine Trip) Channel-A Lost Digital 0-125 V DC lGOl C06 11 l-1 Reactor Control Rod Drive Clutch A Relay K*l Digital 0*125 V DC lCOl C06 l2 42-737 Priwary Sylitem Drain Tank Pump P*7lA Start Digital 0-125 V DC IGOl E-260 807 u 42-ti43 Primary System Drain Tank Pump P-71B Start Digital 0*125 V DC IGOl E-260 808 e 14 lIAX Dirty Waste Drain Tank T-60 Level Digital 0*125 V DC IGOl E-267 C40 15 LIAX Dirty Waste Drain Tank T-60 Level Digital 0*125 V DC IGOl E-267 C40 16 Spare IGOl 17 42-761 llrain Tank Pump P*75A Start *Digital 0-125 V DC IGOl E-264 807 l8 42-831. Equipment Drain tank Pump P-758 Start Digital 0*125 V DC lGOl E-264 808 19 Spare IGOl 20 252-103 Primary Coolant Pump P*50A Digital 0-125 V DC ICOl E-183 A2l 21 252-203 Priwary Coolant Pump P-50B Digital 0*125 V DC IGOl E-183 A2l 2l 252-104 Primary Coolant Pwap P*50C Digital 0-125 V DC ICOl E-183 All 23 252-204 Primary Coolant Pump P-50D Digital 0-125 V DC IGOl E-183 All 24 POS*l042B Prelisurizer Power lllelief Valve Digital 0*125 V DC SoO/ICOl E-256 JJ07 25 POS-l0lf3B Pressurizer Power Relief Valve Digital 0*125 V DC S6l/IG01 E-256 JJ07 26 POS-10578 Pre&liurizer
:S;** **Y Valve
:S;** **Y Valve
* Digital 0*125 V DC S60/IG01 E-253, Sh 2 JJ07 21 POS-10591 Pressurizer Spr1ty Valve Digital 0-125 V DC S61/IG01 E-253 1 Sh 2 JJ07 28 42X-l502 1 42X-l506 42X*l602 1 42X-1606 Pressurizer Backup Heater On Digital 0*125 V DC IGOl E-2S4 JJ07 29 52-1205 Pump P-55A Start Digital 0-125 V DC Bl205/IC01
* Digital 0*125 V DC S60/IG01 E-253, Sh 2 JJ07 21 POS-10591 Pressurizer Spr1ty Valve Digital 0-125 V DC S61/IG01 E-253 1 Sh 2 JJ07 28 42X-l502 1 42X-l506 42X*l602 1 42X-1606 Pressurizer Backup Heater On Digital 0*125 V DC IGOl E-2S4 JJ07 29 52-1205 Pump P-55A Start Digital 0-125 V DC Bl205/IC01
Line 178: Line 178:
DATALOCGElt FIELD REMOTE STATION l STATUS INPUTS DLS Olannel Device
DATALOCGElt FIELD REMOTE STATION l STATUS INPUTS DLS Olannel Device
* Cons;..1e*  
* Cons;..1e*  
,, Channt:l Dt:i;c r i1,?t ion  
,, Channt:l Dt:i;c r i1,?t ion
:f:Xee Sii!!al Voltaise Scheme*
:f:Xee Sii!!al Voltaise Scheme*
le llwlfi No Section 198 XPAl 199 XPBl 200 XPCl 201 XPDl 202 Rl.2 Pressurizer Pressure Digital 0*48 V DC Sl7/IC10l E-206, Sh l
le llwlfi No Section 198 XPAl 199 XPBl 200 XPCl 201 XPDl 202 Rl.2 Pressurizer Pressure Digital 0*48 V DC Sl7/IC10l E-206, Sh l

Revision as of 21:28, 25 April 2019

Rev 0 to Administrative Procedure 4.08, Post-Trip Review Requirements.
ML18051B460
Person / Time
Site: Palisades Entergy icon.png
Issue date: 07/01/1985
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051B459 List:
References
4.08, GL-83-28, NUDOCS 8507100011
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.!J ,_ ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Palisades Procedure No. 4.08 "Information Copy" July 1, 1985 (23 Pages)

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  • PDR U p IC0685-0236-NL04 L PALISADES NUCLEAR PLANT e ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS Proc No 4.08 Revision 0 Page 1 of 9 1.0 PURPOSE This procedure is to provide a systematic method for diagnosing the cause(s) of a reactor trip, ascertaining the proper functioning of safety related and other important equipment during the trip, determining any detrimental effect on plant equipment caused by the trip, and making the determination that the plant can be restarted safely. 2.0 SCOPE A documented review should help ensure events that have had an impact on the cause of the trip and subsequent equipment responses are identified and thoroughly understood.

The review results will permit a determination to be made as to the readiness of the plant to be safely returned to operation.

The format of this procedure can also be used to diagnose reactor plant transients other than those involving reactor trips.

3.0 REFERENCES

3.1 NODS-Al7, "Management Overview" 3.2 NODS-PIS, "Shift Operations" 3.3 Palisades Administrative Procedure 10.41, "Procedure On Procedures" 3.4 Palisades Administrative Procedure 10.42, "Procedure/Document Matrix" 3.5 Palisades Administrative Procedure 10.46, "Plant Records" 3.6 Palisades Administrative Procedure 4.01, "Shift Operations" 3.7 Nuclear Assurance Department Procedure XIX-2, "Plant Safety Engineering Assessment Program".

3.8 Palisades

Plant Site Emergency Plan 4.0 RESPONSIBILITIES

4.1 PLANT

GENERAL MANAGER The Plant General Manager or the Duty and Call Superintendent is responsible for making the decision to start up the reactor. For the purpose of this procedure, reference to the Plant General Manger includes the Duty and Call Superintendent when applicable.

In addition the Plant General Manager shall verify the cause of the trip has been determined and appropriate corrective action taken. ad0285-0014a-93-154 INFORMATION COPY

  • PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS

4.2 PLANT

SAFETY ENGINEERING (PSE) Proc No 4.08 Revision 0 Page 2 of 9 PSE shall perform an assessment of every inadvertant plant trip and provide the results of such assessment to the Plant General Manager in accordance with Reference 3.7. 4.3 OPERATIONS SUPERINTENDENT For a Condition II event, as determined by Step 5.3.4, the Operations Superintendent or his designated alternate shall: a. Report to the Plant site to assist in the further investigation of the trip and to determine necessary corrective action before restart. b. Analyze the event reconstruction and supply information*per Step 5.4.2 to the Plant General Manager. 4.4 LEAD SHIFT ENGINEER The Lead Shift Engineer shall review all completed Reactor Trip Reports. 4.5 DUTY SHIFT ENGINEER The Shift Engineer (SE) on duty shall: a. Complete offsite personnel and agency notification in accordance with Reference 3.6 and 3.8 as apprpriate.

b. Interview plant personnel involved in the trip. c. Collect data for inclusion in trip report. d. Make recommendations to Plant General Manager on reactor startup. e. Prepare Trip Report. 4.6 SHIFT SUPERVISOR/OPERATIONS The Shift Supervisor/Operations (SS) shall: a. Assist the SE with data collection as Plant conditions allow. b. Make recommendation to Plant General Manager on reactor startup. c. Assure Plant shutdown actions are completed after the reactor trip. d. Maintain the Plant in a safe condition.

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.. 5.0 5 .1 5 .1.1 5.1.2 5.2 5.2.1 5.2.2 PALISADES NUCLEAR PLANT e ADMINISTRATIVE PROCEDURE Proc No 4.08 Revision 0 Page 3 of 9 TITLE: POST TRIP REVIEW REQUIREMENTS PROCEDURE GENERAL INSTRUCTIONS Post Trip Review Process The post-trip review process is a five-step process. The five steps are as follows: Step (1) Data collection (2) Trip investigation (3) Restart decision (4) Trip investigation review (5) Independent assessment/

comparison with past trips for trends. Initiation Responsiblity Shift Engineer Shift Engineer Plant General Manager Plant General Manager/PRC Plant Safety Engineering Any unscheduled reactor trip will require the post-trip review process to be initiated.

The post-trip review shall be initiated after plant conditions have stabilized.

The Post-Trip Review Report, Attach-ment 1, guides and documents the post-trip process. The post-trip review shall not distract the Shift Supervisor, Shift Engineer, or operating personnel from their primary responsibility of monitoring plant parameters and maintaining the plant in a safe condition.

DATA COLLECTION Hard Copy Information The Shift Engineer is responsible for the collection of required hard copy information.

The purpose of this data is to reconstruct the transient from prior to the initiating event until plant parameters have stabilized.

Part 2(a) and (b) of the Post-Trip Review Report, Attachment 1, lists the information that should be collected.

Strip chart recordings must accurately reflect real time to have meaningful information.

If this is not the case, the SE should ensure the chart paper is annotated with a time mark, chart speed (chart speed may change during the transient), and time scale. Operator Statements After the plant is in a safe, stable condition, the SE should ensure each individual involved in the trip (eg, reactor operator, man/technician, Maintenance Supervisor, etc) provides a statement concerning his/her involvement in the reactor trip. These statements may be obtained in one of the following ways: ad0285-0014a-93-154 iNFORMATION COPY

  • , .. 5.2.3 5.2.4 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS
a. Written operator statements (use Attachment 2). Proc No 4.08 Revision 0 Page 4 of 9 b. SS/SE interviews with personnel involved in the reactor trip. c. Critique with all involved personnel.

If either of the last two techniques are used, the information should be recorded to ensure future availability of the information.

The operator statements should be restricted to facts concerning the event, and the facts should be stated chronologically, if possible.

The statement should include the following:

a. Plant conditions prior to the trip (for maintenance personnel, this will include the status of maintenance or testing).
b. First indication that a problem existed. c. Individual's actions as a result of the indications.
d. Subsequent indications and plant response, including manual actions. e. Noted equipment malfunctions or inadequacies.
f. Procedure deficiencies identified during the situation.
g. Recommendations to prevent recurrence.

The written statements or tape recordings shall be included in the reactor trip data package to assist in the event reconstruction.

Post-Trip Review Report Data The SE shall complete Part 1 and Part 2 of the Post-Trip Review Report, documenting the initial plant conditions and the plant respQnse.

Information for the Post-Trip Review shall come from a compilation of available data. Post-Trip Review Data Package The SE should collect the hard copy information, operator statements, and the Post-Trip Review Report. This will be the post-trip review data package that will be used during the post-trip investigation.

ad0285-0014a-93-154 INFORMATION COPY.

5.3 5.3.1 5.).2 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS POST-TRIP INVESTIGATION Event Reconstruction Proc No 4.08 Revision 0 Page 5 of 9 The Shift Engineer is responsible for the initial post-trip investigation.

The purpose of this investigation is to determine the cause of the trip, verify proper plant response, and to assess the plant's readiness to return to operation.

The SE will reconstruct the transient in Part 3 of the Post-Trip Review Report, Attachment 1, using the collected data. A chronological description of the event will be developed, using all available data. Pertinent alarms, trips, actuations, and isolations will be listed or marked on the of-events or Feedwater Purity Data Logger printout.

Pertinent plant parameters should be incorporated into the chronological list of events during the reconstruction.

Analysis and Evaluation The Shift Supervisor, and the Shift Engineer shall analyze and evaluate the event reconstruction to determine the cause of the trip and the following:

a. If all major safety-related and other important equipment involved in the trip operated as anticipated or expected.
b. If the trip/transient caused any detrimental effects on plant equipment.
c. If it is acceptable to restart the reactor. The Shift Supervisor and the Shift Engineer should look beyond the obvious indications to diagnose the cause of the trip and evaluate the plant response.

They should review the available information thoroughly, looking for: a. abnormal indications or degraded trends in equipment performance, b. events occurring out of the normal or anticipated sequence, c. failed or degraded response of equipment to control signals, d. . unusual chemistry results or radiation readings, and e. unanticipated alarms. The actual or suspected cause of the trip and any abnormal or degraded indication identified during the transient shall be documented in Parts 4 through 6 of the Post-Trip Review Report. ad0285-0014a-93-154 INFORMATION COPY 5.3.3 5.3.4 5.3.5 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS Preliminary Safety Assessment Proc No 4.08 Revision 0 Page 6 of 9 A preliminary safety assessment of the trip and subsequent plant response shall be performed by the Shift Supervisor and the Shift Engineer.

The maximum and minimum values of selected parameters shall be compared with their established limits in the Technical Specifications.

Parts 7 and & of the Post-Trip Review Report will document this safety assessment.

Trip Classification Based on the results of the analysis and evaluation of the plant trip and subsequent response, the Shift Supervisor and the Shift Engineer shall classify the event as one of the following conditions:

a. Condition I The cause of the trip is positively known and has been corrected; all safety-related and other important equipment functioned properly during the trip, or if not, the malfunction has either been corrected or redundant equipment is available for reactor start-up.
b. Condition II 1. The cause of the trip is not positively known. Or 2. Safety related equipment or other equipment functioned in an abnormal or degraded manner during the trip and the malfunction has not been corrected.

Or 3. Safety related equipment or other equipment functioned in an abnormal or degraded manner during the trip and redundant equipment is not available for startup. If the Shift Supervisor and Shift Engineer cannot agree on tion of the transient, the event will be referred to the Plant General Manager for re-evaluation and classification.

Notifications Once the reactor trip event is classified, the Shift Supervisor/Shift Engineer shall inform the Plant General Manager. If the event is classified Condition II, the.SS/SE shall also inform the Operations Superintendent.

If necessary, emergency plan notifications shall be made as required in References 3.6 and 3.8. ad0285-0014a-93-154 INFORMATION COPY

  • , PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW RE9UIREMENTS Proc No 4.08 Revision 0 Page 7 of 9 5.4 RESTART DECISION 5.4.1 5.4.2 5.4.3 The Plant General Manager has the responsibility and authority to grant permission to commence a reactor startup following a reactor trip. Condition I Events The Shift Supervisor/Shift Engineer shall inform the Plant General Manager if the unscheduled reactor trip event is classified as Condition I. Based upon this classification, the SS/SE recommends restart of the reactor.
  • Condition II Event The Shift Supervisor/Shift Engineer shall inform the Plant General Manager when an event is classified Condition II or when the classification cannot be agreed upon. The Operations Superintendent or his designated alternate shall report to the plant site to assist in the further investigation of -the trip and to determine necessary corrective action before restart. The Operations Superintendent will analyze the event reconstruction, emphasizing the root cause of the trip and the resolution of abnormal or degraded indications.

He should use available expertise to resolve questions concerning the cause and plant response.

Sources of expertise that should be considered include nuclear steam supply vendors, vendor engineers, onsite engineering staff and other experienced operations and.maintenance personnel.

The Operations Superintendent should supply the following information to the Plant Manager:

  • a. The actual or most probable cause of the trip. b. The maintenance and testing necessary before reactor restart including additional measures to verify the most probable cause. c. Additional monitoring or trending required during and/or after reactor restart. d. Necessary briefings to operations and/or maintenance personnel concerning specific equipment indications or possible malfunctions.
e. The conditions necesary for a reactor restart. Plant General Manager Evaluation and Decision The Plant General Manager should evaluate the recommendation made by the personnel performing the trip investigation.

The Plant General Manager should consider convening the PRC to review the trip investigation prior to reactor restart for Condition II events. The ad0285-0014a-93-154 INFORMATION COPY

  • , 5.5 5.5.1 5.5.2 PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS PRC can advise the Plant General Manager on the thoroughness, technical accuracy and consistency of the trip investigation.

Proc No 4.08 Revision 0 Page 8 of 9 The Plant General Manager's decision to restart the reactor shall include the following considerations:

a. The most probable cause of the trip is known and corrected.
b. Major safety-related and other important equipment functioned properly during the transient, or corrective maintenance and satisfactory testing has been performed or will be completed when plant conditions permit. c. The plant response during the event has been analyzed and the plant responded as anticipated, or all abnormalties are understood and corrected as required by Technical Specifications.

If the cause of the trip has not been positively identified, the Plant General Manager shall determine if the cause and the circumstances surrounding the cause have been analyzed adequately.

He shall take adequate measures to prevent repetitive challenges to safety systems during future power operations.

INVESTIGATION REVIEW Condition I Events Condition I event trip reports shall be reviewed by the Lead Shift Engineer, Operations Superintendent, and Plant General Manager within two weeks of the trip. The report should be reviewed by the PRC during the next regularly scheduled PRC meeting. Condition II Events If directed by the Plant General Manager, a Condition II event shall be reviewed by the PRC before a reactor restart is co01D1enced.

Otherwise, a Condition II event will receive a PRC review during the next regularly scheduled PRC meeting. 5.6 PLANT SAFETY ENGINEERING ASSESSMENT PROGRAM Plant Safety Engineering will perform an independent assessment of each unplanned reactor trip as addressed in Reference 3.7. The Lead Assessor shall provide his/her conclusion, independent of the full report, on at least a preliminary basis to the Shift Supervisor or Plant General Manager prior to startup following a trip. The preliminary report will normally consist of a verbal report or Form 40. ad0285-0014a-93-154 INFORMATION COPY

  • ,
  • PALISADES NUCLEAR PLANT e ADMINISTRATIVE PROCEDURE TITLE: POST TRIP REVIEW REQUIREMENTS

6.0 ATTACHMENTS

AND RECORDS 6.1 ATTACHMENTS

6.1.1 Attachment

1, "Post-Trip Review Report" 6.1.2 Attachment 2, "Plant Personnel Statements" 6.2 RECORDS Proc No 4.08 Revision 0 Page 9 of 9 The post-trip review data packages shall be retained for the life of the plant. This will allow the data package to be available for comparison with future trips. ad0285-0014a-93-154 INFORMATION COPY

  • POST-TRIP REVIEW REPORT Date of Occurrence:

Time of Occurrence:

PART 1: INITIAL CONDITIONS

a. Reactor Power % b. Reactor Coolant Pumps Operating (circle) A B c. Hain Feed Pump(s) Operating (circle) A B d. Status of Control Stations (circle) 1. Turbine Control Han 2. A Feedpump Control Han B Feedpump Control Han 3. A Hain Feedwater Reg Valve Han B Hain Feedwater Reg Valve Man 4. Turbine Bypass Valve (-l.--i-CV-0511)

Man s. Pressurizer Level Control Channel A/B Han 6. Pressurizer Pressure Control Channel A/B Man e. PORV Block Valves (circle) OPEN f. Off-normal Status (of any trains/portions of safety systems) Proc No 4.08 Attachment 1 Revision 0 Page 1 of 12 c D Oper Auto Imp In/Imp Out Auto Auto Auto Auto Auto Auto Auto CLOSED DETAILS 1. Reactor Protection System 2. Safety Injection Actuation.

System ad0285-0014b-93-154 fNFORMATION COPY

g. Testing/Surveillances in progress:

ad0285-0014b-93-154 Test Ii Proc No 4.08 Attachment 1 Revision 0 Page 2 of 12 Status/Step fNFORMATION COPY r

.. -POST-TRIP REVIEW REPORT PART 2: PLANT RESPONSE a. Obtain a copy of the applicable parameter Check If Included Parameter

1. Rx Power 2. Pzr Level 3. Pzr Pressure 4. T ave s. Tc WR 6. SG Levels b. Obtain a Printout from: 1. Tennecomp Data Logger 2. Event Recorder 3. Critical Function Monitor plots given below: Proc No 4.08 Attachment 1 Revision 0 Page 3 of 12 c. Obtain pertinent logs from past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Chemistry, Control Room, Auxiliary Operator, etc). d. Safety System Actuation and Performance
1. Reactor Protection System Type of Trip: Time of Trip: 2. Safety Injection Actuation System Actuation Signal/ Actuation Time Number of Trains HPSI I LPSI I 3. Containment Isolation I ad0285-0014b-93-154 INFORMATION COPY

.. POST-TRIP REVIEW REPORT 4. PZR Code Safety Valves Lifted Did they reseat properly?

How Confirmed?

5. Main Steam Relief Valves Lifted Did they reseat properly?

How confirmed?

e. Control System Actions 1. Turbine Trip 2. PCS Pressure Control Did PORV lift? Was PZR heater response normal? Was PZR spray response normal? Was PZR level control normal? 3. Were additional HPSI pumps started? Auto Start Manual Start f. Manual Actions Were any control stations taken from Auto to Manual? ad0285-0014b-93-154 Trip Time Trip Signal Signal Time Start Time Stop Proc No 4.08 Attachment 1 Revision 0 Page 4 of 12 YES NO YES NO YES NO YES NO (circle) YES NO YES NO YES NO YES NO YES NO YES NO INFORMATION COPY

' . Proc No 4.08 Attachment 1 Revision 0 Page 5 of 12 POST-TRIP REVIEW REPORT Specify Station Time/Sequence:

Other Manual Actions: g. Radiological response:

h. Chemistry conditions:

Comments:

ad0285-0014b-93-154 (in.elude abnormal area tion monitor, process tion monitor, or environmental monitoring indication)

2. Secondary fNFORMATION COPY

' . PART 3: SEQUENCE OF EVENT TIME: ad0285-0014b-93-154 POST-TRIP REVIEW REPORT Shift Supervisor:

Shift Engineer:

Proc No 4.08 Attachment 1 Revision 0 Page 6 of 12 EVENT DESCRIPTION:

fNFORMATION COPi:

.. -' POST-TRIP REVIEW REPORT PART 4: PROBABLE CAUSE OF TRIP Comments:

PART 5: UNEXPECTED ASPECT OF TRANSIENT BEHAVIOR (if event compared with previous similar transient, note the transient with which compared)

Proc No 4.08 Attachment 1 Revision 0 Page 7 of 12 ANALYSIS AND EVALUATIONS Compared With Previous trip on: I Date Time ad0285-0014b-93-154 fNFORMATION COPY

.. POST-TRIP REVIEW REPORT Proc No 4.08 Attachment 1 Revision 0 Page 8 of 12 PART 6: IDENTIFICATION OF SYSTEMS WITH INADEQUATE PERFORMANCE System/Component Description of Problem Shift Supervisor I I Signature Date Time Shift Engineer I I Signature Date Time ad0285-0014b-93-154 fNFORMATION COPY

,*._ POST-TRIP REVIEW REPORT PART 7: TRANSIENT DATA FOR PERTINENT PLANT PARAMETERS Maximum a. RCS Pressure Loop A __ B __ b. RCS Temp *Loop A B ----Proc No 4.08 Attachment 1 Revision 0 Page 9 of 12 Minimum Loop A __ B __ Loop A __ B __ c. SG Press Loop A __ B__ Loop A __ B __ d. SG Level , Loop A B ----Loop A __ B __ PART 8: PRELIMINARY SAFETY ASSESSMENT (circle) a. PCS Pressure Remained Above Setpoint for Automatic SI Actuation.

YES NO b. PCS Pressure Remained Below Setpoint for PZR Code Safety Valve Actuation.

YES NO c. PCS Temp. Decrease Less Than 100° F/hr (Tech Spec). YES NO d. Reactor Was Contained Within The PCS and Quench Tank. YES NO e. Indicated PZR Level Remained On Scale. YES NO f. Indicated SG Level Remained On Scale. YES NO Comments:

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  • > POST-TRIP REVIEW REPORT PART 9: EVENT CONDITION Proc No 4.08 Attachment 1 Revision 0 Page 10 of 12 Classify trip as Condition I or Condition II according to guidelines in procedure.

The event on at is a condition Date -rim_e_ I ,II Signature indicates agreement with condition.

I I Shift Supervisor Date Time I I Shift Engineer Date Time Comments:

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  • .r ... POST-TRIP REVIEW REPORT PART 10: PERMISSION TO START UP Proc No 4.08 Attachment 1 Revision 0 Page 11 of 12 Plant General Manager notified and permission granted to start up the reactor. I I Shift Supervisor Date Time I I Shift Engineer Date Time Comments:

ad0285-0014b-93-154 INFORMATION COPY

. , POST-TRIP REVIEW REPORT PART 11: INVESTIGATION REVIEW Proc No 4.08 Attachment 1 Revision 0 Page 12 of 12 Post-Trip Report review conducted:

Lead Shift Engineer Operations Superintendent Plant General Manager Comments (note if PRC review required for Condition I): PRC review of event on: , meeting number: ----Minutes of the meeting(s) are attached I PRC Chairman Date Comments:

ad0285-0014b-93-154 fNFORMATION cop-.

  • .> PLANT PERSONNEL STATEMENTS (See Back for Instructions)

Signature ad0285-0014c-93-154 Proc No 4.08 Attachment 2 Revision 0 Page 1 of 2 I I Date Time INFORMATION

. ..

  • INSTRUCTIONS Proc No 4.08 Attachment 2 Revision 0 Page 2 of 2 Attach statements from personnel involved with the trip concerning the events that-preceeded and followed the trip ... Each individual should submit a statement concerning the way he remembers the event. Example Name: Position:

If handwritten statements are prepared., include the Plant conditions prior to the tip, your indications that a problem existed, your action as a result of those indications, noted equipment malfunctions 6r inadequacies and any identified procedure deficiencies.

Also, include any information you consider important to review this unscheduled reactor trip and actions to prevent recurrence. (Use additional sheets if necessary) ad0285-0014c-93-154 INFORMATION COP't IC0685-0236-NL04 ATTACHMENT II Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Datalogger Digital Inputs "Information Copy" July 1, 1985 (11 Pages)

DATALOGCER flELD REMOTE STATION l STATUS lNPlfIS DLS Conaole O\annel Device Channel Dcscriecion

fne Siti!!al Scheme* Schematic Dwl No Section l Connector AW9J26 IU:actor Core Neutron Flux Channd-A lligh Digital 0-125 V DC lCOl C06 2 Connector AW9J26 keactor Power Rate Change Channel-A High Digitd 0-125 V DC lCOl C06 3 Connector AW9J26 Presi;urizer T-72 Presi;ure Olannel-A High Digital 0-125 V DC ICOl C06 4 Connector AW9J26 Thermal Margin or Coolant Preas Olannel*A Low Digital 0-125 V DC lCOl C06 5 Connector AW9J26 Steam E*50A Presaure Olannel-A Low Digit1tl 0-125 V DC ICOl C06 6 Connector AW9J26 Stea111 E-508.Prelisure Olannel-A Low Digital 0-125 V DC IGOl C06 1 Connector AW9J26 Primuy Coolant loop l Flow Channel-A Low Digital O-U5 V DC lCOl C06 8 Connector AW9J26 Steam Generator E-50A Water Level Ch1tn-A Low Digital 0-125 V DC lGOl C06 9 Connector AW9J26 Steam Generator E-50B Water level Chan-A Low Digital 0*125 V DC lGOl C06 10 Connector AW9J26 Reactor load (Turbine Trip) Channel-A Lost Digital 0-125 V DC lGOl C06 11 l-1 Reactor Control Rod Drive Clutch A Relay K*l Digital 0*125 V DC lCOl C06 l2 42-737 Priwary Sylitem Drain Tank Pump P*7lA Start Digital 0-125 V DC IGOl E-260 807 u 42-ti43 Primary System Drain Tank Pump P-71B Start Digital 0*125 V DC IGOl E-260 808 e 14 lIAX Dirty Waste Drain Tank T-60 Level Digital 0*125 V DC IGOl E-267 C40 15 LIAX Dirty Waste Drain Tank T-60 Level Digital 0*125 V DC IGOl E-267 C40 16 Spare IGOl 17 42-761 llrain Tank Pump P*75A Start *Digital 0-125 V DC IGOl E-264 807 l8 42-831. Equipment Drain tank Pump P-758 Start Digital 0*125 V DC lGOl E-264 808 19 Spare IGOl 20 252-103 Primary Coolant Pump P*50A Digital 0-125 V DC ICOl E-183 A2l 21 252-203 Priwary Coolant Pump P-50B Digital 0*125 V DC IGOl E-183 A2l 2l 252-104 Primary Coolant Pwap P*50C Digital 0-125 V DC ICOl E-183 All 23 252-204 Primary Coolant Pump P-50D Digital 0-125 V DC IGOl E-183 All 24 POS*l042B Prelisurizer Power lllelief Valve Digital 0*125 V DC SoO/ICOl E-256 JJ07 25 POS-l0lf3B Pressurizer Power Relief Valve Digital 0*125 V DC S6l/IG01 E-256 JJ07 26 POS-10578 Pre&liurizer
S;** **Y Valve
  • Digital 0*125 V DC S60/IG01 E-253, Sh 2 JJ07 21 POS-10591 Pressurizer Spr1ty Valve Digital 0-125 V DC S61/IG01 E-253 1 Sh 2 JJ07 28 42X-l502 1 42X-l506 42X*l602 1 42X-1606 Pressurizer Backup Heater On Digital 0*125 V DC IGOl E-2S4 JJ07 29 52-1205 Pump P-55A Start Digital 0-125 V DC Bl205/IC01
  • E-257, Sh 3 812 JO 52-1206 Charging PUlllp P-55B Start Digital 0-125 V DC Bl206/IG01 E-257 1 Sh 3 812 ll 52-1105 O\argiug l'WDp P-55C Start Digital 0-125 V DC 81105/IGOl E-257, Sh 3 BU 32 POS-20038 Letdown Orifice Stop Valve Digital 0*125 V DC SU/lCOl E-236 1 Sh l JJ07 31 POS-20048 Letdown Orifice Stop Valve Digital 0-125 V DC Sl7/IG01 E-236, Sh l Jl07 l4 POS-20058 Letdown Orifice Stop Valve Digital 0*125 V DC Sl7/IG01 E-236, Sh l JJ07 e 15 152-307 Heater Drain Pump P-lOA Digital 0*125 V DC ICOl E-180 All l6 152-308 Heater llrain PU111p P-lOB Digital 0-125 V DC IGOl E-180 All 37 POS-07038 Feedwater Valve CV-0703 Digital 0*125 V DC WOlO/IGOl E-69 Cl3 l8 POS-0701B Feedwater Valve CV-0701 Digital 0-125 V DC W009/lGOl E-69 Cll 39 POSX-3085 tlot leg letdown Valve Digital 0-125 V DC S97/IC01 E-245, Sh 4 CUL 40 POSX-3082 Hot Leg letdown Valve Digital 0*125 V DC B22l3/1G01 E*24't, Sh s COJll 41 Connector keactor Core Neutron Flux Channel-8 High Digital 0-125 V DC 1G02 C06 42 Connector 8W9J26 IU:actor Core Power R<ite Change Channel-8 High Digital o-12s v DC IG02 C06 43 Connector BW9J26 Prtssurizer T-72 Pressure Channel-I High Digital 0-125 V DC IG02 C06 44 Connector BW9J26 Therwal Margin or Coolant Press Channel-B Low Digital 0*125 V DC IG02 C06 45 Connector 8W9J2b Steam Generator E-50A Pressure Channel*B Low Digital o-12s v DC IG02 C06 46 Connector 8W9J26 Steialll Cenerator E-SOB Prei;sure Channel-B Low Digitlll 0*125 V DC IG02 C06 47 Connector BW9J26 Prillldry Coolant loop l l:o'low Channel *B Low Digital 0-125 V DC IG02 C06 48 Connector BW9J2b Stei&lll Generator E-50A Water Level Chan-8 Low Digital 0-125 V DC IC02 C06 49 Connector 8W9J2b Sttam Generator Weter Level Chan-8 Low Digital 0-125 V DC IG02 C06 llJ'0883-041LA-NS04-TrlO INFORMATION COFW ...

DATALOGCER FIELD REMOTE STATION l STATUS INPl!IS DlS Olannel Device Channel Descrietion Signal Si 12!al Voltage so Connector 8W9J26 Reactor load (Turbine Trip) Clannel-8 lost Digital o-12s v DC $1 K.-2 Reactor Control Rod Drive Clutch A Power kelay K-2 Digital 0*125 V DC S2 POS*OSOl Hain Steam Isolation Valve Digital O-l2S V DC SJ POS-0510 Hain Steam Isolation Valve Digital 0*125 V DC S4 POS-OSll Hain Stea111 Bypass Valve Digital 0-125 V DC SS POS-0780 Steam Dump Valve Digital 0-125 V DC S6 386-P Gen Direct Trip Lockout Relay Primary (Trip) Digital O*l2S V DC S7 POS-0179 Steam Dump Valve Digital o-12s v DC S8 POS-0781 Steam Dump Valve Digital O*l2S V DC S9 POS-0782 Steam Dump Valve Digital o-12s v DC 60 1S2-206 Low-Press Safety Injection Pump P-67A Start Digital O*l2S V DC 61 lS2-lll Low-Press Safety Injection Pump P-678 Start Digital O*l2S V DC 62 152-207 High-Presa Safety Injection Pump P-66A Start Digital o-12s.v DC 6l 152-lll High-Presa Safety Injection Pump P-668 Digital o-12s v DC 64 lS2-209 High-Press Safety Injection Pump P-66C . Digital 0-125 V DC 6S lS2*210 Containwent Spray PWDp Injection P-S4A Digital 0*125 V DC 66 152-112 Containment Spray PWDp Injection P-548 Digital 0-125 V DC 67 152-114 Containment Spray Pump Injection P-S4C Digital o-12s v DC 68 POS-1029 Containment SWDp Valve Digital 0-125 V DC 69 POS*lOlO Containment Sump Valve Digital O*l2S V DC 70 POS*lOll Safety Inj and Refueling Water Tank Valve Digital 0-125 V DC 7l POS-1057 Safety Inj and Refuelin&

Water Tank Valve Digital 0-125 V DC 72 POSl-1081 HPSI Train l Valve Digital 0-125 V DC 7l POS-1001 C4>ntainment Spray Valve Digital O*l2S V DC 1 .. POS-1002 Containment Spray Valve Digital 0-125 V DC 75 POS-1008 Low-Preas Safety Inj Valve Digital 0-125 V DC 76 POS-1010 Low-Presa Safety lnj Valve Digital 0-125 V DC 11 POS-1012 low-Preas Safety Inj Valve Digital 0*125 V UC 78 POS-1014 Low-Presa Safety Inj Valve Digital 0*125 V DC 79 POSl-20S6 Cle111ical and Volume Cont letdown Valve Digital 0*125 V DC 80 POSl-3081 llPSI Train 1 Valve Digital 0*125 V DC 81 Connector CW9J26 Reactor Core Neutron Flux *Channel*C High Digital 0-125 V DC 82 Connector CW9J26 Reactor Core Power Rate Change Channel-C High Digital O*l2S V DC 8l Connector CW9J26 Pressurizer T-72 Pressure Clannel-C High Digital O*l2S V DC 8lt Connector CW9J26 ll\ermal Margin or Coolant Pressure Clan-C low Digital 0-125 V DC as Connector CW9J26 Stea111 Generator E-50A Pressure Clannel-C Low Digital O*l2S V DC 86 Connector CW9J26 Steam Cc:ncrator E-SOB Pressure Channel-C low Digital 0-125 V DC 87 Connector CW9J26 Pri111ary Coolant Loop l Flow Channel-C low Digital 0*125 V DC ti8 Connector CW9J26 Steaw Generator E*50A Water level Clannel-C low Digital 0-125 V DC 89 Connector CW9J26 Steaw Generator E-508 Water level Clannel-C Low Digital 0-125 V DC 90 Connector CW9J26 ktactor Load (Turbine Trip) Clannel-C lost Digital 0-125 V DC 9l 1(-l Redctor Control.Rod Drive Clutch 8 Power !Wlay 1(-l Digital 0-125 V DC 92 POS-0569 HP Turbine Stop Vdlve Digital 0-125 V UC 91 POS-0571 llP Turbine Stop Valve Digital 0-125 V DC 9lt POS-0571 HP Turbine Stop Valve Digital 0-125 V LIC 95 POS-0575 HP Stop Valve Digital 0-125 V DC 96 186-B Cen Direct Trip lockout Relay Digital 0-125 V DC 97 74*K.7Al, 74-K7A2 Feedwater PUlllp P-lA Orive Turb K-7A Digital 0*125 V LIC Scheme* IC02 IG02 IC02 IC02 IC02 IC02 IC02 W001/IG02 W001/IC02 W002/IG02 IC02 IC02 IC02 IC02 IC02 IC02 IC02 IC02 Sl4/IC02 Sll/IG02 Sl4/IG02 Sll/IC02 82lll/IC02 Sl9/IG02 Sl9/IC02 Bl .. 7/IC02 8l .. 7/IG02 B247/IC02 B2Sl/IG02 IC02 B2lll/IC02 IGOl ICOl ICOl ICOl ICOl ICOl ICOl ICOl IGOl ICOl lGOl T04/lCOl T04/ICOl T05/IGOl T05/lGOl lGOl lGOl Schematic Dwg No E-238 E-218 E-75 £*218 E-120 E-218 E-218 E*2l8 E-247 E-248 E-249 E-249 E-250 E-251 E-251 E-251 E-246 E-246 E*21t6 E-246 E*221t, E-217 E-217 E*21tlt, E*241t, E*21tlt, E-2 .... , E*2SS E*21tlt, E*ll4 E-11 .. E-114 E-11 .. E-120 E-187 Sb s, 6 Sh l Sh l Sh l Sh 1 Sh 5, 6 INFORMATION COPY Console

  • Section C06 C06 COl-2 COl-2 COl-2 J28l C04 J280 J280 J280 Al2 All e Al2 All Al2 Al2 All All COlil COll COll COlll COll COll CO la Jl07 Jl07 Jl07 Jl07 C02 COlL C06 C06 C06 co6 a C06 9 C06 C06 C06 C06 C06 C06 T04 T04 TOS TOS C04 cu .**

DATALOGGER FIELD REMOTE STATION l STATUS INPlll'S OLS Comrole

  • O'lannel-Device Channel Descr1et1on

!'l'.ee Sijinal Volt1tji<=

Scheme* Schematic No Section 98 74*K78l, 74-K782 Feedwater Pump P-US Drive Turb K-78 Digital 0-125 V DC IG03 E-196 cu 99 152-104 AuJl Feedwater Pump P-8A Drive Hotor Digital 0-125 V DC ICOl E-196 All 100 POS-3007 HP Safety Inj V,alve Digital o-12s v DC 8137/ICOl E-244 J307 101 POS-3009 HP Safety lnj Valve Digital 0*125 V DC 8197/IGOl E-244 J307 102 POS-3064 HP Safety Inj Valve Digital 0*125 V DC B2S7/IC03 E-244 J307 101 POS-3062 HP Safety Inj Valve Digital o-12s v DC 8241/ICOl E-244 J307 104 5P-7 ,8; 51l-7 ,8 Cont Isolation (High Pre6s/High Radiation)

Digital 0-125 V DC IGOl E-208 Cll lOS aux ltadwa6te Area l6olation Digital 0-125 V DC 1809/ICOl

£*27S Cll 106 Spare ICOl 107 POS-0867 Cont Air Clg Service Wtr Valve Digital o-12s v DC 81108/IGOl E-217 J350 108 POS-0871 Cont Air Clg Se'rvlce Wtr Valve Digital 0*125 V DC Bl210/IG03

£*216 JlSO 109 POS-0864 Cone Air Clg Service Wcr Valve Digital O-l2S V DC 81209/IGOl E*216 Jl50 110 POS-0861 Cont Air Clg Service Wcr Valve Digital 0-125 V DC 81208/IGOl . E-216 JlSOe 111 152-204 Service Water Pump P-7A Digital O*l2S V DC ICOl E-154 All 112 152-103 Service Witter Pump P-78 Digital 0-125 V DC IC03 E-154 All 111 1S2*20S Service Witter PWllp P-7C Digital O*l2S V DC ICOl £*154 All 114 42X*l30S Hcain Plant Electric Fire Pump P-9A Digital 0-125 V DC 8130S/IC03 E-163 Cl6 115 lSCllX Hain Plant Diesel Fire PUlllp P-98 Digital 0-125 V DC J025/IC03 E-164 Jl59 116 POS-0618 Htr ElA Dump to Condenser Valve Digital o-12s v DC TOO/lCOl E-115, Sh l COl 117 POS-0629 Htr EUS Dump to Condenser Valve Digital 0-125 V DC T06/IC01 E-115, Sb l COl 118 POS-0626 Htr E28 Dwap to Condenser Valve Digital 0*125 V DC T06/IC0l E-115, Sh l COl 119 POSX-3080 HPSI Train 2 Valve Digital 0-125 V DC 82413/ICOl E-244, Sh s, 6 COll 120 PSX-0741 AWl Feedwater Pump P-8A Sue Press Digital 0-125 V DC WOOl/IGOl

£*238, Sb 2 COl 121 Connector DW9J26 Reactor Core Neutron Flux Channel-D High Digital 0-125 V DC IC04 C06 122 Connector DW9J26 .Reactor Core Power Rate Change Q1annel-D High Digital 0-125 V DC IG04 C06 121 Connector DW9J26 T-72 Pressure Channel-D High Digital 0-125 V DC IC04 C06 124 Connector DW9J26 'l'hermal Hcargin or Coolant Preas 01annel-D Low Digital 0-125 V DC IC04 C06 125 Connector DW9J26 Steam Generator

£-SOA Pre6sure Channel-D Low Digital 0-125 V DC IC04 C06 U6 Connector DW9J26 Steam Generator E-508 Pressure Channel-D Low Digital 0-125 V DC IC04 C06 127 . Connector DW9J26 Prilllary Coolant Loop l Flow Channel-D Low Digital 0-125 V DC IC04 C06 128 Co1U1ector DW9J26 Steam Generator

£-50A Water Level Chan-D Low Digital 0-125 V DC IC04 C06 129 Connector DW9J26 Steam Generator

£-SOB Witter level Chan*D Low Digital 0*125 V DC IC04 C06 130 Connector DW9J26 Reactor load (Turbine Trip) Channel-D Lo11t Digital 0*125 V DC IC04 C06 111 K-4 Control Rod Drive Clutch Power Relay K-4 Digital 0-125 V DC IC04 C06 112 POS-0534 Reheat Stop Valve Digital 0-125 V DC T04/IC04 E-113 T5le lll POS*OS44 Reheat Stop Valve Digital 0-125 V DC T04/IC04 E-lll r52 ll4 POS-0537 lteheat Stop Valve Digital 0-125 V DC T04/IC04 E-lll r51 115 POS-0548 Reheat Stop Valve Digital 0-125 V DC T04/IG04 E-111 T54 136 POSX-05228 Turbine-Driven Aux Feed Pump P-88 Digital 0-125 V DC IC04 E-238, Sb 5 COl 137 POS-0731 Condensate Reject Valve Digital 0-125 V DC IG04 138 POS-0712 Condensate Makeup Valve Digital 0-125 V DC IG04 E-189 Cll 119 POS-0711 Condensate Fast Makeup Valve Digital 0-125 V DC IG04 E-189 Cll 140 POS-053S Reheat Intercept Valve DiKital 0-125 V DC T04/IC04 E-113 TSl 141 POS-0545 Reheat lntercept Valve Digital 0-125 V DC T04/IG04 E-lll r52 142 POS-0547 Reheat Intercept Valve Digital o-ns v DC T04/IC04 E-lll T53 141 POS-0540 Reheat Intercept Valve Digital 0-125 V DC T04/IG04 E-111 T54 144 POS-0539 Rehtr Drain Tank T-4A Dump Valve Digital 0-125 V DC IC04 llt5 POS*OSSS Rehtr Drcain Tank T-48 Dwup Valve Digital 0-125 v oc IC04 146 POS-0602 Heater EbA Bleed Steam Inlet Valve Digital 0-125 V DC T03/lC04 E-112 Cll 147 Po.5-0606 Heater £68 Bleed $teaw Inlet Valve Digital 0-125 V DC T03/IC04 E-112 Cll INFORMATION COPY ...

DATALOGCER FIELD REMOTE STATION l STATUS INPUTS DlS Oiannel Device Channel Description Signal Type Si&nal Voltage Scheme* Schematic Dwg No, Section 148 POS-0601 Heater E6A Dump to Condenser Valve Digital 0-125 V DC TOl/IG04 149 POS-0607 Hester E6B Dwup to Condenser Valve Digital 0-125 V DC TOl/IG04 lSO POS-0610 Heater E4A Bleed Steam Inlet Valve Digital 0-125 V DC T03/IG04 E-112 cu 151 POS-0620 Heater E4B Bleed Steam Inlet Valve Digital 0-125 V DC T03/IG04 E-112 cu 152 POS-0612 Heater E3A Bleed Steam Inlet Valve Digital 0-125 V DC T03/IG04 E-112 cu lSl POS-0611 Htr E4A Dump to Conuenser Valve Digital 0-125 V DC T06/IG04 E-115 CU 154 POS-0621 Htr E4B DWDp to Condenser Valve Di&ital 0-125 V DC T06/IG04 E*U5 cu 155 POS-0621 Htr ElB Bleed Steam Inlet Valve Digital 0-125 V DC T06/IG04 E-U2 cu 156 POS-0614 Htr ElA Dump to Condenser Valve Digital 0-125 V DC T06/1G04 E-115 cu 157 POS-0624 Htr ElB Dump to Condenser Valve Digital 0*125 V DC T06/lG04 £-115 cu POS-0617 Htr £2A Dump to Condenser Valve Digital 0*125 V DC T06/IG04 E-115 cu 159 POSX-3084 Hot leg letdown Valve Digital 0-125 V DC S96/IC04 E*V.5, Sh It Cllll 160 9CC&/a Cooling Tower Diesel Fire Pump P-41 Digital 0*125 V DC Jll5/IG04 E*7l9, Sh 2 Cll7 e 161 252-102 Bus lA 4160 V Bkr 250-102 From Stup XFHR l*l Digital 0-48 V DC IG05 E-132, Sb 2 A21 162 252-101 Bus lA 4160 V Bkr 252-101 From Stn XPHK 1-1 Digital 0*48 V DC IG05 E*lll A2l 161 252-202 bus lB 4160 V Bkr 252*202 Stup XFHR 1-l Digital 0*48 V DC IG05 E-132, Sb 2 A22 164 252-201 Bus lB 4160 V Bkr 252*201 From Stn XFHR l-1 Digital 0*48 V DC lG05 E*lll A22 165 152-301 bus lE 2400 V Bkr 152*301 Fr011 Stup XFHll 1-2 Digital 0*48 V DC lG05 E*U2, Sh 2 All 166 152*302 Bus lE 2400 V Bkr 152-302 FrOll Stn XFHll 1-2 Digital 0-48 V DC IC05 E*lll All 167 252-301/302 Bus lF 4160 V Bkr 252-301 or 302 Digital 0*48 V DC IG05 E-728, Sh l, 2 A2l 168 252-401/402 Bus lC 4160 V Bkr 252-401 or. 402 Digital 0*48 V DC IG05 E-728, Sh l, 2 A24 169 305 ll Turbine Trip Relay 305R Digital 0-48 V DC T07/IG05 E-121, Sh l C04 170 4861T Hain Transformer Bkr 251l5 and 25Fl Digital 0*48 V DC IG05 E-117, Sh 2 C04 171 LOa386C Turbine Coastdown Trip Relay ll66C Digital 0*48 V DC COl/lC05 E-120 C04 172 3051/AST Turbine Trip Relay l-305 Digital 0-48 V DC T07/1G05 E-121, Sh 2 C04 171 u Reactor Trip Digital 0-48 V DC l09/IC05 E-291, Sh 5 C06 174 38 l-11 Bus lC Fast Transfer Digital 0*48 V DC AOOll/IC05 E-136, Sh l, 2 COit 175 lPSl, IUC Generator Range of Cllange of Current l>lgital 0-48 V DC HOl/lC05 E-9 C04, Cll 176 Swicchyard Oscillograph Digital 0-48 V DC 1(01/1C05 E-287, Sh l C50 177 POS-2140 Boric Acid Puwped Feed Valve Digital 0-48 V DC B227/1Cl01 E-241 M27 178 POS-2169 Burle Acid Gravity Feed Valve Digital 0-48 V DC Bl27/IG101 E-241 H27 179 POS-2170 Boric Acid Gravity Feed Valve Digital 0*48 V DC Bl87/IG10l E-241 H87 180 POS-2087 VolU111e Control Tank T-54 Outlet Valve Digital 0*48 V DC Bl6l/IC10l E-242, Sb l H6l 181 POS-3013 Redundant High-Pressure Injection Valve Digital 0-48 V DC Bl5l/IC10l E-244, Sh It Clll lB2 POS-3011 Medundant High-Pressure Injection Valve Digital 0-48 V DC Bl57/IG101 E-244, Sh 4 CUL e 183 POS-3066 Redundant High-Presi;ure Injection Valve Digital 0-4ts V DC B257/1Gl0l E-244, Sh 4 CUR 184 POS-3068 Redundant lligh-Presi;ure Injection Valve Digital, 0-48 v oc B26l/IG10l E-244, Sh It Cllll 185 52-1208 Containment Air Cuoler Recirc Fan V-lA Digital 0-48 V DC IClOl E-216 Bl2 186 S2*l209 Containment Air Cooler Recirc Fan 0-48 V PC IGlOl E-216 Bl2 187 52-1210 Containment Air Cooler Recirc Fan V-lA Digital 0-48 V DC IGlOl E-216 BU 188 S2-ll08 Containment Air Cooler Recirc Fan V-4A Digital 0-48 V DC IGlOl E-217 Bll lB9 152-109 C0111ponent Cooling Pwup P-S2A Digital 0-48 V DC IClOl E-259 All 190 152-208 Cowponent Cooling Water Pump P*52B Digital 0-48 V DC IClOl E-259 All 191 152-116 C0111ponent Cooling Water Puwp P-52C Digital 0-48 V DC IClOl E-259 All 192 R56A Boric Acid Pump P-56A Digital 0-48 V DC IGlOl E-203 Cllll 191 R56B Boric Acid Pump P-46B Digital 0-48 V DC IClOl E-203 Clll 194 PSX-ltsOl Containment Presi;ure Digital 0-48 V DC Sll/IClOl E-207, Sh l Clll 195 PSX-1802 Contairuiient Pressure Digital 0-4d V DC Sl2/1Gl0l E-207, Sh l CllR 196 PSX-1801 Prcs£ure Digital 0-48 V DC S3l/1Cl0l E-207, Sh l Clll 197 PSX-1804 Contai!Ullt:nt Digital 0-48 V DC Sl4/1Gl0l E-207, Sh l cua IU'068l-0411A-NS04-TP10 rNr:flPU "TlnN r.oPtf *"

DATALOCGElt FIELD REMOTE STATION l STATUS INPUTS DLS Olannel Device

  • Cons;..1e*

,, Channt:l Dt:i;c r i1,?t ion

f:Xee Sii!!al Voltaise Scheme*

le llwlfi No Section 198 XPAl 199 XPBl 200 XPCl 201 XPDl 202 Rl.2 Pressurizer Pressure Digital 0*48 V DC Sl7/IC10l E-206, Sh l

  • Cl21 Pressuriier Digital 0-48 V DC Sl8/IC101 E-206, Sh i* Cl2R Pressuriier Pressure Digital 0-48 V DC Sl9/IC10l E-206, Sh l Cl2L Pressurlier Pressure Digital 0-48 V DC S40/1Gl0l E-206, Sb l Cl2R Aux Building Inverter Y210 Sync Digital 0-48 V DC IGlOl E-144 Y210 201 Rl.l AWL Bulldlng lnvertt:r Y220 Dlgltal 0*48 V DC IGlOl E-lltlt Y210 20le Rl. 2 AWL Building Inverter Y220 Sync Dlgltal 0*48 V DC IClOl E-lltlt Y210 20S U-4 AWL Building Battery Charger D-206 Digital 0-48 V DC IClOl E-lltlt Y210 206 AWL Building Battery Charger D-206 Amps Digital 0-48 V DC IGlOl E-9008 207 U-4 Aua Building Battery 01arger D-207 Digital 0-48 V DC IGlOl E-lltlt Y2l0 208 AWL Building Battery Clarger D-207 Amp& Digital 0-48 V DC IGlOl E-9008 209 Sequencer Dlgltal 0-48 V DC 1Gl02 210 211 212 Sequencer Dlgltal 0-48 V DC IG102 e Sequencer Digital 0-48 V DC IC102 Sequenct:r Digital 0-48 V DC IG102 211 Sequencer Digital 0-48 V DC 1Cl02 214 Sequencer Digital 0-48 V DC IG102 21S Sequencer Digital 0-48 V DC IG102 216 Sequencer Dlgltal 0-48 V DC IG102 217 Sequencer Digital 0-48 V DC IG102 218 Sequencer.

Dlgltal 0-48 V DC IG102 219 Sequencer Digital 0-48 V DC 1Gl02 220 221 Sequencer Digital 0-48 V DC 1Gl02 Sequencer Digital 0-48 V DC 1Cl02 222 Sequencer Digital 0-48 V DC 1Gl02 221 224 Sequencer Digital 0-48 V DC 1Cl02 Sequencer Digital 0-48 V DC IG102 22S Sequencer Digital 0-48 V DC 1Cl02 226 Sequencer Digital 0-48 V DC 1Gl02 227 Sequencer Digital 0-48 V DC IG102 228 Sequencer Digital 0-48 V DC IC102 229 Sequencer Digital 0-48 V DC IC102 2l0 Sequencer Digital 0-48 V DC IG102 211 Sequencer Digital 0-48 V DC IG102 212 Sequencer Digital 0-48 V DC IC102 2ll Sequencer Digitol 0-48 V DC 1Gl02 214 Sequenct:r Digital 0-48 V DC 1Gl02 2lS Sequencer Digital 0-48 V DC 1Gl02 236 Sequencer Digital 0-48 V DC 1Gl02 217 Sequencer Digital 0-48 V DC IC102 2l8 Sequencer Digital 0-48 V DC IG102 219 Sequencer Digital 0-48 V DC IC102 240 Sequencer Digital 0-48 V DC IG102 241 Sequencer Digital 0-48 V DC IC102 242 Sequencer Digital 0-48 V DC IC102 241 Sequencer Digital 0-48 V DC 1Gl02 244 24S Sequencer Digital 0-48 V DC 1Cl02 Sequencer Digital 0-48 V DC IC102 246 Sequencer Digital 0-411 V DC IC102 247 Sequencer Digital 0-411 V DC 1Gl02 !lJ'088l-Olel1A-NS04-TPl0 INFORMATION COPY *

DLS Olannel Device 248 249 RU Rl-201 2Sl 2S2 lea and lCll 2Sl Spare DATALOCGER FIELD REMOTE STATION l STATUS INPlfl'S Channel Descrtetion Si15nal !,xee Sil2:!al Voltaie Sequencer Digital 0-48 V DC Awt Bldg lnvtr Y210 Digital 0-48 V DC Awl Bldg Static Switch Y2l0 Digital 0-48 V DC Awl Bldg DLS Power Supply Digital 0-48 V DC Superheater Temperature Digital 0-48 V DC Digital 0-48 V DC Datalogger System Annunciator Breaker Digital 0-48 V DC Scheme* IG102 IGlOl IGlOl IGlOl IGlOl IGlOl IC104 Cons.'.> le Schematic Dwg No Section £-144 Y210 £-144 Y2l0 S900l E-942 C248 *If two sche11e numbers are given, the first corresponds to the given device and its related equipment, the second gives the connection to the datalo&&er.

If only one number is given, it correspomhi to the datalogger connection scheme. k ference Dwg Systea. Input Signals -Held Rewote Station No l, E-Sl, Sh l through Sh 19.

.**

.. . ... . *" DATAlOCGEK FIELD kEHOTE STATION 2 STATUS INPUTS Dl.S eon;;ole Q\annel Device Channel Descrietion Si(5nal :£l'.ee Volta15e Scheme* Schematic Dw15 No Section l DPS-87llA Filter Demin Vessel T-929A Diff Pressure Digital 0-48 V DC K901/1C901 E-925, Sh 19* C201 2 DPS-87llB Filter Demin Vessel t-9298 Diff Pressure Digital O-lt8 V DC K901/IC90l E-925, Sh 19 C20l .,. l DPS-8733C Filter Demin Vessel T-929C Diff Pressure Digital 0-48 V DC K901/IG90l E-925, Sh 19" C20l It DPS-87llD Filter Demin Vessel t-929D Diff Pressure Digital 0-48 V DC K901/IC901 E-925, Sh 19 C20l 5 CIS-8612 Cond Demin System Influent Conductivity Digital 0-48 V DC K901/IC901 E-925, Sh 19 C204 6 DPIS-8734A Post Vessel Resin Strainer F-908A Diff Press Digital 0-48 V DC K901/IC90l E-925, Sh 19 J9107 7 DPIS-87348 Post*Vessel Resin Strainer F-9088 Diff Press .Digital 0-48 V DC K901/IG90l E-925 1 Sh 19 J9105 8 DPIS-8734C Post Vessel Resin Strainer F-908C Diff Presa Digital 0-48 V DC K90l/IG901 E-925, Sh 19 J910lt 9 DPIS-87340 Post Vessel Resin Strainer F-9080 Diff Presa Digital 0-48 V DC K901/IC901 E-925, Sh 19 J9105 10 CIS*86U Cond Dt:min System Ef fliu:nt Conductivity Digital 0*48 V DC K901/IG901

£*925, Sb 19 C20lt 11 FQlS*870ltA Filter Demin Vessel T*929A Eftluent Total Flow Digital 0-48 V DC K90l/IG901 E-925 1 Sh 19 C20l 12 l-'QIS-87048 Filter Demin T*929b Effluent total Flow Digital 0*48 V DC K901/IG901 E-925, Sh 19 C20l ll FQlS-870ltC Filter Demln Vessel T*929C Effluent Total Flow Digital 0-48 V DC K901/1G90l E-925, Sh 19 C20le lit FQIS-870ltD Filter Dellin Vessel T-9290 Effluent Total Flow Digital O-lt8 V DC K901/IG901 1*925, Sb 19 C20l 15 Spare IC901 16 Spare IC901 l7 AIS-8615 Cond De111in System Effluent Sod iWll Digital 0-48 V DC K901/IG901 E-925, Sh 19 C205 18 1S-87l7A Filter Demin Vessel T*929A Recirc Flow Digital 0*48 V DC K901/IC901 E-925, Sh '19 C201 19 FS*87l7B Filter Demin Vessel T-9298 Reclrc Flow Digital 0*48 V DC K901/IC901 E-925 1 Sh 19 C20l 20 FS-87l7C Filter Demin Vessel T-929C Reclrc Flow Digital 0-48 V DC K901/IG90l E-925, Sh 19 C20l 21 FS-87l7D Filter Demin Vessel T-9290 llecirc Flow . Digital 0-48 V DC K901/IC901 E-925 1 Sh 19 C20l 22 CIS-8600 Filter Demin Vessel T*929A Sample Conductivity Digital O-lt8 V DC K90l/IC901 E-925 1 Sh 19 C20lt 21 FS-870ltA Filter Demin Vessel T*929A Effluent Flow Digital 0*48 V DC K901/IG90l E-925 1 Sh 20 C20l 24 FS-87048 Filter Demin Vessel T-9298 Effluent Flow Digital 0-48 V DC K901/IG901

£*925 1 Sh 20 C20l 25 FS-870ltC Filter Dealin Vessel T-929C Effluent .Flow Digital 0-48 V DC K901/IC901 E-925, Sh 20 C20l 26 FS-870ltD tilter Demin Vessel T-929D Effluent Flow Digital O-lt8 V DC K901/IC901 E-925, Sh 20 C20l 27 CIS-8601 Filter Vessel T-9298 Sample Conductivity Digital 0*48 V DC K901/IC90l E-925, Sh 20 C20lt 28 FIS-8747 Cond Dealin System Backwash Wster Flow Di1ital 0-48 V DC K901/lG90l E-925, Sb 20 J920lt 29 Pll-A 1 Pll-8 1 Pll-C, Pll-D Cond Demin System Precoat Sequence Digital 0-48 V DC K901/IC90l E-925, Sh 20 C20l lO Spare IC901 3l Spare IC901 32 Spare 1C901 3l TD*8H, *9H, -lOM 1 zs-121.1 -1lA, C20le -128 1 -llB, -12c 1 -llC Cond Demin System Body Feed Isolation Valve Digital 0-48 V DC K901/IC90l E-925 1 Sh 20 34 CIS-8602 io'Uter Demin Vessel T-92'JC Sample Conductivity

  • Digitiil 0*48 V DC K901/IG90l E-925 1 Sh 20 c2oi. 15 8H-X, 9H-X, lOM-X Cond De111in System Body Feed Any Pump DiKital 0*48 V DC K901/IG90l E-925, Sh 20 c201 l6 lS*B769 Recoat Recirc Tank T-935 level Digital 0-48 V DC K901/1C901 E-925, Sh 20 C20l 37 lS-1'787 Ruin Body Feed T1mk T-932 level Digital 0-48 V DC K90l/IC901 E-925 1 Sh 20 C20l l8 FQIS-8743 Cond Demin Body Feed Total Flow Digital 0-48 V DC K901/IG90l E-925, Sh 20 C20l 39 CIS-8603 Filter Dcmin Vessel T-9290 Sample Conductivity Digital 0*48 V DC K90l/1G901 E-925 1 Sh 20 C20lt 40 ESR-8768 Cond Demin System AC Power Digital 0-48 V DC K901/IC90l E-925, Sh 20 C20l 41 PDS-8778 Cond Dewin System Differential Pressure Digital 0-48 V DC K901/IC901 t:-925, Sh 20 C201 42 PS-8766 Cond lkmin System Oil-Free Air Supply Digital 0-48 V DC K901/IG901 E-925 1 Sh 20 c201 43 Cond Demin System Instrument Air Supply l>igital 0-48 V DC K901/IC901 E-925, Sh 20 c201 44 lolJ Cond Dcmin Syscew HCC-li92 Any Motor Digital 0-48 V DC K901/IC901 E-925, Sh 20 192 leS74-901 Cond Demiu Sy:atem DC Power Digital 0-48 V DC K901/IC90l E-925 1 Sh 20 C20l 46 Spare 1C901 IU>()d8l-04llA-NSOlo-TP10 INFORMATION COPY .**

DATALOGGER FIELD REMOTE STATION 2 Sl'ATUS INPUTS DLS Console* Olannel Device Channel s1e.nal !ne Si&!!al Volta15e Scheme* Schematic Dw15 No Section 4 7 Spare IC90l 48 Spare IC90l 49 LS-8523 Sodium Hypochlorite Storage Tank T-919 level Digital 0-48 V DC J910/IC903 E-926, Sh 19 C202 so C2 Filter Train-A Ruri Digital 0*48 V DC IC903 5935*9/Hlll*ll9 C202 51 LS-8516 Sodium Hypochlorite Day Tank T-920 level Digital 0-48 V DC IC903 S935-9/Hlll*l21t C202 52 CIS-8632 Anion Demin Vessel T-916A Conductivity Digital 0-48 V DC IC903 E-926, Sh 47 C204 53 lS-8415 Raw Water Tank T-910 Level Digital 0-48 V DC IC903 S93S-9/Mlll*l24, C202 54 AST-W Filter Train-A Regeneration Digital 0-48 V DC IC903 S93S-9/Hlll*l30 C202 SS DPS-8430 Anthracite Filters Diff Pressure Digital 0*48 V DC IC903 S93S*9/Hlll*l2S C202 56 LIUO, ll9, Lllll Filter Train-A Ri:generation Digital 0-48 V DC IC903 S935*9/Mlll*ll0 C202 57 DPIS-8429 Carbon Filters Diff -Pressure Uigltal 0-48 V DC IC903 5935-9/Hlll-127 C202 S8 AIS-8622 Anion Demin Vessel T-916A Silica Digit Ill 0*48 V DC Jl006/IG903 E-926, Sh 47 C204 59 LS-8448, 8444 Filtered Water Storage Tank Level Digital 0-48 V DC IC903 S93S-9/Mlll*l07 C202 60 I AIS-8626 Cation Demin Vessel t-914A Sodium Digital 0-48 V DC Jl003/IC903 E-926, Sh 46 ClOS e 61 AlS-8638 Raw Water Chlorine Digital 0*48 V DC JlOOS/IG903 E-926, Sh 47 C20le 62 ll5A, ll2A, Rll filter Train-A Rinse Digital 0-48 V DC IC903 S93S*9/Mlll*llS C202 63 49 Hakeup Water System Any Hotor Overload*

Digital 0-48 V DC Jl001/lC903

£-926, Sh 4S P9000 64 PS-8363 Vacuum Degasifier Vesael T-9lS Digital 0*48 V DC IG903 S93S*9/Mll l

  • ll51 C202 6S C4 Filter Train-B Run Digital 0*48 V DC IG903 S93S*9/Mlll*ll9 C202 66 C6 Mixed Bed Demin Vessel T*9l7A Run Digital 0-48 V DC IG903 593S*9/Mlll-l2lt C202 67 CIS-8633 Anion Demin Veaael T-916B Conductivity Digital 0-48 V DC Jl006/1G903

£-926 1 Sh 47 C2Dlt 68 CIS-8630 Mixed Bed Demin Vessel T-917A Conductivity Digital 0*48 V DC Jl006/IG903 E-926, Sh 47 C204 69 BSTW Filter Train-B RA'!generation Digital 0-48 V DC IC903 5935*9/Hl ll

  • llO C202 10 AHS'I*U Mixed Bed Demin Vessel t-9l7A RA'!generation Digital 0*48 V DC IC903 S93S*9/Hlll*l30 C202 7l LlllO, LRll F.ilter Train-B RA'!generation Digital 0*48 V DC IG903 S935-9/Hlll*ll0 C202 72 Lill, LRll Mixed Bed Demin Vessel T-9l7A Regeneration Digital 0-48 V DC IC903 S93S*9/Hlll-ll0 C202 7l AlS-8623 Anion Demin Vessel T-9168 Silica Digital 0-48 V DC Jl006/1G903 E-926, Sh 47 C2Dlt 74 AlS-8620 Mixed Bed Demin Vessel T-9l7A Silica Digital 0-48 V DC Jl006/IG903 E-926, Sh 47 C204 75 AIS-8627 Cation Demin Vessel T-9148 Sodium Digital 0*48 V DC Jl003/IG903 E-926, Sh 46 C202 76 DPIS-839lA Hued Bed Demin Vessel T-9l7A Diff Pre88 Digital 0-48 V DC IC903 5935*9/Hlll*ll6 C202 77 llSA, ll2A Filter Train-B Rinse Digital 0-48 V DC lC903 S935*9/Hlll-l30 C202 78 lllA, llltA Hiaed Bed Demin Vessel T-9l7A Rinse Digital 0-48 V DC IG903 5935*9/Hlll*llO C202 79 LS-8361 Vacuum Degasifier Vessel T-915 Water Digital 0-48 V DC IC903 S935-9/Hlll*ll5 C20S 80 Llll4 Either Fllter Train Regeneration Digital 0-48 V DC IG903 C202 81 C8 Hiud Bed Dewin Ves11el 1'-9178 Run Digital 0-48 V DC IC903 5935-9/Hlll-139 C202 82 lS-8467A Caustic Storage Tank T-908 level Digital 0-48 V DC IC903 5935-9/Mlll*lll c2029 83 CIS-8631 Mixed Bed Demin Vessel T-9178 Conductivity Digital *o-48 V DC Jl006/IC903 E-926, Sh 47 C204 84 FIS-8539 Caustic Mixing-Tee Input Caustic Flow Digital 0-48 V DC IG903 593S-9/Mlll-:lll C202 8S BHST*U Mixed Bed Demln Vessel T-9178 RA'!gen End* Digital 0*48 V DC IG903 593S-9/Mlll*ll0 C202 86 CIS-862S Caustic Output Dilute Caustic Concentrate Digital 0-48 V DC Jl002/IC90l E-926, Sh 46 C204 87 Llll2, Lllll Mixed Bed Demin Vessel T-9178 Regen Fail Digital 0-48 V DC IG903 593S-9/Hll l *ll0 C202 88 PS-8548 Caustic Feed Pump P-90H Pressure Digital 0-48 V DC IC903 5935-9/Hl 11 *lll C202 89 AIS-8b*2l Hixl:d Bed Demin Vessel T-9178 Silica Diglcal 0-48 V DC Jl00b/IG90l E-926, Sh 47 C204 90 FIS-8534 Caustic Dilution Water Flow Digital 0-48 V DC. IC'J03 S935*9/Hlll-lll C202 91 DPIS-83918 Mixed Bed Demin T-9178 Diff Press Digica l 0*48 V DC 1G903 5935-9/Hll l
  • 136 . C202 92 TS-8502 Caustic Storage Tank T-908 Te111p Ulgital 0-48 V DC IG903 5935-9/Hl 11 *lll
  • C202 93 lllA, ll4A Mixed Bed Demin Vessel T-917H lllnse l.ligltal 0-48 V DC IG'J03 593S-9/Hll l *ll0 C202 94 T1CS-H535 Dilute Caustic tank T-90H Temp Dlgital 0-48 V DC IC903 S935-9/Hlll*lll 95 PS-8343* Hix1ng Air 8luwer C-902 Press Digital 0-48 V DC lC903 5935-9/Hlll-lllt C202 INFORMATION COPY ...

DATALOGCER Hl::LD REMOTE STATION 2 STATUS INPUTS DLS Cons.-> le Olannel Device Channel Signal Type Signal Voltage Scheme* Schematic Dwg Mo Section 96 TS-8530 Hoc-Water Tank Temp Digital 0-48 V DC IG903 5935-9/HlU*lll C202 97 lS-8487A Acid Storage Tank T-907 Digital 0-48 V DC IG903 5935*9/Hlll"'ll2 C202 ... 98 lS-856'* Waste Neutralizer Tank T-921 Digital 0-48 V DC IG903 5935*9/Mlll-136 C202 99 FIS-8545 Acid Hiaing-Tee Input Acid Flow Digital 0-48 V DC IC903 5935*9/Hlll-132 C202 100 PHIS-8634 Waste Tank T-921 pH Digital 0-48 V DC IC903 5935-9/Hlll-136 C202 101 CIS-8624 Acid Htaing-Tee Output Dilute Concentration Digital 0-48 V DC. Jl002/lC903 E-926. Sb 46 C204 102 TS-8503 Waste Neutralizer Tank T-921 Temp Digital 0-48 V DC IC903 5935*9/Hlll-135 C202 103 PS-8518 Acid Feed Pump P-907 Pressure Digital 0-48 V DC IC903 5935*9/Hlll

  • 132 C202 lOlt lS*850lt Waste Neutralizer Tank T-921 Full Regen Digital 0*48 V DC IC903 5935*9/Hlll-136 C202 105 FIS*8540A Acid Mixing-Tee Input Water l"low Digital 0-48 V DC IC903 5935*9/Mlll-132 C202 106 TS-6410 Kaw Water Heat Eachanger

£*901 Outlet Temp Digital 0*48 V DC IC903 5935*9/Hl ll *lVt C202 107 lS-8511 Sodium Hypochlorite leak.age Sump Digital 0-48 V DC J910/lC903

£-926, Sb 19 C238 108 Spare IC903 C204-109 CIS-8636 Hakeup Water Systeai Effluent Conductivity Digital 0-48 V DC Jl005/IC903 E-926, Sb 47 110 Spare IG903 111 AIS-8635 Hakeup Water System Effluen,t SodiWll Digital 0-48 V DC Jl005/lC903

£-926, Sb 47 C205 112 Spare IG903 113 27 4ti0 V Load Center B90 Bus Digital 0-48 V DC lC902/IC902 E-932, Sb 51 B90 114 49 Sump PU111ps HCC 893 Motor Digital 0-48 V DC K902/IC902 E-932, Sb 51 B93 115 49 Feedwater Bldg Services and UVAC HC.C 894 Motor Digital 0-48 V DC lC902/IC902 E-932 1 Sb 51 894 116 49 Feedwater Bldg Services and HVAC HCC 895 Motor Digital 0*48 V DC lC902/IC902 E-932 1 Sh 51 B95 117 27 480 V load Center B9l Bus Digital 0-48 V DC K902/IC902 E-932 1 Sb 5l 191 118 49 Spent Resin Handling HCC ti97 Motor Digital 0-48 V DC lC902/lC902

£-932, Sb 51 897 119 49 Spent Resin Hctndling 140 V HCC P9000 Motor Digital 0-48 V DC lC902/IC902 E-932 1 Sh 51 P9000 120 49 tildg Services 110 V HCC P9001 Motor Digital 0*48 V DC lC902/lC902 E-932 1 Sb 51 P9001 121 LJS-8946 Demin Water Tank T-939 Level Digital 0-48 V DC IL909/IC902 E-932, Sb 51 C203 122 TlS-8945 Dealn Water Tank T-939 Temp Digital 0-48 V DC IT901/IC902 E-932, Sb 5l C203 123 FS-826'* Filtered Air Eahaust Sample System Flow Digital 0-48 V DC B9745/IC902 E-932, Sb 52 C251 121t Spare IC902 125 lS-8834 Dirty Waste Sump Level High Digital 0-48 V DC ll904/1C902 E-932, Sb 53 U90llt 126 LS-8834 Dirty Waste Sump level lU-Hi Digital 0-48 V DC ll 90lt/1C902

£-932, Sb 53 U9014 127 Spare 1C902 128 Spare IC902 129 tDll-8037 Demin Water Tank T-939 Recirc Conductivity Digital 0-46 V DC K902/lC902

£-932, Sb 51 C204 130 lll, 41l, 8R I 9R 1 C226-LOR Heating boiler System Digital 0-48 V DC K902/lC902

£-932, Sb 51 131 llS-8314 l-'uel Oil Tank T-,926 level Digital 0-48 V DC ll 908/1C902

£-932, Sb 52 cu 132 Spare 1C902 133 LS-8882 Recoverable Water Suaap Level Digital 0-48 V DC ll901/IC902

£-932, Sb 52 U9012 Ult Spare IC902 135 LS-8886 Floor and Equipment Drain SWllp level Digital 0-48 V DC IL 903/1C902

£-932, Sb 52 U9011 136 lS-8888 Olemical Drain Suwp level Digital 0*48 V DC IL 902/1C902 E-932 1 Sh 52 U9013 137 LX*ll38X Aua Bldg Sump level Digital 0-48 V DC Jl021/1G902 E-932, Sh 52 C203 138 lS-5210X Turb Bldg Drain .Tank T-41 level Lligital 0*48 V DC Jl021/IC902 E-932, Sh 52 C203 139 FS*8896A 1 B, C, D, £ Eyewash Shower Flow Digital 0-48 V DC K906/IC902

£-932, Sb 52 C203 140 BA, CRl 1-'eedwacer Bldg Air Compressor C903A Digital 0-48 V DC Jll00/IG902 E-932, Sh 52 C203 141 PS-8867 Service Air Header Pressure Digital 0-48 V DC K902/1C902 E-932, Sb 53 C257 142 llll Air Dryer Valve Shift Lligital O-lt8 V DC Jll02/1C902

£-932, Sh 53 C255 143 Spare 1C902 IU'0883-04llA-NS04-TPl0 INFORMATION COPY ...

DATALOGGER FIELD REl'K)TE STATION 2 STATUS INPlTIS DLS ConaJle aumnel Device Channel Descrtecton St 11na l !:r'.l!e Volca'e Scheme* Schemacic Dwi No Section llt4 Spare IC902 v.s BA. Cll.2 Feedwacer Bldg Air Compressor C*903B Digital 0*46 V DC Jll01/IC902 E-932* Sh Sl C20l 146 FS*8S90* rs-8s9o Saaapling System Cooling Wtr Pump P-949 Digital 0-48 V DC K902/IC902 E-932* Sh Sl C206 147 2Rl Instrument Air Dryer Dew Poinc D1gical 0-48 V DC Jll02/IC902 E-932* Sh Sl C2SS 148 AITS*8230AX Phase Separacor Tank T-936A Turbidity Digital 0-48 V DC Jl020/1C902 E-932* Sh Sl C20l 149 1ITS-8792A Phase Separacor Tank T*9l6A Level Digital 0*48 V DC Il90S/IC902 E-932* Sh Sl C20l lSO FS-8234A Decant Pump P-9lOA Discharge Flow Low Digital 0-48 V DC 1F90l/IC902 E-912* Sh Sl C20l Ul FS-82lltA Decant Pump P-9lOA Discharge Flow High Digital 0-48 V DC 1F90l/IC902 E-912* Sh Sl C20l 1S2 AlTS-82lOBX Phase Separator T-9368 Turbidity Digital 0-48 V DC J l020/IC902 E*9l2a Sh Sl C20l-lSl lltS-87921 Phase Separator T-9l6B level Digital 0-48 V DC IL 906/IC902 E-9l2a Sh Sit C20l 154 FS-82348 Decant Pump P-9308 Discharge Flow Lo Digital 0-48 V DC IF902/IC902 E*9l2a Sh S4 C20l lSS FS-82348 Decant Pump P-9lOB Discharge Flow High Digital 0-48 V DC IF902/IG902 E*9l2a Sb Sit C203 lS6 Spare IC'J02 e lS7 Spare IC902 1S8 Spare IC902 1S9 Spare IC902 160 Spare . IC902 161 PS*8671A Boiler Room Fire Sprinkler Flow Digital 0-48 V DC K902/IC902 E-9l2* Sh SS C2S7 162 PS-867U Boller Room Fire Sprinkler Flow Digital 0-48 V DC K902/IC902 K-932, Sb SS C2S7 l6l Spare IC902 164 Spare IC902 l6S Spare IC902 166 Spit re IC902 167 Spare IC902 168 Spare IC902 169 Spare IC902 170 Spare IG902 171 12. 74 Feedwater Bldg Battery Charger/Invert Y2SO Digital 0*48 V DC K902/IC902 E-932* Sh Sl C20l 172 S900l-l Feedwater Bldg DLS P\lr Supply Digital 0-48 V DC K902/IC902 E*9l2, Sh Sl C20l 171 lS-8301 Condensate Receiver Tank T-927 level low . Digital 0-48 V DC K902/IC902 E-932, Sh S2 C22S 174 lS-8101 Condensate Receiver Tank t-927 level High Digital 0-48 V DC 1(902/IC902 K-9l2a Sb S2 C22S 11s Spare IC902 176 Spare IC902 111 l25Ci. 24lCll Flatbed Filter Digital 0-48 V DC J9ll/IC902

£*9l2a Sh Sit C2l0 178 108H*OL Flatbed Filter H-IJ04 Conveyor Motor Digital 0-48 V DC J911/IC902 K-932, Sh Sit c2109 179 Spare 1C902 180 Spare IC902 1.81 llSal Flatbed Filter H-904 Instr Air Press Lligital 0-48 V DC J911/lC902 K-9l2a Sh S4 c210 182 SpMre IC902 l8l Spare IC902 l8lt Spare IC902 185 Annun logic Cabinet. C-257 DC Power Digital 0-48 V DC IC902 C2S7 l86 lll Pretreat and Makeup l>emin Cont Pnl C-202 DC Power Digital 0*48 V DC IG902 £-926, Sh lO C202 INFORMATION COPY .**

DLS Oumnel 187 188 189 190 191 192 Spare Spare Spare Spare Spare Spare Device DATALOCGER 1"11:.Ll.I REMOTE STATION 'I. STATUS lNPl1IS Channel Description Signal Type Sl!$flal Voltage Scheme** 1G902 1Glj()2. 1G902 1C902 1G902 1C902

  • Consci.le
  • Schematic Dwg No Section *If two scheme numbers are given, the first corresponds lo the device and its equipment, the second give11 the connection to_ the datalogger.

If ooly one nUlllber is given, it corre11pondti to the datltlogger connection 11che111e, Reference Dwg Oaulogger Syste11 lnpur Signals -Hdd Remote Station No 'l, t::-54, Sh l through Sh 12 .* IU'O&il-041 lA-NS04-1'l'lO INFORMATION COPY .... ...

IC0685-0236-NL04 ATTACHMENT III Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Event Recorders Inputs "Information Copy" July 1, 1985 (2 Pages)

SERVICE I Events Recorcle Channel SERVICE Events Recorder Channel neutron t ux Cbanne ll1gh pover rate of exchange " B1gh pressurizer pressure * " " I.ov t.be.rml margin/pressure " " S.G. Bo. l tov Press " " j S.G. lio. 2 I.o Presa " " I.o Pr1 coolant tl.o loop l " 11 :s.o. No. 1 ID level " 11 I. s.o. Bo. 2 Io level " " I.oss of load (turb1De trip) " " iClutch pover relay 10.-open '. PJ7rK P7lA OD I 1'11.l'K P7lB OD 1 DU-ty waste Bi level alarm \ Dirt)' vaate B1 level al.army 'Equipment drain pump P75A on lq\dpDeDt clrain pump P75B OD *rk -flit Im& coolant pump P5aA ott I .. 1-2 1-3 1-4 1-5 1-6 1-7 1-8 1-9 1-10 1-11 1-12 1-13. l-14 1-15 1-16 1-17 1-18 1-19 1-20 1mar,Y coo t pump B Ot *

  • Primar,y coolant pump P50C Ott Priar)' coolaDt pump P50D Ott Pressurizer Pov RV CV1042 open Pressurizer Pov RV CVlo43 open Pressurizer spra)' valve CV1057 open Pressurizer spray valve CV1059 open Back-up heaters on Cbarg1Dg pump P55A on Cbarg1Dg pump P55B OD Charg1Dg pump.P55C on. L.D. ORF atop CV2003 open L.D.ORF atop CV2oo4 open L.D. ORF *top CV2005 open Beater clrain pump PlOA ott Beater clra1D pump PlOB ott 0\10703 (F. W. ) closed CV070l (F. W. ) closed Time Spare -

l-1 l-22 1-23 1-24 l-2*5 l.-26 1-27 1-28 . 1-29 1-30 1-31. 1-.32 1-33 1-34 l-35 1-36 1-37 1-38 1-39 1-40 ' SERVICE Events Recorder Channel SERVICE Events Recorder Cbannel H1gh neutron flux Cbanne H1gh pover rate ot change " " B1gb pressurizer pressure 11 " Iov tbermal margin pressure " " :-I.ow pressure steam gen. fl " " I.ov pressure steam gen. #2 " "

  • _ Lov primar)' coolant nov loop#l 11 2-1 2-2 2-3 2-4 2-5 2-6 2-7 Containment spray pump P5 on Containment spray pump P54B on Containment spray pump P54C on Containment sump valve CV3029 Cont.aimnent sump valve CV3030 smw t.aDk valve cv3031 SIRW tank ftlve cv3057. Cont.a1Dment spray cv3001 Lov"water level steam gen. #1" " 2-8 ContaimDent
  • spray cv3002 Lov vater level steam gen. " 2-9 L.P. 1.Dject M03oo8 !Das of load (turbs.ne*

trip) " 11 2-10 L.P. 1.Dject MO)OlO Clutch power relay K2 open " 2-11 L.P. 1.Dject MO)Ol2 Main stm. isolation YBlve CV0501 closed 2-12 L.P. 1.Dject M03014 Ma1D atm. isolation YBlve CV0510 . " 2-13 CV-2056 let clown to M!L1n *stm. bypass ftl.ve CVOSll open 2-14 Ti.me m.rk -.

YBlve cv078o open 2-15 Spa.re Steam &mp wl.ve CVOT19 open. 2-16 steam clump ftlve cv0781. open 2-17 Steam clump ftlve CV:&& open 2-18 'l'1ae mark -*iov 2-19 L.P.s.1. pump Jt'} 2-20 L.P.S.I. puilp P67B OD 2-21 open open close close open open open open open open J[.P.S.1.

pump P66A OD 2-22 B.P.S.I. pump P66B on 2-23 .* £uz 1W pp_ (Started) 2-24 INFORMATION COP\' 2-25 2-26 2-27 2-28 2-29 2-30 2-31 2-32 2-33 2-34 2-35 2-36 2-37 2-38 2-39 2-40 Events Recorder Channel e Eve ow SERVICE SERVICE Recorder Channel H neutron we nne i ra

  • so tion s ra waste vent Bigh power rate ot exchange u " 3-2 Aux FW pp P8C Suction Preas* (Low)
  • High pressurizer pressure " " 3-3 Cont. air cooler serv. vtr. ICV0867 open Lov thenzal margin pressure " " 3-4 Cont. air cooler serv. vtr. ;cvo873 open I.ov pressure steam gen. #1 11 " 3-5 Cont. air cooler serv. vtr. CVo864 open I.ov pressure steam gen. #2 11 11 3-6 Cont. air cooler serv. vtr. CV086l. open I.ow prinary coolant tlov loop 1/1" 3-7 Service water pump P7A on Service vat.er pump P7B on vat.er leveJ, steam gen. #1 11 3-8 Service vat.er pump P7C on lDW vat.er level steam gen. 12 " 3-9 .Fire pump -motor on Loss ot load (turbine trip) 11 3-10 Fire pump -diesel on Clutch power rela.y K3 " " 3-11 Heater ElA drain CV0618 open Turbine stop valve 0569 closed 3-12 Heater ElB drain cvo629 el O'M Of'e/J .SC Turbine stop valve 0571 closed 3-13 Heater E2B drain open Turbine stop valve 0573 closed 3-14 mark -

Turbine stop.,)'&lve 0575 closed 3-15 Aux FW pp P8A Suction Press (Low) F. W. pump tur'D1ne driver A trip 3-16 F.W. pump turbine driver B trip 3-17 Aux FW pp PSA (Started) . 3-18 . Time mark :

3-19 H.P. inject. M03007 open 3-20 H.P. inject. M03009 open 3-21 H.P. inject. M03064 open 3-22 H.P. inject. M03062 open 3-23 Cont. isolation signal 3-24 3-26 3-27 3-28 3-29 3-30 3-31 3-32 3-33 3-34 3-35 3-36 3-37 3-38 3-39 I 3-40 SERVICE Events Recorder.

Channel SERVICE !:vents Record.et Cbanne-< neutron lux c 0 E9D Reheat intercept ve CV 5 5 clos ,... -21 H1gh power rate of change " " 4-2 E9A Reheat intercept valve closed 4-22 High pressurizer pressure " " 4-3 E9C Reheat intercept valve CVO *47 closed 4-23 lDv thenne.l.

margin/press " " 4-4 Tank T4A cvo539 open 4-24 I.ov pressure steam gen. fl " " 4-5 Tank T4B CV055? open 4-25 lDw pressure steam gen. lie " " 4-6 i!rv 06a2 closed 4-26 tov pr1 coolant flow loop#l ti . II 4-7 J1N ()()06 closed 4-27 S G No. 1 Low level " -" 4-8 CV 06a2 closed 4-28

  • S G No. 2 IDw level " II 4-9 CV o6o6 closed 4-29 A Loss of load (turbine tri,p) " II 4-10 * 'B1!V 0610 closed 4-30 Clutch power relay K.:.4 open " II 4-ll. 'B1!V o62*o closed 4-31 Reheat stop "81.ve CV0534 closed 4-12 'B1!V o612 closed 4-32 Reheat stop valve CV0544 closed 4-13 CV o612 closed Reheat stop valve CV0537 closed , 4-14 CV o621 closed 4 34 Reheat stop valve CV0548 4-15 J1N o623 closed 4-35; CV0731 open 4-16 CV o614 closed 4-36. j CV0732 make-up) . -open 4-17 CV o624 closed 4-37 CV o6l.7 .. open 4-38 l cv0733 (fast make-upl open 4-18 slow speed 4-35r
  • each min a ow speed Time -* Time mark -each sec fast speed 4-li Reheat 1nterc_ept valve CV0535 closed -20 E9B Spare fast speed *4-4o INFORMATION IC0685-0236-NL04 ATTACHMENT IV Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Datalogger Analog Inputs "Information Copy" July 1, 1985 (2 Pages)

DLS Olannel Tag No SOl S02 FY-0701 SOl FY-0703 SOit Ft-0404 sos NI-OOS S06 NI-006 S07 Nl-007 S08 HI-008 S09 NI*OOS SlO Nl-006 Sll Nl-007 Sl2 NI-008 SU Rl Slit Ill SlS il Sl6 ll2 Sl7 LT-OlOL\ Sl8 PT-0103 Sl9 TI-Oll2HA S20 TI-Oll2CA S21 TI-Ol22HA S22 Tl-Ol22CA S23 PI*Ol02A S21t iolt-0705 S2S PlC-075li S26 PIC-0752A S27 LT-0702 S28 1T*0704 S29 Spare SlO Turb EH Control 531 WH 532 lilt S33 Spare Slit Spare S3S Spare S36 Spare 537 Spare 538 Spare 539 Spare SltO Spare Sltl Spare Slt2 Spare SU Spare S44 Spare Spare Spare 1lP()lj1U*04l lA*NS04-l'P 10 DAl'ALOGCElt HELD STATION l ANALOG lNPlffS Channel Description Hliln Generator Voltage lWgulator Output Steam Generator E-50A rlow Steam Generator E-508 Flow Safety Injection Pumps Recircµlation Flow Safety Channel-A Neutron FlWl Safety Channel-B Neutron FlWl Safety Olannel-C Neutron Flux Safety Neutron Flux Safety Olannel-A Neutron Flux Safety Channel-B Neutron Flux Safety Channel*C Neutron Flux Safety Channel-D Neutron Flux AWl Bldg Datalogger 125 V DC Positive Bua Volt to Ground Aux Bldg DataloK&er 12S V DC Negative Bua Volt to Ground feedwater Bldg 125 V DC Positive Bua Voltage to Ground Feedwater Bldg ll5 V DC Positive BIMi Voltage to Ground Pre11suri2er T-72 level Pres11ul'12er T-72 Pressure Primary Cool1mt Loop One Outlet Temp Pri111&ry Coolant loop One Inlet Temp Cool1mt loop Two Outlet Temp Primary Coolant loop Two Inlet Temp Reactor Coolant Flow Steam Generator Total Stea111 flow Steam Generator E-50A Pressure Stea111 Generator E*!>OB Pressure Steam Ceueracor E-SOA level Steam Generator

£-508 Level Hain Turbine Speed 21t00 V AC Bus lC Voltage 2400 V AC Bus lD Voltage Signal 1)pe Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Analog Sil:a!!al Volta11ie 0-125 V DC 1-5 V DC 1-5 V DC 1-5 V DC 0-10 V DC 0-10 V DC 0-10 V DC 0*10 V DC 0-10 V DC 0-10 V DC 0-10 V DC 0-10 V DC 0-125 V DC 0-125 V DC 0-125 V DC 0*125 V DC 1-S V DC. l-5 V DC 1-5 V DC l-5 V DC 1-5 V DC 1*5 V DC 1-5 V DC l-5 V DC l-5 V DC l-5 V DC 1-5 V DC l-5 V DC 0-120 v Ac. Scheme* Schematic Dw15 No E01/IG05 E-9 IF32/IG05

£-69 IF33/IC05 E-69 Ult0/IC05 E-94 IN15/IC05 E-62 1Nl6/IC05 E-62 INl7/IC05 E-62 IN18/IC05 E-62 1Nl5/IC05

£-62 1Nl6/IC05 E-62 INl7/lC05 E-62 1Nl8/IC05

£-62 Dl007/1COS

£-90l5 . . Sb 3 Dl007/IC05 E-9015, Sb 3 Dl006/1C05

£-9015, Sb l Dl006/IC05

£-9015, Sb 3 ll09/IG05 E-82, Sh l IP60/IG05 E-84 1 Sh 3 IT32/IG05

£-96, Sb 6 1Tl2/IC05 E-96, Sb 6 IT32/1G05 E-96, Sb 6 ITJ2/IG05 E-96, Sh 6 IF27/1C05 E-96, Sh 4 1Fl2/IG05 E-69, Sh 2 1P2l/IG05 E-83 IP27/ICOS E-83 IFJ2/IG05 E-69, Sh 2 U'33/1C05

£-69, Sh 2 IG05 E-632 Al00l/IG05 E-11 Al002/IG05

£-11 INFORMATION COP't *eona..ile*

Section EOl Cl2 Cl2 Cl2 C06-l C06-l C06-l C06-l C06-l C06-l C06'."l C06-l C273 C273 C27l C27l Cll Cll Cll Cll Cll Cll Cll Cl2 Cl2 cu Cll Cll COl COit ;, e C041le ...

DLS Dlannel S47 S48 Spare Spare Tag No DATALOCCER FIELD REMO'fE STATION 1 ANALOG INPUTS Channel Description Signal !ype Sll!.llal VoltaMe Schewe* Con1*ole Scheuwtic Dwg No Section *1he_ first schelle l\Ullber will i;how the instrument and its related equipwent.

The second scheme nUlllber ls the connecdon to the datalouer.

IC.cference Dwg: Datalouer Syste11 Input Slgnals -Fleli:1 Re111Ute Station No l, E-Sl, Sh 2l and 22. IP088l-0411A-NS04-TP10 INFORMATION COP't ...

IC0685-0236-NL04 ATTACHMENT V Consumers Power Company Palisades Plant Docket 50-255 Generic Letter 83-28 Critical Function Monitor Inputs "Information Copy" July 1, 1985 (8 Pages)

. , CRITICAL f1JNCTION MONITOR INPllIS Signal ,.. Item ..l!2.. Taa No Device Si&!!al Voltage Schematic Dw& No Console Section l AJl-0203 PCS Bordn Analog 0-5 VDC 1801 !*70 co2-1 2 U-0103 Pzr Htr Transformer Amps Analog 0-5 VDC All05 co2-2 3 AI-OlOlt Pzr Htr Transformer Amps Analog 0-5 VDC Al211 C02-2 4 P50A PCP A Amps Analog 0-5 VDC A2103 Cl2*3 5 P508 PCP 8 Amps Analog 0-5 VDC A2203 Cl2*3 6 P50C PCP C Amps Analog 0-5 VDC A210lt Cl2*3 1 P50D PCP D Amps Analog 0-5 VDC A2204 Cl2*3 8 dPT-0112AA PriJDary Coolant Flow Channel l Analog 1-5 VDC IF27 E-96, Sh 4 Cl2*3 9 dPl-0112BA PriJDary Coolant Flow Channel 2 Analog 1-5 VDC IF27 E-96, Sh 4 Cl2*3 10 dPT-0122CA Primary Coolant Flow Channel 3 Analog 1*5 VDC IF27 E-96, Sh It Cl2*3 11 dPT*0122DA Primary Coolant Flow Channel It Analog 1-5 VDC 1F27 E-96, Sh It Cl2*3 12 NI-001 Startup Count Rate X Analog 0*10 VDC IN03 E-61, Sh 2. co2-1 13 Nl-002 Startup Count Rate Y Analog 0-10 VDC IN03 E-61, Sh 2 co2-1 e lit NI-003 Wide Range Power Analog 0-10 VDC IN03 E-61, Sh 2 co2-1 15 Nl-004 Wide Range Power Analog 0-10 VDC IN03 !*61, Sh 2 co2-1 16 PSl*l051A*l6.B-l Acoustical Monitor Channel l Digital 125 VDC Kll E-293, Sh 6 Cl2-lt 17 18 FS-0954 HP Safe Injection Pump P66C Seal Digital 125 VDC Kll E-292, Sh It cu-2 19 FS-0958 Engr Safegrd Pump Seal Water Digital 125 VDC Kll E-292, Sh It Cll-2 20 FI-0202 Primary Letdown Flow Analog 1*5 VDC IF20 E-73, Sh 4 Cl2-lt 21 FI-0212 Charging Line Flow Analog 1*5 VDC IF19 E-73, Sh 1 Cl2-lt 22 FI-0301 CHMI Spray Analog 1*5 VDC IFll E-94, Sh l Cll-lL 23 FI-0302 CNKl' Spray Analog 1-5 VDC 1Fl2 E-94, Sh l cu-u 24 FI-0306 Cooling Flow Control Analog 1-5 VDC IF2l E-73, Sh 6 Cl2*3 25 Fr-0307 LPSI Flow Loop A Analog 1*5 VDC IF03 E-93, Sh l Cll*lL 26 FI-0308 HPSI Flow Loop A Analog 1-5 VDC IF04 E-93, Sh l Cll-lL 27 FT-0309 LPSI Flow Loop 8 Analog 1-5 VDC IF05 E*93, Sh l Cll-lL 29 FT-0310 HPSI Flow Loop 8 Analog 1-5 VDC IF06 E-93, Sh l Cll-lL 29 FT-0311 LPSI Flow Loop C Analog 1*5 VDC IF07 E-93, Sh l Cll-lR 30 FT-0312 HPSI Flow Loop C Analog 1*5 VDC IF08 E-93, Sh l Cll*lR 31 FT-0313 LPSI Flow Loop D Analog 1-5 VDC IF09 E-93, Sh l Cll-lR 32 FT-0314 HPSI Flow Loop D Analog 1-5 VDC IFlO E-93 Cll-11 33 FT-0701 Stm Gen E-50A FW Flow Analog 1-5 VDC IF32 E-69 c12-5 34 FT-0702 Stm Gen E-50A Steam Flow Analog 1*5 VDC IF32 E-69 Cl2-S 35 FT-0701 Stm Gen E-508 FW Flow Analog 1-5 VDC IF33 E-69 Cl2-5 36 FI-0704 Stm Gen E-508 Steam Flow Analog 1-5 VDC IFJJ E-69 Cl2-5 37 FT-0736 Awt FW Flow to Stm Gen E-50B Analog 1*5 VDC IF23 E-76, Sh It Cl2-3 38 FT-0737 Aux FW Flow to Stm Gen'E-50A Analog 1-5 VDC IF21t £-76, _Sh 4 Cl2*3* 39 FT-o83l Ctn' Air Clr Serv Water Leak Det Analog 1*5 VDC IF35 £*74 Cl2-lt 40 LT-0102A Pressurizer Level Channel A Analog 1-5 VDC IL37 E-82, Sh It Cl2*3 Atl LT-0206 Boric Acid Tk T-5JB Analog 1-5 VDC IL36 £*90, Sh 5 Cl2-lt 42 LT-0208 Boric Acid Tk T*53A Analog 1-5 VDC 1Ll5 E-90, Sh 5 Cl2-lt 43 LT-0331 SlRW Tank Ck.t 2 Analog 1-5 VDC IL06 E-87 Cll-R 44 Analog 45 LT-0392 CHKl' Sump Level Analog 1-5 VDC IL152 £-87, Sh 4 Cll-R 46 U-0365 Safety Inject Tank T-82A Analog 1-5 VDC IL16 E-92 Cll-lL 47 LT-0368 Safety lnjcct Tank Analog 1-5 VDC IL17 E-92 Cll-lL 48 LT-0372 Safety Inject Tank T-82C Analog 1-5 VDC 1Ll8 E-92 Cll*lR 49 LT-0374 Safety Inject Tank T-82D Analog 1-5 VDC 1Ll9 E-92 Cll-lR INFORMATION COPY

...

CRITICAL FUNCTION MONITOR INPUTS Item Signal . ...!!2-Tas No Device DescriEtion SiJ2!al Voltage Scheme Schematic Dws No Console Section so TT-0115 Cold Leg Loop l Temp WR Analog 1-5 VDC 1L20 E-96, Sh 3 Cl2*7 51 TT-0125 Cold Leg Loop 2 Temp WR Analog 1-5 VDC IT21 E-96, Sh 3 Cl2*7 I! 52 Lt-0702 Steam Gen E*50A Level Analog 1-5 VDC 1722 E-69, Sh 2 Cl2*1 53 LI-0704 Steam Gen E-508 Level Analog 1*5 VDC 1Fl2 E-69, Sh 2 c12-1 54 Lt-0729 Condenser Level Analog 1-5 VDC 1Fl3 E*80 ci>l-2 55 LT-0752A Steam Gen E-508 Low Level Analog 1-5 VDC IL25 E-78 Cl2*3 56 Pf-0701 Stm Gen Feed Pump PlA Disch Analog 1-5 VDC 11Jt9 E-81 C01*2 57 LI-1012 Clean Waste Receiver Tanks Analog 1-5 VDC IP04 E-63 CltO 58 LI-1014 Clean Waste Receiver Tanks Analog 1-5 VDC 1L53 E-63 C40 59 LT-1016 Clean Waste Receiver Tanks Analog 1-5 VDC 1L54 E-63 CltO 60 Lt-1018 Clean Waste Receiver Tanks Analog 1-5 VDC IL55 E-63 C40 61 LT-2021 Condensate Storage Tank Analog 1*5 VDC IL56 E-87 Cll*l 62 LE*0446A CJtNT Floor Level Analog 1-5 VDC 1L24 E-87, Sh 3 Cll*L 63 LI-0116 Quench Tank T-73 Analog 1-5 VDC IL29 E-72, Sh 2 Cl2*3 6lt 65 PT*l805A Containment Building Pres'sure

.. Analog 1-5 VDC IP147 E-99, Sh 5 Cll-R 66 Pf*Ol02A Pzr Pressure SI Channel Analog 1-5 VDC 1P33 E-84, Sh 2 Cl2*3 67 PT-0103 Pzr Wide Range Preas Analog 1-5 VDC 1P60 E-84, Sh 3 Cl2-l 68 Pf-0116 Quench Tank T-73 Analog 1-5 VDC 1P61 E-72, Sh l Cl2-l 69 PT-0202 lntermed Pressure Letdown Cntrl Analog 1-5 VDC lP6lt £-7l, Sh 5 Cl2*4 70 PT-0205 Volume Control lank I-54 Analog 1-5 VDC IP6S E-71, Sh 2 Cl2*J 71 PT-0318 SI Pu111p Disch Press Ckt 4 Analog 1-5 VDC IP44 E-86 Cll*R 72 Pf-0363 Safety Injection Tk I-82A Analog 1-5 VDC IPSO £*85, Sh 2 Cll*lL 73 PT-0367 Safety. Injection Tk T-828 Analog 1-5 VDC IPSl E-85, Sh 2 Cll*lL 74 Pf-0369 Safety' Injection Tk T*82D Analog 1*5 VDC lP53 E-85, Sh 2 Cll-lR 75 PT-0371 Safety Injection Tk T-82C Analog 1-5 VDC 1PS2 E-85, Sh 2 Cll*Ul 76 Pf-0375 SI Pump Disch Press Ckt 3 Analog 1-5 VDC IP43 E-86. Cll*lL 77 PT-0521 Aux FW Pump Turb Stm Press Analog 1-5 VDC IP06 E-81 COl-2 78 Pf-0751B SC £-50A Low Pressure Analog 1-5 VDC IP24 E-83 Cl2*3 79 PT-07528 SC E-508 Low Pressure Analog 1-5 VDC IP28 £*83 Cl2*3 80 Pf-0763 Condenser Vacuum Analog 1-5 VDC lP49 E-81, Sh 2 Cll*2 81 PT-0789 SC Aux Feed PP Dish Hdr Press Analog 1-5 VDC IP07 E-81 COl-2 82 Pr-0918 Comp Cool Heat Exch Inlet Press Analog l-5 VDC IP46 E-88, Sh 2 C08-R 83 84 PT*l812A Containment Pressure WR Analog 1-5 VDC IP146 E-99, Sh 5 Cll*I 85 RR-0202 Process Radiation Monitor Analog 1-5 VDC IR59 E*57 Cll 86 RCS Ht Vp Rhte 87 n-0210A Boric Acid Hkup Dilut Flow Analog 1-5 VDC IFOl E-90 Cl2-J 88 LI-1115 Dirty Waste Draln Tank T-60 Analog 1-5 VDC 1L62 E-63 CltO 89 LI-1117 Dirty Waste Drain Tank T-60 Analog 1-5 VDC IL63 E-63 CltO 90 SIAS Status 91 Recirculation Activation SIG 92 93 LT-0103 Pzr Wlde Range Level Ind Analog 1-5 VDC 1Ll4 E-82, Sh 3 Cl2-4 94 Lt-0751A Steam Gen E-50A Low Level Analog 1-5 VDC IL45 E-78 Cl2*3 95 LI-020S Volume Control Tank Analog 1-5 VDC IL28 E-71 Cl2-3 96 Temp Di(f on Tower Analog 1-5 VDC 97 TE-0303 Shutdown Heat Exchange Inlet Analog 1-5 VDC 1Tl2 E-95, Sh 2 C03*R 98 Standard Dev Wind Dir lOH Analog 1-5 VDC INFORMATION COP\' ...

CRITICAL f1JNCTION MONITOR INPllIS ** . .. Signal ltell Tag No Device Description

.-!I.P!..

Signal Voltage Schematic Dwg No Console Section 99 Standard Dev Wind Dir 60H Analog l-5 VDC II' 100 Wind Direction JQH Analog l-S VDC 101 lT-0101 Pzr Vapor Temp Analog 1-5 VDC It23 E-98 C-12-4 102 lT-0102 Pzr Wtr Phase temp Analog 1-5 VDC I'I21t E-98 C-12*3 103 Wind Direction 60H Analog l-5 VDC lOlt Wind Speed 30H Analog 1-5 VDC 105 Wind Speed 60H Analog 1-5 VDC 106 NI-005 Power Range Safety Channel A Analog 1*10 VDC JNOlt E-62, Sh 2 C02-l 107 lT-Oll2CA Pria Coolant 'Iemp Protective Ch A Analog 1-5 VDC 1T32 E-96, Sh 6 Cl2*7 108 lT-Oll2CB Prim Coolant 'Iemp Protective Ch B Analog 1-5 VDC ITll E*96, Sh 6 Cl2*7 109 lT-Oll2HA PrlJll Coolant Temp Protective Ch A Analog 1-5 VDC 1Tl2 E-96, Sh 6 Cl2*7 110 lT-0122CA Prim Coolant Temp Protective Ch A Analog 1-5 VDC l'I32 E-96, Sh 6 Cl2-7 ill lT-0122CB Prim Coolant 'Iemp ProtecUve Ch B Analog 1-5 VDC ITll E-96, Sh 6 . Cl2-7 112 lT-0122HB Prim Coolant Protective Cb B Analog 1-5 VDC 1T33 E-96, Sh 6 Cl2-7 113 lT-03SlB Shtdn Cool Inlet-Outlet Temp Analog 1-5 VDC ITltlt E-73, Sh 8 Cl2*8 11 .. . Nl-oo6 Power Range Safety Channel B Analog 0-10 VDC INOlt E-62, Sh 2 C02-l 115 lT-0205 Volume Control Tank Analog l*S VDC IT77 E-71, Sh 2 C02-3 116 TIA-0328 SIRW Tank Analog 1*5 VDC ITU E*9S Cll*L ll7 lT-0201 Regen Heat Exchanger Outlet Analog 1-5 VDC ITltl E*7l C02*3 118 lT-0203 Letdown HX Dis 'Iemp Analog 1-S VDC ITltl E-73 C02-3 119 SP-3 CNHT High Preas Tr A Digital 120 VAC .IC20 E-208 Cll-3 120 SP-6 CNKr High Presa Tr B Digital 120 VAC IG21 E-208 Cll*ll 121 SR-3 CNHT High Radiation Tr A Digital 120 VAC IC20 E*208 Cll-3 122 SR-6 CNKr ttigh Radiation Tr B Digital 120 VAC IC21 E-208 Cll*lll 123 SIS*7 Safety lnj Actv Tr A Digital 120 VAC IC23 E-209 Cll*lL 124 SIS-10 Safety Inj Actv Tr B Digital 120 VAC IC22 E-209 Cll*ll 125 PT-OSBO Turb Hain Still Inlet Press Analog l*S VDC Tl8 E-123, Sh 3 C01*2 126 PT-0703 Sta Gen Feed Pump PlB Disch Analog l-S VDC IP05 E-81 COl-2 127 LSX-0327 Recirculation Actuation Sig Digital 120 VAC IC20 E-207 Cll*lL 128 LSY-0327 Recirculation Actuation Sig Digital 120 VAC IC20 E*207 Cll*lL 129 Kl Reactor Trip Breaker l Digital 125 VDC IGOl E-298, Sh 1 Cll 130 l2 Reactor 'Irip Breaker 2 Digital

  • 125 VDC IG02 E-298, Sh It Cll 131 lt2*1S0l Prop Htr Status No l Digital 120 VAC 81501 E*2Slt co2-2 132 42-1502 B/U Htr Status Digital 120 VAC 81500 E*2Slt, Sh 2 co2-2 133 42-1506 B/U Htr Status Digital 120 VAC BlSOO E*2Slt, Sh 2 co2-2 e lllt lt2-1601 Prop Htr Status No 2 Digital 120 VAC 81601 E-2Slt, Sh l co2-2 135 lt2-1602 B/U Htr Status Digital 120 VAC 81600 E*251t, Sh 2 co2-2 136 lt2-1606 B/U Htr Stotua Digital 120 VAC 81600 E*2Slt, Sh 2 co2-2 137 P8A Aux fW Pump A Status P8A Digital 125 VDC All04 !*196 COl-2 138 139 P2A Condensate Pump P2A Digital 125 VDC A2105 E-182 COl-2 lltO P2B Condensate Pwnp P2B Digital 125 VDC A220S E-182 COl-2 lltl 71t-IC7Al Hain Feed Pump PlA Status Digital 125 VDC lCOl E-298, Sh 6 Cll DR END llt2 71t*IC7Bl Hain Feed Pump PlA Status Digital 125 VDC lCOl E-298, Sh 6 Cll DR END lit) 252-103 PCP A Status (lA) Digital 125 VDC ICOl E-98* Sh 2 Cll DR END 11+4 252-203 PCP B Status (18) Digital 125 VDC ICOl E-98, Sh 2 Cll DR END llt5 252-104 PCP C Status (2A) Digital i25 VDC lCOl E-98, Sh 2 Cll DR END llt6 2S2*20lt PCP D Status (2b) Digital 125 Vl>C ICOl E-98* Sh 2 Cll DR END llt7 PS4A CNHI' Spray Pump P54A Status Digital 125 VDC Al210 E-251 COl-R llt8 P51tB CNKr Spray PWDp PS4K Status Digital 125 VDC Alll2 E-251 COl-L RP088)-0410A-NS04 INFORMATION COPY ...

CRITICAL HONITOR INPUTS .. :. ltea Signal " Tag No Device Sil2,!al Voltage Scheme Schematic Dw15 No Conaole Section 149 P54C CNKI Spray Pump PS4C Status Digital 125 VDC Alll4 E-251 C03-L I< 150 PS5A Charg Pwnp P55A Status Digital 125 VDC Bl205 E-257 co2-2 151 P558 Charg Pump P5SB Status Digital 125 VDC Bl206 E-257 co2-2 152 P55C Charg Pump P55C Status Digital 125 VDC Bll05 E-257, Sh 2 C02-l 153 P56A Boric Acid Pwnp P56A Status Digital 120 VAC B287 E-203 co2-2 154 P56B Boric Acid P568 Status Digital 120 VAC Bl91 E-203 C02*3 155 P66A HPSI Pump P66A Status Digital 125 VDC Al207 E-249 C03-R 156 P668 HPST Pump P66B Status Digital 125 VDC Allll E-249 C03-L 157 P66C HPST Pump P66C Status Digital 125 VDC Al209 E-250 COl*R 158 P67A LPSI Pump P67A Status Digital 125 VDC Al206 E-247 C03-R 159 P678 LPSI Pump P67B Status Digital 125 VDC Allll E-248 C03*L 160 161 162 VlA Containment Cooling Fan Ol Status Digital 125 VDC Bl208 E-216 C08-R 163 V2A Contalrunent Cooling Fan #2 Status Digital 125 VDC 81209 E-216 C08-R 164 V3A Containment Cooling Fan 13 Statua Digital 125 VDC 81210 E-216 C08*R 165 V4A Contai11111ent Cooling Fan 14 Statua Digital 125 VDC 81108 E-217 COB*L 166 167 168 POS-0522A Hain Steam Iso. Valve Ctr. 12 Digital 125 VDC woos E-238SH.3 COl-2 169 POS-05228 Hain Steam Iso. Valve Cir. 12 Digital 125 VDC W006 E*238SH.3 COl-2 170 33/SUJ No. 1 Hain Stop Valve (SLU) Digital 125 VDC IGOl E*298SH.6 Cll DR. End 171 33/SU. No. l Turbine Stop Valve (SLL) Digital 125 VDC lGOl E*298SH.6 Cll DR. End 112 33/SRU No. 4:Hain Stop Valve (SRL) Digital 125 VDC IG03 E*298SH.6 Cl3 DR. End 173 33/SRL No. 2 Turbine Stop Valve (SRU) Digital 125 VDC IGOl E*298SH.6 Cll DR. End 174 POS-0701 FW to Heater E-68 Digital 125 VDC IGOl E*298SH.2 Cll DR. End 175 POS-0703 FW to Steam Gen. E-508 Digital 125 VDC IGOl E*298SH.2 Cll End 176 POS-0824 Service Water Valves Cir. l Digital 125 VDC 507 E*219SH.2 C08*L 177 POS-0847 Service Water Valves Cir. l Digital 125 VDC S07 E*219SH.2 C08-L 178 POS-OS61 Cont. Air Cooler VHX-1 Digital 125 VDC 81208 E-216 C08*R 179 POS-0862 Cont. Alr Cooler VHX-1

  • Digital 125 VDC Bl208 E-216 C08-R 180 POS-0864 Cont. AC VHX-2 Ser. Wtr. 0809 Digital 125 VDC 81209 E-216 C08-R 181 POS-0865 Cont. AC VHX-2 Ser. Wtr. 0809 Digital 125 VDC 81209 E-216 C08-R 182 POS-0867 Serv. Wtr. Disc. Recirc. Fan V4A Digital 125 VDC 81108 E-217 C08*L 183 POS-0869 Serv. Wtr. Dlsc. Recirc. Fan V4A Digital 125 VDC 81108 E-211 COB-L e 184 POS-0870 Cont. AC VHX-3 Ser. Wtr. 0810 Digital 125 VDC Bl210 E-216 C08-R 185 POS-0873 Cont. AC VHX-3 Ser. Wtr. 0811 Digital 125 VDC 81210 E-216 C08-lt 186 POS-2002 Letdn. Orifice Bypass Stp. Value Digital 125 VDC S20 E-236SH.l C02-3 187 POS-2003 Let Down Orifice Valves Digital 125 VDC Sl7 E-236 C02*3 188 POS-2004 Let Down Orifice Valves Digital 125 VDC 517 E-236 C02*3 189 POS-2005 Let Down Orifice Valves Digital 125 VDC Sl7 E-236 C02*3 190 H0-2087 Volume Control Tank Digital 120 VAC 8161 E-242 C02*3 191 192 SV-2153 Boric Acld Heat TRC Alm Clr Digital 125 VDC Sll E-234 co2-2 193 POS-2155A Prlm. Sys. Hakeup Stop Valve Digital 125 VDC Sll E-234 co2-2 194 H0-2169 Cone. Boric Acid Tank' Digital 120 VAC 8127 E-241 co2-2 195 H0-2170 Cone. Boric Acid Tank Digital 120 VAC Bl87 E-241 co2-2 196 POS-2191 PCP Controlled Pump IHeedoff JV Digital 125 WC SJO E-255 C02*3 197 POS-3031 SlRW Tank LVL Cntr Vlv Cir Ul Digital 125 VDC Sll E-246 COl-L 198 POS-3041 SI Tank T*82A Drain Digital 125 VDC 581 £*243SH.2 C03*L RP088l-0410A*NS04 INFORMATION COPY .**
    • CRITlCAL FUNCTION MONITOR INPUIS . .:: ... "' I tea Signal Tas No Device Sil!l!al Voltase Schematic Dws No Console Section 249 POS-1103 Cont. Sump Drain lso. Valve Digital 125 VDC S2l E-235 Cll-lL .,,, 2SO POS-1104 Cont. Sump Drain Iso. Valve Digital 125 VDC S22 E-235 Cll-l 251 POS-1358 Nitrogen lso. Valve Digital 125 VDC S2S E-235SH.3 cu-2 2S2 POS-1910 PRl Sys. Sampling Iso. Vlv. Digital l2S VDC S2l E-235 Cll-lL 253 POS-1911 PRI Sys. Sampling Iso. Vlv. Digital l2S VDC S22 E-235 Cll-3 254 POS-2009 PRI Coolant Letdn. lso. Vlv. Digital l2S VDC S23 E-23SSH.2 C02-3 2S5 POS-2014 Boronometer

& Failed Fuel Digital l2S VDC S30 E-255 C02-3 2S6 POS-2023 Purification Ion Exchange Digital 125 VDC SJO E-25S C02-3 257 POS-20S6 Vol Cont/Radwaste Sys. Vlv. Digital 125 VDC 530 E-25S C02-3 POS-2083 PRI Coolant PHP Coolant Bleed Digital 125 VDC S23 E-23SSH.2 C02-l 259 POS-2111 Charging Line Stop Vlv. Digital 125 VDC SSS E-2l6SH.2 C02-l 260 POS-2113 Charge Dist. Stop Valve Digital 12S VDC SSS E-236SH.2 C02-3 261 POS-2llS Charge Dist. Stop Valve Digital l2S VDC SSS E-236SH.2 C02-3 262 POS-2117 Aux. Spray Stop Valve Digital 12S VDC SSS E-2l6SH.2 C02-3 263 E/P-2122 lnrwems Pewaa. Letdn. Control Analog l-SVDC IP6lt E-7lSH.S C02-lt 264 SV-216S Boric Acid Heat TRC Alm Block Digital 125 VDC Sll E-2llt 002-2 26S POS-3001 CNKI Spray Valves Digital 12S VDC Sl9 E-237 COl-L 266 POS-3002 DNHT Spray Valves Digital l2S VDC Sl8 E-237 C03-R 267 POS-3015 SD Cool From PRI LP2 .300lt Digital 120 VAC 8167 E-242SH.3 C02-3 268 POS-3016 SD From PRl LP2 lOOlt Digital 120 VAC 8271 E-2lt2SH.3 C02-3 269 POS-3018 SI & SD Cool VAives Cir fl Digital l2S VDC S09 E-2ltS COl-L 270 POS-3029 SIRW TK Level Control Valve Digital 125 VDC Slit E-246 COl-ll 271 POS-3030 SIRW 1'K Level Control Valve Digital 125 VDC Sll E-246 C03-L 272 POS-3036 SI &:Shutdn.

Cool Vlv. Cir. 12 Digital l2S VDC SlO E-245 C03-ll 273 POS-3037 SI & Shutdn. Cool Vlv. Cir. 12 Digital 125 VDC SlO E-245 C03-ll 274 POS-30S5 Shutdn. Cool Heat Ex Iso. Vlv. Digital 125 VDC Sl7 E-236 C02-3 27S POS-3059 SI & Shutdn. Cool lso. Vlv. Cir. ll Digital 125 VDC S09 E-24S C03-L 276 POS-3070 SI & Shutdn. Cool Vlv. Ctr. fl Digital 125 VDC 509 E-2ltS C03-L 277 POS-3071 SI & Shutdn. Cool Vlv. Cir. 12 Digital 12S VDC SlO E-2ltS C03-ll 278 H0-3072 Charg. To llPSI Line lao. Vlv. Digital 120 VAC B217 E-242 C03-ll 279 POS-3212 SI Shutdn. Cool Vlv. Cir. 12 Digital 12S VDC 510 E-24SSH.2A C03-ll 280 POS-3213 SI Shutdn. Cool Vlv. Cir. 12 Digital 125 VDC SlO E-2ltSSH.2A C03-R 281 POS-3223 SI Shutdn. Cool Vlv. Cir. 11 Digital 12S VDC S09 E-2ltSSH.2 C03-L 282 POS-3224 SI Shutdn. Cool Vlv. Clr fl Digital l2S VDC 509 E-24SSH.2 C03-L 283 E/P--0306 Shutdn. Cool Flow Control Ana!og 1-S VllC IF2l E-7lSH.6 C33 284 RI-1806 Containment lsolotlon Monitor Analog 0-10 mV IR78 E-227SH.2 Cll-5 285 E/P-0701 SG E-SOA f\I Regulator Analog 1-5 VDC IF32 E-69 Cll-S 286 E/P-0703 SG E-SOB f\I Regulator . Analog 1-5 VDC IFll E-69 Cl2-5 287 E/P--0736 SG E-S08 Aux. f\I Control Analog 1-5 VDC 1M05 E-79 C33 288 E/P--0737 SC E-508 Aux. f\I Control Analog 1-5 VDC IHOlt E-79 C3J l89 E/P-10S7 Pressurizer Spray Analog 1-5 VDC SS6 E-2S3 co2-2 290 E/P-10S9 Pressurizer Spray Analog 1-S VDC S56 E-253 co2-2 291 Rl-1809 Off Gas Monitoring Analog 0-10 mV IR90 E-228SH.2 Cll-3 292 RI-1810 East Engr. Safeguard Hon. Analog 0-10 mV IR91 E-228SH.3 Cll-J 293 RI-1811 West Engr. Safeguard Hon. Analog 0-10 mV IR92 E-228SH.3 Cll-3 294 RI-1817 Off Gas Honl toring Analog 0-10 mV IR87 E-228SH.2 Cll-3 295 llI-2310 Hain Control Room Monitor Analog 0-10 mV IR70 E-227 Cll-S 296 Rl-2313 Spent Pool Pit Monitor Analog 0-10 mV IR7l E-227 Cll-5 297 RI-2316 Fuel Handling Area Hon. 1 Analog 0-10 mV IR74 1::-227SH.2 298 Rl-2317 Fuel Handling Area Hon. 2 Analog 0-10 mV IR93 E-227SH.2 Cll-5 RP0-683-0ltlOA-NSOlt INFORMATION COP'i .**

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  • CRITICAL FUNCTION MONITOR INPUIS .. : .* .. Item Signal \:. Tag No Device Descri2tion Signal Voltage Schematic Dvg No Console Section I: 299 RI-2Jl8 Stack Gas Monitoring Inst *. Analog 0*10 mV IR86 E-228 Cll-3 .I 300 E/P-3025 Shutdn. Cool Flow Control Analog 1*5 VDC IHlO E-79 C33 301 RI*2ll9 Stack Gas Monitoring Inst. Analog 0-10 mv IR86 E-228 Cll*3 302 Rl-5709 Waste Demineralizer Rad Hon. Analog 0*10 mV E-762SH.2 Cll-5 303 Rl-5711 Radwaste Addition Vent Hon. Analog 0*10 111V E*763SH.2 Cll*S 30lt 305 306 307 308 309 310 311 Jl2 TE-1815 Containment Building Dome Temp *. Analog l-5 VDC E-95SH.2 Cll*l 3ll 314 .. 315 316 317 318 319 P'I-lll9 WST Gas Delay TKl Analog l-5 BDC IPlOO E*66SH.6 CltO 320 PT-1120 WST Gas Delay TK2 Analog 1*5 VDC IPlOl E-66SH.6 C40 321 P'I-1121 WST Gas Delay TK3 Analog 1*5 VDC IP102 E*66SH.6 CltO 322 PT-1160 WST Delay TK4 Analog l-5 VDC 1Pll2 E*66SH.5 CltO-A 323 P'I-1161 WST Caa Delay TK5 Analog 1*5 VDC 1Pll3 E*66SH.5 CltO*A 324 PT-1162 WST.Gas Delay TK6 Analog 1*5 VDC IP134 E*66SH.S CltO*A 325 Kl Reactor Trip Breaker 3 Digital 125 VDC IC03 E*298SH 0 6 C*ll 326 Kit Reactor Trip Breaker 4 Digital 125 VDC IC04 E-298SH.8 C*ll 327 POS-0511 Bypass to Condenser 120 VAC IP62 E-75 C01*2 328 POS-0521 Hain Steam Iso. Valve Cir. *2 Digital 125 VDC WOOl E-238SH.2 COl-2 329 330 POS-0937 Comp. Cool & Shtdwn. HX Vlv. 2 Digital 125 VDC 561 E-239 C08*R Jll POS-o938 Comp. Cool & Shtdwn. llX Vlv. l Digital 125 VDC 515 £-239 C08*L 332 POS*lOll Receiver Tanks Recirc. Digital 125 WC J039 E-268 CltO 333 POS-1015 Receiver Tanks Recirc. Digital 125 VDC J039 E-268 CltO 334 POS-1017 Receiver Tanks Recirc. Digital 125 VDC J039 E-268 CltO 335 POS-1019 Receiver Tanks Recirc. Digital 125 VDC J039 E-268 CltO 336 H0-2140 Hake-up Control SCP Bypass Digital 120 VAC B227 E-241 C02*1 337 H0-2160 SlRW Io Charging Pumps Digital 120 VAC 82007 E-242 C02*3 338 POS-2165 Boric Acid heat TRL Alm Cir. Digital 120 VAC HOS E*205SH.3 C30-A 339 H0-3007 HPSI React Cool Loop lA 3002 Digital 120 VAC 8137 E*21t4 C03*L 340 H0-3008 LPSI React Cool Loop lA 3002 Digital 120 VAC 8141 E*21t4 C03-L 341 H0-3009 LPSI React Cool Loop lB 3002 Digital 120 VAC 8197 E-244 C03*L 342 H0-3012 LPI React Cool Loop 2A 3003 Digital 120 VAC 8247 E-244 C03*R 343 H0-3013 HPl React Cool Loop 28 3003 Digital 120 VAC 8151 E-244SH.4 C03-L 344 H0-3014 LPI Reset Cool Loop 28 3003 Digital 120 VAC 8251 E*21t4 C03*R 345 H0-3062 Redundant High Pressure lnj. Digital 120 VAC B24l E-244 C03*R 346 H0-3064 Redundant High Pressure lnj. Digital 120 VAC 8237 E-244 C03*R 347 H0-3066 Redundant High Pressure lnj. Digital 120 VAC 8257 E*21t4 C03-R 348 H0-3068 Redundant High Pressure lnj. Digital 120 VAC 8261 E-21t4 C03*R
  • INFORMATION COPY .**

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    • ' * .. i CRITICAL FUNCTION MONITOR INPUTS ' ., 't i Item Signal " Iag No Device Description

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Signal Voltage Scheme Schema t le Dwg No Console Section .. ..!!2-..... ii 349 POS-0155 Demineral Water Quench TK Vlv. Digital 125 VDC S23 E*235SH.2 C02-3 350 351 POS-0511 Bypass to Condenser Digital 120 VAC IP62 E-75 COl-2 352 POS-0910 Comp. CLG. Wtr. Inlet to Cont. Digital 125 VDC 527 E*235SH.4 cu-2 353 POS-0911 Comp. CLG. Wtr. Disch. from Cont. Digital 125 VDC S27 E-235SH.4 cu-u. 354 POS-0939 Shield Clg. Surge TK Valve Digital 125 VDC S25 E*235SH.3 Cll-2 355 POS-0940 Comp. Clg. Wtr. Disch Cont. CJR 1 Digital 125 VDC 528 E*235SH.4 Cll*ll 356 POS-1014 Receiver Tanks Intake Digital 125 VDC J040 E-268 C40 357 POS-1016 Receiver Tanks Intake Digital 125 VDC J040 E-268 C40 358 POS-1018 Receiver Ianka Intake Digital 125 VDC J040 E-268 C40 359 POS-1502 Cont. Bldg. Steam Discharge Digital 125 VDC S22 E-235 Cll-3 360 POS-1503 Cont. Steam Iso. Vlv. Digital 125 VDC 525 E-235511.3 cu-2 261 POS-1813 Cont. 6i Air RH Purge lso. Vlv. Digital 125 VDC J002 E-221 Cll*lR 362 POS-1814 Cont. 6i Air RH Purge lso. Vlv. Digital 125 VDC JOOl E-221 Cll*lL 363 E/P-2012 Intermd. Preas Letdn. Controller Analog . 1-5 VDC IP64 E*73SH.5 CU-4 364 tl>-2140 Hake-up Control Sys. Bypass Vlv. Digital 120 VAC B227 E-241 Cl2-l 365 POS-2153 Boric Acid Heat IRC Alm. Block Digital 120 VAC HAlll E*205SH.3 C30-A 366 tl>-3007 HPSI React Cool LP lA 3002 Digital 120 VAC Bl37 E-244 C03*L 367 H0-3008 LPSI React Cool LP lA 3002 Digital 120 VAC Bl41 E-244 C03-L 368 H0-3009 HPSI React Cool LP 18 3002 Digital 120 VAC 8197 E-244 C03*L 369 H0-3010 LPSI React Coot' LP 18 3002 Digital 120 VAC Bl47 E-244 C03-L 370 tl>-3011 HPI React Cool LP 2A 3003 Digital 120 VAC Bl.57 E*244SH.4 C03*L 371 H0-3012 LPI React Cool LP 2A 3003 Digital 120 VAC B247 E-244: C03*R 372 tl>-3013 HPI React Cool LP 28 3003 Digital 120 VAC 8151 E-244SH.4 C03*L 373 H0-3014 LPI React Cool LP 28 3003 Digital 120 VAC 8251 E-244 C03-R 374 tl>-3062 Redundant High Pres. lnj. Digital 120 VAC 8241 E-244 C03-R 375 H0-3064 Redundant High Pres. Inj. Digital 120 VAC 8237 E-244 COl*R 376 H0-3066 Redundant High Pres. Inj. Digital 120 VAC 8257 E-244 C03 9 R 377 H0-3068 Redundant High Pres. lnj. Digital 120 VAC 8261 E-244 C03-R 378 POS-1501 Cont. Bldg. Ste8Jll Discharge Digital 125 VDC S21 E-235 C03-U. 379 H0-3010 LPSI React Cool Loop lB 3002 Digital 120 VAC 8147 E-244 C03-L 380 tl>-3011 HPI React Cool Loop 2A 3003 Digital 120 VAC 8157 E*244SH.4 C03-L 381 Al*2401L CNHI Hydrogen Monitor -High Digital 125 VDC K02 9-E-928SH.10 CUA -382 AI-2401R CNHI Hydrogen Monitor -High Digital 125 VDC K02 9-E-928SH.10 CUA 383 RE*2321H CNHI Ganns Radiation Monitor -Hl"gh Digital 125 VDC K02 9-E-928SH.9 CllA 384 RE-2321A CNHI Galllll8 Radiation Monitor -Alert Digital 125 VDC K02 9-E-928SH.9 CUA 385 RE*2322H CNHT Gamma Radlaiton Monitor -High Digital 125 VDC K02 9-E-928SH.9 CUA 386 RE*2322A CNHT G8111118 Radiation Monitor -Alert Digital 125 VDC K02 9-E-928SH.9 CllA 387 RE*2323H Hain Steam Radiation Relief Monitor -HigJI Digital 125 VDC K02 9*E-928SH.ll CllA 388 RE*2323A Halo Steam Radiation Relief Monitor -Alert Digital 125 VDC K02 9-E-928SH.ll CllA 389 RE-2324H Hain Steam Radiation Relief Monitor -High Digital 125 VDC K02 9-E-928SH.ll CUA 390 RE-2324A Hain Steam Radiation Relief Monitor -Alert Digital 125 VDC K02 9-E-928SH.ll CllA 391 RE-2325/26/27-11 Stack Effiuent Radiation Monitor -High Digital 125 VDC K02 9-E-928SH.12 CllA 392 RE-2325/26/27-A Stack Effluent Radiation Monitor -Alert Digital 125 VDC K02 9-E-928SH.12 CllA REFERENCE DWG: CE Drawing CFH Input List D-5 78-422-033 SH.l Thru Sll.7 Hl-W .. RP0883-0410A*NS04 INFORMATION COP).