Part 21 Rept Re Replacement Impellers for Byron Jackson Raw Water Pumps Having Blade Dimensions Out of Tolerance Due to Normal Wear on Pump Internals.Replaced Raw Water Pump Assembly AC-10DML20148D120 |
Person / Time |
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Site: |
Fort Calhoun ![Omaha Public Power District icon.png](/w/images/6/6a/Omaha_Public_Power_District_icon.png) |
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Issue date: |
05/23/1997 |
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From: |
OMAHA PUBLIC POWER DISTRICT |
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To: |
NRC |
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References |
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REF-PT21-97 NUDOCS 9705300073 |
Download: ML20148D120 (4) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20141C4931997-06-17017 June 1997 Part 21 Rept Re Nonconforming Raw Water Pump Impellers.Raw Water Pump Assembly AC-10D Replaced Due to Normal Wear on Pump Internals,Namely Pump Impellers & Impeller Liners ML20148D1201997-05-23023 May 1997 Part 21 Rept Re Replacement Impellers for Byron Jackson Raw Water Pumps Having Blade Dimensions Out of Tolerance Due to Normal Wear on Pump Internals.Replaced Raw Water Pump Assembly AC-10D LIC-94-0164, Part 21 Rept Re Nonconformance in Potentiometers W/ Attachable Switches Mfg by Ohmite & Supplied by Abb C-E. Nonconforming Components Returned to Abb C-E & Abb C-E Issued Info Bulletin 94-02,providing Appropriate Guidance1994-08-24024 August 1994 Part 21 Rept Re Nonconformance in Potentiometers W/ Attachable Switches Mfg by Ohmite & Supplied by Abb C-E. Nonconforming Components Returned to Abb C-E & Abb C-E Issued Info Bulletin 94-02,providing Appropriate Guidance ML20071J5271994-07-26026 July 1994 Part 21 Rept Re Ohmite Model CU1021 & CU1031 Potentiometers Model CS-1 Switches Supplied by Abb C-E.Verified That Potentiometers/Switches Combinations Not Installed at FCS in Location Which Could Have Adverse Safety Implication 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 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl 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 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 ML20085D4971991-10-0707 October 1991 Part 21 Rept Re Cracking in Casing of Exide Type GC-23 Batteries Produced Prior to 1983.Initially Reported on 911003.Caused by Inadequate Design of Cell Terminal Post Seals.Use of pre-1983 Subj Batteries Discontinued ML20079H0921991-08-27027 August 1991 Part 21 Rept Re Failure of Roll Pin Mfg by Cardinal Industrial Products,Corp & Used on DG Damper Actuator Due to Phosphorus Segregation Caused by Improper Tempering Heat Treatment.Inlet & Outlet Dampers on DGs Opened ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20141C9361986-03-17017 March 1986 Part 21 Rept Re Containment Spray Sys Recirculation Lines. Initially Reported on 860311.Matter Under Investigation to Determine Remedial Course of Action.Staff Will Be Kept Informed of Progress ML20199F3351986-03-17017 March 1986 Part 21 & Deficiency Rept Re Failure of Disc Guide Assembly Springs in HCV-247 & HCV-248.Initially Reported on 860314. Springs Replaced & Valves Tested Quarterly.Other Utils Contacted Via Nuclear Network Sys ML20064J5801982-11-0808 November 1982 Part 21 Rept Re Matl That May Not Be in Compliance W/ 10CFR50,App B,Section Viii Requirements.Matl Supplied to Ne Public Power District & Omaha Public Power District.Qa Depts Contacted Re Resolution of Nonconformance Situation ML20010B6741981-07-31031 July 1981 Deficiency Rept Re Potential Defect W/Tornado Venting Sys. Inhouse Assessment Will Be Completed by 810910.Also Reported Per Part 21 1998-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
[Table view] |
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n OMAHA PUBLIC POWER DISTRICT j
. NUCLEAR LICENSING DEPARTMENT i
P.O. . Box 399 Hwy. 75 - North of Fort Calhoun !
Administration Building / Mail Stop: FC-2-4 ;
Fort Calhoun, NE 68023-0399 '
(402) 636-2000 / Switchboard '
(402) 533-7291/ Fax Number -_- -.
FACSIMILE TRANSMITTAL COVER SHEET l s DATE: Ik3h1 NUMBER OF PAGES (Including this Page): 3 ROM:
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E-MAIL ADDRESS: First Initial Last Name@OPPD.COM ;
(mLI.S@OPPD.COM) l COMMENTS: '
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4 Omaha Public Power District (OPPD)
Report on Nonconforming Raw Water Pump Impellers This report is submitted pursuant to 10 CFR 21.21(c)(3)(1). The items below address the specific information required by 10 CFR 21.21.(c)(4).
(1) Identification of individual providing this notification:
S. K. Gambhir Division Manager - Engineering & Operations Support Omaha Public Power District Fort Calhoun Station P. O. Box 399 Fort Calhoun. NE 68023-0399 (ii) Basic components containing defect:
Replacement impellers for Byron Jackson Raw Water pumps had blade dimensions out of tolerance.
(iii) Identification of supplier:
BW/IP International, Inc.
(iv) Nature of Defect:
Raw Water pump assembly AC-100 was replaced due to normal wear on the pump internals namely the pump impellers and impeller liners. The replacement assembly had been rebuilt with new inter al components After installation.
post maintenance and operability testing was performed using a station procedure. . The pump did not satisfy the acceptance criteria contained in the test: therefore the pump remained inoperable. The fact that the pump did not pass the test was very unusual especially considering the pump was completely rebuilt with all new internal subcomponents. The impeller lift setting was reverified and then the post maintenance / operability test was reperformed. '
Again the pump did not pass the test. so the pump assembly was removed and replaced with a another spare pump assembly.
The " defective' pump assembly was then disassembled for inspection to detennine cause of the extremely poor performance. Upon inspection of the first stage pump impeller. it was noticed that the blade profile was. significantly different when compared to the second stage impeller. At least two of the four blades on the first stage impeller appeared to have a " droop" causing the opening or suction eye between the blades to decrease. The size of the suction ;
eye for these particular type of pumps has a large influence on the amount of I discharge flow the pump is able to produce. This is because the decreased suction eye size causes the impeller to become extremely inefficient. With the 4
One other replacement impeller in the warehouse was determined to have similar
, deficiencies.
Potential Safety Significance The subject impellers contained dimensional inaccuracies which could not produce pump discharge flows to satisfy acceptance criteria. The estimated reduction of design flow was 20%. The Plant Review Committee conservatively determined that operation of a Raw Water pump AC-10D at the maximum allowable river temperature (90*F) with the defective impeller Installed could have created a substantial safety hazard by exceeding a safety limit or cause a major degradation of essential safety-related equipment, considering a single failure in addition to the degraded performance of AC-100. The river water temperature at the time of discovery was 36*F.
(v) Date informaJ m defect was obtained:
The installation of the replacement pump assembly with the defective impeller and unsuccessful testing was initially identified on April 8.1997. Based on review of an engineering evaluation of this condition. OPPD management conservatively determined that a defect existed on May 22. 1997. The OPPD Vice President with executive authority over Part 21 issues was informed on May 23.
1997.
(vi) Number and Location of components containing defect:
Two defective impellers passed the OPPD receipt inspectior, and were stocked in the warehouse. One of these impellers was used to rebuild a spare pump assembly which was installed as Raw Water Pump AC-100. The supplier has not reported these impeller defects. The existance of other r,1milarly defective impellers from this supplier is unknown to OPPD.
(vii) Corrective action which has. or is being taken:
The defective impellers are being returned to the supplier. Raw Water pump AC-10D was replaced with a rebuilt pump assembly which passed all surveillance test requirements (viii) Advice related to defect to be given to licensees:
None.
TOTAL P.02
a
[e POWER REACTOR EVENT NUMBER: 32384 FACILITY: FT'CALHOUN REGION: 4 NOTIFICATION DATE: 05/23/97 i UNIT: '[1] [].[.] STATE: NE NOTIFICATION TIME: 17:50 [ET]
j RX TYPE: [1] CE EVENT DATE: 05/23/97 i
EVENT TIME: 10 : 4 0 [CDT]
NRC EOTIFIED BY: TOM MATTHEWS LAST UPDATE DATE: 05/23/97 ,
i HQ OPS OFFICER: STEVE SANDIN l
<. NOTIFICATIONS l EMERGENCY CLASS: NOT APPLICABLE'
- i. 10 CFR SECTION: GARY SANBORN RDO
$- CDEG 21.21 (c)'(3) (i) DEFECTS / NONCOMPLIANCE-VERN HODGE (VIA FAX) NRR UNIT SCRAM CODE RX CRIT INIT PWR INIT RX MODE CURR PWR CURR RX MODE-1 N Y 100 POWER OPERATION. 100 POWER OPERATION EVENT TEXT ]
-THE LICENSEE ISLMAKING A PART 21 NOTIFICATION REGARDING DEFECTIVE RAW WATER PUMP IMPELLERS.
'THE' LICENSEE IDENTIFIED THAT THE REPLACEMENT IMPELLERS FOR BYRON JACKSON RAW WATER PUMPS HAD BLADE DIMENSIONS OUT OF TOLERANCE. AN ENGINEERING.
EVALUATION OF THE DIMENSIONAL INACCURACIES DETERMINED THAT-PUMP DISCHARGE FLOWS-USING THESE IMPELLERS WOULD NOT SATISFY ACCEPTANCE CRITERIA AND COULD POSE A SUBSTANTIAL EETY HAZARD UNDER CSETAIN CIRCUMSTANCES. THIS PROBLEM I WAS INITIALLY IDENTIFIED'ON 4/8/97. THE.TWO DEFECTIVE IMPELLERS WERE RETURNED TO THE SUPPLIER. THE LICENSEE DOES NOT KNOW IF OTHER FACILITIES i ARE AFFECTED. l THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
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