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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML20197J3891997-12-18018 December 1997 25th Year Physical Surveillance of Palisades Npp ML20217C2571997-12-16016 December 1997 Review of Neutron Fluence Data for Palisades Reactor Pressure Vessel ML18067A6351997-07-0909 July 1997 Excerpt from Ampacity Evaluation for Open Air Cable Trays W/Percent Fill Greater than 30% of Useable Cross Sectional Area. ML18067A6381997-07-0909 July 1997 Excerpt from Ampacity Evaluation for Continuously Energized Power Cables Routed Through Fire Stops, Revision 1 ML18067A6371997-07-0808 July 1997 Excerpt from Ampacity Evaluation for Duct Runs Containing Continuously Energized Power Cables, Revision 1 ML18067A6361997-06-26026 June 1997 Excerpt from Ampacity Evaluation for Continuously Energized Power Cables in Open Air Conduits, Revision 1 ML18066A8581997-01-31031 January 1997 Rev 2 to C-PAL-96-1063-01, Operability Assessment for Transient Conditions at Palisades Nuclear Plant in Response to GL 96-06. ML18065B0471996-07-12012 July 1996 TR on Use of Mcbend Code for Calculation of Neutron Fluences in PVs of Lwrs. ML18065A7571996-05-22022 May 1996 Rev 1 to IPEEE Rept, Per GL 88-20 ML20108C1671996-04-0101 April 1996 Nonproprietary Version of Fluence Calculations for Palisades Plant ML18065A5971996-03-23023 March 1996 Evaluation of Effects of Fire on West Wall of Turbine Lube Oil Room Adjacent to Pipe Tunnel Between TB & FW Purity Bldg. ML18065A6011996-03-22022 March 1996 Evaluation of Effects of Fire on West Wall of CCW Pump Room (Fire Area 16). ML20100D7491996-01-18018 January 1996 Rev 0 to Evaluation of Effects of Fire on West Wall of TB Lube Oil Room Adjacent to Pipe Tunnel Between TB & FW Purity Bldg ML18065A4481995-12-14014 December 1995 Radiological Consequences for Palisades Max Hypothetical Accident & Loss of Coolant Accident. ML18064A8321995-06-30030 June 1995 IPE of External Events (Ipeee). ML20085H2801995-05-23023 May 1995 Security Investigation Rept ML18064A7801995-05-19019 May 1995 Rept of SQUG Assessment at Palisades Nuclear Plant for Resolution of USI A-46. ML20078P7021995-01-27027 January 1995 Investigative Rept ML18064A4121994-08-22022 August 1994 Pressure-Temp Curves & LTOP Setpoint Curve for Max Reactor Vessel Fluence of 2.192 X 10^19 Neutrons/cm^2. ML20070J8001994-07-15015 July 1994 Final Rept Containment Sump Check Valves Weld Overlay Repair Implementation Evaluation Palisades Nuclear Plant ML18059B0041994-04-0505 April 1994 Rev 1 to EDG Fuel Supply Sys Storage Tank Tornado Protection Overview of EDG Fuel Supply Sys, Incorporating CARB Comments of 940318 & 24 ML20064E5301994-03-0606 March 1994 Evaluation of Effectiveness of Code Case N-504-1 Repair for Proposed Root Causes for Containment Sump Suction Check Valves ML20064E4451994-03-0505 March 1994 Check Valve Leak Root Cause,Engineering Analysis & Repair/Replacement Options ML18059A5161993-10-31031 October 1993 Nonproprietary Exam...Sections of Pressurizer PORV Line Safe-End Failure from Palisades Nuclear Generating Station. ML20058P1361993-10-31031 October 1993 Crack Propagation Analysis for Circumferential Cracks in Alloy 600 Nozzle Safe-Ends ML18059A4821993-10-25025 October 1993 Evaluation of Potential Interference Between TE-0102 Nozzle & Thermowell. ML18059A4831993-10-25025 October 1993 Structural Evaluation for Machined Thermawell for TE-0101. ML20059D8811993-10-23023 October 1993 Justification of Weld Mods to Pressurizer Temperature Nozzles for TE-0101 & TE-0102 ML18059A4811993-10-22022 October 1993 Acceptability of Partial Severing of TE-0101 Nozzle. ML18059A4801993-10-19019 October 1993 Structural Analysis of Temperature Nozzle Weld Mods for Consumers Power Palisades Pressurizer. ML18059A4791993-10-15015 October 1993 Half Bead Welding for Mods to TE-0101 & TE-0102. ML18059A4221993-10-0707 October 1993 Pressurizer Safe End Crack Engineering Analysis & Root Cause Evaluation. ML18059A3751993-08-31031 August 1993 Rev 1 to Palisades Cycle 11:Disposition & Analysis of SRP Chapter 15 Events. ML18059B0191993-07-31031 July 1993 Detailed Site Study,Berrien County,Mi, Final Rept ML18064A4271993-06-30030 June 1993 Wind Tunnel Predictions of Control Room Intake Concentrations from Three Sources of Radioactive Materials at Palisades Nuclear Power Plant, (CPP-Project 93-0907) ML18058B8661993-05-13013 May 1993 Resolution of Anchor Bolt Design Issues. ML18058B3911992-12-21021 December 1992 Cycle 11:Disposition & Analysis of Standard Review Plan Chapter 15 Events. ML18058B4281992-11-30030 November 1992 Vols 1,2 & 3 of Palisades Nuclear Plant Ipe. ML18058A5391992-06-16016 June 1992 Twentieth Yr Physical Surveillance of Palisades Nuclear Plant. ML20086P8551991-12-0909 December 1991 Criticality Safety Analysis for Palisades Spent Fuel Storage Pool NUS Racks ML20086P8571991-12-0909 December 1991 Criticality Safety Analysis for Palisades New Fuel Storage Array ML18057B3521991-10-31031 October 1991 Large Break Loca/Eccs Analysis W/Increased Radial Peaking & Reduced ECCS Flow. ML18057A8591991-03-31031 March 1991 Benchmarking & Validation of In-House DOT Calculation Methodology. ML20081K7741990-08-14014 August 1990 Incore Detector Algorithm (Pidal) Analysis of Quadrant Power Tilt Uncertainties ML18057A2611990-06-11011 June 1990 Simulator Certification Submittal. 1999-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
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Text
ATTACHMENT A Consumers Power Company Palisades Plant Docket 50-255 SYSTEM EVALUATION DETERMINING MAXIMUM DIFFERENTIAL PRESSURE FOR HIGH PRESSURE SAFETY INJECTION SYSTEM MOTOR-OPERATED VALVES AND AUXILIARY FEEDWATER SYSTEM MOTOR-OPERATED VALVES
- January 15, 1988 88012bAOOOO~
PDR
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Pages 11 MI0687-296C-MA05
Attachment A - pg 1 Table of Contents Title Page No.
High pressure Safety Injection System
- Palisades Design Basis for Operation of HPSIS MOVs 2 Palisades HPSIS Schematic 3 Palisades HPSIS MOV Data Sunnnary 4 Auxiliary Feedwater System Palisades Design Basis for Operation of AFWS MOVs 8 Palisades AFWS Schematic 9 Palisades AFWS MOV Data Sunnnary 10 MI0687-296C-MA05
Attachment A - pg 2 PALISADES DESIGN BASIS FOR OPERATION OF HPSIS MOVs Postulated Postulated Valve Valve Upstream Downstream Function Tag No. Condition Condition Notes Auto Open on M0-3007 High: HPSI pump Low: Atmos press HPSI isolation SIAS M0-3009 shutoff head valves - normally M0-3011 closed M0-3013 M0-3062 M0-3064 M0-3066 Mo-3068 Manually close M0-3007 High: HPSI pump Low: Atmos press following shutdown M0-3009 shutoff head M0-3011 M0-3013 M0-3062 M0-3064 M0-3066 M0-3068 Open for Hot Leg M0-3080 High: HPSI pump Low: Atmos press HPSI flow to injection M:>-3081 shutoff head Hot Leg Manually close from M0-3080 High: HPSI pump Low: Atmos press Control Room M0-3081 shutoff head Close for Hot Leg M0-3082 High: HPSI pump Low: Atmos press HPSI bypass valves injection M:>-3083 shutoff head Manually open from M0-3082 High: HPSI pump Low: Atmos press Control Room M0-3083 shutoff head Manually open from M0-3041 Low: SI tank High: Max normal SI tank isolation Control Room M:>-3045 pressure PCS pressure valves normally M0-3049 locked open see M0-3052 Tech Spec 3.3.1.i Manually closed from M0-3041 Low: SI tank High: Max normal M0-3045 pressure PCS pressure M0-3049 M0-3052
Pell isades HPSIS Schettatic T-82A M0-3041 H0-3081
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- HIGH PRESSURE SAFETY INJECTION Data Sunnnary Switch Settings Prior to Adjust-
. pg 4 Design ments as a Result Settings in Response Valve Valve Basis l'lP* Test fJ.p of Bulletin to Bulletin Valve Operator Function Open/Close Open/Close Open/Close Open/Close Component ID Manufacturer, Manufacturer, Model, Type, Model Motor RPM, Size, Rating Output Speed (RPM)
M0-3007 Limitorque HPSI 1245 psi/ NO TEST 1.0*/l.O 2.5*/<2.5 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 15004fo/N/A 650°F/N/A M0-3009 Limitorque HPSI 1245 psi/ NO TEST N/A*/1.0 2.25*/<2.25 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe
- 1700 RPM W8-376-13MS N/A 2"
15004fo/N/A 650°F/N/A M0-3011 Limitorque HPSI 1245 psi/ NO TEST 1. 75*/l.25 <2.5/<2.5 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 2"
1500/fo/N/A 650°F/N/A M0-3013
- Limitorque HPSI 1245 psi/ NO TEST 3.5*/3.0 2.25*/<2,5 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 2"
1500/fo/N/A 650°F/N/A
MI0687-296E-MA05
Attach - pg 5 HIGH PRESSURE SAFETY INJECTION Data Sunnnary Switch Settings Prior to Adjust- Final Switch Design ments as a Result Settings in Response Valve Valve Basis f!.p Test f!.p of Bulletin to Bulletin Valve QI!erator Function QI!en/Close Open/Close Open/Close Open/Close M0-3062 Limitorque HPSI 1245 psi/ 940/1240 2.0*/1.5 . 2. 75*/2. 75 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 2"
1500/t/N/A 300°F/N/A M0-3064 Limitorque HPSI 1245 psi/ 915/1240 1.5*/l.5 >2.75*/>2.75 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 2"
1500#/N/A 300°F/N/A M0-3066 Limitorque HPSI 1245 psi/ 880/1240 1.0*/2.5 1.5*/1.0 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 2"
1500/t/N/A 300°F/N/A M0-3068 Limitorque HPSI 1245 psi/ 950/1240 2.0*/2.0 1. 75*/1. 75 Velan Valve SMB-00-15 Isolation 1245 psi Corp Globe 1700 RPM W8-376-13MS N/A 2"
1500ft/N/A 300°F /N/A
1 Attachm pg 6 HIGH PRESSURE SAFETY INJECTION Data Summary Switch Settings Prior to Adjust- Final Switch Design ments as a Result Settings in Response Valve Valve Basis ~p Test & of Builetin to Bulletin Valve QI!erator Function QI!en/Close Ol!en/Close QI!en/Close Ql!en/Close M0-3080 Limitorque HPSI Train 1238 psi/ 945/1050 2.0/2.0 1. 75/1. 75 Anchor Darling SMB-0-25 Isolation 1238 psi Gate 1800 RPM DG No 4315-3-1,1 N/A 6"
2500#/2485 psig 650°F/682°F M0-3081 Limitorque HPSI Train 1239 psi/ NO TEST 2.0/2.0 2.0/2.0 Anchor Darling SMB-0-25 Isolation 1239 psi Gate 1800 RPM DG*No 4350-3 N/A 6"
25001~/2485 psig 650°F/682°F M0-3082 Limitorque HPSI Hot Leg 1235 psi/ 640/FAILED AT 2.0/2.0 1. 75/1.5 Ke rot est Isolation 1235 psi 1060 PSI ON Globe 1800 RPM TORQUE D-PAL-D- N/A 22546M0-1 MODIFIED TO -MODIFIED-2" SMB-00-15 ACTUATOR 2500ft/2485 psig 650°F/682°F M0-3083 Limitorque HPSI Hot Leg 1235 psi/ NO TEST >2.0/>2.0 2.25/2.25 Kerotest Isolation 1235 psi Globe 1800 RPM -MODIFIED-D*PAL-D* N/A ACTUATOR 225L16MO*l MODIFIED TO 2" SMB-00-15 25001~/2485 psig 650°F/682°F MI0687-296E-MA05
At tac - pg 7 HIGH PRESSURE SAFETY INJECTION (SAFETY INJECTION TANK DISCHARGE)
Data Summary Switch Settings Prior to Adjust- Final Switch Design *ments as a Result Settings in Response Valve Valve Basis /J.P Test /J.P of Bulletin to Bulletin Valve Operator Function Open/Close Open/Close Open/Close Open/Close M0-3041 Limitorque SI bottle 1885 psi/ NO TEST N/A*/1.0 1, 75*/1.5 Walworth SMB-2-60 Isolation 1885 psi Gate 1800 RPM Dg No A-12348-M-lD 12 11 1500ft/2485 psig 650°F/N/A M0-3045 Limitorque SI bottle 1885 psi/ NO TEST *l.O*/l.O 2,0*/1.5 Walworth SMB-2-60 Isolation 1885 psi Gate 1800 RPM Dg No A-12348-M-lD 1211 1500ffo/2485 psig 650°F/N/A M0-3049 Limitorque SI bottle 1885 psi/ NO TEST N/A*/l.O 2.o*/L2s Walworth SMB-2-60 Isolation 1885 psi Gate 1800 RPM Dg No A-12348-M-lD 1211 1500#/2485 psig 650°F/N/A M0-3052 Limitorque* SI bottle 1885 psi/ NO TEST N/A*/2.0 2.0*/1. 75 Walworth SMB-2-60 Isolation 1885 psi Gate 1800 RPM Dg No A-12348-M-lD 1211 lSOOffa/2485 psig 650°F/N/A
Attachm~- pg 8 PALISADES DESIGN BASIS FOR OPERATION OF AFWS MOVs Postulated Postulated Valve Upstream Downstream Valve Function Tag No Condition Condition Notes Auto Open on M0-0743 High: AFWP shutoff Low: Atmos press AFWP downstream AFAS M0-0748 head pressure isolation valves M0-0753 including service M0-0754 water pump shutoff Normally open M0-0755 head or fire pump M0-0759 shutoff head or head M0-0760 due to maximum M0-0798 CTS level Close for FOGG M0-0743 High: AFWP shutoff Low: Atmos press M0-0748 head pressure M0-0753 water pump shutoff M0-0754 head or fire pump M0-0755 shutoff head or head M0-0759 due to maximum CST M0-0760 level M0-0798 NOTE: CTS STANDS FOR CONDENSATE STORAGE TANK LEVEL MI0687-296E-MA05
Kl 0743 Kl 0798 Fire P-88 SG Protection CST System ..--~---__.... E-50-8 f<<) 0753 ti) 0760 P-8A ti) 0748 MO 0755 SG E-50-A P-8C
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System PAl.l~l\IJ[S AUXILIARY HEOWAHR SYSTEM SCllEMATIC
AUXILIARY FEEDWATER SYSTEM Data Sununary Switch Settings Prior to Adjust-Attachm*-
Final Switch pg 10 Design ments as a Result Settings in Response Valve Valve Basis l!.P Test & of Bulletin to Bulletin Valve QEerator Function Open/Close Open/Close Open/Close QEen/Close M0-0743 Limitorque AFWP, P-8A 1714 psi/ 1524 psid/ 2.5*/2.5 1. 75*/2.0 Anchor/Darling SMB-00-10 and P-8B, 1714 psi 1524 psid Gate 1800 RPM discharge to 1-4F-5A N/A SG 411 E-50..;B 900#/1690 psig 100°F/120°F M0-0748 Limitorque AFWP, p..;ac 1354 psi/ 1239 psid/ 2.0*/2.0 2.0*/3.0 Anchor/Darling SMB-00-10 discharge 1354 psi 1239. psid Gate 1800 RPM to SG E-50B 1-4F-5A N/A 4"
600#/1337 psig 100°F/120°F M0-0753 Limitorque AFWP, P-8A 1714 psi/ 1524 psid/ 2.5*/2.5 2.25*/1. 75 Anchor/Darling SMB-00-10 and P-8B, 1714 psi 1524 psid Gate 1800 RPM discharge to 1-4F-5A N/A SG 4" E-50-A 900#1690 psig 100°F/120°F M0-0754 Limitorque AFWP, P-8C 1354 psi/ 1249 psid/ 2.125*/2.0 <3.0*/<3.0 Anchor/Darling SMB-00-10 discharge 1354 psi 1249 psid Gate 1800 RPM to 1-4F-5A N/A SG 4" E-50-B 600#/1337*psig 100°F/120°F
- AUXILIARY FEEDWATER SYSTEM Data Suunnary Switch Settings Attachment A - pg 11 Prior to Adjust- Final Switch Design ments as a Result Settings in Response Valve Valve Basis /J.P Test /J.P of Bulletin to Bulletin Valve Operator Function Open/Close Open/Close Open/Close Open/Close M0-0755 Limitorque AFWP, P-8C 1351 psi/ 1249 psid/ 2.5*/2.5 3.0*/3.0 Anchor/Darling SMB-00-10 discharge 1351 psi 1249 psid Gate 1800 RPM to 1-4F-5A N/A SG
- 411 E-50-B 6004.t/1337 psig 100°F/120°F M0-0759 Limitorque AFWP, P-BC 1351 psi/ 1244 psid/ 2.5*/2.5 2.75*/2.75 Anchor/Darling SMB-00-10 discharge 1351 psi 1244 psid Gate 1800 RPM to 1-4F-5A N/A SG 411 E-50-A 600#1337 psig 100°F/120°F M0-0760 Limitorque AFWP, P-BA 1711 psi/ 1526 psid/ 2.5*/2.5 2.75*/2.75
- Anchor /Darling SMB-00-10 and P-BB, 1711 psi 1526 psid Gate 1800 RPM discharge to 1-4F-5A N/A SG 411 E-50-A 9004.t/1690 psig 100°F/120°F M0-0798 Limitorque AFWP, P-BA 1711 psi/ 1527 psid/ 2.5*/2.5 2.0*/2.25 Anchor/Darling SMB-00-10 and P-BB, 1711 psi 1527 psid Gate 1800 RPM discharge to 1-4F-5A N/A SG 411 E-50-B 90041/1690 psig 100°F/120°F