|
|
Line 12: |
Line 12: |
| | document report number = LER-81-026-03L, LER-81-26-3L, NUDOCS 8204230076 | | | document report number = LER-81-026-03L, LER-81-26-3L, NUDOCS 8204230076 |
| | package number = ML20049H185 | | | package number = ML20049H185 |
| | document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT | | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
| | page count = 1 | | | page count = 1 |
| }} | | }} |
Latest revision as of 15:58, 15 March 2020
|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000271/LER-1993-0121993-10-0707 October 1993 LER 93-012-00:on 930908,noted That Containment Air Valve & TIP Found to Have Seat Leakage Above That Permitted by Ts. Caused by Leakage Through Check Valve.C/As Will Be Reported in Suppl to LER.W/931007 Ltr 05000271/LER-1993-0101993-08-31031 August 1993 LER 93-010-00:on 930803,fire Protection Valve V76-420 Has Not Been Cycled Through Complete Cycle of Full Travel,Per TS 4.13.B.d.Caused by Human Error.Applicable Surveillance Procedure Revised to Include V76-420.W/930831 Ltr 05000271/LER-1993-0041993-08-19019 August 1993 LER 93-004-01:on 930225,discovered That Surveillance for Jet Pumps Not Performed During Single Loop Operations Due to Inadequate Plant Procedures.Procedures OP-4110 & OP-2428 revised.W/930819 Ltr 05000271/LER-1993-0051993-08-13013 August 1993 LER 93-005-01:on 930406,concluded Control Rod Scram Times Not in Compliance W/Ts Section 3.3.C.Caused by Faulty Scram Solenoid Pilot Valves.Solenoid Valves rebuilt.W/930813 Ltr 05000271/LER-1993-0091993-08-13013 August 1993 LER 93-009-00:on 930716,B Train of RHR Sys Declared Inoperable.Caused by Personnel Error Re Failure to Initiate Rev to Calibration Procedure OP 4347.Instrument re-calibrated & OP 4347 revised.W/930813 Ltr 05000271/LER-1990-0081990-06-29029 June 1990 LER 90-008-00:on 900529,identified That Cables Providing Power to post-accident Monitoring Instrument Loops Not Routed,Per Required Separation Criteria.Caused by Combination of Factors.Design Change prepared.W/900629 Ltr 05000271/LER-1987-003, :on 880412,personnel Found Functional Testing Not Been Tested in Accordance W/Tech Spec Requirements. Caused by Programmatic Tracking Program.Programmatic Tracking Sys Revised as Described in LER 87-031988-05-10010 May 1988
- on 880412,personnel Found Functional Testing Not Been Tested in Accordance W/Tech Spec Requirements. Caused by Programmatic Tracking Program.Programmatic Tracking Sys Revised as Described in LER 87-03
05000271/LER-1983-009, Followup LER 83-009/01T-0:on 830321,primary Containment Isolation Sys Isolation of Containment Ventilation Sys Occurred.Caused by Mods to Reactor Protection Sys Motor Generator.Fuel Handling Activities Suspended1983-04-0101 April 1983 Followup LER 83-009/01T-0:on 830321,primary Containment Isolation Sys Isolation of Containment Ventilation Sys Occurred.Caused by Mods to Reactor Protection Sys Motor Generator.Fuel Handling Activities Suspended 05000271/LER-1981-030, Updated LER 81-030/03L-1:cracks Found on Internal Surface of Valve Bodies & Seating Surfaces of Reactor Water Cleanup Valves Attributed to Surface Shrinking of Casting & Intergranular Stress Corrosion Cracking,Respectively1982-07-0101 July 1982 Updated LER 81-030/03L-1:cracks Found on Internal Surface of Valve Bodies & Seating Surfaces of Reactor Water Cleanup Valves Attributed to Surface Shrinking of Casting & Intergranular Stress Corrosion Cracking,Respectively 05000271/LER-1981-0261981-11-0303 November 1981 LER 81-026/03L-0:on 811005,during Weekly Review of Surveillance Test Data,Discovered That Max Monthly Interval for Functional Test of Atws/Rpt Sys Exceeded by 4 Days. Caused by Oversight in Scheduling ML20064H2211978-12-13013 December 1978 /03L-0 on 781113:during Weekly Surveillance Re Radiological Environ Prog,Air Pump Motor Was Found Inoper. Time Meter Indicated Pump Had Operated Only 0.4 Hours.Air Pump Replaced & New Weekly Air Sample Initiated ML20064E3281978-11-13013 November 1978 /03L-0 on 781014:during Surveillance Test of Main Steam Isolution Valves,V2-86C Closed in 2.6 Seconds Rather than 3-5 Seconds Req in Tech Spec 4.7.D.1.a.1.Caused by Closing Speed Control Valve Coming Loose from Actuator ML20064E3101978-11-13013 November 1978 /03L-0 on 781016:weekly Review of Completed Surveillance Test Following Plant Startup Noted That Monthly Hydrogen Detector Functional Test Was Not Performed Due to Personnel Error ML20064H2291978-08-10010 August 1978 /03L-1 on 780626:during Increase of Reactor Pwr, Noted That Critical Pwr Ratio in 4 Symmetrically Located Fuel Bundles Was Below Tech Spec Values.Caused by Pwr Increasing Xenon Transient ML20064H1681978-07-25025 July 1978 /03L-0 on 780629:during Steady State Oper Motor Control Ctr 893 Lost Voltage Because B Uninterruptible Pwr Supply (UP5) Tripped Due to Blown Inverter Leg Fuse.Failed Components Replaced & Operability Test Performed ML20064H2051978-07-24024 July 1978 /03L-0 on 780625:during Steady State Oper,Noted That Drywell Atmospheric Temp Recorder TR-1-149 Was Inoperable.Caused by Recorder Failure Due to Broken Cord on Chart Drive Mechanism ML20064H1741978-07-24024 July 1978 /03L-0 on 780626:during Reactor Pwr Increase Noted That Local Critical Pwr Ratio in 4 Symmetrically Located Fuel Bundles Was Lower than Tech Spec Levels.Caused by Pwr Increasing Xenon Transient ML20064H1321978-07-24024 July 1978 /03L-0 on 780612:during Steady State Oper,Noted That Drywell Atmospheric Temp Recorder TR-1-149 Was Inoperable.Recorder Failed Due to Failed Idler Assembly 05000271/LER-1976-005, Telecopy LER 76-005:on 760217,portion of Procedure Associated W/Securing Plant from Shutdown Cooling Mode Not Performed.Caused by Failure of Plant Personnel to Follow Appropriate Plant Procedure1976-02-18018 February 1976 Telecopy LER 76-005:on 760217,portion of Procedure Associated W/Securing Plant from Shutdown Cooling Mode Not Performed.Caused by Failure of Plant Personnel to Follow Appropriate Plant Procedure 05000271/LER-1975-003, Corrected LER 75-003:on 750204,core Spray Sys Pump Discharge Pressure Sensor PS-14-44A Actuated at 82 Psig.Caused by Setpoint Drift.Sensor replaced.W/750218 Ltr1975-02-14014 February 1975 Corrected LER 75-003:on 750204,core Spray Sys Pump Discharge Pressure Sensor PS-14-44A Actuated at 82 Psig.Caused by Setpoint Drift.Sensor replaced.W/750218 Ltr 1993-08-31
[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
[Table view] |
LER-2081-026, |
Event date: |
|
---|
Report date: |
|
---|
2712081026R00 - NRC Website |
|
text
NRC F.OZM 366 U. S. NUCLEAR REGULATORY COMMISSION O 8'-26'3' LICENSEE EVENT REPORT '8" I)
~
e ' CONTROL BLOCK: l l l. l -} l l@ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 R lVlTlVlYlSl1l@l0 7 8 9 LICENSEE CODE 10 l- l0 l0 l0 LICEkSE 14 15 l 0 l NUMBER 0 l- l 0 l 0 l@l 4 l 1 LICENSE 25 26 l 111l 1l@l$7 CAT TYPE JG l
5d l@
CON'T L2_Li !
5O E l Ll@ l 0l Sl 0l 0j 0l 2l 7l l@l1 l 010 l 5 l 8 l 1 l@l 1l 110l '4 75 3l 8 l 1l@
REPORT OATE 30 4 60 61 OOCKET NUMSER 68 69 EV ENT DATE 1 EVENT OESCRIPTION AND PROBA3LE CONSEQUENCES h 10121 l During the weekly review of surveillance testing data, it was discovered that the 1 1o 13_; l maximum monthly interval was exceeded by four days for the functional test of the i 10141 l ATWS/RPr SyEtem required by T. S. 4.2.1. Since the test was in med iat ely and l 10 I s I I successfully performed there were no consequences to the health and safety of the 1 10 ls l l public. The only similar occurrence reported to the commission in the last five i 10l7ll years was R0 80-34 /3L. I 10181l I SYSTEM CAUSE C 8.USE COMP. VA LV E CODE CODE SUJCODE COMPONENT CODE SUSCODE SUSCODE ITITI I z l z l@ L^_J@ I c l@ I z l z i z i z i z l z lO Lz.J@ L?J @
7 8 9 10 11 12 13 18 19 20
_ SE QUENTI AL OCCURRENCE REPORT REVISION EVENT YE AR REPORT NO. CODE TYPE N O.
Oag s LER RO 18111 21 22 L--J
??
10121sl 24 26 1-1 27 10131 28 29 In l Jo L.J 31 LO_J 32 AK N AC ON ON PL NT MET HOURS SS ITT FOR 6. SUPPL MANUFAC RER I33 xi@lJ4Hi@ Ih z l@ L_zj@ I01010101 Ls.J@ lNl@ lN lh lz l9 19 19 lh 06 3 '. 40 di 42 43 44 47 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS l i l 0 l l The test was not done because of an oversight in scheduling. The test was immedintel li li l l ly and successfully completed and applicable personnel have been rein e rurena <n thol i , , y y l implementation of thic surveillance testing program. [
liI3Il l l i 141 l l 7 8 9 80 ST S % POWER OTHER STATUS CISCO RY DISCOVERY OESCRIPTION l1 l 5 l l E l@ l0 l9 I6 l@l NA l lBl@l Document Review l A TivlTY CO TENT nELEASED OPRELEASE AMOUNT OF ACTivlTY LOCATION OF RELEASE lil6l 7 8 9 h 10 l
t1 NA 44 l l 45 ,
NA 80 l
PERSONNEL EXPOSURES NUMBER TYDE DESCRIPTION 39 dgf l i 12 l 10 I o l 0 l@l z l@l -
NA l .
PERSO~NE'L ,N,UliES m M.ER oESCRiPTiO~@
li la 8l 9lo in In l@l 7 11 12 NA 80 l
LOSS OP OR DAMAGE TO FACILITY TYPE DESCRI8 TION I i i O I l.zj@l NA l 7 8 3 10 80 ISSUE D
- u l o l Lw_.l8l ESCRIPTION NA l llllllll1l l1l; 7 8 9 10 68 69 80 7, 820"230076 811103 Warren P. Murphy PHONE: (802) 257-7711 2 PDR ADOCK 05000271 S PDR