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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] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20012A0951990-02-0808 February 1990 Forwards Final Radiological Emergency Preparedness Exercise Rept for Waterford 3 Steam Electric Station of 890830 Offsite Exercise.No Deficiencies Noted ML20151Q3761988-04-0808 April 1988 Forwards Waterford 3 Steam Electric Station Site-Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification. Sys Satisfies Requirements of NUREG-0654/FEMA-REP-1,Rev 1.Caveat Removed ML20150B6251988-03-0808 March 1988 Forwards Final Radiological Emergency Preparedness Exercise Rept Waterford 3 Steam Electric Station on 871014.No Deficiencies Identified During Exercise.One Area Requires Corrective Action from Previous Exercise in Oct 1986 ML20211H4211987-02-17017 February 1987 Forwards Final Exercise Rept for 861015 Exercise of Offsite Radiological Emergency Preparedness Plans for Facility.No Deficiencies Identified During Exercise.State of La Included Corrective Action Schedule in Rept ML20138Q9281985-12-26026 December 1985 Forwards 850918 Exercise Rept for Partial Participation Exercise of Offsite Radiological Emergency Preparedness Plan.Plan Adequate to Protect Health & Safety of Public. Several Areas Recommended for Improvement ML20137Q6231985-11-21021 November 1985 Requests NRC Comments & Recommendations on Util Application to Discharge Boron Into Mississippi River within 30 Days of Ltr Receipt ML20126L3361985-07-15015 July 1985 Informs That State of La State & Local Radiological Emergency Plans Re Facility Adequate,Subj to FEMA Verification of State Public Alert & Notification Sys Per App 3 to NUREG-0654-FEMA-REP-1,Rev 1 ML20100J7101985-04-0909 April 1985 Forwards Addendum to Interim Finding on Offsite Radiological Emergency Response Plans Resolving All NUREG-0654 FEMA-REP-1,Rev 1 Planning Elements Re Offsite Radiological Emergency Planning ML20112A2051985-03-14014 March 1985 Provides Supplemental Info Re Offsite Arrangements for Medical Svcs Around Facility.Intent of NUREG-0654 Has Been Met Based on 850107 Finding & 850308 Conference Call ML20111C3731985-01-0707 January 1985 Forwards Schedule of Corrective Actions for Category B Deficiencies Identified During 840208 Offsite Radiological Emergency Preparedness Exercise.Based on Exercise Results & Corrective Action Schedule,Preparedness Considered Adequate ML20138C1821984-08-23023 August 1984 Forwards Project & Budget Proposals for NRC Work for Rev 1 to, Evaluation of Selected NRC Open Items Before Plant Fuel Load & Evaluation of Selected Open NRC Activities at Near-Term OL Sites Needing Action.. ML20093K8831984-07-25025 July 1984 Forwards Final Radiological Emergency Preparedness Exercise Rept of 840208 Joint Exercise ML20090F5261984-07-16016 July 1984 Forwards Resolution of Last Offsite Planning Issue,Per ASLB 821103 Partial Initial Decision & 821212 Amend.State of La Provided Ltrs of Agreement from Support Parishes Identifying Vehicles & Drivers to Be Used in Evacuation ML20084Q2391984-05-11011 May 1984 Forwards Supplemental Interim Findings on Four Offsite Planning Issues Re Emergency Operations Facility Requiring Resolution Prior to Issuance of Full Power OL for Facility, Per ASLB 821103 Decision ML20080K2021984-02-0707 February 1984 Forwards 830916 Interim Finding on Util 831227 Addendum to Interim Finding,Comments on El Quarantelli Rept & Response to Civil Defense Concerns,Per NRC 830325 Request. Test Plan Exercise Scheduled for 840208 ML20076L5441983-09-0707 September 1983 Forwards Evacuation Behavior:Case Study of Taft,La Chemical Tank Explosion Incident ML20077L7481983-07-29029 July 1983 Discusses Review Status of Final Rev 4 to State of La Emergency Plan.Substantial Findings Will Not Be Provided Until 830915,due to Cancellation of Emergency Exercise Because of Flooding ML20070D7081982-09-13013 September 1982 Requests ASLB Order Requesting Further FEMA Testimony on Public Info Brochure & Final FEMA Testimony Filed W/Aslb ML20070D6741982-05-14014 May 1982 Requests L Jones to Turk,Nrc Exhibit on Potassium Iodine & Transcripts for 820506,07 & 12 ML20054D7821982-04-20020 April 1982 Responds to NRC 820416 Ltr Re Emergency Treatment to Rectify Minor Damage to Site 16 Ebr 52,Port Hudson Battlefield,La, Natl Historic Landmark.Agrees W/Archeologist Recommendations for Installing Fabric Mesh & Reseeding ML20054C5041982-03-31031 March 1982 Forwards Interim Findings Re State & Local Plans for Offsite Radiological Emergency Preparedness for Facility.Evaluation Concludes That There Are No Serious Deficiencies in Plan or Capability of State to Implement Plan ML20040D8021982-01-22022 January 1982 Forwards Determination of Eligibility Notification Re Waterford Plantation Workers Quarters Site & Overseers House Site.Both Sites Qualify for Registry as Historic Places ML20009A8421981-07-10010 July 1981 Offers No Comments on Des ML20009B0961981-07-0202 July 1981 Submits Comments on Des for Facility,In Reponse to NRC 810508 Request.Effect of Increased Water Temps on Reactor Coolant Chemicals,Impact of Plant on Ph & Alkalinity & Changes in Chemical Equilibria Should Be Addressed ML20005B5081981-06-30030 June 1981 Informs That Des Will Be Forwarded to Responsible Hud Regional Environ Officer for Review & Appropriate Comment. EISs Should Be Sent Directly to Ofc W/Review Responsibility. List of Regional Environ Officers Encl ML20008G2621981-06-30030 June 1981 Comments on Des for Facility.Proposed Project Action Classified as ER-2 (Environ Reservations,Insufficient Info). Fes & Supporting Documents Should Be Strengthened in Noted Areas ML20005B1961981-06-29029 June 1981 Provides Comments Re Health Aspects of Des NUREG-0769. App I to 10CFR50 & Operating Plan Provide Adequate Assurance That Radiation Exposures Meet Current Radiation Protection Stds ML20005B1231981-06-26026 June 1981 Offers No Comments on Des ML20005A0281981-06-18018 June 1981 Comments on Facility Des,In Response to NRC 810508 Request. No Significant Impacts Found in Areas of Agency Responsibility ML19350E5701981-06-17017 June 1981 Advises That Des for Facility Adequately Analyzes Impacts of Proposed Facility ML20004E7921981-06-0808 June 1981 Comments on Des for Facility.Land That Will Be Utilized During Facility Const & Operation Is Classified as Prime Farmland.Prime Farmland Cannot Be Built Up Urban Land ML19347F2671981-05-13013 May 1981 Verifies Official Filing of 810508 EIS,(NUREG-0779) Per Section 1506.9 of Ceq Regulations.Publication of Fr Notice of Availability Scheduled for 810515.Public Review Period to Terminate on 810629 ML19257D8241980-01-30030 January 1980 Responds to NRC 791231 Request for Info Re Endangered, Threatened,Or Proposed to Be Listed Species in Const Area.No federally-listed Species Present in Project Area ML19291C4601980-01-15015 January 1980 Ack Receipt of NRC 791231 Request for Info Re Presence of Endangered Species in Const Area.Request Is Under Review. List of Species & Info Necessary in Biological Assessment Will Be Forwarded Upon Completion of Review ML20125D5281980-01-0808 January 1980 Advises That Requested Info Re Endangered or Threatened Species in Area of Const Will Be Submitted After Jackson Area Ofc Completes Review ML19207B7231979-07-19019 July 1979 Requests Review of Events & Allegations Listed Re Noncompliance W/Antitrust License Conditions or Significant Change. ML19282C8561979-03-23023 March 1979 Forwards Registration Statement Filed by La Power & Light Co on 790321.W/o Encl ML19319D3091971-11-22022 November 1971 Ack Receipt of Crystal River 3 FSAR on 711119 & Waterford 3 Amend 6 to CP Application on 711122 1990-02-08
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jto er I S UNITED STATES ENVIRONMENTAL PROTECTION AGENCY REGION VI g ggc 1201 ELM STREET DALLAS TEXAS 75270
<9 June 30, 1981 Mr. Frank J. Miraglia k Acting Chief, licensing P anch No. 3 gl U.S. Nuclear Regulatory Commission
- M 0 61981 > % -
Washington, D.C. 20555 ' " M"mla""
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Dear Mr. Miraglia:
- ll g s no We have completed our review of the Draft Environmental Im ement (EIS) related to the operation of the Waterford Steam Electric Station, Unit No. 3, (Docket No. 50-382) St. Charles Parish, Louisiana. The proposed action is to issue an operating license for the start up and operation of Unit 3. The Unit will be built by the Louisiana Power and Light Company about 25 miles west of New Orleanc, Louisiana, and is scheduled for fuel-loading in 1982.
The following comments are provided for your consideration when preparing the Final EIS:
Generic Comments In our past "eviews of Draft EIS's related to light-water nuclear power facilities, we have included generic comments which are applicable to all such facilities. As a result of the Three Mile Island accident and other recent activities, we have decided that we must ravise our generic comments to consider these events and activities. We will provide our revised generic comments to the Nuclear Requlatory Commission (NRC) as soon as they are completed.
Generic areas undergoing review are:
Population dose commitments Reactor accidents Fuel cycle and long-term dose assessments High-level radioactive waste management Transportation impacts Decommissioning Radioactive Waste Treatment Systams The Draft EIS does not contain detailed descriptions of the radio-active waste treatment systems or the NRC staff's detailed evalua-tions. Such matters are referenced to the Safety Evaluation Report (SER), which has not yet been issued. On request, however, we were supplied an advance copy of draft sections on the ventilation and radioactive waste treatment systems. We appreciate being supplied this information.
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2 It appears that the radioactive waste treatment systems are capable of controlling emissions to levels such that, when direct radiation is also considered, operations will be within EPA's Environmental Radiation Standards, 40 CFR 190. However, we note that the pre-draft ZR identifies certain unspecified " confirmatory" information which has not yet been provided by the applicant. Pending receipt of this infornation and NRC staff review, the Liquid Waste Processing System, the Gaseous Waste Processing System, and the Solid Radio-active Waste Treatment System are all considered confirmatory issues. We therefore consider our conclusions, regarding the capabilities of these systems, to be contingent on the successful resolution of the confirmatory items by the NRC staff.
We believe the Final Els should include an evaluation and full discussion of any confirmatory items not resolved by the time it is issued.
Reactor Accidents When discussing accident risk and impacts of design basis accidents, the Draft EIS addresses probabilities of occurrence qualitatively.
Yet, when discussing more severe core melt accidents, the probabili-ties of occurrence are quantified (Table 5.19). For consistency in the presentation o' all environmental risks, we believe the proba-bilities of occurrence of infrequent accidents and limiting fault design basis accidents should also be provided.
Safety Evaluation Report The practice of~1ssuing the Draft EIS in advance of the SER has prevented our performing a complete review of the environmental impacts of the Waterford-3 station. As discussed in our comments on radioactive waste treatment systems, we were provided advance copies of draft SER. sections on those systems, so the problem was l alleviated, although we do not consider this pre-draft information I to be formal documentation. Also, the Drait EIS refers to the SER in several other important areas which are still under NRC review.
These include:
- 1. Site features. The authority of the applicant to control all activities within the exclusien area is still under NRC staff I review. Also, nearby off-site hazards, including those i associated with hydrocarbon and toxic substances pipelines,
! train, truck, and aircraft traffic, and oil and gas fields are i still under review. Exclusion area activ1'ies will be evaluated in the SER, but the evaluation of off-site huards will not be l
completed until later and included in a suppiement to the SER.
i l 2. Emergency preparedness. Facility emergency plans and State l and local plans are reported to be in an advanced, but not yet fully completed stage. NRC staff findings of adequacy and l implementability, for both the on-site and off-site plans, will be reported in the SER.
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3 In view of the above, the conclusion stated in Section 5.12 regarding no conflict between environmental concerns and the proposed action, would seem to be contingent on favorable results on some important ongoing staff reviews and hence premature. The Final EIS should be withheld until the above-mentioned reviews are completed, or should specifically evaluate any of the areas which are still undergoing review.
We urge the NRC to ensure that, in the future, the Safety Evaluation Report is available before issuing the Draft EIS. Material incor-porated into an EIS by reference should be reasonably available for inspection within the time allowed for comment (40 CFR 1502.21).
We do not believe the citations of missing but forthcoming infor-mation in the SER constitutes a " reference" in the common meaning of that word.
Decommissioning The Draft EIS states that planning for decommissioning can have an impact on health and safety as well as cost, and that financial assurance that funds will be available, when required, is a factor to be considered. We concur in this assessment, but were unable to find in the Draft EIS arrangements for financing decommissioning i costs. Although decommissioning costs are noted to be a small fraction of present worth commissioning costs, they will still represent a large cost burden when needed, if not set aside out of revenues during the plant's operating lifetime. The Final EIS should explain what arrangements have been made, or are planned, to assure that funds will be available when required.
In this connection; it is not clear at what point the licensee's financial responsibility is to be terminated. Termination of the nuclear license is required at the end of _ facility life, and this requires decontamination of the facility cuch that unrestricted use can be allowed. One option to achieve roch decontamination is SAFSTOR, which allows deferral of decontamination for up to 100 years. It is not clear, in such a case, whether license termination would occur prior to or at the end of such an extended storage period. If termination occurs at the beginning of the storage
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period, financial arrangements evidently will be necessary to pay for the deferred decontamination. The Final EIS should clarify this point.
Ecoromic Risks As the Three Mile Island accident demonstrated, the cost of reactor building decontamination and replacement power following an accident can be sizable. This underscores the need to develop i standard methodologies for estimating the contribution of these costs to economic risks. Economic risks are addressed in Section 5.9. 2.1.4 ( 6) of the Draft EIS (under Station Accidents). Based on low probability, annualized risk is shown to be modest. Because of the potentially severe economic costs; however, we believe these risks should be mentioned explicitly in the benefit-cost summary, Section 6.6.
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4 Additional Comments
- 1. The statement on page 5-54 that a dose greater than about 25 rems over a short period of time is necessary before any physiological effects are clinically detectable, should be reviewed. Information contained in the World Health Organization technical report No.123 would seem to indicate that physiological changes can occur at exposures as low as 10 rems.
- 2. Table 6.1 lists water samples to be taken from the intake structure, but none from the discharge canal which would provide a measure or the radioactivity discharged from the facility. This should be explained. Also, in this same table, it is not clear whethstr the thermoluminescent dosimeters (TLD) are to be collected on a quarterly schedule which could change to a semi-annual schedule, or whether some TLD's will be collected quarterly and some semi-annually. These points should be clarified in the Final EIS.
- 3. In Table 5.14 population dose is labeled as " mrem" and should be " man-rem." Also, in the same table, truck vs. rail traffic density is unclear.
- 4. The footnote under Table 5.24 appears to be misplaced.
In view of the information provided and our comments on the Draft EIS, we classify the proposed project action as ER-2 (Environmental Reservations, Insufficient Information). We ask that the Final EIS and supporting documents be strengthened in the areas our preceding detailed comments have identified.
Our rating is based on our evaluation of the EIS, advance copies of pre-draft SER sections and other impcrtant areas which are still under-going NRC review as discussed earI1er. We re. serve the right to change our rating if published information is su%tc.tially changed from what we have reviewed.
Our classification will be published in the Federal Register according to our responsibility to inform the puolic of our views on proposed Federal actions, under Section 309 of the Clean Air Act.
Definitions of the categories are provided on the enclosure. Our
. procedure is co categorize the EI5 on both the environmental conse-quences of the proposed action and on the adequacy of the EIS at the draft stage,.whenever possible, a
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We appreciated the opportunity to review the Draft EIS. Please send our office five (5) copies of the Final EIS at the same time it is sent to the Office of Federal Activities, U.S. Environmental Protection Agency, Washington, D.C.
Sincerely, f Is' W =>
Frs. aces E. Phillips
.Nting Regional Administrator Enclosure 1
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ENVIR02 ENTAL IMPACT OF THE ACTION l
EPA has no objections to the proposed action as described in the draft impact statement; or suagests only minor changes in the proposed action.
ER - Environmental Reservations EPA has reservations concerning the environmental effects of certain l aspects of the proposed action. EPA believes that further study of suggested alternatives or modifications is required and has asked the l originating Federal agency to re-assess these aspects. 4 EU - Environmentally Unsatisfactory EPA believes that the proposed action is unsatisfactory because of its potentially harmful effect on the environment. Furthermore, the Agency believes that the potential safeguards which might be utilized may not adequately protect the environment from hazards arising from this action. '
The Agency recommends that alternatives to the action be analyzed further (including the possibility of no action at all).
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ADEOUACY OF THE L9 PACT STATEMENT I
Catecory 1 - Adecuate The draft impact statement adequately sets forth the environmental impact :
of the proposed project or action as well as alternatives reasonably available to the project or action.
Cateaory 2 - Insufficient Information l EPA believes the draft impact statement does not contain sufficient information te assess fully the environmental impact of the proposed project or action. However, from the information submitted, the Agency is able to make a preliminary determination of the impact on the environment. EPA has requested that the originator provide the information that was not included in the draft statement.
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Catecory 3 - Inadecuate l
EPA believes that the draft impact statement does not adequately :
assess the environmental impact of the proposed project or action, t or that the statement inadequately analy:es reasonably available l alternatives. The Agency has requested more information and analysis
( concerning the potential environmental hazards and has asked that l l substantial revision be made to the impact statement. If a draft I statement is assigned a Category 3, no rating will be made of the l project or action, since a basis does not generally exist on which to make a determination. l i
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