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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted 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 ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed 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 ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20083L1201995-03-14014 March 1995 Part 21 Rept Re Model 200,227A,288A & 289A Differential Pressure Instruments Mfg w/B-fill Fluid Possibly Not Functioning If Subj to Radiation Field Greater than 1 Million rads.Long-term Evaluation in Progress JAFP-94-0571, Part 21 Rept Re Spare GE Molded Case Circuit Breaker.Breaker Overcurrent Trip Failed to Perform within Specified time- Current Curve.Defective Breaker Returned to GE for Evaluation1994-11-28028 November 1994 Part 21 Rept Re Spare GE Molded Case Circuit Breaker.Breaker Overcurrent Trip Failed to Perform within Specified time- Current Curve.Defective Breaker Returned to GE for Evaluation ML20058H0741993-12-0303 December 1993 Part 21 Rept Re Discovery That Current Limiting Isolation Resistors Not Located in Respective Scram Contactor Boxes as Required by Plant Design Documents.Recommends That Isolation Resistors Be Installed in Scram Contactor Separation Boxes ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 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 ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20195D2171986-05-27027 May 1986 Rev 1 to Part 21 Rept Re Dowel Displacement on Connecting Rod Bearings Purchased During Nov 1985 - Apr 1986.Initially Reported on 860421.Rod Bearings Will Be Inspected Dimensionally.Further Info Forthcoming ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20138P0281985-12-13013 December 1985 Part 21 Rept Re Defect Identified in Two Oxygen Sensors. Added Thickness of Matl Will Eventually Cause Failure in Diffusion Membrane of Sensors.Sensors in Field Replaced ML20100L1141985-04-0909 April 1985 Part 21 Rept Re Shipment of Two non-safety Grade Circuit Breakers for safety-related Application.Initially Reported on 850405.Breakers Never Installed.Circuit Breakers Returned to GE & Replaced 1999-02-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
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United States Nuclear Regulatory Commission Document Control Desk Mail Station F1-137 Washington, D.C. 20555
SUBJECT:
DOCKET NO. 50-333 REPORTING OF DEFECT: 10 CFR 21 Spare Molded Case Circuit Breaker Failed overcurrent Test Criteria
Dear Sir:
This report is submitted in accordanco with 10 CFR 21. It reports a deviation from procurement specifications identified by the Authority during pre-installation testing of a circuit breaker which was in the warehouse inventory. ,
Questions concerning this report may be addressed to Mr. Donald Simpson at (315) 349-6361.
Very truly yours, HARRY P. SALMON, JR.
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05000333 _ _ _
l 01 OF 02 VITLE (4)
Spare Molded Case Circuit Breaker Failed Overcurrent Test criteria IIPGti BATE (7) UT ER FACILITIE5 larWOLM D (8)
EVUfT DATE (5) (ER IRAEEER (6)
FACILITY mAME 00Ca:ET stMEER SEauENTIAL ttV1510m O TW TEAA 05000 NOWTH CAT TEAR TEAA DAT h/A wtmata Mt.M8E R FACILITT EAME DOCEET stDe&Et 10 03 94 mfA 05000 THIS RFPORT 15 SLEIMITTED furSJAKT TO TPE SfMJIREENTS Of 10 Cf R i: (Check are or enore) (11) . . - _ ,
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'EAME, Mr. Donald Simpson, Senior Licensing Engineer (315) 349-6361 EnePLETE DEIE LluF For I ACH cusOIRWT FAILLutE DESC21 BED te THIS RIMuti (13)
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(This report is provided under 10 CYR 21, Reporting of Defects and Noncompliance.
On 10/3/94, a spare General Electric molded caso circuit breaker, Type THJK, was being bench tested in preparation for installation in a safety related application. The breaker overcurrent trip failed to perform within the specified time-current curve. The breaker was not installed. A second breaker from spare parts inventory was bench tested with satisfactory results.
The defective breaker vaa returned to General Electric for evaluation.
General Electric concluded that the failure to identify this deviation was due to human error and was a one tiIte occurrence.
This deviation was identifled through routine adlninistrative controls in place at FitzPatrick. No further corrective actions arc planned.
etC FORM 346 (5 92)
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(5 02) EKP!RES 5/31/95 ESTIMAT[0 SURDEW PER RESPONSE TO CD4 PLY WITN LICENSEE EVENT REPORT (LER) $a'I CNm s Nao'In ERNa ks I TE o Tue IurotMAtlas Am REconos RA.MACERLur BAABCM (MkB8 7714), U.S. WCLEAR RECULATORY COctitSIOW, TEXT CONTINUATION wAswinciou, oc zosss-ooo1 Amo To Tue PA.ptewanc REDUCTION PRORCT (31$0-0104), OFFICE OF MAnAGEMFWT uD Biffit WASPINGTm. DC 20503. ,
rAc Lirr u w (1) ocxxET uunart (2) LH ultep (O PAK (3) l Jamsa A. Fitzpatrick Nuclear TEAR SE AL RI Power Plant 05000333 02 OF 02 uxr cif w. oece ti ream.o. vee .mittenet cootes of nicans (173 Enrrative on October 3, 1994, a General Electric molded case circuit breaker was withdrawn from the warehouse spares and was being tested to confirm availability as a replacement for an installed breaker during an upcoming plant outage. The breaker is General Electric Catalog Number TILTK426400, Part Number DD188C8963P191, 2 Pole, 125VDC. The breaker was purchased as Safety Related "Q" equipment subject to the provisions of 10 CFR 50 Appendix B and was certified as a qualified replacement part for the specified application. Time current curves for the breaker were required as part of the order. The breaker was received by the Authority and placed in stock inventory in August, 1993.
Pre-installation testing, which is required by site maintenance procedures revealed that the breaker did not meet the time current characteristic required by the purchase order and as certified by the vendor. The breaker failure was nonconservative in that it remained closed beyond the time that it should have tripped. This occurrence is raported as a deviation under the provisions of 10 CFR 21.
The defective breaker was supplied by:
General Electric Company 175 Curtner Avenue M/C 853 San Jose, California 95125 If this breaker had been installed in the plant, the failure would have challenged the DC power system coordination scheme. There is no safety hazard related to this failure because all breakers in this application are tested prior to installation. This was confirmed through a records review.
A second breaker from stock inventory was tested with satisfactory results.
The failed breaker was rejected and returned to the vendor for failure evaluation.
The evaluation results, received on October 31, 1994, indicated that the breaker should not have been shipped based upon a review of dedication test results. Human error {Cause Code A}, inadequate review of test data, was the cause and was determined by the vendor to be a one time occurrence. No additional corrective actions are planned by the Authority.
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POWER REACTOR EVENT NUMBER: 28076-FACILITY: FITZPATRICK REGION: 1 NOTIFICATION DATE: 11/28/94 l UNIT: [1] [] [ ] STATE: NY NOTIFICATION TIME: 14:43 [ET] l RX TYPE: [1] GE-4 EVENT DATE: 10/03/94 )
EVENT TIME: 12 : 00 [EST)
NRC NOTIFIED BY: FACSIMILE LA$T UPDATE DATE: 11/28/94 l HQ OPS OFFICER: WILLIAM HUFFMAN NOTIFICATIONS EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION:
CDEG 21. 21 (c) (3 ) (i) DEFECTS / NONCOMPLIANCE UNIT SCRAM CODE RX CRIT INIT PWR INIT RX MODE CURR PWR CURR RX MODE 1 N Y 65 POWER OPERATION 65 POWER OPERATION EVENT TEXT DEFECTIVE 125 VDC MOLDED CASE CIRCUIT BREAKER.
ON 10/03/94, A SPARE GENERAL ELECTRIC MOLDED CASE CIRCUIT BREAKER,' TYPE THJK, WAS BENCH TESTED IN PREPARATION FOR INSTALLATION IN A SAFETY RELATED APPLICATION. THE BREAKER OVERCURRENT TRIP FAILED TO PERFORM WITHIN THE SPECIFIED TIME-CURRENT CURVE. THE BREAKER WAS NOT INSTALLED. A SECOND BREAKER FROM THE SPARE PARTS INVENTORY WAS BENCH TESTED WITH SATISFACTORY RESULTS.
THE DEFECTIVE BREAKER WAS RETURNED TO GENERAL ELECTRIC FOR EVALUATION.
GENERAL ELECTRIC CONCLUDED THAT THE FAILURE TO IDENTIFY THIS DEVIATION WAS DUE TO HUMAN ERROR AND WAS A ONE TIME OCCURRENCE.
THIS DEVIATION WAS IDENTIFIED THROUGH ROUTINE ADMINISTRATIVE CONTROLS IN :
PLACE AT FITZPATRICK. NO FURTHER CORRECTIVE ACTIONS ARE PLANNED.
A COPY OF THIS REPORT HAS BEEN SENT TO NRR/TQMB (HAASS).
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