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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20154C4131998-09-21021 September 1998 Notice of Violation from Insp on 980712-0822.Violation Noted:On or Before 971217,operations Personnel Failed to Designate Appropriate Vent Valves for Venting to Properly Return Sys to Svc as Required by Omp 7-1 ML20237B1561998-08-0707 August 1998 Notice of Violation from Insp on 980531-0711.Violation Noted:Licensee Failed to Establish Procedural Guidance for Abnormal Vent Path Used for Degassing Unit 1 Volume Control Tank to Environ ML20249A2451998-06-0404 June 1998 Notice of Violation from Insp on 980413-24.Violation Noted: Procedure Investigation Processes 2-M96-1440 & 0-M97-1933 Were Not Initiated within 24 H After Realization That Procedure Investigation Process Should Have Been Written ML20216H6051998-04-0606 April 1998 Notice of Violation from Insp on 980125-0307.Violation Noted:Licensee Failed to Adequately Establish or Adhere to Procedural Guidance for Repair of Two safety-related Containment Isolation Valves as Evidenced ML20203F5921998-02-23023 February 1998 Notice of Violation from Insp on 980105-08.Violations Noted: Licensee Failed to Follow Procedures for Security Badge & Access Control IR 07100102/20120131998-01-12012 January 1998 Notice of Violation from Insp on 971102-1213.Violation Noted:Inadequate Measures Were Provided for Verification or Checking Adequacy of Design Documents ML20199B1571998-01-0505 January 1998 Notice of Violation from Insp on 971205-06.Violation Noted: an Event Occurred on 971202 in Which Person or Persons Made Credible Threat to Commit or Cause Significant Physical Damage to Power Reactor & Not Reported within One Hour ML20203M4471998-01-0505 January 1998 Errata to Notice of Violation for Insp Repts 50-369/97-19 & 50-370/97-19.Statement in Nov,Page 2, Under Authority of Section 182 of Act.42USC 2232,this Response Shall Be Submitted Under Oath or Affirmation, Was Incorrect ML20198N4701997-10-20020 October 1997 Notice of Violation from Insp on 970810-0920.Violation Noted:On 960420,ET Guidelines,Apps C & E Were Not Implemented as Evidenced By;Resolution Analyst Revised & Overruled Reexam Request for SG 2A Tube R7C60 ML20212A0361997-10-0808 October 1997 Notice of Violation from Insp on 970712-0827.Violation Noted:As of 970717,10 of 48 Ice Condenser Inlet Doors on Unit 2 Required Initial Opening Torque in Ixcess of 675 inch-pound Operability Limit ML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility ML20149L5701997-07-28028 July 1997 Notice of Violation from Insp on 970518-0628.Violation Noted:Procedure IP/0/A/3250/12B Inadequate to Provide Sufficient Guidance to Properly Test Emergency Diesel Generator Sequencer Logic Circuitry ML20149G6771997-06-16016 June 1997 Notice of Violation from Insp on 970406-0517.Violation Noted:Procedure PT/1/A/4600/014D Was Inadequate in Providing Sufficient Guidance to Bypass Properly RPS Functions of an Inoperable N-41 Channel to Permit Testing of Channel N-42 ML20148B9621997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violation Noted:Prior to 961130,activities Affecting Quality,Not Accomplished in Accordance W/Instructions,Procedures or Drawings ML20137V1381997-03-24024 March 1997 Notice of Violation from Insp on 970112-0222.Violation Noted:Licensee Failed to Implement Appropriate Emergency Procedures,Conduct Required Drills or Renew Exemptions to Be Excluded from Stated Requirements ML20134L1211997-02-10010 February 1997 Notice of Violation from Insp on 961201-970111.Violation Noted:Inspector Identified Modification Involving Installation of Addl Vital Area Physical Barrier ML20135C2411996-11-15015 November 1996 Notice of Violation from Insp on 960908-1019.Violation Noted:Plant Periodic Test Procedure,Annulus Ventilation Sys Train B Operability Test Not Adequate ML20128H6631996-10-0202 October 1996 Notice of Violation from Insp on 960728-0907.Violation Noted:Licensee Failed to Demonstrate Operability of 1A EDG within Required Time After 1B EDG Was Determined to Be Inoperable ML20059C0261993-12-16016 December 1993 Notice of Violation from Insp on 931017-1120.Violation Noted:On 930909,remote Visual QA Exam Performed on Weld of Tube Plug 39-72 in Unit 1 a Steam Generator Inadequate ML20059K7221993-11-0909 November 1993 Notice of Violation from Insp on Stated Date.Violation Noted:Loss of Normal Letdown Charging or Seal Injection Flow Procedure Was Inadequate Since Failed to Require Any Cautions,Instructions or Guidance ML20059K4291993-10-20020 October 1993 Notice of Violation from Insp on 930822-0925.Violation Noted:Vendors Replacing Roof on Unit 1 Fuel Handling Building Failed to Adhere to Requirements to Use Fire Extinguishers & Obtain Hot Work Permit ML20057C1611993-09-14014 September 1993 Notice of Violation from Insp on 930718-0821.Violation Noted:Surveillance Procedures PT/1/A/4350/36A & PT/1/A/4350/36B Were Not Revised to Incorporate Changes to TS 4.8.1.1.2.e ML20056G9011993-08-19019 August 1993 Notice of Violation from Insp on 930621-25 & 0729.Violation Noted:Loss of Offsite Power Event on Unit 1 Occurred on 910211 for Which Licensee Failed to Immediatley Declare Notification of Unusual Event ML20056E4741993-08-12012 August 1993 Notice of Violation from Insp on 930628-0702 & 930712-16. Violation Noted:Licensee Failed to Notify NRC of Change in Medical Status of Licensed Operators within 30 Days as Required,Per 10CFR55.25 & 10CFR50.74 ML20056E3171993-08-0909 August 1993 Notice of Violation from Insp on Stated Date.Violation Noted:Licensee Had No Specific Procedure in Place Nor Any Preventative Maint Schedule Developed for Lake Level Instrumentation,For Purpose of Entering Emergency Plan ML20127P7331993-01-13013 January 1993 Notice of Violation from Insp on 921115-1219.Violation Noted:On 921105,licensee Completed PIR-0-M92-0140 W/O Identifying Root Cause or Actions Necessary to Prevent Recurrence ML20217B8731991-02-19019 February 1991 Notice of Violation from Insp on 910106-0202.Violation Noted:Measures Not Adequate to Assure Prompt Corrective Action Taken in Correction of Generic Fuse Installation Problems Originally Identified in March 1989 ML20056A5841990-07-24024 July 1990 Notice of Violation from Insp on 900522-0625.Violations Noted:Both Units Operated W/Two of Four Control Room Ventilation (VC) Sys Intakes Closed from 900525-0603 & Failure to Report Inoperable VC Trains in Required Time ML20246N6471989-08-21021 August 1989 Notice of Violation from Insp on 890707-18.Violation Noted: Core Operated in Excess of 102% of 3,411 Thermal MW Limit Briefly & in Excess of 101% for Nearly 3 H ML20245L4281989-08-0808 August 1989 Notice of Violation from Insp on 890622-28.Violation Noted: Design Control Measures for Changes to Plant Inadequate, Leading to Confusing Instructions to Craft Personnel Which Resulted in Installation of nonsafety-related Positioner ML20236E6441989-07-17017 July 1989 Notice of Violation from Insp on 890422-0601.Violation Noted:Procedures PT/1 & 2/A/4255/03A Deemed Inadequate in That Procedures Specified Testing of MSIVs W/Air Assist, Contrary to Assumed Conditions in FSAR ML20244E5861989-06-0808 June 1989 Notice of Violation from Insp on 890330-0421.Violation Noted:Electrical Drawing MCM-1399.03-0300-001 Inadequate in That It Was Not Properly Updated Contributing to Personnel Error & Temporary Loss of RHR Sys on 881201 ML20247N8241989-05-24024 May 1989 Notice of Violation from Insp on 890424-28.Violation Noted: 1987 Semiannual Effluent Release Rept Listed Two Abnormal Releases But Did Not Include Descriptions of Events ML20246J6511989-05-0505 May 1989 Notice of Violation from Insp on 890213-17 & 0227-0303. Violations Noted:On 890215,maint Crew Observed Working on Work Request W/O Following Appropriate Procedure & with Inadequate Preplanning,Procedures & Instructions ML20245G9641989-04-21021 April 1989 Notice of Violation from Insp on 890228-0329.Violation Noted:Failure to Follow Procedures Re Diesel Generator Starting Air Tank 1B2 Drain Valve ML20244A8801989-03-30030 March 1989 Notice of Violation from Insp on 890120-0227.Violations Noted:Control Room Door Seals Repaired on 890117 W/O Authorization on Work Request & Auxiliary Feedwater Resistance Temp Detectors Installed W/O Authorized Request ML20235P5221989-02-14014 February 1989 Notice of Violation from Insp on 881122-890119.Violation Noted:Procedure Not Properly Implemented in That 1A Emergency Diesel Generator Started on 881206 Using 2A Emergency Diesel Generator Test Procedure ML20206A5551988-11-0404 November 1988 Notice of Violation from Insp on 880924-1020.Violation Noted:Personnel Training Not Completed Prior to Returning low-Tave Setpoint Circuitry to Svc Following Setpoint Change & Unit Not Placed in Hot Shutdown within 6 H ML20154F9801988-09-0606 September 1988 Notice of Violation from Insp on 880723-0819.Violation Noted:Procedure OP/2/A/6250/02, Auxiliary Feedwater Sys, Step 2.5 Not Performed as Written & Procedure Not Written & Procedure PT/2/A/4204/05 Inadequate ML20151Z8741988-08-19019 August 1988 Notice of Violation from Insp on 880625-0722.Violations Noted:Procedure for Steam Generator Cold Wet Lay Up Recirculation Inadequate in That Performance of Procedure Caused ESF Actuation ML20151E6041988-07-0808 July 1988 Notice of Violation from Insp on 880521-0624.Violation Noted:Maint Personnel Adjusted Fuel Racks on Diesel Generator 2A to Increase Output W/O Work Request or Procedure ML20195C8481988-06-0909 June 1988 Notice of Violation from Insp on 880502-06.Violation Noted: ASME Code Section XI Stroke Time Tests Performed in Manner That Could Be Unduly Affected by Changes in Measurements & Instruments,Contrary to Tech Spec 4.0.5,in Oct 1987 ML20155J3311988-06-0606 June 1988 Notice of Violation from Insp on 880423-0520.Violation Noted:Procedure PT/1/A/4252/01, Auxiliary Feedwater Pump Number 1 Performance Test Inadequate in That Horizontal Vibration Ranges Did Not Correspond to Required Ranges ML20153F5161988-04-29029 April 1988 Notice of Violation from Insp on 880319-0422.Violation Noted:Procedure PT/O/A/4150/05 Not Properly Implemented & Procedure PT/2/A/4200/28A Not Properly Maintained ML20148H1701988-03-10010 March 1988 Notice of Violation from Insp on 880121-0226.Violation Noted:Procedure IP/O/A/3061/08 Not Properly Implemented & Procedure for Removing Cation Bed Demineralizer from Svc Not Properly Maintained ML20149M1221988-02-19019 February 1988 Notice of Violation from Insp on 871121-880120.Violations Noted:Written Procedures Covering Operation & Maint of safety-related Equipment Not Established,Implemented & Maintained Causing Reactor Trip & Sys Actuation on 871228 ML20149D6151988-02-0404 February 1988 Notice of Violation from Insp on 871107-880113.Violation Noted:Test Program Established to Demonstrate That Component Cooling Sys Will Perform Satisfactorily in Svc Not Adequate ML20149E1991988-01-15015 January 1988 Notice of Violation from Insp on 871215-18.Violation Noted:Failure to Rept Event within 30 Days of Occurrence in Period 870522-0611 IR 07100021/20110201987-12-28028 December 1987 Notice of Violation from Insp on 871021-1120.Violations Noted:Work Performed on Flow Instrument W/O Procedural Verification of safety-related Component & post-mod Test of Main Electrical Busline Exceeded Scope of Procedures ML20236M2921987-10-28028 October 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violations Noted:Diesel Generator Inoperable for More than Allowed Tech Spec Limit & Operations Mgt Procedure Not Properly Implemented 1998-09-21
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000369/19990061999-10-0404 October 1999 Insp Repts 50-369/99-06 & 50-370/99-06 on 990801-0911. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19990051999-08-26026 August 1999 Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Noted Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000369/19990041999-07-13013 July 1999 Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19990101999-06-16016 June 1999 Insp Repts 50-369/99-10 & 50-370/99-10 on 990322-26.No Violations Noted.Major Areas Inspected:Aspect of Licensee Health Physics Activities During Unit 2 Refueling Outage IR 05000369/19990031999-06-0202 June 1999 Insp Repts 50-369/99-03 & 50-370/99-03 on 990328-0508. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19990021999-04-23023 April 1999 Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000369/19993011999-03-18018 March 1999 NRC Operator Licensing Exam Repts 50-369/99-301 & 50-370/99-301 (Including Completed & Graded Tests) for Tests Administered on 990125-0205.Five SRO & Six RO Candidates Received Written Exams & Operating Tests IR 05000369/19990011999-03-10010 March 1999 Insp Repts 50-369/99-01 & 50-370/99-01 on 990103-0213.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980101998-12-18018 December 1998 Insp Repts 50-369/98-10 & 50-370/98-10 on 981004-1121.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19980091998-10-30030 October 1998 Insp Repts 50-369/98-09 & 50-370/98-09 on 980823-1003.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980081998-09-21021 September 1998 Insp Repts 50-369/98-08 & 50-370/98-08 on 980712-0822.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20154C4131998-09-21021 September 1998 Notice of Violation from Insp on 980712-0822.Violation Noted:On or Before 971217,operations Personnel Failed to Designate Appropriate Vent Valves for Venting to Properly Return Sys to Svc as Required by Omp 7-1 IR 05000369/19980111998-08-27027 August 1998 Insp Repts 50-369/98-11 & 50-370/98-11 on 980601-26 & 0805-07.No Violations Noted.Major Areas Inspected:Maint & Engineering Programs.Rept Reviewed Maintenance,Surveillance & Matl Condition of Mcquire,Unit 1 Ice Condenser System IR 05000369/19980071998-08-0707 August 1998 Insp Rept 50-369/98-07 & 50-370/98-07 on 980531-0711. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support ML20237B1561998-08-0707 August 1998 Notice of Violation from Insp on 980531-0711.Violation Noted:Licensee Failed to Establish Procedural Guidance for Abnormal Vent Path Used for Degassing Unit 1 Volume Control Tank to Environ IR 05000369/19980061998-06-25025 June 1998 Insp Repts 50-369/98-06 & 50-370/98-06 on 980419-0530.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000369/19980041998-06-0404 June 1998 Insp Repts 50-369/98-04 & 50-370/98-04 on 980413-24. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support PNO-II-98-030, on 980603,loss of Offsite Power Occurred,Due to Loss of 1B Bus.Caused by Faulted 230 Kv Switchyard Current Transformer.Resident Inspectors Onsite & Responded to Event & Will Continue to Evaluate Activities W/Event1998-06-0404 June 1998 PNO-II-98-030:on 980603,loss of Offsite Power Occurred,Due to Loss of 1B Bus.Caused by Faulted 230 Kv Switchyard Current Transformer.Resident Inspectors Onsite & Responded to Event & Will Continue to Evaluate Activities W/Event ML20249A2451998-06-0404 June 1998 Notice of Violation from Insp on 980413-24.Violation Noted: Procedure Investigation Processes 2-M96-1440 & 0-M97-1933 Were Not Initiated within 24 H After Realization That Procedure Investigation Process Should Have Been Written IR 05000369/19980031998-05-18018 May 1998 Insp Repts 50-369/98-03 & 50-370/98-03 on 980308-0418.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H6051998-04-0606 April 1998 Notice of Violation from Insp on 980125-0307.Violation Noted:Licensee Failed to Adequately Establish or Adhere to Procedural Guidance for Repair of Two safety-related Containment Isolation Valves as Evidenced ML20216H6171998-04-0606 April 1998 Insp Repts 50-369/98-02 & 50-370/98-02 on 980125-0307. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000369/19970201998-02-23023 February 1998 Insp Repts 50-369/97-20 & 50-370/97-20 on 971214-980124. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Including Review of Radiological Protection Practices & Plant Physical Security ML20203F5921998-02-23023 February 1998 Notice of Violation from Insp on 980105-08.Violations Noted: Licensee Failed to Follow Procedures for Security Badge & Access Control IR 05000369/19980011998-02-17017 February 1998 Partially Withheld Insp Repts 50-369/98-01 & 50-370/98-01 on 980114-15 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant & Vehicle Barrier Sys IR 07100102/20120131998-01-12012 January 1998 Notice of Violation from Insp on 971102-1213.Violation Noted:Inadequate Measures Were Provided for Verification or Checking Adequacy of Design Documents ML20198P3771998-01-12012 January 1998 Insp Repts 50-369/97-18 & 50-370/97-18 on 971102-1213. Violations Noted.Major Areas Inspected:Integrated Insp Included Aspects of Licensee Operation,Maint,Engineering & Plant Support ML20199B1571998-01-0505 January 1998 Notice of Violation from Insp on 971205-06.Violation Noted: an Event Occurred on 971202 in Which Person or Persons Made Credible Threat to Commit or Cause Significant Physical Damage to Power Reactor & Not Reported within One Hour ML20199B1641998-01-0505 January 1998 Insp Repts 50-369/97-19 & 50-370/97-19 on 971205-06. Violations Noted.Major Areas Inspected:Licensee Response to 971202 Event Involving Seal Damage Event at Four Air Lock Doors of Unit 2 Containment Bldg ML20203M4471998-01-0505 January 1998 Errata to Notice of Violation for Insp Repts 50-369/97-19 & 50-370/97-19.Statement in Nov,Page 2, Under Authority of Section 182 of Act.42USC 2232,this Response Shall Be Submitted Under Oath or Affirmation, Was Incorrect IR 05000369/19970171997-12-0101 December 1997 Insp Repts 50-369/97-17 & 50-370/97-17 on 970921-1101.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000369/19970151997-10-20020 October 1997 Insp Repts 50-369/97-15 & 50-370/97-15 on 970810-0920. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20198N4701997-10-20020 October 1997 Notice of Violation from Insp on 970810-0920.Violation Noted:On 960420,ET Guidelines,Apps C & E Were Not Implemented as Evidenced By;Resolution Analyst Revised & Overruled Reexam Request for SG 2A Tube R7C60 ML20212A0361997-10-0808 October 1997 Notice of Violation from Insp on 970712-0827.Violation Noted:As of 970717,10 of 48 Ice Condenser Inlet Doors on Unit 2 Required Initial Opening Torque in Ixcess of 675 inch-pound Operability Limit ML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility IR 05000369/19970121997-09-22022 September 1997 Insp Repts 50-369/97-12 & 50-370/97-12 on 970804-08.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise ML20211E7981997-09-16016 September 1997 Insp Repts 50-369/97-16 & 50-370/97-16 on 970712-0827. Violations Being Considered for Escalated Eas.Major Areas Inspected:Review of Aspects of Problem Involving Inoperable Unit 2 Ice Condenser Lower Inlet Doors IR 05000369/19970101997-09-0808 September 1997 Insp Repts 50-369/97-10 & 50-370/97-10 on 970629-0809.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support IR 05000369/19973001997-08-29029 August 1997 NRC Operator Licensing Exam Repts 50-369/97-300 & 50-370/97-300 (Including Completed & Graded Tests) for Test Administered on 970728-31.Exam Results:Five SRO & One RO Passed Exam & One SRO Failed Exam IR 05000369/19970131997-08-22022 August 1997 Insp Repts 50-369/97-13 & 50-370/97-13 on 970721-24.No Violations Noted.Major Areas Inspected:Licensees Program for Compensatory Measures for Degraded Security Equipment ML20217R1161997-08-18018 August 1997 EN-97-076:on 970818,order Prohibiting Involvement in NRC- Licensed Activities for a Period of One Year Will Be Issued. Action Based on Investigation Conducted by Oi,Which Determined Falsification of QA Document PNO-II-97-051, on 970906,McGuire Units 1 & 2 Automatically Tripped.Porvs Utilized Until Steam Dumps Could Be Made Available.Steam Relieved Through Main Steam PORVs Until Power to Bus Kxa Restored & MSIVs Reopened1997-08-0909 August 1997 PNO-II-97-051:on 970906,McGuire Units 1 & 2 Automatically Tripped.Porvs Utilized Until Steam Dumps Could Be Made Available.Steam Relieved Through Main Steam PORVs Until Power to Bus Kxa Restored & MSIVs Reopened ML20149L5751997-07-28028 July 1997 Insp Repts 50-369/97-09 & 50-370/97-09 on 970518-0628. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support ML20149L5701997-07-28028 July 1997 Notice of Violation from Insp on 970518-0628.Violation Noted:Procedure IP/0/A/3250/12B Inadequate to Provide Sufficient Guidance to Properly Test Emergency Diesel Generator Sequencer Logic Circuitry ML20149G6881997-06-16016 June 1997 Insp Repts 50-369/97-08 & 50-370/97-08 on 970406-0517. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20149G6771997-06-16016 June 1997 Notice of Violation from Insp on 970406-0517.Violation Noted:Procedure PT/1/A/4600/014D Was Inadequate in Providing Sufficient Guidance to Bypass Properly RPS Functions of an Inoperable N-41 Channel to Permit Testing of Channel N-42 IR 05000369/19970071997-06-0202 June 1997 Insp Rept 50-369/97-07 on 970406-0503.Violations Noted.Major Areas Inspected:Sg Replacement Project Activities in Areas of Maint & Engineering IR 05000369/19970041997-05-0505 May 1997 Insp Repts 50-369/97-04 & 50-370/97-04 on 970223-0405. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20148B9621997-05-0505 May 1997 Notice of Violation from Insp on 970223-0405.Violation Noted:Prior to 961130,activities Affecting Quality,Not Accomplished in Accordance W/Instructions,Procedures or Drawings IR 05000369/19970051997-04-28028 April 1997 Insp Rept 50-369/97-05 on 970309-0405.No Violations Noted. Major Areas Inspected:Maint,Engineering & Plant Support 1999-08-26
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. O ENCLOSURE 1 E2TICE OF VIOLATION Duke Power Company Docket Nos. 50-369, 370 McGuire Units 1 and 2 License Nos. NPF-9, NPF-17 During the Nuclear Regulatory Commission (NRC) inspection conducted on March 19, 1988 through April 22, 1988, 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 (1987), the violations are identified below:
A. Technical Specification (TS) 6.8.1.a. requires that written procedures be established, implemented, and maintained covering the activities delineated in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Regulatory Guide 1.33, Revision 2, February 1978, Appendix A, requires, in ;; art, that surveillanca procedures be written and implemented for testing including pressurizer safety valve tests and reactor protection system tests.
McGuire procedure PT/0/A/4150/05, Pressurizer Safety Valve Setpoint Test, requires that each of three lifts of the valve be with in the TS required band at 2483 psig plus or minus one percent (2461 to 2509 psig).
- 1. Contrary to the above, procedure PT/0/A/4150/05 was not properly implemented in that the second lift of 2NC1 on June 11, 1987, was outside of the required band (4 psi high) and the test was signed off as satisfactory by both maintenance and quality control personnel.
- 2. Contrary to the above, procedure PT/2/A/4200/28A, Slave Relay Testing, was not properly maintained in that an error in the procedure caused Unit 2 non-safety containment ventilation systems to inadvertently re-align to alternate power sources on March 22, 1988.
This is a Severity Level IV violation (Supplement I) and is applicable to Unit 2 only.
- 8. Technical Specification (TS) 3.7.3 requires that, in Modes 1-4, two independent Component Cooling Water (KC) System loops be operable. With only one KC loop operable, both loops must be returned to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the unit must be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Contrary to the above, Ur.it I was operated in Mode 1 for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with KC loop 8 inoperable between January 29, 1988 and March 9, 1988. KC loop B was inoperable in that the Nuclear Service Water (RN) throttle valve to KC heat exchanger 1B (RN-1908), would not have positioned to provide full design RN flow to the heat exchanger if required to do so in an engineered safety features actuation.
8805100355 PDR 880429 Q ADOCK 05000369 DCD
/1 . ,
Duke Power Company 2 Docket Nos. 50-369, L'70 McGuire Units 1 and 2 License Nos. NPF-9, NFF-17 This is a Severity Level IV violation (Supplement I) and is applicable to Unit 1 only.
C. Technical Specification (TS) 4.0.5 requires th ; inservice testing of ASME Code Class 1, 2, and 3 valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessei Code.
Article IWV 3200 of Section XI of the ASME Boiler and Pressure Vessel Cade requires that valves which perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident shall be tested, following maintenance, and prior to the time of being returned to service, to demonstrate that the performance parameters which could be affected by the maintenance are within acceptable limits.
Contrary to the above, Unit 1 Nuclear Service Water (RN) valve RN-21 underwent maintenance in the form of a packing adjustment on February 4, 1988 but did not receive a valve stroke timing test to verify valve shutting time to be within required limits.
This is a Severity Level IV violation (Supplement I) and is applicable to Unit 1 only.
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washingten, DC 20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, McGuire Nuclear Station within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation if admitted (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.
Where good cause is shown, consideration will be given to extending the response time. If an adaquate 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 action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGtna gy VIRGIL L. L'.lCWNLEE Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects CatedagAtlanta, Georgia this // day of April 1988
e ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-369, 370 McGuire Units 1 and 2 License Nos. NPF-9, NPF-17 During the Nuclear Regulatory Commission (NRC) inspection conducted on March 19, 1988 through April 22, 1988, 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 (1987), the violations are identified below:
A. Technical Specification (TS) 6.8.1.a. requires that written procedures be ,
established, implemented, and maintained covering the activities delineated in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Regulatory Guide 1.33, Revision 2, February 1978, Appendix A, requires, in part, that surveillance procedures be written and implemented for testing including pressurizer safety valve tests and reactor protection system tests.
McGuire procedure PT/0/A/4150/05, Pressurizer Safety Valve Setpoint Test, requires that each of three lifts of the valve be with in the TS required band of 2485 psig plus or minus one percent (2461 to 2509 psig).
- 1. Contrary to the above, procedure PT/0/A/4150/05 was not properly implemented in that the second lift of 2NC1 on June 11, 1987, was outside of the required band (4 psi high) and the test was signed off as satisfactory by both maintenance and quality control personnel.
- 2. Contrary to the above, procedure PT/2/A/4200/28A, Slave Relay Testing, was not properly maintained in that an error in the procedure caused Unit 2 non-safety containment ventilation systems to inadvertently re-align to alternate power sourc.es on March 22, ;
1938.
This is a Severity Level IV violation (Supplement I) and is applicable to Unit 2 only.
B. Technical Specification (TS) 3.7.3 requires that, in Modes 1-4, two independent Component Cooling Water (KC) System loops be operable. With only one KC loop operable, both loops must be returned to operable status ;
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the unit must be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. I Contrary to the above, Unit I was operated in Mode 1 for greater than 72 j hours with KC loop B inoperable between January 29, 1988 and March 0, 1988. KC loop B was inoperable in that the Nuclear Service Water (RN) throttle valve to KC heat exchanger IB (RN-1908), would not have positioned to provide full design RN flow to the heat exchanger if required to do so in an engineered safety features actuation.
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Duke Power Company 2 Docket Nos. 50-369, 370 McGuire Units 1 and 2 License Nos. NPF-9, NPF-17 This is a Severity Level IV violation (Supplement I) and is applicable to Unit 1 only. ,
C. Technical Specification (TS) 4.0.5 requires that inservice testing of ASME Code Class 1, 2, and 3 valves be perforced in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.
Article IWV 3200 of Section XI of the ASME Boiler and Pressure Vessel Code requires that valves which perform a specific function in shutting down a :
reactor to the cold shutdown condition or in mitigating the consequences of an accident shall be tested, following maintenance, and prior to the time of being returned to service, to demonstrate that the performance parameters which could be affected by the maintenance are within acceptable limits.
Contrary to the above, Unit 1 Nuclear Service Water (RN) valve RN-21 underwent maintenance in the form of a packing adjustment on February 4, 1988 but did not receive a valve stroke timing test to verify valve shutting time to be within required limits.
This is a Severity Level IV violation (Supplement I) and is applicable to !
Unit 1 only.
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, McGuire Nuclear Station within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation if admitted, (2) the corrective steps that have been taken and ;
the results achievt/ (3) the corrective steps that will be taken to avoid !
further violations, and (4) the date wher full compliance will be achieved. ,
Where good cause is shown, consideration will be given to extending the !
response time. If an adequate reply is not received within the time specified l 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 action as may be proper should not be *,aken.
- FOR THE NUCLEAR REGULATORY COMMISSION l
VI'rg i j nLA
. Brownlee, Chief l Reactor Projects Branch 3 i Division of Reactor Projects ;
I Dated at Atlanta, Georgia this g day of April 1983 J
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