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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20210H1591999-07-23023 July 1999 Notice of Violation from Insp on 990308-10.Violation Noted: from Time of Receipt of Alarm Until Arrival at Three Different Vital Areas,Response Objective & Physical Security Plan Were Not Met ML20236J6971998-07-0101 July 1998 Notice of Violation from Insp on 980412-0530.Violation Noted:Several Conditions Adverse to Quality Associated W/Cr Ventilation Sys Were Not Promptly Corrected.Conditions Inappropriately Closed Out Before Adequate C/As Completed ML20217E5921998-03-23023 March 1998 Notice of Violation from Insp on 980111-0212.Violation Noted:While Performing Maint on 1A Centrifugal Charging Pump,Maint Personnel Violated Requirements of FNP-0-M-001, Rev 13 IR 07100019/20110291997-12-29029 December 1997 Notice of Violation from Insp on 971019-1129.Violation Noted:As Early as June 1985,licensee Identified Degradation of Cork Seal Between Containment & Auxiliary Bldg Walls, Condition Adverse to Quality ML20199H1281997-11-17017 November 1997 Notice of Violation from Insp on 970907-1018.Violations Noted:Battery Capacity After Svc Test Was Inadequate & Check Valve V003 & V002D F & H Were Not Flow Tested in Manner That Proves That Disk Travels to Seat on Cessation ML20211Q9391997-10-0606 October 1997 Notice of Violation from Insp on 970803-0906.Violation Noted:As of 970906 Licensee Installed One 1-inch Thick Wrap of Kaowool on Sides & Bottoms of Raceways BDE-9 & BDE-15, Carrying Train B Charging Pump Power Cable in Fire Area ML20211K8161997-09-26026 September 1997 Notice of Violation from Insp on 970818-22.Violation Noted: Noted:Nrc Identified That Licensee Failed to Correctly Translate Applicable Design Specfication Input Requirements for Kaowool Electrical Raceway Fire Barrier Sys at Plant ML20217R2021997-08-28028 August 1997 Notice of Violation from Insp on 970622-0802.Violation Noted:On 970616,most of M&TE Used Onsite Did Not Have Written & Approved Calibration Procedures ML20148K6431997-06-0909 June 1997 Notice of Violation from Insp on 970330-0510.Violation Noted:On 970321,facility Licensee Physician Determined That Licensed Operator Eyesight No Longer Met Min Stds Required by 10CFR55.33(a)(1) as Measured by Std of ANSI/ANS-3.4-1983 ML20196G4241997-05-0606 May 1997 Notice of Violation from Insp Completed on 970314.Violation Noted:Prior to 970314,licensee Failed to Prescribe Documented Instructions or Procedures to Implement Listed Activities Affecting Quality of Operation of PRF Sys ML20140B7851997-03-17017 March 1997 Notice of Violation from Insp on 970105-0215.Violation Noted:Test Engineer Failed to Comply W/Procedural Requirements of FNP-1-STP-124.0 During Performance Testing of Plant Penetration Room Filtration Sys Train a ML20133F6891996-12-23023 December 1996 Notice of Violation from Insp on 961013-1123.Violation Noted:On 961010,security Guards Failed to Search Westinghouse Sludge Lance Trailer Prior to Allowing Trailer to Enter Plant Protected Area ML20149M5771996-12-0404 December 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Licensee Failed to Assure Electrical Cables Associated W/Sys Necessary to Achieve & Maintain Hot SD Conditions Encl in Fire Barrier ML20134J4201996-11-0808 November 1996 Notice of Violation from Insp on 960901-1012.Violation noted:non-licensed Sys Operators in Two Separate Events Failed to Properly Implement Applicable Sys Operating Procedures ML20128J9581996-09-27027 September 1996 Notice of Violation from Insp on 960721-0831.Violation Noted:Unit 1 Nis IR Channel Compensating Voltage for NI-35 Was Adjusted by Plant Technicians,Being Below Scale & SR Counts Were Less than 100 Cps ML20128H7431996-09-27027 September 1996 Notice of Violation from Insp on 960812-16 & 26-30. Violations Noted:Properly Approved Configural Control Procedures & Drawings Not Followed in That as Built Sample Line Not Constructed IAW Production Change Notice ML20029E0641994-05-0202 May 1994 Notice of Violation from Insp on 940314-0410.Violation Noted:Licensee,On 940201,operated Reactor at Power in Mode 1 Rendering Nuclear Instrumentation Sys Power Range Channels Inoperable for Approx 10 to 12 H ML20058P7581993-12-0101 December 1993 Notice of Violation from Insp on 930923-1025.Violation Noted:Planner for Work Package Did Not List Removal of A/C Panel as Required Per Step 7.5.1 ML20057E4871993-10-0101 October 1993 Notice of Violation from Insp on 930816-0903.Violation Noted:As of 930903,measures Not Established Assuring That Cause of Conditions Adverse to Quality Determined & C/A Taken to Preclude Repetition of Listed Events ML20057C3021993-09-13013 September 1993 Notice of Violation from Insp on 930730-0830.Violation Noted:Plant Sys Operator & Licensed Shift Foreman Erroneously Isolated Component Cooling Water to Secondary HX Loads ML20056E3221993-08-12012 August 1993 Notice of Violation from Insp on 930712-16.Violation Noted: NRC Identified Multiple Examples of Containers of Radioactive Matl That Were Not Labeled as Required by Licensee Procedure ML20056D2141993-07-23023 July 1993 Notice of Violation from Insp on 930621-25.Violation Noted: Licensee Issued Liquid Waste Release Permit for Batch Release of Liquid Waste Monitor Tank Which Failed to Identify Particulate Nuclides ML20045E5641993-06-0808 June 1993 Notice of Violation from Insp on 930416-0521.Violation Noted:On May 12,electrician Failed to Follow Specified Clearance Tag Out Instructions When Removing Unit 1 1B EDG Output Circuit Breaker ML20036B7371993-05-11011 May 1993 Notice of Violation from Insp on 930324-26,0329-0401 & 0426-27.Violation Noted:As of 930401,selected Background Investigation & Psychological Evaluation Records Contained Incomplete Actual & Checklist Data as Listed ML20035D3611993-03-26026 March 1993 Notice of Violation from Insp on 930210-0322.Violation Noted:On 930202 Operator at Controls Failed to Properly Follow Procedure STP-45.4 ML20128A6821993-01-26026 January 1993 Notice of Violation from Insp on 921208-930108.Violation Noted:Lubricating Oil Was Not Properly Controlled in That Oil Other than That Specified in Applicable Equipment Lubrication & Vendor Manuals Used in Listed Equipment ML20043D8221990-05-29029 May 1990 Notice of Violation from Insp on 900411-0510.Violation noted:10% of 8-h Individual self-contained Battery Packs Found to Have Low Electrolyte Levels,Per Emergency Lighting Sys Requirements ML20012F3031990-03-29029 March 1990 Notice of Violation from Insp on 900226-0302.Violation Noted:On 890524,power-range Flux Trip High Setpoint Increased from Indicated 80% to 109% Rated Thermal Power, Exceeding Limiting Safety Sys Setting of Setpoint ML19332E9471989-12-0101 December 1989 Notice of Violation from Insp on 891002-06.Violation Noted: Contract Worker Performing Svc Insp Work Entered High Radiation Area W/O Authorization from Health Physics ML19332E4841989-11-22022 November 1989 Notice of Violation from Insp on 891002-06 & 16-20.Violation Noted:Failure of Turbine Driven Auxiliary Feedwater Pump Inservice Testing Procedures to Contain Acceptance Criteria for Comparison of Pump Differential Pressure ML19332E4711989-11-0909 November 1989 Notice of Violation from Insp on 890911-1010.Violation Noted:During Unit 2 Refueling Outage,Between Mar & May 1989, Operators Routinely Required to Work 84 H During Seven Consecutive Day Period & Allowed to Work on Days Off ML20248C8111989-07-27027 July 1989 Notice of Violation from Insp on 890424-27 & 0508-12. Violations Noted:Circuit Breakers Not Calibr for Several Yrs Due to Temporary Change Notice to Maint Procedure FNP-0-MP-28.116 Deleting Calibr Requirement for Dc Breakers ML20247R5241989-07-26026 July 1989 Notice of Violation from Insp on 890509-10.Violations Noted:On 890429,30 & 0501 Licensee Affixed Byproduct Matl to Us Currency to Identify Thief & on 890507 Plant Operator Observed Entering High Radiation Area W/O Dosimeter ML20246B0121989-06-16016 June 1989 Notice of Violation from Insp on 890411-0510.Violations Noted:Containment Integrity Breached During Replacement/ Placement of Fuel within Reactor Containment ML20245H5561989-04-19019 April 1989 Notice of Violation from Insp on 890311-0410.Violation Noted:Fire Protection Panel for Sys FSP-21-59 at 139 Ft Elevation of West Corridor Placed in Override Position on 890224 to Perform Cleaning & Calibr of Sys Smoke Detectors ML20245D8061988-09-26026 September 1988 Notice of Violation from Insp on 880811-0910.Violation Noted:Valve Left Open Following Addition of Resin to Cation Demineralizer During Mar-May 1988 Refueling Outage & Bearing Oil Cooler for Pump 2A Overheated ML20151L5741988-07-21021 July 1988 Notice of Violation from Insp on 880611-0710.Violation Noted:Deficient Procedural Implementation Re Storage of 18 Charcoal Filter Elements in Penetration Ventilation Equipment Room ML20151D6401988-07-0707 July 1988 Notice of Violation from Insp on 880511-0610.Violation Noted:Failure to Follow Procedures for Storage of Compressed Gas Cylinders & to Provide Adequate Operability Insps on Unit 1 post-accident Containment Ventilation Filter Unit ML20150C1221988-06-28028 June 1988 Notice of Violation from Insp on 880516-20 & 0606-10. Violation Noted:Procedure,Used to Perform RCS Water Inventory Balance,Was Not Capable of Performing That Required Surveillance Reliably ML20154P5901988-05-20020 May 1988 Notice of Violation from Insp on 880328-0401.Violation Noted:Licensee Failed to Make Attenuation Corrections for Calibr Detectors W/Solid Geometrics Which Resulted in Inaccurate Gamma Spectroscopy Measurements of Gaseous Matl ML20154Q0311988-05-18018 May 1988 Notice of Violation from Insp on 880222-26 & 0307-11. Violation Noted:Failure to Follow Procedures & Failure to Prevent Deficient Conditions from Reccurring in Cases Listed ML20151N8591988-04-19019 April 1988 Notice of Violation from Insp on 880321-24.Violation Noted: Cabinet Containing Safeguards Info Insecure & Unattended ML20148E6191988-03-18018 March 1988 Notice of Violation from Insp on 880229-0304.Violation Noted:Personnel Designated as Operations Shift Aide, Appointed by Interim Emergency Director,Did Not Receive Required Annual Retraining for Communications Personnel ML20148F4271988-03-10010 March 1988 Notice of Violation from Insp on 880104-06.Violation Noted:Radiological Exclusion Area Not Provided W/Locked Doors,But Was Provided W/Warning Signs & Flashing Red Light,Not Adequate to Prevent Unauthorized Entry ML20150B2981988-02-25025 February 1988 Notice of Violation from Insp on 880112-0210.Violations Noted:Required Fire Watches Not Initiated & Fire Suppression Sys Inoperable for 14 H ML20150B5871988-02-19019 February 1988 Notice of Violation from Insp on 871202-04.Violations Noted: Valve Testing Not Performed in Accordance W/Approved Test Procedure & Licensee Failed to Provide Instructions for Fill & Vent of Portion of RHR Train a Piping ML20236X8281987-12-0404 December 1987 Notice of Violation from Insp on 871102-06.Violation Noted: Emergency Diesel Generator Test Data Logs Not Completed as Specified in 850909 Operations Dept Memo ML20236R8301987-11-17017 November 1987 Notice of Violation from Insp on 871019-23.Violation Noted: Work Performed Inside Controlled Area W/O Wearing Protective Clothing Required by RWP 0-87-001A ML20236M9981987-11-0303 November 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Inadequate Control & Installation of Purchased Equipment & Inadequate Corrective Actions & Insps ML20236M8011987-10-28028 October 1987 Notice of Violation from Insp on 870910-1009.Violation Noted:Continuous Fire Watch Assigned to Roof of Auxiliary Bldg to Monitor Open Flame Operations Associated W/Roofing Repairs Not Alert to Duties 1999-07-23
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000348/19990051999-09-0202 September 1999 Insp Repts 50-348/99-05 & 50-364/99-05 on 990627-0807.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000348/19990041999-07-26026 July 1999 Insp Repts 50-348/99-04 & 50-364/99-04 on 990516-0626.One Noncited Violation Identified.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20210H1591999-07-23023 July 1999 Notice of Violation from Insp on 990308-10.Violation Noted: from Time of Receipt of Alarm Until Arrival at Three Different Vital Areas,Response Objective & Physical Security Plan Were Not Met IR 05000348/19990031999-06-10010 June 1999 Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000348/19990021999-04-29029 April 1999 Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000348/19990091999-04-0606 April 1999 Partially Withheld Insp Repts 50-348/99-09 & 50-364/99-09 on 990308-10 (Ref 10CFR73.21).Non-cited Violation Identified. Major Areas Inspected:Area of Plant Support Re Physical Security Program for Power Reactors IR 05000348/19990011999-03-19019 March 1999 Insp Repts 50-348/99-01 & 50-364/99-01 on 990110-0220. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000348/19980081999-02-0202 February 1999 Insp Repts 50-348/98-08 & 50-364/98-08 on 981129-990109.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000348/19980141999-01-0808 January 1999 Partially Withheld Insp Repts 50-348/98-14 & 50-364/98-14 on 981207-10 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress IR 05000348/19980071998-12-28028 December 1998 Insp Repts 50-348/98-07 & 50-364/98-07 on 981018-1128.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000348/19980061998-11-10010 November 1998 Insp Repts 50-348/98-06 & 50-364/98-06 on 980830-1017.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000348/19980101998-11-0303 November 1998 Insp Repts 50-348/98-10 & 50-364/98-10 on 980908-11.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise & Response in Control Room Simulator & Technical Support Ctr IR 05000348/19980051998-09-28028 September 1998 Insp Repts 50-348/98-05 & 50-364/98-05 on 980712-0829.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000348/19980041998-08-10010 August 1998 Insp Repts 50-348/98-04 & 50-364/98-04 on 980601-0711.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20236J7021998-07-0101 July 1998 Insp Repts 50-348/98-03 & 50-364/98-03 on 980412-0530.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20236J6971998-07-0101 July 1998 Notice of Violation from Insp on 980412-0530.Violation Noted:Several Conditions Adverse to Quality Associated W/Cr Ventilation Sys Were Not Promptly Corrected.Conditions Inappropriately Closed Out Before Adequate C/As Completed IR 05000348/19980991998-06-29029 June 1998 SALP Repts 50-348/98-99 & 50-364/98-99 Covering Period 961124-980530 IR 05000348/19980021998-05-0808 May 1998 Insp Repts 50-348/98-02 & 50-364/98-02 on 980221-0411.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20217E5921998-03-23023 March 1998 Notice of Violation from Insp on 980111-0212.Violation Noted:While Performing Maint on 1A Centrifugal Charging Pump,Maint Personnel Violated Requirements of FNP-0-M-001, Rev 13 PNO-II-98-013, on 980308,util Declared NOUE Due to High River Level & Subsequent Flooding.Licensee Established Constant Communications W/Early,Ga & Houston County,Al.Resident Inspectors Are Monitoring Licensee Activities1998-03-0909 March 1998 PNO-II-98-013:on 980308,util Declared NOUE Due to High River Level & Subsequent Flooding.Licensee Established Constant Communications W/Early,Ga & Houston County,Al.Resident Inspectors Are Monitoring Licensee Activities IR 05000348/19970151998-02-0909 February 1998 Insp Repts 50-348/97-15 & 50-364/97-15 on 971130-980110. No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 07100019/20110291997-12-29029 December 1997 Notice of Violation from Insp on 971019-1129.Violation Noted:As Early as June 1985,licensee Identified Degradation of Cork Seal Between Containment & Auxiliary Bldg Walls, Condition Adverse to Quality IR 05000348/19970141997-12-29029 December 1997 Insp Repts 50-348/97-14 & 50-364/97-14 on 971019-1129. Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000348/19970131997-11-20020 November 1997 Partially Withheld Insp Repts 50-348/97-13 & 50-364/97-13 on 971021-24 (Ref 10CFR73.21).Major Areas Inspected:Physical Security Program for Power Reactors IR 05000348/19970111997-11-17017 November 1997 Insp Repts 50-348/97-11 & 50-364/97-11 on 970907-1018. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering ML20199H1281997-11-17017 November 1997 Notice of Violation from Insp on 970907-1018.Violations Noted:Battery Capacity After Svc Test Was Inadequate & Check Valve V003 & V002D F & H Were Not Flow Tested in Manner That Proves That Disk Travels to Seat on Cessation IR 05000348/19970071997-10-10010 October 1997 Insp Repts 50-348/97-07 & 50-364/97-07 on 970825-29.No Violations Noted.Major Areas Inspected:Licensee Corrective Action Program,Including Problem Identification & Resolution ML20211Q9391997-10-0606 October 1997 Notice of Violation from Insp on 970803-0906.Violation Noted:As of 970906 Licensee Installed One 1-inch Thick Wrap of Kaowool on Sides & Bottoms of Raceways BDE-9 & BDE-15, Carrying Train B Charging Pump Power Cable in Fire Area ML20211K8161997-09-26026 September 1997 Notice of Violation from Insp on 970818-22.Violation Noted: Noted:Nrc Identified That Licensee Failed to Correctly Translate Applicable Design Specfication Input Requirements for Kaowool Electrical Raceway Fire Barrier Sys at Plant ML20217R2021997-08-28028 August 1997 Notice of Violation from Insp on 970622-0802.Violation Noted:On 970616,most of M&TE Used Onsite Did Not Have Written & Approved Calibration Procedures IR 05000348/19970081997-08-28028 August 1997 Insp Repts 50-348/97-08 & 50-364/97-08 on 970622-0802. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support PNO-II-97-039A, on 970720,Hurricane Danny Downgraded to Depression.Storm Disipated Without Reaching Farley Nuclear Plant.Farley Nuclear Plant Experienced Light Rain W/Both Units Remaining at Full Power1997-07-21021 July 1997 PNO-II-97-039A:on 970720,Hurricane Danny Downgraded to Depression.Storm Disipated Without Reaching Farley Nuclear Plant.Farley Nuclear Plant Experienced Light Rain W/Both Units Remaining at Full Power IR 05000348/19970061997-07-18018 July 1997 Insp Repts 50-348/97-06 & 50-364/97-06 on 970511-0621.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support PNO-II-97-039, on 970718,response Was Made to Hurricane Danny.Region II State Liason Officer Has Been in Contact W/Fema & State of Al.Plant Staff Taking Precautionary Measures in Preparation for High Wind Conditions1997-07-18018 July 1997 PNO-II-97-039:on 970718,response Was Made to Hurricane Danny.Region II State Liason Officer Has Been in Contact W/Fema & State of Al.Plant Staff Taking Precautionary Measures in Preparation for High Wind Conditions ML20148K6431997-06-0909 June 1997 Notice of Violation from Insp on 970330-0510.Violation Noted:On 970321,facility Licensee Physician Determined That Licensed Operator Eyesight No Longer Met Min Stds Required by 10CFR55.33(a)(1) as Measured by Std of ANSI/ANS-3.4-1983 ML20148K6511997-06-0909 June 1997 Insp Repts 50-348/97-05 & 50-364/97-05 on 970330-0510. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000348/19972011997-05-13013 May 1997 Insp Repts 50-348/97-201 & 50-364/97-201 on 970127-0314.No Violations Noted.Major Areas Inspected:Engineering, Auxiliary Feedwater Sys,Component Cooling Water Sys & Sys Interface Design Review ML20196G4241997-05-0606 May 1997 Notice of Violation from Insp Completed on 970314.Violation Noted:Prior to 970314,licensee Failed to Prescribe Documented Instructions or Procedures to Implement Listed Activities Affecting Quality of Operation of PRF Sys ML20138J6661997-04-28028 April 1997 Insp Repts 50-348/97-03 & 50-364/97-03 on 970216-0329. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support,Including Health Physics IR 05000348/19973001997-04-22022 April 1997 Exam Repts 50-348/97-300 & 50-364/97-300 on 970324-27.Exam Results:Two of 5 Applicants Passed Exam.One Was Grades as Marginal Pass ML20137U6021997-04-0202 April 1997 Insp Repts 50-348/97-04 & 50-364/97-04 on 970125-0314. Violations Noted.Major Areas Inspected:Detailed Esfs Review & Walkdown of Units 1 & 2 PRF Sys,Including Associated Surveillance Test & Sys Design Requirements ML20140B7851997-03-17017 March 1997 Notice of Violation from Insp on 970105-0215.Violation Noted:Test Engineer Failed to Comply W/Procedural Requirements of FNP-1-STP-124.0 During Performance Testing of Plant Penetration Room Filtration Sys Train a ML20140B7921997-03-17017 March 1997 Insp Repts 50-348/97-01 & 50-364/97-01 on 970104-0215. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000348/19960151997-02-0303 February 1997 Insp Repts 50-348/96-15 & 50-364/96-15 on 961124-970104.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20134G3961997-01-24024 January 1997 Insp Repts 50-348/96-14 & 50-364/96-14 on 961209-13.No Violations Noted.Major Areas Inspected:Biennial Emergency Preparedness Exercise ML20133G8371997-01-0909 January 1997 SALP Repts 50-348/96-99 & 50-364/96-99 for Period 950326- 961123 ML20133F6891996-12-23023 December 1996 Notice of Violation from Insp on 961013-1123.Violation Noted:On 961010,security Guards Failed to Search Westinghouse Sludge Lance Trailer Prior to Allowing Trailer to Enter Plant Protected Area ML20133F6921996-12-23023 December 1996 Insp Repts 50-348/96-13 & 50-364/96-13 on 961013-1123. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20149M5771996-12-0404 December 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Licensee Failed to Assure Electrical Cables Associated W/Sys Necessary to Achieve & Maintain Hot SD Conditions Encl in Fire Barrier ML20134J4201996-11-0808 November 1996 Notice of Violation from Insp on 960901-1012.Violation noted:non-licensed Sys Operators in Two Separate Events Failed to Properly Implement Applicable Sys Operating Procedures 1999-09-02
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NOTICE Of VIOLATION Southern Nuclear Operating Company Docket Nos.:
50-348 and 50-364 farley Nuclear Plant. Units 1 and 2 License Nos..
NPF-2 and NPF-8 During an U.S. Nuclear Regulatory Commission (NRC) inspection conducted during the period September 7 through October 18. 1997. certain violations of NRC requirements were identifled.
In accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions." NUREG-1600. the violations are listed below:
A.
10 CfR 50.36(c)(3). Technical Specifications. Surveillance Requirements, states, in part, that surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, and that limiting conditions for operation will be met.
Contrary to the above. as of March 14. 1997, the Auxiliary Building.
Direct Current (DC) Distribution technical specification (TS) surveillance requirement (4.8.2.3.2.C.5). battery capacity after a service test, was inadequate to ensure that limiting conditions for operation would be met.
Specifically. the battery surveillance requirement specified in TS Section 4.8.2.3.2.c.5 was less conservative than the design voltages specified in calculation 07597-E144.
Battery operation at the TS allowed voltage would not have met the design requirement for supplying adequate voltage for all safety-related components.
This is a Severity Level IV violation (Supplement 1).
B.
Technical Specification Section 4.0.5 requires inservice testing of American Society of Mechanical Engineers (ASME) Code Classes 1. 2. and 3 lumps and valves in accordance with Section XI of the ASME Boiler and 3ressure Vessel Code and applicable Addenda.
The licensee is committed to inservice testing in accordance with the 1983 Edition of the Code and Summer 1983 Addenda.
Section XI. Subsection IWV-3522 of the ASME Boiler and Pressure Vessel Code requires valves whose function is to prevent reverse flow to be tested in a manner that proves that the disk travels to the seat promptly on cessation or reversal of flow.
Contrary to the above, neither the turbine-driven auxiliary feedwater pump discharge check valve V003 nor check valves V0020. F. and H. were reverse flow tested in a manner that proves that the disk travels to the seat on cessation or reversal of flow.
Either check valve V003 or check valves V0020. f. and H were required to perform a safety function in the closed position.
1 This is a Severity Level IV Violation (Supplement 1).
l C.
10 CFR Part 50. Appendix B. Criterion XI. Test Controls, states, in part, that a test program shall be established to ensure that all testing required to demonstrate structures, systems, and components will 9711260026 971117 gDR ADOCK 05000348 PDR
' s
.e Notice of Violation 2
l perform satisfactory is identified and performed in accordance with written test procedures.
j Technical Specification 6.8.1,a requires that applicable written procedures recommended in Mpendix A of Regulatory Guide 1.33. Revision l
- 2. 1978, shall be established, implemented and maintained. Appendix A.
Section 8.b of Regulatory Guide 1.33 recommends surveillance test procedures for the Auxiliary Feedwater System.
Contrary to the above, as of March 14, 1997, no surveillance test procedures were established for the turbine-driven auxiliary feedwater pump Class 1E battery to ensure that the battery will perform satisfactorily in servict to the required battery duty cycle in accordance with design basis requirements.
This is a Severity Level IV Violation (Supplement 1).
D.
10 CFR Part 50. Appendix B. Criterion V. Instructions. Procedures, and Drawings, states, in part, that activities affecting quality be prescribed by and performed in accordance with instructions, procedures or drawings which include appropriate acceptance criteria for determining the activity is satisfactorily accomplished.
Contrary to the above, as of March 14, 1997, the following were identi fied:
1.
The Unit 2 Turbine Driven Auxiliary Feedwater (TDAFW) pump battery structural and electrical component installations were not installed in accordance with drawings and instructions (7597 E10,9 29. Revision 1. U265645A, Revision 2, and U263212, Revision D).
2.
The surveillance procedure for verifying the forward flow for check valve V003 did not provide appropriate acceptance criteria for determining that the activity was satisfactorily accomplished.
Specifically, the acceptance criterion of 625 gallons per minute (gpm) full desigr. flow specifled for TDAFW pump check valve V003 in ".irveillance Test Procedure (STP) FNP-1(2)-STP 22.13 was incorrect, because the acceptance criterion did not consider the flow through the minimum flow line.
This is a Severity Level IV Violation (Supplement 1).
E.
10 CFR Part 50. Appendix B, Criterion Ill. Design Control, states, in part, that the design control measures shall provide for verifying or checking the adequacy of the design.
I Licensee's Operations Quality Assurance Program UFSAR 17.2.3.1. states that design control measures will comply with the requirements of American National Standard Institute (ANSI) N45.2.ll-1974.
It further 1
states-that the design control system shall include a method of I.
adequately verifying the design.
l l
's j
Notice of Violation 3
Farley Support Procedure GO H 1. " Designer Interface Document." Revision
- 3. states that calculations or analyses )erformed as a part of engineering support activities for FNP s1all conform to the requirements i
of Section 4.2 of ANSI N45.2.11-1974. -In addition, procedure GO H-1 states that existing calculations should be reviewed to determine if the calculation must be revised.
ANSI N45.2.11 states that design analyses shall be performed in a planned. controlled and correct manner, in addition, the design activities shall be prescribed and accomplished in accordance with procedures which provides adequate checking or verifying the results of the activity.
Contrary to the above, on March 14, 1997.
1.
The design control measures did not ensure that calculations or analyses were verified and controlled adequately to ensure original plant design basis documentation is maintained current and to prevent inappropriate use of the existing calculations for the following examples:
a.
Calculation 38.06. " Determine flow rate through pipe break in CCW system." Revision 0, concerning the Component Cooling Water (CCW) surge tank low low level setpoint. supersedes Calculation 35.6. " Evaluation of CCW Surge Tank Level Setpoints." Revision 0. yet Calculation 35.5 was shown as active on the licensee's calculation index.
b.
Calculation 34.5 " Component Cooling Water System NPSH (ES No. 90 1820)." Revision 0, was affected by Calculation 39.3.
e "CCW Surge Tank Analytical Limit for Level Setpoint."
Revision 0, but Calculation 34.5 was not revised accordingly, c.
Calculation 25.3 "Over pressurization of AFW Piping During Overspeed Testing." Revision 0, determined that an unacceptable piping pressure could develop in the event of turbine overspeed of 125% of rated speed.
This calculation was not revised to reflect the acceptable overspeed setpoint of 115% of rated speed nor was a new calculation pre)ared to supersede Calculation 25.3 when design modification )CN B-88-1-5003. " Change Overspeed Trip Setting for TDAFW Pump."
Revision 1 was implemented.
d.
Calculation E-144. " Determination of Battery Capacity Margins for Adecuacy of Voltage at Safety-Related Components for Various Loac Profiles." Revision 2. reflected a new battery instal'.ation but calculation E 42. " Steady-State DG Loading Calculation for LOSP. SI and SBO." Revision 8, wh4ch used calculation E-144 as an input, was not revised accordingly, e.
Calculation 40.02. " Verification of AFW Flow Bases."
Revision 3 (Unit 1), and the equivalent calculation for Unit
Notice of Violation 4
2 (38.04) provide design basis information for the AFW system: yet Calculation 35.04. " Auxiliary feedwater System Head Curves (ES 90-1831)." Revision 0, which provides similar information. was not referenced or revised to indicate that it did not contain design basis information.
f.
Calculation SC-96 1211-002. "CCW Heat Exchanger Maintenance Repairs." Revision 1. states that it is judged that the increase in weight resulting from the CCW heat exchanger modifications will not affect the acceptability of the i
foundation anchorages.
However, the calculation for the anchorages was not revised nor was the increase in heat exchanger weight re'iected in the appropriate calculation.
2.
Design control measures were not 3roperly implemented to verify or check the adequacy of the design ) asis differential pressures specified for CCW motor operated valves (MOVs).
S)ecifically, differential pressures identified in Design Basis Jocument.
U418109. Revision A for CCW system containment isolation valves MOV 3046. 3052. and 3182 were non-conservative as the effect of post Loss of Coolant Accident (LOCA) containment pressure was not considered.
This is a Severity Level IV Violation (Supplement 1).
F.
10 CFR Part 50. Appendix B. Criterion XVI states that conditions adverse to quality such as malfunctions and deviations be promptly identified and corrected.
Contrary to the above. as of March 14, 1997, the licensee failed to s
promptly correct several differences between CCW system piping and instrument drawings D 205002. Sheet 1. Revision 21: Sheet 2. Revision 10: and Sheet 3. Revision 2 and standard operating procedures (SOPS)
FNP 1(2)-SOP-23.0A " Component Cooling Water System." Revision 5. and FNP-2-SOP-2.1A " Chemical and Volume Control System," Revision 8.
concerning the existence of caps on vents and drain lines.
Differences between piping and instrumentation drawings (P&lDs) and procedures were previously identified in the licensee's CCW system self-assessment in 1990, but no corrective action was identified by the licensee.
This is a Severity Level IV Violation (Supplement I).
G.
10 CFR 73.21(d)(2) requires Safeguards Information (SGI) to be stored in a-locked security storage container while unattended.
10 CFR 73.21(e) requires each document that contains SGI to be marked as " Safeguards Information" in a conspicuous manner to indicate the presence of protected information.
Contrary to the above, as of September 17. 1997 SGI was stored in the main control room in an unlocked container that was routinely left unattended for short periods of time.
Furthermore, some of the SGI was bound in nondescript. unmarked folders and was not marked in a conspicuous manner to indicate its presence.
i
4 Notice of Violation 5
This is a Severity Level IV violation (Supplement 111).
Pursuant to the provisions of 10 CFR 2.201. Southern Nuclear Operating Company is hereby required to submit a written statement or ex)lanation to the U.S.
l Nuclear Regulatory Commission ATIN: Document Control )esk, Washington, DC 20555, with a copy to the Regional Administrator, Region 11, and a copy to the NRC Resident inspector, Farley Nuclear Plant, 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 A through F:
(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 incluue previously docketea correspondence, if the correspondence adequately 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 why such other action as may be proper should not be taken. Where good cause ir, shown. consideration will be given to extending the response time.
The NRC has concluded that information regarding the reason for Violation G, the corrective actions taken and planned to correct the violation and prevent recurrence is already adequately addressed on the docket in the attached inspection report.
Therefore, you are not required to respond to this violation unless the description therein does not accurately reflect your corrective actions or your position.
In that case or if you choose to provide additional information. you should follow the instructions specified in the enclosed Notice.
Because your res)onse will be placed in the NRC Public Document Room (PDR), to the extent possiale, it should not include any personal privacy, )roprietary, or safeguards information so that it can be placed in the PDR wit 1out 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 Atlanta, Georgia this 17th day of November 1997
.