ML20086H295
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| ML20086H295 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 09/29/1972 |
| From: | Rosalyn Jones VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20086H282 | List: |
| References | |
| AO-50-271-72-06, AO-50-271-72-6, VYV-2269, NUDOCS 8401160328 | |
| Download: ML20086H295 (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 |
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VERMONT YANKEE NUCLEAR POWER CORPORATION k
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sevcwTv anven onovc sinccT RuTomo, Vmmont' osvon WV-2269 P. o. oox is7 l vsnNoN. VERMONT 05S54 September 29, 1972 United States Atomic Energy Comission' Directorate of Regulatory Operations, Region I 970 Broad Street Newark, New Jersey 07102 '
REFERENCE:
Operating License DPR-28 Docket No. 50-271 Abnomal Occurrence No. A0-72-06 Gentlemen:
As defined by Technical Specifications for the Vermont Yankee Nuclear Power Station, Section 6.7. A.c, we are reporting the following "~
Abnortul Occurrence as A0-72-06 and confiming our teleptione conversation with your office on this date.
At approximately 10:30 a.n. on September 28, during conduct of the monthly curve 111ance on the Reactor Core Isolation Cooling (RCIC) System instrumentation, one channel of the steam line high d/p isolation failed to operate at 160 (+ 15) inches of water as required by Table 3.2.2.3 of Technical Specifications. At this timo the Reactor was operating at approximately 18% power. Inspection revealed that the common lead between the conduit fitting and the switch torninal board f or DPIS 13-84 was found to be broken.
The broken lead was it: mediately repaired and the switch was functionally tented end verified to be operable. This remedial action was completed in a.
tine span that precluded the necessity of further in:mediato action.
Very truly yours, DOh o[hghjjg VERMONT YANKEE NUCLEAR PWER CORPORATION
- h. <
ftL ' Robert F. Jone -
Plant Superintendent IME/kbd
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