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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 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 ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils 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 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20198Q6961998-01-12012 January 1998 Part 21 Rept Re Failed Operation of Agastat EGPI004 Relay on 971129,as Reported by Limerick Station.Caused by Insufficient Soldering.Will Notify Customers Who Purchased EPI004 & ETR14XXX004 Relays During June 1996 ML20198K5081998-01-0606 January 1998 Part 21 Rept Re Transient Analyses at Exposures Prior to End of Cycle.Caused by Component Defect.Notified Commonwealth Edison of Defect & Provided Revised Limits by Siemens Power Corp ML20203B3691997-12-10010 December 1997 Part 21 Rept Re Potential to Exceed Operating Limits.Cycle 8 Delayed Until Fall 1998 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 ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20134Q0801996-11-27027 November 1996 Part 21 Rept Re Deficiency of Wkm Model 70-13 Pneumatic Actuators Manufactured by Anchor Darling Valve Company Due to Incorrect Calculation of Bench Set & Supply Air Set Points.All Affected Valves Have Been Reviewed & Evaluated ML20128F5011996-10-0404 October 1996 Part 21 Rept & Deficiency Rept Re Wkm Model 70-13 Pneumatic Actuators Mfg by Anchor Darling Valve Co.All Affected Valves Being Reviewed/Evaluated & Design Changes Are Being Initiated as Required ML20117P3141996-09-11011 September 1996 Part 21 Rept Re Deficiency of GE Type RMS-9 Overcurrent Trip Device Programmers ML20113D4201996-05-15015 May 1996 Part 21 Rept Re Certain Lots of Commercial Grade Potentiometers in Transmeters Have Been Supplied W/Lubrication in Noncompliance W/Engineering Spec Requirements ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML20096A4021995-12-28028 December 1995 Interim Part 21 Rept Failure of Scram Discharge Vol Drain Valve 1BFHV-F011.Possible Causes of Failure,Includes Spring mis-adjustment,change in Spring Adjuster Setting & Spring Relaxation.Further Investigation Ongoing ML20082S7401995-04-26026 April 1995 Part 21 Rept Re Hinge Arms Associated W/Sixteen Swing Check Valves Mfg by Anchor-Darling Valve Co ML20081L7701995-03-29029 March 1995 Initial Part 21 Rept Re Anchor-Darling Check Valve Hinge Arms.Cs Pump B Discharge Check Valve Failed to Close in Nov 1994 Because Butt Stop on Hinge Arm Not of Sufficient Length.New Butt Stop Hinge Arm,Hinge Pin & Disc Installed ML20082B5271995-03-28028 March 1995 Part 21 Rept Re Notification 9505 Automatic Switch Co Pilot Solenoid Valve Model NP8323A20V.Caused by Failures of MSIVs to Close to Asco Pilot Solenoid Valves.Subj Valves Replaced W/Valcor 3-way Solenoid Valves ML20082E1901995-03-27027 March 1995 Part 21 Rept Re Sticking of B Core Assembly to Plugnut on Automatic Switch Co Dual Solenoid Valve Model NP8323A20V. Unit 2 Valves Replaced.Unit 1 Valves Will Be Replaced ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20069A8631994-05-17017 May 1994 Final Part 21 Rept Re Secondary Containment Isolation Techno Corp Dampers Equipped W/Parker Hannifin Air Cylinders at LaSalle County Station.All Units 1 & 2 Techno Dampers Equipped W/Parker Air Cylinders Replaced ML20070N3451994-05-0202 May 1994 Part 21 Rept Re Failures of Limit Switch Series EA740-86700 Mfg by Namco Controls Co Due to Excessive Amount of Grease on Contact Block & Contact Carrier & Wrong Matl of O-ring. Series EA740-86700 Switches Replaced w/EA740-50100 Switches ML20063M1701994-03-0202 March 1994 Part 21 Rept Clarifying & Supplementing Info Provided by Licensee Re Deficiency in Qualified Life Calculation for Microswitches Mfg by Comsip,Inc. Subj PTW-5300 Dc Indicators Supplied by Comsip,Inc,Mfg by Microswitch Corp ML20063D0861994-02-0202 February 1994 Part 21 Rept Re Possible Anomaly W/Namco Controls EA740 & EA750 Series Limit Switches.Investigation in Progress & Has Not Been Concluded.Vendor Will Advise NRC within Next Thirty Days Re Matter as Addl Info Becomes Available ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20057C9331993-09-21021 September 1993 Suppls 930216 Potential Part 21 Rept Re NNB-R Neutrals Supplied to Gap on 910510.Part Number (P/N) Qualified & Now Documented as Bussmann Neutral P/N Nnb & Gap Furnished W/ Revised Coc Documenting Correct Bussmann Neutral P/N Nnb ML20046C6591993-08-0505 August 1993 Part 21 Rept:On 930429,deficiency Identified Re Heat Damage to Comsip Series PTW-5300 Dc Powered Microswitches.Initially Reported on 930709.Safety-related Dc Microswitches Will Be Replaced Prior to 931230 ML20045G5591993-07-0202 July 1993 Part 21 Rept Re Defect in safety-related Solenoid Valve Mfg by Automatic Valve Co & Supplied by Atwood & Morrill Co,Inc. Solenoid Valves Installed in Unit 1 MSIVs Visually Inspected.Spare Solenoids Inspected Also ML20128M9201993-02-16016 February 1993 Potential Part 21 Rept Re Treatment of Bussman Neutrals as Being safety-related When Customer Purchase Order Implied That Parts Not safety-related.Vendor Will Notify Util Through NOA 5 of TPQ-TR-91-16 & Request Return of Parts ML20128H9931993-02-0909 February 1993 Interim Deficiency Rept Re Defect in Replacement EDG Fuel Oil Pumps Supplied by Colt Industries (Fairbanks Morse Engine Div).Initially Reported on 930111.Plugs & O-rings Repositioned.Vendor Requested to Perform Evaluation ML18096B2421993-02-0101 February 1993 Part 21 Rept Re Possible Matl Defect in Stainless Steel Swagelock Tube Fittings.Initially Reported on 921218.List of Part Numbers,Heat Codes & Addl Affected Customers Encl ML20127K8811993-01-0606 January 1993 Part 21 Rept Re Engine Driven Fuel Oil Pump Being Returned for Proper Configuration Due to Portion of O Ring Missing from Plug 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D3061999-10-13013 October 1999 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 ML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data 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 ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.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 ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 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 ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. 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 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 ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With 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 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.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 ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 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 ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 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 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 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 ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 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 1999-09-08
[Table view] |
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, ingersell-Dr:sser Pump Company sketzeered rump cearp m wmorwi Pam Phillip burg,. %J OWG 09 JY 98 Fax # 301-816-5151 7 pages total sent US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Mr. Chancey Gould
Subject:
10CFR21 Deportability of a Potential Safety liazard from broken Cast iron Suction lieads in APKD Type Pumps
Dear Mr. Gould:
Per our telephone conversation this aflernoon, Ingersoll-Dresser Pump Company is
- hemby notifying the NRC about a potential safety hazard from potential breakage of L cast iron suction heads in APKD type pumps located at seven (7) different Nuclear j sites.
! Enclosed please find the engineering background, evaluation, conclusions, recommendations, typical component sketch, and a listing of the utilities, sites, pump types, order numbers, quantities and pump serial numbers that may be affected.
If you have any questions from an engineering standpoint, please call Bob Cornman at (908) 859-7256,' and for quality control issues call me at (908) 859-7298.
i Sincerely yours, i R. A. Ile dricks Quality Assurance Manager RAll:sla i CC: R. Rajeski V. P. and Gen. Mgr. Engineered Pump Group \
W. Ord President Engineered Pump Group R. Cornman IDP - PE f t
C I, Enclosures /
. , .I 7 9907150207 990709 PDR ADOCK 05000352:
S PDR m, ingersell Read ' Ped & Worthington Pievgor klence Jewment khneider Pumps
The purpose of this letter is to update the NRC on the Ingersoll-Dresser Pump evaluation of cast iron suction head damage experienced by one utility on Residual lleat Removal (RilR) pumps manufactured by ingersoll-Rand Company. These pumps are of the model APKD designation and were manufactured in the mid 1970's.
BACKGROUND The suction head (part number 360 as shown on Figure 1) is a cast, structural component that holds a bearing located below the double suction first stage impeller on the APKD type pumps (refer to Figure 1).
The bearing holder is connected to the outer portion of the suction head with three or four support ribs depending on the pump designation. 'Ihe suction heads were made from cast iron.
In addition to Ri!R applications, APKD type pumps in several different sizes have been supplied for Low Pressure Core Spray, and liigh Pressure Core Spray applications. Figure 2 contains a listing of the APKD type pumps supplied for various applications.
The problem was initially noted at the PECO Energy Limerick Unit #1 Nuclear Power Plant in May 1998.
While investigating clogging of the #2 Jet pump, a piece of metal was found inside of the reactor vessel which ultimately was traced to the IB RilR pump. A visualinspection (boroscope) of the 1B RIIR pump revealed that a portion of the suction head was missing.
OBSERVATIONS After a careful review of the information from the Limerick site and the inspection of the 1A & 1B RilR pumps, the following observations have been made:
- 1. On the 1B pump, the lower bearing bracket broke off and became lodged in the inlet of the pump. i This was evidenced by the wear pattern on the hub area of the bracket. In addition, the leading I vane edges at the inlet of the lower eye of the first stage impeller had damage that appears to have been caused by contact with a rib of the bracket.
- 2. All bearings (except for the damaged suction head bearing) and impeller to casing wear ring clearances were measured and found to be within tolerance.
- 3. Overall, the IB RilR pump was found to be in good condition. Two minor indications found on the #1 & #3 outer casing vanes required minor work to blend by hand grinding. ,
l l 1 4 The inspection of the 1 A RilR pump revealed that the suction head of the 1 A RHR pump was )
found intact. The suction head journal sleeve (part number 135A on Figure 1) was found to have l moved approximately one quarter inch relative to the shaft.
- 5. Inspections of both the IB & 1 A RIIR pumps indicate that downward movement of the suction head journal sleeve was wearing the key (part number 291 on Figure 1) installed to prevent rotation between thejourna! sleeve and the shaft.
- 6. The 1B RilR pump is of a similar desi nF to the 1 A Condensate pump which experienced a suction head failure in December of 1997. Information obtained from the plant suggests that the 1 A Condensate pump may have been operated in a failed suction head condition with no noticeable degradation in performance for 12 to 18 months of continuous service.
I
- 7. A suction head failure as observed on the 1B RIIR pump would be expected to change the l
vibration response of the pump; however, the vibration data for the IB RIIR pump and the l A i Condensate pump did not indicate an abnormal vibration response during normal operation.
l
- 8. The 1B RilR pump had passed all ofits surveillance test requirements.
l
- 9. A mathematical analysis performed on the suction head, taking into account the expected mechanical, hydraulic, and thermal effects, did not indicate sufficient loading to cause the failure.
CONCI USIONS The failure mode of this suction head appears to start with the migration of the suction head journal sleeve along the lower end of the pump shaft due to wear of the key that holds the sleeve in place. ~1his is a result of the accumulated operating time on tM pump. Once the sleeve is detached from the shaft, it is able to move in the lower portion of the pump and strike the suction head causing breakage of the support rib.
I As demonstrated by the experience with the l A Condensate pump, a pump can operate without a measurable degradation in performance for a period of time with a suction head failure. Gradually, a decline in performance would be observed over time. The expected trends that would result from a pump operating in this degraded condition would be a deterioration in the head' flow characteristics of the pump ,
and a corresponding increase in vibration.
The failure of the suction head would not likely result in an immediate pump parameter change unless a
, portion of the suction head became lodged in one of the pump impellers. It must be noted that at the Limerick I site, both the 1B RIIR pump and the 1 A Condensate pump passed pieces of broken suction head rib without affecting the pump operation.
RECOMMENDATIONS Ingersoll-Dresser Pump's recommended action plan for those pumps listed in Figure 2 is as follows:
- 1. Inspect pumps at reasonable intervals for possible damage to the suction head, suction head journal sleeve, and retaining key.
- 2. If the surveillance testing has shown a recent degradation in the hydraulic performance of the pump or a recent change in the pump vibration, then the pump should be inspected immediately for possible damage to the suction head' suction headjournal sleeve.
- 3. When required, a replacement suction head manufactured from carbon steel with additional rib stiffening and a suction head journal sleeve with improved axial positioning should be installed. !
- 4. Monitor vibration on the pump shaft and motor housing and increase the frequency of the surveillance testing until an inspection of the suction head, suction head journal sleeve, and retaining key can be completed.
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