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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000255/LER-1986-010, Withdrawn LER 86-010-00 Re Missing Pipe Hangers on Integrated Leak Rate Test Instrument Line.Results of Analysis Using ASME Code Case N-411 Revealed That Line,W/O Pipe Support,Statically Qualified1986-04-17017 April 1986 Withdrawn LER 86-010-00 Re Missing Pipe Hangers on Integrated Leak Rate Test Instrument Line.Results of Analysis Using ASME Code Case N-411 Revealed That Line,W/O Pipe Support,Statically Qualified 05000255/LER-1982-015, Updated LER 82-015/03X-1:on 820519,snubber 17 (Main Steam Line Upstream of Atmospheric Dump Valve CV-0780) Contained Insufficient Oil.Caused by Deteriorated O-rings.Snubber Replaced & Will Be Rebuilt on 5-yr Cycle1982-07-14014 July 1982 Updated LER 82-015/03X-1:on 820519,snubber 17 (Main Steam Line Upstream of Atmospheric Dump Valve CV-0780) Contained Insufficient Oil.Caused by Deteriorated O-rings.Snubber Replaced & Will Be Rebuilt on 5-yr Cycle 05000255/LER-1981-037, Updated LER 81-037/03X-1:on 810908,during Maint on Check Valves CK-3103,CK-3118,CK-3133 & CK-3148,disc Nut,Washer & Pin Found Missing.Caused by High Fluid Velocity & Turbulence Creating Accelerated Wear1982-06-0404 June 1982 Updated LER 81-037/03X-1:on 810908,during Maint on Check Valves CK-3103,CK-3118,CK-3133 & CK-3148,disc Nut,Washer & Pin Found Missing.Caused by High Fluid Velocity & Turbulence Creating Accelerated Wear 05000255/LER-1982-012, Updated LER 82-012/01X-1:on 820423,primary to Secondary Leakage in Steam Generator Tubes Increased to Approx 0.32 Gpm.Caused by Two through-wall Defects.Tubes W/Defects Plugged1982-06-0404 June 1982 Updated LER 82-012/01X-1:on 820423,primary to Secondary Leakage in Steam Generator Tubes Increased to Approx 0.32 Gpm.Caused by Two through-wall Defects.Tubes W/Defects Plugged ML20147A8311978-09-11011 September 1978 /01T on 780828:During Cooldown of the Reactor,The Containment Bldg Was Ventilated Thru the Purge Supply & Exhaust Valves.Improper Tagging Caused Valves to Be Open & Containment Integrity Not Met. (Encl to 7809190170) ML20084U2431977-04-0404 April 1977 LER ER-77-011:on 770130,secondary Water Chemistry Limits for Sodium Concentration,Ph & Conductivity Exceeded Tech Spec 3.18 Due to Leak in Main Condenser West Half.Cause Suspected to Be Tube Vibration.Tubes Plugged ML20084U3271977-03-21021 March 1977 LER ER-77-002:on 770106,secondary Water Chemistry Spec Exceeded Tech Spec 3.18 Limits Due to Condenser Leak.Leakage Caused Power Reduction & Plugging of Three Tubes in East Water Box.Leakage Cause Not Determined ML20084U3101977-03-21021 March 1977 Updated LER ER-77-002:on 770106,secondary Water Chemistry Spec Exceeded Tech Spec 3.18 Limits.Caused by Condenser Leakage Which Caused Power Reduction & Plugging of Tubes in East Water Box.Leakage Cause Undetermined ML20084U2291977-02-23023 February 1977 LER ER-77-015:on 760623,discharge Water Temp Rose Above 5 F Limit.Caused by Cooling Water Sys Design.Npdes Limits Not Exceeded ML20084U2281977-02-23023 February 1977 LER ER-77-016:on 770210,two Events Caused Discharge Water Temp to Rise Above 5 F Limit.Cause Related to Starting or Stopping of Cooling Tower Pump P-39A During Power Escalation.Npdes Limits Not Exceeded ML20084U2301977-02-22022 February 1977 LER ER-77-014:on 770107,discharge Water Temp Exceeded 5 F Limit Twice.Cause Related to Stopping or Starting of Cooling Pump P-39B During Startup ML20084U2421977-02-22022 February 1977 LER ER-77-012:on 770205,tank Heater H68A for Boric Acid Tank T-53A Found Leaking During Routine Insp of Chemical & Vol Control Sys.Cause Not Stated.Heater Replaced ML20084U2441977-02-14014 February 1977 LER ER-77-010:on 770131,ice Loading on 345-kV Bus Tie & Station Power Lines Greater than Expected Due to Cooling Tower Plume Passing Lines.Caused by Environ Conditions & Cooling Tower Operation ML20084U2451977-02-0909 February 1977 LER ER-77-009:on 770130,discharge Water Temp Rose Above 5 F Limit During Power Escalation.Caused by Either Starting or Stopping of Cooling Tower Pump P-39A During Power Escalation.Npdes Limits Not Exceeded ML20084U2911977-02-0202 February 1977 LER ER-77-006:on 770117,control Rod 21 Found 9.1 Inches Above Lowest Rod in Bank.Caused by Trainee Pulling Rods While in Manual Individual Rather than Sequential,During Critical Approach for Trip Recovery ML20084U2531977-02-0202 February 1977 LER ER-77-008:on 770117,control Rod 38 Driven 13.6 Inches Below Group When Operator Manually Ran Control Rods in Order to Avert Reactor Trip Following Feedwater Pump Trip.Caused by Operator Failure to Switch Mode Selector ML20084U2841977-01-31031 January 1977 LER ER-77-007:on 770117,discharge Water Temp Rose Above 5 F Limit Following Plant Trip & Subsequent Startup.Caused by Either Effects of Plant Trip or by Placing Cooling Towers in Svc.Npdes Limits Not Exceeded ML20084U2991977-01-17017 January 1977 LER ER-77-004:on 770111 & 12,discharge Water Temp Rose Above 5 F Limit Following Plant Trip & Subsequent Startup.Caused by Either Effects of Plant Trip or by Placing Cooling Towers in Svc.Npdes Limits Not Exceeded ML20084U3301977-01-17017 January 1977 LER ER-77-001:on 770103,control Rod Drive Mechanism 4 Declared Inoperable Due to Seal Leakage Problems.Caused by Beginning Seal Failure.Drive Seal to Be Replaced ML20085E4231977-01-11011 January 1977 LER ER-76-046:on 761225,drain Valve Not Closed Upon Neutralizer Tank Drainage Completion During Shift Change. Caused by Poor Communications Between Operating Shifts & by Operator Error.Procedures Revised ML20085E4371977-01-0404 January 1977 LER ER-76-044:on 761206,steam Generator Low Level Trip Setpoint (Channel D) Found Below Tech Spec Limit.Caused by Setpont Drift & Indistinct Administrative Limit Vs Tech Spec Limit ML20085E4401976-12-30030 December 1976 LER ER-76-043:on 761202,small Leak Observed in Charging Pump Suction Header Near B Charging Pump.Caused by Type of Tee (Field Fabricated Type) & by Pipe Vibration at Tee Location ML20085E4281976-12-21021 December 1976 LER ER-76-045:on 761209,DBA Sequencer 34-1 Failed to Operate During Quarterly Safeguards Test Rerun.Caused by Failure of Sequencer Clutch to Reset Due to Insufficient Clutch Disk Gap to Set Screw Slippage ML20085E4551976-12-17017 December 1976 LER ER-76-038:on 761117,discharge Water Rose Above Temp Limits During Startup.Events Related to Placing Cooling Towers in Svc.Npdes Limit Not Exceeded ML20085E4431976-12-17017 December 1976 LER ER-76-042:on 761201 & 02,two Events Resulted in Discharge Water Above Temp Limit.Cause Related to Effects of Plant Trip or to Placing Cooling Towers in Svc for Plant Startup.Npdes Limits Not Exceeded ML20085E4531976-12-17017 December 1976 LER ER-76-040:on 761130,discharge Water Rose Above Temp Limit During Plant Shutdown.Event Related to Cooling Tower Removal from Svc.Npdes Limit Not Exceeded ML20085E4541976-12-17017 December 1976 LER ER-76-039:on 761125,discharge Water Rose Above Tech Spec Limits During Plant Startup.Event Related to Placing Cooling Towers in Svc ML20085E4561976-12-13013 December 1976 LER ER-76-037:on 761115,trip Setpoint Found Out of Spec While Doing Check Sheet on Neutron Monitor Channel C.Caused by Instrument Setpoint Drift ML20085E4491976-12-10010 December 1976 LER ER-76-041:on 761130,total Chlorine Discharge Into Lake Exceeded Tech Spec Limits During Chlorination of B Cooling Tower.Caused by Excessive Flow from Weir Discharge to Mixing Basin ML20085E4591976-11-19019 November 1976 LER ER-76-036:on 761105,air Leakage Noted During Escape & Personnel Air Lock Door Testing.Caused by Personnel Failure to Follow Procedures.Remedial Action Taken ML20085E4621976-11-11011 November 1976 LER ER-76-034:on 761020,cooling Tower Pumps Tripped Due to Plant Operational Problems.Caused Water Box Vacuum Reestablishment & Pump Starting,Raising Discharge Temp Above Limit.Npdes Limit Not Exceeded ML20085E4631976-11-0303 November 1976 LER ER-76-033:on 761020,dc Bus 2 Voltage Dropped to 60 Volts,Dropping Associated Ac Preferred Bus Voltage to 90 Volts.Caused by Improper Coordination of Battery Charger Current Limiter & Charger Output Breaker ML20085E5141976-09-22022 September 1976 LER ER-76-017:on 760520,one of 24 Reactor Protective Matrix Relays Failed to Operate.Apparently Caused by Mercury Wetted Contacts.Replacement Relays Tested ML20085E4641976-09-21021 September 1976 LER ER-76-031:on 760913,control Rod Drive Mechanism (CRDM) 13 Considered Inoperable Due to Seal Leakage Problems.Caused by Beginning Seal Failure on CRDM 13 ML20085E4651976-09-21021 September 1976 LER ER-76-030:on 760826,rod Withdrawal Unsuccessful After Rod Drop Test.Cause of Failure Probably Associated W/Motor/ Brake Assembly Replaced.Brake Insp Procedures Developed ML20085E4661976-09-21021 September 1976 LER ER-76-029:on 760827,necessary Control Rod Motion to Maintain Reactor Criticality Resulted in Misalignment of Rod 37.Cause Associated W/Motor/Brake Assembly.Motor/Brake Assembly Replaced.Insp Procedures Developed ML20085E4671976-09-0909 September 1976 LER ER-76-028:on 760823,Group 3 Rods Moved While Group 4 Rods Inserted by Manual Sequential Mode.Event Classified as Reportable on 760826.Cause Not Determined ML20085E4851976-09-0909 September 1976 LER ER-76-025:on 760813,during Semiannual Operational Check of Hydrogen Recombiners,Unit M69B Loaded to 43 Kw,Resulting in Heater Temp Below Tech Spec Limits.Caused by Grounded Heater Phase ML20085E4681976-09-0707 September 1976 LER ER-76-027:on 760823,as-found Leakage Rate Found Unacceptably High During Quarterly Testing of Penetration 1 (Purge Air Supply CV1808).Caused by Recent Mod to Valve Stem multi-ring Packing Grease Fitting ML20085E4761976-08-31031 August 1976 LER ER-76-026:on 760817,cooling Water Basin Level Increased More Rapidly than Expected During Determination of Effect of Dilution Water Flow on Plant Output.Test Procedure Revised to Accommodate Level Increase ML20085E4871976-08-13013 August 1976 LER ER-76-024:on 760730,power Dependent Insertion Limits Exceeded Three Times During Power Reduction to Remove Leaking Feed Pump from Svc.Caused by Rapid Power Reduction ML20085E5011976-07-22022 July 1976 LER ER-76-021:on 760627,containment Purge Supply Valve CV-1808 Failed to Open During Monthly Test.Valve Tagged Closed to Meet Containment Integrity Requirements.Cause Not Known.Failure Will Be Investigated ML20085E5431976-05-25025 May 1976 LER ER-76-014:on 760510,diesel Generator Made Inoperable for Preventive Maint W/One of Two HPSI Pumps Also Inoperable. Caused by Operations Staff Oversight.Possible Procedure Changes Reviewed ML20085E5321976-05-21021 May 1976 LER ER-76-013:on 760507 & 09,four Events Resulted in Discharging Water Above 5 F Limit During Startup/Shutdown of Cooling Towers.Cause Related to Cooling Tower Removal from Svc to Repair Leaking Condenser Tube ML20085E5741976-05-20020 May 1976 LER ER-76-010:on 760421,charging Pump P55-A Failed to Perform Properly During Loss of Offsite Power/Sis Test. Caused by Plug Oil Filter.Filter Changed ML20085E5491976-05-14014 May 1976 LER ER-76-012:on 760430,equipment Review Revealed Valves CV-2113 & CV-2115 Possibly Did Not Meet Original Design Specs Re Allowable Stresses at Valve body-to-bonnet Flange. Caused by Use of Different Calculations ML20085E5761976-05-14014 May 1976 LER ER-76-009:on 760419,left Channel Relay SP7 Showed Intermittent Operation During Containment Spray Sys Testing. Causing by Dirty Contacts.Relay Contacts Cleaned ML20085E5611976-05-0606 May 1976 LER ER-76-011:on 760328,test on Penetration 46 Indicated Leakage Above Acceptable Limits.Caused by Worn Valve Seats ML20085E5781976-04-22022 April 1976 LER ER-76-008:on 760408,4 Psig Released from T-101A Instead of T-101B Waste Gas Decay Tank.Caused by Operator Error. Total Kr-85 Activity Released Is 0.02% of Allowable Limit. Event & Possible Consequences Reviewed 1986-04-25
[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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/ 89 15 YPE EN 00CX(T NUM8EA EVENT DATE REPORT DATE O 1 CONT l
- l [_LJ l 0 l 5 l 0l-l 0 l 21 5 l 5 l l 0l1l 0 l 6 l Tl 7l l Ol3 l2 l1l 7l7 l 7 8 57 58 59 80 61 68 69 74 75 80 EVENT OESCAlPTION DE l Due to a condenser leak the secondary water chemistry specification per Tech Spec 3.18 l 7 89 80 E5 l vas exceeded for maxiinum of 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br />. Sodium, conductivity and pH vere outside the l 7 89 80 3l l parameter limits of Table 3.18.1 but were restored within the allovable 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and l 7 89 80 SE I power was reduced to 20% to repair the condenser. (ER-77-02) l 7 89 80 B(i l 80 l
7 89 me C E DE COMPONENT CODE VOLATON 3E l Hl Bl [ BJ lH lT l El Xl Cl Hl lNl l Cl hl 9l 0l (NJ 7 89 10 11 12 17 43 44 47 48 CAUSE OESCRIPTION DE I The condenser leakage resulted in a power reduction to 20% and the plugging of 3 tubes l 7 89 80 3E l in the east water box. Cause of leakage is undetermined at this time. l 7 85 80
@l l 5 % POWEA OTHER STATUS 035 VE OtSCOVERY DESCAPTON 1
{ l 0l 2l 0l l REDUCED P0'4ER l y l NA l 7 8 9 10 12 13 44 45 48 80 L o O ASE AMOUNT OF ACTIVITY LOCATCN OF AELEASE 3E 7 8 l zj 9
WI10 11 NA l 44 l
45 NA 80 l
PERSONNEL EXPOSURES NUM8EA TYPE DESCAFTCN 3E I 0101 of 7 89 11 Wl12 13 NA 80 l
PERSONNEL INJUAIES NUMBEA DESCASTCN 3E l 0l 0l 0l l NA ^_
l 7 89 11 12 80 PROBABLE CONSEQ1CNCES _
DE I NA ,
l 7 89 80 LOSS On OAMAGE TO FACTUTY TYPE OfSCAFTCN 3 [_Zj l NA l 7 89 10 80 PUBLOTY 1
l NA l 7 89 80 AOOmONAL FA0 TORS l ( 3l 89 NA 8306280621 770321 80 l
DE I PDR ADOCK 05000255 l 7 89 S PDR 80 l
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O O ggu Consumers Power l
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W i o.n.,.i omc..: 2i2 w.., u.chigan Avenue, . Jackson, Michigan 49201
April 5,1977 El21977
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Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR PALISADES PLANT - ER-77-02, ER-7T-11, ER-77 TECH 3ICAL SPECIFICATIONS LIMITS -
SODILH, pH, CONDUCTIVITY As a result of recent discussions with your staff and D0R staff, we have con-( cluded that any chemistry excursion, as identified by Section 3.18 of the Palisades Plant Technical Specifications, that occurs du*ing power operation shall be reported even if it does not exceed the allovable time limit.
The attached reportable occurrence (ER-77-11) was not reported previously because this item had not been resolved.
Corrected versions of ER-77-02 and ER-77-17 are being resubmitted at this time.
A a f()b h k (!i'X7 M u David P Hoffhan Assistant Nuclear Licensing Administrator
(
')') / 0 7 6 / S3 APR .8 1977
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