ML20086H307
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| ML20086H307 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 09/26/1972 |
| From: | Rosalyn Jones VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20086H282 | List: |
| References | |
| VYV-2258, NUDOCS 8401160346 | |
| Download: ML20086H307 (1) | |
Similar Documents at Vermont Yankee | |
|---|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20086D3171975-09-0202 September 1975
[Table view]AO 75-018:on 750901,steam Supply Valve 13-15 Failed to Close When Control Switch Placed in Closed Position.After Repeated Attempts,Valve 13-15 Responded & Cycled Closed.Valve Stroked,Timed to Ensure Operability & Declared Inoperable ML20086D3671975-07-25025 July 1975 Telecopy AO 75-014:on 750725,head Gasket on Gland Seal Exhaust Condenser Failed.Replacement of Failed Gasket Initiated Immediately.Condenser Repaired & HPCI Sys Tested & Verified Operable ML20086D3751975-07-0808 July 1975 Telecopy AO 75-013:on 750707,injection Valve CS-11B Failed to Open When Control Switch Placed in Open Position.Valve Immediately Opened Manually to Full Open Position.Sys Aligned to Normal Standby Mode ML20086E0451975-06-0909 June 1975 AO 75-12:on 750609,standby Liquid Control Pump B Delivered High Flow Rate.Cause Under Investigation ML20086E0721975-05-12012 May 1975 AO 75-11:on 750511,intermediate Range Monitor Channel E Failed to Respond to Increasing Neutron Flux Level.Cause Not Stated.Reactor Protection Sys Trip Sys a Manually Tripped ML20086E1451975-04-30030 April 1975 AO 75-10:on 750429,low Water Level Switch Associated W/ Differential Pressure Indicating Sensor 2-3-58B Actuated Low.Switch Adjusted ML20086E1551975-04-0808 April 1975 AO 75-08:on 750408,air Ejector Suction Valve Isolation Time Delay Relay Timer 17-157A Actuated Slow.Cause Not Stated. Timer Reset ML20086E2221975-02-21021 February 1975 AO 75-05:on 750220,sample Accumulator Isolation Valve to Condenser OG-9069 Found Shut,Rendering Radiation Monitors Inoperable.Cause Not Stated.Valve Immediately Opened ML20086E2441975-02-0505 February 1975 AO 75-04:on 750204,gradual Flow Reduction Discovered in Air Ejector Offgas Monitoring Sys.Caused by Removal of 3-way Solenoid Valve for Cleaning & Repair.Valve Replaced ML20086E3461975-02-0505 February 1975 AO 75-03:on 750204,spray Sys Pump Discharge Pressure Sensor PS-14-44A Actuated at 82 Psig,Below Tech Spec Min. Sensor Replaced & Calibr ML20086E3881975-01-0909 January 1975 AO 75-01:on 750108,LPCI Low Reactor Pressure Permissive Switches on Instrument 2-3-52D Actuated High.Caused by Improper Calibr Technique.Switch Reset ML20086E3851975-01-0909 January 1975 AO 75-02:on 750108,personnel Discovered That Carbon Filter Beds Changed on Standby Gas Treatment Sys Train a Instead of Planned Train B.Carbon Beds in Train B Replaced ML20086E4071974-12-20020 December 1974 AO 74-17:on 741219,suppression Chamber Outboard Sample Valve Stuck in Open Position.Caused by Accumulation of Dirt Causing Binding of Solenoid Piston.Valve Cleaned ML20086E4001974-12-16016 December 1974 AO 74-16:on 741214,containment Air Sampling Sys Found Inoperable.Caused by Nonfunctioning Heat Tracing Circuit.Sys Repaired ML20086E4081974-12-0303 December 1974 AO 74-15:on 741202,scram Discharge Vol High Level Scram Switch 3-231A Would Not Actuate Respective Scram Relay. Caused by Fissure in Switch Casement.Switch Replaced ML20086E4111974-10-16016 October 1974 AO 74-14:on 741015,primary Containment Leak Discovered. Caused by Missing 1/2-inch Test Connection Plug on Drywell Penetration X-16A.Plug Installed ML20086E4181974-07-15015 July 1974 AO 74-11:on 740705,08 & 09,both Plant Stack Monitoring Sys Failed.Caused by Direct Lightning Strikes to Ventilation Stacks During Electrical Storms.Radiation Exposure to Personnel Negligible ML20086E4281974-07-0808 July 1974 AO 74-11:on 740705,both Plant Stack Monitoring Sys Failed Following Direct Lightning Strike During Severe Electrical Storm.Generator Turbine Tripped Causing Reactor Scram.Repair of Damaged Equipment Complete ML20086E4601974-07-0303 July 1974 AO 74-09:in 740625,movements of LPCI Loop Break Detection Logic Differential Pressure Indicating Switches 2-129B & 2-129C Found Sticking,Causing Pointer to Log Input Pressure. Caused by Frequent Switch Actuation ML20086E4321974-07-0303 July 1974 AO 74-10:on 740626,HPCI Inverter Tripped,Rendering HPCI Sys Inoperable.Caused by Poor Connection Between Printed Circuit Board & Companion Jack.Connections Cleaned ML20086E4371974-06-27027 June 1974 AO 74-10:on 740626,HPCI Inverter Tripped,Rendering HPCI Sys Inoperable.Cause Not Stated.Inverter Replaced ML20086E4731974-06-26026 June 1974 AO 74-09:on 740625,movements of LPCI Loop Break Detection Logic Differential Pressure Indicating Switches 2-129B & 2-129C Sluggish,Causing Pointer to Lag Input Pressure.Switch 2-129B Replaced & 2-129C Placed in Trip Condition ML20086E5001974-06-13013 June 1974 AO 74-08:on 740525,water Discovered in Ventilation Ducting & in Instrument Penetrations at Biological Shield.Caused by Leak on Control Rod Drive Hydraulic Sys Return Line to Reactor Vessel,Due to Stress Corrosion Cracking ML20086E5761974-06-0404 June 1974 AO 74-08:detailed Rept & Analysis Including Appropriate Corrective Measures Taken Re 740526 Incident Will Be Submitted within 20 Days of Occurrence ML20086E5831974-05-28028 May 1974 AO 74-08:on 740525,water Leakage Discovered Along Reactor Vessel Wall.Caused by Leak on Control Rod Drive Hydraulic Sys Return Line to Reactor Vessel.Engineering Review & Assessment Underway ML20086E6361974-05-15015 May 1974 AO 74-07:on 740509,spike Observed on Plant Stack Gas Recorder,Resulting in Stack Release Peak Greater than Allowed by Tech Specs.Caused by Steam Packing Exhauster Operation ML20086E6391974-05-10010 May 1974 AO 74-07:on 740509,spike Observed on Plant Stack Gas Recorder,Resulting in Stack Release Peak Greater than Allowed by Tech Specs.Cause Not Stated ML20086E6521974-04-25025 April 1974 AO 74-06:on 740418,both Access Doors to North Entrance to Reactor Bldg Found Partially Open.Caused by Personnel Failing to Verify Closure.Design Adequacy Under Review ML20086E6641974-04-19019 April 1974 AO 74-06:on 740418,both Access Doors to North Entrance to Reactor Bldg Found Open.Caused by Personnel Failure to Verify Closure.Methods to Assure Closure Underway ML20086E6771974-03-11011 March 1974 AO 74-05:on 740304,LPCI Loop a Valve V10-25A Failed to Open When Control Switch Placed in Open Position.Caused by Burned Out Valve Motor.Motor Replaced ML20086E6961974-03-0505 March 1974 AO 74-05:on 740304,LPCI Valve V10-25A Failed to Open When Control Switch Placed in Open Position.Caused by Tripped Motor Breaker & Unusually Warm Motor.Motor Replaced ML20086E7131974-03-0101 March 1974 AO 74-04:on 740223,MSIV Rv 2-71B Failed to Open at Required Setpoint.Indirectly Caused by Approved vendor-recommended Mods to Certain Relief Valve Internals.Procedure Revised ML20086E7241974-02-25025 February 1974 AO 74-04:on 740223,MSIV Rv 2-71B Failed to Open at Required Setpoint.Cause Under Investigation ML20086E7321974-02-11011 February 1974 AO 74-03:on 740204,LPCI Differential Pressure Indicating Switch 2-137B Failed to Indicate Properly Upon Isolation from Normal Sys Pressure W/Bypass Valve Open.Caused by Improper Sensor over-range Stop Setting.Sensors Calibr ML20086E7541974-02-0707 February 1974 AO 74-02:on 740131,core Spray Sys Valve CS-11A Failed to Open When Control Switch Placed in Open Position.Caused by burned-out Valve Motor.Motor Replaced ML20086E7471974-02-0404 February 1974 AO 74-03:on 740204,LPCI Differential Pressure Indicating Switch 2-137B Failed to Indicate Properly Upon Isolation from Normal Sys Pressure W/Bypass Valve Open.Cause Not Stated.Sensor Replaced ML20086E7631974-02-0101 February 1974 AO 74-02:on 740131,core Spray Sys Valve CS-11A Failed to Open When Control Switch Placed in Open Position.Cause Not Stated.Surveillance Testing Completed & Sys Aligned to Standby Mode ML20086E7821974-01-31031 January 1974 AO 74-01:on 740124,reactor Scrammed,Resulting from Turbine Trip Causing Automatic Closure of All But One Msiv.Valve 2-80C Failed to Close Due to Failure of Pneumatic Pilot Valve to Actuate.Valve Assembly Returned to Vendor for Insp ML20086E7901974-01-25025 January 1974 AO 74-01:on 740124,reactor Scrammed Due to Turbine Trip, Causing Automatic Closure of All But One Msiv.Cause of Valve 2-80C Failure Not Stated ML20086E8351973-12-27027 December 1973 AO 73-34:on 731217,station Svc Water Pump a 4-kV Breaker Stationary Auxiliary Switch Assembly Rear Mounting Tie Bolt Found Disengaged from Mounting Plate.Caused by Improper Bolt Tightening During Factory Assembly ML20086E8131973-12-26026 December 1973 AO 73-35:on 731219,MSIV Relay 5A-K3C Failed to Energize During Monthly MSIV Functional Test.Caused by Limit Switch Actuating Arm Being in Wrong Position.Arm Manually Reset ML20086E8261973-12-20020 December 1973 AO 75-35:on 731219,MSIV Relay 5A-K3C Failed to Energize During Monthly MSIV Functional Test.Caused by Mispositioned Limit Switch Actuating Arm.Arm Manually Reset ML20086E8401973-12-19019 December 1973 AO 73-34:on 731217,station Svc Water Pump a 4-kV Breaker Stationary Auxiliary Switch Assembly Rear Mounting Tie Bolt Found Disengaged.Bolt Tightened ML20086D6151973-12-12012 December 1973 Updated AO 73-33:on 731204,pressure Switch Ps 14-44B Failed to Actuate at Required Setpoint,Resulting in Failure of B Core Spray Subsystem.Caused by Setpoint Drift.Switch Reset & B Core Spray Subsystem Declared Operable ML20086D6031973-12-0505 December 1973 AO 73-33:on 731204,pressure Switch Ps 14-44B Failed to Actuate at Required Setpoint,Resulting in Failure of B Core Spray Subsystem.Switch Reset & B Core Spray Subsystem Declared Operable ML20086D6271973-11-28028 November 1973 Updated AO 73-32:on 731120,during Monthly HPCI Sys Pump Operability Surveillance Test,Both Gaskets on Gland Seal Exhaust Condenser Failed.Caused by Overpressurization of Condenser.Cooler Repaired & HPCI Verified Operable ML20086D6231973-11-20020 November 1973 AO 73-32:on 731120,during Monthly HPCI Sys Pump Operability Surveillance Test,Both Gaskets on Gland Seal Exhaust Condenser Failed.Cooler Repaired & HPCI Tested & Verified Operable ML20148U1341973-11-14014 November 1973 AO 73-31:on 731107,reactor Scram Occurred During Control Rod 26-23 Friction Test.Caused by Inadequate Implementation of Administrative or Procedural Controls.Control Rod 30-23 Was Fully Withdrawn,While 26-23 Was Being Withdrawn ML20086D7391973-11-14014 November 1973 Updated AO 73-31:on 731107,reactor Scram Occurred,Initiated by high-high Flux Signal from Intermediate Range Neutron Monitoring Sys.Rod 30-23 Fully Withdrawn & Rod 26-23 Being Withdrawn for Friction Test ML20086D8991973-11-0808 November 1973 AO 73-31:on 731107,reactor Scram Occurred Based Upon High Flux Signal from Intermediate Range Neutron Monitoring Sys. Investigation Revealed Rod 30-23 Fully Withdrawn W/Rod 26-23 Withdrawn for Friction Test 1975-09-02 Category:TEXT-SAFETY REPORT MONTHYEARML20217L8831999-10-21021 October 1999
[Table view]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 |
Text
N U Q' < ~*. l n
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, .,5 e N ' V ERh10NT YANKEE N UCLEAR POWER CORPOR ATION SCVENTY GCVCN OROVE STRECT RuTi.Asn, Viq610NT 03701 VYV-2258 " "
- P. O. DOX 157 VERNON, VERMONT oS354 Sep tember 26, 1972 I
United States Atomic Energy Commission Directorate of Regulatory Operations, Region I 970 arcad Street Newark, hw Jersey 07102
REFERENCE:
Operating License DPR-28 Docket No. 50-271 Centlemen:
'!c ara reoorting the following incident f or your information.
On August 3,1972, with the reactor critical and at a pressure of approximately 600 psig, the Reactor Core Isolation Cooling (RCIC) System turbine steam admission valve (RCIC-131) failed. After a RCIC turbine run of approximately one half hour in preparation for a RCIC system quick start as a part of the startup test for the system, the RCIC-131 valve failed to close fully. Investigation revealed that a piece of metal (l" x 3" x 1/2" steel) had lodged on the valve seat and the valve motor had burned out trying to close the valve. The metal was removed, the geatbox and valve seat were inspected, and the valve motor was replaced.
The valve was then repacked, successfully tested and returned to service.
The RCIC System was not required to be operable, as defined by the Technical Specifications, because the reactor did not contain irradiated fuel at the time. The RCIC system has since been extensively tested as a part of the planned Startup Test Program and has been proven operable over a simulated reactor pressure range of 150 psig to 1180 psig.
If you have any questions concerning this incident, please contact me.
Very truly yours, 8401160346 721024 PDR ADOCK 05000271 VERMONT iANREE NUCLEAR POWER CORPORATION 7r
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