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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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iTT sart:n l ITT Pluid Tcchnology Corporation YEARS March 14, 1995 New York Power Authority P.O. Ses 41 Lycoming, NY 13093 ATTENTION: R. Lawton Q.A. Engineer
' Industry Notification of B-Fill Qualification
SUBJECT:
Limitations Industry Advisory is being provided for your The attached Our records indicate that you have purchased Model information.
Number 200, Model Number 227A, Model 288A and Model Number 289A Indicators / Indicating Switches with 5-Fill within the past 10 years. -
If there are a questions regarding this notification, please ,
reon at (018) 961-2547.
e tact Je .
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!JeraldAnderson Director of Quality Assurance -
_l Attachment .
J.: . ..
900 South Tumbull Canyon Road, P.O. Box 1882, City of Industry, CA, USA 91749-1882
"~
' Telephone (818) 961-2547 Fax (818) 333-7241 9505100099 950314 PDR ADOCK 05000333 S PDR
=
a[ N . ' . 4;p;fi ;.a ,,._;,,;,. . .,, ,a LONG ISLAND LIGHTING COMPANY 4
SHOREHAM NUCLEAR POWER STATION P.o. sex 410. NORTH COUNTRY ROAO e WADING RIVER, N.Y,1179S Direct Dial Number (516) 929.s300 ext. 3456 March 23,1995 SSD 95106 Quality Control Manager New York Power Authority
. J. A. Fitzpatrick Nuclear Plant PO Box 41
- Lycoming, NY 13093
Subject:
ITT Barton Model 289A B-Fill Qualification Limitations ' )
Dear Sir:
I l
Please find enclosed a copy of a 10CFR Part 21 Notification which was recently received by the tens Island Lighting Company (LILCO) from ITT Barton. This notification addresses B Fill Qualification Limitations. l The New York Power Authority recently purchased such a switch from LILCO under NYPA Purchase Order No S 95 69163, dated 2/1/95.
This notification is being transmitted to you in accordance with the guidelines set forth in 10CFR Part 21 of Federal Regulations.
If you have any questions, please contact me at (516) 929-8300, extension 3456.
i Timothyg. Cuff, Manager '
Shoreham Salvage Division TPC:na cc: J.OHliard A. Zegel W . ouldi Ale: sed 95106.Itr PC 49N.1
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(Y S::rttn ITT Fluid Technology Corporation
'I YEARS i
l March 14, 1995 Long Island Lighting Company L1140, Shorham Nuclear Facility F.O. Box 528 North Country Road '
Wading River, NY 11792 ATFENTION: Tim Curt .
LILCO Site Salvage Divsion Manager SUBJECTS Industry Notification of B-Fill Qualification Limitations The attached Industry Advisory is being provided for your information. Our records indicate that you have purchased Model Number 200, Model Number 227A, Model 208A and Model Number 209A Indicators / Indicating switches with B-Fill within the past 10 years.
If there are any questions regarding this notification, please contact try Anderson at (018) 961-2547.
i
/
Jerald Anderson
' Director of Quality Assurance Attachment I
i 4
900 South Turnbull Canyon Road, P.O. Box 1882, ci of Industry, CA, USA 917491882 Telephone (818) 9612547 Fax 18) 333 7241 l
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ITT BARTON INDUSTRY ADVISORY (March 13,1995) 1 f
RADIATION LIMITATIONS OF B-FILL ITT Barton supplies Model 200 and Model 227A Differential Pressure Indicators and Model 288A l and Model 289A DifDerential Pressure T=@=14 Switches to the cornmercial nuclear power industry !
- with mild environrnent IEEE-323/344 q" '*8--dons which includes radiadon exposures to 3 Mrads -
(TID gamma) where required. In the past, when a Customer has specified low temnerene R 40 *F1 j installation for these type ofinstruments, ITT Barton has recommended using a beRows f18 fluid consisting of an a-- =1a+8a t of adah niveel rn.flin as long as the r=d =daa le els associatad df. the inae=" - %. are '- 62: 1 '.h.d (TID c;.. .. ). ITT Barton has performed testing demonstratmg the satsinary of B-flE tbr nuclear service where radladaa lewis do not exceed 1 Mind (TID samma). However, as a result ofinternal reviews, it has come to our attention that we have not completely identified the radiation limitations of B-flu to our Customers. .
Our testing has shown that aqueous solutions of ethylene glycol tend to disassociate under gamma radiation exposures in excess of 1 Mrad. The products of this disassociation includes methane and hydrogen gas, which when trapped inside the differential pressure unit bellows, prevents reliable response of the Instrument to d,ifferential pressure changes.
1 This inAiev Adv*2.a is maaM aniv to Lum anaa-i ians ofITT Barton Model 200 and 227A l Indicators qualified under ITT Barton Quahdeada's Report R3-227-2, and Model 288A and 289A l indicating switchen qualified underITT Barton yn.saara*ian r Reports R3-288A-1 or R3-288A 13. 1 i
These Products (specifed Model Numbers), supplied with D fill (demineralized water) or M-fill
- (hydrocarbon oil), are m t a concern as these fB1 fluids have been tested and found to be suitable for nuclear service instaustions with radiation exposures to 3 Mrada consistent with the Qualification
. Report condhions and the supplied Certdications of Quallacadon. l Questions regarding th!S issue sbould be addressed to J. Anderson, Director of Quality Assurance at (818) 961 2547.
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'RIORiiY ATTENilCN REQUIRED MORNING REPORT - RE610N I APRIL 10. 1995
~l License'/e Facility: Notifications l 16ew. York Power Authority MR Nusher: 1-95-0053 FittPatricki Date: 04/10/95 Lycosino.New york SRIPC
'Occiets:0-333 SWR /6E-4 l
Subject:
POTENTIAL FAILURE OF iTT BARTON DIFFERENTIAL PRESSURE INDICATORS i ANDSWITCHES
% i Resortable Event Nusber: N/A i !
Discussions f
i The licensee was notified by ITT Barton that Models 200, 227A. 28BA. I and 289A differential pressure instruments sanufactured with 'B-Fill' fluid say not function if subjected to a radiation field greater than i sillion rads (1 Mrad). For low tesoerature apolications the manufacturer has recossended using an instrusent with a bellows filled ,
cith an aqueous solution of ethylene glycol (B-ff!!). Testino by lii !
3arton has shown that aqueous solutions of ethylene olycol tend to ,
disassociate under gassa radiation exposures in excess of i Mrad. As a
.{
result of internal reviews, the sanufacturer has detersined that not all !
of its customers were made aware of the radiation limitations of B-fill i fluid.
I The licensee reviewed its records and located seven instrueents in four safety related systees. An operability determination by the licensee !
concluded that the affected systees were capable of perforsing their required safety functions. Long tera evaluation is in progress. The licensee is evaluating Part 21 reportability. ,
Regional Actions i l
Noreal resident followup.
Contact:
Ricards Fernandes (3151342-4907 Willias Cook (315)342-4907 l
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