AO 50-267/74/1:on 740114,during Initial Fuel Loading,Six Alignment Dowel Pins Found Cracked or Chipped & Fuel Plugs out-of-spec.Caused by Mfg & Shipment Handling Errors.Dowel Pins & Plugs Replaced Using Ga Co ProceduresML20086E282 |
Person / Time |
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Site: |
Fort Saint Vrain ![Xcel Energy icon.png](/w/images/6/6c/Xcel_Energy_icon.png) |
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Issue date: |
01/14/1974 |
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From: |
Swart F PUBLIC SERVICE CO. OF COLORADO |
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To: |
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Shared Package |
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ML20086E229 |
List: |
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References |
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AO-50-267-74-1, NUDOCS 8312060444 |
Download: ML20086E282 (7) |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20086B1731976-11-0909 November 1976 AO 50-267/74-20A:on 741116,during Low Power Physics Testing, Conflict Found Between Tech Specs 4.2.11 & 4.4.1 Re Moisture Limits.Caused by Last Minute Change in Tech Specs 4.2.11. Tech Specs Revised ML20086B1781976-11-0909 November 1976 AO 50-267/74-20A:on 741116,during Low Power Physics Testing, Conflict Found Between Tech Specs 4.2.11 & 4.4.1 Re Moisture Limits.Caused by Last Minute Change to Tech Specs 4.2.11. Tech Specs Revised ML20086B1001976-09-0303 September 1976 AO 50-267/74-21C:on 741121,high Pressure in Gas Waste Vacuum Tank Lifted Relief Valve Allowing Release of 700 Scf Uncontaminated Gas.Caused by Operator Error.Valves Will Be Replaced W/Kerotest Valves & Change Notice 91 Issued ML20086A0441976-05-28028 May 1976 Telecopy AO 76-012:on 760527,helium Circulator 1B Tripped Twice.Caused by Buffer Seal Malfunction.Sys Operating Procedure Will Be Revised ML20086A0691976-05-20020 May 1976 AO 76-011:on 760510,helium Circulator 1C Tripped Due to Negative buffer-midbuffer Differential Pressure.Cause Associated W/Test ML20086A0871976-05-0303 May 1976 Telecopy AO 76-010:on 760429 & 30,circulators 1A & 1B Tripped on Loss of Bearing Water.Caused by Operator Error ML20085M4351976-02-17017 February 1976 Telecopy AO 76/005:on 760227,loss of Essential 480-volt Bus 2 Caused Trip of Three Helium Circulators Due to Circulator Bearing Water Problems.Loss of 480-volt Bus Could Cause Temporary Loss of Forced Circulation ML20085M4731976-02-0606 February 1976 Telecopy AOs 76/03 & 76/04:on 760206,generator Set 1-B Load Breaker Would Not Close & Generator Set 1A Trouble Alarm Received,Indicating Partial Disconnection of Engine 1B from Generator.Causes Not Stated ML20085M5651975-12-22022 December 1975 AO 50-267/74/23A:on 741211,engine a of Standby Diesel Generator 1A Declutched During 2 H Surveillance Run & No Alarm Annunciated.Caused by Dirt Under Seat of Solenoid Valve.Plant Change Notice 12 Initiated ML20085M7181975-12-22022 December 1975 AO 50-267/75/15A:on 750709,during Repair of Minor Oil Leak on Gasoline Engine of Emergency Fire Pump,Inlet Manifold Piping Found Cracked.Caused by Component Failure.Manifold Repaired ML20086B1541975-12-18018 December 1975 AO 50-267/74-7A:on 740424,fuel Handling Machine Failed to Engage & Lift Reflector Element 09-06-R-01.Caused by Mfg Error.Reflectors de-burred & Ga Co Will Supply Two Column 1 Metal Clad Reflector Elements ML20085M5631975-11-18018 November 1975 AO 50-267/75/24:on 751108,static Seal on Helium Circulator B Inadvertently Released.Cause Presently Undetermined. Circulator B Brake & Seal Manually Set ML20085M6211975-10-21021 October 1975 AO 50-267/75/18A:on 750816,during Installation Preparation, Helium Circulation Damaged.Caused by Lack of Adherence to Approved Procedure.Personnel Counseled to Adhere to Approved Procedures & Supervision ML20085M5711975-09-26026 September 1975 AO 50-267/75/23:on 750916,essential Electrical Cable Discovered to Have Failed.Caused by Circumstances Associated W/Work in Progress.Damaged Cable Replaced ML20085M5771975-09-26026 September 1975 AO 50-267/75/22:on 750912,during Gas Waste Routine Release, Trouble W/Gas Vacuum Tank Observed by Reactor Operator.Cause of Malfunction Unknown.Failure Could Not Be Reproduced.No Further Action Planned ML20086B1151975-09-26026 September 1975 AO 50-267/74-21B:on 741121,high Pressure in Gas Waste Vacuum Tank Lifted Relief Valve Allowing Release of 700 Scf Uncontaminated Gas.Caused by Operator Error.Inlet Valve Seats Will Be Replaced W/Soft Seats ML20085M5821975-09-22022 September 1975 AO 50-267/75/21:on 750911,control Rod Drive Inserted Into Pcrv Rotated 180 Degrees from Required Orientation During Control Rod Drive Mod.Caused by Design & Procedure Error. Procedures Modified ML20085M6181975-09-0505 September 1975 AO 50-267/75/19:on 750825,engine a of Standby Generator a Automatically Shut Down & Declutched During Cooldown Portion of Weekly Surveillance Test.Caused by Difference in Fuel Rack Setting.Setting Changed ML20085M6231975-09-0505 September 1975 AO 50-267/75/18:on 750816,during Installation Preparation, Helium Circulator Damaged.Caused by Lack of Adherence to Approved Procedure.Personnel Counseled to Adhere to Approved Procedures & Supervision ML20085M6121975-09-0505 September 1975 AO 50-267/75/20:on 750826,12 Cord Sets Connecting Process Controllers at I-05 & I-06 Control Board to Cable Rack in Auxiliary Electric Equipment Room Switched.Caused by Malicious Mischief ML20085M6781975-08-15015 August 1975 AO 50-267/75/17:on 750808,instrument Air Compressor 1C Observed Running Continuously in Unloaded Condition.Caused by Component Failure.Failed Unloader Actuator Replaced W/New Unloader Actuator & Tested ML20085M7021975-07-21021 July 1975 AO 50-267/75/16:on 750610,when Engine B of Standby Generator a Dissassembled,Broken Rings,Scored Cylinders & Cracked Pistons Found.Caused by Water Engine.Engines Inspected.Pistons,Liners & Rings Replaced ML20085M7251975-07-18018 July 1975 AO 50-267/75/15:on 750709,during Repair of Minor Oil Leak on Gasoline Engine of Emergency Fire Pump Inlet Manifold, Piping Found Cracked.Caused by Component Failure.New Manifold Ordered & Defective Casting Replaced ML20085M7401975-06-11011 June 1975 AO 50-267/75/14:on 750530,engine B of a Diesel Generator Oversped to 1,900 Rpm While Electrical Overspeed Trip Being Set.Caused by Procedure Error.Test Procedure Changed ML20085L6331975-05-27027 May 1975 AO 75-267/75/13:on 750519,I-B Engine of I-A Standby Diesel Generator Failed to Start.Caused by Failure to Transmit Info That Engine Was Out of Svc to Adjust Overspeed Switches ML20085L6481975-05-12012 May 1975 AO 50-267/75/10:on 750501,exam Revealed Pin on Declutching Mechanism of Engine D of Standby Diesel Generator D Sheared Off.Caused by Inadequate Lubrication.Pin Replaced & Lubrication Frequency Increased ML20085L6301975-05-12012 May 1975 AO 50-267/75/9:on 750404,valve HV-2188-8 Did Not Open When Circulator Seal Release Permissive Circuit Directed Valve to Open.Cause Not Stated.Air Solenoids Inspected & Cleaned ML20085L7871975-05-0707 May 1975 AO 50-267/74-25:on 741018,diesel Engine B of Standby Generator a Tripped from High Water Jacket Temp on Routine Test.Caused by Improper Filling of Water Jackets.Personnel Counseled ML20085L6411975-05-0707 May 1975 AO 50-267/75/11:on 750424,preliminary Calculations Indicated That Helium Bottles Supplying Reserve Shutdown Sys Did Not Have Adequate Restraint for Dbe.Cause Not Stated.New Bottle Racks Designed & Installed ML20085L7881975-04-16016 April 1975 AO 50-267/74/24A:on 741222,static Seal on Helium Circulator a Released During Removal of Temporary Jumpers.Caused by Jumper Contact W/Station Ground ML20085L7671975-04-0808 April 1975 AO 50-267/75/3A:on 750123,dew Point Moisture Monitor Failed to Initiate Reactor Scram When Moisture Content Exceeded Trip Setpoint.Caused by Design & Procedure Inadequacies.New Procedure Developed ML20085L6491975-04-0707 April 1975 AO 50-267/75/9:on 750329,leak in Mechanical Seal of Helium Circulator B Discovered.Caused by Foreign Matl on Sealing Surfaces.No Corrective Actions Planned ML20085L6831975-04-0202 April 1975 AO 50-267/75/6A:on 750202,gas Waste Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Improper Closure of Air Operated Drain Valve Due to Foreign Matl on Valve Seat.Seat Repaired ML20086E1651975-03-21021 March 1975 AO 50-267/74/6A:on 750202,gas Waste Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Failure of Air Operated Drain Valve to Close Properly.Valve Repaired & Reinstalled ML20085L7071975-03-14014 March 1975 AO 50-267/75-4-A:on 750125,tritium Leaked from Secondary Closure of Refueling Region 1.Caused by Normal Presence of Tritium in Pressurizing Gas ML20085L6511975-03-0707 March 1975 AO 50-267/75/8:on 750224,diesel Engine B of Standby Generator a Failed to Function Properly During Weekly Test. Caused by Defective Temp Thermocouple.New Thermocouple Installed & Preventive Maint Program Instigated ML20085L6581975-03-0404 March 1975 AO 50-267/75/7:on 750121-23,reactivity Anamoly Occurred Due to Release of Hopper of Reserve Shutdown Mall Into Core. Cause Not Stated.Valve Seats Modified ML20086B0681975-02-26026 February 1975 AO 50-267/74-22A:on 741129,high Pressure in Gas Waste Vacuum Tank Blew Rupture Disc & Lifted Relief Valve Allowing Release of 750 Scf Uncontaminated Gas.Caused by Design Inadequacy.Pressure Indicator Installed ML20085L6851975-02-18018 February 1975 AO 50-267/75/6:on 750202,gas Waste Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Improper Closure of Air Operated Drain Valve.Valve Will Be Disassembled for Insp ML20085L7011975-02-17017 February 1975 AO 50-267/75/5:on 750127,gas Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Inadequate Procedures.Procedure Rewritten ML20085L7121975-02-14014 February 1975 AO 50-267/75/4:on 750125,tritium Leaked from Secondary Closure of Refueling Region 1.Cause Will Be Determined When Vessel Pressure Dropped to Atmospheric or Below ML20085L7721975-02-12012 February 1975 AO 50-267/75/3:on 750123,dew Point Moisture Monitors Failed to Initiate Reactor Scram When Moisture Content Exceeded Trip Setpoint.Caused by Failure of Sample of Primary Coolant to Reach Monitor.Tech Specs Revised ML20086B1231975-02-12012 February 1975 AO 50-267/74-21A:on 741121,high Pressure in Gas Waste Vacuum Tank Lifted Relief Valve Allowing Release of 700 Scf Uncontaminated Gas.Caused by Procedural Error.Inlet Valve Seats Will Be Replaced & Interim Procedure Modified ML20085L7401975-02-0707 February 1975 AO 50-267/75/1:on 750118,230-kV Breaker Tripped Due to High Winds,Causing Standby Diesel Generator a to Receive Start Signal.Generator B Did Not Receive Start Signal.Caused by Sensitive Relay Setting.Relay Recalibr ML20085L7271975-01-31031 January 1975 AO 50-267/75/2:on 750113,reactor Bldg Exhaust Charcoal Filters Failed to Meet Tech Spec Leak Rate Requirements. Caused by Use of oil-based Paint & Organic Solvents.Filters Changed Out ML20085L6501975-01-25025 January 1975 AO 50-267/75/24A:on 741222,static Seal on C-2101 (Helium Circulator C) Released During Removal of Temporary Jumpers. Caused by Blown Fuse & Seal Release Valve Leak.All Circulator Brake & Seal Vent Valves Checked ML20085L7341975-01-24024 January 1975 Telecopy Ao:Charcoal in Reactor Bldg Exhaust Filters Failed to Meet Tech Spec Requirements ML20085L7901975-01-14014 January 1975 AO 50-267/74/24:on 741222,static Seal on C-2101 (Helium Circulator C) Released During Removal of Temporary Jumpers.Caused by Jumper Across Logic Circulator a Coming in Contact W/Station Ground ML20086B0501974-12-23023 December 1974 AO 50-267/74-23:on 741211,engine a of Standby Diesel Generator 1-A Declutched & No Alarms Annunciated.Caused by Cylinder Air Pressure Decay Due to Dirt Under Solenoid Valve Seat.Change Notice 11 Re in-line Filters Approved ML20086B0641974-12-19019 December 1974 Telecopy AO 50-267/74-23:on 741211,diesel Engine a of Standby Generator 1-A Declutched 1976-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
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X' I DATE: _
' FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATTEVILLE, COLORADO 60651 REPORT NO. 50-26T/74/1 Interim X Final IDENTIFICATION OF OCCURREIICE:
This report is to describe the fuel element descripencies found during inspection associated with Initial Fuel Loading. ,
This event is considered to be an abnormal occurrence as defined ,
i in the Technical Specifications, paragraph 2.1F.
I CONDITIONS PRIOR TO OCCURRE!CE: Steady. State Power Routine Shutdown Hot Shutdown Routine Load Change Cold Shutdown I Other (specify)
Refueling Shutdown Initial Fuel Loading -
Routine Startup The major plant parameters at the. time of the event were as follows:
Power RTR, N/A MWth ELECT, N/A MWe Secondary Coolant Pressure N/A psig .
*F Temperature N/A _
8312060444 741106 Elov N/A 8/hr.
PDR ADOCK 05000267 S PDR
- ~
I .
mv Page 2 u
f Primary Coolant Pressure N/A psig.
Temperature N/A "F Core Inlet
-{'
N/A 'F Core Outlet-Flow N/A #/hr.
I DESCRIPTION OF OCCURRENCE: .Ii i
During reactor fuel loading at Fort St. Vrain the following fuel !
discrepancies were found: ,
- 1. Six alignment dowel pins were found to be cracked and/or chipped.
- 2. One fuel hole plug that extended above the surface of the el'ement.
- 3. One fuel hole plug was found to be missing.
See Attach =ent "A" APPARENT CAUSE '
OF OCCURRENCE: Design Unusual Service Cond.
Including Environ.
X Manufacture _
Component Failure Installation /Const. X Other-(specify)
Operator Handling in Preparation Procedure for Shipment ANALYSIS OF OCCURRENCE:
These discrepancies are being investigated by General Atomic as to the cause of the damage and as to why their Quality Assurance procedures failed l
to find them. General Atomic has been requested to provide Public Service Co=peny
~
o o
Paga 3 l with full information See Attachtent "B". _
f CORRECTIVE ACTION:
The six devel pins and out-of-specification Iuel plug were replaced at Fort St. Vrain, using procedures and supervisory personnel supplied by General Atomic. A plug was inserted into the fuel hole which was found to be without one, using a procedure provided by General Atomic.
FAILURE DATA /SIMILIAR REPORTED OCCURRENCES:
No failures of this type had previcusly been experienced.
PROGRAMATIC IleACT:
No progra=latic impact vill be experienced insofar as repairs were completed during fuel loading on site. .
CODE IMPACT: ;
No codes involved!
Approvedi b
n4a ,. 1 J F/edericE. Swart Superintendent, Fort St. Vrain Nuclear . ,
Generating Station 13
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, 931333 Vrain p Unit No. 1 ,
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. = Mr. John Crnich, Project Manager -
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. Culf General Ato=ic '
e P. O. Box 426 '
. Platteville, Colo. 80651 -
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Fuel / Reflector Block-Quality
Subject:
Fort St. Vrain Unit No.1
Dear Mr. Crnich:
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As you.are aware, we have experienced so=e proble=s'vith fuel and
_,' reflector elecents which, in our opinion, are related to, or maybe the result of, inadequate quality assurance and/or shop procedures.
. 1. In several instances devels of fuel ele =ents were broken. It
' is difficult for us to determine how this breakage occurred.
It is requested, however, that GGA investigate this =stter in
. . an atte=pt to deter =ine if a shop procedure or a packing and shipping procedure should be changed to prevent this type of damage fron occurring in the. future core ele =ents for Forc St.
Vrain.
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_ , 2. .Several graphite reflector blocks were rejected because of exces-sive da= age. From all indications, this da= age did not occur in ship =ent, which would indicate inadequate inspection prior to shipnent. This, again, appears' to be an area where existing procedures or inspection progra=s are inadequate. It is reques-ted that CGA investigate this matter, address the possible cauces,
,1uid take necessary action to prevent possible- reoccurrence in future ship =ents. i
- 3. 'Almost all of the metal clad reflector blocks were shipped with
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metal burrs, drill shavings, dirt and other foreign =sterial. ;
Again it appears that these ele =ents did not receive adequate l inspection prior to ship =ent. It is requested.that GGA inves- '
tigate this =atter,, address the possible causes, and take nece-
, maary action to prevent reoccurrence. -
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y'h 7 Quality
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..'>*,.'* F;rt Sts ,Vrdin Ui No. 1 ,
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4.. On two fuel elements two fuel hole plugs ' vere not in p15ce. Please investigate this catter and address the possible causes and the .
action taken to prevent similar reoccurrences.
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- We would appreciate your review of the abo.fe matters at your earliest
,, convenience. Please address these matters in sufficient detail to include proposed actions taken to permit us to evaluate the causes and the adequacy
. of the corrective action taken. . .
s.:,:. .e. .--
. Very truly yours, .
R 2 9. W a.L w -
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- 1. F. Walker, Vice President Engineering Planning & Analysis RN/bs - -
ec: Director, Quality Assurance - Don Ware = bourg
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