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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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Text
i Northern States Power Company Prairie island Nuclear Generating Plant 1717 Wakonade Drive East Welch, Minnesota 55089 July 10, 1995 Technical Specification Section 3.14 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Report of Inoperable Fire Protection Pumps This special report is being submitted in accordance with Prairie Island Technical Specification 3.14.B.3.
Technical Specification 3.14.B.3 requires
- that, With the FIRE SUPPRESSION WATER SYSTEM otherwise inoperable:
Establish a backup FIRE SUPPRESSION WATER SYSTEM within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and a.
- b. Provide a special report to the Commission within 30 days outlining i
the actions taken and the plans and schedule for restoring the inoperable system to OPERABLE status.
On June 10, 1995 surveillance procedure, SP-1202, Fire Pumps Test, was being performed as required per Technical Specification 4.16.B.l.g.
This procedure verifies the auto-start function of the fire pumps and checks pump capability.
During performance of the test, the 122 Diesel Fire Pump started 2 psig below the acceptable pressure range allowed by this procedure.
122 Diesel Fire Pump was logged out of service. This caused three fire protection pumps to be logged out of service at the same time.
l l
The 122 Diesel Fire Pump has the lowest auto-start pressure range of the three l
fire protection pumps.
In order to adequately test the auto-start function of the diesel pump, the remaining two pumps are isolated from the fire header to allow the header pressure to be reduced to the start point of the diesel pump.
Since the 122 Diesel Fire Pump did not meet the acceptable auto-start pressure range, three fire protection pumps were logged out of service at the same time.
> 4 es m-9507170138 950710 DR ADDCK 0500 2
d l
i USNRC NORTHERN STATES POWER COMPANY July 10,,1995 Page 2 Although the three fire protection pumps were logged out of service per Technical Specification 3.14.B, two pumps were available for fire service, if needed.
Surveillance procedure SP 1202 contains guidance to allow Operations j
personnel to immediately return 121 Motor Driven Fire Pump and 121 Screenwash l
Pump to service, if required for fire duty. Operators were stationed in the plcnt Screenhouse during performance of SP 1202 to allow a rapid return of these pumps, if needed. Also, the plant cooling water system was available for cross-tie to the fire header for back-up suppression supply, if needed.
The 122 Diesel Fire Pump auto-start pressure switch was subsequently adjusted per plant work order and a non-conformance report was issued for further investigation.
The applicable portions of SP 1202 were successfully completed and all fire protection pumps were returned to service within the same day.
In addition, we submitted a report dated June 12, 1995 which reported 121 Motor Driven Fire Pump out of service for greater than 7 days.
This report has one inadvertent error in it.
We reported that: "During the time the Motor Driven Fire Pump is and has been out of service, either the 122 Diesel Driven Fire Pump or the 121 Screenwash Pump have been operable." As discussed above, both 122 Diesel Driven Fire Pump and 121 Screenwash were inoperable at the same time on June 10.
The reason that the June 12 letter contains this mis-statement is that it was written and reviewed on Friday, June 9, the day before the situation described above. However, the letter was signed on Monday, June 12, without knowledge of the situation that occurred on the intervening Saturday.
All three pumps were declared operable on June 9,1995.
No new NRC commitments are being made in this letter.
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions related to this letter.
/
Roger O Anderson h
Director Licensing and Management Issues c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg FPOOS795. DOC
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