|
---|
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 ML20059K3601990-09-14014 September 1990 Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise 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 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 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 ML20247F2211989-09-0808 September 1989 Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62 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 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 ML20245L3311989-08-11011 August 1989 Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation 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 ML20247J8481989-07-27027 July 1989 Requests Util Address Encl Concerns Re 890321 Application for Amend to License NPF-38.Amend Would Replace Tech Spec on Control Room Air Conditioning Sys W/Four Specs on Air Filtration,Air Temp & Isolation & Pressurization ML20247K5751989-07-27027 July 1989 Forwards Insp Rept 50-382/89-20 on 890705.No Violations or Deviations Noted.One Unresolved Item Identified in Paragraph 2 of Encl Rept Re Review of Findings of Lab Failure Analysis & Licensee Planned Response Actions IR 05000382/19890071989-07-21021 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07.Requests Response Encompassing Issues Discussed in 890713 Telcon Re Violation 382/8907-02 ML20247L6931989-07-18018 July 1989 Forwards Insp Rept 50-382/89-17 on 890601-30 & Notice of Violation.Util Will Be Requested to Address Concerns on Administrative Guidance for Inoperable Support Sys Effect on Safety Sys Operability ML20247K6491989-07-17017 July 1989 Forwards Insp Rept 50-382/89-18 on 890626-30.Violations Noted.One Unresolved Item Identified in Paragraph 3 of Rept ML20246M9061989-07-14014 July 1989 Forwards Exam Rept 50-382/OL-89-01 Administered During Wk of 890515.All Candidates Passed Exams & Appropriate Licenses Issued 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] |
Text
.-_ _ _ - _ _ _ ___
.. ..-
'
,-
., 4
.
,
.
.InReply.Referio:. .
'
FEB 21 E 1 Docket:. 50-382/88-19 ^
Louisiana Power,S Light Compan o ATTN: ;J. G. Dewease, Senior Vice President -
Nuclear Operations 317 Baronne Street ;
New Orleans, Louisiana 70160 .
.
. Gentlemen:.
Thank 'you for 'your letters of September 26, 1988, and January 26, 1989,;
- in response to our letters.and Notice of. Violation dated August 25, 1988,'and LDecember 20, 1988. We have reviewed your supplemental response to Violations 382/8819-01 and 382/8819-02-and found it contained the additional information that was requested. We now consider it responsive'.to the concerns
. raised in our Notice of Violation dated August 25, 1988. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
Sincerely, Onginal Sigxd By:
L J. CALLAN L. J. Callan, Director Division of Reactor Projects cc:
Louisiana Power & Light Company ATTN: R. P. Barkhurst, Vice President
.
Nuclear Operations P.O. Box B K111ona, Louisiana 70066 Louisiana Power & Light Company ATTN: N. S. Carns, Plant Manager P.O. Box B Killona, Louisiana 70066
. Louisiana Power & Light Company ATTN: R. F. Burski, Manager, Nuclear Safety & Regulatory Affairs 317 Baronne Street P.O. Box 60340 New Orleans, Louisiana 70160 RIV:DRP/A Ah W D:Db ATHowell;df C:DRP/Ahk'n DDChamberlai LJCallan 2/gi/89 2/pl/89 2/d/89 (
8902280352 890221 .
PDR
'
O ADOCK 05000382 PDC
. . i
___ _ _ - - - - - - . - ---
_ . - - _ - - _ . - . _ _ - - - - - - - _ _ -
. .
<
.. .
.
,
Louisiana Pcwer.& Light. Company -2-Louisiana Power & Light Company 1
~ ATTN: L. W. Laughlin, Site ;
Licensing Support Superviso P.O. Box B
+ Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: G. M. Davis, Manager, Events '
Analysis Reporting & Response P.O. Box B Killona, Louisiana 70066
' Middle South Services ATTN:- Mr. R. T. Lally ;
P.O. Box 61000 New Orleans, Louisiana 70161 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 DRS(2)
D. Wigginton, NRR Project Manager.(MS: 13-D-18) Lisa Shea, RH/ALF
_____ ---__ _ -_- _ -_- -_- -_ _ _ _ __ _ ____ - _ _ L
- _ _ _
. , _
.
.
. .
.
- P. O. BOX 60340 LOUISI& AN POWER A / 317NEW L1GHT BARONNE STREET ORLEANS, LOUISIANA 70160 *
(504) 595-3100 U1 ONIVSNU January 26, 1989 W3P89-0011 A4.05 QA U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 9{'
ip
-
M@(MllNII-
-
! :$
Washington, D.C. 20555 l g3l@
Subject: Waterford 3 SES ,,
Docket No. 50-382 License No. NPF-38 Violations 8819-01 and 8819-02, Supplemental Information References: LP&L Letter No. W3P88-1800 dated 09/26/88 from R.F. Burski i to U.S. Nuclear Regulatory Commission NRC letter dated 12/20/88 from L.J. Callan to J.G. Dewease Gentlemen:
Louisiana Power & Light hereby submits the following information on the subject violations as a supplement to the responses that were provided in Reference This information, which is contained in Attachment 1, addresses the concerns expressed in Reference 2 vith regard to the lack of including, in the original responses, the corrective steps taken to avoid further violation Also being provided, in Attachment 2, is a revised copy of the original responses for Violations 8819-01 and 8819-02. You will note that a revision bar has been placed in the margin to indicate the area where the supplemental information has been adde If you have any questions concerning these responses, please contact T.J. Gaudet at (504) 464-3325. N Ver uly yours,
-
R . Burski nager uclear Safety & Regulatory Affairs l
! RFB:TJG:ssf Attachments cc: R.D. Martin, J.A. Calvo, D.L. Wigginton, NRC Resident Inspectors Office, E.L. Blaka, W.M. Stevenson I
o c7 no n o ni <( , __ "AN EQUAL OPPORTUNITY EMPLOYER"
__?_- N___N __
_ _ ____
. .
. .. , Attachmsnt to
" *
W3P89-0011
Page 1 of'2 ATTACHMENT 1 Supplemental Information For Violations 8819-01 and 8819-02 VIOLATION NO. 8819-01: Failure To Report To NRC NRC CONCERN: No corrective action was listed to preclude future instances of failing to satisfy reporting requirement RESPONSE: As documented in LP&L Letter W3A89-0104 dated January 23, 1989, the Events Analysis Reporting and Response (EAR &R) Manager discussed the details of this violation with members of his staff to advise them of
'the importance of adhering to reporting requirements when reviewing plant event Also, subsequent to the issuance of the violation, LP&L 1) placed the NRC Resident Inspector for Waterford 3 on distribution for all Potential' Reportable Events (which includes the initial deportability determination) and 2) contacted the NRC-NRR Project Manager for Waterford 3 (and as necessary will contact in the future) when management felt it prudent to do so in situations where questions remained about reporting requirements after internal reviews had been performe It is also noteworthy of mentioning that both the Vice President-Nuclear and the Plant Manager-Nuclear has counselled the current EAR &R Manager to be more sensitive and solicitous of the deportability opinions of others and to avoid the concerns of the pas Based on the above information, LP&L feels that sufficient actions have been implemented to prevent a recurrence of a violation for failing to satisfy reporting requirement II. VIOLATION NO. 8819-02: Failure To Follow Procedure OP-4-020 NRC CONCERN: Your response did not address what was done to assure that operators will follow procedures in the futur RESPONSE: In August, 1988, the individuals responsibit for the violation were cautioned in the importance af acknowledging Bypassed and Inoperable Status Indication System indicators as well as were reminded of the importance in complying with procedures. Although this action occurred prior to the issuance of the violation response (which was issued September 26, 1988), LP&L chose not to include a discussion of it in the response since documentation to validate such action was not available. [ Note: This information was provided to the Resident Inspector on October 3, 1988].
- - - _ _ _ _ - _ - _ -
- - - _ - - - _ -
. .
, , ,,
-Attschm2nt to
'
W3P89-0011'
'
Page 2 of 2 Subsequently, LP&L Letter W3089-0019 was issued to document the counselling of the responsible individuals. Also, in efforts to bring this matter t the attention of operations personnel and thereby ensure that this type. of' violation does not recur, a briefing on the procedure violation, to include a discussion of the corrective actions implemented, was held on January 13, 1989 during a shift supervisors'
meeting.
l Based on the above information, LP&L feels confident that a recurrence of this type of violation should be prevented in the futur :
,
i i
l l
I l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ;
__ - _ _ _ - - _ _ .
. .
'
. . ,
Attachmsnt to
'
W3P89-0011 Page 1 of 7 ATTACHMENT 2 Revision 1 to the LP&L Responses for Violations 8819-01 and 8819-02 Identified in Appendix A of Inspection Report 88-19 VIOLATION NO. 8819-01 Failure To Report To NRC 10 CFR 50.73(a)(1) states, in part, that the holder of an operating license for a nuclear, power plant shall submit a Licensee Event Report (LER) for any event of the type described in this paragraph within 30 days after the discovery of the even Attachment 6.5 of LP&L Administrative Procedure UNT-6-010, Revision 4,
" Event Notification and Reporting," requires, in part, an LER as described above to be submitted when there was any operation or condition prohibited by the plant's Technical Specification (TS) or if an event or condition during operation results in the nuclear power plant being in a condition that was outside the design basis of the plan Contrary to the above, the staff identified four examples where the licensee failed to comply: Until April 18, 1988, the licensee failed to issue an LER I identifying a condition found on April 2, 1987, where nonsafety electrical circuits were not separated from safety circuits using double circuit breakers in accordance with NRC Regulatory Guide 1.75 as committed in the FSAR. This was a condition that was {
outside the design basis of the plan . Until April 18, 1988, the licensee failed to issue an LER l identifying conditions discovered on August 19, 1987, where Gas !
Decay Tank sampling was not performed as required by TS Table j 3.3-13. As a result, the plant was in a condition prohibited by 1 the T . Until April 18, 1988, the licensee failed to issue an LER identifying conditions discovered on October 21, 1987, where Containment Atmosphere Purge Isolation Valves CAP-103 and CAP-205 had exceeded the stroke time periodicity specified by TS 4. and 4.0.5. As a result, the plant was in a condition prohibited by the T . Until July 11, 1988, the licensee failed to issue an LER identifying conditions discovered on May 17, 1988, where Snubber SISR-1352 was found missing from a shutdown cooling line that was required to be operable per TS 3.7.8 and 3.9.8.2 while the plant was being refueled. As a result, the plant was in a condition prohibited by the T This is a Severity Level IV violati l i
- _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ - .
__ _ _ _ _ - _ _ _
. .
.
.
Attechmtnt to
" '
W3P89-0011
'
Page 2 of 7 RESPONSE
! LP&L admits this violation in that LERs for each of the above noted events should have been submitted in accordance with 10CFR50.73(a)(1)
l since conditions that were either outside the design basis of the
' plant or were prohibited by the TSs existe (1) Reason For The Violation Item 1 addresses the nonreporting of a failure to meet safety to nonsafety electrical distribution separation criteria that was identified on April 2, 1987. The baais for not submitting an LER was strictly due to an oversight on the initial deportability determination which was dated April 6, 1987. On March 23, 1988, the deportability determination was subsequently revised and LER 87-029 was issued on April 18, 1988 accordingl . Item 2 cites the failure to submit an LER within 30 days from discovery of a missed Waste Gas Decay Tank sample on August 19, 1987. It was believed, prior to expiration of the 30 day limit, that the 25% surveillance extension of Technical Specification (TS) 4.0.2 applied to TS Limiting Condition for Operation (LCO) time requirement Consequently, the event was determined to be not reportabl On April 18, 1988, a voluntary report (LER 87-030) was submitted which discussed in detail how plant staf f made the deportability determination. It has since been learned that the 25% extension of TS 4.0.2 does not apply to LCO time limit . Item 3 identified the failure to submit an LER within 30 days from discovery of missed stroke test surveillance of two Containment Atmosphere Purge (CAP) valves in accordance with TS 4.0.5. Prior to expiration of the 30 day limit, the event was determined to be not reportable. The basis for this determination was that by declaring valve CAP 205 inoperable, which necessitates classifying leakage through valves CAP 103 and CAP 104 as bypass leakage, leakage would still remain well within the allowable limi (It is important to note that CAP 103 was tested within TS 3.6. LCO time limits.)
On April 18, 1988, a voluntary report (LER 87-031) was submitted which discussed in detail how plant staff made the deportability determination. It has since been understood, which was not apparent at the time of the initial deportability determination, that missed TS 4. surveillance constitute a condition prohibited by TS _ - _ - _ _ _ - _ - -
--___ __
. .
. . .
Attachtsnt to
'
'
W3P89-0011
Page 3 of 7 4. The last Item addresses the issuance of LER 88-017 on July 11, 1988, for the identification of a snubber missing from the Shutdown Cooling System that was discovered on May 17, 198 In the initial deportability determination dated May 19, 1988, the event was determined to be reportable as a condition prohibited by the TSs. The basis for this determination was the TS requirement for both Shutdown Cooling Trains to be operable when water level above the reactor pressure vessel flange is lowered below 23 feet, which occurred on May 12, 1988. Snubber SISR 1352 was not discovered as being removed (inoperable) until May 17, 198 Based on an engineering evaluation which determined that shutdown cooling system operability was not affected by the removal of the snubber, the deportability determination was subsequently revised (Revision 1) on June 2, 1988 to classify the event as not reportabl It is noteworthy to mention that a recommendation was made in the evaluation to remove snubber SISR 1352 during the next refueling outage and a modification has since been approved to do s Revision 2 to the deportability determination was issued on June 21, 1988 reclassifying the event as a reportable LER due to a condition prohibited by TS The basis for reclassifying the event as reportable was that even though SISR 1352 is not required for Shutdown' Cooling System operability, the snubber was still under the control of TS 3.7.8 thereby requiring it to be operabl Since Revision 2 to the deportability determination was dated after the expiration of 30 days from the event discovery, it was necessary to use the guidance provided in NUREG-1022, Supplement 1 (" Licensee Event Report System") to develop an adequate timeframe for drafting and approving an LER. Section 14 of NUREG-1022 states, in part, "The LER must be submitted within 30 days of discovery of the event or condition that is reportable." Accordingly, LER 88-017 was issued on July 11, 1988, which was within 30 days from Revision 2 to the event deportability determination, when the condition was discovered to be reportable. Since Section 14 of NUREG-1022 also states that "If the LER is not submitted with 30 days from the event date, explain the relationship between the event date, discovery date, and report date in the LER text", this information was explicitly provided in LER 88-01 The deportability determinations associated with this event represent a good faith interpretation of reporting regulations and guidelines by plant staff. In this particular incident, the issue of deportability was initially believed to be the operability of the Shutdown Cooling System, which was satisfactorily resolved. However, the snubber was still administrative 1y controlled by TSs which was not considered until later.
_ _ - _ _ _ _ _ _ _ _ . _
___-____-__
.
, , ,
Attachmsnt to
- -
.W3P89-0011
-
Page 4 of 7 (2) Corrective Actions That Have Been Taken All four items have been reported in the proper LER forma As documented in LP&L Letter W3A89-0104 dated January 23, 1989, the Events Analysis Reporting and Response-(EAR &R) Manager discussed the details of this violation with members of his staff to advise them of the importance of adhering to reporting requirements when reviewing plant events. Also, subsequent to the issuance of the violation, LP&L 1) placed the NRC Resident Inspector for Waterford 3 on distribution for all Potential Reportable Events (which includes the initial deportability determination) and 2) contacted the NRC-NRR Project Manager for Waterford 3 (and as necessary will contact in the future) when management felt it prudent to do so in situations where questions remained about reporting requirements after internal reviews had been performe It is also noteworthy of mentioning that both the Vice President-Nuclear and the Plant Manager-Nuclear has counselled the current EAR &R Manager to be more sensitive and solicitous of the deportability opinions of others and to avoid the concerns of the pas Based on the above information, LP&L feels that sufficient actions have been implemented to prevent a recurrence of a violation for failing to satisfy reporting requirement (3) Corrective Actions Which Will Be Taken Revisions to LER 87-030 and LER 87-031 will be submitted by October 15, 1988, to appropriately classify them as conditions prohibited by TSs. [ Note: Revisions to LER 87-030 and LEF 87-031 were actually submitted September 30, 1988 in LP&L Letter Nos. W3A88-0109 and W3A88-0110, respectively.]
(4) Date When Full Compliance Will Be Achieved Based on the above information, LP&L is currently in full complianc !
i
_ _ _ _ - _ - _ _ _ - _ _ _ _ _ _ _
- ________ _ _ _ _______
. .
.
- a . Attachment to
W3P89-0011 Page 5 of 7 B. VIOLATION NO. 8819-02 Failure To Follow Procedures Technical Specification 6.8.1.a requires, in part, the implementation of procedures covering activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2, including the procedures for abnormal, off-normal, or alarm condition The licensee's Operating Procedure OP-4-020, Revision 0, " Bypassed and Inoperable Status Indication Systems," requires monitoring of safety equipment status by way of computer and requires operator acknowledgement of annunciator alarms in evaluation of systems that have been computed to be inoperabl Contrary to the above, the inspectors observed alarming annunciators l in the control room which had not been acknowledged on February 5 and 9, 198 In addition, on February 8 and 10, 1988, the inspectors observed annunciators alarm (Containment Isolation and Emergency Feedwater related, respectively) which were not acknowledged as specified by procedur This is a Severity Level V violatio RESPONSE LP&L acknowledges that a violation of TS 6.8.1.a existed when operators failed to acknowledge Bypassed and Inoperable Status Indication System indicator actuations in accordance with OP-4-02 (1) Reason For The Violation The purpose of the Bypassed and Inoperable Status Indication System (BISIS), as delineated in Operating Procedure OP-4-020, is to provide the operator with a supplemental means of identifying bypassed and inoperable safety system conditions. The system is not designed to be used in place of plant administrative procedures when determining bypassed or inoperable equipmen Nonetheless, when an operator sees that a system is computed as inoperable, his actions in accordance with OP-4-020 are to initially acknowledge the signal (by depressing the applicable pushbutton), then evaluate the status of the equipment which caused the computer to illuminate an indicator. Based on the importance of ensuring that equipment is properly operating, the more logical sequence for an operator to follow is to first determine the validity of a BISIS indicator by evaluation; then, acknowledge the indication if valid or insert an appropriate value for the point in question, log the required information on the BISIS Point Deviation Sheet (Attachment 8.5 of OP-4-020) and
.
generate a condition identification (CI) accordingly if invali l l
_- ___________ _
_ _ _ _ _ - _ _ _ _ _ _ _ _ _
. .
'
. . .
Attacharnt to
W3P89-0011-
'
Page 6 of 7 During the incidents cited in the Inspection Report, the operators, acting on plant knowledge and past experiences with invalid indications, chose to evaluate the equipment status prior to acknowledging the BISIS indicator which resulted in-the procedure violation. It is important to note that the fact that the operators were aware of the status of the monitored systems in question, that the systems were verified as being operable, was substantiated by the NRC Inspectors (as noted in Inspection Report 88-200). Also, since'the invalid indications were spurious in that the appropriate values reappeared prior to I having them inserted, no further action was required by the operato (2) Corrective Actions That Have Been Taken ,
,
Effective August 19, 1988, Operating Procedure OP-4-020 was revised to change the sequence in which an operator responds to a BISIS indication. The current sequence, which is a more realistic and logical approach for responding to such indications, is as follows: first, when an operator sees that a system is computed as inoperable, he should evaluate the status of the equipment that caused the BISIS indication as soon as possible; then, if valid, the operator acknowledges the signal by depressing the associated pushbutton or if invalid, he generates a CI to correct the proble In August, 1988, the individuals responsible for the violation were cautioned in the importance of acknowledging Bypassed and Inoperable Status Indication System indicators as well as were reminded of the importance in complying with procedures. (LP&L Letter W3089-0019 was issued to document the counselling of the responsible individuals.) Also, in efforts to bring this matter to the attention of operations personnel and thereby ensure that this type of violation does not recur, a briefing on the procedure violation, to include a discussion of the corrective actions implemented, was held on January 13, 1989 during a shift supervisors' meetin Although not specifically part of the corrective actions completed to date for this violation, it is important to note that System Engineering performed an evaluation of the BISIS logic. The purpose of this evaluation was to identify improvements that will reduce the number of invalid indication (Note: The detailed results of this evaluation are documented in Letter W3E88-0257 dated 10/28/88.)
_ _ _ _ _ _ _ _ _ _ - - - - - - _ -__
-- - _ . _ - . _ - .. -. - - __
- .-.
. . ,.
.
. . , ..
Attachm:nt to
'
"" *
- W3P89-0011
'
Page 7 of 7
~
(3). Corrective Actions Which Will Be Taken Based on the above information, LP&L feels confident that a
~
recurrence of this type of violation should be prevented in the
' future. (4) Date When Full Compliance Will Be Achieved LP&L is currently in full' complianc l l
- _ _ - _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ . - _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _