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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
[Table view] |
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W3F1-93-0374 l A4.05 M
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.,1 December 29,-1993 U.S. Nuclear Regulatory Commission $
1 ATTN: Document Control Desk Washington, D.C. 20555-. .
] 1
Subject:
Waterford 3 SES' ,
-Docket No. 50-382 i License No. NPF-38 NRC Inspection Report 93-28 ,'l!
. 1 a
Gentlemen: j Entergy' Operations, Inc. hereby submits in Attachment 1 the' responseto the- 3 emergency preparedness weaknesses documented in the subject Inspection: :
-Report. These responses are attached and include analysis of. the j weaknesses, description of corrective measures and schedules for 1 completing these actions as requested. .;
i If you_ have-any questions concerning' this response, please contact _
,q F.J-Englebracht, Emergency Planning & Administration Manager, 'at -(504)-.739- !
6607.
- Very truly yours, i
~d .
/- N
+ ny .i k!
. ski j
'i ._
tor j
. Nuclear Safety- .;
RFB/GCS/ssf :f Attachment /-
cc: ' J.L.L Milhoan- (NRC Region 'IV), D.L. WiggintonL(NRC-NRR),- U R.B. McGehee, N.S; Reynolds, NRC-Resident Inspectors Office j
'9401060137 931229-PDR--ADOCK 05000382- 9@ ,
. -G 'PDR: g; -
Attachment to
. W3F1-93-0374 Page 1 of 7 ATTACHMENT'l ENTERGY OPERATIONS. INC RESPONSE TO THE EMERGENCY EXERCISE WEAKNESSES DOCUMENTED IN INSPECTION REPORT 93-28 EAKNESS N0. 9328-01 The Technical Support Center staff did not aggressively pursue the identification of the source of the penetration leakage through the shield building ventilation' system to the plant stack or.its termination. At 1:41 p.m., identification of the release path was established as a priority for' ,
the Technical Support Center and the Emergency Operations Facility. While.
there was much discussion as to possible sources of the release, it was not' ,
until 2:51 p.m. that a team was dispatched to determine if leakage was occurring at suspected penetrations. Throughout the decision process, the Technical Support Center staff considered the possibility of- 3 overpressurizing the ventilation system plenum but did not attempt in.
i parallel to dispatch a leak search team or attempt to determine the ,
maximum plenum pressure should it become necessary to shutdown the shield .
building exhaust system. At 3:44 p.m., immediately prior to terminating i the scenario, . attempts had not been made to isolate the release nor had a E
decisive mitigation strategy been determined. ;
i '
It was not clear from discussions in the Technical Support Center that any assessment of core damage was being performed during the event. '
Discussions between the Operations Coordinator and the Health. Physics Coordinator indicated a concern that some core damage _had occurred, but- ll neither indicated that any assessment was being performed to confirm their -
opinions. It was not observed'that this concern was communicated to the Emergency Coordinator, who might have been able to dedicate resources to ;
initiate an assessment. The'0perations/ Engineering Coordinator in the l Emergency Operations Facility discussed with the Operations' Communicator'in- l the Technical Support Center the need for an assessment of core damage, but-there were no follow-up communications regarding the assessment. For ;i example, no one requested a Post' Accident Sampling System sample during the i L
exercise to help perform a core damage assessment. I The above' examples of nonaggressive assessment of plant ~ conditions and mitigation strategies were identified'as an exercise weakness. H i
d 4. Attachment to-I ,
W3F1-93-0374 Page.2 of 7 RESP 0 IGE -
(1) Analysis of the Weakness The lack of timely assessment of plant conditions and . identification
'of the release pathway is attributed to poor communications'among emergency response facilities, lack of clearly' defined. task.
l- assignments and responsibilities for completing task assignments and
!. timely follow-up.
With regard to communications, it appeared to the Entergy Operations,.
Inc. Drill Control Team that the Control Room staff was aware of the-release pathway, but that this information was not clearly-communicated, or understood, throughout the emergency response organization. In addition, the E0F engineering staff generated numerous ideas regarding the source of the ' release and ways to secure-it, but feedback from the TSC on these ideas was not provided to the EOF staff, and not actively pursued by the EOF staff.
Although many ideas were discussed in the TSC and EOF, it'would have been more effective if specific task assignments were generated with a specific lead engineer and a report back time assigned'to each.
This would have provided better trending and ownership of' mitigation strategies and assisted in providing overall. direction 'of response actions.
Several examples of lacking a . follow-up of good ideas were observed.
When Reactor Auxiliary Building increased. air activity was suspected, I
a team of Health Physics personnel could have been' assigned to look' for leaks and take air samples in the suspected areas. The EOF staff-requested the status of containment isolation several times, but.-
follow-up to provide this information back to the EOF was.not observed.
(2) Corrective Measures
-Two specific corrective actions are planned:
- 1. Lesson plans for. Control Room staff, TSC- Health Physics: Support -
personnel, TSC Operations Coordinator,-TSC Operations Communicator, TSC Engineering staff, TSC Supervisor, TSC :
Emergency Coordinator, EOF Health Physics Support personnel, E0F Operations / Engineering Coordinator, EOF Operations /_
Engineering Coordinator Assistant, EOF Engineering staff, EOF Director and Deputy EOF Director will be revised to incorporate a discussion of the accident assessment problems in the 1993
- i. annual exercise as lessons learned. This discussion will l
' Attachment to
... W3F1-93-0374 j Page 3 of 7 ,
l include emphasis on clear communications amo q facilities. and- j c clear and timely feedback, assignment and trw 'ng of tasks, development of' corrective action strategies anc 'horough l follow-up. of ideas.
- 2. The Emergency Planning Department will' incorporate the above~
lessons learned discussion 'in the annual tabletop p'rogram J during 1994. The department conducts a minimum of 4 tabletops a year for TSC, OSC,.and EOF positions. In addition, the
- Emergency Planning Department will address the lessons learned discussion in seminars with all Operations shifts in 1994- .
(3) Date When Full Compliance Will Be Achieved i Corrective Measure 1 will be completed by April 1,1994.
Corrective Measure 2 will be completed by December 14, 1994.
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...- Attachment to W3F1-93-0374 Page 4 of 7 ,
WE KNESS NO. 9328-02 The following problems with the approval and issuance of Protective Action Recommendations were observed by the inspectors in the Technical- Support '
Center:
The initial General Emergency notification made an erroneous Protective
- Action Recommendation of sheltering the 2-mile radius and evacuating 2 to 5 .
miles downwind. This Protective Action Recommendation was telephonically communicated to the state and parishes via the Operational- Hot Line at' 11:52 a.m. The correct Protective Action Recommendation should have been to shelter the 2-mile radius and 2 to 5 miles downwind. This erroneous Protective Action Recommendation was corrected on the message form at 11:55- -
a.m. by the Technical Support Center Lead Communicator without acquiring the approval of the Emergency Coordinator or the review of the Health !
Physics Coordinator. The corrected Protective Action Recommendations were subsequently communicated to the state and parishes several minutes later.
Emergency Preparedness Implementing Procedure EP-002-010, Revision 20,,
" Notifications and Communications," Section 5.2, Note I., specifies that- >
the Health Physics Coordinator in the Technical Support Center is responsible for completing the notification message forms. Contrary to' this procedure, the short notification form for the initial General Emergency notification was co aleted by the' Technical Support Center Lead Communicator and was reviewed and approved by the Emergency Coordinator -
prior to issuance. The Health Physics Coordinator did not complete or ,
review this message form.
Incorrect Protective Action Recommendations were issued on a second occasion when the wrong procedure attachment was used to determine the .
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recommendations. Emergency Preparedness Implementing Procedure EP-002-052, . _
" Protective Action Guidelines," Section 5.2.1, requires that "if dose >
projection information is available, a release is occurring and the.
duration of the release is unknown, use Attachment 7.1 and proceed to~ Step 5.3." These enabling conditions existed at about 12:20 p.m. : Step 5.3: ;
specifies that a Protective Action Recommendation of evacuation from O'to 2 miles in all sectors and 2 to 5 miles in' the affected sectors, and shelter 5 to 10 miles in the_ affected sectors- should be issued. Contrary to.this'-
procedure, notification message No. F-11 was issued at 12:23 p.m. which
- incorrectly recommended that all affected sectors be sheltered.
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Attachment to l W3F1-93-0374 Page_5 of 7 i The issuance of incorrect Protective Action Recommendations,:the failure to follow applicable procedures for completing notification messages :
containing Protective Action Recommendations, and the failure to receive the Emergency Coordinator's approval _ to modify previously approved Protective Action Recommendations were identified as an exercise weakness.
RESPONSE
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mn for the Weakness -
L .ure to identify appropriate protective action recommendations in s timely manner, ensure modifications to protective actions are authorized and follow procedures to complete notification message-forms is attributed to two root causes: 1) difficult procedures, 2)_ l need for additional training. "
The protective action guidelines procedure is difficult to implement because it includes,three different methods of arriving at protective ,
actions (no release, release with duration known, release.with ,
duration unknown). In addition, the procedure requires consideration of evacuation time estimates, plume ' travel times, CET temperatures, saturation margins and containment integrity condit_ ions. In attempting to consider the various conditions addressed in the '
procedure, the user might erroneously allow an initial recommendation of sheltering to stay in place for some time, even though dose ;
assessment information indicates evacuation should be the recommendation. .
Regarding completion of notification forms, it .is Waterford 3's position that a Lead Communicator (TSC) or Communications Coordinator I (EOF) should have the ability (by procedure) to complete a message form, either partially or in its entirety, as. directed by the facility Health Physics personnel. The notifications and communications procedure does not clearly specify that the communicators have'the authority to perform this function.
1 Given the complicated nature of the protective-action guidelines procedure, and the many variables involved in arriving at protective action recommendations, additional training on the determination of protective actions'is necessary. This need for additional training was evident in the 1993 exercise. Several individuals were observed !
working to arrive at the recommendations, and all had difficulty in determining the appropriate attachment of the procedure to use; i Because the same problem.was experienced by at least three ,
individuals in the TSC, the cause of the problem is attributed to an I additional training need and not personnel error. !
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Attachment to
. W3F1-93-0374 l Page 6 of 7 -i (2) Corrective Measures
- 1. EP-002-052, Protective Action Guidelines, has been revised with !
an effective date of January.1, 1994. This revision not only-implements revised 10CFR20 and EPA 400 concepts and philosophy, 'i but eliminates many of the variables and complicated logic :i contained in the old procedure.
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- 2. EP-002-010, Notifications and Communications, will be revised ,
to allow the partial, or full completion of offsite messages.by .
communications personnel as directed by Health Physics personnel.
- 3. Special training seminars have been conducted by Emergency ,
Planning for each Operations Shift and the following emergency response organization positions.: Health Physics Coordinator, ;
Health Physics Coordinator Assistant, Dose Assessment !
Coordinator, Dose Assessment Coordinator Assistant, ,
Radiological' Assessment Coordinator, Radiological Assessment Coordinator Assistant, Field Team Controller, Dose Projection- j Coordinator. A portion of these seminars was devoted to a i discussion of the problems with protective ' action recommendations in the 1993 annual exercise as lessons learned. l' Training on the generation of protective action recommendations using the revised procedure was also included in the' seminars'.
- 4. In addition to the above seminars, .the Emergency Planning Department will incorporate special training on the generation of protective action recommendations and a discussion of 1993 [
exercise problems associated with protective action 4 recommendations as lessons learned in the annual tabletop i programs during 1994. The department conducts a minimum of 4 1 tabletops a year for TSC, OSC, and EOF ~ positions. The 1994 tabletops will include problems that, require the participants i
to develop the appropriate protective actions for at least :
three different scenarios. >
- 5. A discussion of the 1993 annual' exercise problems' associated' '
with protective action recommendations as-lessons learned will l be' incorporated in lesson plans for TSC Health Physics Support j personnel, E0F Health Physics Support personnel, TSC Emergency ;
Coordinators, EOF Directors, Shift Supervisors, Control Room j Supervisors, TSC Communicators and EOF Communicators.
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Attachment to i W3F1-93-0374 Page 7 of 7 <
(4) Date-When Full Comoliance Will Be Achieved Corrective Measures 1 and 3 have been completed.
Corrective Measures 2 and 5 will be completed by April 1,1994.
- Corrective Measure 4 will be completed'by December 14, 1994.
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