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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] |
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= .ENTERGY EilN"""'"
K&sa LA 70066
/ ,.g .
Tel 504 739 6774 R. F. Burski CwcKv.
t Adar Safety ,
V.Wer!ce) 3 !
W3F1-95-0164 )
A4.05 !
PR October 5,1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Emergency Response Data System (ERDS)
Plant Attribute Library Update Gentlemen:
Waterford 3 is hereby submitting (attached) an update to the ERDS Plant Attribute Library (PAL) in accordance with 10CFR50, Appendix E, VI, 3.b.
The update is associated with equipment and software changes being incorporated during the Waterford 3 Plant Monitoring Computer upgrade. The changes are being incorporated during Refuel 7, currently in progress. The attached updated library will be effective at the completion of the refueling outage, which is currently scheduled to occur on November 6, 1995. Waterford 3 personnel will notify the NRC Operations Center by phone when the ERDS is back in service (at the completion of the outage) with the new PAL in effect.
0G00G1
&l 9510060229 951005 l
PDR ADOCK 050003B2 p PDR
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re 'l
- - - $DS Plant Attribute Library Update ]'
W3F1-95-0164~
Page-2 ,
'3 October 5', 1995 ;
If you have,any questions ~ concerning the above, please contact 0.P. Pipkins :
at (504) 739-6707.. I Very truly yours, 4 t
R.F. Burski Director- !
Nuclear Safety
- RFB/0PP/ssf.
Attachment 3 l
cc: L.J. Callan, NRC Region IV C.P. Patel, NRC-NRR
'R.B.~ McGehee J.R. Jolicoeur, NRC-AE0D N.S. Reynolds NRC Resident Inspectors Office .
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4 APPENDIX B l
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ERDS COMMUNICATIONS DESCRIPTION
! AND SURVEY QUESTIONNAIRE 4
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APPENDIX B ERDS COMMUNICATIONS DESCRIPTION AND SURVEY QUESTIONNAIRE ne to!!owing is a questionnaire pertaining to the Nuclear Regulatory Commission's (NRC)
Emergency Response Data System (ERDS). It consists of a senes of quesuons concerning plant I/O points. software protocols, data formats. transmission frequencies. and other plant com-puter specific information to be used in the ERDS computer database files. Also. included here are descriptions and examples of data streams that the NRC is expecting to see transmitted over the communicauon line.
The purpose of collecting the data is to develop a plant specific database that will be retrieved into the ERDS once the system is acuvated by a utility. It will also be used to desi ment ERDS software that can receive the utility's data transmission. th In informa-essence.gn and imple-tion will provide the basis for building a profile of the plant in the ERDS database.
In some cases the I/O point data may be distributed over several computers. The ERDS consid-ers this situation a multi. feeder site and Section IV must be filled out for each feeder.
For plants that utilize the PC based interface described in AppendizJ. item 15.Section IV must
- be filled out for the ERDS interface PC as well as each computer which feeds data to the inter-face PC.
His request is covered by Off!ce of Management and Budget Clearance Number 3150 0150 which expires March 31,1992.ne estimated average butden hourn is 32 person hours per lican-ses response, including staff and management review and preparation of the requested re-sponse. Dese estimated average butden hours pertain only to those identified response related matters and do not include the time for any follow on implaamatariaa Sand comments regard-ing this burden estimate or any other aspect of this collection ofinformation. including sugges-tions tor reducing this burden. to the Records and Reports Management Branch. Division of informsuon Support Services. Office of Information Resources Management. (*.S. Nuclear lleguistorv Commission. Washington. DC 20555: and to the Paperwork Reducuen Project j 0150-0150). Office of Management and Budget. Washington. DC 20503.
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B-1 NUREG-1394. Rev. I
- 1. Contacts Note: Please provide name. title. malling address. and phone number.
A. Survey Coordinator (i.e contact for later clarifiestion of questionnaire answers):
Clarence Kimble Engineer Senior P.O. Box B Killona LA 70066 (504) 739-6405 B. Computer Hardware Specialist (s):
Clifton George
- Senior Maintenance Specialist P.O. Box B K111ona, LA 70066 (504) 739-6729 C. Systems Software Specialist (s)-
1 Clarence Kimble , l l
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D. Application level Software SWaHMs): .
Clarence Kimble Robert Verderame Engineer II P.O. Box B 4 Killona, LA 70066 (504) 739-6727 J
E. Telephone Systems SWeliet(s);
i Donald St. Germain
'- IT Specialist P.O. Box B Killona, LA 70066 4
(504)739-6241 4
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NUREG-1394. Rev.1 B-2
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II. ERDS Communications Description l-l A. Hardware i The followmg hardware will be supplied:
- for a single. feeder site:
l Codex 2235 modem or equivalent V.222400 bps. asynchronous. auto. dialing. auto-
! answer. error correcting. using the AT command 4
a
- set I' '
- for a multiple feeder site:
I Codex 6015 multiplexer.
! Codex 2264 modem or equivalent V.329600 bps, asynchronous, auto dialing auto-answer. error correctmg, using the AT command set I (for an alternate approach see Appendix A. Item 7) l De modems are intended to be operated in the auto reliable link mode (referred to as MNP ih the modem manuals). Ders are several modem parameters that affect MNP operation. Thess are discussed in the sections of the modem manuals pertaining to MNP. The single feeder mo-dams at the NRC Operations Center are configured for auto reliable link mode, local terminal l- flow control and default break handling.
! B. Software t
i 1. Data Transmission All transmissions. from both the site and the ERDS.will be terminated with a carriage return
( < CR > ). .
l
! a. Site will initiate a link request in ASCH using:
- the three. character site designator.
[
- the word LINK.
4
- local site time and date in the format MM/DD/YY/HitMM:SS and l j
- a < CR > .
o
' If the site does not receive a response from the ERDS within one minute. it should send i
another link request message and continue sending them at one minute intervals. If more than five minutes elapses without a response, site personnel should notify the NRC before disconnecting the line.
l- b. ERDS will respond in ASCII with: ,
l - the three<:baracter site designator.
- the word ACCEPTED or DENIED. and ,
- a<CR>.
if the ERDS responds with the denied message. the site should wait one minute and then send a link request message and continue sending them at one.mmute intervals. If g.) Mf fB e#* ****
...c, . _ _ _ _ . .
1
.more than rive m nutes elapses without s response site personnel shout nottrv the
! NRC betore disconnecting the line.
- c. When the ERDS is ready to receive data, it will send an initiate message in ASCH
~
- using:
I - the three character site designator.
! - the word INTIIATE. and
- - a < CR> .
If the ERDS does not send an initiate message within one minute of the accept mes-sage. the site should send the link reconnect message (desenbed in Section II.B.1.f.).
f d. Upon receipt of the initiate message, the plant begins transminion of data at a 15 second rate. The data string consisu of:
! - a header containing the three character site designator and date and time in the
- format MM/DD/YY/HItMM
- SS.
- the data packet sequenced with point identiSer value, and quality tag.
- a trailer containing the checksum value of the data packet. and a < CR>. -
4 h e. When the site or ERDS wishes to terminate the connection. an ASCH message will be sent containing: #
t
! - the three character site designator.
I -
the word 'IT.RMINATE and
- s<CR>.
1
- t. If a site is inadvertently terminated (due to loss of communications or receipt of termi-
- nate message) and the incident is still underway, the site should reconnect with the l ERDS by redialing and using the link reconnect message. The link reconnect message
! Should be used any time the phone line is lost atter the receipt of an Accept Message
! (described in Section II.B.1.b). This message is in ASCII and will contain:
(
i
- the three character site designator.
} - the word RECONNECT.
j - local site time and date in the format MM/DD/YY/HH:MM:SS. and i
- s<CR>.
Upon receipt of this message. the ERDS will respond with the accept and initiate mes-l sages as described in Sections !!.B.1.b and ILB.1.c. lf the ERDS responds with a link
- deny message (described in Section II.B.1.b). the site should stop trying to reconnect j snd send a link request message (described in Section II.B.1.a). lf the ERDS does not j respond to the site's reconnect request within one minute. the site should send another reconnect request and conunus sending reconnect requests once a minute. If more l j than tive minutes elapses without a response. site personnel should notify the NRC before disconnecting the line. It is the responsibility of the site to monitor the outgoing i
line tor loss of communications. '
i J
Once a physical connection has been established with the NRC. the site should not disconnect the phone line until a TERMINATE message tdescribed in section i
l NUREG-1394. Rev.1 8-4 l 1
!!.B.1.'e) has been transmitted. If problems are encountered in the link recuest se.
quence. do not hang up the line but proceed with the steps outlined above.
g.
If the site will transmit in EBCDIC rather than ASCII. the following applies:
(1) The link request message (defined in II.B.I.a) and the reconnect message (defined in II.B.1.f) must be in ASCII.
(2) All replies sent by the ERDS to the site will be in ASCII.
(3) The terminate message sent by the site may be in EBCDIC or ASCII.
(4) All update sets sent by the site must be in EBCDIC.
- 2. Data Format The following three delimiters have been identified:
(1) field delimiter (*).
(2) data set delimiter (\). and j (3) carriage return ( < CR > ).
- Note
The length of the messages sent by the ERDS (e.g ACCEPTED. DENIED.-
! INITIATE. TERMINATE) are variable and it is recommended that the site so
- ware use the data set delimitar as the message delimiter for messages received from the ERDS.
t
- a.
! I. ink requests will be in ASCII as described in II.B.1.a. with each field separated by a i field delimiter and the request terminated with a data ses delimiter. For example.
pal' LINK'01/12/89/11:48.50\ < CR > .
i b.
+ The ERDS response will be in ASCU as dercribed in II.B.Lb. with each field sepa-i rated by a field delimiter and the response terminated with a data set delimiter. For example. pal
- c.
When the ERDS is ready to receive data it will respond in ASCII as described in II.B.1.c with each field separated by a field delimiter and the res j a data set delimiter. For example. pal
- INITIATE \ < CR>. ponse terminated with l d.
Data streams will be in ASCII and will consist of three parts (header. data. and trailer) as described in II.B.1.d. with each field separated by a field delimiter and each of the j three parts separated by a data set delimiter. For example.
, Header: pal *01/12/89/11:50:30\
Data:
B21CP004*-0.1234E+00'3'... (for each parameter)\
Trailer: 0000056000\ < CR>
e.
The point identifier may be up to 12 characters in length.
f.
The value may be up to 20 chr.racters in length.
B-5 NUREG-1394. Rev.1 I
, l I
I ., .-
! e. The tollowinc quality tags will be accepted by the ERDS:
1
- Good - =0 Value is within range tolerance for discreet points or in-put points are within tolerance for composed points.
l Off scan =1 Point is currently out of. service.
I e Suspect =2 Value is not bad yet should not be considered good.nis
! quality will occur primarily on composed values when j enough good inputs are present to allow the calculation to be made yet a bad quality on other inputs may make i the result questionable.
- Bad =3 Value is not within tolerance for discrest points or calcu.
lation of a composed point may not be made due to the qualities of its inputs.
Unknown =4 No quality indicator available.
Operator Entered =5 Value has been manually entered. overriding the dise creet or composed value.
High Alarm =6 Value is in high alana.
1 j Low Alarm =7 Value is in low alarm. l
- h. The checksum which accompanies each update set wiu be an integer value calculated 1
, by summing each of the bytes of the transmission, up '.s and including the dataset de- 1 i limiter following the body of the update set (the body of the update set being the por-tion containing the parameter. value, and quality indications). This integer checksum value will then be encoded into the update set as a 10 digit value, left. padded with zeros as required to fill the 10 digit field.The checksum is the sum of the transmitted bytes.
. i. De reconnect link request message will be in ASCII as described in Section II.B.1.f j with each field separated by a field delimiter and the request terminated with a data 4 set delimiter. For example. pal' RECONNECT *01/12/89/11:48:50\ < CR > .
4
- 3. Protocol 4
- a. ERDS will use XON/XOFF to stop. resume, or suspend data transminion for the site.
- b. Communication parameters:
- eight data bits 1 stop bit
- parity = none d
- 4. Ezeeptions 1
Please note any exceptions which must be taken to Section II and explain why.
No exceptions to Section II.
. NUREG-1394. Rev. I 84 i
)
~
III. Selection Of Data Feeders 1
A. How many data feeders are there (six maximum)?
f l There is one data feeder supporting the Waterford 3 ERDS interface.
The Plant Monitoring Computer (PMC) is the ERDS data feeder.
1 i
1 1
I B. Identify the selected data feeders and provide the following for each:
- (1) a short description of the categories of data points it will provide *(e.g., met. rad. or plant data points, by unit) and (2) the rationale for selecting it if another system can r.lso provide its categories of data' points.
- (1) The PMC will supply all point data in the Waterford 3 DPL. No 1
changes to the DPL are required or anticipated during the Waterford 3 Plant Monitoring Computer replacement.
(2) All data required for the Waterford 3 DPL is available from the PMC
. through existing system interconnections.
a 3
i C. Which data feeder is the site time determining feeder? This should be the feeder which is providing the majority of the data points.
l The Plant Monitoring Computer is the site time deterinining feeder.
1 I
)
d 8-7 NUREG-1394. Rev.1
I
)
. IV. Data Feeder Information ,
Note: A new Section IV must be filled out for each feeder system selected.
General Questions
- 1. Identification of Data feeder
- s. What is the name in local parlance given to this data feeder (e.g., Emergency Response Information System)? Please give both the acronym and the words formmg it. ,
PNC - Plant Nonitoring Computer
- b. Is this the site time determining feeder?
Yes, the PMC is the site time determining feeder.
- c. How often will this feeder transmit an updata set to the ERDS (in seconds)?
An update set will be transferred to the ERDS every 30 seconds. -
i
- 2. Hardware / Software Environmens i
- s. Identify the manufacturer and model number of the data feeder hardware. ,
I Digital Equipment Corporation Alpha 4000-610
- b. Identity the operating system. I DEC Open VMS AXP Rev. 6.1
- c. What method of timekeeping is implemented on this feeder system (Daylight Savings.
Standard. Grasmnch)?
Standard / Daylight Savings Time l
J. In wnst time zone is this feeder located?
5 Central Time Zone '
i l !
i l
i
! , NUREG-1394. Rev. I B-3
/
' .2 '. Dats Communication Details
, .t . Can this dats teeder provide asynchronous serisi dsts communication IRS 32 C) witn tull mocem control?
Yes, the PMC can support this mode of operation and a RS-232-C serial port is available.
- b. Will this feeder transmit in ASCII or EBCDIC' i
The PMC will transmit in ASCII.
- c. Can this feeder transmit at s serial baud rate of 2400 bps? If not. at what baud rate can it transmit?
The PMC will transmit at 2400 bps.
- d. Does the operating system support XON/XOFF flow control?
l XON/X0FF flow control is supported by the PMC.
- 1. Are any problems foreseen with the NRC using XON/XOFF to control the trans. l mission of data?
. No problems are anticipated using XON/XOFF flow control.
1 i
- e. If it is not feasible to reconfigure a serial port for the ERDU linkup ti.e change the baud rate. parity. etc.). please explain why.
N/A 1
(
- f. Do any ports currentiv exist for the ERDS linkup?
Yes, a port is available for ERDS linkup.
- 1. If not. is it possible to add additional ports?
3 N/A B-9 NUREG-1394. Rev. I L
- 2. li yes. Eiil the port be used solely by the ERDS or shared with otner non.
emergency time users! Give details.
The port will be dedicated to the ERDS interface.
- 4. Data Feeder Physical Environment and Management
- a. Where is the data feeder located in terms of the TSC. EOF. and control room?
The Plant Monitoring Computer room is imediately adjacent to the control room, within 200 feet of the TSC, and within 2 miles of the EOF.
- b. Is the data feeder protected from loss of supply of electricity?
Yes, the PHC is supported by the Waterford 3 Computer SUPS (approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- c. Is there a human operator for this data feodar?
Yes, there is an on-duty PMC operator / technician.
- 1. If so, how many hours a day is the feeder attended?
. The PMC operator position is staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
J 4
4 1
1 J
NUREG-13M. Rev. I D-10
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