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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
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r3 ca Lis 70066 Ls ,74 739 f,774 R. F. Bursk8
- r. 1 o m.1, s !
gry r* s b W3F1-94-0086 A4.05 PR June 20, 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 9
Subject:
Waterford 3 SES Docket No. 50-382 !
License No. NPF-38 Reference Materials For Licensing Examination Preparations Gentlemen; i The attached indices list reference materials which were shipped separately on ,
June 17, 1994, for your use in preparation for the licensing examinations ,
scheduled for the weeks of September 12 and 19, 1994. The reference materials furnished were identified in Attachment 2 of ES-201, as specified in your letter dated May 26, 1994. Also attached are copies of the Airborne Express mailing forms for the packages shipped on June 17, 1994. l t
If you require any additional material, please contact Mr. T.D. Brown at (504) ;
739-6005.
Very truly yours, !
o M M R.F. Burski .
Director i Nuclear Safety RFB/0PP/ssf Attachments cc: L.J. Callan (NRC Region IV), D.L. Wigginton (NRC-NRR),
T.P. Gwynn (NRC Region IV), J.L. Pellet (NRC Region IV), '
I. Barnes (NRC Region IV), R.B. McGehee, N.S. Reynolds,
,9 '; p p 1 -7 NRC Resident Inspectors Office K 0 h 382 PDR 1
. LESSON PLANS AUXILIARY FEEDWATER ZAFW-700-00 BLOWDOWN ZBD-000-02 BORON MANAGEMENT ZBM-000-01 CONTAINMENT BUILDING ZCB-000-02 COMPONENT COOLING ZCCW-000-01 CONTAINMENT COOLING ZCCS-000-00 CONDENSATE ZCD-000-00 CONDENSATE POLISHER ZCDP-000-00 CONTROL ELEMENT DRIVE ZCED-700-00 CHILLED WATER ZCHW-700-01 CORE OPERATING LIMITS SUPERVISORY SYSTEM ZCOL-000-00 CORE PROTECTION CALCULATORS ZCPC-700-01 CONTAINMENT SPRAY ZCS-700-01 CHEMICAL AND VOLUME CONTROL ZCVC-000-00 CIRCULATING WATER ZCW-000-00 D.C. DISTRIBUTION ZDC-700-00 MAIN TURBINE DIGITAL ELECTRD-HYDRAULIC CONTROL SYSTEM ZDEH-000-00 EMERGENCY BREATHING AIR SYSTEM ZEBA-000-00 ELECTRICAL DISTRIBUTION ZED-000-00 EMERGENCY DIESEL GENERATOR ZEDG-000-01 EMERGENCY FEEDWATER ZEFW-000-01 ELECTRO-HYDRAULIC ZEH-000-00 EXCORE NUCLEAR INSTRUMENTS ZENI-700-00 EXTRACTION STEAM ZES-700-01 FUEL HANDLING AND STORAGE ZFHS-000-01 FIRE PROTECTION & DETECTION ZFPD-000-02 FUEL POOL COOLING AND PURIFICATION ZFS-000-00 ;
FEEDWATER ZFW-000-00 i FEEDWATER CONTROL ZFWC-700-00 FEEDPUMPS AND AUXILIAIES ZFWP-000-00 GENERATOR AUXILIARIES ZGA-000-00 GENERATOR AND 25 KV DISTRIBUTION ZGEN-000-00 GLAND SEAL ZGS-700-00 GASEOUS WASTE MANAGEMENT ZGWM-000-00 HYDROGEN RECOMBINER & ANALYZER ZHRA-000-00 HEATING AND VENTILATION, CONTROL ROOM ZHVC-000-00 HEATING AND VENTILATION, FUEL HANDLING ZHVF-000-00 HEATING AND VENTILATION, REACTOR ZHVR-000-00 TURBINE / POLISHER BUILDING BUILDING VENTILATION ZHVT-000-01 INSTRUMENT AIR ZIA-700-00 INVERTERS AND DISTRIBUTION ZID-000-01 INCORE NUCLEAR INSTRUMENTS ZINI-700-01 LUBE OIL GENERATOR ZLOG-700-01 LOW VOLTAGE DISTRIBUTION ZLVD-000-00 LIQUID WASTE MANAGEMENT ZLWM-700-00 MAIN STEAM ZMS-700-00 MAIN TRANSFORMERS AND SWITCHING STATION ZMT-700-00 POST ACCIDENT SAMPLING ZPAS-700-00 PLANT MONITORING COMPUTER ZPMC-700-00 PRESSURIZER LEVEL /PRESSUkE CONTROL SYSTEM ZPLC-000-00 PLANT PROTECTION SYSTEM ZPPS-700-01 POTABLE WATER ZPW-000-00 QUALIFIED SAFETY PARAMETER DISPLAY ZQSP-000-00 REACTOR COOLANT SYSTEM ZRCS-000-00 RADIATION MONITORING ZRMS-000-00
REACTOR COOLANT PUMP ZRCP-000-00 REACTOR POWER CUTBACK SYSTEM ZRXC-000-00 REACTOR REGULATING SYSTEM ZRR-000-00 REACTOR VESSEL AND INTERNALS ZRVI-700-00 REACTOR VESSEL LEVEL MONITORING ZRVL-700-00 1 SAFETY INJECTION ZSI-000-00 i SEISMIC MONITORING ZSM-700-01 l SHIELD BUILDING VENTILATION ZSBV-700-03 )
STEAM BYPASS CONTROL SYSTEM ZSBC-000-00 l STEAM GENERATOR CONSTRUCTION, OPERATION, SHRINK AND ZSG-700-00 l SWELL AND INSTRUMENTATION PLANT SUMP SYSTEM ZSP-000-00 ,
TURBINE REHEAT SYSTEM ZTUR-000-01 :
TURBINE BUILDING COOLING WATER ZTC-000-00 :
TURBINE SUPERVISORY EQUIPMENT ZTSI-700-01 i VIBRATION AND LOOSE PARTS MONITOR ZVLP-700-01 VIBRATION INSTRUMENTS ZVM-000-00 CORE DAMAGE ASSESSMENT VITAL INSTRUMENTATION ZCDA-003-00 SECONDARY CHEMISTRY ZCHM-002-00 PRIMARY CHEMISTRY ZCHM-003-00 CORROSION ZCHM-001-00 READING CONTROL WIRING DRAWING ZCWD-000-00 ELECTRICAL PLANT COMPONENTS ZEPC-000-01 TEAM SKILLS TRAINING AND DIAGNOSTICS ZGOP-801-00 TEAM SKILLS TRAINING AND DIAGNOSTICS ZG0P-802-00 HYDRAULIC CONTROLS ZHYD-000-00 HAZARD 0US MATERIALS RESPONSE REFRESHER TRAINING ZHZT-000-00 POST TMI SIGNIFICANT EVENTS AND WATERFORD 3 LER'S ZINC-000-00 INSTRUMENT AND CONTROL THEORY MEASUREMENT DEVICES AND ZIC-001-00 CHART RECORDERS INSTRUMENT AND CONTROL THEORY PROCESS CONTROL THEORY ZIC-002-00 INSTRUMENT AND CONTROL THEORY VALVE ACTUATORS AND ZIC-003-00 POSITIONERS PRINCIPLES OF LUBRICATION ZLUB-000-00 '
INTRODUCTION AND FIXED INCORE NEUTRON DETECTORS ZMCD-801-00 EXCORE NUCLEAR INSTRUMENTATION SYSTEM ZMCD-802-00 VITAL INSTRUMENTS ZMCD-003-00 RADI0 CHEMISTRY ZMCD-804-00 MITIGATING CORE DAMAGE - RADIATION MONITORING ZMCD-805-00 cf.S GENERATION AND REMOVAL ZMCD-806-00 CORE EXIT THEM0C0VPLES ZMCD-807-00 ELASTICITY ZMSC-701-00 CRYSTALLINE STRUCTURE AND METAL PROPERTIES ZMSC-702-00 DUCTILE TO BRITTLE TRANSITIONS AND PLANT OPERATING ZMSC-703~-00 CURVE FRACTIONS AND REAL NUMBERS ZMTH-701-00 EXPONENTS ZMTH-702-00 ROOTS, RADICALS AND FRACTIONAL EXPONENTS ZMTH-703-00 LOGARITHM .
ZMTH-704-00 .
ALGEBRAIC FACTORS AND FRACTIONS ZMTH-705-00 ALGEBRAIC EQUATIONS AND WORD PROBLEMS ZMTH-706-00 TRIGONOMETRIC FUNCTIONS ZMTH-707-00 .
FUNCTIONS, DERIVATIVES AND INTEGRALS ZMTH-708-00 l APPLICATIONS OF PHYSICS AND UNIT ANALYSIS ZPHY-701-00 !
FORCE AND HOTION/ MASS AND WEIGHT ZPHY-702-00 l IMPULSE AND MOMENTUM ZPHY-703-00 TEMPERATURE AND HEAT ZPHY-704-00 i
WORK ENERGY AND GENERAL ENERGY EQUATION ZPHY-705-00 ADMINISTRATIVE - GENERAL ZPPA-001-02 ADMINISTRATIVE PROCEDURE - CHANGES & HANDLING ZPPA-002-00 INTRODUCTION & EMERGENCY ENTRY PROCEDURE ZPPE-001-00 LOCA RECOVERY PROCED'JRE ZPPE-703-00 EXCESS STEAM DEMAND ZPPE-705-01 DEGRADED ELECTRICAL DISTRIBUTION RECOVERY PROCEDURE ZPPE-706-00 LOSS OF MAIN FEEDWATER SAFETY FUNCTION ' RECOVERY ZPPE-707-01 PROCEDURE STEAM GENERATOR TUBE RUPTURE SAVETY FUNCTION REC 0VERY ZPPE-007-01 l PROCEDURE POWER OPERATION AND ASI GUIDELINES ZPPN-801-01 PLANT HEATUP - MODE 5 TO MODE 3 ZPPN -802-01 OP-10-001 (MODE l'TO MODE 5) ZPPN-803-01 PLANT HEATUP-MODE 5 TO MODE 3 ZPPN-701-01 STARTUP AND NORMAL OPERATION ZPPN-702-01 OP-10-001 (MODE 1 TO MODE 5) ZPPN-703-03 SECONDARY SYSTEM 0FF-NORMALS ZPPD-701-00 SELECTED OFF-NORMALS AT POWER ZPPD-801-00 SELECTED OFF-NORMALS WHILE SHUTDOWN ZPP0-802-00 EVACUATION OF CONTROL ROOM AND SUBSEQUENT PLANT ZPPD-803-01 SHUTDOWN PIPING SYSTEMS AND COMPONENTS - VALVES ZPSC-001-01 PIPING SYSTEMS AND COMPONENTS - PUMPS ZPSC-002-00 PIPING SYSTEMS AND COMPONENTS - HEAT EXCHANGERS AND ZPSC-003-00 CONDENSERS PIPING SYSTEMS AND COMPONENTS DEMINERALIZERS AND ION ZPSC-004-00 EXCHANGERS RADIATION DETECTION AND CONTROL ZRAD-001-01 ENVIRONMENTAL MONITORING AND ATMOSHERIC DISPERSION ZRAD-003-02 RADIATION PROTECTION ZRAD-002-00 RADIATION MONITORING TECHNICAL SPECIFICATIONS ZTS-701-00 TECHNICAL SPECIFICATIONS ZTS-702-00 TECHNICAL SPECIFICATIONS ZTS-801-00 TECHNICAL SPECIFICATON (RS,PDL,RE & REM) ZTS-803-00 SAFETY AND CONTROL SYSTEMS TECHNICAL SPECIFICATIONS ZTS-804-00 (PART 1)
SAFETY AND CONTRO SYSTEM TECHNICAL SPECIFICAITONS ZTS-805-00 (PART 2)
EFFLUENT TECH SPEC ZTS-806-00 THERMODYNAMICS ZTYH-701-00 TURBINE THERMODYNAMICS ZTYH-702-00 FLUID FLOW ZTYH-703-00 HEAT TRANSFER METHODS ZTYH-704-00 REACTOR HEAT GENERATION ZTYH-705-00 ,
REACTOR FUEL HEAT TRANSFER ZTYH-706-00 REACTOR THERMAL LIMITS ZTYH-707-00 HEAT BALANCE CALCULATIONS ZTYH-708-00 CORE HEAT REMOVAL CONSIDERATIONS ZTYH-709-00 INTEGRATED THERMODYNAMICS ZTYH-710-00 THERMODYNAMICS ZTYH-801-00 TURBINE THERMODYNAMICS ZTYH-802-00 FLUID FLOW ZTYH-803-00 HEAT TRANSFER METHODS ZTYH-804-00 REACTOR HEAT GENERATION ZTYH-805-00 )
REACTOR FUEL HEAT TRANSFER ZTYH-806-00 1 REACTOR THERMAL LIMITS ZTYH-807-00 1
n
. BASIC CONCEPTS FOR ELECTRICAL THEORY ZTYE-001-00 AC THEORY ZTYE-002-00 ELECTRICAL THEORY \AC GENERATORS ZTYE-004-00 BATTERY AND CHARGERS ZTYE-005-00 NUCLEAR PHYSICS CONCEPTS ZTYR-001-00 FISSION AND THE NEUTRON LIFE CYCLE ZTYR-002-00 i NEUTRON KINETICS ZTYR-003-00 !
REACTOR KINETICS ZTYR-004-00 l SUBCRITICAL BEHAVIOR ZTYR-005-00 )
REACTIVITY COEFFICIENTS & DEFECT ZTYR-006-00 i FISSION PRODUCT POIS0NS ZTYR-007-00 CONTROL POISONS ZTYR-008-00 OPERATIONAL ASPECTS ZTYR-009-00 PLANT SPECIFIC OPERATIONAL ASPECTS ZTYR-010-00 REACTOR THEORY ZTYR-801-00 THEORY, REACTOR (SPECIFIC OPERATING CHARACTERISTICS ZTYR-802-00 i THEORY, REACTOR (FUEL HANDLING AND CORE PARAMETERS ZTYR-803-00 SYSTEM DESCRIPTIONS EMERGENCY FEEDWATER EMERGENCY DIESEL GENERATOR AND SEQUENCER MAIN TURBINE AND MSR'S CIRCULATING WATER / INTAKE SYSTEM COMPONENT COOLING WATER / INTAKE SYSTEM MAIN FEEDWATER/ AUXILIARY FEEDWATER REAC10R AUXILIARY BUILDING HVAC INSTRUMENT AIR / STATION AIR CONDENSER AIR EVACUATION STEAM GENERATOR BLOWDOWN FIRE DETECTION AND PROTECTION VIBRATION AND LOOSE PARTS MONITORING REACTOR COOLANT SYSTEM / REACTOR COOLANT PUMPS DIGITAL ELECTRO-HYDRAULIC CONTROL CONDENSATE SYSTEM MAIN GENERATOR INVERTERS AND DISTRIBUTION CHEMICAL AND VOLUME CONTROL SAFETY INJECTION PLANT PROTECTION SYSTEM CONTAINMENT AND CONTAINMENT ISOLATION HYDROGEN CONTROL HAIN STEAM 6.9 KV DISTRIBUTION 4.16 KV DISTRIBUTION 480 VOLTS AC 125 VOLTS DC CONTAINMENT COOLING AND VENTILATION CONTROL ROOM HVAC REACTOR REGULATING FEEDWATER CONTROL PRESSURIZER LEVEL CONTROL / PRESSURE CONTROL REACTOR VESSEL AND INTERNALS CONTROL ELEMENT DRIVE MECHANISM CONTROL EXCORE NUCLEAR INSTRUMENTATION INCORE NUCLEAR INSTRUMENTATION l
CONTAINMENT SPRAY FUEL HANDLING AND STORAGE EQUIPMENT PRIMARY / SECONDARY SAMPLING SEISMIC MONITORING AUXILIARY STEAM MAIN TURBINE LUBE OIL /EH POST ACCIDENT SAMPLING RADIATION MONITORING GLAND STEAM TURBINE COOLING WATER l LOW VOLTAGE DISTRIBUTION l NORMAL AND EMERGENCY LIGHTING l PLANT SUMPS :
SEWERAGE SYSTEM l ESSENTIAL / SUPPLEMENTAL CHILLED WATER TURBINE BUILDING HVAC CORE OPERATING LIMITS SUPERVISORY SYSTEM CORE PROTECTION CALCULATION PLANT MONITORING COMPUTER ,
REACTOR POWER CUTBACK :
STEAM BYPASS CONTROL SYSTEM PRIMARY MAKE-UP ,
CONDENSATE MAKE-UP HEATERS, VENTS, AND DRAINS FEED PUMP TURBINE / CONTROL GENERATOR GAS STATOR COIL WATER SEAL OIL TRANSFORMER AND SWITCHING STATION COMPRESSED GAS COMMUNICATIONS SYSTEMS
- WATER TREATMENT SYSTEMS !
FUEL HANDLING BUILDING HVAC SHIELD BUILDING HVAC ,
PLANT DATA BOOK SIMULATOR INITIAL CONDITIONS >
SIMULATOR CAUSE AND EFFECT DOCUMENT SIMULATOR EVENTS LISTING SIMULATOR SIGNIFICANT PROBLEM REPORTS SIMULATOR SCENARIOS EXAMINATION QUESTION BANK JOB PERFORMANCE MEASURES 001*001*01*01 REACTOR TRIP BREAKER OPERATION -
001*002*01*01 PERFORM ESTIMATED CRITICAL CONFIGURATION (WITHDRAWING CEAS TO CRITICALITY) 001*002*01*04 PLACE A CEA/PLCEA SUBGROUP ON THE HOLD BUS 001*004*02*01 PERFORM SHUTDOWN MARGIN CALCULATIONS 001*006*01*01 PERFORM CEA POSITION INITIALIZATION ON PMC t
G01*007*01*04 CEA DRIVE MG SET STARTUP 001*008*01*01 OPERATE THE CEAS TO CONTROL AXIAL SHAPE INDEX 001*008*01*04 CEA DRIVE MG SET SHUTDOWN 001*010*01*01 MANUALLY TRIP THE REACTOR 001*013*01*04 PARALLEL MG SETS 001*018*01*01 PERFORM SHUTDOWN BANK WITHDRAWAL 001*020*01*01 OPERATE CEAS IN AUTOMATIC SEQUENTIAL (AS) MODE 001*021*01*01 OPERATION OF CEA(S) IN MANUAL GROUP (MG) MODE 001*035*04*01 PERFORM OPERATIONS INVOLVING CEA MISALIGNMENT 003*001*01*01 START A REACTOR COOLANT PUMP 003*003*01*01 PERFORM A NORMAL REACTOR COOLANT PUMP SHUTDOWN 004*005*01*04 PURGE THE VCT WITH HYDR 0 GEN AND ESTABLISH A HYDROGEN BLANKET ON THE VCT 004*006*01*01 PERFORM BORON CONCENTRATION CHANGE CALCULATIONS 004*009*01*01 MAKEUP TO THE VCT USING THE AUTO MAKEUP MODE 004*018*01*01 OPERATE THE CVCS TO FORM A STEAM BUBBLE IN THE PRESSURIZER 004*025*01*01 BLENDED MAKEUP TO VCT USING MANUAL MODE 004*029*01*01 SECURE CHARGING AND LETDOWN DURING NORMAL OPERATION 004*034*01*01 PERFORM BLENDED MAKEUP TO THE RWSP 004*047*01*01 DIRECT DILUTE TO RCS 004*048*01*01 DIRECT B0 RATION TO RCS 004*050*01*01 PERFORM MAKEUP-BORATE MODE CALCULATION 004*051*01*01 SHIFT CHARGING PUMPS 004*056*01*01 PURGE THE VCT WITH HYDROGEN AND ESTABLISH A HYDROGEN BLANKET ON VCT 005*003*01*01 ALIGN LTOP RELIEF FOR SERVICE 005*004*01*01 ALIGN SHUTDOWN COOLING TRAIN TO STANDBY 005*005*01*01 PLACE SHUTDOWN COOLING TRAIN IN SERVICE 005*005*01*04 PLACE SHUTDOWN COOLING PURIFICATION IN SERVICE 005*006*01*01 SECURE SHUTDOWN COOLING TRAIN 005*008*01*01 PLACE SHUTDOWN COOLING PURIFICATION IN SERVICE 005*009*01*01 SECURE SHUTDOWN COOLING PURIFICATION 006*001*02*01 PERFORM EMERGENCY CORE COOLING SYSTEM (ECCS) PUMP OPERABILITY CHECKS 006*003*01*01 ADJUST SAFETY INJECTION TANK LEVEL WITH SIT ALIGNED FOR SAFETY INJECTION 006*005*01*01 RAISE SAFETY INJELTION TANK PRESSURE WITH NITROGEN 006*009*01*01 PREPARE SAFETY INJECTION TANK FOR A NORMAL STARTUP 006*014*05*01 ALIGN HIGH PRESSURE SAFETY INJECTION FLOW FOR HOT LEG AND COLD LEG INJECTION 006*015*02*01 PERFORM HPSI PUMP PRESERVICE OPERABILITY CHECK 008*006*01*01 PLACING CCW PUMP A/B IN SERVICE TO REPLACE CCW PUMP 008*027*01*01 ORM MANUAL STARTUP OF ACCW PUMP 010*001*01*01 CONTROL PRESSURIZER PRESSURE MANUALLY, USING LETDOWN BACKPRESSURE REGULATOR 010*002*01*01 CONTROL PRESSURIZER PRESSURE IN MANUAL MODE DURING C00LDOWN 010*003*01*01 TRANSFER FROM MANUAL TO AUTOMATIC PRESSURE CONTROL 010*012*04*01 CONTROL PRESSURIZER PRESSURE USING AUXILIARY SPRAY 010*013*01*01 BORON EQUALIZATION 010*016*04*01 PERFORM OPERATIONS INVOLVING FAILURE OF PRESSURIZER PRESSURE INSTRUMENT 010*018*04*01 PERFORM OPERATIONS INVOLVING PRESSURIZER SPRAY VALVE MALFUNCTION 011*001*04*01 OPERATE THE PRESSURIZER LEVEL CONTROL IN MANUAL
011*002*04*01 TRANSFER FROM LOCAL TO RRS PRESSURIZER LEVEL SETPOINT CONTROL .
011*010*04*01 PERFORM OPERATIONS INVOLVING CONTROLLING LEVEL CHANNEL MALFUNCTION 011*012*04*01 PERFORM OPERATIONS INVOLVING PRESSURIZER LEVEL SETPOINT MALFUNCTION WITH ABNORMAL HOT LEG TEMPERATURE INDICATION 011*013*04*01 PERFORM OPERATIONS INVOLVING PRESSURIZER LEVEL SETPOINT MALFUNCTION WITH AENORMAL COLD LEG TEMPERATURE INDICATION 012*010*01*01 DISPLAY CPC POINT I.D.
012*011*01*01 CHANGE CPC ADDRESSABLE CONSTANTS 012*014*01*01 PERFORM CPC WARM RESTART 012*016*01*01 PLACE THE REACTOR TRIP ON TURBINE TRIP IN SERVICE 015*001*02*01 STARTUP CHANNEL HIGH VOLTAGE TEST AND RANGE CHECK 015*002*02*01 STARTUP CHANNEL AUDIBLE COUNT RATE FUNCTIONAL TEST 015*003*01*01 AUDIO COUNT RATE CHANNEL OPERATION 015*016*01*01 ADJUST THE BORON DILUTION MONITOR SFTPOINT 015*026*01*01 STARTUP AND CONTROL CHANNEL OPERATION 1 (2) 015*027*01*01 SAFETY CHANNEL OPERATION A(B)(C)(D) 018*007*01*01 VLPH ACTIONS FOR IMPACT EVENT ALARM CONDITION 022*016*01*01 STOP A REACTOR CAVITY COOLING FAN 028*002*01*01 STARTUP THE HYDROGEN RECOMBINERS 033*002*01*04 ADD MAKEUP TO THE SPENT FUEL POOL FROM THE REFUELING WATER STORAGE POOL 038*010*01*01 SHUTDOWN THE STEAM GENERATOR BLOWDOWN SYSTEM 039*003*01*01 PERFORM A MOISTURE SEPARATOR / REHEATER COLD START 039*008*01*04 OPERATE THE ATMOSPHERIC DUMP VALVES LOCALLY (USING AIR AND MANUAL) 045*002*02*04 PERFORM MAIN TURBINE PROTECTION DEVICES TRIP TEST 045*006*01*04 TRIP THE MAIN TURBINE GENERATOR LOCALLY 045*031*05*01 MANUALLY TRIP THE TURBINE GENERATOR 046*003*01*04 TRANSFER GLAND SEAL SUPPLY FROM MAIN STEAM TO AUXILIARY BOILER 059*009*01*01 PERFORM FEEDWATER PUMP SHUTDOWN 059*020*01*01 STEAM GENERATOR FEEDWATER TURBINE STARTUP USING MAIN STEAM 059*022*01*04 MANUALLY TRIP MAIN FEEDWATER PUMPS LOCALLY 059*027*01*01 PERFORM PREPARATION FOR STARTING A STEAM GENERATOR FEED PUMP 059*031*01*01 PLACE THE SECOND MAIN FEEDWATER PUMP IN SERVICE 059*032*01*01 PERFORM MFIV SLOW CLOSURE 061*001*02*01 061*006*01*01 PERFORM EMERGENCY FEEDWATER PUMP A(
LINE UP THE EFW SYSTEM FOR AUTOMATI 061*007*01*04
- TRANSFER EMERGENCY FEEDWATER PUMP SUCTION TO AUXILIARY COMPONENT COOLING WET TOWERS 061*009*01*01 SHUTDOWN THE EMERGENCY FEEDWATER SYSTEM 061*012*01*01 RETURN EMERGENCY FEEDWATER TO NORMAL AFTER EFAS INITIATION 061*012*01*04 RESET EMERGENCY FEEDWATER PUMP TURBINE STOP VALVE AFTER OVERSPEED TRIP 061*013*01*01 PERFORM EFW RECIRC AND SAMPLING 061*014*01*01 FILL THE STEAM GENERATORS DURING SHUTDOWN CONDITIONS 061*015*01*01 PERFORM AMMONIA INJECTION TO THE EFW SYSTEM 061*016*01*01 PERFORM HYDRAZINE INJECTION TO THE EFW SYSTEM 061*017*02*01 PERFORM EMERGENCY FEEDWATER PUMP AB OPERABILITY 062*003*01*04 STARTUP SUPS 3MA-5, 3MB-S, 3MC-S, OR 3MD-S
- 062*013*01*04 RACK-IN AN AUXILIARY BUS BREAKER (4160V OR 6900V) 062*033*01*04 DEENERGIZE A SUPS 063*007*01*04 RETURNING BATTERY CHARGER TO SERVICE 063*009*01*04 REMOVE BATTERY CHARGER FROM OPERATION 064*002*01*04 MANUALLY START THE EMERGENCY DIESEL GENERATOR LOCALLY 064*002*01*04 MANUALLY START THE EMERGENCY DIESEL GENERATOR LOCALLY -
064*003*01*01 SYNCHRONIZE AND LOAD THE EDG 1 064*005*01*01 UNLOAD, STOP, AND RETURN EDG A(B) TO STANDBY l 073*004*02*01 PERFORM RADI0 ACTIVE LIQUID EFFLUENT MONITORING ;
SYSTEM SOURCE CHECK FP.0M CP-6 073*012*01*01 REBOOT THE RM-11 1 078*001*05*01 LINE UP POTABLE WATER TO INSTRUMENT AIR COMPRESSORS- i FOR EMERGENCY COOLING l 078*005*01*04 REMOVE AN AIR DRYER FROM SERVICE 086*005*01*04 MANUALLY START / SECURE THE DIESEL FIRE PUMPS i 086*020*01*04 MANUALLY ACTUATE FIRE PROTECTION SYSTEMS STANDING ORDERS 1
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