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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20149G9861994-11-0404 November 1994 Special Rept:On 941006,Unit 1 Fuel Storage Pool Conductivity Exceeded 10 Micro/Mho/Cm TS Limit & Returned to within TS on 941010.Caused by Decomposition of Biological micro-organisms in Fuel Storage Pool.Temporary Demineralizer Restarted BECO-86-173, Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified1986-11-12012 November 1986 Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified BECO-86-171, Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released1986-11-10010 November 1986 Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released ML20211E0731986-09-26026 September 1986 Unplanned Operating Event Rept 85-6, Manual Reactor Trip Following MSIV Closure Due to Inadvertent Emergency Feedwater Actuation,851009 BECO-86-125, Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found1986-08-29029 August 1986 Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found ML20238E4601986-08-28028 August 1986 Partially Withheld Secrity Event Rept:On 860824,bomb Threat Received for Plants.Bomb Search Initiated.No Suspicious Objects Found ML20211K8211986-06-18018 June 1986 Special Rept:On 860521,valid Failure Occurred on Div 2 Diesel Generator During Performance of Tech Spec Surveillance 4.8.1.1.2.Caused by Failure of Jacket Water Thermostatic Control Valve to Open ML20238E4591986-06-17017 June 1986 Partially Withheld Security Event Rept:On 860612,withheld Discovery Made Re 860604 Moderate Loss of Security Effectiveness.Caused by Inadequate Post Orders & Training for Assignment.Assignments Will Be Specifically Addressed 05000000/LER-1986-009, Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised1986-04-14014 April 1986 Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised BECO-86-016, Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended1986-02-20020 February 1986 Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended BECO-85-220, Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured1985-12-0909 December 1985 Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured AECM-84-0204, Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored1984-04-0606 April 1984 Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored ML20198H3691983-11-14014 November 1983 Ro:On 831003,results of as-found Tests Indicated Crosby Main Steam Relief Valves Had Lift Points Exceeding Tech Spec Limits.Valves Disassembled & Rebuilt by Mfg ML20105D2431983-06-24024 June 1983 Special Rept:Five Individuals Found to Have Received Radiation in Excess of 10CFR20.101 Limits W/O Required Documentation.Caused by computer-based Sys Feature Allowing Use of Outdated Info & Personnel Error.Procedures Revised ML20069E5351983-03-15015 March 1983 RO 83-014:on 830219,contaminated Demineralized Water Released Into Condenser,Allowing 0.7 Mci to Steam Out of Vent.Caused by Personnel Error.Operator Opened Valve MO-3-1301-10 Instead of Valve MO-3-4399-74 ML20069A3561983-03-0909 March 1983 RO 83-016:on 830207,contaminated Water from Drain & Refill of 2/3A Heating Boiler Inadvertently Released to Storm Sewer Sys.Caused by Operator Not Realizing Floor Drain Led to Storm Sewer Sys,Not Radwaste Sys.Tech Specs Not Violated ML20054F7971982-06-0909 June 1982 RO 82-027:on 820511,excessive Radioactive Contamination Identified in Two Areas of Offsite Dump.Caused by Inadequate Control of Dump Access & Failure to Survey Large Loads of Matl Thoroughly.Area Cleaned Up & Procedure 12-5 Revised ML20137G4501981-03-24024 March 1981 Ro:During walk-through of Operator Training Program, O-ring Seal of Filter Holder Found Not Seated Properly Causing Partial Bypass of Filter for Air Sucked Into instrument.Filter-in Lock Adjusted ML20071F0861980-09-25025 September 1980 Ro:On 800912,sample Analysis Taken from Hydrazine Addition Tank Indicated Sodium Chloride in Tank.Anonymous Telcon Indicated Salt May Have Been Added Prior to Labor Strike by Unknown Persons ML20086D5141978-01-0606 January 1978 Telecopy Ro:On 780105,discovered That One of Two Nuclear Engineering Co Model B3-1 Shipping Casks Provided w/1-inch Diameter Lid Bolts Rather than 1-1/4 Inch Size Specified in Certificate of Compliance 6058 ML20086D5201977-12-14014 December 1977 Telecopy Ro:Heating Steam Coil Leak in Reactor Bldg Ventilation Supply Unit V-AH-4A Resulted in Freezing of Condensate at Inlet to Unit & Subsequent Inoperability of Associated Secondary Containment Isolation Dampers ML20086D5371977-10-14014 October 1977 Telecopy Ro:Insp of Internal Torus Catwalk Support Structure Revealed That Catwalk Mitered Sections Not All Attached to Horizontal Catwalk Support Plates in Some Manner.Attachment Locations Will Be Upgraded ML20086D5501977-10-13013 October 1977 Telecopy Ro:On 771012,local Leak Rate Testing of MSIV AO-2-80A & Nitrogen Instrument Air Sys Isolation Valve CV-7436 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation ML20086D5541977-10-0505 October 1977 Telecopy Ro:On 771004,local Leak Rate Testing of HPCI Sys Discharge Isolation Check Valve HPCI-9 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation ML20086D5571977-09-29029 September 1977 Telecopy Ro:On 770929,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO-14-13A Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation ML20086D5611977-09-14014 September 1977 Telecopy Ro:On 770913,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO 14-13B Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Related Event on 770914 ML20086D5671977-09-12012 September 1977 Telecopy Ro:Main Steam Drain Isolation Valve MD 2373 & Main Steam Outboard Isolation Valve AO 2-86A Exceeded Tech Spec Acceptance Criteria for Local Leak Rate Tests ML20086D6421977-07-11011 July 1977 Telecopy Ro:On 770709,determined That Recombiner Sys a Offgas Flow Control Valve PCV 7489A Could Be Opened W/ Controlling Solenoid Valve Deenergized.Valve Held from Svc Pending Investigation ML20137G4461977-06-23023 June 1977 Ro:On 770621,radioactive Source Containing 200 Mci Cs-137 Recovered from Brine Well 33.Incident Described in ML20086F0801977-06-0606 June 1977 Ro:On 770506,plant Iodine & Particulate Release Rate Exceeded 4% of Facility Tech Spec Averaged Over Second Calendar Quarter of 1977.Caused by Fuel Perforations Coupled W/End of Cycle Testing & Reactor Coolant & Steam Leaks ML20084R9011977-03-23023 March 1977 Telecopy Ro:On 770322,while Completing Operability Surveillance Following Maint on Sys Air Compressors,Diesel Generator Field Failed to Flash & Diesel Generator 2/3 Failed to Start on First Attempt.Cause Unknown ML20086D6911977-03-0202 March 1977 Telecopy Ro:On 770301,torus Water Vol Found to Be Slightly Below Min Vol Established by Tech Specs.Water Vol Restored to Normal Operating Level ML20086D7031977-02-24024 February 1977 Telecopy Ro:On 770223,while Withdrawing in-sequence Control Rod to Bring Reactor Critical,Reactor Period of Less than 5 Obtained ML20084A0611976-12-20020 December 1976 Telecopy Message of Ro:On 761220,empty Spent Fuel Cask Areas Found W/Removable Contamination ML20084L7821976-12-15015 December 1976 RO 50-237/1974-27A update.Three-yr Study of Use of phosphorus-bronze in Place of Teflon as Bushing Matl in torus-to-drywell Vacuum Breakers Provides No Justification for Replacement of Teflon Bushings ML20084A0991976-12-15015 December 1976 Telecopy Message of Ro:On 761215,4% Reduction Made in Allowable Maplhgr.Caused by Error in GE ECCS Analysis ML20084A2151976-12-13013 December 1976 RO 50-237/76-66:on 761113,HPCI Sys Injection Valve 2-2301-8 Failed.Valve Repairs to Be Completed at Next Outage ML20086F4181976-12-0909 December 1976 RO Re Plant Iodine & Particulate Release Rate Exceeding 4% of Tech Spec 3.8.C.2 Averaged Over Fourth Calendar Quarter 1976.Caused by Leaks in Reactor Water Cleanup Sys.Leaks Repaired & Equipment Modified to Reduce Leakage ML20084A1391976-12-0606 December 1976 Telecopy Message of Ro:Empty Spent Fuel Shipping Cask Received W/Areas of Removable Surface Contamination ML20084A1811976-12-0202 December 1976 Telecopy Message of Ro:On 761202,empty Spent Fuel Shipping Cask Received W/Areas of Removable Surface Contamination ML20084R9111976-11-19019 November 1976 Telecopy Ro:On 761119,potential HPCI Design Error Discovered Which Could Cause Failure of HPCI Valve MO3-2301-8 During Certain Postulated Conditions.Caused by Design Wiring Problem.Valve Placed out-of-svc in Open Position ML20070J8681976-10-20020 October 1976 RO 76-13:on 760916,normal Boric Acid Makeup to Vol Control Tank Could Not Be Accomplished Due to Plugging of Chemical & Vol Control Sys Line 1-inch-CH-56-152.Cause Unknown.Line Will Be Inspected for Indications of Solidification ML20070J8581976-10-0101 October 1976 RO 76-12:on 760909,low Pressure Alarm Occurred on Safety Injection Accumulator C,Resulting in Pressure Reduction. Caused by Partially Open HCV 1936 & Body to Bonnet Leaks on HCV 1898 & 1549.Valves Repaired & Accumulator Repressurized ML20070J8961976-09-29029 September 1976 RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated ML20070J8801976-09-24024 September 1976 RO 76-07:on 760913,monthly Average of Gaseous & Airborne Particulate Wastes for Previous 12 Months Found Greater than Tech Spec Limit.Caused by Interpretational Changes in Tech Spec Section 3.11.B.New Limit Approved ML20084R9181976-09-20020 September 1976 Telecopy Ro:On 760914,during Reactor Power Operation, Primary Containment Oxygen Content Found Greater than 4%. Caused by Terminated Unit Shutdown After Sys Min Load Problems Developed ML20086D7881976-09-10010 September 1976 Telecopy Ro:On 760909,discovered That Torus Water Vol Several Hundred Cubic Ft Below 68,000 Cubic Ft Min Required by Tech Specs.Caused by Failure to Correct for Vol Vs Level Correlation ML20084R5841976-06-15015 June 1976 Suppl Rept to ROs 50-249/75-10A,11A & 33A:motors Replaced on Valves 3-1402-4A & 3-1501-5A & Original Motors Sent to Manufacturer for Evaluation.Valve Trips Occurred Due to Undersized Overload Heaters.Mods Initiated ML20086D8231976-05-0505 May 1976 Telecopy Ro:On 760504,during Routine Surveillance Test, Primary Containment Oxygen Concentration Found to Be in Excess of Tech Spec Limit.Caused by Leakage from Drywell Instrument Air Sys Into Containment Nitrogen Supply Line ML20090E3751976-03-25025 March 1976 Telecopy Ro:On 760325,through-wall Crack Indication Found on HPCI Steam Supply Line safe-end.Cause Not Stated 1994-11-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with 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 ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With ML20154L3681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20154N4131998-09-30030 September 1998 1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20153C5061998-09-21021 September 1998 SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1 ML20151Y2711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A7161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236Q5851998-06-30030 June 1998 1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20236T8331998-06-30030 June 1998 COLR for Dresden Station Unit 3,Cycle 15 ML20236T8391998-06-30030 June 1998 Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept ML20236M6041998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20248M3021998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F3391998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20216C9651998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20216D4411998-03-31031 March 1998 First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059 ML20216E2531998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station ML20202F7831998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept ML20198P5321997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Dresden Nuclear Power Station ML20198P7021997-12-31031 December 1997 Fourth Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 ML20203F8781997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Dresden Nuclear Power Station ML20199B0701997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Dresden Nuclear Power Station ML20217H7201997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20210V2401997-09-19019 September 1997 Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual ML20216J3781997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for DNPS ML20210H5511997-07-31031 July 1997 Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02 1999-09-30
[Table view] |
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SUBJECT:
REPORT OF ABNORMAL OCCURRDJCE PER SETION 6.6.B 0F THE TECIMICAL SPIEIPICATIONS.
PRIMARY SYSTB4 LEAKS.
References:
- 1) Regulatory Guide 1.16 Rev.1 Appendix A
- 2) Notification of Region III of AEC Regulatory Operations Telephone: Mr. F. Maura,1515 heurs en septe= der..13._.1974 Telegram Mr. J. Keppler, 1543 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.871115e-4 months <br /> on September 13, 1974
- 3) Drawing Number: P&ID W 26 Report Number: 50-237/1974 m 26 Report Dates September 19, 1974 Occurrence Date: September 13, 1974 Facility: Dresden Nuclear Power Station, Morris, Illinois IDDTPIPICATION OF OCCURRD'CE On September 13, 1974, a leak was discovered on line 2-0203B-4"-4 in the "B" reciro. system. The next day a leak was diccovered on line 2-0203A-4"-A in the "A" recire. system. This reprocents an abnormal degradation of a boundary designed to contain radioactive materials.
CONDITIONS PRIOR TO OCCURRB;CE
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At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on September 13, 1974, Unit 2 was in shutdown.
DESCRIPTION OP OCCURRSEE At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on September 13,~ 1974, Unit 2 was in shutdown due to high .
drywell leakage. Inspections were in progress to determine the cause of the leakage. At this time, a. leak was discovered on 2B recirc. loop at
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Mr. Jam a G. Ksppler v Ssptemb:r 19, 1974
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the connection of 2B recire. pu=p discharge valve bypass line (2-0203B-4"-A) with the recire. loop (2-0201B-28"-A). The line was cracked at the point where the line is welded to an inverted reducer. The crack was a circumfer-ential crack which ran along approximately 75% of the pipe circumference and was completely through the pipe in two areas. This crack was upstream of the bypass valve and was casily isolatible.
The next day a crack was found on the 2A recire. loop. The crack was also in the 4" equalizins line, but downstream of the bypass valve at the 28"x4" reducer to the 28" recire. riser. This crack consisted of an approximately 3/4" long circumferential crack with about a 1-1/2" tail running along the length of the pipe. Only the circumferential part of the crack was completely through the pipe. This crack was not isolatible.
DESIGNATION OF APPARFNT CAUSE OF OCCURRENCE At this time, no apparent cr.use is known. Pieces of the cracked pipe were sent out for analysis. A followup letter will be written when the results of these analyses are returned.
ANALYSIS OF OCCURRENCE There were no safety consequences to the public or plant personnel as a result of this occurrence because the cracks were found before any major damage was done. All water was contained in the drywell sumps and pumped to Raduaste for processing. The shift b,' shift monitoring of the drywell sumps found this problem immediately and allowed for a safe shutdown before excessive leakage reculted. Had the pipe broken under operation, LPCI, HFCI and core spray were available to provide core cooling.
CORRECTIVE ACTION The 2B loop crack was isolated, the section of cracked pipe cut out, and a new section welded in. The 2A loop is at the present, unisolatible. Plans are being formulated for repairing this crack. The followup letter will include the method used for repairing this crack. Subsequent investigations will be conducted on Unit 3 to disclose similar cracking at the earliest opportunity.
FAILURE DATA These are the first idlures of this type.
Sincerely, B. B. Stephenson Superintendent BBS:do
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