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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058E8621990-11-0101 November 1990 Forwards Understanding of Current Status of Unimplemented GSIs at Facility,Per 900626 Response to Generic Ltr 90-04. Timely Completion of Encl GSIs Urged ML20058G1561990-10-31031 October 1990 Requests That Matl Listed in Encl 1, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams, Be Furnished by 901207 for Retake of Operating Exams Scheduled for 910122 ML20058B3101990-10-23023 October 1990 Forwards Insp Rept 50-382/90-22 on 900905-1001 & Notice of Violation IR 05000382/19900231990-10-17017 October 1990 Submits Revised Schedule for Electrical Distribution Sys Functional Insp 50-382/90-23.Insp Team Will Arrive at Plant Site on 910107 ML20058B2681990-10-17017 October 1990 Informs That Util Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058A6711990-10-16016 October 1990 Forwards Insp Rept 50-382/90-21 on 900910-14.No Violations or Deviations Noted ML20058A4771990-10-16016 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-17 ML20062B6231990-10-12012 October 1990 Confirmation of Action Ltr CAL-90-06,confirming That Plant Will Not Enter Mode 2 Until NRC Confirms Actions Assuring That Adequate Safety Exists for Continued Power Operation IR 05000382/19900151990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-15.NRC Unable to Clearly Determine Actions Intended to Address Overall Retest & Program Weaknesses ML20059N7041990-10-10010 October 1990 Ack Receipt of Util 900717 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20059K8651990-09-14014 September 1990 Forwards Interfacing Sys LOCA Insp Rept 50-382/90-200 on 900730-0810.Deficiencies in Availability of Design Calculations,Check Valve Maint & Plant Equipment Labeling Noted ML20059K3601990-09-14014 September 1990 Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise ML20059D5901990-08-28028 August 1990 Forwards Insp Rept 50-382/90-17 on 900625-29.No Violations or Deviations Noted.Exercise Weakness Re Performance of Emergency Responders Noted ML20056B4841990-08-22022 August 1990 Forwards Errata to Amend 62 to License NPF-38,consisting of Revised Bases Page Re Time Intervals for Surveillance Requirements,Per 900717 Application & Generic Ltr 89-14 ML20056B2731990-08-16016 August 1990 Ack Receipt of 900720 & 0803 Ltrs Re Objectives & Guidelines for Annual Emergency Preparedness Exercise.Objectives Appear Reasonable.Exercise Scenario & Associated Matls Should Be Submitted at Least 60 Days Prior to Exercise for NRC Review ML20058P3441990-08-15015 August 1990 Advises That Although Adequate Info Provided to Justify Continued Plant Operation Until Plant Completes Final Rept Per Schedule Delineated by NRC Bulletin 88-11,adequate Bases Not Provided for 40-yr Plant Life ML20056A0301990-07-30030 July 1990 Forwards Insp Rept 50-382/90-11 on 900625-29.No Violations or Deviations Noted IR 05000382/19900021990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-02 ML20055G7951990-07-19019 July 1990 Forwards Insp Rept 50-382/90-14 on 900625-29 & Notice of Violation.Actions Taken Re Previously Identified Insp Findings Also Examined ML20055E6501990-07-0909 July 1990 Discusses Generic Implications & Resolutions of Control Element Assembly (CEA) Failures at Maine Yankee.Waterford Unit 3 Does Not Have Old Style CEAs Installed in Reactor Core & Does Not Plan to Use Any in Future ML20055C9751990-06-26026 June 1990 Forwards Page 6a for Insertion in Insp Rept 50-382/90-09 ML20055C7781990-06-15015 June 1990 Forwards Insp Rept 50-382/90-09 on 900501-31.No Violations or Deviations Noted.One Unresolved Item Identified.Licensee Test Acceptance Criteria Did Not Appear to Account for Effect of Flow on Valve Closing Time ML20059M9171990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4121990-03-0202 March 1990 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Imposed by NRC 900202 Order.Corrective Actions Will Be Examined During Future Insp ML20055C2991990-02-23023 February 1990 Advises That 890410 Changes to Emergency Plan,Acceptable ML20248G1871989-10-0202 October 1989 Forwards Insp Rept 50-382/89-25 on 890828-0901.No Violations or Deviations Noted ML20248C6531989-09-27027 September 1989 Forwards Insp Rept 50-382/89-23 on 890801-31.Violations Noted.Enforcement Conference Scheduled for 891011 in Region IV Ofc to Discuss Violation,Reason for Occurrence & Corrective Actions ML20248A4091989-09-26026 September 1989 Requests That Jl Pellet Be Removed from Distribution for Controlled Documents Updates & Revs ML20247Q4211989-09-22022 September 1989 Provides Results of Review of Amend to Rev 5 of Inservice Testing Program for Pumps & Valves.Amend to Rev 5 Acceptable for Implementation & That Testing Requirements Impractical for Item for Which Relief Being Granted ML20247R5681989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-92,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, for Signature ML20247J6851989-09-15015 September 1989 Forwards Insp Rept 50-382/89-16 on 890717-21 & Notice of Violation ML20247D4781989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-05 ML20247F2211989-09-0808 September 1989 Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62 ML20247H8501989-09-0808 September 1989 Ack Receipt of 890531 & 0821 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07. NRC Disagrees W/Licensee Denial of Violation.Implementation of Corrective Actions Will Be Reviewed During Future Insp ML20246P6081989-09-0606 September 1989 Forwards Summary of 890712 Meeting w/C-E Owners Group & Utils Re General Design Features of Diverse ESFAS to Be Installed,Per 10CFR50.62.Safety Evaluation on Plant Design Expected to Be Issued in Near Future ML20246N3131989-08-31031 August 1989 Ack Receipt of Re Violations Noted in Insp Rept 50-382/89-08 & 890516 Notice of Violation.Requests Supplemental Response Re Examples 1-3 of Notice ML20247A5841989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.Agenda & List of Attendees Also Encl ML20246M6491989-08-29029 August 1989 Forwards Amend 56 to License NPF-38 & Safety Evaluation. Amend Increases Frequency of Channel Calibrs from Quarterly to Monthly on Waste Gas Holdup Sys Explosive Gas Monitoring Sys ML20245J0021989-08-14014 August 1989 Confirms 890808 Conversation W/Rp Barkhurst Re Util Participation in NRC Impact Survey Scheduled for 891010 & Submits Info Re Survey ML20245L3311989-08-11011 August 1989 Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation IR 05000382/19890121989-08-11011 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-12.Excluding Incident 1,Violation 382/8912-02 Should Stand as Cited. Response W/Corrective Actions Requested within 30 Days ML20245J2451989-08-0909 August 1989 Advises That Requalification Exams Scheduled for Wk of 890911 Changed to Wk of 890905 to Accommodate New INPO Schedule Issued in May 1989 IR 05000382/19890051989-07-31031 July 1989 Discusses Insp Rept 50-382/89-05 on 890213-17 & Forwards Notice of Violation.No Addl Info Was Provided to Change NRC Position & Therefore Util in Violation of Requirements.Basis for NRC Determination of Violation Provided IR 05000382/19890061989-07-28028 July 1989 Ack Receipt of 890706 Supplemental Response Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-06 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20196E6931999-06-22022 June 1999 Forwards Corrected Ltr Re Changes to Rev 19 to Emergency Plan.Original Ltr Had Error in Subject Line ML20196E0831999-06-21021 June 1999 Forwards Insp Rept 50-382/99-12 on 990524-27.No Violations Noted.Purpose of Insp Was to Conduct Assessment of Emergency Preparedness Program ML20196D9941999-06-18018 June 1999 Forwards Insp Rept 50-382/99-11 on 990524-28.No Violations Noted ML20195J8091999-06-17017 June 1999 Forwards Safety Evaulation Re First 10-yr Interval Inservice Insp Relief Request for Plant,Unit 3 ML20196C8711999-06-15015 June 1999 Discusses Insp Rept 50-382/99-08 & Forwards Notice of Violation Re Unescorted Access Which Was Mistakenly Granted to Individual Whose Background Investigation Indicated That He Had Failed Prior Drug Screening with Another Employer ML20196F3721999-06-0909 June 1999 Corrected Ltr Forwarding Rev 19 to Emergency Plan ML20195G3711999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981223,which Transmitted Waterford 3 Steam Electric Station Emergency Plan,Rev 24,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20207E8541999-06-0303 June 1999 Forwards SE Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressurizer Safety Valves at Plant,Unit 3 ML20207G3441999-06-0303 June 1999 Forwards Insp Rept 50-382/99-09 on 990411-0522 & Notice of Violation.One Violation Identified & Being Treated as Noncited Violation C ML20207D3771999-05-27027 May 1999 Ack Receipt of 990401 & 0504 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-01 on 990303 ML20207A5121999-05-24024 May 1999 Refers to Which Responded to NOV & Proposed Imposition of Civil Penalty Sent by .Violations A,B & E Withdrawn & Violations C & D Changed to Severity Level IV ML20206U7851999-05-18018 May 1999 Forwards Insp Rept 50-382/99-06 on 990405-09.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML20206N6961999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S4411999-05-10010 May 1999 Forwards Insp Rept 50-382/99-05 on 990228-0410.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3841999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamental Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam,With Answer Key,Encl for Info.Without Encl ML20206K0951999-05-0606 May 1999 Discusses Insp Rept 50-382/99-08 Issued 990503 Without Cover Ltr Documenting EA Number & Subject Line Indicated NOV Which Was Incorrect.Corrected Cover Ltr Encl ML20206F4701999-05-0303 May 1999 Forwards Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Re Failure to Review & Consider Derogatory Access Authorization Background Info as Required by PSP Identified & Being Considered for Escalated Enforcement Action ML20206K1211999-05-0303 May 1999 Corrected Cover Ltr Forwarding Insp Rept 50-382/99-08 on 990405-07.One Violations Noted & Being Considered for Escalated EA ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M0561999-04-0909 April 1999 Forwards Insp Rept 50-382/99-04 on 990301-19.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20205J8781999-04-0505 April 1999 Forwards Insp Rept 50-382/99-02 on 990117-0227.No Violations Noted.Inspectors Determined That Six Violations Occurred & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20205J0901999-04-0202 April 1999 Informs That Info Submitted by & 970313 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) ML20205A4681999-03-26026 March 1999 Forwards Insp Rept 50-382/99-03 on 990308-12.Two Violations of Radiation Protection Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205A6141999-03-25025 March 1999 Forwards SE Accepting Request to Use Mechanical Nozzle Seal Assemblies (Mnsas) as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Application at Plant,Unit 3 ML20205F3311999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Plant,Unit 3 PPR Review,Which Was Completed on 990211.Performance at Plant,Unit 3 Was Acceptable ML20204E4941999-03-17017 March 1999 Discusses TSs Bases Change Re 3/4.4.1,3/4.6.1.7,3/4.6.3, 3/4.7.12 & 3/4.8.4.Forwards Affected Bases Pp B 3/4 4-1, B 3/4 6-3,B 3/4 6-4,B 3/4 7-7 & B 3/4 8-3 ML20207F1251999-03-0303 March 1999 Forwards Insp Rept 50-382/99-01 on 990125-29 & 0208-12 & Notice of Violations ML20203H8501999-02-17017 February 1999 Forwards SE Accepting Licensee 970701 Submittal of Second Ten Year ISI Program & Associated Relief Request for Plant, Unit 3.Nine Relief Requests Had Been Authorized Previously & Proposed Alternatives Remain Authorized ML20203D7211999-02-11011 February 1999 Forwards Request for Addl Info Re Licensee 970317 & 990111 Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Response Should Be Provided within 60 Days 1999-09-09
[Table view] |
See also: IR 05000382/1988013
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SEP 26 Il2
In Reply Refer To:
Docket: 50-382/88-13
Louisiana Power & Light Company
ATTN: J. G. Dewease, Senior Vice President
Nuclear Operations
317 Baronne Street
New Orleans, Louisiana 70160
Gentlemen:
Thank you for your letter of August 17, 1988, in response to our letter and
Notice of Violation dated July 18, 1988. We have reviewed your reply and find
it responsive to the concerns raised in our Notice of Violation. We will review
the implementation of your corrective actions during a future inspection to
determine that full cortpliance has been achieved and will be maintained.
Sincerely.
Onginal Sgad Sp
l'. J: CALLAN
L. J. Callan, Director
Division of Reactor Projects
cc:
Louisiana Power & Light Iompany
ATTN: G. E. Wuller, Ons ite
Licensing Coordinator
P.O. Box B
Killona, Louisiana 70066
Louisiana Power & Light Company
ATTH: N. S. Carns, Plant Manager
P.O. Box B
Killona, Louisiana 70066
Middle South Services
ATTN: Mr. R. T. Lally
P.O. Box 61000
New Orleans, Louisiana 70161
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Louisiana Power & Light Company
ATTN: R. F. Burski, Acting Manager
Nuclear Safety and Regulatory
Affairs
317 Baronne Street
P.O. Box 60340
New Orleans, Louisiana 70160
Louisiana Radiation Control Program Director
bectoDMB(IE01)
bec distrib. by RIV:
RRI R. D. Martin, RA
SectionChief(DRP/A) DRP
RPB-DRSS MIS System
Project Engineer, DRP/A RSTS Operator
RIV File D. Wigginton, NRR Project Manager
DRS Lisa Shea, RM/ALF
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August 17, 1988 W3P88-1270
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QA
U.S. Nuclear Regulatory Comission
ATTN: Document Control Desk
Washington, D.C. 20555
Subj ect: Waterford 3 SES
Docket No. 50-382
License No. NPF-38
NRC Inspection Report 88-13
In accordance with 10CFR Part 2.201, Louisiana Power & Light hereby submits
in Attachment I the responses to the Violations identified in Appendix A of
the subject Inspection Report.
If you have any questions concerning these responses, please contact
L.W. Laughlin, Site Licensing Support, at (504) 464-3499.
Very truly yours,
yd
R.F. ski
Manager
Nuclear Safety & Regulatory Affairs
RFB:TJG:ssf
Attachment
ec: * R.D. Martin, NRC Region IV/
J.A. Calvo, NRC-NRR
D.L. Wigginton, NRC-NRR
NRC Resident Inspectors Office
E.L. Blake
W.M. Stevenson
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ATTACHMENT 1
LP&L Responses to Violations Identified in Appendix A
of Inspection Report 88-13
A. VIOLATION NO. 8813-01
Inadequate Maintenance Work Instructions
Technical Specification 6.8.1.a requires written procedures to be esta-
blished, implemented, and maintained covering the applicable procedures
recommended in Appendix A of Regulatory Guide 1.33, Revision 2. February
1978.
Regulatory Guide 1.33 requires procedures appropriate to the circums'tances
for performing maintenance on safety-related equipment.
Procedure UNT-7-005, Revision 2 "Cleanliness Control," is an approved
procedure that requires cleanliness control requirements to be established
when opening emergency diesel generator air systems.
Contrary to the above, on May 11, 1988, control air valves were manipu-
lated, the starter system disconnected, and the start air system actuated
using work instructions that were not appropriate in that they did not
include these tasks and they did not require the implementation of clean-
linese controls.
This is a Severity Level IV violation.
RESPONSE
LP&L acknowledges that this incident was a Violation of the guidelines
of Regulatory Guide 1.33 in that the work instructions for replacing
control air interface check valve EGA-421B were not detailed enough
relative to the circumstances.
(1) Reason For The Violation
The requirements for dispositioning a condition as "Troubleshoot"
when the failure mechanism or the reason for a degraded condition
cannot be detected easily are provided in Plant Operations Admini-
strative Procedure UNT-05-015. "Work Authorization Preparation and
Implementation". Since specific guidance for determining where to
differentiate between troubleshooting and rework is not provided in
the procedure, a conscientious decision has to be made by maintenance
personnel when in the field performing routine maintenance under a
specific work authorization. Because troubleshooting involves a
logical sequence of events which is determined by the outcome of a
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previous step or action, specific troubleshooting instructions are
difficult to write in the planning process. In this incident, the
extent of work after valve replacement was not known or defined at ,
the time, so a statement to troubleshoot was included on the work
authorization in accordance with UNT-05-015.
The responsibilities and criteria for cleaning fluid systems and
associated components are provided in Plant Administrative Procedure
UNT-07-005, "Cleanliness Control". This procedure, which is based on
the guidance provided in Regulatory Guide 1.37 (Quality Assurance
Requirements for Cleaning of Fluid Systems and Associated Components
of Water-Cooled Nuclear Power Plants) and ANSI N45.2.1-1973 (Cleaning
of Fluid Systems and Associated Components for Nuclear Power Plants)
is written primarily to address fluid systems. Although the diesel
generator air system is listed as a Class "C" cleanliness system in
the attachment of UNT-07-005, the procedure does not realistically
address maintaining cleanliness in such an instrument and control
system. The inspection criteria detailed in the procedure are not
adequate for an instrument systems of such a small size Therefore,
maintenance personnel had the impression that the procedure did
not apply, as was the case cited in this inspection.
(2) Corrective Actions That Have Been Taken
Since the occurrence of this incident, a Maintenance Directive (No.
28) entitled, "Troubleshooting" was developed to provide guidance on
writing troubleshoot instructions and establishing limitations on
what can and cannot be done in the field on work authoritations
dispositioned as "Troubleshoot". The directive instructs Maintenance
personnel to contact their supervisor for clarification if it becomes
questionable as to whether or not a certain activity is allowed under
troubleshoot authority. The directive also points out that trouble-
shooting does not allow deviation from procedural requirements and
that complete and accurate documentation of all steps and actions
taken as well as observations noted is imperative.
With regard to cleanliness control during maintenance on instrument
and control tubing and air lines, Instrument and Control Planners
have been trained and instructed to include Cleanliness Control Forms
(Attachment 6.1 of UNT-07-005) into the work authorization packages
whenever breaking a system boundary.
(3) Corrective Actions To Be Taken
UNT-07-005 will be revised to include responsibilities for establi- '
shing and maintaining adequate cleanliness controls when performing
maintenance activities on instrument and control tubing.
Although not specifically part of the corrective actions for this
violation, it is worthwhile to note that beginning in September,
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1988, a pilot program entitled "Operation ZERO Deviations" will
be implemented at Waterford 3 in the areas of Operations, Mainte-
nance, Security, Heslth Physics and Chemistry. The intent of this
program is to emphasize procedure and work instruction compliance and
to instill in employees the importance of stopping work when neces-
sary as opposed to deviating from a procedure or instruction. This
program emphasizes management concern and efforts toward reducing
unauthorized procedure and work instruction deficiencies.
(4) Date When Full Compliance Will Be Achieved
UNT-07-005 will be revised by September 30, 1988.
B. VIOLATION 8813-02
Failure To Implement Quality Assurance Procedures
Criterion II of Appendix B to 10 CFR Part 50 states, in part, that a
quality assurance program shall be documented in procedures and carried
out in accordance with those procedures.
Quality Assurance Program Procedure QAP-012, Revision 6, "Corrective
Action," requires initiation of a Quality Notice when conditions adverse
to quality are identified.
Contrary to the above, Quality Assurance Inspection Report 88-012, dated
April 21, 1988, noted that several wires of hydrogen analyzer "A" had been
landed at the wrong terminal points and accepted by quality assurance
inspectors during the replacement of the hydrogen analyzer. No Quality
Notice had been initiated on this condition which is adverse to quality as
of June 15, 1988, when the NRC inspector reviewed the work documentation.
This is a Severity Level IV violation.
RESPONSE
LP&L acknowledges that this incident was a violation of criterion II
of Appendix B to 10CFR50 in that a Quality Notice (QN) should have been
issued in accordance with Quality Assurance Procedure QAP-012. "Corrective
Action" since a condition adverse to quality (incorrect wire terminations
that damaged equipment) existed.
(1) Reason For The Violation
Prior to April 20, 1988, terminations were made and verified by
QA Inspection to the Hydrogen Analyzer Sequencer Module. On April
20, 1988, during the performance of functional testing, damage to a
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transistor on a different module occurred. Upon troubleshooting, an
I&C technician found wires on the Hydrogen Analyzer Sequencer Module
to be incorrectly terminated. Subsequently, on April 21, 1988, the
following sequence of events took place: the work instructions were
revised to correctly terminate the Sequencer Module, the work was
completed per the revised work instructions and Quality Assurance
verified the rework and reterminations.
On April 22, 1988, the QA inspector learned from a cognizant member
of the Nuclear Operations Engineering Department that a design
construction package change (DCPC) was going to be issued to address
the wiring error. Based on the premise that the work instruction was
revised, the errors were corrected, a DCPC was to be issued and the
overall concerns were documented in Inspection / Observation Report
88-012,'which was dated April 21, 1988 but signed off by the inspec-
tor on April 22, 1988, the inspector believed that no further a'tions e
were warranted. Consequently, a QN was not issued by Quality
Assurance.
(2) Corrective Actions That Have Been Taken
Two QNs were issued on June 17, 1988 to document the errors made
during the implementation of SH 983. QN QA-88-075 was issued to
Operations QA for the inspection error and QN QA-88-080 was issued to
Nuclear Operations Engineering and Construction for the incorrect
wiring of the hydrogen analyzers. Corrective action taken by QA has
resulted in an emphasis by the Quality Inspection organization on
attention to detail involving inspections.
A training session on attention to details was presented to inspec-
tors on August 8, 1988. Inspectors were cautioned as to the
importance of recognizing, reviewing and understanding the inspection
requirements imposed on the work document. Inspectors were also
reminded to complete all the necessary steps when performing an
inspection. In addition, the ese of inspection observation reports
has been discontinued as a means of problem identification.
(3) Corrective Actions To Be_Taken ,
1
Quality Assurance personnel will undergo lessons Learned Training.
Emphasis will be placed on the importance of paying attention to
detail and utilizing the corrective action systems that are currently
in place.
(4) Date When Full Compliance Will Be Achieved
Lessons Learned Training will be completed by September 30, 1988.
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C. VIOLATION 8813-03
Failure To Identify And Correct Deficiencies
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Criterion XVI of Appendix B to 10 CFR Part 50 states, in part, that
measures shall be established to assure that conditions adverse to i
quality, such as deficiencies, are promptly identified and corrected,
and that the causes be determined and corrective action taken to l
preclude repetition. ,
i
Contrary to the above, NRC inspectors identified deficiencies in l
safety system operating procedures and/or component identification l
labeling during ten inspections performed from February 1, 1986,
through May 31, 1988. Again, on June 7, 1988, the NRC inspector !
identified procedural and component identification labeling !
deficiencies with the hydrogen analyzer system. Licensee management' l
has failed to establish adequate measures to independently identify, i
correct, and preclude repeated deficiencies with safety system !
procedures and component identification labeling. l
This is a Severity Level IV violation.
RESPONSE
LP&L acknowledges that this incident was a violation of Criterion XVI !
of 10CTR Part 50, Appendix B in that adequate corrective actions have
not been taken to preclude repeated deficiencies with safety system (
procedures and component identification labeling. l
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(1) Reason For The Violation j
Plant Administrative Procedure OP-100-004, "UNID/EQ Tagging of
Plant Components", delineates the method for replacement of i
Unique Identification (UNID)/ Environmentally Qualified (EQ) !
equipment tags and also provides the administrative requirements :
for installation of new UNID/EQ tags. UNID tags which are hung I
as part of a design change are the responsibility of the ,
department or group that implements the change. Since there are ,
no requirements to verify that tags are hung correctly or to use l
controlled drawings for ensuring proper placement of tags, j
inconsistencies in the hanging of UNID tags have resulted. !
(NOTE: The failure to implement the above requirements has !
resulted in the incorrect hanging of various tags on the Hydrogen L
Analyzer as was stipulated in this inspection report.)
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Additionally, for components which are identified as not having
UNID numbers, the method in place for assigning a UNID to a compo-
nent, ensuring the UNID tag is hung properly and notifying the
cognizant work groups of this type of situation is not sufficiently
integrated to ensure the elimination of the type of problem described
in the violation. The current approach for addressing these items,
which involves the use of several procedures by several different
groups, has proven to be unreliable. This condition coupled with the
lack of a formal program to identify, correct and preclude deficien-
cies with safety system procedures and component identification
labeling is the basis for the violation.
(2) Corrective Actions That Have Been Taken
In early 1988, the responsibility for trending was transferred from
the QA department to the Event Analysis, Reporting and Response'
(EAR &R) organization, which reports directly to the Plant Manager.
In May,1988, using the QA Trending Program as a baseline, the EAR &R
organization established the Nuclear Operations Trending Program.
This program, which broadens the scope of that which was previously
trended, provides a method for collecting, correlating and analyzing
j corrective action reports in efforts to identify potentially signifi-
cant trands. The Program is utilized for the review and analysis of
Licensee Event Reports (LERs), KRC Reports Quality Notices, Noncon-
forming Condition Identifications, Discrepancy Notices and other
reports which identify incidents or occurrences to determine apparent
and/or root cause.
Plant Administrative Procedure UNT-6-014. "Root Cause Determination
and Trending", was approved in August, 1988. The specific purposes
of this procedure are to establish the requirements for the evalu-
ation and investigation of an event or condition for root cause
determination and to provide a method for the categorization of root
causes and their trending criteria. An adverse trend will be identi-
fled for recurring deficiencies. By the use of an Adverse Trend
Report, an adverse trend, which will include a summary of the defi-
,
ciency, root causes and any recommendations, will be submitted to the
'
appropriate Department Head, Group Head and Assistant Plant Manager.
The Department Head, with approval by the Assistant Plant Manager,
will be responsible for determining the necessary corrective actions.
After completion of the corrective actions, the item will be trans-
mitted to EAR &R for closure. Implementation of this procedure will
provide a significant enhancement to the existing trending program.
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(3) Corrective /etions To Be Taken
OP-100-004 is being revised to specifically address the repeated
tagging concerns regarding improper installation of UNID tags.
To alleviate inconsistencies that currently exist on two forms,
the forms vill be consolidated into one. This form, the UNID Tag
Replacement Form, will be used to tequest, hang and verify proper
placement of UNID tags. This procedure will also be revised to
require an individual, when hanging or verifying a UNID tag, to
refer to the primary source document for ensuring that the tag is
correctly placed. A procedural requirement will be implemented
to ensure that labeling and/or tagging deficiencies found during
lineups will be appropriately documented so that the necessary
corrective actions will be performed. To ensure that separate
procedures are not utilized by various departments, a Plant
procedure will be developed to cover all aspects of UNID taggirg.
Additionally, to ensure completeness of lineups in safety
systems, the existing Procedure Review Checklist in
Administrative Procedure OP-100-013, "Writer's Guide For -
Operating Procedures", will be revised to require that
valve / breaker lineups be verified with appropriate documentation.
Implementation of these actions coupled with the performance of
ongoing detailed system walkdowns in accordance with Administrative
Procedure OP-10-001, "Duties and Responsibilities of Operators on
Duty", will provide assurance that the procedures for safety related
systems reflect the actual plant configuration to the maximum extent
possible.
The above actions will address the present violation. However, to
provide additional assurance that repeated deficiencies with safety
system procedures and component identification labeling are mini-
mized, Management has set an objective, which is scheduled for
completien by December 31, 1989, to have applicable system engineers
perform walkdowns of the accessible portions of safety systems using
design documentation.
(4) Date When Full Compliance Will Be Achieved
Procedures OP-100-004 and OP-100-013 vill be revised by
September 30, 1988.
Development of the new procedure for UNID tagging is scheduled
for completion by 0, a mber 31, 1988.
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