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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML17326A1671999-09-22022 September 1999 Notice of Violation from Insp on 990717-0825.Violation Noted:On 990521,licensee Performed Surveillance Test on Unit 2 East Residual Heat Removal Train Using Component Cooling Water Sys Without Having Performed Full SE ML20154L9861998-10-13013 October 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $500,000.Violation Noted:As of 980227,licensee Had Not Provided Instructions Appropriate to Circumstances for Activity Affecting Quality ML17334B8021998-06-30030 June 1998 Notice of Violation from Insp on 980428-0611.Violation Noted:On 980505,licensee Identified That Measures Taken to Correct Significant Condition Adverse to Quality,Failure to Properly Vent Primary Sys Were Not Effective ML17334A7151998-05-28028 May 1998 Notice of Violation from Insp on 980313-0427.Violation Noted:On 980424,inspectors Determined That in March 1997, Contract Workers Failed to Properly Implement Maintenance Procedure for safety-related Equipment ML17334B7491998-04-21021 April 1998 Notice of Violation from Insp on 980209-13.Violations Noted: on 980126,licensee Offered Radioactive Matl Consisting of Two Packages Labeled as Surface Contaminated Objects to Carrier for Transport & Did Not Include Description of Matl IR 07100108/20120271998-01-23023 January 1998 Notice of Violation from Insp on 971108-1227.Violation Noted:On 971116,inspector Identified Failure to Maintain Records Which Contained Written Safety Evaluation for Three Control Room Annunciators ML17334A6211998-01-13013 January 1998 Notice of Violation from Insp on 970926-1107.Violation Noted:Inspectors Identified That Emergency Operating Procedure E-O,01(02)-OHP 4023.E-o,rev 14,was Not Appropriate to Circumstances ML17333B0151997-07-15015 July 1997 Notice of Violation from Insp on 970505-23.Violation Noted: on 970510,inspectors Identified That Safety Related Temporary Mod 1-95-1,which Did Not Require Outage for Restoration,Assigned Administrative Date 960827 ML17334B6351997-05-30030 May 1997 Notice of Violation from Insp on 970210-0314.Violation Noted:Two Procedures Involving Complex Jobs Where Reliance on Memory Cannot Be Trusted & Sequences Cannot Be Altered Were Not Designated as In-Hand Procedures ML17333A8361997-03-27027 March 1997 Notice of Violation from Insp on 970105-0215.Violation Noted:Inspectors Identified That on 970128,licensee Personnel Performed New Fuel Unloading Work for Unit 1 W/O Using Listed Procedure ML17333A7691997-02-0404 February 1997 Notice of Violation from Insp on 961118-1213.Violation Noted:Inspectors Identified That Maint Work Package for 1E Centrifugal Charging Pump Failed to Include Adequate Instructions for Lube Oil Sample Collection ML17333A7481997-01-22022 January 1997 Notice of Violation from Insp on 961013-1123.Violation Noted:Licensee Failed to Include in Written Safety Evaluation for Design Change Package 56 Adequate Bases for Determination That Change to New Models of Isolation ML17333A5841996-09-27027 September 1996 Notice of Violation from Insp on 960805-29.Violation Noted:Test Program Did Not Demonstrate That CCS Performance Satisfactory as Listed in UFSAR Table 9.5-2 ML17333A4581996-05-16016 May 1996 Notice of Violation from Insp on 960227-0408.Violation Noted:On 960322,licensee Utilized Temporary Change Process & Did Not Perform Safety Review Prior to Issuing Listed Changes to Procedures Which Changed Intent of Procedure IR 05000315/20070301996-03-11011 March 1996 Notice of Violation from Insp on 951220-960116.Violation Noted:On 950315-0730,while in Modes 1,2 & 3,Unit 1 West (Train B) Centrifugal Charging Pump Inoperable ML17333A3041996-02-0808 February 1996 Notice of Violation from Insp on 951205-960116.Violation Noted:Ts Surveillances Were Not Accomplished Under Suitably Controlled Conditions ML17333A2181995-12-0808 December 1995 Notice of Violation from Insp on 950919.Violation Noted: on 950816,licensee Failed to Review Fitness for Duty pre-access Test Results to Ensure That Negative pre-access Test Result Had Been Received for Individual IR 05000620/20080171995-09-12012 September 1995 Notice of Violation from Insp on 950620-0817.Violation Noted:Operators Failed to Reduce Power During Loss of Main Turbine Condenser Vacuum Transient ML17332A8181995-06-28028 June 1995 Notice of Violation Based on Results of Investigation & Administrative Hearings Re DOL Case 89-ERA-022.Violation Noted:Hydro Nuclear Svcs Requested Technician Sign Form Which Would Waive Rights Under ERA ML17332A7351995-04-0505 April 1995 Notice of Violation from Insp on 950131-0320.Violation Noted:Calculations & Work Procedures Did Not Specify That Minimum Effective Thread Length of .41 Inches Had to Be Attained for Installation of 3/8-inch Shutoff Adapters ML17332A7061995-02-28028 February 1995 Notice of Violation from Insp on 941208-950104.Violation Noted:Util Failed to Base Decision for Continued Access Authorization on Review & Evaluation of All Pertinent Info Developed Resulting in Individual Who Retained Access ML17332A3111994-09-21021 September 1994 Notice of Violation from Insp on 940702-0812.Violation Noted:During 1993,25 Operators Incorrectly Initialed Tour Datasheet Indicating That Tour of Associated Area Performed When Tour Had Not Been Performed ML17332A2251994-07-20020 July 1994 Notice of Violation from Insp on 940604-0701.Violation Noted:Licensee Failed to Replace Pitted Valve Stem on MSSV Dump Valve Test selector,2-MMO-240,significant Condition Adverse to Quality ML17332A1981994-06-27027 June 1994 Notice of Violation from Insp on 940423-0603.Violation Noted:Review Process Completed 930625 Did Not Evaluate & Document Basis for Acceptance of Test When Max Thrust Requirements Were Exceeded & Test Requirements Were Not Met ML17331B4351994-06-15015 June 1994 Notice of Violation from Insp on 940601-08.Violation Noted: Inspector Observed Grinding,Welding & Cutting Activities in Turbine Building That Did Not Have Combustibles Removed or Covered within 35 Feet of Activities ML17331B4061994-05-27027 May 1994 Notice of Violation from Insp on 940411-22.Violations Noted:Ccw HX Outlet Water Temp Exceeded TS Limits on 940127 W/O Required Evaluation to Determine If Unreviewed Safety Question Existed ML20029E8461994-05-12012 May 1994 Notice of Violation from Insp on 940404-22.Violation Noted: License Procedure 1&2OHP4030STP.022CS,Rev 2, Essential Svc Water Cold Shutdown Test, Was Not Appropriate to Circumstances ML17331B3321994-04-0606 April 1994 Notice of Violation from Insp on 940118-0308.Violation Noted:On 940221,maint Work on Main Steam Stop Valve Dump Valve 2MRV-241 Not Performed,Per Procedure 12IHP6030.IMP.030,Rev 5 ML17331B3431994-04-0101 April 1994 Notice of Violation from Insp on 940216-0321.Violation Noted:Attachment 2,rev 15,CS-4, RCS Drain to One to Two Feet Below Reactor Vessel Flange W/Fuel in Core, Inappropriate to Circumstances ML17331B0911993-11-24024 November 1993 Notice of Violation from Insp on 930817-0928.Violation Noted:Rwst Instrumentation Loop Setpoint Calculation 1-2-I9-03,dtd 930825 Erroneously Derived Setpoint Uncertainty Value Based on Use of Model N-E13 Transmitters ML17331A9871993-09-30030 September 1993 Notice of Violation from Insp on 930728-0910.Violation Noted:Attachment 10 of Licensee Procedure Ohp 4050.FHP.004, Rev 1 Did Not Include Insp sign-offs for Verifying Tightening of Fasteners for Pressure Boundary Components ML17334B4541993-02-0808 February 1993 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $37,500.Noncompliance Noted:On or About 920910, AB EDG Became Inoperable with Unit in Modes 3 & 4,EDG Was Not Restored to Operable Status within 72 H ML17329A0701991-06-24024 June 1991 Notice of Violation from Safety Insp on 910603-07.Violation Noted:Personnel Not Trained in Skill Area on 910603 & 04 ML17328A9101991-03-0606 March 1991 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $150,000.Noncompliance Noted:Licensee Identified Conditions Adverse to Fire Protection & Failed to Promptly Correct Deficiencies ML17328A9111991-03-0606 March 1991 Notice of Violation from Insp on 820412-0610.Violation Noted:Redundant Trains of Following Sys Not Provided W/Acceptable Fire Protection ML17328A7741990-11-0909 November 1990 Notice of Violation from Insp on 900910-14,1005 & 1106. Violation Noted:Staff Member Selected for Nuclear Safety & Design Review Committee for Audit Team Had Responsibilities in Fire Protection & Safe Shutdown Capability Assessment ML17328A7911990-11-0808 November 1990 Notice of Violation from Insp on 900611-0713.Violation Noted:Licensee Replaced Valve in Component Cooling Water HX Inlet Line Mfg by Centerline Co W/Valve Mfg by Henry Pratt Co W/O Engineering Review ML17328A4821990-10-0505 October 1990 Notice of Violation from Insp on 900827-31 & 0914.Violation Noted:Test of Operability of Highly Contaminated Chemical Vol & Control Sys Safety Relief Valve Conducted W/O Adequately Evaluating Extent of Radiological Hazards ML17328A6741990-04-24024 April 1990 Notice of Violation from Insp on 891004-1106 & 1227-900206. Violations Noted:On 891012,nonlicensed Auxiliary Equipment Operator Failed to Perform Various Assigned Area Insps & Falsely Signed Log Sheets Indicating Insps Were Performed ML17325B4271990-03-0909 March 1990 Notice of Violation from Enforcement Conference on 900227. Violation Noted:Unit 2 Continuously Operated in Modes 1,2 & 3 from 890620-0815 & 0817-900108 W/Stop Valve 2-MRV-210 Inoperable ML17328A6021990-02-26026 February 1990 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Violation Noted:Failure to Have Three Independent Steam Generator Auxiliary Feedwater Pumps & Flow Paths Operable from 780831-891110 ML17328A5411990-01-0909 January 1990 Notice of Violation from Insp on 891113-1221.Violations Noted:Environ Qualification Records Did Not Contain Positive Statement Re Level of Qualification for Each Component & Sys Component Evaluation Sheets Incomplete ML17328A1611989-09-13013 September 1989 Notice of Violation from Insp on 890719-0829.Violation Noted:Unit Shift Supervisor Signatures & Auxiliary Equipment Operator Signatures Missing in Approximately 20% of Log Sheets Reviewed for Period 890620-0731 ML17328A0971989-08-0101 August 1989 Notice of Violation from Insp on 890607-0718.Violation Noted:Inoperable Channels Not Placed in Trip Condition, Pending Data Evaluation ML17326B5681989-03-13013 March 1989 Notice of Violation from Insp on 890209-15.Violation Noted: Failure to Adhere to Procedure 2-THP-4030 STP.202 Re Control of Test Configuration of Weld Channel Pressurization Sys & Four Valves Mispositioned During Temp Stabilization Period ML17325B0581988-12-0101 December 1988 Notice of Violation from Insp on 881020-1116.Violation Noted:Fire Watch Covering Welding of Unistrut Attachment on Steam Generator 21 Specified Under Hot Work Permit 1247 Not Present ML17326B4891988-11-0808 November 1988 Notice of Violation from Insp on 880908-1019.Violation Noted:Four of twenty-four Hydrogen Skimming Sys Dampers Not Positioned Per Procedure 1-OHP 4021.029.008 for Some Undetermined Period Prior to 880907 ML17325A7621988-05-25025 May 1988 Notice of Violation from Insp on 880316-0518.Violation Noted:Substitution of Weld Matl Utilized for Chemical & Vol Control Sys cross-tie Mod Did Not Receive Adequate Engineering Review ML17326B3811988-05-10010 May 1988 Notice of Violation from Insp on 880315-0425.Violation Noted:Contrary to Tech Spec 4.3.1.1.1,licensee Failed to Perform Channel Checks at Required 12 H Frequency While Facility Was in Mode 3 W/Reactor Trip Sys Breakers Closed ML17326B3461988-02-29029 February 1988 Notice of Violation from Insp on 880125-29.Violation Noted: Communication Tests of Emergency Notification Sys & Health Physics Network Telephone Equipment Had Not Been Tested by Designated Licensee Personnel Since June 1987 1999-09-22
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000315/19990251999-10-21021 October 1999 Insp Repts 50-315/99-25 & 50-316/99-25 on 990816-20. Non-cited Violations Noted.Major Areas Inspected:Evaluate Adequacy of Procedures Used to Refurbish 4.16kV & 600Vac Circuit Breakers IR 05000315/19990271999-10-15015 October 1999 Partially Deleted Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24 (Ref 10CFR73.21).Noncited Violation Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of Plant Facility. 15 IR 05000315/19990161999-09-27027 September 1999 Insp Repts 50-315/99-16 & 50-316/99-16 on 990719-23 & 0802-06.Violations Noted & Being Treated as Ncvs.Major Areas Inspected:Review of Training Administrative Procedures & Operating Exam Matls & Evaluation of Program Controls IR 05000315/19990171999-09-22022 September 1999 Insp Repts 50-315/99-17 & 50-316/99-17 on 990717-0825. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML17326A1671999-09-22022 September 1999 Notice of Violation from Insp on 990717-0825.Violation Noted:On 990521,licensee Performed Surveillance Test on Unit 2 East Residual Heat Removal Train Using Component Cooling Water Sys Without Having Performed Full SE IR 05000315/19990071999-09-16016 September 1999 Insp Repts 50-315/99-07 & 50-316/99-07 on 990712-30 & 0816. Violations Noted & Being Treated as Ncvs.Major Areas Inspected:Discoery Phase of Licensee Expanded Sys Readiness Review Effort IR 05000315/19990181999-09-15015 September 1999 Insp Repts 50-315/99-18 & 50-316/99-18 on 990726-30 & 0816. Violations Noted.Major Areas Inspected:Completed Evaluation of Effectiveness of Audit of Expanded Sys Readiness Review Program by Licensee Performance Assurance Dept PNO-III-99-039, on 990819,seventeen Persons Were Arrested for Trespassing During anti-nuclear Demonstration at DC Cook Plant.Demonstration,Involving About 80 Persons,Took Place at Entrance to owner-controlled Portion of Site1999-08-20020 August 1999 PNO-III-99-039:on 990819,seventeen Persons Were Arrested for Trespassing During anti-nuclear Demonstration at DC Cook Plant.Demonstration,Involving About 80 Persons,Took Place at Entrance to owner-controlled Portion of Site IR 05000315/19990151999-08-13013 August 1999 Insp Repts 50-315/99-15 & 50-316/99-15 on 990528-0716.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000315/19990131999-07-12012 July 1999 Insp Repts 50-315/99-13 & 50-316/99-13 on 990517-0611.One Violation Occurred & Being Treated as non-cited Violation. Major Areas Inspected:Corrective Action Design Engineering, Plant Engineering & Observation & Maint Functunal Areas PNO-III-99-033, on 990625,American Electric Power Co Announced Schedule for Restarting DC Cook Nuclear Power Station.Unit 2 Lead Unit Is Scheduled for Restart in Apr 2000 & Unit 1 Is Scheduled for Restart in Sept 20001999-06-25025 June 1999 PNO-III-99-033:on 990625,American Electric Power Co Announced Schedule for Restarting DC Cook Nuclear Power Station.Unit 2 Lead Unit Is Scheduled for Restart in Apr 2000 & Unit 1 Is Scheduled for Restart in Sept 2000 IR 05000315/19990141999-06-18018 June 1999 Insp Repts 50-315/99-14 & 50-315/99-14 on 990517-0603.No Violations Noted.Major Areas Inspected:Licensee Radiological Effluent Control & Radiation Protection Programs IR 05000315/19990121999-06-18018 June 1999 Insp Repts 50-315/99-12 & 50-316/99-12 on 990503-21.No Violations Noted.Major Areas Inspected:Expanded Sys Readiness Review Program IR 05000315/19990101999-06-11011 June 1999 Insp Repts 50-315/99-10 & 50-316/99-10 on 990417-0527.Two Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000315/19990061999-06-0303 June 1999 Insp Repts 50-315/99-06 & 50-316/99-06 on 990329-0505.No Violations Noted.Major Areas Inspected:Licensee Performance Assurance Dept Audit of Expanded System Readiness Review Program IR 05000315/19990111999-05-26026 May 1999 Insp Repts 50-315/99-11 & 50-316/99-11 on 990426-30.No Violations Noted.Major Areas Inspected:Root Cause Investigations for Electrical Faults Associated with Motor Control Centers 2-AM-B & 12-TSC-S IR 05000315/19990091999-05-21021 May 1999 Insp Repts 50-315/99-09 & 50-316/99-09 on 990405-23.No Violations Noted.Major Areas Inspected:Review of Expanded Sys Readiness Review Program IR 05000315/19990041999-05-14014 May 1999 Insp Repts 50-315/99-04 & 50-316/99-04 on 990303-0416.Four Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000315/19990081999-05-12012 May 1999 Insp Repts 50-315/99-08 & 50-316/99-08 on 990412-16. Violations Noted.Major Areas Inspected:Reviewed EP Program as Aspect of Plant Support IR 05000315/19990031999-04-23023 April 1999 Insp Repts 50-315/99-03 & 50-316/99-03 on 990308-12 & 22-26. Violations Noted.Major Areas Inspected:Implementation of Expanded Sys Readiness Review Program & Progress of Expanded Sys Readiness Review Teams IR 05000315/19990051999-04-0909 April 1999 Insp Repts 50-315/99-05 & 50-316/99-05 on 990315-19.No Violations Noted.Major Areas Inspected:Effectiveness of Licensee Solid Radwaste Mgt & Radioactive Matl Transportation Programs & Review of QA Program IR 05000315/19990011999-03-26026 March 1999 Insp Repts 50-315/99-01 & 50-316/99-01 on 990114-0302. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000315/19990021999-03-19019 March 1999 Insp Repts 50-315/99-02 & 50-316/99-02 on 990202-19.No Violations Noted.Major Areas Inspected:Review of Expanded Sys Readiness Review Program (ESRR) & Evaluate Effectiveness in Training of Personnel Involved IR 05000315/19980271999-02-0909 February 1999 Insp Repts 50-315/98-27 & 50-316/98-27 on 981204-990113. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000315/19980301999-02-0909 February 1999 Insp Repts 50-315/98-30 & 50-316/98-30 on 981214-990115.No Violations Noted.Major Areas Inspected:Review of Corrective Actions Relative to NRC Identified Issues IR 05000315/19980171999-01-29029 January 1999 Insp Repts 50-315/98-17 & 50-316/98-17 on 980921-1222. Violations Noted.Major Areas Inspected:Licensee Conduct of Safety Sys Functional Insp on AFW Sys IR 05000315/19980231999-01-19019 January 1999 Insp Repts 50-315/98-23 & 50-316/98-23 on 981116-20 & 1207- 11.No Violations Noted.Major Areas Inspected:Review of Licensee Emergency Operating Procedures & Continuing Training Programs to Support Safe Unit Restart PNO-III-99-003, on 990114,licensee Announced That Startup of Both Units Will Be Delayed While Expanded Engineering Reviews of Important Plant Sys Are Being Performed.New Restart Schedule Should Be Available in May1999-01-14014 January 1999 PNO-III-99-003:on 990114,licensee Announced That Startup of Both Units Will Be Delayed While Expanded Engineering Reviews of Important Plant Sys Are Being Performed.New Restart Schedule Should Be Available in May IR 05000315/19980261999-01-0808 January 1999 Insp Repts 50-315/98-26 & 50-316/98-26 on 981130-1210.No Violations Noted.Major Areas Inspected:Licensee C/As for Issues Identified by NRC Inspections & LERs Submitted to NRC IR 05000315/19980211998-12-28028 December 1998 Insp Repts 50-315/98-21 & 50-316/98-21 on 981016-1203. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000315/19980241998-12-14014 December 1998 Partially Withheld Insp Repts 50-315/98-24 & 50-316/98-24 on 981112-19 (Ref 10CFR73.71).Violations Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of DC Cook Facility IR 05000315/19980251998-12-0909 December 1998 Insp Rept 50-315/98-25 on 981112-19.No Violations Noted. Major Areas Inspected:Special Insp to Review Restart Metrics Developed to Evaluate Plant Readiness for Restart & Evaluate Progress in Engineering Resolution of Ice Condenser Issues IR 05000315/19980201998-11-0909 November 1998 Insp Repts 50-315/98-20 & 50-316/98-20 on 980928-1002.No Violations Noted.Major Areas inspected:engineering.Close-out Insp of NRC Review of GL 89-10 IR 05000315/19980181998-11-0606 November 1998 Insp Repts 50-315/98-18 & 50-316/98-18 on 980828-1015.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support ML17335A5021998-11-0404 November 1998 EN-98-064:informs Commission,Per Section III of Enforcement Policy,That NRC Will Exercise Enforcement Discretion Per Section VII.B.2 of Enforcement Policy & Not Issue NOV to Licensee for Violation Associated with MOVs at DC Cook ML20154L9861998-10-13013 October 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $500,000.Violation Noted:As of 980227,licensee Had Not Provided Instructions Appropriate to Circumstances for Activity Affecting Quality ML17335A3351998-10-13013 October 1998 EN-98-063:on 981013,NOV & Notice of Proposed Imposition of Civil Penalties in Amount of $500,000 Will Be Issued to Licensee.Action Based on Violations Stemming from Breakdown in Control of Activities That Led to Matl Degradation IR 05000315/19980191998-09-25025 September 1998 Insp Rept 50-315/98-19 & 50-316/98-19 on 980831-0903.No Violations Noted.Major Areas Inspected:Radiation Protection Program,Including Radiological Environ Monitoring Program & Maint of Effluent Monitors IR 05000315/19980161998-09-23023 September 1998 Insp Repts 50-315/98-16 & 50-316/98-16 on 980717-0827.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000315/19980151998-08-12012 August 1998 Insp Repts 50-315/98-15 & 50-316/98-15 on 980612-0716.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000315/19980121998-06-30030 June 1998 Insp Repts 50-315/98-12 & 50-316/98-12 on 980428-0611. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support ML17334B8021998-06-30030 June 1998 Notice of Violation from Insp on 980428-0611.Violation Noted:On 980505,licensee Identified That Measures Taken to Correct Significant Condition Adverse to Quality,Failure to Properly Vent Primary Sys Were Not Effective IR 05000315/19980101998-06-18018 June 1998 Insp Repts 50-315/98-10 & 50-316/98-10 on 980414-0521.No Violations Noted.Major Areas Inspected:Examination of Part Length Control Rod Housings IR 05000315/19983051998-06-10010 June 1998 Initial Operators Licensing Retake Exam Repts 50-315/98-305OL & 50-316/98-305OL Administered on 980511-14. Exam Results:All Applicants Passed Respective Retake Exams & Were Issued SRO or RO Licenses IR 05000315/19980131998-06-0909 June 1998 Insp Repts 50-315/98-13 & 50-316/98-13 on 980601-02. Violations Noted.Major Areas Inspected:Circumstances Re Worker Who Entered Containment W/Open Wound,In Violation of Station Procedures IR 05000315/19980071998-06-0303 June 1998 Insp Repts 50-315/98-07 & 50-316/98-07 on 980201-0427.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000315/19980111998-06-0202 June 1998 Partially Withheld Insp Repts 50-315/98-11 & 50-316/98-11 on 980504-08 (Ref 10CFR73.21(c)(2)).No Violations Noted.Major Areas Inspected:Security Program Plans,Security Program Procedures,Security Organization & Administration ML17334A7161998-05-28028 May 1998 Insp Repts 50-315/98-08 & 50-316/98-08 on 980313-0427. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML17334A7151998-05-28028 May 1998 Notice of Violation from Insp on 980313-0427.Violation Noted:On 980424,inspectors Determined That in March 1997, Contract Workers Failed to Properly Implement Maintenance Procedure for safety-related Equipment IR 05000315/19980091998-05-0707 May 1998 Insp Repts 50-315/98-09 & 50-316/98-09 on 980414-15.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Design Control & Engineering 1999-09-27
[Table view] |
Text
Enclosure 1
NOTICE OF'IOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY Indiana and Michigan Power Company D. C.
Cook Nuclear Plant Units 1 and 2
Dockets No. 50-315 and 50-316 Licenses No. DPR-58 and No.
DPR-74 EA 90-194 During an NRC inspection conducted during the period of September 10 through November 6, 1990, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1990), the Nuclear Regulatory Commission proposes to impose a civil penalty pursuant to Section 234 of the Atomic Energy Act of 1954, as amended (Act), 42 U.S.C.
- 2282, and 10 CFR 2.205.
The particular violation and associated civil penalty are set forth below:
I.
Violation Assessed a Civil Penalt 10 CFR 50.48(b) requires that all nuclear power plants licensed to operate prior to January 1,
1979 satisfy the applicable requirements of Appendix R
to 10 CFR Part 50 including, specifically, the requirements of Sections III.G, III.J, and III.O.
10 CFR Part 50, Appendix R, Section III.G.2, requires, in part, that, where cables or equipment, including associated non-safety circuits that could prevent operation or cause maloperation due to hot shorts, open circuits, or shorts to ground, of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located within the same fire area outside of primary containment, means of ensuring that'ne of the redundant trains is free of fire damage shall be provided.
10 CFR Part 50, Appendix R, Section'II.G.2,
- requires, in part, that the means to be employed shall be (a) separation of cables and equipment and non-safety circuits of redundant trains by a fire bar rier having a 3-hour rating, or (b) separation of cables and equipment and associated non-safety circuits of redundant trains by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards and fire detectors and an automatic fire suppression system installed, or (c) enclosure of the cables and equipment and non-safety circuits of one redundant train in a fire barrier having a one-hour rating with fire detectors and an automatic fire suppression system installed.
10 CFR Part 50, Appendix R, Section III.G.3, requires, in part, that independent alternative or dedicated shutdown capability shall be provided where the fire protection features for structures,
- systems, or components whose functions are required for hot shutdown do not satisfy Section III.G.2.
P)03f30094 9>00~~+gg5 pDR
@DOCH, 0 p
9
Notice of Violation Contrary to the above, for Unit 1 of the D.C.
Cook facility, licensed to operate prior to January 1, 1979, the licensee failed to ensure that one of the redundant trains of components and cabling located within the same fire area outside of primary containment whose function was required to achieve and maintain hot shutdown conditions were adequately separated or protected.
Specifically, as of August 24, 1990, the power supply cabling in Fire Areas 48 and 49 for both control room indication and local shutdown indication (redundant trains of indication necessary to achieve and main-tain hot shutdown of Unit 1) were not adequately separated or protected in that the cabling was not separated by a fire barrier having a 3-hour rating, a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards or a one-hour fire barrier and no independent alternative/
, dedicated shutdown indication was provided.
This is a Severity Level III violation (Supplement I).
Civil Penalty
$ 150,000.
,II.
Violations Not Assessed a Civil Penalt A.
Sections 2.C(4) and 2.C.3(o) of Amendments No.
31 and No.
12 to Plant Operating Licenses No.
DPR-58 and No.
DPR-74, respectively, require the administrative controls for fire protection, as described in the licensee's submittal dated October 27, 1977, shall be implemented and maintained.
The October 27, 1977 licensee submittal specifies that the Operations guality Assurance Program will meet the criteria as described in Attachment No.. 6 of'he NRC document, "Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and guality Assurance."
Paragraph 8.0 of Attachment No.
6 states, in part, that measures shall be established to ensure that conditions adverse to fire protection, sucl as deficiencies and defective components, are identified and corrected promptly.
Contrary to the above, the licensee identified conditions adverse to fire protection, i.e.,
emergency lighting system deficiencies, and failed to promptly correct the deficiencies.
Examples of these failures include:
1.
Battery deficiencies associated with Emergency Lightira Unit 366 v'<ere identified on July 19, 1988, and were not corrected.
The deficiencies were identified again on September 20, 1988.
2.
Battery deficiencies associated with Emergency Lighting Unit 386 were identified on November 8, 1988, and were not corrected.
The deficiencies were identified again on December 23, 1988.
This is a Severity. Level IV violation (Supplement I).
e B.
Sections 2.C(4) and 2.c.3(o)'f Amendments No.
31 and No.
12 to Plant Operating Licenses No.
DPR-58 and No. DPR-74, respectively, require that the administrative controls for fire protection as described in
Notice of Violation 3
w This C.
the licensee's submittal dated October 27, 1977 shall be implemented and maintained.
The October 27, 1977 licensee submittal specifies that the Operations guality Assurance Program will meet the criteria described in Attachment No.
6 of the NRC document, "Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and
guality Assurance."
Paragraph 1.0 of Attachment No.
6 states, in part, that measures shall be established to assure that applicable guidelines are included in design documents.
These measures shall include design reviews to verify adequacy of wiring isolation and cable separation criteria.
10 CFR Part.50, Appendix R,Section III.G.2, used as a criteria by the licensee for design of Fire Area 29 requires, in part, that redundant trains of cables be separated by a horizontal distance of more than 20 feet with no intervening combustibles.
Contrary to the above, licensee design reviews failed to ensure the adequacy of wiring isolation and cable separation for fire protection considerations.
Specifically, as of September 6, 1990, the licensee failed to verify that Cable Nos.
1-1936R and 2-12467 in Fire Area 29, which provide the Unit 2 LSI panels alternative and normal power supply, respectively, had been adequately separated.
The cables were physically separated but the fire area was not free of intervening combustibles.
is a Severity Level IV violation (Supplement I).
10 CFR 50.48(b) requires that all nuclear power plants licensed to operate prior to January 1,
1979 satisfy the applicable requirements, of Appendix R to 10 CFR Part 50 including, specifically, the requi rements of Sections III.G, III.J, and III.O.
10 CFR Part 50, Appendix R, Section III.J, requires that emergency lighting units with at least an eight hour battery power supply shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes to those locations.
Contrary to the above, from April 14, 1988 through August 30,
- 1990, for Units I and 2 of the D.C.
Cook facility, licensed to operate prior to January 1, 1979, adequate emergency lighting was not provided in certain plant areas needed for operation of safe shutdown equipment and in access and egress routes'to those locations.
For example:
C 1.
The Nuclear Sampling Room, Elevation 587 feet; 2.
The Unit 2 Auxiliary Building Piping Penetration Area, Elevation 591 feet, at Local Shutdown Panel 2-LSI-2; 3.
The Unit 1 Mest Non-Essential Service Mater Valve Gallery, Elevation 612 feet; and
0
Notice of Violation 4.
The Unit 2 West Non-Essential Service Water Valve Gallery, Elevation 612 feet.
This is a Severity Level IV violation (Supplement 1;.
D.
10 CFR 50.48(b) requires that all nuclear power plants licensed to operate prior to January 1,
1979 satisfy the applicable requirements of Appendix R to 10 CFR Part 50 including, specifically, the requirements of Sections III.G, III.J, and III.O.
10 CFR Part 50, Appendix R;Section III.G, requires, in part, that, where cables or equipment, including associated non-safety circuits that could prevent operation or cause maloperation due to shorts to ground, of redundant trains of systems necessary to achieve and main-tain hot shutdown conditions are located withir. the same fire area outside of primary containment, means of ensuring that one of the redundant trains is free of fire damage shall be provided.
'I 10 CFR Part 50, Appendix R, Section III.L.7, requires, in part, that the safe shutdown equipment and systems for each fire area shall be known to be isolated from ass'ociated non-safety circuits in the fire area so that shorts to ground in the associate0 circuits will not prevent operation of the safe shutdown equipmert.
Contrary to the above, as of September 14, 199"., for Unit 1 of the D.C.
Cook facility, licensed to operate prior to January 1, 1979, the safe shutdown equipment for each fire area was not known to be isolated from associated non-safety circuits in the fire area, such that shorts to ground in the associated circuits would not prevent operation of
'he safe shutdown equipment.
Specifically, th:- licensee's circuit coordination study had not included an evaluation of the potentially adverse affect of high impedance=faults, a typ=-.of short to ground.,
on the safe shutdown equipment from all associated non-safety circuits located within any fire area.
This is a Severity Level IV violation (Supplement I.'.
E.
10 CFR Part 50, Appendix B, Criterion III, "Design Control," requires, in part, that measures be established to assure that applicable regu-latory requirements and the design basis are ccrrectly translated into drawings and procedures.
These design control measures shall include control of design interfaces and coordination among participating design organizations.
The design control meas'res shall provide for verifying or checking the adequacy of the desicn.
Contrary to the above, the licensee failed to ensure that adequate design control measures were provided.
Specifically, on or about November 13, 1985, for Unit 1 and on or about June 23, 1984, for Unit 2, the licensee failed to verify that the component cooling water (CCW) and essential service water (ESW) low header pressure isolation
0
Notice of Violation relay wiring changes had been correctly translated onto Drawing Nos..l-98405 and 2-98405 (CCW) and Nos.
1-98415 and 2-98415 (ESM) by a design interface organization.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, the Indiana and Hichigan Power Company (Licensee) is hereby required to submit a written statement of explanation to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, within 30 days of the date of this Notice of Violation and Proposed Imposition of Civil Penalty (Notice).
This reply should be clearlv marked as a "Reply to a Notice of Violation" and should include for each alleged viola-tion:
(1) admission or denial of the alleged violation, (2) the reasons for the violation if admitted, and if denied, the reasons why, (3) the corrective steps that have been taken and the results
- achieved, (4) the corrective steps that will be taken to avoid further violations, and (5) the date when full compliance is achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other actions as may be proper should not be taken.
Consideration may be given to extending the response time for good cause shown.
Under the authority of Section 182 of the Act, 42 U.S.C.
2232, this response shall be submitted under oath or affirmation.
Within the same time as provided for the response required under 10 CFR 2.201, the Licensee may pay the civil penalty by letter addressed to the Director, Office of Enforcement, U.S. Nuclear Regulatory Coomission, with a check, draft, money order, or electronic transfer payable to the Treasurer of the United States ir the amount of the civil penalty proposed above, or may protest imposi-tion of the civil penalty in whole or in part, by a written answer addressed to the Director, Office of Enforcement, U. S. Nuclear Regulatory Conmission.
Should the Licensee fai] to answer within the time specified, an order imposing the civil penalty will be issued.
Should the Licensee elect to file an answer in accordance with 10 CFR 2.205 protesting the civil penalty, in whole or in
- part, such answer should be clearly marked as an "Answer to a Notice of Violation" and may:
(1) deny the violations listed in this Notice in whole or in part, (2) demonstrate extenuating circumstances, (3) show error in this Notice, or (4) show other reasons why the penalty should not be imposed.
In addition to protesting the civil penalty in whole or in part, such answer may request remission or mitigation of the penalty.
In requesting mitigation of the proposed penalty, the factors addressed in Section V;B of 10 CFR Part 2, Appendix C (1990), should be addressed.
Any written answer in accordance with 10 CFR 2.205 should be set forth separately from the statement or explanation in reply pursuant to 10 CFR 2.201, but may incorporate parts of the 10 CFR 2.201 reply by specific reference (e.g., citing page and paragraph numbers) to avoid repetition.
The attention of the Licensee is directed to the other provisions of 10 CFR 2.205, regarding the procedure for imposing a civil penalty.
Notice of Viol ation Upon failure to pay any civil pena1ty due which subsequently has been determined in accordance with the applicable provisions of 10 CFR 2.205, this matter may be referred to the Attorney General, and the penalty,.unless compromised,
- remitted, or mitigated, may be collected by civil action pursuant to Section 234c of the Act, 42 U.S.C.
2282c.
The response noted above (Reply to Notice of Violation, letter with payment of civil penalty, and Answer to a Notice of Violation) should be addressed to:
Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region III, 799 Roosevelt
- Road, Glen Ellyn, Illinois 60137, and a copy to the NRC Resident Inspector at the Donald C.
Cook Nuclear Plant.
FOR THE NUCLEAR RfGULATORY COYYISSION Dated at Glen Ellyn, Illinois this 6th day of Harch 1991 A. Bert Davis Regional Administrator
Enclosure 2
SYNOPSIS 3-82-024 The D.C.
Cook Nuclear Plant (Cook Plant), which was licensed to operate by the U.S. Nuclear Regulatory Commission (NRC) prior to January 1, 1979, is owned by the Indiana and Michigan Electric Company (IMEC).
IMEC is one of a number of operating electric utility companies which together comprise the American Electric Power system.
The American Electric Power Company, Inc.
(AEP) is the parent or holding company for the American Electric Power Service Corporation (AEPSC) and all of the operating electric utility companies within the American Electric Power system.
AEPSC is the AEP subsidiary which provides management, professional and technical services to the companies comprising the American Electric Power System.
On April 8, 1982, the NRC Office of Investigations (OI) initiated an investigation relating to an alleged false statement made by AEPSC on March 27, 1981.
That alleged false statement was discovered by NRC during preparation for the Special Team Fire Protection Inspection of the D.C.
Cook Nuclear Plant (Cook Plant).
That alleged false statement related to Cook Plant's state of compliance with 10 CFR 50.48 and Appendix R to 10 CFR Part 50, "Fire Protection Program for Nuclear Power Plants Operating Prior to January 1, 1979."
The report of that investigation was.completed on February 4, 1983.
That report provided documentation indicating that AEPSC corporate officials were apprised on February 5, 1982, of apparent Cook Plant noncompliance with those requirements.
Subsequent to review of the investigation report, NRC Region III Administrator, James G. Keppler, related that he and other Region III officials had discussed fire protection matters during a meeting on March 16, 1982, with those AEPSC officials.and notification was not made at the time of what NRC believed to be a reportable deficiency.
As a result of that information, OI was requested by Mr. Keppler to conduct a supplemental investigation into the apparent failure to notify NRC of a reportable deficiency.
The additional investigation effort by OI involved not only the new allegation, but also a reanalysis of the false statement allegation.
This report provides information, in the form of statements, testimony, communi-cations and documentation, indicating that the AEPSC Executive Vice President, Construction and New York Engineering; Assistant Vice President, Nuclear Engineering; Assistant Division Manager Nuclear Engineering; Section
- Manager, Nuclear Safety and Licensing; Cognizant Nuclear Engineer; Cognizant Electrical Engineer and Cognizant Fire Protection Engineer participated in the preparation and submittal of the false letter to NRC dated March 27, 1981.
It was testified that those individuals agreed upon an approach to the new fire protection regulation where AEPSC would interpret Appendix R as reouiring Cook Plant to only have the alternate safe shutdown system that was already installed in the plant without any modifications, while each of those individuals knew, as noted through admissions or allusion in testimony, that Cook Plant did not meet the specific requirements of Appendix R.
This report also provides information indicating that the AEPSC Executive Vice President, Construction and New York Engineering, the responsible officer of AEPSC and IMEC, had obtained information on or about February 5, 1982, indicating that Cook Plant was in noncompliance with Appendix R as interpreted by NRC
- and, having received that information, failed to notify NRC of Cook Plant's noncompliance.
During a discussion of the upcoming Appendix R inspection at a meeting between AEPSC and NRC on March 16, 1982, the responsible officer was afforded direct opportunity to provide notice of Cook Plant's noncompliance; but instead, queried NRC concerning the ramifications of being in noncompliance.
Between the dates of February 5, 1982, and March 30,
- 1982, he received numerous cues from his staff and from NRC identifying noncompliance areas at Cook Plant;
- however, the AEPSC letter to NRC dated March 30, 1982, signed by the responsible officer merely indicated that an interpretation difference concerning Appendix R
existed between AEPSC and NRC, that AEPSC should be given a second opportunity to review Cook Plant for corn'pliance with Appendix R and that the upcoming inspection should be postponed until the second review was comp1eted.
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