05000366/LER-1980-147, Updated LER 80-147/03X-1:on 801029,A & B post-accident Monitoring Drywell Hydrogen Peroxide Analyzers Found Inoperable.Caused by Combination of Failures of Related Equipment.Components Associated W/Analyzers Repaired
From kanterella
| ML20064L185 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/08/1983 |
| From: | Tipps S GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20064L156 | List: |
| References | |
| LER-80-147-03X, LER-80-147-3X, NUDOCS 8302150142 | |
| Download: ML20064L185 (2) | |
Similar Documents at Hatch | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20210B8151986-02-0303 February 1986
[Table view]LERs 85-048,85-049 & 85-051 Have Been Canceled 05000366/LER-1984-001, Revised LER 84-001-01:on 840203,plant Personnel Detected Fracture in 66-inch Vent Header in Bay 5.Caused by Brittle Fracture of Vent Header Matl.Vent Header Will Be Repaired Prior to Startup1984-03-21021 March 1984 Revised LER 84-001-01:on 840203,plant Personnel Detected Fracture in 66-inch Vent Header in Bay 5.Caused by Brittle Fracture of Vent Header Matl.Vent Header Will Be Repaired Prior to Startup 05000366/LER-1983-040, Updated LER 83-040/03X-1:on 830709 & 14,control Rod Drive Low Pressure or High Level Alarm Received for HCV 2C11-26-31 & 02-29.Caused by Leaking EP-111 Nitrogen Charging Valves. Valves Replaced & HCVs Returned to Svc1984-03-12012 March 1984 Updated LER 83-040/03X-1:on 830709 & 14,control Rod Drive Low Pressure or High Level Alarm Received for HCV 2C11-26-31 & 02-29.Caused by Leaking EP-111 Nitrogen Charging Valves. Valves Replaced & HCVs Returned to Svc 05000366/LER-1983-055, Updated LER 83-055/03X-1:on 830713 & 21,RCIC Pump 2E51-C002 Would Not Deliver 600 Gpm Required Tech Spec Flow.Caused by Unadjusted Electric Governor Remote Actuator.Actuator Adjusted.W/Amended1983-12-0505 December 1983 Updated LER 83-055/03X-1:on 830713 & 21,RCIC Pump 2E51-C002 Would Not Deliver 600 Gpm Required Tech Spec Flow.Caused by Unadjusted Electric Governor Remote Actuator.Actuator Adjusted.W/Amended 05000366/LER-1983-126, Amended LER 83-126/03L-0:on 831113,safety Relief Valve Tailpipe Temp Recorder 2B21-B614 Observed Stamping Erratically.Caused by Component Failure.Advancing Mechanism, Solenoid & Arm & Hub Assembly Replaced1983-12-0505 December 1983 Amended LER 83-126/03L-0:on 831113,safety Relief Valve Tailpipe Temp Recorder 2B21-B614 Observed Stamping Erratically.Caused by Component Failure.Advancing Mechanism, Solenoid & Arm & Hub Assembly Replaced 05000366/LER-1983-127, Amended LER 83-127/03L-0:on 831108,while Pumping Water from Drywell Equipment Drain Sump,Pump Discharge Valve 2G11-F018 Would Not Open.Sys Declared Inoperable.Caused by Blown Fuse in Valve Control Circuit1983-12-0505 December 1983 Amended LER 83-127/03L-0:on 831108,while Pumping Water from Drywell Equipment Drain Sump,Pump Discharge Valve 2G11-F018 Would Not Open.Sys Declared Inoperable.Caused by Blown Fuse in Valve Control Circuit 05000366/LER-1983-099, Updated LER 83-099/03X-1:on 830925 & 1005,hydrogen Dioxide Analyzer a Declared Inoperable During Procedure HNP-2-3882 & Out of Calibr,Respectively.Caused by Worn Diaphragms in Sample Pump a & Instrument Drift1983-10-28028 October 1983 Updated LER 83-099/03X-1:on 830925 & 1005,hydrogen Dioxide Analyzer a Declared Inoperable During Procedure HNP-2-3882 & Out of Calibr,Respectively.Caused by Worn Diaphragms in Sample Pump a & Instrument Drift 05000366/LER-1982-068, Updated LER 82-068/03X-1:on 820707 & 24,volumetric Weighted Average Drywell Air Temp Exceeded Tech Spec Limit of 135 F. Caused by High Ambient Temp & Failure of Alternate Chiller Fans 8B & 9B.New Chilling Units Installed1983-10-26026 October 1983 Updated LER 82-068/03X-1:on 820707 & 24,volumetric Weighted Average Drywell Air Temp Exceeded Tech Spec Limit of 135 F. Caused by High Ambient Temp & Failure of Alternate Chiller Fans 8B & 9B.New Chilling Units Installed 05000366/LER-1980-096, Updated LER 80-096/03X-2:on 800619 & 27,w/reactor Mode Switch in Run,Reactor Bldg to Torus Vacuum Breaker Isolation Valve Failed to Open.Caused by Failure of D-P Switch to Actuate.Switch Replaced1982-12-23023 December 1982 Updated LER 80-096/03X-2:on 800619 & 27,w/reactor Mode Switch in Run,Reactor Bldg to Torus Vacuum Breaker Isolation Valve Failed to Open.Caused by Failure of D-P Switch to Actuate.Switch Replaced 05000366/LER-1980-124, Updated LER 80-124/03X-1:on 800813 & 27,during Surveillance of Torus/Drywell Vacuum Breakers,J & I Breakers Failed to Give Proper Light Indication.Caused by Air Control Valves Being Out of Adjustment.Valves Adjusted & Breakers1982-12-16016 December 1982 Updated LER 80-124/03X-1:on 800813 & 27,during Surveillance of Torus/Drywell Vacuum Breakers,J & I Breakers Failed to Give Proper Light Indication.Caused by Air Control Valves Being Out of Adjustment.Valves Adjusted & Breakers Tested 05000321/LER-1979-082, Updated LER 79-082/03X-2:on 790825-27,attempt to Perform RCIC Pump Operability Procedure Unsuccessful When Turbine Failed to Trip Upon Manual Signal.Caused by Burned Out Turbine Trip Actuator Coils & Binding Assembly1982-11-23023 November 1982 Updated LER 79-082/03X-2:on 790825-27,attempt to Perform RCIC Pump Operability Procedure Unsuccessful When Turbine Failed to Trip Upon Manual Signal.Caused by Burned Out Turbine Trip Actuator Coils & Binding Assembly 05000321/LER-1981-120, Updated LER 81-120/01T-1:on 811105,AE Advised That in Event of Main Steamline Break or Scram Discharge,Isolation of HPCI & Reactor Core Isolation Cooling Sys Could Occur.Caused by Erroneous Analysis.Event Would Not Occur1982-08-0303 August 1982 Updated LER 81-120/01T-1:on 811105,AE Advised That in Event of Main Steamline Break or Scram Discharge,Isolation of HPCI & Reactor Core Isolation Cooling Sys Could Occur.Caused by Erroneous Analysis.Event Would Not Occur ML20147H5271978-12-20020 December 1978 /03L-0 on 781207:during Normal Oper & Performance of Procedure HNP-2-3307,HPCI Steam Line Flow Ft&C Switch 2E41-N004 Was at -217 in Water,Due to Instru Drift ML20147H5671978-12-20020 December 1978 /03L-0 on 781210:w/reactor in Run Mode,During Weekly Calibr Check HNP-2-3604,2N62-N009B Was Found Inoper, Due to Bad Hydrogen Sensor ML20147H5131978-12-20020 December 1978 /03L-0 on 781208:during Steady State Oper,During Procedure HNP-2-3410,2E51-N017 Would Trip at -116 of Water for Low Setpoint & 111.9 of Water at High Setpoint,Due to Instru Drift ML20147H4781978-12-20020 December 1978 /03L-0 on 781210:noted That 2B21-N017C Tripped at 37.7 Inches of Water Decreasing.Caused by Instru Drift ML20062G3171978-12-18018 December 1978 /03L-0 on 781130:refueling Floor Vent Exhaust sensor(D11-N012C)gave False High Indication.Caused by Sensor Mounted in Such a Way as to Allow Rain Water to Enter ML20147H5591978-12-18018 December 1978 /03L-0 on 781205:w/reactor in Run Mode During Special Inspec of 3-hour Fire Barriers,A Manila Rope Was Found Thru Fire Seal of Cable Tray 2BHA902 in the RPS M.G. Set Room,Due to Constr Personnel Error ML20062G2991978-12-18018 December 1978 /03L-1 on 780710:shock Suppressor RHRH-229 Found to Be Low on Fluid.Caused by Leaking O Ring Seal ML20147C2781978-12-11011 December 1978 /03L on 781121:failure to Submit RO 50-366/78-55 W/In 30 Days.Caused by Deviation Rept 2-78-79 Not Received by Responsible Dept Head Nor Superintendent of Plant Engr Svcs.Personnel Were Reminded of Procedures ML20062F3991978-12-0909 December 1978 /03L-0 on 781027:severe Arcing at Exciter Collector Ring of B31-S001A Trippingamg Set Causing Ring & Brushes to Burn.Caused by Bolts Used to Fasten Brush Holders to Yoke Assembly Having Insufficient Length ML20147C2981978-12-0909 December 1978 /03L-0 on 781203:settings Found at 1090 Psig on Turbine Control Valve Fast Closure Oil Pressure Low Trip Switches 2C71-N005A & 2C71-N005B.Tech Specs Req 1100psig. Caused by Instru Drift ML20147C2531978-12-0808 December 1978 /03L-0 on 781204:in Run Mode,Both Secondary Containment Doors on the 130 Ft El Were Opened at the Same Time Due to Personnel Error.Incident Presented No Hazards. Personnel Were Reminded of Proper Procedure ML20147C1471978-12-0101 December 1978 /03L-0 on 781117:during Reactor Water Level Test & Calibr HND-2-5281,2B21-NO25A Failed to Meet Acceptance Criteria Due to Mech Failure of Instru.Caused by Binding of Pointer Shaft Inits Bushing on Low End of Scale ML20147C1941978-12-0101 December 1978 /03L-0 on 781117:procedure HNP-2-3003 Was Not Completed W/In Specified Interval Per Tech Specs 4.3.1.1(4) for Instru 2B21-N017D.Caused by Personnel Repairing 2 Other Instru & Procedure Had to Be Stopped Due to Repairs ML20147C2621978-11-28028 November 1978 /03L-1 on 780724:average Drywell Temp Exceeded Limit of 135F as Set Forth in Tech Specs 3.6.1.7.Caused by Stratification of Air Temp in Drywell ML20147C2071978-11-22022 November 1978 /03L-0 on 781109:suppression Chamber Drywell Vacuum Breakers Were Not Demonstrated Operable W/In Tech Spec Time Limit Due to Personnel Error ML20147C3341978-11-22022 November 1978 /03L-0 on 781115:procedure HNP-2-5202 Took Over 2 Hours Because 2B21-NO17C Could Not Be Calibr.Instru Was Replaced ML20062F4021978-11-20020 November 1978 /03L-0 on 781120:during NRC Audit It Was Found That RHR Time Delay Relay E11-K126 Had Been Left in Uncalibrated State from 780412 to 780627.Redundant Relays E11-K125 a & B Were Functioning.Procedures Will Be Rev ML20062D6471978-11-20020 November 1978 /03L-0 on 781109:during Normal Oper Core Drills Were Made Thru Diesel Generator Room Walls to Allow Conduit to Be Run Thru Walls.Fire Watch Established Per Tech Specs ML20148P4151978-11-20020 November 1978 /03L-0 on 781102:reactor Maximum Cooldown Rate of 100 Degrees F Exceeded During Reactor Auto Scram & Vessel Depressurization.Caused by Personnel Error;Personnel Have Been Admonished ML20197D4151978-11-20020 November 1978 /01T-0 on 781109:suppression Chamber to Drywell Vacuum breaker(2T48-F323I)inoperable.Caused by mis-interpretation of Tech Specs ML20062D3251978-11-15015 November 1978 /03L-0 on 781101:a Main Steam Line Radiation Monitor (D11-K603D) Failed to Initiate a Half Scram During a Test.Caused by a Loose Wire Which Had Damaged Some Components ML20062D3561978-11-14014 November 1978 /03L-0 on 781031:surveillance of Fire Protec Equip & Circuitry(Procedures HNP-1-3356 & HNP-1-3360)had Been Neglected Due to Personnel Oversight.Importance of Fire Detector Surveillance Reemphasized to Personnel ML20197C9091978-11-14014 November 1978 /03L-0 on 781031:during Procedure HNP-2-10531 & Reactor in Run Mode,The 2R43-S001 C Diesel Failed to Reach 250 RPM W/In 7 Seconds,Due to Faulty Elec Speed Switch Signal ML20062D3151978-11-13013 November 1978 /03L-0 on 781028:at 95% Rated Pwr,Lprm Calibr OD-1 Was Performed,Changing Cmflpd from 0.97 to 1.004.Flow Was Reduced After Which Peak LHGR Was Reduced to 99% of Its Limit.Caused by Inaccurate Base Distrib in Computer ML20197D0911978-11-0909 November 1978 /03L-0 on 781026:32 Instru Discovered as Having Exceeded Calibr Interval.Caused by Failure of Personnel to Maintain Accurate Calibr Records.Personnel Admonished & Procedures Rev ML20197D1651978-11-0808 November 1978 /03L-0 on 781029:during Scram 2-78-14,2B21-NO24A Instru Switch 2 Failed to Actuate at Setpoint 111.6+/-3.6 Inches.Cause:Magnet on 2 Switch Had Metal Shavings on It. Instru Cover Was Loose & Shavings Entered Instru ML20197C9411978-11-0707 November 1978 /01T-0 on 781101:dimensions of Condensing Pots 2B21-D004 a & B Were Found to Be Installed Per Design Causing RCIC & HPCI High Level Trips to Exceed Tech Spec ML20150C1851978-11-0303 November 1978 /03l-0 on 781027:while Performing Procedure HNP-2-10315,2E41-F001 Valve Failed to Oper During HPCI Quick Start.Caused by Motor Shunt Field Insulation Failure ML20150C1991978-11-0202 November 1978 /03L-0 on 781018:hose Stations Were Not Inspected as Req by Tech Spec.Caused by Changeover in Procedures, Resulting in Oversight.Personnel Instructed & New Procedures Implemented ML20062C7941978-11-0202 November 1978 /03l-0 on 781022:severe Arcing Observed at Exciter Collector Ring of B31-S001A.A M.G. Set Tripped Before It Could Be Removed from Svc.Bolts Used to Fasten Brush Holders to Yoke Assembley Caused Brushes to Arc ML20197C0191978-10-27027 October 1978 /03L-0 on 781017:during Startup Testing While Calibrating APRM High Flux Scram Setpoints,Discerned That Trip Setpoints Were Set in Excess of Reg Guide Criteria. Caused by Deficiency in Procedures ML20062G2791978-06-30030 June 1978 /03L-1 on 780609:procedure HNP-1-3902,Safety Relief Valve Functional Test Tried Unsuccessfully on 2 Solenoids.One Failed Due to Bent Plunger;Other Failure Due to Plunger Not Properly Secured to Actuating Springs 1986-02-03 Category:TEXT-SAFETY REPORT MONTHYEARML20217D3061999-10-13013 October 1999
[Table view]SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.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 ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207E7631999-06-0303 June 1999 Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable HL-5795, Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with ML20206G1691999-05-0404 May 1999 SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii) HL-5784, Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5766, Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207M1891999-03-11011 March 1999 SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld HL-5755, Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20206P6981999-01-0707 January 1999 Ehnp Intake Structure Licensing Rept HL-5726, Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20196J4931998-12-0707 December 1998 Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15 HL-5714, Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5706, Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With ML20155B6121998-10-28028 October 1998 Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20238F7131998-08-31031 August 1998 9,change 2 to QAP 1.0, Organization HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5640, Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20248B8651998-05-15015 May 1998 Quadrennial Simulator Certification Rept HL-5628, Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant1998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant HL-5604, Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20216B2711998-02-28028 February 1998 Extended Power Uprate Safety Analysis Rept for Ei Hatch Plant,Units 1 & 2 HL-5585, Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5571, Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 11998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 1 HL-5551, Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20199B0561997-12-31031 December 1997 Rev 0 GE-NE-B13-01869-122, Jet Pump Riser Weld Flaw Evaluation Handbook for Hatch Unit 1 HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997 Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2 HL-5533, Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5514, Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20212A1981997-10-16016 October 1997 Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H5311997-10-0101 October 1997 Rev 2 to Unit 1,Cycle 17 Colr ML20211H5251997-10-0101 October 1997 Rev 3 to Unit 1,Cycle 17 Colr 1999-09-30 |
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