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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] |
Text
~._
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= Entergy g y n a m ,i . !
Operations. xciore ta 700ee !
- Te! 504-739-f650 -
l l l I
W3F1-97-0002 ,
L A4.05 l PR i
. l l
l January 21,1997
)
U.S. Nuclear Regulatory Commission i
~ ATTN: Document Control Desk !
Washington, D.C. 20555 i
Subject:
Waterford 3 SES l Docket No. 50-382 i License No. NPF-38 J l NRC Inspection Report 50-382/96-13 !
l Reply to Notice of Violation i Gentlemen: !
l
! In accordance with 10CFR2.201, Entergy Operations, Inc. hereby submits in l Attachment 1 the response to the violations identified in Enclosure 1 of the subject Inspection Report. i 1
l Waterford 3 acknowledges the three concerns expressed in the cover letter to the L
inspection report: (1) operators failed to follow procedures regarding configuration
- control, (2) operators failed to recognize that the wet cooling tower fans were
- rendered inoperable during a maintenance activity and failed to enter appropriate l Technical Specification (TS) Limiting Conditions for Operation, and (3) review of the l Inservice Test (IST) program did not identify the need to perform testing on the dry
[ cooling tower isolation valves which are required to be repositioned during the design i
basis tornado event. l Regarding the first concern, Waterford 3 has previously identified an increasing trend in the number of human performance violations. Our comprehensive corrective actions to address that trend are detailed in Letter W3F1-96-0213 dated 12/13/96.
l We believe those corrective actions, in concert with the actions detailed in i Attachment 1, will help prevent similar violations from recurring and will improve i operator attentiveness. I cpEbi i 9701230168 970121
'PDR G
ADOCK 0 g2
~
Reply to Notice of Violation (IR 96-13)
W3F1-97-0002 Page 2 January 21,1997 In add. tion to the corrective actions detailed in Attachment 1 for the second concern,
! we are continuing to implement corrective actions from the FOCUS plan (reference l Letter W3F1-96-0130 dated 8/19/96) to improve our performance in the area of TS l implementation. These actions include enhancing the procedure process, utilizing l assessments as a tool to identify additional improvement opportunities, improving i operator awareness of plant conditions prior to approving maintenance activities, and establishing specific guidance concerning the control of work and pre-job briefings to ensure proper Operations oversight. Furthermore, Waterford 3 management has placed significant focus on assuring that the culture and policy for implementing ;
~
Technical Specifications are conservative from a safety standpoint and comply with regulatory requirements.
1 Regarding the third concern, the dry cooling tower isolation valves will be added to !
the IST plan. Furthermore, we are developing a document that details the design basis tornado event. This document should increase the probability that similar conditions, if they exist, are identified and corrected. l
- l. Should you have any questions concerning this response, please contact .
i me at (504) 739-6666 or Jeff Thomas at (504) 739-6531. !
l Very truly yours, 1
/
n Of
- T.J. Gaudet l- Acting Director, Nuclear Safety & Regulatory Affairs TJG/GCS/tjs Attachment cc
- E.W. Merschoff (NRC Region IV)
, C.P. Patel (NRC-NRR) ,
j R.B. McGehee !
i N.S. Reynolds ;
l NRC Resident inspectors Office i f
i l
I
- l Attachment to W3F1-97-0002 Page 1 of 8 ATTACHMENT 1 ENTERGY OPERATIONS. INC. RESPONSE TO THE VIOLATION IDENTIFIED IN i ENCLOSURE 1 OF INSPECTION REPORT 96-13 l
l l .
VIOLATION NO. 9613-01 i
Technical Specification 6.8.1.a requires, in part, that written procedures shall be implemented covering applicable procedures recommended in .
( Appendix A of Regulatory guide 1.33, Revision 2, February 1978. Appendix A,
! Section 3, requires that the licensee have procedures for operation of safety ielated l systems.
i i
- 1. Procedure OP-002-010, " Reactor Auxiliary Building HVAC and Containment 2 Purge," Revision 11, Section 6.6, required that the airborne radioactivity i removal system be secured when stopping containment purge.
Contrary to the above, on October 1,1996, the licensee failed to secure the l airborne radioactivity removal system after stopping containment purge. The airborne radioactivity removal system was not secured until observed in the abnormal configuration on October 20,1996, a period of 19 days.
- 2. Procedure OP-002-003, " System Operating Procedure - Component Cooling Water System," Revision 10, Section 6.0, " Normal Operations," required the dry cooling tower fan control switches be in the AUTO position.
Contrary to the above, on October 19,1996, at 3:37 a.m., operators inadvertently placed the Dry Cooling Tower Fan 13-B control switch in the OFF position. The switch remained in the OFF position until observed in the abnormal configuration at 4:40 p.m. on October 20, a period of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- 3. Procedure OP-903-121, " Safety Systems Quarterly IST Valves Tests,"
Revision 1, Section 7 2, " Safety injection Train B," requires that Valve Sl139B be closed following inservice testing.
Contrary to the above, on November 19,1996, at 1:42 a.m., operators failed to close Valve SI-139B following inservice testing. Valve SI-139B was not closed until operators observed the abnormal configuration at 4 p.m. on November 21,1996, a period of 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br />.
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$ This is a Severity Level IV violation (Supplement 1). (50-382/9613-01) l l
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RESPONSE I I
l (1) Reason for the Violation j l
This violation was due to personnel error and inattention to detail in that operators involved with each of the occurrences failed to follow procedures and failed to closely monitor activities that were taking place on the control board. The operators are required to be cognizant of activities on all the control panels and the attention given to the control panels with the incorrect j configurations was not adequate. The operations shift turnover on the plant i l configuration was inadequate in that configuration errors existed over several l l shifts and were never discussed or identified by the oncoming shifts until 19
! days for example 1,36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for example 2 and 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br /> for example 3 of the i violation. In addition, Operations supervisory personnel (Control Room Supervisor [CRS] and Shift Superintendent [SS) ) did not provide adequate !
l oversight of the activities taking place on the control panels. l f l Contributing to the failure to follow procedure OP-002-010, " Reactor Auxiliary l Building HVAC and Containment Purge," to secure the airborne radioactivity
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removal system was an inadequate place keeping method in procedure OP-002-010. This procedure does not have sign-offs for each action step ;
delineated. Consequently, steps in the procedure, such as those securing the l airborne radioactivity system, may be overlooked due to a sign-off not being required. In addition, Operations supervisory personnel (Control Room Supervisor [CRS] and Shift Superintendent [SS) ) did not provide adequate oversight of the activities taking place on the control panels.
Contributing to the failure to follow procedure OP-002-003, " System Operating l Procedure- Component Cooling Water System," which requires the Dry l Cooling Tower Fan 13-B control switch to be in Auto position was that there is l no difference in light indication on the DCT fan control switch when the switch is in auto position compared with the off position. The operators rely on the i position of the control knob pointer to determine the position of the control switch. In addition, Operations supervisory personnel did not provide l
adequate oversight of the activities taking place on the control panels.
Contributing to the failure to follow Section 7.2, " Safety injection Train B," of
, procedure OP-903-121, " Safety Systems Quarterly IST Valves Tests," was
' that the operators, who should have closed valve SI-139 from the control board, were involved with another activity which distracted their attention and caused them to overlook the position of valve SI-139. Even though distractions are a cue to self checking, proper self checking was not done. In 4 addition, Operations supervisory personnel did not provide the proper work environment to minimize these distractions.
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l Attachmsnt to W3F1-97-0002 Page 3 of 8 (2) Corrective Steps That Have Been Taken and the Results Achieved
- 1. Condition reports 96-1639,96-1640 and 96-1847 were generated for I each one of the self-identified occurrences.
- 2. All the components were placed in their correct configuration.
- 3. All the operators involved with the failure to restore the plant to its i correct configuration have been counseled.
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- 4. Operations Manager reinforced the operators requirement to perform thorough control board walkdowns.
)l l 5. All control room operators are required to sign a new addendum sheet to the shift log indicating completion of control board panel walkdowns.
l (3) Corrective Steos Which Will Be Taken to Avoid Further Violations
- 1. The Operations Manager will issue a letter to all Shift Superintendent ,
and Control Room Supervisors which will emphasize the importance of ,
properly prioritizing tasks to avoid excessive operator work load.
- 2. The Operations Manager will clarify to operations supervisory
, personnel the expectation that licensed operators have responsibility for monitoring plant controls. The supervisory personnel will convey i these expectations to the operations staff.
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- 3. The Operations department will form a team to review and improve, if l appropriate, the current method used for shift turnover. A review of the j inadequacy of reviewing shift logs will also be perfonned.
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- 4. A review will be performed on normal operating procedures to j
! determine if the method for place keeping in procedures can be improved.
(4) Date When Full Comoliance Will Be Achieved Waterford 3 is in full compliance. Items 1,2, and 3 will be completed by 2/28/97 and item 4 will be completed by 7/1/97. ;
./ Att: chm:nt to VV3F1-97-0002 Page 4 of 8 ATTACHMENT 1 ENTERGY OPERATIONS. INC. RESPONSE TO THE VIOLATION IDENTIFIED IN ENCLOSURE 1 OF INSPECTION REPORT 96-13 VIOLATION NO. 9613-03 Technical Specification 3.7.4.f requires, in part, that, with more than one wet cooling tower fan inoperable and the outside air temperature greater than 70 degrees F, the dry bulb temperature must be determined at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Contrary to the above, between May 5 and 9,1996, with more than one wet cooling tower fan inoperable and the outside air temperature greater than 70 degrees F, the licensee did not determine the dry bulb temperature at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
This is a Severity Level IV violation (Supplement 1). (50-382/9613-03)
RESPONSE
(1) Reason for the Violation l
Entergy Operations admits this violation and believes that the root cause is '
inadequate work controls in that the method used in the engineering evaluations was not standardized. There was no standard method or process to establish administrative controls for the format, required level of l review / approval, and operations interface of the ovaluation that was used to document the inoperability of the wet cooling tower fans. Guidance on the use of engineering input to evaluate work that may impact operabilty of safety related or technical specification equipment was inadequate. As a result, an adequate level of review of the engineering evaluation was not performed and the fact that the wet cooling tower fans would be rendered inoperable while netting was placed around the wet cooling tower basin was not clearly communicated to operations. As a result of operations not being cognizant of the wet cooling tower fans inoperability, the required actions per Technical i Specification 3.7.4.f was not performed.
l (2) Corrective Steos That Have Been Taken and the Results Achieved
- 1. Condition report 96-729 was generated to document and address this matter.
- 2. LER 96-005 Revision 0 was issued to report this occurrence.
l 3. The temporary netting that rendered the fans inoperable was removed.
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- 4. Operations Administrative Procedure OP-100-014," Technical Specification Compliance," has been revised to require the following:
I a. If any system, sub-system, or component becomes unable to l- perform its intended safety function due to surveillance, calibration, or maintenance, then declare that equipment
- inoperable and enter the appropriate Tech / Spec TRM (Technical l Requirements Manual) action.
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- b. If a component is thought to be Inoperable enter the appropriate Tech Spec /TRM action and initiate LCO tracking in accordance with OP-100-010, " Equipment Out of Service."
- c. The engineering guidance should have at least two signatures ;
on it indicating that a technical review has been performed. i
!- d. The engineering guidance must be specifically bounded against )
any applicable Tech Specs. All engineering guidance parameters must be bounded by Tech Spec parameters, and in i all cases, operators will adhere to the Tech Specs.
- e. The STA should perform a review of the engineering guidance and provide a recommendation to the SS concerning the ,
adequacy of the guidance.
- 5. Plant Administrative Procedure UNT 007-053 " Engineering Work Authorization," has been revised to specify the following.
- a. An engineering input will not be used to make operability determinations for technical specifications or safety related ,
equipment, nor will it be used to implement configuration j changes.
- b. All nonconformance conditions are addressed by Corrective Action Site Directive, W2.501.
- c. Engineering inputs are only used to facilitate work such as bolting, torquing, gasketing, material condition improvements,
- l. troubleshooting and venting requirements.
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- d. All engineering inputs require a technical reviewer signature. l i
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l ' Attachm:nt to W3F1-97-0002 Page 6 of 8 (3) Corrective Steos Which Will Be Taken to Avoid Further Violations The Engineering Request process will replace the Problem '
Evaluation /Information Request (PElR) for the purpose of engineering evaluations.
.(4) Date When Full Comoliance Will Be Achieved -
, Waterford 3 is currently in full compliance.' The above corrective action will be I i
completed by 9/30/97.
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l ATTACHMENT 1 '
l ENTERGY OPERATIONS. INC. RESPONSE TO THE VIOLATION IDENTIFIED IN ENCLOSURE 1 OF INSPECTlON REPORT 96-13 l VIOLATION NO. 9613-04 10 CFR 50.55a(g) requires, in part, that inservice testing to verify operational readiness of pumps and valves whose function is required for safety be accomplished in accordance with Section XI of the ASME Boiler and Pressure Vessel l Code.
Contrary to the above, as of October 29,1996, the licensee failed to verify the operational readiness of certain valves whose function is required for safety in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.
Specifically, the licensee failed to perform testing which ensured the operational ,
readiness of manually operated dry cooling tower isolation valves used to maintain 1 the safety function of the ultimate heat sink during the design basis tornado event.
l l This is a Severity Level IV violation (Supplement 1). (50-382/9613-04) )
RESPONSE
(1) Reason for the Violation The root cause of this violation is believed to be insufficiently explicit design- l basis tornado event documentation. The documentation was not specific !
enough to readily allow the IST plan reviewers to conclude that the Dry l Cooling Tower inlet and outlet valves had a safety function and should be included in the IST program for testing. These valves were not included in the IST plan during initial IST plan development, during the IST design basis document (DBD 24) reviow, or during the current (although not completed) review of all ASME Class 1,2, and 3 valves.
A contributing cause for this violation was that the reviewer did not examine all l of the available design basis tornado event documentation during the current IST plan review process. It is believed that had the reviewer examined the calculation related to the design basis tornado event, he would have
- concluded that the Dry Cooling Tower inlet and outlet valves should have been in the IST plan.
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Attachm:nt to VV3F1-97-0002 Page 8 of 8 (2) Corrective Steos That Have Been Taken and the Results Achieved The Dry Cooling Tower manual inlet and outlet valves were successfully l tested per IST requirements on 12/7/96.
(3) Corrective Steos Which Will Be Taken to Avoid Further Violations
- 1. The Dry Cooling Tower Manual inlet and outlet valves will be included in the IST program.
- 2. A review of the design basis tornado event will be performed and the design basis documents will be revised, as necessary, based on the
! results of the review.
l 3. The IST basis document will be reviewed by the appropriate design engineering disciplines in support of the development of the IST plan for the second ten interval. -
(4) Date When Full Comoliance Will Be Achieved l
Waterford 3 is in full compliance. Item 1 will be completed by 1/31/97, item 2 will be completed by 8/31/97 and item 3 will be completed by 12/1/97.
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