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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20199D6161999-01-0404 January 1999 Notice of Violation from Insp on 981025-1205.Violation Noted:Its Requirements for Valve Position Verifications Not Met as Evidenced by Listed Examples ML20249A2941998-06-0808 June 1998 Notice of Violation from Insp on 980322-0509.Violation Noted:As of 980423,licensee Had Not Complied W/Requirements of Procedure CP-111,in That,Only Two of Discrepancies Identified in Ioc NL97-0262,had Been Documented ML20216H8871998-04-0808 April 1998 Notice of Violation from Insp on 980208-0321.Violation Noted:On 980220,Axial Power Imbalance Alarm Was Inoperable for Approx 3.5 Hours & Axial Power Imbalance Was Not Verified to Be within Acceptable Operating Limits ML20248L6171998-03-16016 March 1998 Notice of Violations from Insp on 980126-30.Violations Noted:Test Program for ECCS Operating in Piggyback Mode Did Not Demonstrate That Sys Would Perform Satisfactorily in Service ML20216E9291998-03-0404 March 1998 Notice of Violation from Insp on 980104-0207.Violations Noted:On 980203 Licensee Failed to Accomplish Required Posting of Bulletin Boards ML20203F5561998-02-23023 February 1998 Notice of Violation from Insp on 971021-24,1208-12 & 980105-09.Violations Noted:Implementation of Validation Program Did Not Adequately Demonstrate Usability of Emergency Procedures ML20199G6761998-01-16016 January 1998 Notice of Violation from Insp on 971201-16.Violation Noted: as of 971211,licensee Health Physics Supervisors Failed to Identify & Correct Personnel Contamination Repts That Were Not Completed IAW Requirements of Procedure HPP-104 ML20198N6211997-12-29029 December 1997 Notice of Violation from Insp on 971026-1129.Violation Noted:On 971105,licensee Failed to Perform Adequate Se,Per 10CFR50.59 for Functional Test Procedure for B Emergency Diesel Generator Power Upgrade & Radiator Replacement Mods ML20203A1911997-12-0404 December 1997 Notice of Violation from Insp on 971006-24.Violation Noted:Work Request Numbers 333797 & 333798,issued in Mar 1997 to Install Stem Protectors on Actuators Were Closed W/O Performing Work ML20202D7301997-11-24024 November 1997 Notice of Violation from Insp on 970921-1025.Violation noted:10CFR50.59 SE Had Not Been Performed as Required within 90 Days on Wds Piping non-conforming Condition ML20212B9061997-10-16016 October 1997 Notice of Violation from Insp on 970817-0920.Violations Noted:Scaffolding Control Program Does Not Contain Measures to Assure That Deviations from Design Quality Std for safety-related Equipment Installed Have Adequate Control ML20211Q2581997-10-14014 October 1997 Notice of Violation from Insp on 970922-26.Violation Noted:On 970820,individual Was Terminated & Authorized Access Was Not Removed from Plant Security Computer Until 970905 ML20211E4891997-09-12012 September 1997 Notice of Violation from Insp on 970713-0816.Violations Noted:On 970728,licensee Personnel Performed quality-related Work to Restore once-through SGs During Reduced RCS Inventory Operation Without Written & Approved Procedure ML20210V5241997-09-0505 September 1997 NOV from Insp on 970602-20.Violation Noted:Licensee Made Change to Facility,W/O Prior Commission Approval,That Involved USQ ML20216E3961997-09-0505 September 1997 Errata to NOV from Insp on 970804-06.Violation Noted: Licensee Failed to Have Adequate Assessment of 10 Zones to Facilitate Response to Detection of Penetration of Protected Area Perimeter & Assessment of Existence of Threat ML20210R9221997-08-27027 August 1997 Notice of Violation from Insp on 970804-06.Violation Noted: Licensee Failed to Have Adequate Assessment of 10 Zones to Facilitate Response to Detection of Penetration of Protected Area Perimeter & Assessment of Existence of Threat ML20210M5681997-08-11011 August 1997 Notice of Violation from Insp on 970608-0712.Violation Noted:Licensee CAs for NRC NOV EA 97-094 Inadequate in That Rev 1 of Procedure CP-151 Inadequate to Prevent Repetition of Violation ML20149G1061997-07-0707 July 1997 Notice of Violation from Insp on 970504-0607.Violation Noted:Security Staff Failed to Understand Adequately & Develop Guidance Properly to Address Multiple Temporary Losses of Power to Central Alarm Station Computers ML20148P8991997-06-0606 June 1997 Notice of Violation from Insp on 970127-0321.Violation Noted:Licensee Failed to Report Condition That Was Outside Design Basis of Plant,Unanalyzed Condition That Compromised Plant Safety & Vulnerability in Safeguard Sys ML20140E7741997-06-0505 June 1997 Notice of Violation from Insp on 970319-21.Violation Noted:Licensee Made Changes to Facility & Procedures Described in FSAR That Involved USQs Based on Inadequate SE ML20140D2681997-06-0202 June 1997 Notice of Violation from Insp on 970330-0503.Violation Noted:On 970327,red Tags from Released Electronic Clearance Order (Eco) 96-012-98 Found on 4160 Volt Breaker Cubicles for a & B Makeup Pumps ML20140F0461997-05-29029 May 1997 Notice of Violation from Insp on 970317-21.Violation Noted: on 970116,outdated Physical Security & Training & Qualification Plans & 1990 Safeguards Info Insp Repts & LERs Were Left Unattended & Not Locked in Secured Area ML20138J4041997-04-21021 April 1997 Notice of Violation from Insp on 970223-0329.Violation Noted:Licensee Failed to Accomplish Activities Affecting Quality in Accordance W/Procedures to Control Equipment for Normal Operating Conditions ML20140E7411997-04-18018 April 1997 Notice of Violation from Insp on 970317-21.Violation Noted: on 960209,licensee,through Deliberate Action of Three Individuals,Allowed Badge/Key to Leave Protected Area W/O Being Under Observation & Control of Security Force ML20148F9791997-04-0404 April 1997 Notice of Violation from Insp on 960729-0802.Violation Noted:R Stewart Deliberately Failed to Provide Complete & Accurate Info During Preemployment Process & Include History of Criminal Convictions on Personal History Questionnaire ML20137T0311997-03-24024 March 1997 Notice of Violation from Insp on 970112-0222.Violations Noted:Licensee Failed to Prescribe Quality Related Clearance Tagging Activities Into Appropriate Procedure That Compliance Procedure 115 Nuclear Plant Tags ML20137E5291997-03-12012 March 1997 Notice of Violation from Insp on 961206.Violation Noted: in April 96 Licensee Made Change to Facility Described in Fsar,Which Involved Three USQ W/O Prior Commission Approval ML20137E4441997-02-28028 February 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Noted:Procedures Were Not Implemented & Maintained to Detailed Requirements Necessary to Implement Security Plan for Plant Operations ML20135C7071997-02-21021 February 1997 Notice of Violation from Insp on 960805-09.Violation Noted: Fuel Handling Event Involving Fuel Assembly N8C6 Was Not Recorded in Operating Logs or Refueling Log & Main Fuel Handling Bridge Was Not Verified for Indexing ML20134P3951997-02-0505 February 1997 Notice of Violation from Insp on 961201-970111.Violations Noted:Rcs Cooldown Rate Allowed to Exceed Limits Specified in PTLR for Approximately One Hour,During Unit Cooldown ML20132C7991996-12-0505 December 1996 Notice of Violation from DOL Recommended Decision & Order, & Investigation by NRC OI Completed on 960924. Violation Noted:Licensee Discriminated Against Ta James, Former Security Escort & Firewatch ML20135C3921996-11-27027 November 1996 Notice of Violations from Insp on 961006-1102.Violations Noted:No Licensee Sp Included Channel Check for Motor Driven Emergency Feedwater Pump Discharge Pressure Gauge ML20129H7261996-10-30030 October 1996 Notice of Violation from Insp on 960908-1005.Violation Noted:Failure of Clearance for Work Request Nu 0337713 to Require Tripping Fuel Racks Prior to Opening Air Supply Isolation Valve Resulted in Inadvertent Start of Generator ML20129A1561996-10-0404 October 1996 Notice of Violation from Insp on 960811-0907.Violation Noted:Technician Failed to Follow Requirements of PT-366, Resulting in Inadvertent Initiation of Control Room Emergency Ventilation Sys & Escort Lost Contact W/Visitor ML20134C3091996-09-12012 September 1996 Notice of Violation from Insp on 960714-0810.Violation Noted:Failure to Take Prompt Corrective Actions to Address Discrepancies Identified in Feb 1995 During make-up Sys Audit ML20149J2031994-02-16016 February 1994 Notice of Violation from Insp on 930825.Violation Noted: DA Tritt Discharged from Employment on 871203,for Engaging in Protected Activities (88-ERA-29) ML20059C0791993-12-10010 December 1993 Notice of Violation from Insp on 931108-12.Violations Noted: Surveillance Procedure SP-182,rev 10, Reactor Bldg Structural Integrity Surveillance Program Not Implemented as Described ML20058P6781993-12-0303 December 1993 Notice of Violation from Insp on 931101-19.Violation Noted: Facility Licensee Physician Made Determination That Two Operators Eyesight No Longer Met Min Stds Required by 10CFR55.33(a)(1) ML20057B4201993-09-10010 September 1993 Notice of Violation from Insp on 930628-0730.Violation Noted:Design Control Measures Had Not Assured Design Bases Were Properly Translated Into Min Terminal Voltage Specified by Battery Svc Test Surveillance Procedure SP-523,Rev 28 ML20057C3231993-09-0909 September 1993 Notice of Violation from Insp on 930711-0814.Violation Noted:Measure Did Not Assure Corrective Actions Preclude Repetition of Reactor Coolant Sys Overcooling Event of 930305 ML20056E9861993-08-0909 August 1993 Notice of Violation from Insp on 930606-0710.Violation Noted:Mut Hydrogen Regulator Adjusted W/O Required Safety Evaluation Being Performed ML20126F1881992-12-11011 December 1992 Notice of Violation from Insp on 921018-1114.Violation Noted:Dg Inoperable for Two H During Performance of Surveillance procedure,SP-907B.Required Breaker Alignment & Power Availability Verifications Not Performed ML20062D9451990-11-0707 November 1990 Notice of Violation from Insp on 900918-1005.Violation Noted:On 900918,containment Integrity for Unit Not Maintained While in Mode 1 in That Valve Dhv 43 Did Not Fully Shut After Performing Cycling & Disabling Evolution ML20059G6001990-08-31031 August 1990 Notice of Violation from Insp on 900707-0810.Violation Noted:Valve Realignment Sequence Violated in That Air Dryer Bypass Valve Closed First Instead of Last While Releasing Work Request 90-07-036 ML20247Q1791989-09-13013 September 1989 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Noncompliance noted:safety-related Motor Control Ctrs in Auxiliary Bldg Had Not Been Demonstrated to Be Qualified for Environ Conditions ML20246Q3321989-09-0101 September 1989 Notice of Violation from Insp on 890708-0804.Violations Noted:Channel Functional Test Not Performed on Containment Hydrogen Monitors & Six Manual Valves Associated W/Emergency Containment Not Verified Closed Every 31 Days ML20246N7571989-08-21021 August 1989 Notice of Violation from Insp on 890710-14.Violations Noted: Verification of Remote Position Indicators at Remote Shut Down Panel Not Being Performed & Record of Results for Relief Valve BSV-19 Vacuum Function Testing Did Not Exist ML20245K2891989-08-11011 August 1989 Notice of Violation from Insp on 890619 & 20.Violation Noted:No Surveillance Procedure Written or Implemented to Test Automatic Start Logic Paths for motor-operated Emergency Feedwater Pump ML20245K0331989-08-0101 August 1989 Notice of Violation from Insp on 890603-0707.Violation Noted:On 890621,several Cells of Station Batteries a & B Had Electrolyte Levels Greater than Max Level Mark & Four Unqualified Personnel Assigned Duty on Fire Brigade ML20246K7251989-07-0707 July 1989 Notice of Violation from Insp on 890531-0602.Violations Noted:Operator Failed to Have Procedures Present for Performing Actions Not Routine & Rev 80 to General Plant Operating Procedure OP-02 Re Plant Heatup Inadequate 1999-01-04
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000302/19990051999-09-13013 September 1999 Insp Rept 50-302/99-05 on 990704-0814.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000302/19990041999-07-27027 July 1999 Insp Rept 50-302/99-04 on 990523-0703.Noncited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19990031999-06-0404 June 1999 Insp Rept 50-302/99-03 on 990411-0522.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Maint, Operations,Engineering & Plant Support IR 05000302/19990021999-05-0606 May 1999 Insp Rept 50-302/99-02 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Engineering, Maintenance & Plant Support IR 05000302/19990011999-03-29029 March 1999 Insp Rept 50-302/99-01 on 990117-0227.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000302/19980101999-01-0404 January 1999 Insp Rept 50-302/98-10 on 981025-1205.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Insp Also Included Results of Physical Security Specialist ML20199D6161999-01-0404 January 1999 Notice of Violation from Insp on 981025-1205.Violation Noted:Its Requirements for Valve Position Verifications Not Met as Evidenced by Listed Examples IR 05000302/19980131998-12-16016 December 1998 Insp Rept 50-302/98-13 on 981116-20.No Violations Noted. Major Areas Inspected:Area of Plant Support by Regional Safeguards Specialist.Physical Security Program Was Evaluated IR 05000302/19980121998-12-0101 December 1998 Insp Rept 50-302/98-12 on 981013-16.No Violations Noted. Major Areas Inspected:Observation & Evaluation of Biennial EP Exercise for Crystal River Unit 3 IR 05000302/19980091998-11-13013 November 1998 Insp Rept 50-302/98-09 on 980913-1024.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19980081998-10-0606 October 1998 Insp Rept 50-302/98-08 on 980802-0912.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering, Maint & Plant Support IR 05000302/19980071998-08-31031 August 1998 Insp Rept 50-302/98-07 on 980621-0801.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19983011998-07-31031 July 1998 NRC Operator Licensing Exam Rept 50-302/98-301,including Completed & Graded Tests,For Tests Administered on 980629-0702 IR 05000302/19980061998-07-20020 July 1998 Insp Rept 50-302/98-06 on 980510-0620.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000302/19980041998-06-0808 June 1998 Insp Rept 50-302/98-04 on 980322-0509.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20249A2941998-06-0808 June 1998 Notice of Violation from Insp on 980322-0509.Violation Noted:As of 980423,licensee Had Not Complied W/Requirements of Procedure CP-111,in That,Only Two of Discrepancies Identified in Ioc NL97-0262,had Been Documented IR 05000302/19980991998-06-0404 June 1998 SALP Rept 50-302/98-99 for 961006-980509 ML20216H8941998-04-0808 April 1998 Insp Rept 50-302/98-03 on 980208-0321.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20216H8871998-04-0808 April 1998 Notice of Violation from Insp on 980208-0321.Violation Noted:On 980220,Axial Power Imbalance Alarm Was Inoperable for Approx 3.5 Hours & Axial Power Imbalance Was Not Verified to Be within Acceptable Operating Limits ML20248L6171998-03-16016 March 1998 Notice of Violations from Insp on 980126-30.Violations Noted:Test Program for ECCS Operating in Piggyback Mode Did Not Demonstrate That Sys Would Perform Satisfactorily in Service IR 05000302/19980021998-03-13013 March 1998 Insp Rept 50-302/98-02 on 980126-30.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering.Emergency Operating Procedures Were Also Reviewed ML20216E9611998-03-0404 March 1998 Insp Rept 50-302/98-01 on 980104-0207.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20216E9291998-03-0404 March 1998 Notice of Violation from Insp on 980104-0207.Violations Noted:On 980203 Licensee Failed to Accomplish Required Posting of Bulletin Boards ML20203F5561998-02-23023 February 1998 Notice of Violation from Insp on 971021-24,1208-12 & 980105-09.Violations Noted:Implementation of Validation Program Did Not Adequately Demonstrate Usability of Emergency Procedures ML20203F5631998-02-23023 February 1998 Insp Repts 50-302/97-12 on 971020-24,1208-12 & 980105-09. Violations Noted.Major Areas Inspected:Adequacy of EOPs Development Process PNO-II-98-005, on 980201,plant Commenced Reactor Startup & Entered Mode 2 Conditions (Keff 0.99).On 980202,criticality Was Achieved,Followed by Mode 1 Conditions.Unit Scheduled to Be at 100% Power Late 9802051998-02-0202 February 1998 PNO-II-98-005:on 980201,plant Commenced Reactor Startup & Entered Mode 2 Conditions (Keff 0.99).On 980202,criticality Was Achieved,Followed by Mode 1 Conditions.Unit Scheduled to Be at 100% Power Late 980205 PNO-II-98-004, on 980130,Region II Administrator Informed FPC That NRC Was Satisfied W/Completion of FPC Actions Specified in Cal, & Concurred That Plant,Unit 3 Could Operate IAW License1998-01-30030 January 1998 PNO-II-98-004:on 980130,Region II Administrator Informed FPC That NRC Was Satisfied W/Completion of FPC Actions Specified in Cal, & Concurred That Plant,Unit 3 Could Operate IAW License IR 05000302/19970191998-01-29029 January 1998 Insp Rept 50-302/97-19 on 971130-980103.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-II-98-003, on 980120,licensee Placed Two Reactor Coolant Pumps in Operation to Add Heat to Rcs.Licensee Has Not Yet Requested Release from Cal.Licensee Issued Press Release1998-01-22022 January 1998 PNO-II-98-003:on 980120,licensee Placed Two Reactor Coolant Pumps in Operation to Add Heat to Rcs.Licensee Has Not Yet Requested Release from Cal.Licensee Issued Press Release ML20199G6761998-01-16016 January 1998 Notice of Violation from Insp on 971201-16.Violation Noted: as of 971211,licensee Health Physics Supervisors Failed to Identify & Correct Personnel Contamination Repts That Were Not Completed IAW Requirements of Procedure HPP-104 ML20199G6861998-01-16016 January 1998 Insp Rept 50-302/97-20 on 971201-16.Violations Noted.Major Areas Inspected:Operations,Radiological Protection,Maint & Surveillance Programs IR 05000302/19972011998-01-0909 January 1998 Insp Rept 50-302/97-201 on 970929-1003.No Violations Noted. Major Areas Inspected:Review of Selected Conditions & Records Since Last Insp,Verification of CAs Previously Committed by Licensee & Related Discussion W/Personnel IR 05000302/19970181998-01-0606 January 1998 Insp Rept 50-302/97-18 on 971117-21 & 1201-12.No Violations Noted.Major Areas Inspected:Plant Support ML20198N6271997-12-29029 December 1997 Insp Rept 50-302/97-19 on 971026-1129.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20198N6211997-12-29029 December 1997 Notice of Violation from Insp on 971026-1129.Violation Noted:On 971105,licensee Failed to Perform Adequate Se,Per 10CFR50.59 for Functional Test Procedure for B Emergency Diesel Generator Power Upgrade & Radiator Replacement Mods ML20198P2251997-12-29029 December 1997 Insp Rept 50-302/97-21 on 971203.Violations Noted.Major Areas Inspected:Noncompliances in Design control,10CFR50.59, Procedural Adequacy,Reportability & Corrective Actions.No Notice of Violation Being Issued in This Case ML20199A2091997-12-22022 December 1997 EN-97-116:on 971229,informs Commission That Staff Intends to Exercise Enforcement Discretion in Accordance W/Section VII.B.2 of Enforcement Policy & Not Issue NOV or Proposed Imposition of Civil Penalty to Util for Violations PNO-II-97-063, on 971218,Crystal River Unit 3 Achieved Significant Milestone by Declaring a EDG Operable & Thus Making Both EDGs Operable for Mode 5.Licensee Does Not Plan to Issue Press Release.State of Fl Notified1997-12-19019 December 1997 PNO-II-97-063:on 971218,Crystal River Unit 3 Achieved Significant Milestone by Declaring a EDG Operable & Thus Making Both EDGs Operable for Mode 5.Licensee Does Not Plan to Issue Press Release.State of Fl Notified IR 05000302/19973011997-12-17017 December 1997 NRC Operator Licensing Exam Rept 50-302/97-301 Including Completed & Graded Test for Test Administered on 971118. Exam Results:Sro Candidate Passed Written Exam ML20203A1911997-12-0404 December 1997 Notice of Violation from Insp on 971006-24.Violation Noted:Work Request Numbers 333797 & 333798,issued in Mar 1997 to Install Stem Protectors on Actuators Were Closed W/O Performing Work ML20203A2061997-12-0404 December 1997 Insp Rept 50-302/97-14 on 971006-24.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML20202D7301997-11-24024 November 1997 Notice of Violation from Insp on 970921-1025.Violation noted:10CFR50.59 SE Had Not Been Performed as Required within 90 Days on Wds Piping non-conforming Condition IR 05000302/19970161997-11-24024 November 1997 Insp Rept 50-302/97-16 on 970921-1025.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-II-97-059, on 971118,established Vacuum in Main Condenser & Steam Bubble in Pressurizer.Completed Work on Planned Upgrades for B Edg.Resident & regional-based Inspectors Are Closely Monitoring Subject Activities1997-11-18018 November 1997 PNO-II-97-059:on 971118,established Vacuum in Main Condenser & Steam Bubble in Pressurizer.Completed Work on Planned Upgrades for B Edg.Resident & regional-based Inspectors Are Closely Monitoring Subject Activities ML20212B9061997-10-16016 October 1997 Notice of Violation from Insp on 970817-0920.Violations Noted:Scaffolding Control Program Does Not Contain Measures to Assure That Deviations from Design Quality Std for safety-related Equipment Installed Have Adequate Control IR 05000302/19970131997-10-16016 October 1997 Insp Rept 50-302/97-13 on 970817-0920.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19970151997-10-14014 October 1997 Partially Withheld Insp Rept 50-302/97-15 on 970922-26 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support by Regional Safeguards Inspector ML20211Q2581997-10-14014 October 1997 Notice of Violation from Insp on 970922-26.Violation Noted:On 970820,individual Was Terminated & Authorized Access Was Not Removed from Plant Security Computer Until 970905 ML20211E4891997-09-12012 September 1997 Notice of Violation from Insp on 970713-0816.Violations Noted:On 970728,licensee Personnel Performed quality-related Work to Restore once-through SGs During Reduced RCS Inventory Operation Without Written & Approved Procedure ML20211E5791997-09-12012 September 1997 Insp Rept 50-302/97-11 on 970713-0816.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support 1999-09-13
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NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. DPR-72 During an NRC inspection conducted-on January 26 through 30. 1998. violations .;
of NRC requirements were identified. 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, Appendix B. Criterion XVI, Corrective Action, requires that .
measures be established to assure conditions adverse to quality be j 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 corrective action taken to preclude repetition.
-Contrary to the above.
- 1. As of January 11, 1998, corrective actions for a significant condition adverse to quality regarding errors in procedures used for in-plant E0P actions were not adequate to. preclude repetitive errors in procedures used for in-plant E0P' actions such as Abnormal Procedure AP-770. Emergency Diesel Generator Actuation, and Abnormal Procedure AP-470. Loss of Instrument Air.
- 2. As of January 26, 1998. corrective actions for a condition adverse to quality regarding not performing radiological mission doses for personnel installing flow elements to accomplish reactor.
building purging for post-accident hydrogen concentration control were inadequate in that:
(a) The radiological mission dose evaluation did not account for the radiological dose from the loading of the Auxiliary Building ventilation filter banks. ,
(b) The radiological mission dose evaluation did not account for the radioactive loading from a 50 gpm Residual Heat Removal (RHR) pump seal leak on the loading of the- Auxiliary Buildings filters.
(c) The time validation inputting into the mission dose evaluation'used a non-conservative time for two people carrying a cart with approximately 50 pounds of equipment on it up the stairs to the Auxiliary Building location.
l This is a Severity Level IV Violation (Supplement I). !
B. 10 CFR 50. Appendix B. Criterion XI. Test Control, requires in part that I a test program be established to assure that all testing required to demonstrate that structures, systems, and com)onents will perform ;
satisfactorily in service which incorporate t1e requirements and !
Enclosure 1 9903230283 980316 PDR ADOCK 05000302 :
G PDR
_____ - _ _ ___ _ __ _ _ __ _ _ _____ _ _ _ ___- __ _ -_ _ _-__--___ - _ ___ a
2 acceptance limits contained in applicable design documents. The test program shall. include operational tests.
Updated Final Safety Analysis-Report. Section 14.2.2.5.4. Emergency Core Cooling System (ECCS) Qualification, states in part. "In order to qualify the ECCS. the NRC placed requirements on the ECCS to ensure that '
.the health and well being of the public is not impacted. These requirements are specified in 10 CFR 50.46 and 10 CFR 50. Appendix K.
The criteria contained in Part 50.46 are applicable to all sizes of LOCAs and are necessary in order to verify adherence. These criteria are as follows ... A path to long-term cooling must be established."
This section further states that BAW-10104. Rev. 3. is the methods report on how the computer model used to ensure compliance with 10 CFR 50.46 is assembled and run. Section 14.2.2.5.4 further states "The LBLOCA application report for the 177 FA lowered loop plants is BAW-10103A.,
Topical Report BAW-10103A. Rev. 3. "ECCS Analysis of B&W 177-Fuel Assembly Lowered-Loop NSSS." and Topical Report BAW-10104. Rev. 3. "ECCS Analysis Of B&W's 177-FA Lowered-Loop NSS." Chapter 10. Long-Term Cooling. Section 10.2 states in aart that several alternate modes of operation of the ECC systems can )e used during long-term cooling, if necessary, while maintenance is being performed on normal equipment and one of these modes is: "One LPI pump operating with injection through-its associated injection line and with the crossover to the associated HPI string open: the associated HPI pump would be pumping through its HPI lines."
Contrary to the above, as of January 26, 1998, the test program for the emergency core cooling system operating in the piggyback mode did not demonstrate that the system would perform satisfactorily in service.
This is a Severity Level IV Violation (Supplement I).
C. 10 CFR 50. Appendix B. Criterion II. Quality Assurance Program, requires l that a quality assurance program be established. This program shall be documented by written policies, procedures or instructions and carried out in accordance with those documents.
l The Quality Assurance Program as described in the Updated Safety Analysis Report lists ANSI 45.2.11. 1974 " Quality Assurance Requirements for the Design of Nuclear Power Plants." under the committed standards.
ANSI 45.2.11. Section 3. Design Input Requirements. Subsection 3.2. :
Requirements. states that the design input shall include but shall not i be limited to instrumentation and control requirements including type of instrument, range of measurement, and location of indications. !
l Enclosure 1 l l
I
3 ANSI 45.2.11..Section 4. Design Process, Subsection 4.1. General, states in part that design activities shall be prescribed and accomplished in accordance with procedures of a type sufficient to assure that ap]licable design inputs were correctly translated into procedures Su)section 4.5. Other Design Documents, states, in part, that procedures shall be established for the preparation and control of test procedures.
Contrary to the above, as of January 26, 1997, the quality assurance program as documented by written policies, procedures or instructions was not carried out in accordance with those documents in that:
- 1. The design input for Calculation I-90-0023. Reactor Building Hydrogen Concentration Loop Accuracy Calculation. Revision 1.
dated November 19, 1997, did not adequately include the instrumentation and control requirements of instrument uncertainty affecting the post-accident time duration before initiating reactor building purge for hydrogen concentration control.
- 2. The design input for Calculation I-90-0013. Post Accident RB Hydrogen Purge Instrument Accuracy. Revision 2. dated December 29.
1994, did not adequately include the instrumentation and control requirements of instrument location affecting the accuracy of the reactor building purge flow rate indication used for post-accident hydrogen concentration control.
- 3. The design activity of controlling test procedures was not adequately accomplished such that the stroke time acceptance criteria of the applicable surveillance procedures for valves DHV-42 and 43 was less conservative than that indicated in Calculation M-97-0120. Stoke Time for DHV-42/43 for Boron Precipitation. Rev.
- 1. dated November 1. 1997.
This is a Severity Level IV Violation (Supplement I).
D. 10 CFR 50. Appendix B. Criterion V. Instructions. Procedures and Drawings, requires, in part, that activities affecting quality be prescribed by documented procedures.
Contrary to the above, as of January 26, 1998 an activity affecting quality was not adequately prescribed by documented procedures in that step 1.6 of Emergency Plan Procedure. EM-225A. Post Accident Reactor Building Hydrogen Control, directing installation of the flow elements to be used for purging the reactor building to maintain post-accident hydrogen concentrations, did not include flanged connection torquing information from the vendor manual or direction to plug the flow instrument's power cord into the receptacle.
This is a Severity Level IV Violation (Supplement I).
1 Pursuant to the provisions of 10 CFR 2.201. Florida Pcwer Corporation is i Enclosure 1
4 l 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 Crystal River Unit 3-facility, within 30' days of j 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 l 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 com)liance will be achieved. Your response may reference or include previous I docceted correspondence.e 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 is i shown, consideration will be given to extending the response time. '
Because your res)onse will be placed in the NRC Public Document Room (PDR). to 4 the extent possi)le. it should not include any personal privacy. 3roprietary, or safeguards information so that it can be placed in the PDR witlout i redaction. If personal privacy or proprietary information is necessary to l 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 material you must s)ecifically identify the portions of your response that you seek to have with1 eld and provide in detail the bases 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 l
. protection described in 10 CFR 73.21.
Dated at Atlanta Georgia this 16th day of March 1998 ,
Enclosure 1