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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
[Table view] 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
[Table view] |
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Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330 5500 December 7, 1992 Technical Specifications TS 3.14.A and TS 3.14.G.2 U S Nuclear Regulatory Comraission Attn:
Document Control Desk Washington, DC 2055S PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50 282 License Nos. DPR-42 50 306 DPR 60 Report of Plans for Alternate Provisions for Inonerable Fire Detection Instruments and Fire Barriers This letter is provided in accords.nce with Section 3.14.A and 3.14.C of the Prairie Island Technical Specifications which require that Fire Detection Instrumentation and Fire Protection Penetrations be OPERABLE whenever equipment they are protecting is required to be operable.
INOPERABLE FIRE DETECTION INSTRUMFNTATION i
Technical Specification 3.14.A states that:
Fire Detection Instrumentation 1.
The minimum fire detection instrumentation for each fire detection zone shown in Table 3,14-1 shall be OPERABLE whenever equipment in that fire detection zone is required to be OPERABLE (except as specified in 3.14.A.2).
Fire detection instruments located within containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.
2.
If specification 3.14. A.1 cannot be met:
Within one hour, establish a fire watch patrol to inspect the a.
cone with the inoperable instruments at least once per hour.
Fire zones located inside primary containment are exempt from this requirement when CONTAINMENT INTEGRITY is required.
140007 9212140125 921207 PDR ADOCK 05000282
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e Northem States Power Company USNRC
~ December 7, 1992 Page 2 e
b.
Restore the inoperable instruments to operable status'within 14 days or submit a special report to the Commission within 30 days outlining the cause of the malfunction and the plans for-l restoring the instruments to OPERABLE status.
1 On October 30, 1992, durin6 a dual unit outage, work began on the replacement of the cooling water pipe. The large amount of cutting and grinding that took place from that time forward required the detection instrumentation in some fire tones to be bypassed to avoid frequent alarms. Within an hour of the zone being bypassed, either a continuous or a roving fire watch was posted,-
depending on Technical Specification requirements.
In addition, separate fire watches were posted for each ignition source activity, por plant _ directives.
The zones will remain in bypass with the required fire watches posted until i
construction activity is complete and in any case will be restored prior to 4
either Unit 1 or 2 resuming power operation.
Since the detection instruments were not restored to OPERABLE status within the 14 days required by Technical Specification 3.14.A.2.b, a written report is required which this submittal satisfies.
INOPERABLE PENETRATION FIRE BARRIERS Technical Specification 3.14.0 states that:
Penetration Fire Barriers 1.
All penetration fire barriers in fire area boundaries protecting equipment required to be OPERABLE shall be OPERABLE (except-as specified in 3.14.G.2 below).
2.
If Specification 3.14.C.1 cannot be met within one hour:
a) establish a continuous fire watch on at least one side of the-affected penetration (s), or b) verify the OPERABILITY of the fire detectors on.at least one side of the inoperable barrier:and establish an hourly fire watch.
Restore the inoperable-penetration fire barriers to OPERABLE status within 7 daysfor submit _a special report to the Commission within 30.
days outlinin6 the cause of the inoperability and the plans and q
schedule for restoring the barriers to OPERABLE status.
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Northern States Power Company December 7, 1992 Page 3 On October 30, 1992 a number of fire penetrations were breached to remove and install the new cooling water pipe. The penetrations to fire areas that protect safety related equipment were subsequently covered by either continuous or roving fire watches as required by Technical Specifications.
These penetrations will remain open until the cooling water project is complete and will be restored prior to Unit 1 or 2 resuming power operation.
The open penetrations also included the Unit 1 door to the control room which.
was open from November 6 to November 14, 1992 to allow cable to pass through for a control board modification.
During the time the door was open a fire watch was posted.
Since the fire penetrations were not restored to OPERABLE status within the 7 days requirement of Technical Specification 3.14.C.2, a written report is required which this submittal satisfies.
Please contact us if you require additional information.
YM4
' Thomas M Parker Director of Licensing Nuclear Cencration c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg P
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