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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20211M6491997-10-0808 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 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 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 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 ML20095J7981992-04-29029 April 1992 Part 21 Rept Re Failure of Anchor Darling Swing Check Valve to Move Freely Through Entire Range of Motion.Caused by Insufficient Clearance Between Swing Arm & Shaft Bushings. Valve Repaired Onsite by Vendor ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML20247M5851989-07-27027 July 1989 Part 21 Rept Re Failed Globe Valve Stem on 890405.Caused by Improper Heat Treatment of 410 Stainless Steel Alloy Used in Stem Which Increased Susceptibility to Stress Corrosion Cracking.Larger Shaft Modified by Machining Radius ML20246H5331989-02-14014 February 1989 Part 21 Rept Re Defect in Motor Mounting Bolts on Limitorque Operators & Reliance Motors.Caused by Loosening of Motor End Bell Bolts.All Normally Inaccessible Operators W/Susceptible Bolting Will Be Inspected ML20204D1911987-03-20020 March 1987 Part 21 Rept Re Potential Existence of Design Defect in Bingham/Willamette RHR Pumps Flow Capacity.Ge Will Perform Evaluation of Conditions.Operators Will Be Alerted in Writing to Miminize Time in Min Flow Mode FVY-86-105, Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl1986-11-10010 November 1986 Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl ML20196E1171986-09-16016 September 1986 Part 21 Rept Re GE Solenoid Valve Rebuild Kits.Defect Found During Failure to Scram on 860613-28.Util Replaced All 178 Hydraulic Control Unit Scram Solenoid Internals,Plus Two Discharge Vol Solenoid Valve Internals NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List ML20141A0881986-03-28028 March 1986 Part 21 Rept Re Potential Defect in Contact Block Kits Supplied by Namco Controls.Initially Reported on 860227. Defective Kits Replaced.Vendor QA Program Under Reevaluation ML20154N5141986-03-10010 March 1986 Part 21 Rept Re Failure of Standby Liquid Control Sys Squib Valve to Fire.Caused by Discrepancies Identified Between Conax Corp Drawings of Trigger Assemblies & Wiring Configuration of Trigger Assemblies in Stock ML20154K3611986-03-0505 March 1986 Part 21 Rept Re Possible Wiring Defect in Fabricated Primer Chamber Assemblies for Standby Liquid Control Valves. Initially Reported on 860214.Listed Corrective Actions Will Be Completed by 860328 ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20129G4401985-05-29029 May 1985 Part 21 Rept Re Failure of Inner Polar Connector Between Damper Bar Circuit on Generator Main Field.Cause of Failure Not Defined.Further Investigation Necessary ML20116K0891985-03-0505 March 1985 Followup Part 21 Rept Re Overcompression of Power Lead Gland Assembly Sealant During Factory Assembly.Procedures Revised to Specify That Only One Coat of Threaded Lubricant Will Be Applied.Proprietary Rept Encl.Rept Withheld ML20096C5761984-08-31031 August 1984 Part 21 Rept Re Potential Defect in Power Lead Gland Assemblies Qualified for Nuclear Svc.Parts 7D92-11000-01-04, 7D92-11001-01-05,N-11150-01 & N-11151-01 Showing Loss of Electrical Continuity.Customer Informed & Evaluation Begun ML20093D8711984-07-13013 July 1984 Part 21 Rept Responding to NRC Re IE Info Notice 84-30 on Bahnson Co HVAC Equipment.Units Not Supplied to Facility.Stringent QA Program Implementation Essential to Prevent & Detect Problems ML20093D1431984-06-29029 June 1984 Part 21 Rept Re Defective Uninterruptible Power Supply Batteries Supplies by Exide Corp.Util Replaced Batteries During Current 1984 Refueling Outage ML20082E7801983-11-21021 November 1983 Part 21 Rept Advising That Review of QA Program Initiated in Response to IE Bulletins 83-06 & 83-07 to Address Possible Fraudulent Actions by Suppliers ML19305F2001980-11-0303 November 1980 Part 21 Rept Re Failure of Fire Penetration Seals to Pass Fire Test.Cause Undetermined.Tested Matl Will Be Analyzed 1997-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.With BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998 Corp 1998 Annual Rept. with BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station ML20198H5481998-12-23023 December 1998 Rev 2 to Vermont Operational QA Manual,Voqam ML20196H8641998-12-0101 December 1998 Cycle 19 Operating Rept BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20237E9221998-08-20020 August 1998 Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603 BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station ML20248C5081998-05-31031 May 1998 Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20 ML20248C4951998-05-31031 May 1998 Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247G4001998-05-12012 May 1998 Interview Rept of Ej Massey ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee 1999-09-30
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VERMONT YANKEE NUCLEAR POWER CORPORATION FVY 86-20
. , RD 5, Box 169, Ferry Road, Brattleboro. VT 05301 y,,g ,o y ENGINEERING OFFICE 1671 WOnCESTER HO AD
- FnAMINGHAM. MASSACHUSETT3 01701
. If L 8 fHONE, Gi f 4'J 4100 March 10, 1986 U.S. Nuclear Regulatory Commission Office of Inspection & Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Dr. Thomas E. Murley Regional Administrator
References:
a) License No. DPR-28 (Docket No. 50-271)
Dear Sir:
Subject:
Notification of Potential Existence of a Defect in Accordance with 10CFR21.21 In accordance with the provisions of 10CFR Part 21, Section 21, we are hereby notifying you that we have obtained information indicating that a defect may exist with respect to SLC squib valve tirgger assemblies manufactured by Conax Corporation.
Enclosure I to this letter documents the details of this notification.
Should you have any questions regarding this matter, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION (440-- Ym Warren P. Murphy Vice President an Manager of Operations
/dm 0603170342 860310 2 1 DR ADOCK 0 6
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F -VERMONT YANKEE NUCLEAR POWEP CORPORATION g,.
3 U.S. Nuclear ' Commission s+
March 10,1986 .
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, s cc: (3) U.S. Nuclear Regulatory Commission Director, Office of Inspection ,A Enfo, rey,,.ent Washington, D.C. 20555 -
(3) Chairman, Vermont Yankee Nuclear -
Safety Audit and Review Committee .,
(1) Manager, Operational Quality Assurance Dept. i,.-
Yankee Atomic Electric Company .
(1) ' Institute of Nuclear Power Operations (INPO) '
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ENCLOSURE I f
SLC SQUIB VALVE TRIGGER ASSEMBLY PART 21 REPORT I
L COMPANY INFORMING Vermont Yankee Nuclear Power Corporation THE COMMISSION RD 5, Box 169 Ferry Road Brattleboro, Vermont 05301 FACILITY Vermont Yankee Nuclear Power Station PO Box 157 Governor Hunt Road Vernon, Vermont 05354 FIRM SUPPLYING Conax Corporation l COMo0NENT 2300 Walden Avenue Buffalo, New York 14225 g NATURE OF DEFECT Following routine surveillance testing on February 6 and 11, 1986, during which Vermont Yankee's Standby Liquid Control (SLC) System squib valve failed to fire, Vermont Yankee identified that trigger assemblics supplied by Conax Corporation had two different pin to coil con-figurations. This failure to fire occurred despite indi-cation via the continuity test circuit that continuity t was present.
Discrepancies were identified between Conax manufac-turing drawings and the wiring configuration of trigger assemblies in stock at Vermont Yankee. According to the Conax drawing, bridge wires were supposed to be wired across Pins 1 and 4 with the second bridge across Pins 2 and 3. Testing of pin assemblies of the units currently installed at Vermont Yankee determined that there was a bridge wire across Pins 1 and 2 with the second bridge across Pins 3 and 4. Testing of pin assemblies purchased before and after pin assemblies currently installed at Vermont Yankee determined that they had bridge wire con-nections across Pins 1, 4 and 2, 3.
During a meeting with Conax on February 19, 1986, it was learned that there should only be one pin configuration with the correct configuaation having bridges across Pins 1, 4 and 2,,3. Conax felt that the cause of the problem (Units with two different pin configurations) was the i
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Enclosure I Page 2 moving of their manufacturing operations to Florida.
From approximately mid-1983 to near the end of 1985,
,I Conax had primer trigger. assemblies manufactured at their Florida plant. . Conax has since moved these manufacturing operations back to Buffalo, New York.
DATE ON WHICH A potential Part 21 Report Evaluation was initiated on
. DEFECT WAS DETECTED February 14, 1986.
. NUMBER.0F' COMPONENTS Vermont Yankee had six (6) trigger assemblies with AT FACILITY incorrect pin to coil wiring configurations.
1.
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CORRECTIVE ACTIONS Vermont Yankee is modifying its procedures to require a pin to pin continuity check for.all trigger assemblies prior to installation.
! 2. Vermont Yankee is modifying its existing procedure which tests the first primer of each batch to require the testing to be performed in the firing circuit.
- 3. Vermont Yankee is investigating the possibility of revising the continuity test circuit design to ensure it actually indicates ability to " fire" the squib charge.
- 4. . Incorrectly wired trigger assemblies are being returned to Conax Corporation for replacement.
- 5. The surveillance test performed which uncovered this problem will be repeated prior to declaring the system operable.
RELATED ADVICE Vermont Yankee recommends other BWR operators review in detail USNRC IE Information Notice No. 86-13, " Standby Liquid Control Squib Valves Failure to Fire" issued February 21, 1986.
Vermont Yankee also warns BWR operators that, although our wiring did not agree with our wiring diagrams, the as-found wiring was acceptable per General Electric SIL No. 186 issued July 30, 1976. Accordingly, compliance with this SIL does not alleviate the concern Vermont Yankee has identified.
i'