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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20196C9461999-06-15015 June 1999 Notice of Violation from Insp Completed on 990422.Violation Noted:Licensee Failed to Consider Info Contained During Background Investigation Before Granting Temporary Unescorted Access to Contractor Employee ML20207F1581999-03-0303 March 1999 Notice of Violation from Insp on 990125-29 & 0208-12. Violation Noted:Inspector Determined That Waterford Audits SA-98-025.1 & SA-98-036.1,dtd 980916,were Conducted by Individuals Not Independent of Program Mgt Being Audited ML20155D0411998-10-29029 October 1998 Notice of Violation from Insp on 981005-08.Violation Noted: Inspectors Identified That Radiation Surveys to Evaluate Extent of Radiation Levels Had Not Been Performed Prior to Operations Personnel Entering Area ML20155D5021998-10-27027 October 1998 Notice of Violation from Insp on 980914-18.Violation Noted: Performance Tests of Protected Area Detection Sys Identified That Two Detection Zones Did Not Meet Design Criteria to Detect Test Individuals ML20154L0831998-10-0909 October 1998 Notice of Violation from Insp on 980726-0905.Violation Noted:On 980721,NRC Inspectors Found Door 206,vital Area Portal,Unlocked & Not in Alarm at Central Alarm Station ML20236P2431998-07-10010 July 1998 Notice of Violation from Insp on 980503-0613.Violation Noted:On 980521,AP UNT-005-013 Was Not Implemented in That Impairment to Fire Door D150 Was Not Controlled ML20249A9611998-06-16016 June 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Licensee Identified That Calculated Peak Fuel Cladding Temp Would Have Exceeded 2200 F Using Licensing Basis Analysis & HPSI Flow ML20248F6801998-05-29029 May 1998 Notice of Violation from Insp on 980322-0502.Violation Noted:Licensee Failed to Establish Adequate Procedures for Operation of EDG When in No or Low Electrical Loading Condition in That No Specific Guidance Provided ML20217B6731998-04-21021 April 1998 Notice of Violation from Insp on 980201-0321.Violation Noted:On Past Occasions,Engineer Operated Governor Valve on Emergency Feedwater Turbine W/O Direction or Concurrence of Shift Superintendent or Control Room Supervisor ML20216E1311998-03-12012 March 1998 Notice of Violation from Insp on 980302-06.Violation Noted: Licensee Did Not Make Surveys Reasonable Under Circumstances to Ensure Compliance w/10CFR20.1501(a) ML20216E5841998-03-12012 March 1998 Notice of Violation from Insp on 980202-12.Violation Noted: on 980211,inspector Identified That Derailer Was Not Locked in Derail Configuration,Per Plant Security Procedure PS-012-101,rev 9 IR 07100029/20120011998-03-12012 March 1998 Notice of Violation from Insp on 971201-980205.Violation Noted:From 971029-1201,licensee Failed to Initiate Condition Rept When Adverse Condition Was Identified ML20203L2081998-03-0303 March 1998 Notice of Violation from Insp on 980202-06.Violation Noted: on 971226,two Individuals Did Not Make Surveys That Were Reasonable Under Circumstances to Ensure Compliance w/10CFR20.1201(a)(2)(ii) ML20199L2851998-02-0505 February 1998 Notice of Violation from Insp on 971215.Violation Noted:On 971110,two Independent Trains of Auxiliary Component Cooling Water Were Not Maintained Operable in Mode 1 ML20198M2751998-01-12012 January 1998 Notice of Violation from Insp on 971102-1213.Violation Noted:Licensee Failed to Require Adequate Postmaintenance Testing to Insure That Equipment or Sys Capable of Performing Intended Safety Function ML20198C4431998-01-0202 January 1998 Notice of Violation from Insp on 971117-1205.Violation Noted:On 970224,individual,who Identified Adverse Condition Affecting safety-related Sys,Failed to Promptly Identify Nonconformance That Called Into Question Operability of Sys ML20202E2831997-12-0202 December 1997 Notice of Violation from Insp on 970922-26 & 1006-10. Violation Noted:On 960704,desired Changes Identified for Entries in Table 3.8-1 of Technical Requirements Manual & as of 971010,had Not Been Evaluated Under 10CFR50.59 Process ML20199F7291997-11-19019 November 1997 Notice of Violation from Insp on 970921-0001.Violation Noted:Administrative Procedure UNT-007-006 Not Implemented ML20217K8831997-10-23023 October 1997 Notice of Violation from Insp on 970929-1003.Violation Noted:Procedures Not Maintained for EOP in That Licensee Failed to Revise EOP OP 902-008 to Provide Operators W/Instructions for Closing Containment Spray Valves ML20211Q3641997-10-17017 October 1997 Notice of Violation from Insp on 970810-0920.Violation Noted:As of 970731,Condition Rept 97-0989 Identified 3 Addl Valves That Had Non Qualified Thermal Overload Relays Installed in TS Required Equipment ML20211Q5131997-10-0909 October 1997 Notice of Violation from Insp on 970922-26.Violation Noted: on 970110,0507 & 24,0611 & 12,radiation Workers Entered Radiological Controlled Area W/O Required Electronic Dosimeter or Thermoluminescent Dosimeter or Both ML20210R3661997-08-28028 August 1997 Notice of Violation from Insp on 970629-0809.Violation Noted:As of Jan 1997,for Emergency Ls,Licensee Failed to Establish Goals Commensurate W/Safety as Described in 10CFR50.65(a)(1) ML20210R5231997-08-27027 August 1997 Notice of Violation from Insp on 970707-25.Violation Noted: Final Safety Analysis Rept Updated File in May of 1996 Did Not Include Latest Matl Developed 6 Months Prior to Date of Filing ML20149J9081997-07-22022 July 1997 Notice of Violation from Insp on 970518-0628.Violation Noted:On 970520,procedure UNT-005-003 Was Not Implemented Properly & W/O Independent Review by Licensed Operator ML20141B5901997-06-19019 June 1997 Notice of Violation from Insp on 970406-0517.Violation Noted:As of 970404,design Basis Not Correctly Translated Into Procedures in That Procedural/Instructional Requirements to Limit Emergency DG Loading Not Implemented ML20140J3041997-06-16016 June 1997 Notice of Violation from Insp on 970428-0502.Violation Noted:Licensee Failed to Translate Design Requirements for Cold Weather Operation of Wet Cooling Tower Into Sys Operating Procedure OP-002-001, Accws, Rev 10 ML20148E2621997-05-29029 May 1997 Notice of Violation from Insp on 970421-25.Violation Noted: Licensee Determined That Waterford 3 Security Superintendent Had Not Been Notified Prior to or Concurrently W/Depature from Plant Site of Approx 10 Contract Employees ML20141K0331997-05-23023 May 1997 Notice of Violation from Insp on 970421-25 w/in-ofc Insp & follow-up Continuing Through 970501.Violations Noted: Measures Did Not Assure That Welding Was Controlled IAW Requirements in Listed Examples ML20148C3201997-05-0909 May 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:From 951031 to 960823, Licensee Operated Facility W/O Assuring That Two Independent Groups of Containment Cooling Fans Were Operable ML20138K2241997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violations Noted:Licensee Failed to Implement Requirements of TS 6.2.2.e & Procedure UNT-005-005 Between 970201 & 0301 ML20137E8511997-03-24024 March 1997 Notice of Violation from Insp on 970112-0222.Violation Noted:As of 970218,licensee Did Not Perform Surveys Required by 10CFR20.1501 That Resulted in Failure to Post Caution, Radioactive Matl Sign ML20134K1831997-02-0707 February 1997 Notice of Violation from Insp on 961201-970111.Violation Noted:Security Patrol Officer Observed Protective Lighting Sys Deficiency When Lighting Was Needed & Did Not Immediately Notify Central or Secondary Alarm Station ML20133A0511996-12-26026 December 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Actual Design Configuration of Containment Vrs Different from That Described in Amend 28 to Plant FSAR from 1985 - Jul 1996 ML20132G0551996-12-19019 December 1996 Notice of Violation from Insp on 961013-1130.Violation Noted:On 961001,licensee Failed to Secure Airborne Radioactivity Removal Sys After Stopping Containment Purge ML20132E1441996-12-13013 December 1996 Notice of Violation from Insp on 960123-0628.Noncompliance Noted:On 960111,RM Gracin,Employee of Entergy Operations, Inc,Deliberately Provided Info to NRC Inspector & Licensee Representatives That Was Inaccurate Re Unescorted Access ML20134K7781996-11-13013 November 1996 Notice of Violation from Insp on 961021-25.Violations Noted:Licensee Failed to Verify Operational Readiness of Valves Whose Function Required for Safety IAW Section 11 of ASME Boiler & Pressure Vessel Code ML20129K2341996-11-0404 November 1996 Notice of Violation from Insp on 960901-1012.Violation Noted:Licensee Used a Pressure Instrument w/full-scale Range That Exceeded Three Times Ref Value or Less ML20129D7531996-09-20020 September 1996 Notice of Violation from Insp on 960721-0831.Violation Noted:Work Authorization 01149346 Not Appropriate to Circumstances by Not Requiring Return of Manual/Automatic Setpoint to Original State Prior to Returning Sys to Svc ML20149F3031994-08-0505 August 1994 Notice of Violation from Insp on 940529-0709.Violation Noted:In Violation of TS 6.8.1a,CVC Sys Flow Diagram Failed to Show All Letdown Radiation Monitor Purge Connections & Component CWS Flow Diagram Failed to Show All Valves in Sys ML20059H0181994-01-20020 January 1994 Notice of Violation from Insp on 931031-1211.Violation Noted:Maint Technician Made Entries Into Overhead on +46 Foot Level of Radiation Controlled Area W/O Contacting Health Physics Personnel Prior to Making Entries ML20058H4871993-12-0707 December 1993 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Noncompliance Noted:On 930201-0930,one of Two Independent Spray Sys Inoperable & Required Actions Not Taken ML20058E6251993-11-29029 November 1993 Notice of Violation from Insp on 930919-1030.Violation Noted:On 930817,Valve CMU-1131 Was Opened & Left in Open Position Until 931019 ML20059J8821993-11-0505 November 1993 Notice of Violation from Insp on 930913-14 & 1019-22. Violations noted:hand-carried Item Entered Protected Area W/O Being Searched by X-ray Exam Device or Being Physically Searched by Security Officer ML20059E1561993-10-28028 October 1993 Notice of Violation from Insp on Stated Date.Violation Noted:Nrc Identified That Site Directive W4.1.1 Inadequate for Initiating Evaluation to Determine Reportability of Event or Condition ML20057G2011993-10-15015 October 1993 Notice of Violation from Insp on 930913-17.Violation Noted: No Nasal Wipes Were Obtained from Individuals Who Were Identified as Having Facial Contamination on 920925 & 930729 ML20057D4461993-09-28028 September 1993 Notice of Violation from Insp on 930726-30 & 0826.Violation Noted:Licensee Failed to Identify & Initiate Nonconformance Condition Identifications for ASME Section III Pressurizer Safety Valves Exceeding + or - 1% Tolerence Specified in TS ML20128D1181993-02-0101 February 1993 Notice of Violation from Insp on 921129-930109.Violation Noted:Corrective Actions Taken in Response to Violations 50-382/8941-02 & 50-382/9201-01 Inadequate,As Evidenced by Listed Examples ML20126A4201992-12-16016 December 1992 Notice of Violation from Insp on 921018-1128.Violation Noted:Failure to Properly Implement Consumable Control Program ML20217B3821991-03-0404 March 1991 Notice of Violation from Insp on 910109-0219.Violation Noted:New Type Digital Voltmeter Not Reviewed by PORC or Approved by General Manager ML20058K0641990-11-30030 November 1990 Notice of Violation from Insp on 901002-1113.Violation Noted:Technician Commenced Timing of Thermal Element Delay Few Seconds After Adjusting Current Through Phase C Thermal Element 1999-06-15
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000382/19990201999-10-21021 October 1999 Insp Rept 50-382/99-20 on 990815-0925.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support Activities IR 05000382/19990141999-10-19019 October 1999 Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Major Areas Inspected:Operator Requalification Training Program PNO-IV-99-038A, on 990929,restart of Waterford 3 Occurred. Cause Identified as Failed Seal Water Heat Exchanger Baffle. New Battle & Seal Assembled Were Installed & Reactor Coolant Pump 2B Was Returned to Svc Satisfactorily1999-10-0101 October 1999 PNO-IV-99-038A:on 990929,restart of Waterford 3 Occurred. Cause Identified as Failed Seal Water Heat Exchanger Baffle. New Battle & Seal Assembled Were Installed & Reactor Coolant Pump 2B Was Returned to Svc Satisfactorily IR 05000382/19990181999-09-29029 September 1999 Insp Rept 50-382/99-18 on 990830-0902.Violations Noted.Major Areas Inspected:Implementation of NRC-approved Fire Protection Program IR 05000382/19990191999-09-27027 September 1999 Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted. Major Areas Inspected:Plant Support PNO-IV-99-038, on 990910,operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.New Baffle & Seal Assembly Were Installed & Plant Was Returned to Power Operations on 9908101999-09-15015 September 1999 PNO-IV-99-038:on 990910,operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.New Baffle & Seal Assembly Were Installed & Plant Was Returned to Power Operations on 990810 IR 05000382/19990151999-09-14014 September 1999 Insp Rept 50-382/99-15 on 990719-23 with in Ofc Insp Until 0819.No Violations Noted.Major Areas Inspected:Assessment of 10CFR50.59 Safety Evaluation Program & Review of Previous Insp Findings Involving Tornado Missile Protection IR 05000382/19990071999-09-0808 September 1999 Insp Rept 50-382/99-07 on 990601-11.Noncited Violations Identified.Major Areas Inspected:Operations IR 05000382/19990161999-09-0101 September 1999 Insp Rept 50-382/99-16 on 990704-0814.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support PNO-IV-99-032A, on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plant Sd.New Baffle & Seal Assembly Was Installed1999-08-12012 August 1999 PNO-IV-99-032A:on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plant Sd.New Baffle & Seal Assembly Was Installed IR 05000382/19990101999-08-11011 August 1999 Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Major Areas Inspected:Solid Radioactive Waste Mgt & Radioactive Matl Transportation Programs PNO-IV-99-032, on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plan Shutdown.Resident Inspectors Will Monitor1999-08-0303 August 1999 PNO-IV-99-032:on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plan Shutdown.Resident Inspectors Will Monitor IR 05000382/19990131999-07-15015 July 1999 Insp Rept 50-382/99-13 on 990523-0703.Noncited Violations Noted.Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19990121999-06-21021 June 1999 Insp Rept 50-382/99-12 on 990524-27.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000382/19990111999-06-18018 June 1999 Insp Rept 50-382/99-11 on 990524-28.No Violations Noted. Major Areas Inspected:Implementation of Liquid & Gaseous Radwaste Effluent Mgt Program,Status of Effluent Radiation Monitors & Counting Room Instruments ML20196C9461999-06-15015 June 1999 Notice of Violation from Insp Completed on 990422.Violation Noted:Licensee Failed to Consider Info Contained During Background Investigation Before Granting Temporary Unescorted Access to Contractor Employee IR 05000382/19990091999-06-0303 June 1999 Insp Rept 50-382/99-09 on 990411-0522.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20209B8581999-05-25025 May 1999 EN-98-046A:on 990524,staff Withdrew Proposed Civil Penalty in Amount of $110,000 Issued to Licensee.Action Based on Severity Level III Problems Associated with ECCS & Afws IR 05000382/19990061999-05-18018 May 1999 Insp Rept 50-382/99-06 on 990405-09.Non-cited Violations Identified.Major Areas Inspected:Issue Previously Identified During Architect Engineering Insp Which Documented NRC Insp Rept 50-382/98-201 IR 05000382/19990051999-05-10010 May 1999 Insp Rept 50-382/99-05 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support ML20206F4801999-05-0303 May 1999 Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Noted & Being Considered for Escalated Eas.Major Areas Inspected:Plant Support Including Licensee Access Authorization Program IR 05000382/19990041999-04-0909 April 1999 Insp Rept 50-382/99-04 on 990301-19.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Review of Licensee Implementation of Facility ISI Program & Followup Review of Reactor Trip Breaker Performance IR 05000382/19990021999-04-0505 April 1999 Insp Rept 50-382/99-02 on 990117-0227.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support Activities IR 05000382/19990031999-03-26026 March 1999 Insp Rept 50-382/99-03 on 990308-12.Violations Noted.Major Areas Inspected:Radiation Protection Program Focusing on RF09 Refueling Outage Activities IR 05000382/19990011999-03-0303 March 1999 Partially Deleted Insp Rept 50-382/99-01 on 990125-29 & 0208-12 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Plant Support ML20207F1581999-03-0303 March 1999 Notice of Violation from Insp on 990125-29 & 0208-12. Violation Noted:Inspector Determined That Waterford Audits SA-98-025.1 & SA-98-036.1,dtd 980916,were Conducted by Individuals Not Independent of Program Mgt Being Audited IR 05000382/19980181998-12-21021 December 1998 Insp Rept 50-382/98-18 on 981018-1128.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980151998-11-24024 November 1998 Insp Rept 50-382/98-15 on 980906-1017.No Violations Noted. Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities PNO-IV-98-054, on 981117,plant Shutdown Greater than 72 H Due to Unidentified Leak.Investigations by Licensee Verified That Leakage Occurred from RCP 2b Seal Area1998-11-19019 November 1998 PNO-IV-98-054:on 981117,plant Shutdown Greater than 72 H Due to Unidentified Leak.Investigations by Licensee Verified That Leakage Occurred from RCP 2b Seal Area IR 05000382/19980131998-11-17017 November 1998 Insp Rept 50-382/98-13 on 980831-0901 & 981005-08.No Violations Noted.Major Areas Inspected:Maint Using Guidance of Temp Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers ML20155D0561998-10-29029 October 1998 Insp Rept 50-382/98-17 on 981005-08.Violations Noted. Major Areas Inspected:Routine Review of Radiation Protection Program Activities ML20155D0411998-10-29029 October 1998 Notice of Violation from Insp on 981005-08.Violation Noted: Inspectors Identified That Radiation Surveys to Evaluate Extent of Radiation Levels Had Not Been Performed Prior to Operations Personnel Entering Area ML20155D5111998-10-27027 October 1998 Partially Withheld Insp Rept 50-382/98-16 on 980914-18. Violations Noted.Major Areas Inspected:Licensee Physical Security Program.Portions Withheld (Ref 10CFR2.790) ML20155D5021998-10-27027 October 1998 Notice of Violation from Insp on 980914-18.Violation Noted: Performance Tests of Protected Area Detection Sys Identified That Two Detection Zones Did Not Meet Design Criteria to Detect Test Individuals ML20154L0831998-10-0909 October 1998 Notice of Violation from Insp on 980726-0905.Violation Noted:On 980721,NRC Inspectors Found Door 206,vital Area Portal,Unlocked & Not in Alarm at Central Alarm Station ML20154L1281998-10-0909 October 1998 Insp Rept 50-382/98-14 on 980726-0905.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-IV-98-045, on 980926,Unit 3 Declared Unusual Event of Hurricane Warning in St Charles Parish.River Bend Station Continued to Operate at Full Power Since Hurricane Force Winds Were Not Predicted in Vicinity of Site1998-09-28028 September 1998 PNO-IV-98-045:on 980926,Unit 3 Declared Unusual Event of Hurricane Warning in St Charles Parish.River Bend Station Continued to Operate at Full Power Since Hurricane Force Winds Were Not Predicted in Vicinity of Site PNO-IV-98-040, on 980917,licensee Commenced Shutdown of Reactor in Order to Replace Pressurizer Code Safety Valve That Had Been Experiencing Increased Leakage.Licensee Plans to Restart Facility on 9809231998-09-18018 September 1998 PNO-IV-98-040:on 980917,licensee Commenced Shutdown of Reactor in Order to Replace Pressurizer Code Safety Valve That Had Been Experiencing Increased Leakage.Licensee Plans to Restart Facility on 980923 IR 05000382/19980121998-08-21021 August 1998 Insp Rept 50-382/98-12 on 980614-0725.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19992011998-07-27027 July 1998 Insp Rept 50-382/99-201 on 990511-0619.No Violations Noted Major Areas Inspected:Engineering IR 05000382/19980101998-07-20020 July 1998 Insp Rept 50-382/98-10 on 980622-26.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program Including Access Authorization,Alarm Stations,Protected Area Access Control of Personnel & Packages & Vehicles ML20236P2431998-07-10010 July 1998 Notice of Violation from Insp on 980503-0613.Violation Noted:On 980521,AP UNT-005-013 Was Not Implemented in That Impairment to Fire Door D150 Was Not Controlled IR 05000382/19980091998-07-10010 July 1998 Insp Rept 50-382/98-09 on 980503-0613.Violations Noted.Major Areas Inspected:Aspects of Operations,Maint,Engineering & Plant Support Activities.Fire Door in Reactor Auxiliary Bldg Was Observed to Be Open W/No Controls in Place ML20249A9611998-06-16016 June 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Licensee Identified That Calculated Peak Fuel Cladding Temp Would Have Exceeded 2200 F Using Licensing Basis Analysis & HPSI Flow ML20151R9131998-06-0909 June 1998 EN-98-046:on 980616,notice of Proposed Imposition of Civil Penalty in Amount of $110,000 Issued to Licensee.Action Based on Level III Problem Involving HPSI Flow Issues at Waterford-3 Facility IR 05000382/19980081998-05-29029 May 1998 Insp Rept 50-382/98-08 on 980322-0502.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20248F6801998-05-29029 May 1998 Notice of Violation from Insp on 980322-0502.Violation Noted:Licensee Failed to Establish Adequate Procedures for Operation of EDG When in No or Low Electrical Loading Condition in That No Specific Guidance Provided IR 05000382/19980991998-04-24024 April 1998 SALP Rept 50-382/98-99 for 961201-980321 ML20217B6731998-04-21021 April 1998 Notice of Violation from Insp on 980201-0321.Violation Noted:On Past Occasions,Engineer Operated Governor Valve on Emergency Feedwater Turbine W/O Direction or Concurrence of Shift Superintendent or Control Room Supervisor ML20217B6981998-04-21021 April 1998 Insp Rept 50-382/98-06 on 980201-0321.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering 1999-09-08
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ENCLOSURE 1 NOTICE OF VIOLATION Entergy Operations, Inc. Docket No.: 50-382 Waterford Steam Electric Station; Unit 3 License No.: NPF-38 During an NRC inspection conducted on April 28 through May 2,1997, four violations of NRC requirements were identified. In accordance with the " General Statement of Policy l and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
1 A. 10 CFR Part 50, Appendix B, Criterion lit, " Design Control," states, measures shall l be established to assure that applicable regulatory requirements and the design l basis are correctly translated into specifications, drawings, procedures, and I instructions. In addition, measures are required to be established for the l identification and control of design interfaces and for coordination among I participating design organizations.
10 CFR Part 50, Appendix A .erion 34, " Residual Heat Removal," requires that suitable redundancy in comt - ents and features shall be provided to assure that for l onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished assuming a single failure.
Contrary to the above, on May 2,1997, the NRC determined that:
- 1. The licensee had failed to translate the design requirements for cold weather operation of the wet cooling tower into System Operating Procedure OP-002- j 001, " Auxiliary Component Cooling Water," Revision 10. ;
- 2. The licensee had failed to translate the design requirements for seismic j qualification into Maintenance Procedure MM-008-01, "(Inside) Maintenance Access Hatch and (Outside) Maintenance Access Hatch Shield Door Opening, inspection and Closing," Revision 5, the installation instruction for the reactor shield building door. l 1
- 3. The licensee had failed to establish adequate measures for the identification and control of design interf aces and for coordination among participating I
design organizations. Specifically, the licensee had failed to provide l
adequate coordination between the mechanical and the electrical design l organizations on three occasions:
- a. The emergency diesel generator load calculation and the associated Final Safety Analysis Report Table were not updated when Licensing Document Change Request 96-0161 added the manual start of a fuel pool cooling pump 12 heurs after a loss-of-offsite power with a safety injection actuation signal.
9706190360 970616 PDR ADOCK 05000382 G PDR
3-iI i
l C. Technical Specification 4.8.1.1.2.e, " Electrical Power Systems Surveillance Requirements," requires that each diesel generator shall be demonstrated OPERABLE at least once per 18 months during shutdown by.
"3. Simulating a loss-of-offsite power by itself, and:
1 "a) Verifying deenergization of the emergency busses and load shedding from the ,
emergency busses. !
l "b) Verifying the diesel energizes the auto-connected shutdown loads through the load sequencer . . . ,
l "b. Simulating a loss-of-offsite power in conjunction with an $1AS actuation test signal, and:
"a) Verifying deenergization of the emergency busses and load shedding from the emergency busses.
"b) Verifying the diesel energizes the auto-connected shutdown loads through the load sequencer."
Contrary to the above, on May 2,1997, the NRC inspector identified that, within the last 18 months, the licensee had not adequately implemented these surveillance requirements. Specifically,
- 1. The licensee did not verify that the pressurizer heater group circuit l
l breakers opened as required and load shed during the simulated loss-
! of-offsite power test or the loss-of-offsite power in conjunction with the safety injection actuation signal test.
l l 2. The licensee did not verify the following loads correctly shed and started on their corresponding load sequencer block: Shutdown Heat Exchanger A and B room coolers, the Component Cooling Water Heat Exchanger A and B room coolers, and Control Room Heater EHC-34 and Switchgear Room Heater EHC-36.
This is a Severity Level IV violation (Supplement I) i50-382/9710-04).
. i Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at . Arlington, Texas this 16th day of June 1997 l
l l
, T Entergy Operations, Inc. E-Mail report to T. Boyce (THB)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
- bec to DCD (IE01) bec distrib. by RIV:
Regional Administrator Resident inspector DRP Director DRS-PSB Branch Chief (DRP/D) MIS System Project Engineer (DRP/D) RIV File Branch Chief (DRP/TSS) l i(
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190013 DOCUMENT NAME: R:\_WAT\WT9710RP.LJS
, To receive copy of document, indicate in box: "C" = Copy without enclosuy "E" = Copy with enclosures "N" = No copy RIV:RI:EB C:EB D:DRf ), ,JJ/ D:DRSA)U LJSmith/Imb PM _ . CAVanDenbyr, qty TPGdy)( @ 7, / _ ATHoWgL W 06 8/97 V fD 06/(/97 NW 06/G4f94 fd #
06fb/9T OFFICIAL RECORD COPY
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l Entergy Operations, Inc. .
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Should you have any questions concerning this inspection, we will be pleased to discuss l them with you. !
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Sincerely, ;
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h Arthur T. Howell 111, Director Division of Reactor Safety ;
Docket No.: 50-382 ,
License No.: NPF-38 ;
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Enclosures:
1.: Notice of Violation .
- 2. NRC Inspection Report 50-382/97 10 cc w/ enclosures: !
Executive Vice President and Chief Operating Officer Entergy Operations, Inc. .
P.O. Box 31995 Jackson, Mississippi 39286-1995 Vice President, Operations Support Entergy Operotions, Inc.
P.O. Box 31995 Jackson, Mississippi 39286-1995 Wise, Carter, Child & Caraway P.O. Box 651 1 Jackson, Mississippi 39205 General Manager, Plant Operations Waterford 3 SES Entergy Operations, Inc.
P.O. Box B Killona, Louisiana 70066 9
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4 Entergy Operations, Inc. Manager - Licensing Manager
- Waterford 3 SES Entergy Operations, Inc.
P.O. Box B Killona, Louisiana 70066 Chairman Louisiana Public Service Commission One American Place, Suite 1630 Baton Rouge. Louisiana 70825 1697 Director, Nuclear Safety &
Regulatory Affairs Waterford 3 SES Entergy Operations, Inc.
P.O. Box B Killona, Louisiana 70066 William H. Spell, Administrator Louisiana Radiation Protection Division P.O. Box 82135 Baton Rouge, Louisiana 70884-2135 Parish President St. Charles Parish -
P.O. Box 302 f Hahnville, Louisiana 70057 )
Mr. William A. Cross Bethesda Licensing Office 3 Metro Center Suite 610 Bethesda, Maryland 20814 Winston & Strawn 1400 L Street, N.W.
Washington, D.C. 20005-3502 l
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i ENCLOSURE 1 1 NOTICE OF VIOLATION Entergy Operations, Inc. Docket No.: 50-382 Waterford Steam Electric Station, Unit 3 License No.: NPF-38 During an NRC inspection conducted on April 28 through May 2,1997, four violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A. 10 CFR Part 50, Appendix B, Criterion Ill, " Design Control," states, measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and ;
instructions. In addition, measures are required to be established for the '
identification and control of design interfaces and for coordination among i participating design organizations. )
10 CFR Part 50, Appendix A, Criterion 34, " Residual Heat Removal," requires that suitable redundancy in components and features shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished assuming a single failure.
Contrary to the above, on May 2,1997, the NRC determined that:
- 1. The licensee had failed to translate the design requirements for cold weather operation of the wet cooling tower into System Operating Procedure OP-002-001, " Auxiliary Component Cooling Water," Revision 10.
- 2. The licensee had failed to translate the design requirements for seismic l qualification into Maintenance Procedure MM-008-01, "(Inside) Maintenance Access Hatch and (Outside) Maintenance Access Hatch Shield Door l Opening, inspection and Closing," Revision 5, the installation instruction for the reactor shield building door.
- 3. The licensee had failed to establish adequate measures for the identification l
and control of design interfaces and for coordination among participating design organizations. Specifically, the licensee had f ailed to provide adequate coordination between the mechanical and the electrical design organizations on three occasions:
- a. The emergency diesel generator load calculation and the associated Final Safety Analysis Report Table were not updated when Licensing Document Change Request 96-0161 added the manual start of a fuel pool cooling pump 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after a loss-of-offsite power with a safety injection actuation signal.
9706190360 970616 PDR ADOCK 05000382 G PDR
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- b. The emergency diesel generator load calcelation and the associated Final Safety Analysis Report Table were not updated when Mechanical Calculation MN(Q)-9-9, " Wet Cooling Tower During a LOCA," Revision 3, Change 1, paragraph 5.2, changed the operating time of the wet cooling tower fans,
- c. The emergency diesel generator load calculation and the associated Final Safety Analysis Report Table were not updated when Licensing Document Change Request 96-0161 changed the length of time that the auxiliary component cooling water system was required to be in service following a large break loss-of-coolant accident.
- 4. The licensee had not assured that the requirements of General Design Criterion 34 were correctly translated into specifications for the emergency feedwater system, which is credited as a residual heat removal system.
Specifically, Calculation EC-M96-004, " Design Basis Reconstitution for EFW Flow Rate," Revision A, had not been analyzed for offsite electric power system operation (assuming onsite power is not available).
This is a Severity Level IV violation (Supplement 1)(50-382/9710-01).
B. 10 CFR 50.59(a)(2) states, that a proposed change shall be deemed to involve an unreviewed safety question if the probability of malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased.
10 CFR 50.59(b)(1) requires that the licensee maintain records of changes in the f acility and of changes in procedures made pursuant to this section, to the extent that these changes constitute changes in the facility as described in the safety analysis report or to the extent that they constitute changes in the procedures as described in the safety analysis report. Further, these records must includo a written safety cvaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
Contrary to the above, -on May 2,1997, the NRC determined that the licensee had not provided an adequate bases in their written safety evaluation that a change in diesel generator fuel oil margin did not involve an unreviewed safety questior.
Specifically, the safety evaluation for Licensing Document Change Request 93-0091 did not address the reduction in required fuel oil storage margin and the associated increase in probability that the emergency diesel generator would run out of iuel before 7 days because of uncertainties associated with the time-dependent load method for determining fuel oil storage requirements.
This is a Severity Level IV violation (Supplement l} (50-382/9710-02).
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C. Technical Specification 4.8.1.1.2.e, " Electrical Power Systems Surveillance Requirements," requires that each diesel generator shall be demonstrated :
OPERABLE at hast once per 18 months during shutdown by-
"3. Simulating a loss-of-offsite power by itself, and:
"a) Verifying deenergization of the emergency !
busses and load shedding from the emergency busses.
"b) Verifying the diesel energizes the auto-connected shutdown loads through the load sequencer . . .
"5. Simulating a loss-of-offsite power in conjunction with an SIAS actuation test signal, and: l "a) Verifying deenergization of the emergency busses and load shedding from the emergency busses.
"b) Verifying the diesel en'ergizes the auto-connected shutdown loads through the load sequencer."
Contrary to the above, on May 2,1997, the NRC inspector identified that, within the last 18 months, the licensee had not adequately implemented these surveillance requirements. Specifically,
- 1. Tne licensee did not verify that the pressurizer heater group circuit I breakers opened as required and load shed during the simulated loss- l of-offsite power test or the loss-of-offsite power in conjunction with the safety injection actuation signal test.
- 2. The licensee did not verify the following loads correctly shed and l started on their corresponding load sequencer block: Shutdown Heat Exchanger A and B room coolers, the Component Cooling Water Heat Exchanger A and B room coolers, and Control Room Heater EHC-34 and Switchgear Roon Heater EHC-36.
This is a Severity Level IV violation (Supplement 1)(50-382/9710-04).
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D. 10 CFR Part 50, Appendix B, Criterion XVI, " Corrective Action," states, measures shall be established to assure that conditions adverse to quality, such as failures, i malfunctions, deficiencies, deviations, defective material, and equipment are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and '
the corrective action taken to preclude repetition. The identification of the significant condition adverse to quality, the cause of the condition, and the corrective actions taken shall be documented and reported to appropriate levels of 1 management.
Contrary to the above, on May 2,1997, the NRC determined that the licensee had failed to identify and correct two significant conditions adverse to quality.
Specifically:
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- 1. The licensee did not correct the deficient design basis for tornado protection )
of the ultimate heat sink and, as a result, they did not identify and correct ,
unprotected e' trical conduit and cables, l l
- 2. The licensee did unt promptly identify and correct nozzle ring setting deficiencies, similar to those described in information Notice 96-24, " Nozzle Ring Settings on Low Pressure Water-Relief Valves."
This is a Severity Level IV violation (Supplement 1)(50-382/9710-06). j J
Pursuant to the provisions of 10 CFR 2.201, Entergy Operations, Inc., is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident inspector at the f acility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the rcquired response, if an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time. !
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l 5-Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards j information so that it can be placed in the PDR without redaction. However, if you find it i necessary to include such information, you should clearly indicate the specific information l l that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public. '
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j Dated at Arlington, Texas !
l this 16th day of June 1997 ;
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