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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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P,- "* .
~VER1 NT YANKEE NUCLEAR POWER CORPORATION
. R D 5, Box 169, Ferry Road, Brattleboro, VT 05301 h,86-83 p ENGINEERING OFFICE 1671 WCRCESTER ROAD
+ FRAMINGHAM, MASSACHUSETTS 01701 e
TELEPv40NE E17-4721100 l
September 16, 1986 U.S. Nuclear Regulatory Commission Office of Inspection & Enforcement Region I 631 Park Avenut King of Prussia, PA 19406 Attn: Dr. Thomas E. Murley Regional Administrator
Reference:
a) License No. DPR-28 (Docket No. 50-271)
Dear Sir:
Subject:
Notification of Potential Existence of a i Defect in Accordance with 10 CFR 21.21 I In accordance with the provisions of 10CFR21, Section 21, we are hereby notifying you that we have obtained information indicating that a defect may exist with respect to solenoid valve rebuild kits supplied by General Electric Company.
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 4+4-~ WM Warren P urphy -
Vice President and l Manager of Operations
/dm 8802290045 060916
- l PDR ADOCK 050002"/1 - '
S DCD ~ ".
,I
. o ENCLOSURE I COMPANY INFORMING Vermont Yankee Nuclear Power Corporation THE COMMISSION RD 5, Box 169 Ferry Road Brattleboro, Vermont 05301 FACILITY Vermont Yankee Nuclear Power Corporation PO Box 157 Governor Hunt Road Vernon, Vermont 05354 FIRM SUPPLYING General Electric Company COMPONENT 175 Curtner Avenue San Jose, California 95125 NATURE OF DEFECT During the 1985-86 refueling outage, all Hydaulic Control Unit (HCU) scram solenoids were rebuilt based on a General Electric recommendation and with rebuild kits supplied by General Electric. It should be noted that the replace-ment parts kits are supplied by ASCO to GE as non-safety commercial grade parts.
Following completion the the solenoid rebuilding, all control rods were single rod scram tested, which revealed that one control rod failed to insert following inspection of the failed HCU and subsequent testing. It was determined that the failure was attributed to a detached core assembly from the solenoid core spring. On additional detached spring was found during additional testing.
There are two solenoids on each HCU arranged in a two-out-of-two logic.
In thi s arrangement, both solenoids must be de-energized to allow the associated control rod to scram. Since the solenoids are a de-energized to scram valve, they are designed such that, when energized, the core assembly is being pulled into the solenoid coil and the core spring is in compression. When de-energized, the solenoid coil loses its attraction to the core assembly which allows the core spring to push the core away from the solenoid coil. This action seals off the supply air and exhausts the valve air which scrams the control rod. However, if the core assembly has become detached from the core spring, no movement of the core assembly will occur when the solenoid is de-energized, which prevents rod movement. Additionally, since the HCU solenoids are arranged in a two-out-of-two logic, if either one of the solenoids f ail, rod insertion is prevented.
DATE ON WHICH OEFECT WAS DETECTED The failure to scram event occurred on June 13-28, 1986. A potential Part 21 Report Evaluation was initiated on July 23, 1986.
NUMBER OF COMPONENTS AT FACILITY Vermont Yankee has 180 of this type of solenoid in use.
1.t .- =A CORRECTIVE ACTIONS
- 1) ' Vermont Yankee replaced all 178 HCU ' scram solenoid internalsi plus 2 scram-discharge. volume, solenoid valve internals,;with new replacement. kits which were 100% inspected to tolerances specified on manufacturing drawings.,
This inspection was' performed by the Automatic Switch Company ~(ASCO),.the-manuf acturer, aM witnessed.by Vermont Yankee and General Electric.
This inspection found 127 of the 200 kits inspected to be out of manufac-turer's tolerance. However, it-was concluded that-the out-of-spec com-ponents would not . contribute to the' problem nor. were tlwy of any consequence. It should be noted that; Vermont Yankee did not accept any components that were'out of tolerance.
- 2) A pre-operational functional. test consisting of a full scram air only time testing was performed.
- 3) All 89 controls rods were successfully single rod scram. tested at tem--
perature and pressure (between 20% and 30% power levels) during startup.
1 )
RELATED ADVICE L Vermont Yankee recommends other BWR operators review in detail RICSIL No. l 008 "Control Rod Drive Scram Anomaly". Utilities'should also initiate inspec-l tion and testing GE replacement Pilot Head Kits No. FV 204-139 for proper ,
spring to core attachment. l During the review and inspection of the above mentioned discrepancies, another problem with the same batch of replacement kits was found. -This problem, however, was not considered to be a safety concern as the problem would i i be discovered during scram time testing and as such was not reportable under j 10CFR21.21. The problem as identified by Vermont Yankee denit with a parts mix- '
- up with the core assembly and the Zytel needle which protrudes out the end. The l
) problem was found to be the size of the hole (a standard core assembly for
- another type valve) in the core assembly was 1=rger than it should be for this a
valve, thus allowing the Zytel needle to protrude further than it should.
I l This additional protrusion would not allow the valve to exhaust its air, j
upon a scram signal, as rapidly as designed. The valves did work, however, not l within the time allowed by Technical Specifications.
i
- It is recommended that utilities inspect for this problem, as well as the spring attachment, in an effort to preclude problems'during startup activities.
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