ML20087A638
| ML20087A638 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/28/1984 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 27328, NUDOCS 8403080171 | |
| Download: ML20087A638 (16) | |
Text
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@ Consumers Power James W. Cook l
lll VicePresident Projects. Engineering and Construction General of fices: 1945 West Parnall Road, Jack son, MI 49201 + (517) 788-0453
/PRl:!C! PAL STAFF jn%[Wl February 28, 1984 v
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Mr J G Keppler, Regional Administrator Q_.
ENF i-US Nuclear Regulatory Commission Region III 799 Roosevelt Rond Glen Ellyn, IL 60137 MIDLAND NUCLEAR C0 GENERATION PLANT -
DOCKET NOS. 50-329 AND 50-330 ITEMS FOR NRC CLOSURE FILE 0.4.2 SERIAL 27328 In accordance with your request, we are submitting the attached list of items which have been reviewed by CP Co and have been determined to be ready for review and closure by the NRC.
This is a complete list which includes the items that were transmitted on October 4,1983 that have not been closed subsequent to that time. The items marked with an asterisk (*) have been reviewed by the Region III Inspectors and will be removed from the list when closed in an inspection report.
CC WRBird, P-14-418A DMBudzik, P-24-517A RCook, NRC-Midland JFFremeau, Midland JHarrison, NRC JNLeech, P-24-507 DLQuamme, Midland JARutgers, Bechtel-AA
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RAWells, Midland REWhitaker, Midland 8403000171 840220 MAR 2 1984 gonAo0cK05000 OC0284-0001A-QLO2 I
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NRC inh ection' Report Items p
1 Miscellaneous-Items Ready For Closure 1)r je Subj ect Closure Location Item y
79-12-05 Unresolved Pressure Test of' Pressurizer Relief Valve Site 80-09-01 Deficiency Leveling of Internal Core Support Structure Site
- 80-30/31-01 Unresolved Battery Rack Acidic Environment Site 81-12-09/10 Violation Lack of Approved Procedures Covering Rework Site 81-20-01 Unresolved Cable Tray Dividers Site 82-05 Deviation QA Staffing Site l
82-06-02 Violation Cable Pulling Site 82-18-02/01 Violation Dewatering Fines Monitoring Site 82-1s-03/02 Violation Slope Layback Site 82-20-01 Open Training of RMS Personnel for Emergency Procedures and Training of Crafts Site 83-03-02 Unresolved Expansion of Excavation Permit System to Underpinning Site 83-13/14-03 Deviation Slope Layback in the Drifts Site MIO284-0001A-QLO2 2/23/84 Page 1 of 3 I
.. --j NRC In piction Report Items
. Items Dealing With Hanger Design The following items all were-' initiated 'by I Yen, 'and need to be resolved by a scheduled trip to Ann Arbor
.with a possibility of going to ITT Grinnell in Providence ~.
-Item Tm Subject Closure Location
/8-19-02 URI
-Locking Devices on Bolts used in ITT Grinnel Ann Arbor l
78-19-03 URI ITT Grinnell Evaluation of Bolt Holes Near Edge of Plate Ann Arbor 79-01-02 URI Adequacy of Drawing Hanger Review Ann Arbor 79-05-02 URI' Additional reviews of ITT Hanger Design Ann Arbor or Providence 79-05-03 URI.
Bechtel' System for Design Interface of Hanger Loadings on Existing Structures Ann Arbor 80-11/12-01 URI Bolted Joints Ann Arbor 82-07-01 URI Review of Other Disciplines for Handling of 4
CPDC's Ann Arbor l
l MIO284-0001A-QLO2 2/23/84 Page 2 of 3
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Bulletina - Circulars - Notices Ready For Closure Faulty Overcurrent Trip Delay Device in Circuit Breakers for Engineered Safety Systema
' BULLETIN 73-01 "BUT.LETIN 74-01 Valve Deficiencies
' BULLETIN 74-06 Defective Westinghouse Type W-2 Control Switch Component
' BULLETIN 74-08 Deficiency in ITE Molded Case Circuit Breakers Type,HE-3
- BULLETIN 74-09 Deficiency in General Electric Model 4kV Magna-Blast Breakers Incorrect Coils.in Westinghouse Type SC Relays at Trojan
' BULLETIN 74-12 l
- BULLETIN 74-15 Misapplication of Cutler-Hammer Three Positioned Maintained Switch, Model 10250T Improper Machining of Pistons in Colt Industries (Fairbanks-Morse) Diesel Generators BULLETIN 74-16 Atypical Wald Material in Reactor Pressure Vessel Welds BULLETIN 78-12 Potential Misapplication of Rosemount Inc Models 1151 and 1152 Pressure Trans-BULLETIN 80-16 mitters with either "A" or "D" Output Codes.
4 BULLETIN 82-01 Alteration of Radiographs of Welds in Piping Assemblies.
Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless Steel, BULLETIN 82-03 Recirculation System Piping at BWR Plants.
Deficiencies in Primary Containment Penetration Assemblies.
BULLETIN 82-04 Stress Corrosion Cracking in Large Diameter Stainless Steel Recirculation BUI.LETIN 83-02
-System Piping at BWR Plants.
CIRCULAR 76-01 Crane Holst Control Circuit Modifications Hydraulic Shock and Sway Suppressors Maintenance of Bleed and Locking on CIRCULAR 76-05 ITT Grinnell's Model Number Figure 200 and 201 Catalog PH-74-R RP1083-00ll-MG04
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' CIRCULAR 02
' Potential Heavy Spring Flooding CIRCULAR 77-06 Effects of Hydraulic Fluid on Electrical Cables 3
CIRCULAR 78-05 Inadvertent Safety Injection.during Cooldown
'CIkCULAR 78-13 Inoperability of Multiple Service Water Pumps CIRCULAR 78-15 Check Valves Fail to Close in Vertical Position CIRCULAR 79-05 Hoisture Leakage in Stranded Wire Conductors CIRCULAR 79-11 Design / Construction Interface CIRCULAR 79-12 Potential Diesel Generator Turbocharger Problem, j
CIRCULAR' 80-16 Operational Deficiency on Rosemount Model 510DU Trip Units and i
Model 1152 pressure Transmitters CIRCULAR 80-17 Fuel Pin Damage to Water Jet from Baffle Plate Corner g
CIRCULAR 80-21 Regulation of Refueling Crews 4
CIRCULAR 81-05 Self-Aligning Rod End Bushings for Pipe Supports f
CIRCULAR 81-06 Potential Deficiency Affecting Certain Foxboro 10 to 50 M1111 ampere Transmitters i
CIRCULAR 81-07 Control of Radioactively Contaminated Material i
CIRCULAR 81-08 Foundation Materials I
J CIRCULAR 81-09 Containment Effluent Water Heat Bypasses Radioactivity Monitor CIRCULAR' 81-11 Inadequate Decay lleat Removal During Reactor Shutdown i
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I CIRCULAR 81-12 Inadequate Periodic Test Procedure of PWR Protection System CIRCULAR 81-14 Main Steam Isolation Valve Failures to Close NOTICE 79-06 Stress Analysis of Safety-Related Piping NOTICE 79-09 Spill of Radioactively Contaminated Resin NOTICE 79-11 Lover Reactor Vessel Head Inaulation Support Problem
. NOTICE 79-12 Attempted Damage to New Fuel Assemblies NOTICE 79-13.
Indication of Low'Watee Level in the Oyster Creek Reactor (BWR)
J NOTICE 79-16 Nuclear Incident at Three Mile Island NOTICE 79-17 Source Holder Assembly. Damage from Misfit between Asser.bly and Reactor Upper Crid Plate (Westinghouse Units only)
NOTICE 79-18 Skylab Reentry L
NOTICE 79-28 Overloading of Structural Elements due to Pipe Support Loads NOTICE 79-29 Loss or hansarety-nelated Keactor coolant system tua t t umuu 6 6.
during Operation.
NOTICE 79-32 Separation of Electrical Cables for HPCI and ADS (BWR only)
NOTICE 79-37 Cracking in Low Pressure Turbine Discs NOTICE 80-04 BWR Fuel Exposure in Excess of Limits I
NOTICE 80-06 Notification of Significant Event and Supplement RP1083-00ll-MC04
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NOTICE 80-17 Potential Hszards Associated with Interchangeable Parts on Radiographic l
Equipment NOTICE 80-20 Loss of Decay Heat Removal Capability at Davis-Besse Unit'I while in Refueling Mode NOTICE 80-22.
Breakdowns in Contamination Control Programs J
NOTICE 80-23 Loss of Suction to Emergency Feedwater Pumps NOTICE 80-24 Low Level Radioactive Waste Burial Criteria NOTICE 80-25 Transportation of Pyrophoric Uranium NOTICS 80-27 Degradation of Reactor Coolant Pump Studs NOTICE 80-29 Broken Studs on Terry Turbine Steam Inlet Fla. ige NOTICE 80-30 Potential for Unacceptable Interaction between the Control Rod Drive Scram Function and Nonessential Control Air at Certain C E BWR Facilities NOTICE 80-33 Determination of Teletherapy Timer Accuracy NOTICE 80-35 Leaking and dislodged Iodine-125 Implant Seeds NOTICE 80-37 Containment Cooler Leaks and Reactor Cavity Flooding at Indian Point 2 NOTICE 80-45 Potential Failure of BWR Backup Manual Scram Capability NOTICE 81-02 Transportation of Radiography Devices NOTICE 81-04 Cracking in Main Steam Lines NOTICE 81-06 Failure of ITE Model K-600 Circuit Breaker RP I OR'l-0011 -MG04
D NOTICE 81-07 Potential Problem with Water Soluble Purge Das Materials used during
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Inert Gas Welding NOTICE 81-08 Repetitive Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key NOTICE 81-10 Inadvertent Containment Spray due to Personnel Error i
NOTICE 81-11 Alternate Rod Insertion for BWR Scram Represents a Potential Path for Loss of Primary. Coolant.
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l Guidance on Order Issued January 9, 1981, Regarding Automatic Control Rod NOTICE 81-12 Insertion on Low Control Air Pressure (BWR only).
i NOTICE 81-13 Jammed Source Rack in a Gamma Irradia'or c
NOTICE 81-14 Potential Overstress of Shafts on Fisher Series 9200 Butterfly Valves with Expandle T-Rings NOTICE 81-15 Degradation of' Automatic ECCS Actuation Capability by Isolation of Instrument Lines.
g NOTICE 81-16 Control Rod Drive System Malfunction (BWR only)
NOTICE 81-17 Never Issued i
NOTICE 81-18 Excessive Radiation Exposute to Fingers NOTICE 81-19 Lost Psrts in Primary Coolant System NOTICE 81-20 Test Failures of Electrical Penetration Assemblies NOTICE 81-21 Potential Loss of Direct Access to Ultimate Heat Sink Section 235 and 236 Admendments to the Atomic Energy Act of 1954 NOTICE 81-22 RPf081-0011-MG04
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NOTICE 81-23,
Fuel Assembly Damage due to Improper Positioning of Fuel Handling Equipment
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AFW Pump Turbine Bearing Failures'
' NOTICE
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NOTICE 81-26.
Cor.p11ation of Hedith Physics Related Informatfon Items '. -
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- NOTICE
.81-27
', Flammable cas Mixtures in* the, Waste Decay Tanks'in BWR. Plants.
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NOTICE 81-28.'
Failure of Rockwell-Elward Main Steam Isolation Valves Ye
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NOTICE 81-29 Equipment Qualificatien Testing Experience
' NOTICE 81-30
. Velan Swing Check Valves f:
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Failure of Safety Injection Va14 m to Operate Against r
NOTICE 81-31
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L Ditferential Pressure.
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NOTICE 81-32 Transfer and/or Disposal of Spent Generators Lecking Devices Inadequately Installed on Main Steam Isolation Valves NOTICE 81-33 L
NOTICE 81-34 Accidental Actuation of Prompt Public Notification Syerem
-rj NOTICE 81-35 Check Valve Failures NOTICE 81-36 Replacement Diaphrams for Robertshaw Valve (Model No VC-210)
NOTICE 81-37 Unnecessary Radiation Exposure to Public and Workers during Events Involving Thickness and Limit Measuring Devices.
F NOTICE 81-38 Potentially Significant Equipment Failures Resulting from Contamination of Air-Operated Systems EPA Crosscheck Program Low-Level radioiodine in Water Intercomparison Study NOTICE 81-39 RP1083-00ll-MG04
j NOTICE 82-01 AFW Pump Lockout Resulting from Westinghouse W-2 Switch Circuit Hodification Westinghouse NBFD Relay Failures in Reactor Protection Systems at Certain Nuclear NOTICE 82-02 Power Plants l
' NOTICE 82-03
' Environmental Tests of Electrical Terminal Blocks I
Potential deficiency of'Certain Agastat E-7000 Series Time Delay Relays NOTICE 82-04 NOTICE 82-05 Increasing Frequency of Drug-Related Incidents 1
NOTICE.
82-07 Inadequate Security Screening Programs NOTICE 82-09 Cracking in Makeup Coolant Lines at B&W Plants NOTICE 82-10 Following Up Symptomatic Repairs to Assure Resolution of the Problem Potential Inaccuracies in Wide Range Pressure Instruments Used in Westinghouse NOTICE 82-11 Designed Plants NOTICE 82-12 Surveillance of Hydraulic Snubbers NUTICE 82-13 Failure of General Electric Type HFA Relays Notification of Nuclear Regulatory Commission (NRC)
NOTICE 82-15 NOTICE 82-16 HPC1/RCIC High Steam Flow Set Points Assessment of Intakes of Radioactive Materials by Workers NOTICE 82-18 Loss of High Head Safety ' Injection Emergency Boration and Reactor Coolant NOTICE 82-19 Makeup Capability NOTICE 82-20 Check Valve Problems RP1083-0011-MG04
C P ~ CE 82-21 Buildup of Enriched Uranium in Effluent Treatment Tanks NOTICE 87-22 Failures in Turbine Exhaust Lines
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NOTICE 82-23 Main Steam Isolation Valve Leakage l
l NOTICE 82-24 Water Leakage from Uranium Hexafloride Overpacks l
NUTICE 82-26 RCIC and HPC1 Turbine Exhaust Check Valve Failure (BWR only)
NOTICE 82-27 Fuel Rod Degradstion Resulting from Water-Jet Baffle Impingement NOTICE 82-28 Hydrogen Explosion while Grinding in Vicinity of Drained and Open RCS NOTICE 82-29 Control Rod Drive (CRD) Guide Tube Support Pin Failures at Westinghouse PWR (Westinghouse Plant's only)
NOTICE
$2-30 Loss of Thermal Sleeves in RCS Piping at Certain Westinghouse PWR Plants NOTICE 82-31 Overexposure of Diver during Work in Fuel Storage Pool
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Control of Radiation Levels in Unrestricted Arena Adjacent to Brachytherapy NOTICE 82-33 Patients (Medical Institutions only)
NOTICE 82-35 Failures of Three Check Valves on HP1 Lines to Pass Flow l
NOTICE 82-36 Respirator Users Warning for certain 5-Minute Emergency Es: ape Self-Contained Breathing Apparatus NOTICE 82-37 Cracking in the Upper Shell to Transition Cone Girth Weld af a Steam Generator on an Operating PWR NOTICE 82-38 Change in Format and Distribution System for IE Bulletins. Circulars and Information Notices RP1083-00ll-HC04
NOTICE 82-39 Service Degradation of Thick Wall Stainless Steel Recirculation System.
Piping at BWRs NOTICE 82-40 Deficiencies in Primary Containment Electrical Penetration Assemblies l
NOTICE 82-41 Failure of Safety Relief Valve to Open at a BWR NOTICE 82-42 Defects Observed in Panasonic Model 801 and Model 802 Thermoluminiscent Dosimeters NOTICE 82-43 Deficiencies in LWR Air Filtration / Ventilation Systeam NOTICE 82-44 Clarification of Emergency Plan Exercise Requirements NOTICE 82-45 PWR Low' Temperature Overpressure Protection NOTICE 82-46 Defective and Obsolete Combination Padlocks NGTICE 82-51 Overexposure in PWR Cavities Equipment Environmental Qualification Testing Experience - Update of NOTICE 82-52 Test Summaries Previously Issued in IN 81-29 NOTICE 82-54 Westinghouse NBFD Relay Failures in Reactor Protection Systems NOTICE 82-55 Seismic Qualification of Westinghouse AR Relay with Latch Attachment used in Westinghouse Solid-State Protection System.
NOTICE 83-01
!!ay Miller, Inc.
NOTICE S3-07 Ncnconformities with Materials Supplied by Tube-Line Corp NOTICE 83-09 Safety and Security of Irradiators NOTICE 83-12 Incorrect Boron Standards RPIO83-00ll-MG04
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NOTICE 83-13 Design Misepplication of Bergen Patterson Standard Strut Restraints NOTICE 83-14 Dewatered Spent Ion Exchange Resia Susceptability to Exothermic Chemical Reaction NOTICE 83-15 Falsified Pre-Employment Screening Records a
NOTICE 83-16 Contamination of Auburn Steel Company with Cobalt-60 NOTICE 83-20 ITT Crinnel Figure 306/307 Mechanical Snubber Attachment Interferences l
NOTICE 83-21 Eefective Emergency Use Respirators NOTICE 83-22 BWR Safety / Relief Valve Failures NOTICE 83-26 Failure of Safety / Relief' Valve Diecharge Line Vacuum Breakers 4
NOTICE 83-29 Fuel Binding Caused by Fuel Rack Deformation NOTICE 83-32 Rupture of Americium-241 Source (s) Contained in Well Logging Device t
NOTICE 83-34 Event Notification Information Worksheet NOTICE 83-35 Fuel Movement with Control Rods Withdrawn Transformer Failure Resulting from Degraded Internal Connection Cables NOTICE 83-37 NOTICE 83-39 Failure of' Safety / Relief Valves to Open at a BWR - Interim Report NOTICE 83-42 Reactor Mode Switch Malfunction Potential Damage to Redundant Safety Equipment as a Result of Backflow through the NOTICE 83-44 Equipment and Floor Drain System NOTICE 83-52 Radioactive Waste Gas System Events 1
RP1083-00ll-MC04
NOTICE 83-53 Primary Containment Isolation Valve Discrepancies NOTICE 83-54J Common Node Failure of Main Steam Isolation Nonreturn Check Valves NOTICE 83-55 Misapplication of Valves by Throttling beyond Design Range NOTICE 83-59 Dose Assignment for Ubrkers in Non-Uniform Radiation Fields NOTICE 83-60 Falsification of Test Results for Protection Coatings NOTICE 83-61 Alleged Use of Stand-Ins for Welder Qualification Tests NOTICE 83-62 Failure of Redundant Toxic Cas Detectors Positioned at Control Room Ventilation Air Intakes Potential Failure of Westinghouse Electric Corp Type SA-1 Differential Relays NOTICE 83-63 NOTICE 83-64 Lead Shielding Attached to Safety-Related Systems without 10CFR50.59 Evaluations L
NOTICE 83-66 Fatality ac Argentine Critical Facility NOTICE 83-67 Emergency Use Respirator Material Defect Causes Production of Noxious Cases Respirator User Warning - Defective Self-Contained Breathing Apparatus Air Cylinders NOTICE 83-68 NOTICE 83-73
' Radiation Exposure from Cloves Contaminated with Uranium Daughter Products.
NOTICE 83-74 Rupture of Cesium-137 Source used in Well-Logging Operations NOTICE 83-80 Use.of Specialized " Stiff" Pipe Clamps NOTICE 83-82 Failure of Safety Relief Valves to Open at BWR - Formal Report RP1083-00ll-MG04
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