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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:INCOMING CORRESPONDENCE
MONTHYEARML20217L0101999-10-18018 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 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 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 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 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 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 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-1999-010, 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 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 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 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 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 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos 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 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 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 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 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 ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits1999-06-24024 June 1999 Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits ML20196G5731999-06-24024 June 1999 Forwards Operator Licensing Exam Outlines Associated with Exam Scheduled for Wk of 991004.Exam Development Is Being Performed in Accordance with NUREG-1021,Rev 8 ML20212J4121999-06-23023 June 1999 Responds to NRC Re Reconsideration of EA 98-022. Details Provided on Actions Util Has Taken or Plans to Take to Address NRC Concerns with Ability to Demonstrate Adequate Flow Availability to Meet Design Requirements ML20196E9371999-06-22022 June 1999 Forwards Revs Made to EP Training Procedures.Procedures NTC-217 & NTC-217 Have Been Deleted.Procedure NTP-203 Was Revised to Combine Requirement Previously Included in Procedures NRC-216 & NTC-217 ML20196A1021999-06-17017 June 1999 Provides Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Per 990513 Request of NRC Project Manager ML20195F3671999-06-0909 June 1999 Forwards Rev 21,Change 0 to EP-001-010, Unusual Event. Rev Reviewed in Accordance with 10CFR50.54(q) Requirements & Determined Not to Decrease Effectiveness of Emergency Plan ML20195C7801999-06-0303 June 1999 Submits Response to Violations Noted in Insp Rept 50-382/99-08.Corrective Actions:All Licensee Access Authorization Personnel Were Retrained Prior to Completion of Insp ML20195C2951999-05-28028 May 1999 Forwards Annual Evaluation of Changes & Errors Identified in Abb CE ECCS Performance Evaluation Models Used for LOCA Analyses.Results of Annual Evaluation for CY98 Detailed in Attached Rept,Based Upon Suppl 10 to Abb CE Rept ML20195C0241999-05-28028 May 1999 Notifies NRC of Operator Medical Condition for Waterford 3 Opertaor Sp Wolfe,License SOP-43723.Attached NRC Form & Memo Contain Info Concerning Condition.Without Encls ML20196L3281999-05-24024 May 1999 Informs That Entergy Is Withdrawing TS Change Request NPF-38-205 Re TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection Submitted on 980629 ML20206S4691999-05-17017 May 1999 Requests Waiver of Exam for SRO Licenses for an Vest & Hj Lewis,Iaw 10CFR55.47.Both Individuals Have Held Licenses at Plant within Past Two Year Period,But Licenses Expired Upon Leaving Util Employment.Encl Withheld 05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.31999-05-14014 May 1999 Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3 ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J1471999-05-0606 May 1999 Requests That Implementation Date for TS Change Request NPF-38-211 Be within 90 Days of Approval to Allow for Installation of New Monitoring Sys for Broad Range Gas Detection Sys ML20206J1721999-05-0606 May 1999 Notifies That Proposed Schedule for Plant 1999 Annual Exercise Is Wk of 991013.Exercise Objective Meeting Scheduled for 990513 at St John Baptist Parish Emergency Operations Ctr ML20206G8021999-05-0404 May 1999 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-382/99-01.Licensee Denies Violation as Stated.Change Made Is Denoted by Rev Bar & Does Not Materially Impact Original Ltr ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20205T2531999-04-22022 April 1999 Forwards LER 99-S02-00,describing Occurrence of Contract Employee Inappropriately Being Granted Unescorted Access to Plant Protected Area ML20205R2611999-04-20020 April 1999 Forwards Rev 19 to Physical Security Plan,Submitted in Accordance with 10CFR50.54(p).Plan Rev Was Approved & Implemented on 990407.Rev Withheld,Per 10CFR73.21 ML20205Q3241999-04-16016 April 1999 Submits Addl Info Re TS Change Request NPF-38-215 for Administrative Controls TS Changes.Appropriate Pages from New Entergy Common QA Program Manual Provided as Attachment to Ltr 1999-09-07
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Text
l g Enttrgy Operztlons, Inc.
t a Killona. LA 70066 Tel 504 739 6242 l James J. Fisicaro l Safety Waterford 3 W3F1-96-0143 A4.05 PR September 5,1996 l l
U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk Washington, D.C. 20555 )
Subject:
Waterford 3 SES Docket No. 50-382 l License No. NPF-38 -
NRC Inspection Report 96-10 ,
Reply to Notice of Violation l Gentlemen:
In accordance with 10CFR2.201, Entergy hereby submits in Attachment 1 the I response to the violations identified in Enclosure 1 of the subject inspection Report.
1 The staff expressed concerns with the two violations in the cover letter of the inspection Report. Regarding the concern of the use of Plant Monitoring Computer (PMC) alarms, Waterford 3 (W3) agrees the PMC alarm function should not have been discontinued without ensuring that appropriate compensatory measures were in place. Although compensatory measures were not in place, efforts were being made to address the alarm screen discrepancies. It is our belief that Operations has accepted and maintained ownership of this process while continuing to operate Waterford 3 in a safe and conservative manner. Waterford 3 agrees with your concern regarding adherence to radiological requirements and W3 concurs that adherence to radiological requirements is important to assure personnel radiation protection and an effective ALARA program. '
l
+, ' , Q i 96o9110210 960905 i PDR ADOCK 05000382 i G PDR
1 NRC Inspection Report 96-10 Reply to Notice of Violation W3F1-96-0143 Page 2 September 5,1996 If you have any questions concerning this response, please contact me at (504) 739-6242 or Tim Gaudet at (504) 739-6666.
Very truly yours, O
&c J.J. Fisicaro Director Nuclear Safety JJF/WDM/ PRS /tjs Attachment cc: L.J. Callan (NRC Region IV)
C.P. Patel (NRC-NRR)
R.B. McGehee N.S. Reynolds NRC Resident inspectors Office
l Attachment to W3F1-96-0143 Page 1 of 7 ENTERGY RESPONSE TO THE VIOLATIONS IDENTIFIED IN ENCLOSURE 1 OF INSPECTION REPORT 96-10 VIOLATION NO. 9610-01 l Technical Specification 6.8.1.a requires, in part, that written procedures shall be implemented covering the applicable procedures recommended in Appendix A of l Regulatory Guide 1.33, Revision 2, February 1978. Appendix A, Sections 1 and 7, l
- require that the licensee have Administrative and Radioactivity Control Procedures.
l l 1. Administrative Procedure OP-100-001, " Duties and Responsibilities of i l Operators on Duty," Revision 10, Step 4.4.9 required, in part, to evaluate and l l acknowledge all computer and annunciator alarms received. )
l . \
l Contrary to the above, from November 5,1995 to May 23,1996, Procedure !
OP-100-001 was not properly implemented in that computer alarms were !
consistently not acknowledged or evaluated by the on-shift operations crew'. )
This is a Severity Level IV violation (Supplement I) (50-382/9610-01).
RESPONSE l (1) Reason for Violatica .
Entergy believes the root cause of the violation is inadequate administrative controls in that compensatory measures were not established while awaiting permanent resolution to identified problems with the new Plant Monitoring Computer (PMC) alarm screen.
The Waterford 3 PMC was replaced during Refuel 7 (RF7) under Design Change 3374. In the months leading up to the installation, a team from Waterford 3 consisting of personnel from Operations, Reactor Engineering and Performance (RE&P), Design Engineering, and Modification Control monitored the progress of the project. In January of 1995, the team was able )
to see Waterford 3's specific alarm screen for the first time. Several problems ;
were noted that were considered unacceptable by the team. However, I because it was important to ship the PMC to Waterford 3 for a parallel run
- with the existing PMC, the decision was made to send the unit in its present
! condition and proceed with the implementation. Work to resolve the alarm
{ screen problems was an ongoing process throughout the i.mplementation, and j accelerated towards total resolution during the second quarter of 1996.
l ,
I I l'
1 Attachment to W3F1-96-0143 Page 2 of 7 Following the parallel run and installation, the decision was made to start up the plant coming out of RF7 with the PMC alarm screen still not accepted by Operations or RE&P. Continuous contact was made with the vendor in an attempt to correct the problems. It was determined that the new screen would i
not be useful as an operator aid to monitor alarmed parameters. Because of
, the vast number of computer points that were alarming, the PMC audible alarm became a hindrance to the Control Room operators, and was disabled.
i OP-100-001, Duties and Responsibilities of Operators on Duty, Step 4.4.9, was written under the assumption that PMC alarms would be valid and provide useful information to the operators. OP-100-001, Section 5.6, Plant j Tour, instructs Operations personnel to make frequent tours of the unit to ensure that plant equipment is functioning in its expected manner. Control Room annunciators alert operators to abnormal conditions with vital plant equipment. Although Operations Management is confident that plant equipment was being sufficiently monitored, adequate compensatory measures were not established while awaiting permanent resolution to the PMC alarm screen problems.
In January of 1996, it was discovered that the vendor's alarm system package was undergoing a revision that would more closely meet Waterford 3's needs.
Subsequent contact with the vendor resulted in an agreement to support the alarm screen upgrade and an upgrade path was mapped out This upgrade will be delivered in three phased revisions and is scheduled for completion by October 31,1996.
(2) Corrective Steps that Have B_een Taken and Results Achieved Standing Instruction 96-10 was issued to Operations personnel with the following information:
The enhancement for the PMC Alarm Screen will begin the week of July 15. This enhancement will be performed in four stages and completed in October. In the interim, the following will be done:
- 1. Keep two alarm screens active.
- 2. Frequently (several times per hour) observe the alarm screens to monitor for changing plant / equipment conditions.
- 3. Have the onshift PMC technicians clear the alarm back:og approximately every two hours.
The following changes were made to OP-100-001 so that the wording more I closely resembled the intention of the procedure:
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Attachmsnt to W3F1-96-0143 Page 3 of 7
- Step 4.4.9: Evaluate and acknowledge all annunciators received.
Respond in accordance with Step 5.7, Annunciators.
. Step 4.4.10: Frequently monitor the plant computer alarm screen for changing plant conditions and promptly acknowledge and evaluate audible computer alarms. 1 Revision 1 of the PMC alarm upgrade accomplished the following:
. Added a two character date code to each record.
- Added column headers to the red divider line on the alarm screen.
l e Replaced MORE ALARMS message with a count of unacknowledged l alarma.
Reduced tha font from double size to normal size, e Changed tw ACKNOWLEDGED area from 16 to 20 records.
- Changed the UNACKNOWLEDGED area from 4 to 14 records.
Revision 2 of the PMC alarm upgrade accomplished the following:
. Acknowledged alarms which return to normal will automatically be deleted from the screen
. If an acknowledged alarm point has an alarm cutout defined (i.e.,
Bearing temp alarm only if the pump is running) and the cutout point transitions to the alarm inhibit state, the alarm point will automatically be cleared from the screen. 1 e The audible alarm will be reinstated.
. Acknowledged alarms which undergo an alarm quality change will be automatically cleared from the alarm system and reposted with a new l alarm message.
l . All but valid alarms conditions will be deleted.
A visual cue will be added to indicate the presence of critical alarms not visible on the alarm screen (page full conditions).
(3) Corrective Steps Which Wi!I Be Taken to Avoid Further Violations Subsequent revisions will accomplish the following:
. Operators will be able to lock unacknowledged alarms to protect them j from being acknowledged until they are released.
j e A " hot key" will be provided to allow return to the first page of the alarm j screen.
j e Points in the alarm backlog will be able to be pulled up either by j description or by point identification (ID).
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Attachm*nt to W3F1-96-0143 Page 4 of 7 l
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- Alarms will be posted as they clear from the alarm screen to the i message backlog in first-in, first-out order.
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- A message / alarm backlog file will be added.
- Point ID's which go to a " bad" quality will give a single occurrence alarm to alert the operators.
l i (4) Date When Full Compliance Will Be Achieved l Based on the interim measures in place, Standing Instruction 96-10 and the I changes made to OP-100-001, Waterford 3 is in full compliance. The final upgrade for the alarm package is scheduled for completion by October 31, 1996.
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Attachment to W3F1-96-0143 i Page 5 of 7 VIOLATION NO. 9610-03 l
- Technical Specification 6.8.1.a requires, in part, that written procedures shall be i implemented covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Appendix A, Sections 1 and 7, require that the licensee have Administrative and Radioactivity Control Procedures.
, Health Physics Procedure HP-001-152, " Labeling, Handling, and Storage of l Radioactive Material," Revision 10, Section 10.1, " Control of Radioactive Material within the RCA (Radiologically Controlled Area)," required, in part, that tools and equipment be smeared by health physics prior to storing and that contaminated tools and equipment not in a posted contaminated area be packaged in a yellow bag and labeled CAUTION RADIOACTIVE MATERIAL.
l Health Physics Procedure HP-001-101, "ALARA Program implementation,"
! Revision 10, Section 4.10.5 required, in part, that individuals comply with l warning signs.
- Contrary to the above
l a. As of June 11,1996, Procedure HP-001-152 was not properly implemented in
! that contaminated operations department tools and equipment were not i smeared prior to storage and were not packaged in a yellow bag and labeled CAUTION RADIOACTIVE MATERIAL. l l
l b. On July 18,1996, Procedure HP-001-101 was not properly implemented in I that licensee personnel did not comply with warning signs. Specifically, two individuals were observed drinking in a radiologically controlled area even though warning signs indicated that no drinking was allowed.
This is a Severity Level IV violation (Supplement 1) (50-382/9610-03).
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RESPONSE
1 (1) Reason for the Violation
- a. The root cause for Example "a" of the violation was personnel error in that contaminated Measuring and Test Equipment (M&TE) was not labeled and was stored in an unposted locker in breach of HP-001-152,
" Labeling, Handling, and Storage of Radioactive Material."
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! b. The root cause for Example "b" of the violation was personnel error in
! that a questioning attitude was not utilized with respect to thirst j quenchers being located in an RCA considering the postings as well as i
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Attachm:Intto W3F1-96-0143 Page 6 of 7 radiation worker training prescribing, "No Eating, Smoking Or Drinking" in the RCA. The contributing factor was the physical location of the cooler of consumable liquids in the RCA with accompariying cups, and without adequate labeling to indicate for Emergency First Aid Team (EFAT) use only. Thirst quenchers are only staged in the RCA during
- outages when heat stress is a concern. ,
(2) Corrective Steps That Have Been Taken and the Results Achieved
- The following corrective steps have been taken to prevent recurrence of this
- violation are: l l a. Condition Report CR-96-0906 was immediately prepared to address !
the occurrence. The specific individual (s) involved could not be identified; therefore, procedural expectations were reviev'ed and communicated to Operations personnel through the Daily Instructions. ,
On August 15,1996, CR-96-1264 was initiated to address a similar event (eight gages were placed in Operations M&TE locker without accompanying fitting caps or taping).
- b. The cooler of thirst quencher with associated cups was immediately removed from the RCA. On July 27,1996, a lockable chest container
- was procured for storage of thirst quencher in the RCA, and it was 2
labeled "EFAT USE ONLY." Individual containers of quencher will be 4
stored in the chest. To assure personnel cognizance, the condition report along with its resolution was presented to personnel at the Safety meetings held August 28 and 29,1996.
(3) Corrective Steps Which Will Be Taken to Avoid Further Violations
- a. Shift Supervisors presented the requirements of HP-001-152 (with Health Physics assistance) to Operations personnel to assure adequate knowledge and deference for the procedural requirements regarding contamination and tooling. New locks are to be placed on the Operations M&TE lockers with the SS/CRS being responsible for and controlling personnel access to the lockers. This measure is intended to assist in early identification of individuals who have not been completely indoctrinated by the training.
- b. A guidance directive will be developed to address use of thirst quenchers in an RCA.
Attachment to W3F1-96-0143 Page 7 of 7 It is believed that the above corrective steps, addressing operations control, worker performance and supervision, are adequate to avoid further violations I
of this type.
(4) Date When Full Compliance Will Be Achieved Waterford 3 is in full compliance and the remaining actions described above in Section 3 will be completed by October 31,1996.
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