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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
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LOUISI AN A / 442 oe-0~oe erneer . m eaxewe POWER & LIGHT / NEW ORLE ANS LOUSANA 70174eOOO O 0504)366-234"5 MlOOLE SOUTH UTIUTIES SYSTEM February 6, 1984 W3P84-0288 3-A1.01.04 Q-3-A20.02.02 L.02 Director of Nuclear Reactor Regulation Attention: Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Waterford SES Unit 3 Docket No. 50-382 Response to Generic Letter 83-28, Item 1.2, Post-Trip Review - Data and Information Capability
Dear Sir:
The subject Generic Letter, in Item 1.2, requested a report describing the adequacy of equipment for diagnosing the cause of an unscheduled reactor shutdown.
Enclosed please find a description of the Waterford 3 capability for assess-ing sequence of events and analog variable time history both pre- and post-trip. When used in conjunction with our standard Post Trip Review this capability affords an effective means for diagnosing unscheduled reacter trips.
Should you have any questions or comments in this matter, please contact Mike Meisner at (504) 363-8938.
Yours very truly, 7
K. W. Cook Nuclear Support & Licensing Manager KWC/MJM/ch Enclosure cc: W.M. Stevenson, E.L. Blake, J. Wilson, G.L. Constable G402100237 840206 PDR ADOCK 05000382
((
l' A PDR 8
e CENERIC LETTER 83-28
~ '
1 i
1.2 POST TRIP REVIEW - DATA AND INFORMATION CAPABILITY
- l. Capability of assessing sequence of events.
j A. Sequence of Events is logged by a progran in the Plant Monitoring-Computer.
B. Attachment 1 is a list of computer points monitored by the sequence of events program.
C. Time discrimination between events is 5 milliseconds.
D. Sequence of Events hard copy format.
l l Point State Point I.D. Description Message Date -Time XSSNNTTT 30 CHARACTERS 8 CHARACTERS MM/DD/YYL HH:MM:SS.SSS The hardcopy printout is presented in time order, 1 entry per printed line.
E. When the first sequence of event file is 90% full it is j'
automatically. assigned to a printer device. Once the sequence of-events file has been auto-printed the contents of the file are no longer available. The operator may demand either the logging of the SOE's before the Auto-print condition' occurs or-the display of.
the SOE contents on one of the utility CRT monitors.
F. The power source for the Plant Monitoring' Computer is Non-Class IE Static Uninterruptible. Power Supply with Primary and Secondary Power coming.from Class IE safety related switchgear. -The battery
. will supply power for approximately 20 minutes on a loss of both
- primary and secondary AC supplies.
- 2. Capability for assessing the time' history.of-analog variables needed to determine the cause of unscheduled reactor shutdowns, and the functioning of safety related equipment.
A. Post Trip Review File
- 1. Post Trip' Review File is-. logged by a program resident in the Plant Monitoring Computer..
I i
1 .. .
- - ,= --. - ,, e . , e , , ~ , - - , , - -- , , n-.- , , x
283. Attachments 2 and 3 are the parameters monitored. The parameters in Attachment 2 are sampled every 2 secs and data is kept for 30 secs prior to and 30 seca post trip. The parameters in Attachment 3 are sampled every 30 secs and kept for 300 secs prior to trip and 300 secs post trip. The parameters were selected to monitor Reactor Trip parameters and Post Trip Engineered Safety Features Functions. The sampling rate is based on available Plant Monitoring Computer capacity with all other functions operating in a post trip environment.
- 4. Post Trip Review File hardcopy Format is shown in Attachment 4
- 5. Post Trip Review File will be maintained on a disk file with hardcopy capability on demand.
- 6. The power supply is the Non Class IE Static Uninterruptible power supply for the PMC.
B. Safety Parameter Display System (SPDS)
- 1. SPDS is a progran resident in the Plant Monitoring Computer.
- 2. The SPDS will monitor approximately 400 parameters, sampled every 1 second and stored for retrieval at a later time. The parameters are selected based on the requirements of NUREG 0737, Supplement 1. The selected parameters as well as a justificatioa for their selection will be detailed in the SPDS Safety Analysis report to be submitted to the NRC in the near future.
- 3. The SPDS Historical File will store data for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pre-event and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> post event.
- 4. Format for diaplay is shown in Attachment 4.
- 5. At this time it has not been decided whether the Historical File will be assigned to a magnetic tape file or a diskfile.
- 6. SPDS is a program in the Plant Monitoring Computer which is powered from a non-class IE Statis Uninterruptible power supply.
- 3. Other data is available from various sources listed below.
A. Core Protection Calculators (CPCs) store a snapshot of values in memory when a trip is generated. This snapshot information can be dumped to a printer during the post trip evaluation.
l' B. Control Board Recorders i Pressurizer Pressure 0-300 psia Pressurizer Level .0-100%
Hot Leg Temperature 50-750*F
. Cold Leg Temperature 10-600'F
. Reactor Vessel Head Level Reactor Vessel Plenum Level Subcooled Margin Reactor Power 200%
Reactor Power 2X10 ~g200%
Steam,_ Generator 1 pressure 0-1200 psia Steam Generator 2 pressure 0-1200 psia Steam Generator 1 level 0-100% narrow range Steam Generator 2 level 0-100% narrow range Containment Pressure -5 to 195 psig Containment Flood level 0-20 ft
- 4. There are no changes planned to Data or Information Capability at this time.
's y
?
s .
ATTACHMENT 1 SOE LISTING 1
OPERATING SYSTEM PTID EBASCO TAG DESCRIPTION Conden. Pump A D02100 BKR-CD-2300A2 SWGR 3Al-9 BRKR On-Off ,
D02101 ES-CD-2300A Mtr. Overcurrent/ Overload D02107 ES-CD-2304A Hotwell A Lo Lvl Conden. Pump B D02200 SWGR 3B1-9 BRKR On-Off D02201 ES--CD-23003 Mer. Overcurrent/ Overload D02207 ES-CD-2304B Hoewell B Lo Lvl Conden. Pump C D02300 BKR-CD-2300C2 SWGR 3Al-10 BRKR On-Off D02301 ES-CD-2300C Mer. Overcurrent/ Overload D02307 ES-CD-2304C Hotwell C Lo Lvl Steam Gen. Feed Pump / D08202 ES-FW-2012A WPT Manual Trip Turbine A D08204 ES-FW-2134A FWPT Lube Oil D08225 ES-FW-2131A Recire. Flow Lo D08226 ES-FW-2132A Main Flow Hi Trip D08227 ES-FW-2133A Suction Pres. Lo D08228 ES-FW-2135A Turb. Exhaust Pres. High D08229 ES-FW-2136B Condensate Pump Trip to cause a WPT trip D08230 ES-FW-2137A Thrust Bearing 011 Pres. Lo D08231 ES-FW-2137A Overspeed Trip D08232 ES-FW-2139A High Vibration Trip D08234 ES-MD-3003A Steam Gen. Feed Pump / D08502 ES-FW-20123 FWPT Manual Trip Turbine B D08504 ES-FW-2134B FWPT Lube Oil Pres. Lo D08525 ES-N-21313 Recire. Flow Lo D08527 ES-FW-2133B Section Pres. Lo D08528 ES-FW-2135B Tube Exhaust Pres. High D08529 ES-FW-2136B Condensate Pump Trip to cause a FWPT trip D08530 ES-N-3137B Thrust Bear Oil Pres. Lo D08531 ES-FW-2138B Overspeed Trip D08532 ES-FW-2139B High Vibration Trip D08534 ES-MD-3003B 011 Drain Tank Lvl Lo D08526 ES-FW-21323 Main Flow High Em. Fw. Pmp. A D10100 Gd,-Fv/-6@A2. SWGR 3A3-5-10 BRKR On-Off D10102 ES- N-8300A Overcurrent/ Overload Trip Em. Fw. Pmp. B D10200 S M . w .S D B2. SWGR 3B3-S-2 BRKR On-Off D10202 Eis-map 6 Overcurrent/ Overload Trip-l l
l l
l , , - ,- .- ,-
CPERATING SYSTEM PTID EBASCO TAG DESCRIPTION RCP Mtr. lA D13200 BKR-RC-0150A2 SWGR 3Al-7 BRKR On-Off D13202 ES-RC-0152 overcurrent/ overload Trip RCP Mer. 2A D13400 BKR-RC-0160A2 SWGR 3 Al-8 BRKR On-Off j D13402 ES-RC-0162 Overcurrent/ Overload Trip RCP Mtr. 1B D13600 8gR. RC-Ol70AZ SWGR 3B1-7 BRKR On-Off
- D13602, r9- RC-CI T2- ~0vercurrent/ overload Trip RCP Mer. 2B D13800 W e %'0I N E SWGR 3B1-8 BRKR On-Off D13802 F4 -RC'o F62, Overcurrent/ Overload Trip CEDMCS Inputs to PMC D36616 ES-PP-1091 Undervoltage Relay #1 Disconnect D36617 ES-PP-1092 Undervoltage Relay #2 Disconnect D36618 ES-PP-1093 Undervoltage Relay #3 Disconnect D36619 ES-PP-1094 Undervoltage Relay #4 Disconnect PPS Trips Operator D38239 _ ES- FF-225h Trip Cir. Brk. #1, #5 Man. Discon. CP-2 CP-2, 7, 8 D38240 Es-79-1252. Trip Cir. Brk. #2, #6 Man. Discon.-CP-8 D38241 ES-#F- 21S3 Trip Cir. Brk. #7, #3 Man. Discon. CP-2 D38242 ES- FP- 2254 Trip Cir. Brk. #8, #4 Man. Discon. CP-8 D38243. _..E5_% 2255" ._ _ Trip Cir. Brk. #1,#5 Man. Discon.LCL C.
D38244 Es-N- 225G Trip Cir. Brk. #2,#6 Man. Discon.LCL C.
D38245__. ES- &-MS7 Trip Cir. Brk. #7,#3 Man. Discon.LCL C.
D38246_ ES- fY-0.258 Trip Cir. Brk. #8,#4 Man. Discon.LCL C.
PPS Set Points D38300 ES-PP-1001 SG 1 Lo Lvl Chal. A and Trips D38301 ES-PP-1002 SG 1 Lo Lvl Chnl. B D38302 ES-PP-1003 SG 1 Lo Lvl Chnl. C D38303 ES-PP-1004 SG 1 Lo Lvl Chal. D D38304 ES-PP-1005 SG 2 Lo Lvl Chnl. A D38305 ES-PP-1006 SG 2 Lo Lvl Chnl. B D38306 ES-PP-1007 SG 2 Lo Lvl Chnl. C D38307 ES-PP-1008 SG 2 Lo Lvl Chnl. D D38308 ES-PP-1009 SG 1 Pres Lo Chal. A
D38322 ES-PP-1024 Prz Pres Lo Chnl. C D38323 ES-PP-1025 Prz Pres Lo Chnl. D l
i OPERATING SYSTEM PTID EBASCO TAG DESCRIPTION PPS Setpoints D38324 ES-PP-1026 LIN Fwr. Si Chnl. A and Trips (continued) D38325 ES-PP-1027 LIN Pvr. Hi Chnl. 3 l D38326 ES-PP-1028 LIN Pwr. Hi Chnl. C l D38327 ES-PP-1029 LIN Pwr. El Chnl. D :
D38328 ES-PP-1034 Cont. Pres Hi Chnl. A (RPS)
D38329 ES-PP-1035 Cont. Pres Hi Chnl. B (RPS)
D38330 ES-PP-1036 Cont. Pres Hi Chnl. C (RPS)
D38331 ES-PP-1037 Cont. Pres Hi Chnl. D (RPS)
D38332 ES-PP-1038 Cont. Pres Hi Chnl. A (ESF)
D38333 ES-PP-1039 Cont. Pres Hi Chnl. B (ESP)
D38334 ES-PP-1040 Cont. Pres Hi Chnl. C (ESF)
D38335 ES-PP-1041 Cont. Pres Hi Chnl. D (ESF)
D38336 ES-PP-1042 DNBR Lo Chnl. A D38337 ES-PP-1043 DNBR Lo Chnl. B D38338 ES-PP-1044 DNBR Lo Chal. C D38339 ES-PP-1045 DNBR Lo Chnl. D D38340 ES-PP-1046 LPD Hi Chul. A D38341 ES-PP-1047 LPD Hi Chnl. B D38342 ES-PP-1048 LPD Hi Chnl. C D38343 ES-PP-1049 LPD Hi Chnl. D D38344 ES-PP-1050 LOG Pwr. Ei Chal. A D38345 ES-PP-1051 LOG Pwr. Hi Chnl. B D38346 ES-PP-1052 LOG Pwr. Ei Chal. C D38347 ES-PP-1053 LOG Pwr. Hi Chnl. D D38348 ES-PP-1054 Cont. Pres Hi Hi Chnl. A D38349 ES-PP-1055 Cont. Pres Hi Hi Chnl. B D38350 ES-PP-1056 Cont. Pres Hi Hi Chnl. C D38351 ES-PP-1057 Cont. Pre's Hi Hi Chnl. D D38352 ES-PP-1058 RWSP Lo Lvl Chal. A D38353 ES-PP-1059 RWSP Lo Lvl Chal. B D38354 ES-PP-1060 RWSP Lo Lvl Chnl. C D38355 ES-PP-1061 RWSP Lo Lvl Chnl. D D38356 ES-PP-1062 SG 1 Hi Lvl Chnl. A D38357 ES-PP-1063 SG 1 Hi Lvl Chnl. B +
D38358 ES-PP-1064 SG 1 Hi Lvl Chnl. C D38359 ES-PP-1065 SG 1 Hi Lvl Chnl..D D38360 ES-PP-1066 SG 2 Hi Lvl Chnl. A D38361 ES-PP-1067 SG 2 Hi Lvl Chnl. B D38362 ES-PP-1068 SG 2 Hi Lvl Chal. C D38363 ES-PP-1069 SG 2 Hi Lvl Chnl. D D38364 . -ES-PP-1070 SG 1 Pres > SG 2 Pres Chnl. A l D38365.. ..ES-PP-1071 SG 1 Pres) SG 2 Pres Chal. B t
D38366 ES-PP-1072 SG 1 Pres > SG 2 Pres Chnl. C
! D38367 ES-PP-1073 SG 1 Pres ?SG 2 Pres Chnl. D 1
D38368 ES-PP-1074 SG 2 Pres >SG 1 Pres Chnl. A D38369 ES-PP-1075 SG 2 Pres > SG 1 Pres Chnl. B D38370 ES-PP-1076 SG 2 Pres) SG 1 Pres Chnl. C l D38371 ES-PP-1077 SG 2 Pres > SG 1 Pres Chnl. D
! D38372 ES-PP-1151 Spare Chnl. A D38373 ES-PP-1152 Spara Chnl. B l D38374 ES-PP-1153 Spare Chnl. C D38375 ES-PP-1154 Spare Chnl. D
I OPERATING SYSTEM PTID E3ASCO TAG DESCRIPTION PPS Set Points D38376 ES-PP-1155 Spare Chnl. A and Trips (continued) D38377 ES-PP-1156 Spare Chnl. B D38378 ES-PP-1157 Spare Chnl. C D38379 ES-PP-1158 Spare Chnl. D D38380 ES-PP-1159 Spare Chnl. A D38381 ES-PP-1160 Spare Chnl. B D38382 ES-PP-1161 Spare Chal. C D38383 ES-PP-1162 Spare Chnl. D D38384 ES-PP-1163 Spare Chal. A D38385 ES-PP-1164 Spare Chnl. B D38386 ES-PP-1165 Spare Chnl. C D38387 ES-PP-1166 Spare Chnl. D D38388 ES-PP-1167 Spare Chnl. A D38389 ES-PP-1168 Spare Chal. B D38390 ES-PP-1169 Spare Chnl. C D38391 ES-PP-1170 Spare Chnl. D D38392 ES-PP-1171 Spare Chnl. A D38393 ES-PP-1172 Spare Chnl. B D38394 ES-PP-1173 Spare Chnl. C D38395 ES-PP-1174 Spare Chal. D RTSG Brkrs D38501 E S- P'#-dl82A1 RTSG Trip Cir. Brkr 1 Not Closed / Closed D38503 n- PP- C183A2. RTSG Trip Cir. Brkr 2 D38505 _ Es - PP-oi 8 4 A7. RTSG Trip Cir. Brkr 3 D38507 E M Pf'-Ci 8 S As RTSG Trip Cir. Brkr 4 D38509 _ _ g s- FF- cis(, A7. RTSG Trip Cir. Brkr 5 D38511, _ ES-FA-OIS 7 A7_ RTSG Trip Cir. Brkr 6 D38513 _. es,-FP-oie6 AT . RTSG Trip Cir. Brkr 7 D38515 es,.FF-03 8%7 RTSG' Trip Cir. Brkr 8 -
D38517 E s-FP-ciq0 A 2._ ,RTSG Trip Cir. Brkr 9 ESFAS D38600 ES-PP-9900 CSAS Chal. A in Action D38601 ES-PP-9901 MSIS Chnl. A in Action D38602 ES-PP-9902 CIAS Chnl. A in Action D38603 ES-PP-9903 RAS Chnl. A in Action D38604 ES-PP-9904 CCAS Chnl. A in Action D38605 ES-PP-9905 EFAS-1 Chnl. B in Action D38606 ES-PP-9906 EFAS-2 Chnl. B in Action D38607 ES-PP-9907 CSAS Chnl. B in Action l D38608 ES-PP-9908 MSIS Chal. B in Action !
D38609 CIAS Chnl. B in Action 1 D38610 ES-PP-9910 RAS'Chnl. B in Action D38611 ES-PP-9911 CCAS Chnl. B in Action D38612 ES-PP-9912 EFAS-1 Chnl. A in Action D38613 ES-PP-9913 EFAS-2 Chnl. A in Action D38618 ES-PP-9940 STAS Chnl. A in Action
, D38620 ES-PP-9941 SIAS Chnl. B in Action i
l CVCS Chg. Pump A D39600 BKR-CH-224X2 SWGR Brkr 3A31-S-5 Off-On
- D39604 PS-CH-0228X Current Overload Trip
( D39605 PS-CH-0229X Lube 011 Pres Lo
1 OPERATING SYSTEM PTID EBASCO TAG DESCRIPTION CVCS Chg. Pump B D39700 BRK-CH-24Z2 SWGR 3B31-S-6 Brkr. Off-On D39704 PS-CH-0228Z Overload (Current) Trip D39705 PS-CH-0229Z Lube Oil Pres Lo CVCS Chg. Pump A/B D39800 BRK-CH-224Y2 SWGR 3AB31-S-4 Brkr. Off-On D39804 ES-CH-0228Y Current Overload Trip D39805 PS-CH-0229Y Lube Oil Pres to Cont. Spray Pump A D42400 BKR-CS-7111A2 SWGR 3A3-S-6 Brkr. Off-On D42404 ES-CS-7114A Mtr. Overload Trip Cont. Spray Pump B D42500 BRK-CS-7111B2 SWGR 3B3-S-5 Brkr. Off-On D42504 ES-SI-6703B Mtr. Overcurrent/ Overload Trip LPSI Pump A D43100 BRK-SI-6710A2 SWGR 3A3-S-5 Brkr. Off-On D43102 ES-SI-6711A Mtr. Overcurrent/ Overload Trip (Alarm)
LPSI Pump B D43200 BKR-SI-6710B2 SWGR 3B3-S-4 Brkr. Off-On D43202 ES-SI-67113 Mtr. Overcurrent/ Overload Trip (Alarm)
HPSI Pump A D43400 BKR-SI-6700A2 SWGR 3A3-S-4 Brkr. Off-On D43402 ES-SI-6701A Mgr. Overcurrent/ Overload Trip (Alarm)
HPSI Pump B D43500 BKR-SI-6700B2 SWGR 3B3-S-3 Brkr. Off-On D43502 ES-SI-6701B Mer. Overcurrent/ overload Trip (Alarm)
HPSI Pump A/B D43600 BKR-SI-6700C2 SWGR 3AB3-S-3 Brkr. Off-On D43604 ES-SI-6703C Mer. Overcurrent/ Overload Trip (Alaan)
Main Turbine General D55019 LS-TA-4301 Mn. Turb. Lube 011 Res Lo Trip Points Reserved for D55800 PS-TA-4316 Mn. T/G Bearing 011 Pres Lo Trip Main Turb. Trips D55802 PS-TA-4307A EH Fluid Lo Pres Trip R2 corded by SOEs D55803 PS-TA-4317 Mn. Turb. Thrust Brg. Oil Pres Lo Trip D55804 PS-TA-4318 Mn. T/G High Exhaust Pres D55807 ES-TA-4360 overspeed Trip D55808 ES-TA-4361 EH Cntrl. D.C. Bus No Pwr Trip D55810 ES-TA-4364 High Vibration /High Differ. Expans.
4 400 MWe Trip ,
D55811 ES-TA-4367 Gen. Seal 011 Differ. Pres Lo-Lo Trip D55812 ES-IA-4368A F.W. Her. 6A Lvl Hi-Hi Trip D55813 ES-TA-4369A F.W. Her. 5A Lvl Hi-Hi Trip D55814 ES-TA-4370A1 Moist. Sep. RH-A Lvl Trip D55815 ES-TA-4371B1 Moist. Sep. RH-B Lvl Trip .
D55827 ES-TA-4368B F.W. Her. 6B Lvl Hi-H1 Trip l D55828 ES-TA-4368C F.W. Her. 6C Lvl Hi-Hi Trip D55829 ES-TA-4369B F.W. Her. 5B Lvl Hi-Hi Trip D55830 ES-TA-4369C F.W. Her. SC Lvl Hi-H1 Trip D55831 ES-TA-4379A Moist. Sep. RH-B Lvl Trip D55832 ES-TA-437132 Moist. Sep. RH-B Lvl Trip D55834 ES-TA-4374 High Vib/High Diff Exp. Trip > 400 MWu i
9
1 OPERATING SYSTEM PTID EBASCO TAG DESCRIPTION Main Generator Trip D58700 ES-EC-7200 Mn Trans Differ Curr Trip 74-1 Relay D58701 ES-EC-7201A Mn Trans 3A Grnd Rly Trip 74-2 Relay D58702 ES-EC-7201B Mn Trans 3B Grnd R1y Trip 74-3 Relay D58703 ES-GN-4623 Field Failure Trip (86GI)
D58704 ES-EC-7300 SGG1 SW. Sta. Intik Relay D58705 ES-GN-4626 Reverse Pwr Trip D58707 ES-EC-7202A Mn Trans 3A Differ Curr Trip D58708 ES-EC-7202B Mn Trans 3B Differ Curr Trip D58709 ES-GN-4632 Mn Gen Diff Prot Relay D58710 ES-GN-4623 Neg Seq Trip (Mn Gen)
D58712 ES-EC-7204A Mn Trans 3A Sudden Gas Press Trip D58713 ES-EC-7204B Mn Trans 3B Sudden Gas Press Trip D58714 ES-EC-7301 SW Sta Intik Relay D58715 ES-TA-4363 Trip From CP-15-Gen Loc 86Gl/G2 D58718 ES-EC-7010A1 D58719 ES-EC-7010A2 Unit Aux Trn 3A Sudden Gas Press Trip D58720 ES-EC-7010B1 Unit Aux Trn 3B Diff Current Trip D58721 ES-EC-7010B2 Unit Aux Trn 3B Sudden Gas Press Trip D58722 ES-EC-7203 86G2 Station Bus Diff Curr Trip D58723 ES-EC-8060 Distance Lockout Relay D58724 ES-GN-4622 Manual 86G1 Trip D58725 ES-GN-4631 Manual 86G2 Trip D58726 ES-CN-4634 86Cl Grnd Trip D58727 ES-TA-4355 86G2 Field Failure Trip D58728 ES-GN-4627 Turb Trip Relay System 88 D58826 ES-7A-4300 Turb Exhaust Hood High Temp (Trip Alarm)
Main Turbine Supervisory D56004 PS-TA-1806 Exh Press Diff/ Gen Monitoring Alarm Startup Traneformer DS9200 ES-EC-7000Al Diff Current Trip (3A)
DS9201 ES-EC-7000A2 Ground Trip (3A)
DS9202 ES-EC-7000A3 Sudden Gas Press Trip (3A)
D59203 ES-EC-7000A4 Lockout Relay Trip SWGR 3Al DS9204 ES-EC-7001A 3A Trans to 6.9KV Bus Overcurrent Trip D59207 ES-EC-7000B1 3B Diff Current Trip DS9208 ES-EC-7000B2 3B Ground Trip D59209 ES-EC-7000B3 3B Sudden Gas Press Trip D59210 ES-EC-7000B4 Lockout Relay Trip SWGR 3B1 D59211 ES-EC-7001B 3B Trans to 6.9KV Bus Overcurrent Trip Switching Station DS9349 ES-EC-8050A7 011 Cir Erkr A BF Operation D59379 ES-EC-8050B7 Oil Cir Brkr B BF Operation D59360 ES-EC-8050AIB Pole Disagreement (A)
DS9370 ES-EC-8050BlB Pole Disagreement (B)
. '. .o OPERATING SYSTEM PTID EBASCO TAG DESCRIPTION i
6.9 KV Switchgear DS9400 BKR-EC-7000A2 SU Trans 3A WDX to 6.9KV Bus 3Al DR Bi D59401 BRK-EC-7000B2 SU Trans 3B WDX to 6.9KV Bus 3B1 ."UR 31 DS9402 BRK-EC-7010A2 Unit Aux Trans 3A WDX to 6.9KV-3B1 Aux F Bkr DS9403 BKR-EC-7010B2 Unit Aux Trans 3B WDX to 6.9KV-331 Aux F Ekr 4 D59404 ES-EC-7000A 6.9KV-3Al Under V. Trip D59412 ES-EC-7000B 6.9KV-3B1 Under V. Trip DS9413 ES-EC-701085 6.16 KV DS9500 BKR-EC-4000A2 SU Trans 3A WDY to 4.16KV-3A2 t/2 FDR Switchgear Bkr DS9501 BKR-EC-4010A2 Aux Trans 3A WDY to 4.16KV-3A2 #1 FDR DS9502 ES-EC-4000A5 00 r. n IA W M ~' ~ ' '
D59503 ES-EC-4010A5 A ux "Tm .4 .3A W oy % 4. lWi/. S A7. S. 4 i DS9506 ES-EC-4029A 4.16KV-3A2 Under V. Relay DS9516 BRK-EC-4000B2 SU Trans 3B WDY to 4.16KV-3B'i #4 FDR Bkr DS9517 BKR-EC-4010B2 Unit Aux 3B WDY to 4.16KV-3B2 #1 FDR Bkr D59518 ES-EC-4000B5 SU Trans 3B WOT M 4.16R.V-3BZ FDR OC DS9519 ES-EC-4010B5 Unic Aux 3B wof w .2. IM/-392. FDR OC D59522 ES-EC-4029B 4.16KV-3B2 Under V.
. Cire. Water Pump A D62100 h < R. cw - #221&2. SWGR 3Al-5 Brkr Off-On D62101 ES-tw-8221 A SWGR 3Al-5 Overcurrent/ Overload Trip Cire. Water Pump B D62200 BKR,-Cv/-07.Zitff. SWGR 3B1-5 Brkr Off-On D62201 ES-C.td- 322 t 3 SWGR 3B1-5 Overcurrent/ Overload Trip Circ.* Water Pump C D62300 SKA-Cu.)-822tC2- SWGR 3Al-6 Brkr Off-On D62301 ES-cet-9221 C Mtr. Overcurrent/ Overload Trip Cire. Water Pump D D62400 3<R-cts-822tD 2- SWGR 3B1-6 Brkr Off-On D62401 ES -C.W- 8 2.2 t D Mer. Overcurrent/ Overload Trip i
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ATTACHMENT 2 2 SEC GROUP A12217 CPC.PZR Press CH 1 0 to 3000 psia C26242 PZR Lv 1 0 to 100 P CNT A92208 CNTMT Press ,
O to 70 psia Allll4 SG 1 Press s 0 to 1200 psia All108 SG 1 Lv 1 0 to 100 PCNT C26260 SG 1 FW Flow 0 to 8 MPPH C26258 SG 1 STM Flow 0 to 8 MPPH All214 SG 2 Press O to 1200 psia A11208 SG 2 Lv 1 0 to 100 PCNT C26261 SG 2 FW Flow 0 to 8 MPPH C26259 SG 2 STM Flow 0 to 8 MPPH C26236 Log Power CHC l~ to 200%
C26330 Lin Power CHD 0 to 200%
C26413 CET SAT Margin 200 to -2100 'F A13200 RCPM 1A Amps 0 to 1200 Amps A13600 RCPM 1B Amps 0 to 1200 Amps A13400 RCPM 2A Amps O to 1200 Amps A13800 RCPM 2B Amps O to 1200 Amps C48088 CVP Exh Rad lE -07 to .1 uci/cc All300 Mod Demand SBC Value 1 0 to 100%
ATTACHMENT 3 30 SECOND GROUP Include all points in 2 second group
! A12300 PzR Quench Tank Level O to 100 PCNT c A12304 PzR Quench Tank Temp 0 to 300 Deg. F A12301 PzR Quench Tank Press 0 to 150 PSIG C26237 Boron Concentration 0 to 6000 PPM
, C26402 Rx VSL Lv 1 Head 0 to-100 PCNT
]
l C26403 Rx VSL Lv 1 Plenum- O to 100 PCNT i
C26229 EFW Flow SG 1 O to 800 GPM C26231 EFW Flow Sg 2 0 to 800 GPM S43101 LPSI Pump A Flow 0 to 5000 GPM S43201 LPSI Pump B Flow 0 to 5000 GPM C26247 HPSI Flow to RCL 1A 0 to 500 GPM
~
C26248 HPSI Flow to RCL 1B 0 to 500 GPM C26249' HPSI Flow to RCL 2A 0 to 500 GPM C26250 HPSI Flow to RCL 2B 0 to 500 GPM C26245 Charging Flow 0 to 150 GPM C26246 Letdown Flow 0 to 150 GPM A61111 IA Dryer Outl Air Press 0 to 125 psig C26340 CNTMF Hi range Rad 10 to lE08 R/HR C48071 Stack Gas Rad IE-07 to .1 VCI/CC
! A59900 3A-DC-S Volts J to 150 VDC A59901 3D-DC-S Volts - O to 150 VDC i
A59902 3AB-DC-5 Volts O to 150 VDC A60104 EDG A Freq. 55 to 65 H g.
'A60204 EDG B Freq. 55 to 65 H g C26238 -RCS Loop 1 Th .50 to 750 Deg. F.
? C26331 RCS Ioop 2 Th ' 50 to 750 Deg. F.
C26239 RCS Inop 1A Tc 50 to 750 Deg. F.
C26333 RCS Lmp 1B Tc 50 to.750 Deg. F..
C26240 RCS Icop 2A Tc '50:to 750 Deg. F.
C26332- RCS ' cop 2B Tc 50 to 750 Deg. F.
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ATTACl! MENT 4 PTID POINT DESCRIPTION
- 1. ASSNTTT
- 2. ASST.TTT Point Description
- 3. ASSNITT Point Description TIM:: 1 2 3 IIII:MM: SS UNITS UNITS UN1TS XXXXXXXXQ XXXXXXXXQ XXXXXXXXQ v