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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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Entergy = c = " " "c-Kiuona, LA'70066 Tel 504 739 G242 Early C. Ewing lit or f4 dear Safety Assurance 4
W3F1-99-0152 A4.05
, PR October 18,1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES
. Docket No. 50-382 License No. NPF-38 Fidelity of Updated Final Safety Analysis Report (UFSAR)
Gentlemen:-
This letter provides an update of the Waterford 3 effort for the review of the UFSAR.
The information is presented in the following format: (1) Background,
. (2) Management Expectations, (3) Review Status and Results, (4) Clarifications Regarding Review, and (5) Conclusion.
- 1. Background '
The fidelity of the UFSAR is a vital aspect of our responsibility to ensure the safe )
L operation of Waterford 3 (W3) and regulatory compliance. In the past years, there
' have been various assessments of the UFSAR. These assessments have included, 4 for example, Safety System Functional Inspections (SSFI's), Quality Assurance j
- audits, NRC Inspections, and specific assessments of the UFSAR. Also, there have
' been a number of activities that have improved the fidelity of the UFSAR. These ,
activities.have included, for example, reconstitution of Design Basis Documents l (DBD's), reconstitution of calculations, and other recent design basis initiatives.
' Collectively, these efforts have confirmed the overall integrity of the UFSAR and conformance with regulatory requirements. These efforts also identified 1 discrepancies and the need to enhance the fidelity of the UFGAR. In this context, as
. part of the EOl response to the NRC Staff's 10 CFR 50.54(f) ietter on Design Basis O h EOI, on behalf of W3, made a commitment to review certain sections of the UFSAR, Reference EOl letter No. W3F1-97-0025, dated February 6,1997. The last schedule '
. 050^34 991'0270047 991018 PDR- ADOCK 05000382 K PDR
Fidelity of Updated Final Safety Analysis Report (UFSAR)
W3F1-99-0152 i
.Page 2 October 18,1999 '
communicated to the NRC Staff for completing this review is December 31,1999,
. Reference EOl letter No. W3F1-98-0009,' dated January 15,1998.
Subsequent to the EOl response to the NRC Staff's 10CFR 50. 54(f) letter on Design Basis, we undertook a number of broad initiatives to improve the fidelity of the ,
UFSAR. Initially, we analyzed historical UFSA'R problems, reviewed past - !
assessments, and benchmarked the programs of other utilities in order to target specific improvements. The specific improvements that have been achieved include:
o ? A new program plan that specifies the various elements for maintaining the fidelity of the UFSAR.
l c A new' procedure for maintaining the fidelity of the UFSAR.
o' A new guide that contains fidelity and content guidelines, o _ A new electronic responsibility matrix that identifies the responsible departments for each section of the UFSAR.
o Training of Waterford 3 personnel for maintaining the fidelity of the UFSAR.
i o Enhanced integration of the design basis review and the UFSAR review efforts.
These broad initiatives' have enhanced personnel awareness of the need to maintain the fidelity of the UFSAR. These initiatives also provided a framework for proceeding with a dedicated review of selected sections of the UFSAR.
r.
'2.. Management Expectations Maintainir,g the fidelity of the UFSAR is a crucial element of our responsibility to ensure the safe operation of Waterford 3, demonstrate regulatory compliance, and
- operate economically.' We have implemented both broad initiatives that address cultural and process improvements and specific review initiatives that address
- UFSAR historical discrepancies. We are continually adjusting the elements of the
. review to gain optimum results.
A new project instruction has been prepared which reflects the experience gained from the ongoing review of the UFSAR and industry experience. The management I
4 Fidelity of Updated Final Safety Analysis Report (UFSAR)
. .W3F1-99-0152 Page 3 October 18,1999 i expectations in the project instruction are:
o The UFSAR must be accurate and complete to support the safe operation of the
. plant and the operability of structures,' systems, and components, o The UFSAR must be consistent with the operations, design, and licensing basis of Waterford 3. This means the UFSAR must be consistent with the following:
. The. actual operation of the plant, procedures, and the configuration of !
structures, systems, and components.
. The design assumptions, design inputs, analyses, and codes and standards that establish the design for the operation and configuration of structures, systems, and components, e Applicable regula'tions and other documents that demonstrate compliance with regulations, such as the operating license, technical specifications, NRC Staff safety evaluation reports, docketed commitments, and the Quality Assurance Program Manual.
o The UFSAR 'must reflect a high standard of fidelity to ensure the information is accurate and complete.
' Management and the project personnel maintain a strong communication to ensure
- management expectation issues are effectively addressed.
- 3. ' Review Status and Results We commenced the review of the UFSAR'in July 1998. The review was held in abeyance during Refuel 9. The reviews of Chapters 6,7,8,9,10,11, and 12 have been_ completed. No discrepancies have been found that adversely affect the safe
. operation of the plant or that would prevent safety systems from performing their safety function. No discrepancies have been found that affect the operability of l
equipment or which constitute unreviewed safety questions.
!: Generally,- the discrepancies found can be characterized as: 1.) Information lacking a L
definitive design basis,2.) Differences between the UFSAR and other operations, ,
design,' or licensing basis documents like procedures, calculations, or technical 1 specifications, 3.) Incorrect or incomplete data or statements about equipment performance or configuration, and 4.) Editorial errors.
I
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Fidelity of Updated Final Safety Analysis Report (UFSAR)
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Almost all of the discrepancies did not require the generation of a Condition Report because they did not meet the threshold of an adverse condition. The discrepancies are input into an ACCESS database for tracking and correction.
Although the discrepancies have not been safety or operationally significant, some UFSAR sections, including tables and figures, have historically not been well i maintained. The measures previously discussed address the underlying causes. j
\ l l One major shift we have implemented is that EOl personnel rather than contract personnel are now perfomling the review. This shift has allowed us to dedicate a more diverse team to ensure a strengthened technical review. l l Also, as part of the review effort, we are holding discussions with key personnel and management to ensure an understanding of fidelity concepts and requirements, developing fidelity tools, such as a plan for maintaining figures, and assessing needs for additional training, The remainder of the review is planned, prioritized, and scheduled. The current goal l for completing the review is October 31,2000 rather than December 31,1999 as )
previously communicated to the NRC Staff. The new projected completion date has changed as a result of holding the project in abeyance during Refuel 9, dedicating ;
EOl personnel to the review effort, adjusting the scope and basis of the review, and the Entergy Renewal Initiative. The new projected completion date is a target date for managing goals, and the date is subject to change.
- 4. Clarifications Regarding Review One of the important elements of our UFSAR fidelity focus is to keep abreast of industry achievement and regulatory initiatives relating to UFSAR fidelity. These achievements and initiatives include, for example, the promulgation of the Nuclear Energy Institute (NEI) document NEl 98-03, Revision 1, " Guidelines for Updating Final Safety Analysis Reports," and the NRC Staff Safety System Engineering inspection at the Grand Gulf Nuclear Station Facility documented in NRC Staff Inspection Report No. 50-416/99-02.
NEl 98-03 is expected to be a valuable tool in applying guidance for updating the UFSAR.' We have carefully reviewed and applied NEl 98-03 in our review effort
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- Fidelity of Updated Final Safety Analysis Report (UFSAR)
W3F1-99-0152 i L Page 5 October 18,1999 throughout its development. _ However, we also note, based on NRC Staff Inspection j Report 50-416/99-02 that some aspects.or details of licensee review efforts may ,
vary from NRC Staff perceptions. Accordingly, we would like to highlight some {
" aspects and details of our review effort.
l The first priority of the review is to identify information which is suspect and could potentially affect the safe operation of the plant, the ability of structures, systems, or components to perform their safety function, or the operability of equipment.
1 The second priority of the review is to identify any information which is suspect and )
may not be consistent with the operations, design, and licensing basis of the plant.
The third priority of the review is to identify information that is suspect and may need to be reconstitute'dto improve the accuracy and completeness of the UFSAR. l The review objectives are to ensure: 1 o The information has a supporting and definitive design basis, o Information is consistent with the operations, design, and licensing documents, o Information is consistent with the actual performance, design' data, or configuration of st uctures, systems, and components.
o The classificaticos for structures, systems, and components are correct.
~a The description of the implementation of codes, standards, and commitments is correct.
o The information is consistent with the information in other sections of the UFSAR, tables, and figures.
1 o : The information is clear, unambiguous, and sensible.
The review attempts to find editorial errors because they could be misinterpreted and lead to more serious errors.
- The review is not intended to verify all information. Rather, the reviewer, based on
- expertise and judgment, confirms select information if it is suspect or has safety or risk significance.
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L ' The review does not entail a verification of the configuration of the plant. The UFSAR l
information regarding the performance capabilities of structures, systems or components or plant configuration is reviewed based on the expertise and judgment of the reviewer. The information is verified only if the accuracy or completeness of the information in the UFSAR is suspect.
Although the review entails a comparison of the UFSAR with operations, design, and licensing documents, the intent is not to verify the adequacy of the source documents. There are processes in place to ensure documents such as calculations, operations procedures,' or technical specifications are complete and accurate. The j adequacy of the source document is evaluated only if the information in the source document is suspect, and the information could constitute a potential UFSAR fidelity problem.
The review assesses the information in the UFSAR describing how codes and standards are implemented.' The intent of the review is to confirm the information has a supporting and definitive design basis; agreement with operations, design, and licensing bases; and the information is accurate and complete based on the expertise
.and judgment of the reviewer. However the intent of the review is not to verify the adequacy of the design or analyses, including whether the necescary exceptions or clarifications have been identified.
Figures in the UFSAR are reviewed to ensure the figure revision in the UFSAR matches the current revision of the figure. The figures receive a cursory review.
l However, the design details and configurations depicted in the figures are not verified since the design control process ensures the adequacy of the design. Additional l
reviews are performed to the extent suspect information is found in the text sections ,
or if the figures contain critical design basis or analytical information' corresponding to or supporting the text sections.
The review is not intended to verify plant configuration or the adequacy of the design, analyses, or source documents. However, the reviewers look for such discrepancies based on judgment and expertise? Once suspect information is identified, the reviewer will review all aspects associated with the suspect information, including l plant configuration, design, analysis, or source documents as necessary to establish
' the scope and basis of the discrepancy.
- Historicalinformation is not' reviewed. NEl 98-03 is used in determining what information is historical. Basically, historical information is
'(1) information not intended to be updated for the life of the plant,
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(2) information not affected by changes to the plant or its operation, or (3) information that does not change with time. Specific examples are meteorological information, i description of original factory testing of equipment, or description of start-up or . l preoperational tests.
Although not analytically structured, the foregoing approach places emphasis on safety-related, risk significant, or suspect information. The review focus and l l confirmation is adjusted based on the Chapter or section being reviewed and also on ;
the types of discrepancies being identified. The effectiveness of the review is highly i dependent on the expertise and judgment of the reviewers. . Therefore, we have dedicated a highly diverse and experienced EOl % terford 3 team to the UFSAR Fidelity Project.
- 5. Conclusion l
The fidelity of the UFSAR is vital for the safe operation, regulatory compliance, and the economic viability of Waterford 3. Various assessments over the past years have ;
confirmed the overallintegnty of the UFSAR. However, these assessments have l also identified the need to enhance the UFSAR. We have carefully evaluated the historical record and instituted broad and specific initiatives to enhance the UFSAR.
Management expectations for maintaining the fidelity of the UFSAR have been carefully considered and documented. One initiative currently ongoing is the review of the UFSAR.To date, this review of the UFSAR has not identified any discrepancies that adversely impact safety or the operability of equipment.
Certain UFSAR sections, tables, and figures have not been well maintained, but recent and ongoing initiatives address this issue. Some aspects and details of our review have been highlighted to provide a more visible picture of our effort.
The current review, although not analytically structured, focuses on safety-related, risk significant, or suspect information. The effectiveness of our review is achieved by virtue of the diversity and experience of our review team.
This submittal does not contain any commitments.
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Please contact E.P. Perkins at (504) 739-6379 or myself should there be any l l
question regarding this letter. !
I Very truly yours, ;
U ' M If e EC.b'g')
E.C. Ewing .
Director Nuclear Safety Assurance l
- ECE/RJM/rtk cc
- E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR
. J. Smith N.S. Reynolds NRC Resident inspectors Office t.
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