ML19309G729
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| ML19309G729 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/30/1980 |
| From: | Tierney F NORTHERN STATES POWER CO. |
| To: | |
| References | |
| NUDOCS 8005070459 | |
| Download: ML19309G729 (1) | |
Similar Documents at Prairie Island | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20006E8101990-02-20020 February 1990
[Table view]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 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 ML19320C3261980-07-0101 July 1980 RO 80-18:on 800629,steam Generator 12 Experienced Minor primary-to-secondary Leakage of About 0.006 Gallons Per Minute.Leakage Was Carefully Monitored & Showed Increase. Facility Is Shutdown.Cooldown Is Planned 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 ML19309G7291980-04-30030 April 1980 RO 80-15:on 800429,volumetric Test of Facility Containment Main Airlock Showed Leakge of 600 Scc/Minute,Exceeding Tech Specs.Caused by Opening of Inner Airlock Door.Seals for Inner Door Were Replaced.Leakage Was Acceptable ML19296A6521980-01-24024 January 1980 RO-80-06:on 800123,diesel Generator D2 Tripped on High Crankcase Pressure When Crankcase Eductor Supply Pipe Came Loose.During Operability Testing of Other Diesel Generates, Jacket Coolant Hose on Water Pump Ruptured ML19291C1991980-01-15015 January 1980 Supplemental Info to RO 80-3.One Tube Defective on Steam Generator Hot Leg 21.One Tube Defective & Ten Tubes Degraded on Cold Leg 21.Hot Leg 22 to Be Inspected.Four Tubes Defective & 42 Degraded on Cold Leg 22.Cause Unknown 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 ML19210C6831979-11-0101 November 1979 Environ Event Rept 79-10 Re Operation of Circulating Water Sys in Partial Recycle Mode W/Daily Average Blowdown Flow in Excess of 150 Cfs.Higher Flow Required to Maintain Cooling Water Inlet Temps at Less than 85 F 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 ML19209B7041979-10-0303 October 1979 RO 79-27:on 791003,reactor Tripped on Low Pressurizer Pressure Followed by Safety Injection & Containment Isolation.Caused by Steam Generator Tube Leakage.Failed Tubes Will Be Plugged & Inspected 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 1990-02-20 Category:LER) MONTHYEARML20006E8101990-02-20020 February 1990
[Table view]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 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 ML19320C3261980-07-0101 July 1980 RO 80-18:on 800629,steam Generator 12 Experienced Minor primary-to-secondary Leakage of About 0.006 Gallons Per Minute.Leakage Was Carefully Monitored & Showed Increase. Facility Is Shutdown.Cooldown Is Planned 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 ML19309G7291980-04-30030 April 1980 RO 80-15:on 800429,volumetric Test of Facility Containment Main Airlock Showed Leakge of 600 Scc/Minute,Exceeding Tech Specs.Caused by Opening of Inner Airlock Door.Seals for Inner Door Were Replaced.Leakage Was Acceptable ML19296A6521980-01-24024 January 1980 RO-80-06:on 800123,diesel Generator D2 Tripped on High Crankcase Pressure When Crankcase Eductor Supply Pipe Came Loose.During Operability Testing of Other Diesel Generates, Jacket Coolant Hose on Water Pump Ruptured ML19291C1991980-01-15015 January 1980 Supplemental Info to RO 80-3.One Tube Defective on Steam Generator Hot Leg 21.One Tube Defective & Ten Tubes Degraded on Cold Leg 21.Hot Leg 22 to Be Inspected.Four Tubes Defective & 42 Degraded on Cold Leg 22.Cause Unknown 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 ML19210C6831979-11-0101 November 1979 Environ Event Rept 79-10 Re Operation of Circulating Water Sys in Partial Recycle Mode W/Daily Average Blowdown Flow in Excess of 150 Cfs.Higher Flow Required to Maintain Cooling Water Inlet Temps at Less than 85 F 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 ML19209B7041979-10-0303 October 1979 RO 79-27:on 791003,reactor Tripped on Low Pressurizer Pressure Followed by Safety Injection & Containment Isolation.Caused by Steam Generator Tube Leakage.Failed Tubes Will Be Plugged & Inspected 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 1990-02-20 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 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 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 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With 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 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 ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 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 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 ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 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 ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.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 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 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 ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30 |
Text
8 0 0 5 0 7 0VS9 S
NSD NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT RR #2 Welch, SIN 55089
) April 30, 1980 Mr. James G Keppler, Director Region III Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 ATTN: D C Boyd Reportable Occurrence No. 80-15 On April 29, 1980, a volumetric test of the Unit 1 containment maintenance airlock showed leakage of about 600 sec/ min. The Tech Spec limit is 409 scem.
The seals for the inner door were replaced and leakage was acceptable.
The volumetric test pressurizes the space between the doors to 46 psig. Thus, the tes t pressure tends to open the inner airlock door. Also, door s tops are installed prior to the test to prevent overcompression of (and damage to) the door seals. For these reasons it is concluded that is is quite possible that door leakage would have been acceptable during the postulated accident. However, this was not proved.
The outer door was operable throughout the period.
Sincerely, c.
Q P. Tier e h Jr.,
Plant Manager Prairie "aland Nuclear Plant FPT:div cc: L 0 Mayer Director, MIPC (2)
% Distribution Services Branch, DDC, ADM C D Feierabend V
, g 0 1
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