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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits1999-06-24024 June 1999 Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits ML20196G5731999-06-24024 June 1999 Forwards Operator Licensing Exam Outlines Associated with Exam Scheduled for Wk of 991004.Exam Development Is Being Performed in Accordance with NUREG-1021,Rev 8 ML20212J4121999-06-23023 June 1999 Responds to NRC Re Reconsideration of EA 98-022. Details Provided on Actions Util Has Taken or Plans to Take to Address NRC Concerns with Ability to Demonstrate Adequate Flow Availability to Meet Design Requirements ML20196E9371999-06-22022 June 1999 Forwards Revs Made to EP Training Procedures.Procedures NTC-217 & NTC-217 Have Been Deleted.Procedure NTP-203 Was Revised to Combine Requirement Previously Included in Procedures NRC-216 & NTC-217 ML20196A1021999-06-17017 June 1999 Provides Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Per 990513 Request of NRC Project Manager ML20195F3671999-06-0909 June 1999 Forwards Rev 21,Change 0 to EP-001-010, Unusual Event. Rev Reviewed in Accordance with 10CFR50.54(q) Requirements & Determined Not to Decrease Effectiveness of Emergency Plan ML20195C7801999-06-0303 June 1999 Submits Response to Violations Noted in Insp Rept 50-382/99-08.Corrective Actions:All Licensee Access Authorization Personnel Were Retrained Prior to Completion of Insp ML20195C2951999-05-28028 May 1999 Forwards Annual Evaluation of Changes & Errors Identified in Abb CE ECCS Performance Evaluation Models Used for LOCA Analyses.Results of Annual Evaluation for CY98 Detailed in Attached Rept,Based Upon Suppl 10 to Abb CE Rept ML20195C0241999-05-28028 May 1999 Notifies NRC of Operator Medical Condition for Waterford 3 Opertaor Sp Wolfe,License SOP-43723.Attached NRC Form & Memo Contain Info Concerning Condition.Without Encls ML20196L3281999-05-24024 May 1999 Informs That Entergy Is Withdrawing TS Change Request NPF-38-205 Re TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection Submitted on 980629 ML20206S4691999-05-17017 May 1999 Requests Waiver of Exam for SRO Licenses for an Vest & Hj Lewis,Iaw 10CFR55.47.Both Individuals Have Held Licenses at Plant within Past Two Year Period,But Licenses Expired Upon Leaving Util Employment.Encl Withheld 05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.31999-05-14014 May 1999 Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3 ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J1471999-05-0606 May 1999 Requests That Implementation Date for TS Change Request NPF-38-211 Be within 90 Days of Approval to Allow for Installation of New Monitoring Sys for Broad Range Gas Detection Sys ML20206J1721999-05-0606 May 1999 Notifies That Proposed Schedule for Plant 1999 Annual Exercise Is Wk of 991013.Exercise Objective Meeting Scheduled for 990513 at St John Baptist Parish Emergency Operations Ctr ML20206G8021999-05-0404 May 1999 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-382/99-01.Licensee Denies Violation as Stated.Change Made Is Denoted by Rev Bar & Does Not Materially Impact Original Ltr ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20205T2531999-04-22022 April 1999 Forwards LER 99-S02-00,describing Occurrence of Contract Employee Inappropriately Being Granted Unescorted Access to Plant Protected Area ML20205R2611999-04-20020 April 1999 Forwards Rev 19 to Physical Security Plan,Submitted in Accordance with 10CFR50.54(p).Plan Rev Was Approved & Implemented on 990407.Rev Withheld,Per 10CFR73.21 ML20205Q3241999-04-16016 April 1999 Submits Addl Info Re TS Change Request NPF-38-215 for Administrative Controls TS Changes.Appropriate Pages from New Entergy Common QA Program Manual Provided as Attachment to Ltr 1999-09-07
[Table view] Category:UTILITY TO NRC
MONTHYEARW3P90-1505, Forwards Proposed Operator Licensing Exam Schedule & Proposed Requalification Exam Schedule,Per Generic Ltr 90-071990-09-17017 September 1990 Forwards Proposed Operator Licensing Exam Schedule & Proposed Requalification Exam Schedule,Per Generic Ltr 90-07 W3P90-1163, Forwards Relief Requests Associated w/10-yr Inservice Insp Program Per Section 50.55a(g)(6)(i) of 10CFR501990-09-0606 September 1990 Forwards Relief Requests Associated w/10-yr Inservice Insp Program Per Section 50.55a(g)(6)(i) of 10CFR50 W3P90-1191, Responds to Violations Noted in Insp Rept 50-382/90-15. Corrective Actions:Tech Spec Surveillance Procedure PE-005-004 Will Be Revised to Ensure That Normally Closed Valves Opened & Verified to Close for Toxic Gas Signal1990-08-31031 August 1990 Responds to Violations Noted in Insp Rept 50-382/90-15. Corrective Actions:Tech Spec Surveillance Procedure PE-005-004 Will Be Revised to Ensure That Normally Closed Valves Opened & Verified to Close for Toxic Gas Signal W3P90-1194, Submits Fitness for Duty Performance Data for 6-month Period from Jan-June 19901990-08-29029 August 1990 Submits Fitness for Duty Performance Data for 6-month Period from Jan-June 1990 W3P90-1184, Responds to Violations Noted in Insp Rept 50-382/90-14. Corrective Actions:Local Leak Rate Test Activities Shall Be Administratively Controlled to Require Use of Test Method Other than Pressure Decay1990-08-20020 August 1990 Responds to Violations Noted in Insp Rept 50-382/90-14. Corrective Actions:Local Leak Rate Test Activities Shall Be Administratively Controlled to Require Use of Test Method Other than Pressure Decay W3P90-1187, Forwards Booklet Entitled, Safety Info - Plans to Help You During Emergencies, Recently Distributed to General Public1990-08-17017 August 1990 Forwards Booklet Entitled, Safety Info - Plans to Help You During Emergencies, Recently Distributed to General Public W3P90-1189, Forwards Waterford 3 Steam Electric Station Emergency Preparedness Exercise for 901024. Annual Exercise Will Be Performed Using Control Room Simulator1990-08-17017 August 1990 Forwards Waterford 3 Steam Electric Station Emergency Preparedness Exercise for 901024. Annual Exercise Will Be Performed Using Control Room Simulator W3P90-1162, Forwards Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-19951990-08-16016 August 1990 Forwards Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-1995 W3P90-1174, Forwards Rev to Emergency Plan & QA Program,Consisting of Chart Indicating Changes to Util Organization1990-08-0707 August 1990 Forwards Rev to Emergency Plan & QA Program,Consisting of Chart Indicating Changes to Util Organization W3P90-1177, Forwards Revised Objectives for Emergency Preparedness Exercise Scheduled for 9010241990-08-0303 August 1990 Forwards Revised Objectives for Emergency Preparedness Exercise Scheduled for 901024 W3P90-1164, Forwards Waterford Steam Electric Station Unit 3 Basemat Monitoring Program Special Rept 3. Rept Documents Continued Integrity of Basemat as Verified by Program from Time of Inception of Monitoring in 1985 Through Mar 19901990-08-0303 August 1990 Forwards Waterford Steam Electric Station Unit 3 Basemat Monitoring Program Special Rept 3. Rept Documents Continued Integrity of Basemat as Verified by Program from Time of Inception of Monitoring in 1985 Through Mar 1990 W3P90-1167, Forwards Rev 12 to Emergency Plan Implementing Instruction EP-001-001, Recognition & Classification of Emergency Conditions, Reflecting Name Change of State Agency to Louisiana Radiation Protection Div1990-07-19019 July 1990 Forwards Rev 12 to Emergency Plan Implementing Instruction EP-001-001, Recognition & Classification of Emergency Conditions, Reflecting Name Change of State Agency to Louisiana Radiation Protection Div W3P90-1148, Responds to NRC 900503 Submittal Concerning Review of Util Rev 6,Change 1 to Inservice Testing Program for Pumps & Valves1990-07-17017 July 1990 Responds to NRC 900503 Submittal Concerning Review of Util Rev 6,Change 1 to Inservice Testing Program for Pumps & Valves W3P90-1143, Advises That 900404 Request for Addl Info Re Tech Spec Change Request NPF-38-103 Will Be Provided by 900803.Change Will Extend Test Frequency of Channel Functional Tests for ESF Actuation Sys & Reactor Protection Sys Instrumentation1990-07-0606 July 1990 Advises That 900404 Request for Addl Info Re Tech Spec Change Request NPF-38-103 Will Be Provided by 900803.Change Will Extend Test Frequency of Channel Functional Tests for ESF Actuation Sys & Reactor Protection Sys Instrumentation W3P90-1379, Provides Notification That Util Has Consolidated Operation of All Nuclear Facilities,Effective 9006061990-07-0202 July 1990 Provides Notification That Util Has Consolidated Operation of All Nuclear Facilities,Effective 900606 ML20044A5541990-06-26026 June 1990 Forwards Response to Generic Ltr 90-04 Requesting Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20044A5551990-06-22022 June 1990 Describes Changes Required to Emergency Plan as Result of Transfer of Operations to Entergy Operations,Inc. Administrative Changes to Plan Necessary to Distinguish Support Functions to Be Retained by Louisiana Power & Light W3P90-1365, Provides Notification of Change in Operator Status Per 10CFR50.74 Due to Entergy Corp Consolidating Operation of All Nuclear Generating Facilities,Including Plant Under Util1990-06-19019 June 1990 Provides Notification of Change in Operator Status Per 10CFR50.74 Due to Entergy Corp Consolidating Operation of All Nuclear Generating Facilities,Including Plant Under Util ML20043G3431990-06-14014 June 1990 Requests That All NRC Correspondence Re Plant Be Addressed to RP Barkhurst at Address Indicated in 900523 Ltr ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043F2621990-06-0606 June 1990 Requests Withdrawal of 900504 Request to Extend Implementation Date of Amend 60 Re Transfer of Operations to Entergy,Inc.All Necessary Regulatory Approvals Obtained & License Conditions Implemented ML20043C1861990-05-29029 May 1990 Submits Response to 900426 Comments Re Investigation Case 4-88-020.Util Issued P.O. Rev Downgrading Order of Circuit Breakers & Eliminating Nuclear Requirements ML20043E5441990-05-24024 May 1990 Forwards Public Version of Change 1 to Rev 2 to EPIP EP-002-015, Emergency Responder Activation. Release Memo Encl ML20043B3501990-05-23023 May 1990 Forwards Response to Concerns Noted in Insp Rept 50-382/90-02.Response Withheld ML20043B3781990-05-23023 May 1990 Requests Change in NRC Correspondence Distribution List, Deleting Rt Lally & Adding DC Hintz,Gw Muench & RB Mcgehee. All Ref to Util Changed to Entergy Operations,Inc.Proposed NRC Correspondence Distribution List Encl W3P90-1314, Requests NRC Concurrence That Design/Controls/Testing to Minimize Potential for Common Header Blockage Acceptable Per 900510 Meeting.Tap Alternatives for Shutdown Cooling Level Indication Sys Discussed1990-05-21021 May 1990 Requests NRC Concurrence That Design/Controls/Testing to Minimize Potential for Common Header Blockage Acceptable Per 900510 Meeting.Tap Alternatives for Shutdown Cooling Level Indication Sys Discussed ML20043B3271990-05-21021 May 1990 Forwards Justification for Continued Operation Re Taped Splice for Use in Instrument Circuits,Per 900517 Request ML20042F5251990-05-0404 May 1990 Requests Extension of 90 Days to Implement Amend 60 to License NPF-38 in Order to Provide Securities & Exchange Commission Time to Review Transfer of Licensed Activities to Entergy Operations,Inc ML20042E5501990-04-17017 April 1990 Responds to Request for Addl Info Re Feedwater Isolation Valve Bases Change Request Dtd 891006 ML20012F4551990-04-10010 April 1990 Forwards Rev 10,Change 4 to Physical Security Plan.Encl Withheld ML20012F5491990-04-0606 April 1990 Advises That Util Installed Two Addl Benchmarks for Use as Part of Basemat Surveillance Program to Increase Efficiency of Survey Readings.New Benchmarks Will Be Shown on FSAR Figure 1.2.1 as Part of Next FSAR Rev ML20012F3181990-04-0606 April 1990 Forwards Util,New Orleans Public Svc,Inc & Entergy Corp 1989 Annual Repts ML20012E8971990-03-30030 March 1990 Submits Results of Evaluation of Util 900414 Response to Station Blackout Rule (10CFR50.63).Station Mod May Be Required to Change Starting Air Sys to Accomodate Compressed Bottled Air ML20012E2551990-03-27027 March 1990 Responds to Violation Noted in Insp Rept 50-382/90-01. Corrective Actions:Qa Review of Licensed Operator Medical Exam Records Conducted & Sys Implemented to Track Types & Due Dates of Medical Exams Required for Operators ML20012E0511990-03-27027 March 1990 Forwards Rev 10,Change 3 to Physical Security Plan.Rev Withheld ML20012D5461990-03-22022 March 1990 Forwards Documentation from Nuclear Mutual Ltd,Nelia & Nuclear Electric Insurance Ltd Certifying Present Onsite Property Damage Insurance ML20012D4911990-03-21021 March 1990 Responds to NRC 900208 Ltr Re Violations Noted in Investigation Rept 4-89-002.Corrective Action:Proper Sequence of Insp Hold Point Placed in Procedure Under Change Implemented on 880425 ML20012C0691990-03-14014 March 1990 Advises That Util Intends to Address Steam Generator Overfill Concerns (USI A-47) Utilizing Individual Plant Exam Process,Per Generic Ltr 89-14 ML20012C0421990-03-12012 March 1990 Forwards Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Results Not Reflective of Particular Calendar Yr ML20012B6731990-03-0707 March 1990 Responds to NRC Bulletin 88-011,Action 1.a Re Insp of Surge Line to Determine Discernible Distress or Structural Damage & Advises That Neither Surge Line Nor Affiliated Hardware Suffered Any Discernible Distress or Structural Damage ML20006F5321990-02-22022 February 1990 Forwards Payment for Order Imposing Civil Monetary Penalty in Response to Enforcement Action EA-89-069 ML20011F1401990-02-21021 February 1990 Responds to Violations Noted in Insp Rept 50-382/89-41. Corrective Action:Review of Independent Verification Requirements Re Maint Activities Performed ML20006F1731990-02-19019 February 1990 Forwards Corrected Pages 9.2-21 & 9.2-22 of Rev 3 to FSAR, Per 891214 Ltr ML20006E5781990-02-13013 February 1990 Forwards Third Refueling Inservice Insp Summary Rept for Waterford Steam Electric Station Unit 3. ML20006D0571990-02-0202 February 1990 Responds to SALP Rept for Aug 1988 - Oct 1989.Contrary to Info Contained in SALP Rept,Civil Penalty Not Assessed by State of Nv for Radioactive Matl Transport Violations.Issue Resolved W/State of Nv W/O Issuance of Civil Penalty ML20006C1631990-01-30030 January 1990 Requests Extension of Commitment Dates in Response to Violations Noted in Insp Repts 50-382/89-17 & 50-382/89-22 to 900222 & 19,respectively.Violations Covered Use of Duplex Strainers & Missing Seismic Support for Cabinet ML20006C1581990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13 Re safety-related Open Svc Water Sys.Instruments in Place on Component Cooling Water Sys/Auxiliary Component Cooling Water Sys HXs Which Connect to Plant Monitor Computer ML20006C1611990-01-29029 January 1990 Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Instructions for Determining Acceptable Refueling Boron Concentration Provided in Procedure RF-005-001 ML20006B4121990-01-26026 January 1990 Informs That Photographic Surveys Discontinued,Per Basemat Monitoring Program.Monitoring Program Implementing Procedure Will Be Revised to Reflect Change ML20006A7091990-01-22022 January 1990 Forwards List of Individuals That No Longer Require Reactor Operator Licenses at Plant 1990-09-06
[Table view] |
Text
,
P. O. BOX '60340 LO UISI POWER AN A
& LIGHT / 317 NEWBARONNESTREET ORLEANS, LOUISTANA 70160 +
(504) 595-3100 MIDDLE SOUTH urnmts system October 14, 1986 W3P86-2557 A4.05 QA Mr. George W. Knighton, Director PdR Project Directorate No. 7 Division of PWR Licensing-B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Waterford SES Unit 3 Docket No. 50-382 Detailed Control Room Design Review Final Summary Report Supplement
REFERENCE:
W3P85-1015 dated April 30, 1985
Dear Mr. Knighton:
By the referenced letter LP&L submitted the Detailed Control Room Design Review (DCRDR) Final Summary Report in response to NUREG 0737 Supplement 1.
Included in Volume 2 of the Summary Report was a listing of the human engineering discrepancies (HEDs) and corrective actions identified during the course of the DCRDR.
In implementing the various HED corrective actions scheduled for completion prior to completion of the first refueling outage it was evident that revisions to the HEDs, the corrective actions, or the implementation schedule were necessary in a minority of cases. It was also determined that a large number of HED corrections originally scheduled for the second refueling outage could be implemented prior to completion of the first refueling outage.
The following discussions are submitted as a supplement to the initial DCRDR Summary Report:
- 1. Invalid HEDs A total of 8 items originally identified as HEDs have been subsequently determined to be invalid:
HED: 92 241 110 267 182 304 202 324 The updated HED description pages along with the reason for declaring the HEDs invalid are included in Attachment 2. o
/\ CO 7 8610210236 861014 N DR ADOCK 0500 2 EQUAL OPPORTUNITY EMPLOYER i I
'Page 2 W3P86-2557
- 2. Accept As Is Five HEDs were re-evaluated and found to be acceptable as-is:
HED: '35 262 239 413 260 The updated HED description pages along with the reason for declaring the HEDs acceptable as-is are included in Attachment 2.
- 3. Defer to the Second Refueling Outage While.LP&L has made a concerted effort to complete the approximately 100 HEDs scheduled for completion by the end of the first refueling outage, limited engineering resources and lead time on replacement parts have made it necessary to defer implementation for five HEDs to the second refueling outage:
HED: 36 277 126 302 127 The updated description pages for these HEDs are included in Attachment 2. All have been assessed and it has been determined that no undue safety concern is present due to the deferral.
- 4. Implementation Uncertain by the First Refueling Outa_ge As the Waterford 3 refueling outage approaches and more safety significant modifications compete for limited engineering and technician resources, the implementation schedule for eight HEDs is -
uncertain:
HED: 81 234 176 272 224 321 228 323 These HEDs remain scheduled for completion prior to the first refueling outage; however, should the implementatien not be complete, the.HEDs will be placed on the forced outage list to be worked at unscheduled outages following the first refueling outage. The updated description pages for these HEDs are included in Attachment 2.
- 5. Early Implementation LP&L has made every effort to complete ~HED corrective actions for items not scheduled for completion until the second refueling outage.
A total of 38 second refueling outage HEDs will be complete by the end of the first refueling outage. These HEDs are listed in Attachment 1.
It is also worth noting that significant inroads have been made in completing second refueling -HEDs associated with the plant computer displays.
4 i Page 3 W3P86-2557 i I 6 .' Increased Priority I
l - Upon subsequent review, LP&L has increased the priority of one HED i
4
(#246) as noted in Attachment 2.~
j 7. Completed Through Revised Approach
'One HED (#99) has been resolved through a revised approach to the '
corrective action as noted in Attachment 2.
- 8. New HED The LP&L HED Committee, in a meeting following the submittal of'the i DCRDR Summary Report, has identified an additional HED (#416) as described in Attachment 2.
4 The above HED determinations were evaluated by the principal and affected members of the HED Assessment Team in accordance.with Section 10.2 of the DCRDR Summary Report. !
! As previously noted, the above revisions to HED corrective' action are dictated, in part, by limited resources and higher priority safety significant plant modifications. While the potential exists for not completing 13'HEDs as scheduled by the end of the first refueling outage, the scope of the 38 HEDs_ completed a cycle early far exceeds that of the incomplete HEDs.
I
! Should you require further information concerning the Supplement to the l DCRDR Final Summary' Report, please feel free to contact Mike Meisner at (504) 595-2832.
i Yours very truly, K.W. Cook Nuclear Support & Licensing Manager f KWC:MJM:ssf l 1
Enclosures I cc: R.D. Martin, NRC Region IV J.H. Wilson, NRC-NRR
, NRC Resident Inspectors Office B.W. Churchill l W.M. Stevenson j
1 I
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ATTACHMENT I Second Refueling HEDs To Be Completed By the End of the First Refueling Outage 123 162 230 142 163 232 143 164 251 144 165 288 145 166 289 146 167 291 148 169 293 149 170 294 150 1/1 297 151 172 298 152 173 404 153 178 405 156 179
ATTACHMENT 2
CORRECTIVE. ACTIONS HED NO.: 0035-GUIDE NO.: 5.4.1.C CATEGORY: 3 FINDING:
'Two scales on the Reactor Core vessel level (CP7) are imposed on the same axis of this recorder. From bottom to top, the recorder reads 0-100 and then another 0-100.
RESPONSE
The recorder is appropriately labeled. The green pen indicates the Head Level while the red pen indicates the Plenum Level. These readings are sequential and not concurrent. Because the operators have used this recorder without any problems, it is recommended that this recorder should not be modified.
IMPLEMENTATION:
Accept as is.
A-1
CORRECTIVE ACTIONS HED NO.: 0036 GUIDE NO.: 5.4.1.I CATEGORY: 3 FINDING:
Paper-speed adjustability on the recorders is not available. A high, paper speed option should~be provided to run out records for detachment. A lower speed should be available to permit adjustment of' the time scale so that rate-of-change information can be indicated.
RESPONSE
A variable-speed multipen recorder will be placed on CP2 which monitors Tave,'Tc, Start-up Power, and Tref. This modification, however, is not considered critical to operator performance.
IMPLEMENTATION:
By the completion of the second refueling outage.
l A-2 i
CORRECTIVE ACTIONS HED NO.: 0081 GUIDE NO.: 4.1.2.A CATEGORY: X FINDING:
The clock above Panel CP2 is not permanently mounted. It is subject to falling and could damage or inadvertently actuate controls on the reactor panel. It could also cause personal injury.
RESPONSE
A clock will be permanently mounted in the control room.
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not completed, this enhancement will be placed on the forced outage list.
A-169
I I
CORRECTIVE ACTIONS .
HED NO.: 0092 GUIDE NO.: 2.1.2.B.6 CATEGORY: INVILID FINDING:
The telephone vertically mounted on CF2 is in the way of the operators.
When'an operator is using the reactor panel, the phone is an obstruction which prevents him from moving back and forth in front of the instrumentation.
RESPONSE
It has been determined that this HED was based on the isolated opinion of a minority of operators. Subsequent discussions with Operations personnel have identified no further concerns over the telephone location, nor was there a preference to relocate-the telephone.
IMPLEMENTATION:
Accept as is.
l t
l 3
A-129
i 4
s
- CORRECTIVE ACTIONS 1
HED NO.: 0099 i
GUIDE NO.: 2.1.6.E.2 CATEGORY: 2 i
1 FINDING:
Audio gain controls on the P.A. system are not limited to preclude reducing volume below an audible level, a
i i-
- RESPONSE
1
~
The recommended change to limit the capability to reduce the volume on the j{
public address system below an audible level has been completed by
. Executive Directive ED-017. Periodic sound surveys of the public address
- system will be conducted.
i i
IMPLEMENTATION:
Fix complete.
1-i i,
l 1
A-4 t
._ _ _ . . .. -, ....___,.,yg,_. , _ _ . , . , _ , . . . , . , , ,. _,,_.c .,y...._,, ,-_m-..,-_,-.._m., , _. . . _
CORRECTIVE. ACTIONS HED NO.: 0110 GUIDE NO.: 5.1.3.A CATEGORY: INVALID FINDING:
The lettering on some of the horizontal meters is too small (3/16") to read from the required viewing distance.
RESPONSE
This HED is considered to be invalid because the character height of 3/16 inch meets the NUREG-0700 character height guideline for a viewing distance of 30 inches.
l IMPLEMENTATION:
Accept as is.
l i
I i
A-5
CORRECTIVE ACTIONS HED NO.: 0126 GUIDE NO.: 2.1.6.E.1, 2.2.6, 3.2.1.A CATEGORY: X FINDING:
The auditory signals (annunciator horns) do not provide a value of at least 10dB(A) above average ambient noise. In fact the speaker volume exceeds these annunciators.
RESPONSE
All annunciator horns will be modified so that the volume is acceptable.
Due to limited ~ engineering resources and replacement material availability this HED is being deferred to the second refueling outage. An assessment has determined that no undue safety concern exists due to the deferral.
IMPLEMENTATION:
By the completion of the second refueling outage.
A-137
.. = _ - ____
CORRECTIVE ACTIONS HED NO.: 0127 GUIDE NO.: 3.2.1.D CATEGORY: X FINDING:
The average volume of annunciator horns is 71dB. All individual horns deviate from the average more than the +/-2.5 dB recommended by NUREG-0700.
4 i
RESPONSE
~
All annunciator horns will be adjusted to a level 10dB above ambient (HED i 0126) and within +/-2.5dB from the average volume. Due to limited
! engineering resources and replacement material availability this HED is
] being deferred to the second refueling outage. An assessment has l determined that no undue safety concern exists due to the deferral.
i IMPLEMENTATION:
i 4
By the completion of the second refueling outage.
i r
l t
I i
l A-148
CORRECTIVE ACTIONS HED NO.: 0176 GUIDE NO.: 3.3.4.A CATE~'"Y: X FINDING:
The " Blowdown' Tank Drain Pump Trouble" annunciator tile (CP1-E-D19) is ambiguous to the operators.
RESPONSE
The title will be re-engraved based on the operator comments.
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not complete, this enhancement will be placed on the forced outage list.
A-158
CORRECTIVE ACTIONS HED NO.: 0182 GUIDE NO.: Validation I CATEGORY: Invalid.
FINDING:
f Presently the system is not sensitive enough in measuring tube leaks and isolation steam tube rupture isolations. There should be an improvement of the steam.line radiation monitor for det'ction e of low level radioactivity during tube rupture, i
j RESPONSE:
An engineering analysis has been performed to determine radiation instrumentation needs~during a SGTR. The Blowdown Radiation Monitor (see HED 260) will provide sufficient sensitivity to determine the location of a tube rupture.
IMPLEMENTATION:
Accept as is.
1 e
4 l
< A-6 i
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+ m--.-... .- - - . . ._-.._,......,-r ._.___m- --y m --. - . , . .
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, CORRECTIVE ACTIONS i
i HED NO.: 0202 a
GUIDE NO.: T.A. HTS, PZR10
\ [
i.
l~ CATEGORY: Invalid i
FINDING:
i l The pressurize proportional heater meters (CP2) are labeled " current" but
, actually measure power.
1 i
a I
RESPONSE
This meter reads current and not power; and therefore, should not be relabeled.
s ' IMPLEMENTATION:
1 Accept as is.
4 i
k 1
1 i
i 3
4 A-/
i 1
L
_.. ,,. . . _ . . . . - , _ - ,-__,.-m.m. -,__.___ _,m., . , . , . m_. .. .-_-m.,,. , ,., y-_.3, ,mm.,. , - , ,,, y
CORRECTIVE ACTIONS HED NO.: 0224 GUIDE NO.: T.A. PWR13, CTS /11 CATFCORY: X I
FINDING:
i The ranges and divisional markings of each containment pressure. CIAS, and CSAS meter should be standardized, p
I
RESPONSE
Communication with the operator has determined that-the CIAS and CSAS Containment Pressure meters should be similar in range and numerical j progression in order to quickly determine actual pressure. The range for these meters will be 0-30 psia, i
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not completed, this enhancement will be placed on the forced outage list. l l
1 4
A-8
, --- . ~ , , .. ., , -
CORRECTIVE ACTIONS HED NO.: 0228 GUIDE NO.: T.A. D17 CATEGORY: X FINDING:
The setpoint meter on the steam bypass master controller (CPI) should be identical to the process meter on the same controller.
RESPONSE
This will be investigated and modified if product availability allows. If no other meter scale can be added it will be reevaluated.
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not completed, this enhancement will be placed on the forced outage list.
A-63
CORRECTIVE ACTIONS HED NO.: 0234 GUIDE NO.: T.A. PZRll, 2, 3, 9 CATEGORY: X FINDING:
The Pressurizer Level recorder should be a dual pen recorder as opposed to a single pen recorder. This additional information would allow the operator to compare trends on both X and Y Channels on the same recorder.
RESPONSE
The Pressurizer Level recorder will be changed to a dual pen recorder.
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. It not completed, this enhancement will be placed on the forced outage list.
t A-87
CORRECTIVE ACTIONS HED NO.: 0239 GUIDE NO.: T.A. PWR 18 CATEGORY: 3 FINDING:
The operators need a blowdown radiation level monitor recorder for the steam
. generator on cpl. This trend information assists the operator in the performance of his duties.
RESPONSE
There is a live radiation reading every 10-15 minutes from a RAD monitor display which will be on CP6. A Blowdown Radiation recorder for the Steam Generator on CPI will not be added. Trend information is considered not necessary, and very little room is available on CPI for placement.
IMPLEMENTATION:
Accept as is.
i A-9 l
I
CORRECTIVE ACTIONS HED NO.: 0241 GUIDE NO.: T.A. RCll, EL7 CATEGORY: Invalid FINDING:
Two 6.9KV voltage meters should be added to CPI to assist the operators in confirming that power is available.
RESPONSE
Power unavailability is already annunciated on CPI due to 230KV line undervoltage. Voltage on the bus can be determined by the presence of lights in the appropriate vatthour meter located in the control room.
IMPLEMENTATION:
Accept as is.
A-10
CORRECTIVE ACTIONS i
HED NO.: 0246 CUIDE NO.: T.A. PWR 13 CATE0GRY: 1 FINDING:
.Four " Containment Vacuum breaker pressure isolation valve" indicators are
> needed on CP18.
RESPONSE
Containment to Annulus DPT containment header valves'CVRISV-401A
- . (2HV-E634A) and CVRISV-401B (2HV-E633B) open and closed position indication will be included in the control room in accordance with Regulatory Guide 1.97, i
a w f
2 IMPLEMENTATION:
~
By the completion of the first refueling outage.
1 i A-11 i
i
. -- , . -- , - . . , - . . , _ _ - - - . , . . , _ , . ..-..._,~,__,,..,_m., . ~ , . . .. ._,,,,..-...m..,_,_.-.,..m.-..,m r, ,- , . . .~ -
' CORRECTIVE ACTIONS HED NO.: 0260 GUIDE NO.: A1.06, T.A. PWR18 CATECORY: X FINDING:
Response to the operator survey indicated that the blowdown radiation f
monitor controls.need to be designed so that the operator can switch alignment to the opposite steam generator. This would aid the operator in determining which steam generator had a tube leak.
f
RESPONSE
Further review has determined that identification of the affected steam generator can be accomplished by selectively isolating the steam generator blowdown sample flows either locally at valves SSL-8007A/SSL-8008A and SSL-8007B/SSL-8008B, or from the control room at valves SSL-8004A/SSL-8006A and SSL-8004B/SSL-8006B.
IMPLEMENTATION:
Accept as is.
l l
j A-3 l
4 E.
CORRECTIVE ACTIONS HED NO.: 0262 GUIDE NO.: Oper. Survey A2.01 CATEGORY: 3 FINDING:
Response to the operator survey indicated,that the controller.for the potable water shutoff valve on CP13 is not needed and is never used.
RESPONSE
This controlier will not be removed because it is required during potable water line breaks.
IMPLEMENTATION:
Accept as is.
A-12
CORRECTIVE ACTIONS HED NO.: 0267 GUIDE NO.: Oper. Survey A3.04, A3.13 CATEGORY: Invalid FINDING:
Response to the operator survey indicates a need for individual voltage indication for all busses on cpl. The computer is too slow and closed breakers do not necessarily mean that the bus is fully power or even energized.
RESPONSE
See response to HED 0241.
MPLEMENTATION:
Accept as is.
A-14
-. . - _. . -. =. -- - - -
i CORRECTIVE ACTIONS 1
HED NO.: 0272~
GUIDE NO.: Op Survey A3.10 CATEGORY: X 1
FINDING:
J Response to the operator survey indicated a need for a dedicated CVC Volume. l Control Tank Chart recorder. When the computer goes down, this indication
! is out, so the operator needs a dedicated recorder.
I
RESPONSE
~
f A CVC Volume Control Tank Chart Recorder wil1 be added.
I i
1MPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not completed, this enhancement will be placed on the forced outage list.
A-14
_ . _ _ _ _ _ . - _ _ ~ _
CORRECTIVE ACTIONS HED NO.: 0277 GUIDE NO.: Op Survey AS.01, C1.01 CATEGORY: X FINDING:
Communication between the control desk and the protection panel area in the back is impossible due to unnecessarily high background noise levels from CPC ventilation fans on CP21 and CP22. This fan noise bleeds over into front panel area and creates background noise. The RPS noise is a consistent high problem concerning normal verbal control room communication.
RESPONSE
Various methods of noise reduction which could lower the background noise levels between the control desk and the back panels have been investigated.
A significant portion of this noise is attributed to the high speed CPC ventilation fans on CP21 and CP22, in the general area of these two panels, the noise level is 72-82 decibels. This fan noise interrupts verbal communication between the front and the back panels, but will not pose any problems to health or cause any potential hearing loss. In addition, the working environment in the front panel area is relatively quiet. Because of the interactive effects of vibration, velocity and heat, it will be necessary to conduct further studies into the trade-offs between these threa variable. These analyses will be initiated after the first refueling outage.
IMPLEMENTATION:
By the completion of the second refueling outage.
A-15
, CORRECTIVE ACTIONS i
i HED NO.: 0302 GUIDE NO.: B6.02, C1.02
~ CATEGORY: X FINDING:
Emergency alarms, i.e.. plant fire, plant emergency alarm, controls should be near plant operator console.. The low volume of the first alarms makes j them difficult to hear at a distence.
i t
t
RESPONSE
} The fire alarm auditory cignal levels will be adjusted to an acceptable j level. The acknowledge buttons are in the control room and are accessible
- to'the operators. Due to limited engineering resourcrs and replacement j material availability this HED is being deferred to the second refueling outage. An assessment has determined that no undue safety concern exists due to the deferral.
t i
I IMPLEMENTATION:
'By the completion of the second refueling outage.
f I
i 4
I
! A-33 4
4
, . - - - , - ,m. _ . . . , _ , , . . . _ . _ _ , _ . . _ ~ , . _ _ , . _ _ . , _ _ . . . - . , , _ . . . . . _ . - . . _ _ . - - . _ _ , , - _ _ . , . . , _ _ . _ - _ _ . - - _ - - _
CORRECTIVE ACTIONS HED No.: 0304 FJIDE NO.: B6.04 CATEGORY: Invalid FINDING:
On some HICs, it is difficult to determine what the output or setpoint should be since a 0-100% setpoint may not correspond to a 0-100% valve stroke or whatever output is controlling.
RESPONSE
This HED is invalid because the output and setpoint meter indications should not be correlated on a one-to-one basis.
IMPLEMENTATION:
Accept as is.
A-16
CORRECTIVE ACTIONS HED NO.: 0321 GUIDE NO.: C3.02 CATEGORY: X FINDING:
CP2 panel K ESFAS annunciators can lead the operators to believe that actuations have occurred which may not have occurred.
RESPONSE
Alarm actuations will be modified to match actual PPS actuations.
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not completed, this enhancement will be placed on the forced outage list.
A-45
CORRECTIVE ACTIONS HED NO.: .0323 GUIDE NO.: Oper. Survey C6.03 CATEGORY: X FINDING:
CP18 annunciator panels SA and SA Row A column 1, 2, 3, 4, 6, 7, 8, 9 are very confusing engravings. " Seal Water" is engraved on the tiles when the actual affected parameter is "CCW".
RESPONSE
These annunciator tiles will be reengraved.
IMPLEMENTATION:
Prior to the first refueling outage if time and resources permit. If not completed, this enhancement will be placed on the forced outage list.
4 A-47
CORRECTIVE ACTIONS HED NO.: 0324 GUIDE NO.: Oper. Survey C6.04 CATEGORY: Invalid FINDING:
"RCP Seal Water Low" annunciator should actually be " Seal Cooling Flow".
RESPONSE
This annunciator tile does not exist, therefore it is invalid.
IMPLEMENTATION:
Accept as is.
A-17 1
m.+-*
CORRECTIVE ACTIONS HED NO.: 0413 CUIDE No.: 5.2.1.B CATEGORY: 3 FINDING:
Three meters at.LCP43 contain superheated and subcooled values. Add positive and negative signs on the meters to clarify this.
RESPONSE
Positive and negative signs will not be added to the meter faces. These are considered by the operators as being unnecessary additions to the control panels. The scales are already labeled with the abbreviations "SUPHT'.' and "SUBCOOL." which is considered sufficient indication.
IMPLEMENTATION:
Accept as is.
-i A-18
I COR'RECTIVE ACTIONS HED NO.: 0416 GUIDE NO.: E0P VERIFICATION CATEGORY: 2 FINDING:
The scales on the Reactor Core Saturation Margin temperature recorders on CP-7 depicts temperatures that are not valid.
RESPONSE
The scales should be modified to read the appropriate Saturation Margin temperatures.
IMPLEMENTATION:
By the completion of the first refueling outage.
A-19
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