ML19326D983
| ML19326D983 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/16/1980 |
| From: | Tierney F NORTHERN STATES POWER CO. |
| To: | |
| References | |
| NUDOCS 8007250340 | |
| Download: ML19326D983 (1) | |
Similar Documents at Prairie Island | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20086G7951995-07-10010 July 1995
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217G4461999-09-30030 September 1999
[Table view]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
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 |
Text
__
TO ' O ? b-So to M f3 9 NORTHERN STATES P'O W E R COMgANY PIL\\llllE ISLAND NUCLEAll GENEllATING PLANT 1111 # 2 Welch,.\\lN 35089 July 16, 1980 Mr. James G. Keppler, Director Regica III Office of Inspection and Enf orcement 4
U S Nuclear Regulatory Corr.ission 799 Roosevelt Road Glen Ellyn, IL 60137 ATIN:
W. S. LITTLE Reportable Occurrence No. 80-20 On 7/15/80 with Unit 2 at 100% power and Unit 1 at cold shutdown, a severe electrical storm caused operation of several breakers in the substation. At about 2030 the main generator was separated from the grid and one of fsite source was lost and the reactor and reactor coolant pumps tripped. Natural circulation was established for core cooling.
At about 2138, No. 10 Transformer was locked out and with only one offsite source remaining (a degraded one), th diesel generators started and closed in on the safeguards buses. Ne safety injection was actuated.
At about 2240 the Cr11 source was restored and at 2319 No. 10 Transforcer was restored putting the plant back within Tech Specs.
At 0137 the next day, the substatien was completely nornal and Unit 2 is now operating at 100% power.
- ely,
M A
y F. P. Tierney, J r.
Plant Manager Prair4.e Island Nuclear Plant FFT/maj cc:
L. O. Mayer
~
eDirector, MIPC (2) m
- " N = tr(bution Services Branch, DDC, ADC C. D. Feierabend Gdh
/g 8007250.3/tf