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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20086G7951995-07-10010 July 1995
Special Rept:On 950610,122 Diesel Fire Pump Started 2 Psig Below Acceptable Pressure Range Allowed by Procedure
ML20085G0591995-06-12012 June 1995
Special Rept:On 950515,121 Motor Driven Fire Pump Was Taken Out of Svc Due to Failed Transformer in Pump Control Circuitry
HL-4693, Special Rept 1-94-001:on 940911,seven Days Elapsed Since Main Stack post-accident Effluent Monitoring Sys Declared Inoperable Due to Damage to Sys Electronics by Lightning. Sys Expected to Be Returned to Svc by 9409211994-09-15015 September 1994
Special Rept 1-94-001:on 940911,seven Days Elapsed Since Main Stack post-accident Effluent Monitoring Sys Declared Inoperable Due to Damage to Sys Electronics by Lightning. Sys Expected to Be Returned to Svc by 940921
ML20072C8621994-08-0909 August 1994
Special Rept:On 940711,fire Protection Pump Removed from Service for Greater than Seven Days Due to Normal Preventive Maint Work.Pump Returned to Svc on 940721
ML20063M1741994-03-0303 March 1994
Special Rept:On 940117,fire Protection Equipment Removed from Svc for Greater than 14 Days.No NRC Commitments Being Made in Ltr
ML20125C8771992-12-0707 December 1992
Special Rept:On 921030,fire Zones Bypassed to Avoid Frequent Alarms During dual-unit Outage to Replace Cooling Water Pipe.Separate Fire Watches Posted for Each Ignition Source Activity & Open Penetration Door
ML20055D4051990-06-28028 June 1990
Special Rept:On 900607,inoperable Fire Suppression Water Sys Not Restored within 7-day Time Frame Per Tech Spec 3.14.B.2. Caused by Worn Bearing/Impeller Assembly.Efforts Underway to Procure Spare Bearing Housings for All Fire Pumps
ML20006E8101990-02-20020 February 1990
Special Rept Re Plans for Alternate Fire Suppression Sys Redundancy.Diesel Driven Fire Pump 122 Run Daily,Except When Out of Svc from 900126-29
ML20155B5661988-09-29029 September 1988
Ro:On 880903,circulating Water Pump 12 Suction Bay Isolated & Drained Down,Rendering diesel-driven Fire Pump Inoperable & on 880910,circulating Water Pump 11 Suction Bay Isolated & Drained Down,Rendering motor-driven Fire Pump Inoperable
ML20028C1621982-12-29029 December 1982
RO 82-15:on 821228,tiny through-wall Crack Found in Heat Affected Zone of Weld in Safety Injection Supply Line from Boric Acid Storage Tanks.Investigation in Progress
ML20052J0761982-05-14014 May 1982
RO P-RO-82-7:on 820501,rod Control Sys Component Failed Causing Loss of Drive Motion for Some Rods.Caused by Failed Bridge Thyristor in Power Cabinet 1BD.Unit Brought to Hot Shutdown & Rod Control Sys Repaired on 820502
ML20009A0101981-07-0202 July 1981
Environ Event Rept 81-01:on 810604,daily Chlorination Cycle Extended for 126 Minutes.Caused by Malfunction of Timer. New Timer W/More Precise Time Control Installed W/Setting of 110 Minutes Per Day
ML19340C8321980-12-0303 December 1980
RO 80-25,Revision 1:on 800904,during Investigations Re Generic Technical Activity A-12,CVM Steam Generator Mounting Bolts Found Defective.Caused by Stress Corrosion Cracking. New Steam Generator Mounting Bolts Installed & Tensioned
ML19347A9651980-09-25025 September 1980
Environ Event Rept 80-03:on 800820,during Special Chlorination Program,Certain Levels of Chlorine Found Outside Circulating Water Sys That Exceeded Concentration Limits in Tech Specs 2.4.1
ML19332A8141980-09-0505 September 1980
RO 80-25:on 800904,w/unit in Refueling Shutdown,Ultrasonic Examination of Steam Generator Support Bolts Revealed Most Bolts Had Crack Indications.Several Bolts Failed When Detensioning Was Attempted.Cause Not Determined
ML19326D9831980-07-16016 July 1980
RO 80-20:on 800715,w/Unit 2 at 100% Power & Unit 1 at Cold Shutdown,Main Generator Separated from Grid & One Offsite Source Was Lost,Tripping Reactor & Coolant Pumps.Caused by Severe Electrical Storm.Transformer Restored
ML19323G9411980-06-0404 June 1980
Environ Event Rept 80-02:on 800513-14,reclaiming Ion Exchanger Out of Svc When Steam Generator Blowdown Water Discharged Into River.Sample of Outfall Revealed Ph Value Greater than 8.5.Caused by Seasonal Change of River
ML19312E2141980-05-30030 May 1980
Environ Event Rept 80-01:on 800501,daily Average Discharge Temp Exceeded Ambient River Water Temp by 5.7 F While Two Cooling Towers Were Undergoing Insp,Cleaning & Repair.One Tower Returned to Svc & Electrical Load Reduced
ML19257B9051980-01-10010 January 1980
RO 80-03:during Eddy Current Insp of Steam Generator 21, Defect Discovered in One Tube.Caused by Movement of One Tube Lane Blocking Devices Against Outside Surface of Tube, 17 Inches Above Tubesheet.Tube Will Be Plugged
ML19257B2561980-01-0707 January 1980
RO 80-1 on:800106,at 100% Power,Both Trains of Caustic Addition to Containment Spray Sys Found Valved Out.Caused by Valves Mistakenly Closed on 800103 During Unit 2 Cooldown for Refueling.Containment Spray Sys Operable During Period
ML19260B1531979-12-0303 December 1979
Environ Event Rept 79-11 for 17 Days in Nov.Slowdown Flow in Excess of Tech Specs Required to Complete Special Chlorination Treatment Authorized by 791102 ETS Change
ML19250B9621979-10-31031 October 1979
Environ Event Rept 79-09:on 791007,neutralizing Tank Batch Discharged W/Ph Greater than 8.5.Discharge Determined to Be 11.65.Caused by Improper Operation of Ph Monitor on Tank Effluent Pipe.Shift Supervisors Reinstructed
ML20058A1521978-11-0101 November 1978
Environ Event Rept 78-10;covering Operation of Circulating Water Sys in Partial Recycle Mode W/Daily Average Blowdown Flow in Excess of 150 Cfs
ML19329F4161975-11-14014 November 1975
RO 75-02:on 750810,long Lived Halogen & Particulate One Yr Release Rate Exceeded Design Objective 3.9.2.6.Corrections Not Required Because Prairie Island Tech Spechs More Conservative than Reg Guide 1.42,Revision 1,requirements
1995-07-10
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pingp.With
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML20217A1691999-09-22022 September 1999
Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20216E7151999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with
ML20211J2851999-08-26026 August 1999
Safety Evaluation Supporting Amends 146 & 137 to Licenses DPR-42 & DPR-60,respectively
ML20211D3981999-08-24024 August 1999
Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively
ML20211C2531999-08-0404 August 1999
Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526
ML20210Q4891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with
ML20211B5971999-07-31031 July 1999
Cycle 20 Voltage-Based Repair Criteria 90-Day Rept
05000282/LER-1999-007-01, :on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted1999-07-23023 July 1999
- on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted
ML20209J1131999-07-15015 July 1999
Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions
ML20209F9811999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20196F4081999-06-23023 June 1999
Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20195G5181999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included
ML20207B5931999-05-26026 May 1999
SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs
ML20196L2501999-05-13013 May 1999
Rev 0 to PINGP Unit 1 COLR Cycle 20
05000282/LER-1999-005-01, :on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event1999-05-0808 May 1999
- on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event
ML20206L6191999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with
ML20205N1081999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with
ML20205B3351999-03-17017 March 1999
Safety Evaluation Supporting Amends 143 & 134 to Licenses DPR-42 & DPR-60,respectively
ML20205Q5101999-03-15015 March 1999
Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229
05000306/LER-1999-001-01, :on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With1999-03-0808 March 1999
- on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With
ML20207J6951999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant
ML20202J7711999-02-0404 February 1999
Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept
ML20207L2811999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2
ML20202G3761999-01-31031 January 1999
Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units
ML20202J1731999-01-22022 January 1999
Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety
05000306/LER-1998-006-01, :on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted1999-01-18018 January 1999
- on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted
ML20205H0561998-12-31031 December 1998
Northern States Power Co 1998 Annual Rept. with
ML20206P7861998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With
ML20198J6441998-12-17017 December 1998
Rev 0 to PINGP COLR Unit 2-Cycle 19
05000306/LER-1998-005-02, :on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With1998-12-0909 December 1998
- on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With
ML20198L2211998-12-0707 December 1998
Safety Evaluation Supporting Amends 141 & 132 to Licenses DPR-42 & DPR-60,respectively
ML20206N2731998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
05000282/LER-1998-016, :on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With1998-11-24024 November 1998
- on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With
ML20196D7341998-11-20020 November 1998
Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi
ML20195D3821998-11-0404 November 1998
Safety Evaluation Supporting Amends 140 & 131 to Licenses DPR-42 & DPR-60,respectively
ML20155K6301998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20195D3761998-10-30030 October 1998
Safety Evaluation Supporting Amends 139 & 130 to Licenses DPR-42 & DPR-60
05000306/LER-1998-004-01, :on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With1998-10-0505 October 1998
- on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With
ML20202J7991998-09-30030 September 1998
Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept
ML20154H4061998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With
ML20198R8061998-09-30030 September 1998
Rev 1 to NSPLMI-96001, Prairie Island Nuclear Generating Plant Ipeee
ML20154B9241998-09-22022 September 1998
Safety Evaluation Supporting Amends 138 & 129 to Licenses DPR-42 & DPR-60,respectively
ML20198P0571998-09-0303 September 1998
Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator
ML20153B0761998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With
05000282/LER-1998-009-01, :on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures1998-08-27027 August 1998
- on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures
ML20237D6491998-08-13013 August 1998
Safety Evaluation Supporting Amends 137 & 128 to Licenses DPR-42 & DPR-60,respectively
ML20237A3961998-08-11011 August 1998
Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View
1999-09-30
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l Northern States Power Company 414 Niconet Mau Minreapoks. Minnesota 55401 Telephone (612) 330 5500 September 29, 1988 Director Office of Nuclear Reactor Regulation Attn: Document Control Desk U S Nuclear Regulatory Commission Washington, D C 20555 PRAIRIE IS1AND NUCLEAR GENERATING PIANT Docket Nos. 50 282 License Nos. DPR 42 50-306 DPR 60 Removal of Fire Punms from Service _Durinc Maintenance Activities This report is provided in accordance with Section 3.14.B.2 of the Prairie Island Technical Spesifications. This section requires submittal of a report to the Commission outlining plans and procedures to be used to provide for the loss of redundancy in the fire suppression water system whenever fire puap(s) are inoperable for more than seven days.
On Saturday, September 3, l'88 the nwnber 12 circulating water pump suction bay was isolated and drained down to allow replacement of the number 12 circulating water pump impeller and wear rings during this refueling outage.
This rendered the 122 diesel driven fire pump inoperable.
On Saturday, Septeruber 10, 1988 the number 11 circulating water pump suction bay was isolated and drained down to perform the normal inspections and preventative maintenance activities scheduled for this refueling outage.
This rendered the 121 motor driven fire pump inoperable.
On Wednesday, September 21, 1988 work was completed and the 121 motor driven fire pump and the 122 diesel driven fire pump were returned to service.
To provido assurance of fire suppresvion water system redundancy during this period, tho screen wash pump (back op fire pump) was run daily to verify its operability a.: required by Technical Specification 4.16.B.2.
In addition, seven crossover valves from the safety grado cooling water systern were available to provide backup water supply to the f tre protection system.
This is true even during loss of off site power.
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Northem States Power Company 414 Nicoret Ma!!
Menneapoks. M,nnesota $540' Te'ephone (612) 330 5500 September 29, 1988 Director Office of Nuclear Reactor Regulation Attn: Document Control Desk U S Nuclear Regulatory Commission Washington, D C 20555 PRAIRIE ISLAND NUCLEAR GENERATING PIANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR 60 Ret
- oval of Fire Pumns from Service Durinr. Maintenance Activities This report is provided in accordance with Section 3.14.B.2 of the Prairie Island Technical Specifications.
This section requires submittal of a report to the Commission outlining plans and procedures to be used to provide for the loss of redundancy in the fire suppression water system whenever fire pump (s) are inoperable for more than seven days.
On Saturday, September 3, 1988 the number 12 circulating water pump suction bay was isolated and drained down to allow replacement of the number 12 circulating water pump impeller and wear rings during this refueling outage.
This rendered the 122 diesel driven fire pump inoporable.
On Saturday, September 10, 1988 the number 11 circulating water pump suction bay was isolated and drained down to perfcrm the normal inspections and preventative maintenance activities scheduled for this refueling outage. This rendered the 121 motor driven fire pump inoperable.
On Wednesday, September 21, 1988 work was completed and the 121 motor driven fire pump and the 122 diesel driven fire pump were returned to service.
To provide assurance of fire suppression water system redundancy during this period, the screen wash pump (back up fire pump) was run daily to verify its operability as required by Technical Specification 4.16.B.2.
In addition, seven crossover valves from the safety grade cooling water system were available to provide backup water supply to the fire protection system.
This is true even during loss of off site power.
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4 Dir cf NRR Northem States Power Company
_ Pago 2 September-29, 1988 Please contact us if you have any questions related to the measures taken during these refueling outage activities to provide redundancy of fire suppression water supplies.
De ' O Nw David Musolf l
I Manager Nuclear Support Services c: Regional Administrator. III, NRC i
NRR Project Manager NRC NRC Resident Inspector G Charnoff t
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