|
---|
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
~
~ 13-ifS-A20 APPENDIX C
(- ~
PS SO 4 '
P GW s>!7 "~S ~
R
+
6, h.
<MBA LIG HT
/ 317 SRRONN NE'SV "3 R - =~ P 0., BOX 6"3PO ORLEANS, LOUISIANA 70l60 ~ ( 0') 95.31CO Feb:ua:y 21 LaSa 43P89-0028 A4.05.
QA L'.S.. yuclez". Regulzcory Co.=-.'ssion ATTN: Docu;enc Conc".ol Desk
~ash'ngton, "..C. 20555 Subjecc: Pacer'."Ord 3 SES Docker No. 50-382 L'cense .'to. NP:-38 Gene=ic .Leccer SS"-14 Gencle=.en:
The yHC 'ssued Ge ne". ic Lec-e" 88-1 4 3 T ~
a Sw ~ wrtpR Pe ~ ~
r h r Supo s
~ R ' Sv5 ePR p oo1 e~s
~ Pp Pt OP' Re" zced:-"u',".en: o'n Au zus: S, lo 88 c~e
'c: ecc 3 4'2 s -o -.ecues: cha- l'ce..s ees ."eviev arose o
( anc a ~ 'h' a des gp. anc opec2c'np s ve: = 'ac'on 0:.
ve Czz Oa ~ 4'zs ces-:hac ac:
Co RwP lS a
~ PRO ins.c"u=enc ' cons'ac.lc Css Cne i~pap ~ u aC S eCO ~lenC2C OP.S N OC Pd v cu2 co 'pone .Cs se=ved.
e".i =ca='on chat nzincenance p".ac"'ces, e~e".gency procecu".es, and t"aining a"e aceoua"e co ensu"e chac sa=ecy-".ela:ed ecuip=ewe v ll
.unccion as 'ncenced on 'oss o= insc".u=enc a'".
P ~ ecR 'ca= 'on .hzc che des'gn o che en" '."e insc".u en'i." svsceq nc uding a '." o". oche" pneuaacic accu=ulztors 's 'n acco".dance l;ich
'cs incended .unc:'on, inc'ud "..g ve".ificzcion by case chac ai=-ope".ate 'z=ety-relaced co-ponencs vi pe::o".= as expecced 'r accordance ~i:h a design-'oas's evencs, including 2 loss oi che no a 'ns " =enc a'" svs-e=.;h's
~ r X cesign ve"'='ca-ion shou'd
'ac
~
zn 2. alys s 0 cu .enc 2'pe 2 ed co"poner.c :zilu: ,pcs':icns eou ed sa ecv u,c ons.
ve chey a e co ec S.oc assu g To pe o che a bove, 2 "ulci-discipline cask :c."ce '-zs o".=ed :o "eviev, eva' a-e aro ".es po"c co che gene"'c le =e". '.".'s task =orce cons- sceo o:
-.epre sencz='ves G. Ope ac oa s, P Ore"2 o..s Suppo and Assess=enc ('.:OSA ) Nuclea" Opera:'cns anc C ons:"uc ='n (NOETIC) ano L'cens'ng.
I 3 cll oo(
AN EQUAL OP>ORTUNt 7 EMPLQyER>> 3
~3-i1S-A20 APPENDIX C Page ?
t'3PG9-0028 February 21, 1989 The attached response has been divided into rhree (3) sections corresponding respect.'ve'y to the above.
has been included as a preface to the response.
esc"';stem Shoulc you recuire add 'ona'nfo .ation please
'
p f ee .ree to contact me or L.4'. Laughl'n, S'te Licensing Support Supe viso., at (504) 4/4>>'i4o<
- i. 's response s submitted zs recuired under a'"d avi- v under prov's.'ons c:
Section 182a of the Atom c Energy Act of 1954, as amendec Very tru'y vours, R. 7 Bu-.
~
Hanage". sk'afety Nuclear 6 Regulatory Ac=
R.=3: O~C: ss:
c ~ar n) YRC Beg on IV D.L. 'Vigginton, NRC-YPZ P~C Res'dent nspecto"s 0 =ice L ~ 'lavic
~ ~
Stevenson
13-MS-A20 APPENDIX C UNITED STATES OF AMERICA NUCLEAR R GULATORY COMMISSION In: ie matter of Loui s i ana Power E L ioht Company Docket No. 50-382 Vater ord 3 Steam Electric Station AFFIDAVIT R. F. Burski,being duly sworn, hereby deposes and says that he is Nuclear Safety and Reoulatory Af airs Manager of Louisiana Power 5 Lioht Company; that he is duly authorized to sion arid file with the Nuclear Regulatory Commission the attached response to NRC Generic Letter 88-14; that he is ami liar with the co'ntent thereof; and that the matters set forth therein are true and corre to the best cf his knowledoe, i n fo ri".ia t i e n a n d b e l. i e f .
~ ~ r ~ J R... Qursiii Nuclear SafetY 5 RegulatorY Ai fairs-Manage.
STAT. OF LOUIS lAHA)
I
)ss PAR.'SH OF ORLEANS )
Subsc.ibed and sworn to before me, and S"ate ibove named ioBQ h s ~'!.c'ay a Notary Public o
inpnd =or the Parish kllAQ f ~
r No arv Pubol ic My Cor,'l ss 'on expl res
13-MS-A20 APPENDlX C 4'Ag"=".-.OP& 3
".:-PO!lS" 70 G:.!i:.~"'C i".:".."; SS-14
~'3PB & -002S
13-MS-A20 APPENDIX C SYST Mi DESC.".IP; ION e 'instrument air system at Waterford 3 0'rov
's des'"ned to ' reliabl supp lv v of clean, c1 dry, oil-free air for pneumatic instruments con" rois and contro
'
and pneu.-,.a 'cally operated valves during no "mal p'lant L I p oper ol era won. ine h
inst.rument air system, serves no safetv !unc 'on. Air operated valves tha are requ'red for safe shutdovn and'accident m t'gat on are rovided '
safety re la t ed accumulators.
The instrument ai. sys em consists of:
two orizon a1, o'l-free,'ing'e stage, ro" ary air comoressors t1:o air drver assemblies 1-ith pre- ano a" er- ftors one ver ica air rcce:ve ace ins t lumcnt a'omD css or Dackage cors sts o=. an 'n1et comoressor, mo stur seoarator hea ex""z-e " and c'sc'"a "g f' ice 1
on . e e p c..ag s
'- d.:scharged .'r;to he instrume"t ai" rece.ver bv coa.mon header. The air then Dasses through the ai" 'ter/drver a s s e...b 1 es norma 'Dc t'ns a p- cssu c voce'o + 'S be '~e en A ~
p rec ver ~ ~
be o ';C:- Dsig, the second i"stru" "- a = co=.presso. starts au orna t'a ' 1 1~ ~ oe ~ ~ <<o
ii
'0
~li
13-MS-A20 APPEHDIX C drop below 100 ps' c.oss connec- valve between the ins rument -um an s-ation air s ys~ems opens al owing stat 1 ~
on air to he'" ma'n- -n ain instrumc air sys em pressur.. The se vice air is introduced ups ream of the instrument air receiver and the air f'1-er/drver assemb?mes release note that at waterford 3 .he station and instrument air compress a re ident.ical uni t.s. The on?y diffe ence in systems is that the station air svstem does no have air filter/dryer assem'olies..
The ins rument air filter/dry
./ e" assemb4);'es a'e provided with an .automatic biomass which opens wnen drver ou let oressu"e 11 s b elow 1 o.> psig. A s- aine: is installed in ;n the . 1 er/drye. biomass 1'ne to coarse filter th ax Anrunc ia ion is prov.'ced in the ct:" rw} room for the follow.'ng'ondit?ons xr.s- rument, Rec 'ver Pressure Ei/::o Irstrument Compressor A(3) Trip/Trou'ole Irst"ument 4 v Compressor A(B) Separa-o Level ri/Lo
.nstrument D~va+ (( <<), v oub o Ins- rume" t Erver Bi~assed I .st ument Ai . ressure Backup Valve Ooen
'ns=r ment Compre sor A("=) oc':: c 0 =
Va ve Opera<or N. Backuo Actuated/Troub?e
13-MS-A20 APPENDIX C E en though .they are not saie~y-re1ated, the instr~ant air coL'pressors supplied pover frora sa.'et@ buses. If a loss of of site pover occurs t
'nstrw.. nt air conpressors trio. They can be nanually reconnected to th emergency diesel gene a-o s at. the con -ol roon's d'screticn
~
g
0
~O
13-HS APO APPEHDTX C SECT<OÃ I A list vas p-e p a-ed - o~. aiil safe y re aced s
'L 1 ai" ope."aced components.
list consisted of }73 valveses and dampers. Purchase specifications for majori y of the above ~ere reviewed for air qual'ty a '.ty requirements. They specified on'y c'ean, drv ai>> 'h The major manu acturers vere also conta~
to determine if there ~as any '~'"
speci..'c air oual'ty i reouremen s for the equipme.. Thev con" c n. rmed ti.at he only .eouirement +as for clean t r a L4 ~
The purchase s pec'iica.ions for the ins"susen aiir supo u j'ystem i.e.
comp."essors, drvers, e'c., ~ere then reviewed for ouali-y reouiremen-s o:
he d'scharged air. Tho on'v reouiremen-s ver to provide cLean, dry ai:
The pre-operational startuo flush orocedures (5:'2".-00} ;".=ough'005) co>>
ihe ins r~~ent ai sys- m ~ere reviewed..The acceotanc Io partic a" e anc organics ~e e as follows:
~ ho pa t cula e 0'" ll be l? rge than 1/32 'inch bv }/} 6 'ch vhen ? i>> 'I C amoled th ough a r es.ail>> ro a '"u<<ee Th s}s.em piping shall be free of o>>ganics as ve"'-"'ed b 1'c,
>gn e sa Dle =<<e r o
.hes: criteria ve e doc zen ed zs met.
~ 1
~ ~ 13-MS-A20'PPENDIX C
T e pre-operat'onal startup test procedure (SPO-23-001) >-'as a 1so revieve(
The acceptance c"':
- c. ~e 'a for f the instrument a'r d~'e <as an outl et de~o:
temperature o. -40 degrees .= or .lo>-er. Th's cr'e ion ~as doc"scented as met.
~ ~
prior to the issuance of Gene ic Lecto: 88-]4, waterford 3 did not have a instrument air sampling p! og .am. In response to th's letter a sampling program 'has been initiated.
.c as reviewed applicable instrument air system dra>: ngs and ident'fie enti ie those headers which feed the majoritv of the sa=etv-re>ated a'r ope"ated 7 o... t..'s, .' n (.5) loca"ions vere then ident'=ied at >:hich >
dra~ samples. Samo'es v'll be taken ~rom 've (5) sample'po nts at leas-once each re.'uel'ng c,c>e on a .ro a n" basis. In this >:ay all '.5 points
>:i>l oe samoled onc ev rv three re:ueling cycles. A co . ac'a.s b n a~'arced to an outside laborator., to analyze these sampl s. In oroer to ob='a.n su table sano'es for analvs.'s spec.a sa.-.p 'ng eo 'pment is recu'ed. Th's eouipment 's oescr."oed below'.
samo 'ng pro ecuiooed .-i h aciustzble =los me=er and filters o>>>:e'ucleopore teo a" bag eou.poed >." -h isolation vaLve hyg rome te
!he aooroor a test oroc dure J instruct personne'o>- and >:here o cra-
-he a ~
= sam" es, be .. plac p 'o to the n xt re=u '." ou=ag
13-HS-A20 Al thou h th
'PPENDIXin'rocedu P C
e is not co specia t'est procedu.e on Mork author =at'o ion (V') ~ 010~"052 <as 1ssued to perform t..e nitial instrumen air sampl'n"6 Tne ai sample draL:n during, this,t e analy"ed for moisture, particulate and hydrocarbons. The acceptance,criter a are as follows:
Particulate 10 microns DeLaoint -10 Hydrocarbons 3 ppm The accep
.installed drve-conL.itiors Co 'l ance
'>>'ere cr te 'a .or part culate e..'ltf'> o- size ' o.
revieMeo and used to 10 was based micrcns.:or dete~'n" on the deLpoint
. e acceptance presentlv l oca 'ii
c c"i-eria.
The nydrocarbon accentance cr<<te-ia L:as based on in'o.mat on "rom-the sta <<u l Lisil packages ~ Because the compressors are an o'l:ree type, no oi: l o hycrocarbons vere foL!nc 1n 'tne 0 na ':ll'sh samples. The th" e (3) ppm acc p"ance c='-eria L:as baseo on i this L."th a ig t aOL:ance for s 1.'
natu:al hacky"ound leve s of methane.
s no. fo" hydrocarbons L:ill be per=ormed du"'r o "his s pec a . tes <<. <<Lnd
<<hp<<L oni<<c a ter a maior-svstpm ...Od'a 8 A-c'- 'on, '.e. Comoressor "e emer.
d <<p <<p<<<< iL <<e. :l ----,
ci- <<pp L:a-
~
r-ring t>~e om-r sso.s. Lhe oryers are an act<<vated cess" can- typo. SL t. 0Guc 1 on o 0'1 'nto the 'ns-r ~cot a'r sys e.-. = ro" hese c omponents is no. cr c-ble.
- h " ore, pending s t's ~ p ~~ >
- ur-he-hydrocaroon testi-- c:i be per=c=.ec excep as =rev ous'y s<<a" ec
~O 4i
13-'HS-A20 APPENDXX C pie'or 'the special tes- <as taken on reb"ua iPPa an n,'iso~en al Industr al Research Associates (zg> ) fc analysis..The resu'ts resul s o the air sar..pie are no expected before this
~
response is due 'to the hRC. Thhere.ore, vxth n 30 aays of rece'pt, LP&L iill proi'ide he hVC a s" a event of o -~ " "3 'ins rv~ent-ates.ord Mat .
'
air quality.
0 4i
13-HS-A20 APPE';1DIX C S t.C. ioN
.; -
i . vas prep- ed of the maj or instrument air system components
..aintenance LI procedures', cal'bration procedu es and "e"e 't've tas 's for these components vere identified and reviewed for adeouacy This reviev, as veil as compressor flov tests vhich shall be discussed furt,he. in Sec t.ion Iii, ident,i ied several deficiencies. The vendor manu.
used to reMork the Hash sh air ai compressors +as found to be inadeouate. kith vendo. assistance the ve ndor d manual vas revieved and the deficiencies <e:
'
iden"- .'.ied. This, manual to be revised to incorporato the necessarv
~
's in:orma icn. To ensure the adeouacy of the upd'a ed manua'n:ormation, this in:ormation ~'as utilized to revork a stat.ion a'r compressor, vhose vu put, had degraded. (HOT:.: 4'a er:ord 3 uses he same mode! Yash compresso. in bo"h he .'nstrument and' 2 on a',stems. ) The rosult that comp essor capacity vas eturn d to an accep 2 le eve Arother prob em assoc.'ated vith the above vas a 1a ck.. o= post. ma'n" enance flo~ testing. rior t.o hose concuc=ed in.December 1488 f>ov t,es-s ve e not pe =ormed tollovi"8 epa.'rs or over'"au's of 'rstrument or se";'c a'-
coiip essors ~ T>e eou reme" ts to oer=orm a ovine compresso ma n-enance vil be incorporated 'nto the appropr'at,e procedures. Ho otho" d ='c'encies vere id .",= = ed ~ ~4 ~ 4 eem+O
~~ ~ air syste.. comoonen procedur s.
1
0 0
0
13-HS-A20
~ . be above,
<< APPENPIX C procedures cal'b"a ion main enanc p occdli c5 and repetitive tasks for tbc safety related ai" o~e rate d coc:ponents Mere revie'ed for a 'eouacy. !io maior deficiencies <<ere d"scov "c' 5 revie<<'. Seve .al e.. ancemen s vere iden-'cd and are bei.
eing eva'uated fo p ssible 'mnleme." ation ~L ~
A review o= no.mal, emerg ncv and off-normal ope"at'ng proce ures Mas pe..o.med o, dete. ...'ne <<'hich addressed or need ed t, o a ddrress actions fol11.oving loss of instrument air. In addition to the nine (9) Emergencv Operating Procedures tbe folio<<'ing f ive (5) procedures Mere iden 'd
.-->00-vOn, An" nciator Response for Con rol Room Cabine 0".--:00-00"-, Annuncia or Response :or Control Room Cabinet H Or-.OO-OIO, ns ~nn nc'a or Response for Con rol Room Cao n .t
, al v,c ion 0""-G".-0 c em s . i z Os>
~
r..
~ ~
istem do - od as potent'a de='c enc'es. They a e p eseia ~v bc g v'c<<'~c <<.itb Operzt,'ons pe sonnel. Appropr'a-e proce 're
'm em c by the nex re=1-'e1-n outage for those items con= rmec as de='c nc es.
- l. 0."- OG-Oj0 noes no cou' bio<<oo<<n oC thc ls umcn 2 5:stem oo<<ns oa<< o= the cryers << "enever the 'nst 1' 5 A' i'c assec I -2
13-MS-A20 APPENDIX C Maintenance personnel, excluding engin and superviso."s, receive gene".
o'a o.'ant svste= ra.ning and spec. fic raining in the'" resnectiv 1 a, d
i.e. e'ectr'cal. ho spec': c train.ng zs given h main e" ance craft.
personne'egarding loss of instrument ai. and/or he e'a ed procedures.
Tnis t:ain- ng vou'.d not be relevant to the duties these indiv duals are expected to perform.
Engineerih g personnel includ ng Hain enance eng neers and superv'sors air system train'ng under
're o fered inst,rument the "system of the month tra'n'ng p.ogram. Th s tra'n'ng not on'y covers svs em and component operating parameters but also provides training on the follow'ing procecu es:
Ope.a 'ng Procedure G."-"3-015: Instrument Air Svstem Qf c norma p ocecu e Qp-001 03S: gns ument A~ Svs<<em
,Hal u<<action Th.'s train'ng has bee" reviewed and considered adeouate =or these ind'iduals.
Opera tions personne as pa o the ": cense trai" ng <<ece'e svstem an o =-normal procedure training. They also receive simulator rain'ng involvl..g loss 0 ' s u e 2'evie~ c: t..'s ra'n ng has oeen performec ano fou"d o be adeo ate
13-MS-A20
/ APPENDIX C SECTION III A review of the instrument air supp'ly sys em ias pe. formed bv LPSL. The ability cf th'e system to supply the required ouanti-y ard oua litv o f ai r was reevaluated. Testing was also performed to determine the present condition of the equipmcnt.
As previously discussed in Sect'on I, the only air ouality requirements for the supply system or air operated components are clean, dry air. The acceptance criteria established in the sampling procedure wll satisfy these air reou'ments. It is anticipated tha 'when the results of the initial a'amp e are rece'ved,. =he accep"ance c".'r" will be a met.
Ins'um .".: a'" comoressor des'gn and pe" ormance were rev'ed. Tne or'ginal system design reouired the capacitv of each comoresso. to.be 80 SC.=.'l at I00 PSIG. Compressor capacity tests per ormed n Dec mbe 1988 showed t..at bo-h:nstru.=ent z = coc:pressors were operat'ng at considerably less than th.s capac. y. A deta'led analysis pe =o~ed by LPcL determined tha- the plan- a'r de-and was approxi=ately 280 SC~.
The operation of the fter/drver assemblies was also reviewed. ach as sem'olv
'
rated a 360 SCW. anile in ope ration, each ' -e "/drve-assemoly recuir s approxi-a e'y 60 SC:... cont nuous: ow for regeneration.
This 'regeneration flow is d'scharged to atmosphere ano 's there'ore los-
.rom the system. Comp essor output 's sp between the two assemblies.
.xcept .cr mai"t "a"ce pe .ocs, both dr;ers are conti "ous'v r se v ce Th's mea "s a regeneration f 'ow o approximate>v '."0 SC:..".. s cont-'=uouslv los- -o atmospnere.
4
iO
~li
~O
13-MS-A20 APPENDIX C Civen z system demand o. aooroximately 2SO SC-" >>d 'er/dryer purge require=ents of app ox.mately I?0 SCQ, a total of approximate} 400 SC:,
needed for no.=al plant operation. In their p.esen condit.'on "oth compresso"s are reou. red full time to meet the ~io<< re r oui uirements. vnce compressors are reworked one compresso" ope"a 'ngg fu>1 t'ime 2nd another load ng intermittent}y should provide the required flo<<. Re<<ork of the instrument air compressors Mil'e completed bv the nex r e fueng outa ge To reduc compressor demands, the possibility of using one fi'lter/drver assembly at a t me. s being considered. Full flo<< through one assemblv h:
been attemoted 'th t..sat
~ith u". s actor's resu ts. ihe pressure aron across the assemblv exceeded vendor recor:.mendations, The cause of the p"essu"e ""or a eros s the .'V e /d-yye. zssem' '~j
/d 's be'rg inves iga=ea.
4 Deperding on the results oi th's investigatior., -he use of a single assemoly <<'ith the other in standby is being co,.s.dered. This should reduce the re "eneration f'.o<<'oui cmen s cons c 2 i the bv 0 c s'ng compressor oemancs Nni evaluating system performance, ter=' several i-ems <<hich could increase svstem re'iao'1-'v <<ere dentified. These ite. s vi 'e evaluated ~or possibl '..corpo "at on. Thev zre as o 0'<<'s:
Replace IQ m econ drye a e rs <<'i th 0. 3 micron absolute 41 o>> s.
Install au" omztic drain vzlves ".. -he drver .~r = e-
13-HS-A20 APPENDIX C Install manual drain valves on instr"went and "serv>>ce air recc'e s
- 4. ~
R.- cva lua 1 ua e the .i ter/dr,'er bypass setpo'nt value.
On the basis o~ the above evaluation the ins "ument
. e~
ai svstem is meet
~ ~ ~ ~
its intendended~ .unc.ion; providing adequate amounts of clean, dry air. Ei Mith the compressors at less than rated capac'tv, the sys em's performan is adequate to satisfy plant requirements.
The system as p i descr." ption. .
iit v "
Seve.al S
is p.esent.y operating vas compared to the i
minor disc epanc es ~ere found. As E'SAR previous>v svsrem discuss d seve- al1 ideas for possibly increas ng system reliability and/c c ency ~ere identi'ed durin~ s~'s em rev' rev ev. Tnese i"e...s are curren:
being evaluated for pos s.'ble inco po a ion. A te maYing the i'na1
( determina system, the on >>s
""S.~R to which,
~ill i'ny, of the above then be revised to make necessary c:ill be acded to the correc-'ons and ref'ec all enhancements.
As stated in Se -on i, ka e":ord 3 has lI3 safetv-related valves and dampe s o e aure positio, olLO<'g 'oss 0 Ls um t c, 0 eac, component vas ident'ied. This 4'as -. en compared to the actua'omoonent C>>ai~ u pos tio ~a ~ P ll comoonents a ed to the reouired oos'ion
. er'od'c surveiances a e per=o med o ensure valv operaoilitv.
addition -o ths, a. ope ated comoonen s ~ere success=u~ ~y- este'r lo ~
- o. nstr e nt air and po~er during pre-ope a ional s-artup s---
I ~
"=a c'"
component ~as ested nc vtoua' as par= o= s resoec ve svs-em's pre-operational tes-.
13-MS-A20 APPEND IX C
~ ~
A ~ur ihc v rrcv1 cw oi c above comDoncnts was perfo=med t.o dete ine wh recc'ved an ".""'Cd Sa ety .caturc (r~ ~
) ac-uat on signa'. The s igna and correspondn' p os
' tion .or each component was iden'i ied. The positions these c o mpone is were recuired to move to on th e<<a ir ICSDeCt1Ve actuation si s.'gnals were ver'fied t.o be correc . Th ese va've ooerations ar ested periodically unde. the following surveillance procedures.
OP-903-02o Safety Injectaon Actuation Signal Test S
OP-903-032, Quarter}y'ISI Valve Tests OP-903-033, Cold Shutdown ISI Valve Tes s OP-903-036, Contairment Spray Ac uation Signal Test OP-903-040, Containment Isolation Actuation Signal Test OD op"3-00477, eEmergency reedwate" Ac uation Signa> Tes-
. -.03-09},
ops no Pecirculat'on Actuation Signal Tes OD opr poo n Steam Isolation Actuation S go a Test OD<<O03-094 <<Sr AS SL<<~g oL' Re av ~est - Ooera ir.g OP-cp3-OoS <<<<w aS Subg ouD Relav Tes- - chutdown A review of a>>
11 sa etv-re 1aied valves was a~so ~e"=ca e d. o ioenti-y which were scrv.'ced bv accu=ulaiors. 1h'y tour (34) valves use n'troge..
accu-u'ators and 24 are provided with air accumu>ato"s rout (4) othe" componen s, t.o be addresseo la e- th'n is section, we e loen eo as need'ng fur h " eva'nation
.c 'as reviewed -hee ce c s'~n oi he nitrogen acc ~u aior systems. ~no-e 4
a e te acc'-.u a ors 'c se."'ce ~~'valves. These accumu'ato-s we veri=ied to be of su= 'c "= s'"e to sat'sfy the tim ana stro):e eou'e~e SDeCt-ve va veS. T DA
. c ~
a so r viewec des'gr.
13-MS-A20 APPENDIX C ravings to verify ha he seismic and pipi"g class reouirements ~e"e e
correct o" the ni rogen acc -ulator systems. These vere ound to be acceptable for the'r in ended 'unc ions it snould be noted ha- the seismic oualif'cation of individual comnonen a"sociated vith valves and/or valve operators, i.e. filter regula ors I electric/pneumatic transducers etc., ~ere not reviewed. This 'individual
.-omponent record sea. ch and verifica cion +as determ'ned to be bevond the scooe of Gene<<ic Letter 8S-14.
Ai" accumulators .are ins-alled on 24 valves. The function of these 24 valves vas re-reviewed to determi"e their reou re,.enrs for operat n post acc.oent. Oi tne 24 valves, only 2 (Si 602A c 3; Safety injection Rec rculat.'on Sump Outle Va ves) ~'ere reou red to change position fol oiing loss o: instr ment air to mitigate the conseou nces of an acc" den . One (:) valve (CC 620; Fuel ."ool'ieat ".xchan"er Temnerature Control 'Halve) reo "red an accumulator on'y to close o 'ts " a C p II pos'"ion oa loss o=:ns-r went a "... For the rema'ni"g 2l valves, position they fail to o loss o= ins" rument a' +as determined to be a S?.~e pos t oa ~ . Th se valves are not reouired to chang ~"om th s pos't'on for sa=e shutdown,or acc'cen mitigation. The'" respect ve accumu 1
- a. ors, ther ore per=orm no sa:ety-related fuse- ons assoc aced v',
~
'
va 've a ua '...'ough 'av be co..ve ent 0 . ?. Ooe ? 'a a s andpo.'nt to opera e hese 2'. valves olloving loss o: ns=rument
't. 's no reou'rec. acc .ators 'or t"ese 2l va ves are there ore 0 t:-.is g " ric e==er a"c <
a review o capaci y, seismic and,piping class requirements
( vas performed bv LPSi. and found t.o, be adequate as is.'
ir 'accumulators assoc '
ted with valves SI 602A c 8 were sized t o all each valve to cycle once vithin an hour of losing,instrv~ent air. This v verified by test in Augus, 1958 unde WA 99000219. However, during desi review, the possib litv these valves may need to operate bevond the prese:
60 m'nute limi:t vas identified. This situation is be'ng reviewed further by LPc 'nde." P oblem Evaluation/In ormation Request (PEIR) 10673.'uring th above reviews, four (4) additional components were 'dentified
~
whose position for an Eng'neered Safety Pea ure (ES:-) actuation signal is differen from 'ts loss oi instr'~ent air posi-ion. These componen s either co no- have accumulators or have ones that have no be n tested.
Th v a.e:
SVS 101 a 1C:; Sv -chgea .",akeup Dampers cV )54A 6 3; Feedvater lsolat'on Valves c ves 8 l54 c" QL st close on 2 ma n steam 'solation s- gnal ( e'S) ese vz ves have small accumulators as pa = of he'r ooera o assemolies but are not leai: tes-ec. This situat'on vas r v ewed by Lpe . The D Q' g la o valves w 173A a 8 and h s a 1 ocA cc c'csed or. a 1oss of ns rumen air. There'o.e, e cva-er rso 2 '.. va ves 1 154A ='v. I n valves i 2 r: 1 as is 0 loss o s "Ie
~
s
~
I ~r. d anc ' 160A cx 3 vi 1 c'ose. Surve' 'arce test 'ng o these va 'es to insure ope.ab y .'s discussed later in his sec=.'o".
o
4>
13-MS-A20 APPENDIX C SVS )01 6 102 arre .a' open daupers <<hich Mere original'y d esigne to clo oa a safety injection ac uation signal (SIAS). These components do not have accv".ulators. ~T under PE'H. 10672, has r evieMed the above and det'ermined t.he SIAS LPaL, I~S to these comnonents is not re"v.'ed q 'or sa.e C "s'tdo<<n oc o e plant or to mi". gate the consequences of an accident,. Therefore the fail open position on loss of'nstrument air is acceptable.
Leak testin g of the. a ccrmulator systems had only been performed on the nitrog n accumulators. During startun th e ten (10)
( ) nitrogen accumulators vere tested in accordance <<ith SPO-25-001. 'g Du"'ag ope ope ra t.'n, surve "at.'r i lance procedure OP-903-032 leak t,es ted t,he t<<'o check valves asso'ciat.ed <<'ith each accumulator system. 'A revieM of th's procedure ident'ied a need to reevalvat.e the test durat on and acceptance cri er'z Tes req "'remen:s,nave be .". re-eva'lua ec anc the above procecure <<'i' be rev sed. T<<o (2) separate tests <<'ill no<<'e pe" ormed on each n'trogen accumulator. The fi st is a check valve one aoi3.'"v -est to be ner'o~ed onc a ovarter. Th's is a functional t.est -o nsure the check va'ves are not stvck in the onen pos'on.
Th secondd 's a sys" em leakage 'test <<h ch <<'i1l b e per:ormed once everv 18 months P'ach nitrogen accumv1 a nor <<'> ll be rsola ted rom ' res res'pec i'e al and n'rogen sources for a prede ermned t'me. Any eak'ng components
<<"; th' the test boundarv <<ill be id n
"'
ec. P t he end'=
pressure crop and s'ubsequent leakage for the acc aula o" <<i11 b>>
ae e rmined. T"is ~ s ~
I \A i 11 oe aaoed o svrve': la" ce -roc dur>>
O~-o0.-033
~O
~
i i
13- MS - A20 APPENDIX C As discussed earlier in this is sect on, only hree (3 of the 24 valve,s vi "ir accumula o s are, Mithin the scope of th's report and require testin"6 Tne accu-u'ator leakage tests for va'ves SI ~
60'>'
1 B ave been added to have t surve llance proce'dure OP-903-032. The fa 1 safe position of valve CC 6 is closed. It has no safety rela ed requiremen to move from th's posi.'on.
os 1" on The only furction of the accumulator is to fail this modulatii valve closed on loss of instrument air. A leak or caoacity test is not applicable in this instance. To ensure valve operability, a func ional test <<'hich fa'ls air to the valve and veri ies closure <<ill be pe" orme once every )8 months. This functional test <<ill also be part, of 0>-o03-0".".
As nreviouslv disc"sse" sc ssed, . e c osing o: valves "4 173A & B and .""w'66A 6 a's
.'n loss of 'nstrument used in lieu of leak. testing the accumulators on >'84A a 8 To nsure he above, a runct:ona'est <<'hich 'as a'" to
-he ""~ ]73A c 3 and o.~ a 3 and ver.' es closure <<'ill be performea onc every'co'c shutdo<<n. .".' functior.a 1 test <<ill be pa>>" o- QP-903-033.
The above chan~es'"
ng -'e
<<.ill ncorporated in o su ~eillance procedu h es
..d 0 ".0~"0.~ by the next re=ue"g outa complct on c" these pr o cedure revxsaons, test ng Mall be aaeouate to censure oo o '. o tho requ red accumulator systems
'0 II 0
13-HS-A20 APPENDIX C
- 2. O?-901"038 does not s those components +hose pos1txon on an EST signal is d'i..e.ent than it s failure posi-ion on a loss o Inst um Air
- 3. Neither 0?-901-038 nor 0?-500-OOS .e:erence th e ir. a ab3.e Spent r"u<
Pool seals.
0?-3-016 d'id not. describe how to set the purge ra e on the Instrumen Air Dryers.
0 ~ OP-3-016, Step 6.1.11 onl y reou'res bio~down o. the sys em ~
in during st.rtup through SA-1271 and IA-140. "h's ti 7 .'s is satis=ac-ory if no mois ur is oiscove.ed dur ng bio+down. .f mo's-ure 's found, thea additional bio~doc:n at o her point.s may,be necessa.y- .'o ensu e t ere is no moisture in the svstem.
The .mergencv Ooerat ng ?roc dur~ (EO~) csee."'is p
PS~ 404-A(3) and PSL 406-A(B). The Unique Ãumbe iden" i=ication (U'i D) num'oers .or these va'ves have beea changeo t,o. S L 8004-A(3) ant SSL 8006-A(3).
~
A cv ec: o the tra'ning rece:ved by Operations, ."maintenance and
~
Engineer'ng persona > ias per=ormed. .he re'"'ei ~as to de erm'ne which groups rece ved or needed to rece ve train'ng rela- d to a loss of
'rs :,ument ai" even= and "he adecuac" thereof