Notice of Violation from Insp on 970302-0412.Violation Noted:On 970324,licensee Failed to Open C-S Sfpcs Pump Discharge Valve When Placing C-S Pump in Service.Sys Operated for About 2.5 Hours with Discharge Valve ClosedML20141C981 |
Person / Time |
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Site: |
Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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Issue date: |
05/12/1997 |
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From: |
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
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To: |
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Shared Package |
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ML20141C976 |
List: |
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References |
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50-327-97-03, 50-327-97-3, 50-328-97-03, 50-328-97-3, EA-97-083, EA-97-233, EA-97-83, NUDOCS 9705190290 |
Download: ML20141C981 (6) |
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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20202J5471999-02-0101 February 1999 Notice of Violation from Insp on 981122-990102.Violation Noted:Following Unit 1 Rt on 981109,procedural Requirements of EOP ES0.1 Were Not Properly Implemented,In That RCS Temperatures Were Not Monitored & Steam Not Dumped ML20196D6081998-11-24024 November 1998 Notice of Violation from Insp on 980914-1016.Violation Noted:As of 980916,requirements of 0-MI-MXX-061-001 Not Implemented ML20195G5521998-11-0909 November 1998 Notice of Violation from Insp on 980830-1010.Violation Noted:Licensee Failed to Assure That All Testing Required to Demonstrate That Safety Related Circuit Breakers Would Perform Satisfactorily in Svc ML20237B1851998-08-0404 August 1998 Notice of Violation from Insp on 980606-0718.Violations Noted:On or Before 971103,conditions Adverse to Qualify Were Not Promptly Identified & Corrected,In That Licensee Failed to Correct &/Or Initiate Problem Evaluation Rept ML20236J6591998-06-26026 June 1998 Notice of Violation from Insp on 980426-0606.Violation Noted:Inservice Testing of Valves Not in Accordance with Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda as Required by 10CFR50.55a ML20247L5781998-05-15015 May 1998 Notice of Violation from Insp on 980315-0425.Violation Noted:Licensee Failed to Perform Surveillance Requirement 4.8.1.1.1.a,within 1 H & at Least Once Per 8 H Thereafter ML20216H7701998-04-10010 April 1998 Notice of Violation from Insp on 980201-0314.Violation Noted:License Failed to Rept an Adverse Condition on Work Request/Work Order &/Or Problem Evaluation Rept ML20217K3751998-03-30030 March 1998 Notice of Violation from Insp on 980126-0213.Violation Noted:On Listed Dates,Licensee Made Changes to Facility as Described in FSAR W/O Adequate Written SE Which Provides Bases for Determination That Changes Did Not Involve USQ ML20203J5411998-02-19019 February 1998 Notice of Violation from Insp on 971231-980131.Violation Noted:On 980126 Individuals Failed to Monitor Themselves in Whole Body Contamination Monitor or W/Hand & Foot Frisk Monitor ML20197F5541997-12-0808 December 1997 Notice of Violation from Insp on 970725-0704 & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Sro Failed to Implement Step 8.4.8 of Soi 0-S0-250-1. Predecisional EC Agenda & Documentation Encl ML20211E2531997-09-22022 September 1997 Notice of Violation from Insp on 970706-0823.Violation Noted:On 970714,containment Isolation Valve 1-FCV-31C-229 Failed to Exhibit Required Change of Obturator Position & Was Not Repaired or Replaced & Data Not Analyzed ML20141H9531997-07-28028 July 1997 Notice of Violation from Insp on 970525-0705.Violation Noted:Licensee Failed to Implement Prompt Corrective Actions to Resolve Condition Adverse to Quality ML20149L5671997-07-24024 July 1997 Notice of Violation from Insp on 970623-27.Violation Noted: on 960627,licensee Had Loss of Security Electronic Equipment & Failed to Post Officers in Position to Provide Surveillance of Entire Protected Area Perimeter ML20149G8681997-07-10010 July 1997 Notice of Violation from Insp on 970324-0522.Violation Noted:Licensee Failed to Esatblish Measures to Assure That Significant Condition Adverse to Quality Was Promptly Identified & Corrected & C/A Taken to Preclude Repetition ML20141G0361997-06-20020 June 1997 Notice of Violation from Insp on 970413-0524.Violation Noted:Each Intermediate & Power Range Channel Was Not Subj to Channel Function Test within 12 H Prior to Initiating Physics Test ML20141C9811997-05-12012 May 1997 Notice of Violation from Insp on 970302-0412.Violation Noted:On 970324,licensee Failed to Open C-S Sfpcs Pump Discharge Valve When Placing C-S Pump in Service.Sys Operated for About 2.5 Hours with Discharge Valve Closed ML20137F6771997-03-18018 March 1997 Notice of Violation from Insp on 970119-0301.Violations Noted:Alarm Response Procedure for 2A-A Emergency Diesel Generator Inadequate in Items Listed ML20137S9921997-03-14014 March 1997 Notice of Violation from Insp on 970124.Violation Noted:Licensee Failed to Maintain Complete & Accurate Info Re Fire Watch Log Not Being Completed for Control Bldg ML20134G8921997-01-13013 January 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Noncompliance Noted:Tva,Through Actions of Former Vice President of Nuclear Operations, Discriminated Against Mgt Employee ML20134G1721997-01-13013 January 1997 Notice of Violation from Insp on 960923-1219.Violation Noted:Plant Mod M11730A,rev 0,was Approved on 951130 for Modifying Unit 1 Rod Control Sys W/O Incorporating Applicable Design Inputs Re New Failure Modes ML20133F6121996-12-24024 December 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.00.Noncompliance Noted:Failure to Implement Adequate Corrective Actions,Failure to Implement MI-10.9.1 Properly & Failure to Notify Sos of Condition ML20134Q3271996-11-19019 November 1996 Notice of Violation from Insp on 960915-1026.Violation Noted:On 960916,section XI IST Procedures for EDG Starting Air Receiver Pressure Relieving Devices Were Inadequate in That Sps Were Set in Range of 340-360 Psig ML20134Q2001996-11-19019 November 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 for Violations Noted During Insp on 960708-0822.Violations Noted:Adverse Conditions Re Fire Protection Program Not Promptly Identified &/Or Resolved ML20129A2101996-10-10010 October 1996 Notice of Violation from Insp on 960728-0914.Violation Noted:Prompt Corrective Action Not Implemented for Condition Adverse to Quality ML20059B4491993-12-23023 December 1993 Notice of Violation from Insp on 931107-1204.Violations Noted:Licensee Failed to Identify Existence of Water Accumulation,Some Containment Liner Degradation & Design Inconsistencies ML20059C0131993-12-17017 December 1993 Notice of Violation from Insp on 931115-19.Violation Noted: Procedures Delineating Process for Administering Comprehensive Requalification Exams Did Not Contain Appropriate Guidance for Conducting Annual Operating Tests ML20058P6571993-12-0303 December 1993 Notice of Violation from Insp on 931011-1106.Violation Noted:Procedures Were Not Implemented in That on 931028, Asos Failed to Complete Time/Date Release Portion of Clearance 2-93-1334 Prior to Sys Being Returned to Svc ML20059K9471993-11-10010 November 1993 Notice of Violation from Insp on 931006-08.Violation Noted: Licensee Alcohol Testing Procedures Did Not Address Those QCs Used to Ensure Test Results Were Valid ML20059L0851993-11-0909 November 1993 Notice of Violation from Insp on 930904-1010.Violation Noted:Nrc Requirements Were Not Met for Listed Examples ML20058B7491993-10-15015 October 1993 Notice of Violation from Insp on 920802-29 & 1101-28. Violation Noted:Licensee Determined That Records Required by Statute or Commission Regulations,Orders or License Conditions Not Complete & Accurate ML20057E7731993-10-0101 October 1993 Notice of Violation from Insp on 930913-17.Violation Noted: Licensee Failed to Adequately Control Radioactive Material in That 930913,unattended Tranfer Bag Containing Unlabeled Radioactively Contaminated Material Found Outside Area ML20057A4141993-09-0303 September 1993 Notice of Violation from Insp on 930711-0807.Violation Noted:Licensee Implemented Design Change Outside Established Design Control Measures & Sys & Components Found Incorrectly Translated Into Listed Category 1 Drawing ML20057A4521993-08-20020 August 1993 Notice of Violation from Insp on 930628-0702 & 12-23. Violations Noted:Procedures Covering Test Activities of safety-related Equipment Not Implemented ML20056E2951993-08-12012 August 1993 Notice of Violation from Insp on 930712-16.Violation Noted: Licensee Granted 80 Individuals Unescorted Access W/O FBI Fingerprint Check Being Conducted & Failed to re-fingerprint 12 Individuals Deemed non-classifiable by FBI ML20056D1361993-07-23023 July 1993 Notice of Violation from Insp on 930621-25.Violations Noted:On 930428,worker Received Portal Contamination Monitor Alarm & Failed to Rept Event to Radcon Field Operations Shift Supervisor ML20056D1391993-07-21021 July 1993 Notice of Violation from Insp on 930606-0710.Violations Noted:Fuel Handling Supervisor Did Not Perform Evolutions of FHI-3A,recovery of Leaning Fuel Assembly H64 ML20128A4301993-01-15015 January 1993 Notice of Violation from Insp on 921129-930102.Violations Noted:Procedure S0I-82.2 Not Followed & Periodic Instruction 0-PI-OPS-000-006.0 Inadequate ML20062H5501990-11-20020 November 1990 Notice of Violation from Insp on 900723-0914.Violation Noted:Licensee Failed to Implement Instructions,Procedures & Performance That Would Prevent Storage &/Or Accumulation of Loose Conductive Matl in safety-related Electrical Boards ML20062F5541990-11-16016 November 1990 Notice of Violation from Insp on 901006-1105.Violation Noted:Large Amount of nonfire-rated Wood Left Unattended in Auxiliary Bldg on Elevation 669 ML20058F1271990-11-0101 November 1990 Notice of Violation from Insp on 900906-1005.Violation Noted:Root Cause of Reactor Trip Not Identified in post-trip Review Rept & Approved by Plant Operations Review Committee Prior to Plant Restart ML20058A8631990-10-11011 October 1990 Notice of Violation from Insp on 900827-31.Violations Noted: Procedure 1/2-PI-NXX-092-001.0 Incorrect & Failure to Follow Vendor Recommendations Re Power Range Instruments ML20056A4771990-07-27027 July 1990 Notice of Violation from Insp on 900606-0705.Violation Noted:Licensee Exceeded Overtime Requirements of AI-30 on Numerous Occasions from Nov 1989 - 900527 W/O Proper Authorization ML20248C1191989-09-22022 September 1989 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $87,500.Noncompliance Noted:Change Made to Facility as Described in FSAR W/O Performing Written Evaluation & Margin of Safety Reduced W/O NRC Approval ML20247B0061989-08-31031 August 1989 Notice of Violation from Insp on 890424-28.Violation Noted: Licensee Failed to Follow Procedures to Reduce Voltage at Shutdown Board & Board Voltage Remained at 7,400 Volts During Testing of Emergency Diesel Generator 2A-A ML20246M6161989-08-25025 August 1989 Notice of Violation from Insp on 890706-0805.Violation Noted:Channel N-31 Exhibited Severe Spiking & Taken Out of Svc W/O Level Trip Switch in Bypass Position & Licensee Failed to Reduce Power to Meet Action Statement 2.d ML20245K4361989-08-10010 August 1989 Notice of Violation from Insp on 890606-0705.Violation Noted:Unit 2 Operated at 100% Power W/O Operable Ice Bed Temp Monitor/Recorder in Main Control Room & Ice Bed Temp at Local Ice Condenser Temp Monitoring Panel Not Determined ML20245L3131989-08-0808 August 1989 Notice of Violation from Insp on 890626-30.Violation Noted: Failure to Instruct Workers in Use & Operation of Radiation Monitor Ludlum-300 ML20246B6321989-06-26026 June 1989 Notice of Violation from Insp on 890506-0605.Violations Noted:Configuration of RM 90-404 Re Detector Cable Not Correctly Controlled & Licensee Failed to Established Procedures to Maintain Thermal Power within License Limits ML20245D4041989-06-20020 June 1989 Notice of Violation from Insp on 890508-12.Violation Noted: Surveillance Procedure in Use,Did Not Adequately Account for RCS Leakage Measurements Which Result in Negative Unidentified Leakage 1999-02-01
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000327/19990051999-09-27027 September 1999 Insp Repts 50-327/99-05 & 50-328/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Mitigating Sys ML20210V1621999-08-13013 August 1999 Insp Repts 50-327/99-04 & 50-328/99-04 on 990601-0717.One Potentially Safety Significant Issue Noted.Major Areas Inspected:Licensee Emergency Preparedness IR 05000327/19990031999-06-30030 June 1999 Insp Repts 50-327/99-03 & 50-328/99-03 on 990328-0531.Non- Cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19990021999-04-23023 April 1999 Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19990011999-03-15015 March 1999 Insp Repts 50-327/99-01 & 50-328/99-01 on 990103-0213. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19983021999-03-12012 March 1999 NRC Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 (Including Completed & Graded Tests) for Test Administered on 980928-1001 ML20202J5471999-02-0101 February 1999 Notice of Violation from Insp on 981122-990102.Violation Noted:Following Unit 1 Rt on 981109,procedural Requirements of EOP ES0.1 Were Not Properly Implemented,In That RCS Temperatures Were Not Monitored & Steam Not Dumped IR 05000327/19980111999-02-0101 February 1999 Insp Repts 50-327/98-11 & 50-328/98-11 on 981122-990102. Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19980101998-12-0707 December 1998 Insp Repts 50-327/98-10 & 50-328/98-10 on 981011-1121.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980141998-12-0404 December 1998 Insp Repts 50-327/98-14 & 50-328/98-14 on 981102-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Sequoyah Nuclear Plan ML20196D6081998-11-24024 November 1998 Notice of Violation from Insp on 980914-1016.Violation Noted:As of 980916,requirements of 0-MI-MXX-061-001 Not Implemented IR 05000327/19980131998-11-24024 November 1998 Insp Repts 50-327/98-13 & 50-328/98-13 on 980914-1016. Violations Noted.Major Areas Inspected:Aspects of Licensee maint,testing,engineering,self-assessment & Problem Evaluations of Licensee Ice Condenser Sys ML20195G5521998-11-0909 November 1998 Notice of Violation from Insp on 980830-1010.Violation Noted:Licensee Failed to Assure That All Testing Required to Demonstrate That Safety Related Circuit Breakers Would Perform Satisfactorily in Svc IR 05000327/19980091998-11-0909 November 1998 Insp Repts 50-327/98-09 & 50-328/98-09 on 980830-1010. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19980081998-09-18018 September 1998 Insp Repts 50-327/98-08 & 50-328/98-08 on 980719-0829.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Licensee Conducted Radiological Emergency Plan Drill IR 05000327/19980071998-08-0404 August 1998 Insp Repts 50-327/98-07 & 50-328/98-07 on 980607-0718. Violations Noted.Major Areas Inspected:Aspects of Licensee Operation,Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Preventing Problems ML20237B1851998-08-0404 August 1998 Notice of Violation from Insp on 980606-0718.Violations Noted:On or Before 971103,conditions Adverse to Qualify Were Not Promptly Identified & Corrected,In That Licensee Failed to Correct &/Or Initiate Problem Evaluation Rept ML20236J6631998-06-26026 June 1998 Insp Repts 50-327/98-06 & 50-328/98-06 on 980426-0606. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20236J6591998-06-26026 June 1998 Notice of Violation from Insp on 980426-0606.Violation Noted:Inservice Testing of Valves Not in Accordance with Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda as Required by 10CFR50.55a IR 05000327/19983001998-06-25025 June 1998 NRC Operator Licensing Exam Repts 50-327/98-300 & 50-328/98-300 (Including Completed & Graded Tests) for Tests Administered on 980601-02 IR 05000327/19980051998-06-12012 June 1998 Insp Repts 50-327/98-05 & 50-328/98-05 on 980504-08.No Violations Noted.Major Areas Inspected:Maint Procedure.Insp Team Comprised Region II & Headquarters Personnel.Switchgear & Surrounding Areas Found in Good Matl Condition ML20247L5781998-05-15015 May 1998 Notice of Violation from Insp on 980315-0425.Violation Noted:Licensee Failed to Perform Surveillance Requirement 4.8.1.1.1.a,within 1 H & at Least Once Per 8 H Thereafter IR 05000327/19980041998-05-15015 May 1998 Insp Repts 50-327/98-04 & 50-328/98-04 on 980315-0425. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H7841998-04-10010 April 1998 Insp Repts 50-327/98-03 & 50-328/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H7701998-04-10010 April 1998 Notice of Violation from Insp on 980201-0314.Violation Noted:License Failed to Rept an Adverse Condition on Work Request/Work Order &/Or Problem Evaluation Rept IR 05000327/19980991998-04-0101 April 1998 SALP Repts 50-327/98-99 & 50-328/98-99 for Period 960728- 980221 ML20217K3751998-03-30030 March 1998 Notice of Violation from Insp on 980126-0213.Violation Noted:On Listed Dates,Licensee Made Changes to Facility as Described in FSAR W/O Adequate Written SE Which Provides Bases for Determination That Changes Did Not Involve USQ ML20217K3801998-03-30030 March 1998 Insp Repts 50-327/98-01 & 50-328/98-01 on 980126-0213.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980021998-03-0505 March 1998 Insp Repts 50-327/98-02 & 50-328/98-02 on 980202-06.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations & Maint.Review of Initial & Requalification Training Programs Were Also Conducted ML20203J5411998-02-19019 February 1998 Notice of Violation from Insp on 971231-980131.Violation Noted:On 980126 Individuals Failed to Monitor Themselves in Whole Body Contamination Monitor or W/Hand & Foot Frisk Monitor ML20203J5541998-02-19019 February 1998 Insp Repts 50-327/97-18 & 50-328/97-18 on 971221-980131. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Resolving Problems ML20216D8431998-02-0606 February 1998 EN-97-109A:on 980206,informs of Withdrawal of Proposed Civil Penalty of $55,000 Issued to Licensee.Credit for Identification Appropriate to Recognize Diligence of TVA Training Instructor Who Discovered Vital Battery Problem IR 05000327/19970171998-01-16016 January 1998 Insp Repts 50-327/97-17 & 50-328/97-17 on 971109-1220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970141997-12-0808 December 1997 Insp Repts 50-327/97-14 & 50-328/97-14 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support,Effectiveness of License Controls in Identifying,Resolving & Preventing Problems ML20197F5541997-12-0808 December 1997 Notice of Violation from Insp on 970725-0704 & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Sro Failed to Implement Step 8.4.8 of Soi 0-S0-250-1. Predecisional EC Agenda & Documentation Encl IR 05000327/19970161997-12-0505 December 1997 Insp Repts 50-327/97-16 & 50-328/97-16 on 971103-06.No Violations Noted.Major Areas Inspected:Evaluation of 971017 Wire Damage Event at Electrical Penetration 22 ML20197F6971997-12-0303 December 1997 EN-97-109:on 971208,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Severity Level III Problem Re Failure to Maintain Direct Current Vital Battery Channel Energized & Operable ML20199H1451997-11-0606 November 1997 Exam Repts 50-327/97-300 & 50-328/97-300 on 970919-1007. Exam Results:Four Out of Seven Candidates Passed Exam.One Candidate Was Marginal Performer IR 05000327/19970121997-10-24024 October 1997 Insp Repts 50-327/97-12 & 50-328/97-12 on 970824-0927.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support & Operator Requalification Program IR 05000327/19970151997-10-23023 October 1997 Insp Repts 50-327/97-15 & 50-328/97-15 on 970922-29.No Violations Noted.Major Areas Inspected:Emergency Preparedness PNO-II-97-055, on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie1997-10-0606 October 1997 PNO-II-97-055:on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie ML20211E2531997-09-22022 September 1997 Notice of Violation from Insp on 970706-0823.Violation Noted:On 970714,containment Isolation Valve 1-FCV-31C-229 Failed to Exhibit Required Change of Obturator Position & Was Not Repaired or Replaced & Data Not Analyzed IR 05000327/19970081997-09-22022 September 1997 Insp Repts 50-327/97-08 & 50-328/97-08 on 970706-0823. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970091997-09-15015 September 1997 Insp Repts 50-327/97-09 & 50-328/97-09 on 970804-08.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering Re Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems ML20198H7911997-09-11011 September 1997 Insp Repts 50-327/97-13 & 50-328/97-13 on 970725-0904. Violations Noted.Major Areas Inspected:Insp Scope,Event Synopsis & Observations & Findings ML20141H9581997-07-28028 July 1997 Insp Repts 50-327/97-06 & 50-328/97-06 on 970525-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20141H9531997-07-28028 July 1997 Notice of Violation from Insp on 970525-0705.Violation Noted:Licensee Failed to Implement Prompt Corrective Actions to Resolve Condition Adverse to Quality ML20149L5671997-07-24024 July 1997 Notice of Violation from Insp on 970623-27.Violation Noted: on 960627,licensee Had Loss of Security Electronic Equipment & Failed to Post Officers in Position to Provide Surveillance of Entire Protected Area Perimeter IR 05000327/19970071997-07-24024 July 1997 Insp Repts 50-327/97-07 & 50-328/97-07 on 970623-27. Violations Noted.Major Areas Inspected:Aspects of Licensee Plant Support ML20149G8681997-07-10010 July 1997 Notice of Violation from Insp on 970324-0522.Violation Noted:Licensee Failed to Esatblish Measures to Assure That Significant Condition Adverse to Quality Was Promptly Identified & Corrected & C/A Taken to Preclude Repetition 1999-09-27
[Table view] |
Text
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NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 and 50 328 Sequoyah Units 1 & 2 License Nos. DPR-77 and DPR 79
, EA 97-083 EA 97 233 b
During an NRC inspection conducted from March 2 through April 12, 1997, 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. Technical S>ecification 6.8.1.a requires, in part, that procedures shall be establisled, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2 February :
1978, " Quality Assurance Program Requirements (Operations)." Appendix A of Regulatory Guide 1.33, Section 4, includes procedures for startup and shutdown of the Fuel Storage Pool Purification and Cooling System.
System Operating Instruction (50I) 78.1, Spent Fuel Pit Coolant System (SFPCS), Revision 53, provided instruction for placing in service the C-S SFPCS pump, including opening the pump discharge valve.
Contrary to the above, on March 24, 1997, the licensee failed to open the C S SFPCS pump discharge valve when placing the C-S aum) in service.
The system subsequently operated for about 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> wit 1 t1e discharge valve closed and cooling flow to the spent fuel pool isolated.
This is a Severity Level IV Violation (Supplement I).
B. Technical S)ecification 6.8.1.a requires, in part, that procedures shall be establisled, implemented, and maintained covering the activities t recommended in Appendix A of Regulatory Guide 1.33 Revision 2. February 1978, " Quality Assurance Program Requirements (Operations)." Appendix A of Regulatory Guide 1.33, Section 9, requires procedures for maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with documented
, instructions.
d Work Order 97-006117, was issued to provide instructions to repair electrical conductors which had been damaged during a modification to a l main control room hand switch. The Work Order required, as a prerequisite to the repair, that electrical breaker 1716 be verified open. !
- I Enclosure 1 9705190290 970512
- {DR ADOCK 05000327 PDR
- i NOV 2 Contrary to the above, on April 4, 1997, Work Order 97-006117 was not followed in that the licensee did not ensure that electrical breaker 1716 was open arior to beginning repair of the damaged conductors.
Consequently w1en repairs began, power was lost to the 1A A Shutdown Board.
This is a Severity Level IV Violation (Supplement I), for Unit 1 only.
C. Unit 2 Technical Specification.(TS) 4.3.1.1.2 requires that the total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation. This TS is applicable to components listed in Table 3.31, Reactor Trip System Instrumentation. Table 3.3 1.
Functional Unit 22, Reactor Trip System Interlocks Section "G",
contains the Reactor Trip - P-4 function.
Contrary to the above:
- 1. On August 29, 1996, the Unit 2 "A" reactor trip breaker total interlock function was not demonstrated to be OPERABLE at least ,
once per 18 months for the Table 3.31 Functional Unit 22.G. !
Reactor Trip P 4 interlock, in that the "A" reactor trip breaker >
P 4 reactor trip turbine trip interlock (breaker contactor) had not been tested since May 1994 as a " spare" and was installed as i an OPERABLE component. The breaker was not adequately tested until January 18, 1997.
2
- 2. On August 29, 1996, for the "A" reactor tria breaker and on October 22, 1996, for the "B" reactor trip areaker, the total interlock function was not demonstrated to be OPERABLE at least once per 18 months for the Table 3.3 1 Functional Unit 22.G, Reactor Trip - P 4 interlock, in that following replacement of the
. in service reactor trip breakers with spare / refurbished breakers, the reactor trip breaker auxiliary contacts to cubicle contacts were not checked to verify circuit continuity. This invalidated the previous 18 month TS 4.3.1.1.2 surveillance, which was last completed on May 31, 1996. The breakers were not adequately tested until January 18. 1997. for the "A" reactor trip breaker and on February 7, 1997, for the "B" reactor trip breaker.
This is a Severity Level IV Violation (Supplement I), for Unit 2 only.
D. Technical S>ecification 6.8.1.a requires, in part, that procedures shall be establisled, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2. February 1978, " Quality Assurance Program Requirements (Operations)." Appendix A of Regulatory Guide 1.33, Section 5, requires procedures for Abnormal, offnormal or Alarm conditions.
Site Standard Practice (SSP) 8.50, Conduct of Technical Support, Revision 10, requires that the Technical Support System Engineer respond to a Technical Support Investigation Request (TSIR).
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O NOV 3 Contrary to the above, Technical Support failed to adequately respond to TSIR 96 N55 77 580, dated October 29, 1996 and TSIR No. 96 NSS 77 630, dated December 28, 1996, which identified offnormal and alarm conditions associated with the Turbine Driven Auxiliary Feedwater (TDAFW) sump pumps until March 13, 1997. On March 17, 1997, Technical Support determined that both sump pumps were significantly degraded, which potentially could have caused the TDAFW pump to overspeed.
This is a Severity Level IV Violation (Supplement I), for Unit 1 only.
E. Technical Saecification 6.8.1.a requires, in part, that procedures shall be establis1ed, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33. Revision 2, February 1978, " Quality Assurance Program Requirements (Operations)." Appendix A of Regulatory Guide 1.33, Section 1, requires administrative equipment control.
Site Standard Practice (SSP) 12.53, Annunciator Disablement, Revision 5, requires that prior to the disablement of any annunciator the reason for the annunciator to be in the alarm condition shall be thoroughly evaluated.
Contrary to the above, on November 30, 1996, the Unit 1 Turbine Driven Auxiliary Feedwater sump high level annunciator was disabled without the reason for the alarm condition being thoroughly evaluated.
This is a Severity Level IV Violation (Supplement I), for Unit 1 only.
F. 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, requires that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.
Contrary to the above, since September 18, 1990, the licensee had failed to implement promat corrective action to resolve a condition adverse to '
quality as descriaed in Problem Evaluation Report (PER) No.
SQP900372PER. The PER described reactor core design changes which had been implemented and had not been reconciled or reflected in Nuclear Engineering (NE), design basis documents, environmental qualification binders. As of April 1,1997, the EQ binders had not been revised.
This is a Severity Level IV Violation (Supplement I).
G. 10 CFR 50, Appendix B, Criterion III, Design Control, requires in part that measures be established to assure that applicable regulatory requirements are correctly translated into drawings and procedures. The measures shall include provisions to assure that appropriate quality standards are specified and included in design documents. The design control measures shall also provide for verifying or checking the adequacy of design.
Tennessee Valley Authority Nuclear Quality Assurance Plan TVA NQA PLNB9-A. Revision 6. Section 7.0, Design Control, requires that measures be
NOV 4 established to ensure that the performance of design analysis shall be :
planned and controlled. Additionally. it requires that measures to control plant configuration and ensure that the actual 31 ant :
configuration is accurately depicted on drawings and otler appropriate ;
design output documents and reconciled with the applicable design basis '
shall be established, documented, and implemented.
TVA NQA PLN89 A, through Section 7.0 and Appendix B, endorses the requirements of ANSI N45.2.11-1974, Quality Assurance Requirements for :
the Design of Nuclear Power Plants. Section 4.0 of this standard requires that design analyses shall be performed in a planned, ,
controlled, and correct manner. Design analyses shall also be in a form suitable for reproduction, filing and retrieving.
Contrary to the above the established design control measures were i deficient'in that the following deficiencies were identified:
- 1. As of July 30,-1990, radiation dose values contained in design basis calculation TI RPS 48, Integrated Accident Dose Inside Primary Containment and Annulus, Revision 3, were never incorporated in calculation TI-ECS 55, Summary of Harsh Environment Conditions for Sequoyah Nuclear plant, to ensure revision of environmental data drawing series number 47E235.
Additionally, FSAR Figures 3.11.21. and 3.11.2 2 were never revised to reflect the new 100 day integrated accident doses based on a source term of 1000 EFPD. This failure to control plant configuration and ensure that actual plant configuration was accurately depicted on drawings resulted in discrepancies in design basis information listed in FSAR Table 15.1.7 1 and FSAR Figures 3.11.2-1 and 3.11.2-2.
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- 2. On December 12, 1991, TVA management approved design basis calculation TI-RPS 48, Revision 5, " Integrated Accident Dose Inside of Primary Containment and Annulus," to document the ,
100 day integrated beta and gamma radiation doses based on a i' source term of 650 EFPD. Radiation dose values contained in this calculation were not incorporated into calculation TI-ECS 55,
" Summary of Harsh Environment Conditions for Sequoyah Nuclear Plant. Additionally, plant modification DCN No. 508114A, Revision 16, revised environmental drawings number 1,2-47E235 sheets 45, 47, and 48 to realace radiation values that were no longer conservative. T1ese drawing revisions did not accurately depict actual plant configuration in that on the following dates listed the core average exposure for both units exceeded 650 EFPD :
operation. t i
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NOV 5 Unit No. Cycle No. Date EFPD Exceeded 1 4 12-29 89 1 5 06 09 91 2 3 12 30 88
. 2 4 05 24 90 2 5 09 28 91 This failure to control plant configuration and ensure that actual plant configuration is accurately depicted on drawings resulted in :
discrepancies between the units current licensing basis of 1000 EFPD burnup criterion and approved design basis information ;
depicted on the environmental drawings.
- 3. From February 11, 1994, to November 15, 1996, the licensee failed to perform a calculation to determine the integrated maximum ,
hypothetical accident gamma and beta doses inside the primary containment to support a justification for continued operation for SQ PER 900372 PER.
This is a Severity Level IV Violation (Supplement I).
Pursuant to the provisions of 10 CFR 2,201 Tennessee Valley Authority 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 II, 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). This reply should be clearly marked as a " Reply to a Notice of i 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 i include previously docketed correspondence, if the correspondence adequately i addresses the required 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 I why such other action as may be proper should not be taken. Where good cause l is shown, consideration will be given to extending the response time. I Because your res>onse will be placed in the NRC Public Document Room (PDR), to the extent possi ale, it should not include any personal privacy, 3roprietary, or safeguards information so that it can be placed in the PDR wit 1out redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such meterial, you must s)ecifically identify the portions of your response that you seek to have with1 eld and provide in detail the bases 1
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NOV 6 for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Atlanta, Georgia this 12th day of May 1997