Responds to Generic Ltr 91-06, Resolution of Generic Issue A-30, 'Adequacy of Safety-Related DC Power Supplies.' Each Div of Dc Power Distribution Sys Has Common Alarm Window on Control Room Panel CP-35ML20085K180 |
Person / Time |
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Site: |
Waterford ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
10/24/1991 |
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From: |
Burski R ENTERGY OPERATIONS, INC. |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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REF-GTECI-A-30, REF-GTECI-EL, TASK-A-30, TASK-OR GL-91-06, GL-91-6, W3F1-91-0601, W3F1-91-601, NUDOCS 9110300189 |
Download: ML20085K180 (10) |
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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
.
.O YB ENTERGY '"I'"*""*""""'
i it.F,Dueski W3rl-91-0601 A4.05 .
QA October 24 1991 U.S. Nuclear Regulatory Commission -
ATTH: Document Control Dock Washington, D.C. 20555 Subjects Watorford 3 SES Docket No. 50-382 Licenro No. NPP-38 Genoric letter 91-06/ Resolution of Generic Issuo A-30 "Adoquacy of Safoty-Rolated DC Pwr Supplies," pursuant To 10 CFR 50.54 (f)
Gentiomont This letter is submitted in responso to Generic Lottor 91-06 1 issued April 29, 1991. The Generic Lotter f *L) requested responses to questions that would provido the staff with information to dotormine if any further action is required by Waterford 3_in resolution of Genoric Issuo (GI) A-30. The GI is concerned with adequacy of-safety-related de power in operating nuclear power plants, especially in the area of multiple and common causo failuros.
Attached you will find the completed onclosure from GL 91-06 (Attachment 1). The attachment contains supporting discussion where applicable for answers to questions that requiro como clarification.
Should you havo-any additional questions pleano fool froo to '
contact me or Oscar pipkins at (504)739-6707.
Very truly yours, A Sp
. RFU)QPPfdc 4 Attachment
//cof # R.D. Martin, NRC Region IV
- 7 D.L. Wigginton, NRC-NRR R.D. McGohoo N.S. Reynolds j NRC Resident Inspectors Offico
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91103oo199 911o24 . i noa noca: osocon2 P PDR {
-UNITED STATES OF AMERICA ,
NUCLEAR lil:GULA'IORY COMMISSION In tho matter of- )
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Entergy Operations, lucorporated ) Docket No. 50-382 3 Waterford 3 Steam Elect:4c Station )
i AFFil)AVIT l L.W. laughlin, being duly Aworn, hereby deposes and says that he is Manager, i Lleensing - Waterford 3 of Entergy Operations, Incorporated; that he is duly authorized to sign alul file with the Nuclear Regulatory Commission the attached Hesponno to NitC Genoric Letter 91-0Gt that he is famillar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief. ,
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LW%Ihughlin' /
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STATE OF LOUlslANA )
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Subscribed and sworn to before me, a Notarytubtip in and for the Parish und Stato above ucmod this 2 ye! day of O..#~/- , 1991. '
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ATTACIIMENT 1 10 CFR 50. 5 4 (f) Request - Generic Issue (GI).A-30 " Adequacy of Safety-Related DC Power Supplies" QuqEtions The following information is to be provided for each unit at each sito:
- 1. Unit Waterford 3 (Single Unit Plant)
- 2. a. The number of indopondant rodundant divisions of Class 1E or safety-related de power for this plant is 2 .
(Include any separato Class 3 E or safety-related de, such as any de dodicated to the diesel generators.)
Disegnaipa The two redundant power divisions are doulgnated the A battery / bus and B battery / bus. There is a third, safety-related de division (designated AB battery / bus) in the plant. Although thin AB division is not " redundant" to the A or 14 divisions, it does provido control power to 1E components which can Lo aligned to the redundant ac divisions.
In addition, the control power for tio breakers (from both redundant ac divisions to the An " swing" bus) and the Emergency Feodwater Pump Turbino controls are fed from the AB de division,
- b. The number of functional safety-related divisions of de power nocessary to attain safo shutdown for this unit is 1
Discueplsn Under certain equipment alignments, it is possible for the AB dc division to be supplying control power to components required for safo shutdown of the plant.
Por the W3 FSAR, this division is considcred safety-related.
- 3. Does the Control Room sit this unit have the following coparato, indopondently annunciated alarms and indications for each division of dc powor?
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- a. alarms NOTE: In - the caso of common alarms, an Auxiliary Operator dispatchod to the local panola would identify which of the pooniblo alarm initiatorn had activated the Control Room alarm. Plant Operations Proceduro OP-500-003 ontitled " Annunciator Res ponno Proceduro
-Control Room Cabinot C" providea the operator ,
with possiblo causos of alarms and recommended actions.
- 1. Dattery disconnect or circuit breaker open? Icn DIEGlD119.D!
Each division of the de power distribution syntom has a common alarm window on control Room Panel CP-35 (1.o. .
window "148" for diviolon "SA" bus, window "!11 0 " for division "SB" bus and window "!!9" for diviulon " SAD" 1:un) ontitled " Battery SA (SB or SAD) Troublo". The alarm in designed to be activated when oither of throo conditiono exists (1) the division battery disconnect switch is ,
opon, (2) a de bus ground exista on the division dc bun, or (3) an unoorvoltsgo condition exista on the diviolon de bus.
- 2. Battery charger disconnect or circuit breakor opon (both input ac and output de)? Ygg Discussio.D:
Upon opening of a battery chargor circuit breaker (input ac and/or output de), the control Room operator w111 got a common " Battery Charger Troublo" alarm on CP-35 Windowa LB, L9, L10, MB, M9, or M10 (a separato Window for each battery charger, with two battery chargers por de division bus) dependant upon the chargor involved.
- 3. do System ground? Xca j DitLGMER19.D:
Each division of the de power distribution system has a
- ommon alarm window on Control Room Panol CP-35 (i.e.
uindow "N8" for division "SA" bus, wi ndow "N10" for civision "SB" bus and window "N9" for division "SAB" bus) ontitled " Battery SA (SB or SAB) Troublo". The alarm is designed to be activated when either of throo conditions exist: (1) the division battery diaconnect switch in open, (2) a dc bus grour.d oxists on the diviolon de bua, J
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or (3) an undervoltage condition exists on the division :
do bus. Each load contor has a ground detector relay, 4 5 .
l the de systems operato ungrounded. A ground detector voltmotor is provided in each load center.
- 4. de bus undorvoltago? Its [
Dinguaoion f Each division of the do power distribution system has its own common alarm vindow on control room Panol CP-35 (i.e. ,
window " 11 8 " for division "SA" bus, window "1110" for ,
division "SD" bus and window "119" for tho " SAD" bus),' l which reads " Battery SA (SD or SAD) Troublo". The alarm 1 is designed to be activated whon either of throo conditions exists (1) the division battery disconnect ,
switch is open, (2) a do bus ground . exists on tho division de buu, or (3) an undervoltago condition exists t on the diviolon de bus. DC bus voltago indication is ;
available both in the Control Room (CP-1) and at the i local bus panols. -
- 5. dc bus overvoltago? Iqn D1R M M1.QD:
There-is an overvoltage alarm on each of the two chargers on cach of the de division buson (SA. SD and SAD) on ,
CP-35 in the control Room. Each alarm is a common window (L8, L9, Llo, MB, M9, and M10) ontitled "Dattery Charger (e.g. SA1) Troublo". The overvoltago alarm has shared inputs with the respectivo charger low voltago, no chargo, and ac power failuro alarms. DC --bus voltago motors are hva11able in the control Room (CP-1) and
-locally at the battery chargora.
- 6. Battery charger failuro? Yea l ningussion:
Control Room Panol CP-35 has an -- alarm window - ontitled "Dattery Charger (u.g. SA1) Troublo" for each of two ['
charf, s on each of the division de buses (SA, SD and SAD). The alarm actuators are high voltage shutdown, low voltago, high voltage, no chargo,-and ac power supply fhilure. <
- 7. Battery dischargo? Ica ,
Dlacussion:
i Control Room Panol CP-35 common "Dattery Charger Troublo" alarm has an ittput for "no chargo" condition. A local -
charger panel pilot lamp will illuminato to identify tho
r .
no chargo condition. Under a no chargo condition the de loads on tho affected bun would be nupplied by the battory in a discharging modo. The chargora are equipped with pilot lights that indicato a no chargo condition.
- b. Indications
- 1. Dattery float chargo curront? t(p Dl#C110.R12D*
Indication of battery float chargo current la not provided in thu control room. bocal panol indication 10- provided for this paramotor (DC EM-A3, 11 3 , and A113 ) . Th10 arrangement in considorod adoquato. Oporations performs watchstation curvoillancos, collectin., thin data from the local panol instrumontation on a por shif t bauin fer each battery chargor (DA1, DA2, SDA, SD2, SA111_ and SAD 2) . fho Control 1(oom Supervicor ,
reviewn watchntation logo on a por chift banis por oporationa Inntruction 01-004-000, l'I oa t chargo current is a paramotor that in unoful in normal operating modo. The paramotor in not one that tho- .
operatora nood to havo readily availablo- in an off-normal situation to analyze bun integrity- 4 during an accident. A common alarm window ontitled t "Dattory Chargur (bun identiflor)
Troublo" on control panol Cp-35 in the control Itoom in unod to alort the Control Itoom operators if a failuro ,
occurn on -n battery chargor. This alarm in also activated by the "No Chargo" input from the respectivo chargorn. Thorofore battory float chargo current in adoquatoly monitored without
. Control Room indication.
- 2. Battory circuit output curront? RQ Dincunajon:
Indication of battery output current :10 not provided in the Control Room. bocal panol indication of- this paramotor (DC-EM-A3, D3, AB3) in provided. This arrangement in connidorod adoquato.
Operations performa watchstation surveillancos, collecting data for this paramotor from the local
.panol instrumentation-on a por chift basin.- The Control Room Supervinor reviews - watchntation- logs on a por ohlf t . banis por Operationn Instruction ,
01-004-000. Alarma . are available to alert the Control Room Operatoro if a failure occurs on a battery charger ("Dattery Charger Troublo") .or if a >
battery djaconnect switch was opon("Dattery Trouble"). DC bun voltago lo available in the
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L Control Room (CP-1) and is the moro critical paramotor to havo readily available sinco it is a measure of the electromotive force available to operato the loads. The syntom can be adoquatoly analysed based on bus voltage readings. Thoroforo, a battery circuit output curront monitor is not necessary in the Control Room.
- 3. dattery discharge? Hg Discussinn:
Indication of battery dischargo status is not provided in the control Room. Local panel .
Indication of this paramotor is provided. Tho arrangement is considered adequato. " Battery -
discharge" is interpreted here as being a condition wherein de loads are being fed by a de safoty bus battery (charger not availablo). As mentionod above, the Control Room Operator would got a common
" Battery Charger Troublo" alarm on CP-35 windows '
L8, L9, L10, H8, M9, or M10 (a sophrate window for each hattery charger, with two battery chargers por do bus) dependant upon the charger involved.
Thoroforo, battery dischargo is adequately monitored without Control Room indication. The chargern are equipped with pilot lights that indicato a no chargo condition.
- 4. Bus voltago? Iqa piccussion:
DC bus voltage is indicated in the control Room on CP-1. Also computer points, which oxist for this parameter, are available to the Control Room Operators. l 4 c. Does the unit have written proceduros for response to the above alarms and indicationo? 192 Discuosion:
Operations Proceduro OP-500-003 ontitled
" Annunciator Responso Proceduro control Room Cabinot C" provides: guidanco for responding to annunciator alarms. Also, off-Normal Proceduro OP-901-055 ontitled " Loss of a 125v DC Bus" providos instructions to the operators for handling ;
asacciated plant conditions.
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- 4. Does this unit have indication of bypassed and inoperablo ,
status of circuit breakers or other devices that can ba used to disconnect the battery and battery chargor from its de bus ,
and tho battery charger irum its ac power sourco during maintenance or testing? Eca Diaquea1on Upon opening a battery charger circuit breaker (both input ac and output do) for maintenanco or testing purposen, the Control Room Operator will got a common "Battory Chargar Troublo" alarm on CP-35 Windows 1.8, L9, L10, H8, H9, or M10 (a separate window for each battery chargor, with two battery ;
charguro por dc bus) dependant upon the charger involved.
Each divicion of tho de power distribution nyatom has its own common alarm window on Control Room Panol CP-35 (1.o window
"!!8" for division "SA" bus, window "1110" for division "SB" bun and window "119" for division "SAB" bus) which roada " Battery SA (SB or SAB) Troublo". The alarm in doulgned to be activated when either of throo conditiono exists (1) the division battery disconnect switch in open, (2) a de bun ground exista on the olvision dc bus, or (3) an undervoltago condition exists on- the division dc bus. Thorofore if a battery disconnect were opened for maintenanco or tonting, thin alarm would bo procent in the Control Room. The Control Room also has coparato and indopondent computer point indication of battory disconnect switch status (e.g. D59921 125 VDC Pill 3A-DC-S Battery Disc)
- 5. If thu answer to any part of quantion 3 or 4 la no, then provido information justifying the existing donign features of the facility's safety-related do syntoms.
Discussion:
Support for existing design featuros adequacy in included 1 under " discussion" for annwora marked "no".
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- 6. (1) llave you conducted a review of maintenanco and testing activitios to minimizo the potential for human error causing more than ono do division to be unavailablo? len - and (2) do plant proceduros prohibit maintenanco or testing on rodundant de divisions at the camo tino? Len -
Disgussion Waterford 3 has recently comploted a procedurou upgrado program nn operations and maintenance proceduros. Tho upgrado program includod human factors considerations. Resultu of the upgrado offort are discussed in NRC Inspection Report ,
50-382/91-07. .
Watorford 3 controls scheduling maintenanco or testing on redundant de divisions by designating 'A' Train vooks and 'B' Train wooks for routino maintenanco and test activltion. The schedulo is reviewed by Scheduling, ti.o Operaticns coordinator, the operations. Superintendent, and- -the Maintenanco Superintendent. Planning and ncheduling proceduro (PLG-009-007) requires that any work on the schedulo requirity entry into a Technical Specification Action Statomont requiros-approval by the oporations Superintendant or designoo.
Approval is usually obtained at the Plan-of-tho-Day (pod) muoting. The Shif t Supervisor authorizos work and reviews for Technical- Specification applicability and rodundant train operability requirements.
If the facility Technical Specifications have provisions equivalent to thoso found in the Westinghouso and Combustion Engincoring Standard Technical Specifications for maintenanco and surveillanco, then question 7 may be skipped and a statomont to that offect may-be insorted horo. Waterford 3 Technical _S n qilications hate provisigng_qnuivalent to thqpo found in the Coml MD11on 2 IDginggrinti Standard Technical Snocification (NUREG-212) ..
- 8. Does this plant havo operational features t,uch that following loss of one safoty-related de power supply or bus:
- a. Capability is maintained for ensuring continued _ and adequato react,or cooling? Inn -
- b. Reactor coolant system integrity and isolation capability are maintainod?- 122-L
a
- c. Operating proceduros, instrumentation (including indicators and annunciators), and control functions are adequato to initiate syntoms as requirad to maintain adoquato core cooling? Xg2
- 9. If tho answer to any part of question 6, 7 or 8 is no, then provido your basis for not performing the maintenanco, survoillanco and tost procedures doacribed and/or the bacon for not including the operational features cited. *Soo note below. (!!oto that answers to questionn 6, 7 and a woro "you")
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