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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20154H7501998-10-13013 October 1998
Revised Notice of Violation from Insp on 971118.Violation Noted:In April 1996,licensee Made Changes to Procedures as Described in Safety Analysis Rept Without Seeking Prior Commission Approval & Changes Had Effect of Changing TS
ML20199E3161997-11-18018 November 1997
Notice of Violation from Insp on 971020-26.Violation Noted: on 971021,inspector Identified Gap in Vehicle Barrier Sys That Provided Path for Design Basis Vehicle to Gain Access to Unauthorized Proximity to Vital Area
ML20059D2141993-10-15015 October 1993
Notice of Violation from Insp on 930402-0517.Violation Noted:Licensee Determined That Records Required to Be Maintained by NRC Not Complete & Accurate in All Matl Respects
ML20150F9771988-06-29029 June 1988
Notice of Violation from Insp on 880606-09.Violation Noted: on 880512,individual Entered Radwaste Bldg W/O Being Accompanied or Provided W/Radiation Monitoring Device & on 880608,door to Radwaste Bldg Not Locked
IR 07100001/20110051987-12-0404 December 1987
Notice of Violation from Insp on 871001-1105.Violation Noted:Maint Electrician Worked More than 24 H in 48 H Period & Plant Operations Committee Meeting Held W/Chairman & Three Rather than Four Members as Required
ML20206U1861986-09-18018 September 1986
Notice of Violation from Insp on 860616-27
ML20062H6601982-08-0202 August 1982
Notice of Violation from Insp on 820607-0709
1998-10-13
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Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000397/19990011999-03-19019 March 1999
Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Major Areas Inspected:Physical Security Program
ML20154H7501998-10-13013 October 1998
Revised Notice of Violation from Insp on 971118.Violation Noted:In April 1996,licensee Made Changes to Procedures as Described in Safety Analysis Rept Without Seeking Prior Commission Approval & Changes Had Effect of Changing TS
PNO-IV-98-025, on 980615,WNP-2 Initiated Plant Shutdown as Result of Traversing Incore Probe That Could Not Be Moved. Licensee Observed Some Drive Cable Damage & Cable Wrapped Around Some Components Under Reactor Vessel1998-06-16016 June 1998
PNO-IV-98-025:on 980615,WNP-2 Initiated Plant Shutdown as Result of Traversing Incore Probe That Could Not Be Moved. Licensee Observed Some Drive Cable Damage & Cable Wrapped Around Some Components Under Reactor Vessel
ML20199E3161997-11-18018 November 1997
Notice of Violation from Insp on 971020-26.Violation Noted: on 971021,inspector Identified Gap in Vehicle Barrier Sys That Provided Path for Design Basis Vehicle to Gain Access to Unauthorized Proximity to Vital Area
IR 05000397/19970071997-11-18018 November 1997
Partially Withheld Insp Rept 50-397/97-07 on 971020-26. (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support Re Vehicle Barrier Sys Which Was Consistent W/Summary Description & Accurately in Security Plan
IR 05000397/19970061997-06-0909 June 1997
Insp Rept 50-397/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Insp Consisted of Review of Licensee Planned & Implemented Activities Associated W/Isi Program
IR 05000397/19970021997-03-0606 March 1997
Insp Rept 50-397/97-02 on 970127-31 & 0212-14.No Violations Noted.Major Areas Inspected:Engineering & Plant Support Security
IR 05000397/19960231996-12-16016 December 1996
Insp Rept 50-397/96-23 on 961118-22.No Violations Noted. Major Areas Inspected:Engineering & Plant Support
ML20134Q0381996-11-21021 November 1996
EN-96-084:on 961126,notice of Proposed Imposition of Civil Penalty in Amount of $100,000 Issued to Licensee.Action Based on Several Instances Where Surveillances Not Performed & Mode Changes Made W/O Assurances That Equipment Operable
PNO-IV-95-007, on 950218,plant Reactor Scrammed from 80% Power Due to Turbine Trip.News Media Was Notified of Event1995-02-21021 February 1995
PNO-IV-95-007:on 950218,plant Reactor Scrammed from 80% Power Due to Turbine Trip.News Media Was Notified of Event
PNO-V-93-021, on 931201,chemical Spill in Radwaste Building. Caused by Addition of Oxidizing Agent,Hydrogen Peroxide. Employees Working on Floor Were Moved to Different Part of Plant1993-12-0202 December 1993
PNO-V-93-021:on 931201,chemical Spill in Radwaste Building. Caused by Addition of Oxidizing Agent,Hydrogen Peroxide. Employees Working on Floor Were Moved to Different Part of Plant
ML20059D2141993-10-15015 October 1993
Notice of Violation from Insp on 930402-0517.Violation Noted:Licensee Determined That Records Required to Be Maintained by NRC Not Complete & Accurate in All Matl Respects
IR 05000397/19930281993-08-26026 August 1993
Insp Rept 50-397/93-28 on 930809-13.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program, Emergency Detection & Classification,Notification & Communication
PNO-V-93-004, on 930121,automatic Reactor Scram Received Due to Low Level in Reactor Pressure Vessel.Licensee Estimates That Plant Will Be Shut Down for Repairs & Maint for 3 to 5 Days.Inspector Onsite During Event.Press Release Issued1993-01-21021 January 1993
PNO-V-93-004:on 930121,automatic Reactor Scram Received Due to Low Level in Reactor Pressure Vessel.Licensee Estimates That Plant Will Be Shut Down for Repairs & Maint for 3 to 5 Days.Inspector Onsite During Event.Press Release Issued
IR 05000397/19920341992-12-30030 December 1992
Insp Rept 50-397/92-34 on 921207-11.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program
PNO-V-92-024, on 920711,while Retesting Main Steam SRV at Approx 14% Reactor Power,Srv 3B Opened When Operated from Control Room But Would Not Close.Reactor Operators Reduced Reactor Pressure in Effort to Reseat Valve1992-07-13013 July 1992
PNO-V-92-024:on 920711,while Retesting Main Steam SRV at Approx 14% Reactor Power,Srv 3B Opened When Operated from Control Room But Would Not Close.Reactor Operators Reduced Reactor Pressure in Effort to Reseat Valve
PNO-V-91-031, on 911119,licensee Declared Unusual Event Following Low Reactor Pressure Vessel Level Condition W/Eccs Injecting.Reactor Tripped on Turbine Trip.All ECCS Sys Responded as Designed1991-11-19019 November 1991
PNO-V-91-031:on 911119,licensee Declared Unusual Event Following Low Reactor Pressure Vessel Level Condition W/Eccs Injecting.Reactor Tripped on Turbine Trip.All ECCS Sys Responded as Designed
ML20203C2231991-06-14014 June 1991
PNO-V-91-04B on 910614,Region V Issued Rev 3 to CAL Concerning Actions to Be Taken by WPPSS Subsequent to Unsuccessful Simulator Requalification Retake Exam Performed 910605-06
PNO-V-90-049, on 901207,w/plant Operating at Full Power, Explosion Occurred in Area of B Phase Insulator of Plant Main Transformer,Which Caused Turbine & Reactor Trip.Unusual Event Was Declared Due to Explosion1990-12-0707 December 1990
PNO-V-90-049:on 901207,w/plant Operating at Full Power, Explosion Occurred in Area of B Phase Insulator of Plant Main Transformer,Which Caused Turbine & Reactor Trip.Unusual Event Was Declared Due to Explosion
PNO-V-90-041, on 901024,licensee Declared Unusual Event After Determining That Vital & non-vital Instrument Power Supplies Interconnected Through Certain Sys Instrumentation1990-10-25025 October 1990
PNO-V-90-041:on 901024,licensee Declared Unusual Event After Determining That Vital & non-vital Instrument Power Supplies Interconnected Through Certain Sys Instrumentation
PNO-IV-90-028, on 900603,while Attempting to Energize Station Normal Auxiliary Power Transformers,Short Circuit Failure in Bus Works for 25 Kv Sys.Fire Brigade Responded But No Fire Was Reported.Event Under Investigation1990-06-0404 June 1990
PNO-IV-90-028:on 900603,while Attempting to Energize Station Normal Auxiliary Power Transformers,Short Circuit Failure in Bus Works for 25 Kv Sys.Fire Brigade Responded But No Fire Was Reported.Event Under Investigation
PNO-V-88-054, on 880824,licensee Declared Unusual Event as Result of Increase in Unidentified Leakage to Level Above TS Limit of 5 Gpm.Reactor Was Later Shutdown & Unidentified Leakage Rate Had Correspondingly Decreased to Approx 8 Gpm1988-08-24024 August 1988
PNO-V-88-054:on 880824,licensee Declared Unusual Event as Result of Increase in Unidentified Leakage to Level Above TS Limit of 5 Gpm.Reactor Was Later Shutdown & Unidentified Leakage Rate Had Correspondingly Decreased to Approx 8 Gpm
IR 05000397/19880221988-06-29029 June 1988
Insp Rept 50-397/88-22 on 880606-09.Violation Noted.Major Areas inspected:880512 Radioactive Resins Spill in Radwaste Bldg Which Resulted in Declaration of Unusual Event & Facility Tour
ML20150F9771988-06-29029 June 1988
Notice of Violation from Insp on 880606-09.Violation Noted: on 880512,individual Entered Radwaste Bldg W/O Being Accompanied or Provided W/Radiation Monitoring Device & on 880608,door to Radwaste Bldg Not Locked
PNO-V-88-013, on 880213,plant Experienced Condenser Tube Failure & Shut Down Manually Scramming Plant from 35% Power. on 880214,reactor Bldg Air Supply Fan Started W/O Trip Circuit Being Energized.Cause Under Investigation1988-02-16016 February 1988
PNO-V-88-013:on 880213,plant Experienced Condenser Tube Failure & Shut Down Manually Scramming Plant from 35% Power. on 880214,reactor Bldg Air Supply Fan Started W/O Trip Circuit Being Energized.Cause Under Investigation
IR 07100001/20110051987-12-0404 December 1987
Notice of Violation from Insp on 871001-1105.Violation Noted:Maint Electrician Worked More than 24 H in 48 H Period & Plant Operations Committee Meeting Held W/Chairman & Three Rather than Four Members as Required
IR 05000397/19870271987-12-0303 December 1987
Insp Rept 50-397/87-27 on 871001-1105.Violations Noted.Major Areas Inspected:Control Room Operations,Esf Status, Surveillance & Maint Programs,Lers,Special Insp Topics & Licensee Action on Previous Insp Findings
PNO-V-87-079, on 871126,digital Voltmeter Connected to Wrong Terminal Resulting in Inadvertent Opening of Safety Relief Valve 2D.Caused by Technician Error.Position of Safety Relief Valve Identified & Shut1987-11-27027 November 1987
PNO-V-87-079:on 871126,digital Voltmeter Connected to Wrong Terminal Resulting in Inadvertent Opening of Safety Relief Valve 2D.Caused by Technician Error.Position of Safety Relief Valve Identified & Shut
ML20236T8241987-10-30030 October 1987
Exam Rept 50-397/OL-87-03 on 870922-30.Exam Results:Four Out of Six Reactor Operator Candidates & Eight Out of Eleven Senior Reactor Operator Candidates Passed Exams.Sample Test & Other Supporting Info Encl
ML20236G3791987-10-26026 October 1987
PNS-V-87-008:on 871024,licensed Plant Operator Reportedly Arrested by Kennewick City Police Dept & Charged W/Discharge of Firearm within City Limits & Reckless Endangerment. Licensee Suspended Employee Unescorted Access to Plant
PNO-V-87-024A, on 870322,reactor Manually Tripped Due to Loss of Feedwater.Caused by Mechanical Failure of 1/4-amp Fuse in Feedwater Control Sys.Rcic Sys Operated Properly.Plant Restarted on 8703241987-03-25025 March 1987
PNO-V-87-024A:on 870322,reactor Manually Tripped Due to Loss of Feedwater.Caused by Mechanical Failure of 1/4-amp Fuse in Feedwater Control Sys.Rcic Sys Operated Properly.Plant Restarted on 870324
PNO-V-87-024, on 870322,both Main Feedwater Pumps Lost Suction Pressure & Tripped.Plant Operator Manually Tripped Reactor Upon Losing All Feedwater Flow.Reactor Vessel Level Restored & Heat Manually Removed.Investigation Pending1987-03-23023 March 1987
PNO-V-87-024:on 870322,both Main Feedwater Pumps Lost Suction Pressure & Tripped.Plant Operator Manually Tripped Reactor Upon Losing All Feedwater Flow.Reactor Vessel Level Restored & Heat Manually Removed.Investigation Pending
ML20205G6601987-03-20020 March 1987
Exam Rept 50-397/OL-87-02.Requalification Program Evaluated as Satisfactory,Per Rev 0 to NUREG-1021 & WT Russell 860522 Memo Re Listed Requirements
PNO-V-87-022, on 870319,licensee Found Pressure Switch on Discharge Side of RHR Sys Pump B Isolated.Licensee Unisolated Switch & Restored Sys to Full Operability.Region V Followup Continuing1987-03-20020 March 1987
PNO-V-87-022:on 870319,licensee Found Pressure Switch on Discharge Side of RHR Sys Pump B Isolated.Licensee Unisolated Switch & Restored Sys to Full Operability.Region V Followup Continuing
IR 05000397/19870031987-03-18018 March 1987
Insp Rept 50-397/87-03 on 870223-27.No Violations Noted. Major Areas Inspected:Calibr of Instrumentation,Ie Bulletin Followup,Licensee Action on Previous Insp Findings,Licensee Action on Items of Noncompliance & Part 21 Followup
IR 05000397/19870011987-03-0303 March 1987
Insp Rept 50-397/87-01 on 870104-0214.No Violations or Deviations Identified.Major Areas Inspected:Control Room Operations,Esf Status,Surveillance Programs,Maint Topics, Lers,Special Insp Topics & Listed Insp Procedures
PNO-V-87-015, on 870220,shutdown Commenced Due to Decreasing Lubrication Oil Pressure to Turbine Bearings.Caused by Flange or Pipe Leak Inside Lube Oil Reservoir.Shutdown Will Continue for Approx 4 to 6 Days1987-02-20020 February 1987
PNO-V-87-015:on 870220,shutdown Commenced Due to Decreasing Lubrication Oil Pressure to Turbine Bearings.Caused by Flange or Pipe Leak Inside Lube Oil Reservoir.Shutdown Will Continue for Approx 4 to 6 Days
IR 05000397/19860371987-01-16016 January 1987
Insp Rept 50-397/86-37 on 861116-870103.No Violations or Deviations Identified.Major Areas Inspected:Esf Status.Lers, Surveillance Program,Maint Program,Special Insp Topics & Licensee Action on Previous Insp Findings
IR 05000397/19860381987-01-0707 January 1987
Insp Rept 50-397/86-38 on 861124-26 & 1215-19.No Violations Noted.Major Areas Inspected:Gaseous Waste Sys,Liquids & Liquid Wastes,Facilities & Equipment,Followup on IE Info Notices & Enforcement Items
PNO-V-86-084, on 861120,plant Shut Down Due to Inoperability of Acoustic Monitor for Safety Relief Valve 5c.Caused by Lack of Environ Qualification Documentation for Connector. Investigation Underway.Plant Will Be Restarted on 8611251986-11-20020 November 1986
PNO-V-86-084:on 861120,plant Shut Down Due to Inoperability of Acoustic Monitor for Safety Relief Valve 5c.Caused by Lack of Environ Qualification Documentation for Connector. Investigation Underway.Plant Will Be Restarted on 861125
IR 05000397/19860261986-11-19019 November 1986
Insp Rept 50-397/86-26 on 860915-20.No Violations Noted. Major Areas Inspected:Emergency Preparedness Exercise & Associated Critique & Followup on Open Items Identified During Previous Insps
PNO-V-86-078, on 861107 & 09 Increased Vibration from Reactor Recirculating Water Pump a Occurred.Licensee Reduced Reactor Power & Shifted Pumps Into Low Frequency Operation, Decreasing Vibration Level1986-11-12012 November 1986
PNO-V-86-078:on 861107 & 09 Increased Vibration from Reactor Recirculating Water Pump a Occurred.Licensee Reduced Reactor Power & Shifted Pumps Into Low Frequency Operation, Decreasing Vibration Level
PNO-V-86-064A, on 860918,licensee Declared Alert Due to Tornado Warnings & High Winds.Train a Svc Water Sys out-of- Svc Due to Fire in Svc Water Pump House.Licensee Also Experiencing Low Fire Main Header Pressure1986-09-18018 September 1986
PNO-V-86-064A:on 860918,licensee Declared Alert Due to Tornado Warnings & High Winds.Train a Svc Water Sys out-of- Svc Due to Fire in Svc Water Pump House.Licensee Also Experiencing Low Fire Main Header Pressure
PNO-V-86-064, on 860918,licensee Declared Unusual Event Due to High Winds of 85 Mph.Svc Water Pump B out-of-svc Resulting in Emergency Diesel Generator B Being out-of-svc. Rupture in Low Pressure Fire Main Also Reported1986-09-18018 September 1986
PNO-V-86-064:on 860918,licensee Declared Unusual Event Due to High Winds of 85 Mph.Svc Water Pump B out-of-svc Resulting in Emergency Diesel Generator B Being out-of-svc. Rupture in Low Pressure Fire Main Also Reported
ML20206U1861986-09-18018 September 1986
Notice of Violation from Insp on 860616-27
IR 05000397/19860311986-09-17017 September 1986
Enforcement Conference Rept 50-397/86-31.Topics Discussed: Violations Identified in Insp Rept 50-397/86-12 Re Equipment Qualification Program,Violations in Insp Rept 50-397/86-11 & Repeat Violations in Control of Combustible Matls
ML20206U7381986-09-17017 September 1986
Exam Rept 50-397/OL-86-02 on 860811-14.Exam Results:One Senior Reactor Operator Candidate Failed Simulator Portion & One Senior Reactor Operator Candidate Failed Oral & Simulator Portions of Exam.Eight Candidates Passed
PNO-V-86-060, on 860903,reactor Feedwater Pump B Tripped Due to Failure of Overspeed Controls.Caused by Partial Control Valve Closure Re Tripping of Hydraulic Power Units. Investigation Underway1986-09-0404 September 1986
PNO-V-86-060:on 860903,reactor Feedwater Pump B Tripped Due to Failure of Overspeed Controls.Caused by Partial Control Valve Closure Re Tripping of Hydraulic Power Units. Investigation Underway
IR 05000397/19860111986-07-25025 July 1986
Insp Rept 50-397/86-11 on 860616-27.Violations Noted.Major Areas Inspected:Mgt Controls & Licensee Activities,Including Operator Recovery Actions,Qa Program,Measuring & Test Equipment & Tech Spec Surveillances & Tests
PNO-V-86-034, on 860620,licensee Measured 1.3 Gpm Leakage Into RHR Sys B.Caused by Leak Through LPCI Injection Valve 53B.Util Repairing Valve.Startup Will Be Delayed Until 860629 Due to BPA Load Requirements1986-06-23023 June 1986
PNO-V-86-034:on 860620,licensee Measured 1.3 Gpm Leakage Into RHR Sys B.Caused by Leak Through LPCI Injection Valve 53B.Util Repairing Valve.Startup Will Be Delayed Until 860629 Due to BPA Load Requirements
1999-03-19
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REVISED NOTICE OF VIOLATION Washington Public Power Supply System Docket No. 50-397 Washington Nuclear Project 2 License No. NPF-21 EA 97-138 During an NRC inspection completed November 18,1997, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
10 CFR 50.59 states, in part, that a licensee may make changes in procedures as :
described in the safety analysis report without prior Commission approval, unless the proposed change involves a change in the technical specifications.
WNP-2 Technical Specifications 1.36,1.19, and 1.12, (WNP-2 License Amendment No.' i 137, 98, and 94, respectively) define REACTOR PROTECTION SYSTEM RESPONSE TIME, ISOLATION SYSTEM RESPONSE TIME, and EMERGENCY CORE COOLING !
SYSTEM (ECCS) RESPONSE TIME to be the time interval from when the monitored !
parameter exceeds its actuation setpoint at the channel sensor until appropriate equipment actuations are completed (e.g., deenergization of scram pilot valve solenoids, isolation valve travel to required positions, or required ECCS equipment response such as pump discharge pressures reaching required values).
WNP-2 Technical Specification 4.3.1.3 (WNP-2 License Amendment No.139) requires that the REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shall be demonstrated to be within its limit at least once per 18 months.
WNP 2 Technical Specification 4.3.2.3, (WNP 2 License Amendment No.139) requires that the ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shall be demonstrated to be within its limit at least once per 18 months.
WNP-2 Technical Specification 4.3.3.3, (WNP-2 License Amendment No.139) requires that the ECCS RESPONSE TIME of each ECCS trip function shall be demonstrated to be within its limit at least once per 18 months.
Contrary to the above, in April 1996, the licensee made changes to procedures as described in the safety analysis report without seeking prior Commission approval, and the changes had the effect of changing technical specification requirements.
Specifically, the licensee changed surveillance procedures which implemented the provisions of WNP-2 Technical Specifications 4.3.1.3,4.3.2.3, and 4.3.3.3, and performed response time measurements in 1996 which were not in accordance with the above technical specification requirements. The testing did not include the time interval for sensor response in the RESPONSE TIME measurement for certain instruments in the Reactor Protection System, Isolation Actuation System and the Emergency Core Cooling System. (01014)
This is a Severity Level IV Violation (Supplement 1).
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9810140308 981013 PDR ADOCK 05000397 G PDR
a 2
The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violations and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in the Supply System's letters dated January 20, and March 19,1998, and NRC Inspection Report No. 50-397/96-22. If you choose to respond, clearly mark your response as a " Reply to a Notice of Violation," and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV , and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
If you choose to respond, your response will be placed in the NRC Public document Room (PDR). Therefore, to the extent possible, the response should not include any personal privacy, ;
proprietary, or safeguards information so that it can be placed in the PDR without redaction.
Dated at Rockville, Maryland this13th day of October 1998 I
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Enclosure:
PDR IE 14 LPDR NUDOCS SECY EC's: RI, Ril, Rlli CA PA (0-2G4)
EDO (0-17G21) OlG (T-5D28)
DEDO (0-17G21) LIEBERMAN, OE (0-7H5)
OE:EAFile (0-7H5) O! (0-3E4) l CHANDLER, OGC (0-15B18) GOLDBERG, OGC (0-15B18) l COLLINS, NRR (0-12G18) BOGER, NRR/ADP (0-12G18)
! POLUSNY,NRR OC/DAF (T-9E10)
OC/LFDCB (T-9E10) AEOD (T-4D18)
RA Reading File GSanborn-EAFile
- WISE RIV Files MIS Coordinator PAO l RSLO WILLIAMSON, Ol MBridger (EDO 980559 E-MAIL DISTRIBUTION:
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DOCUMENT NAME: G:\\97138re3.tr To receive copy of document, indic4l In box: "C" = CopyWthod enclosures "E"M enclosures "N" = No copy OE A OE;Dl' RIV M N%PW/l EDOn TR M M JLkebprman EffeMchoff WllMWan LJQ k _
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