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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999
Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20217N2111999-10-19019 October 1999
Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings
ML20217L0101999-10-18018 October 1999
Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions
ML20217L0141999-10-18018 October 1999
Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator
ML20217G7051999-10-14014 October 1999
Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004
05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999
Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal
ML20217D5151999-10-0707 October 1999
Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls
ML20217C6251999-10-0505 October 1999
Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives
ML20212J6921999-09-29029 September 1999
Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified
ML20216G2441999-09-27027 September 1999
Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted
05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999
Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form
IR 05000382/19993011999-09-21021 September 1999
Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14
ML20212D8761999-09-16016 September 1999
Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl
ML20212C2471999-09-16016 September 1999
Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld
ML20212C2391999-09-16016 September 1999
Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901
ML20212C5881999-09-14014 September 1999
Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted
ML20211Q4421999-09-0909 September 1999
Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations
ML20211P4121999-09-0707 September 1999
Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d)
ML20211M8391999-09-0303 September 1999
Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl
ML20211L3681999-09-0202 September 1999
Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld
ML20211K9741999-09-0101 September 1999
Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy
05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999
Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form
ML20211M3641999-08-30030 August 1999
Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld
ML20211G5751999-08-27027 August 1999
Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4
ML20211E3281999-08-26026 August 1999
Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments
05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999
Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately
05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999
Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form
ML20211F5421999-08-24024 August 1999
Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed
ML20211F3561999-08-24024 August 1999
Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable
ML20211F4611999-08-24024 August 1999
Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements
ML20211G1731999-08-23023 August 1999
Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20211C5101999-08-19019 August 1999
Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15
ML20210T9791999-08-18018 August 1999
Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210S0561999-08-12012 August 1999
Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3
ML20210Q6161999-08-12012 August 1999
Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos
ML20217F2661999-08-12012 August 1999
Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator
ML20210R9231999-08-11011 August 1999
Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999
Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl
ML20210H4291999-07-29029 July 1999
Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs
ML20210F9451999-07-27027 July 1999
Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790
ML20210D3171999-07-23023 July 1999
Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr
05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999
Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached
ML20210D8701999-07-23023 July 1999
Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3
ML20210B1521999-07-15015 July 1999
Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations
ML20209G9771999-07-13013 July 1999
Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654
IR 05000382/19990081999-07-12012 July 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503
ML20209E5231999-07-0909 July 1999
Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583
ML20209D4051999-07-0707 July 1999
Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L0101999-10-18018 October 1999
Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions
ML20217L0141999-10-18018 October 1999
Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator
ML20217G7051999-10-14014 October 1999
Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004
05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999
Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal
ML20217D5151999-10-0707 October 1999
Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls
05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999
Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form
ML20212C2391999-09-16016 September 1999
Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901
ML20212C2471999-09-16016 September 1999
Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld
ML20211P4121999-09-0707 September 1999
Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d)
ML20211M8391999-09-0303 September 1999
Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl
ML20211L3681999-09-0202 September 1999
Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld
05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999
Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form
ML20211M3641999-08-30030 August 1999
Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld
ML20211E3281999-08-26026 August 1999
Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments
05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999
Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form
05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999
Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately
ML20211F3561999-08-24024 August 1999
Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable
ML20211F5421999-08-24024 August 1999
Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed
ML20211C5101999-08-19019 August 1999
Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15
ML20210Q6161999-08-12012 August 1999
Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos
ML20210S0561999-08-12012 August 1999
Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3
ML20217F2661999-08-12012 August 1999
Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator
05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999
Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl
ML20210H4291999-07-29029 July 1999
Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs
ML20210F9451999-07-27027 July 1999
Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790
ML20210D3171999-07-23023 July 1999
Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr
05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999
Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached
ML20209G9771999-07-13013 July 1999
Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654
ML20209D4051999-07-0707 July 1999
Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode
ML20209B6081999-06-30030 June 1999
Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl
05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits1999-06-24024 June 1999
Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits
ML20196G5731999-06-24024 June 1999
Forwards Operator Licensing Exam Outlines Associated with Exam Scheduled for Wk of 991004.Exam Development Is Being Performed in Accordance with NUREG-1021,Rev 8
ML20212J4121999-06-23023 June 1999
Responds to NRC Re Reconsideration of EA 98-022. Details Provided on Actions Util Has Taken or Plans to Take to Address NRC Concerns with Ability to Demonstrate Adequate Flow Availability to Meet Design Requirements
ML20196E9371999-06-22022 June 1999
Forwards Revs Made to EP Training Procedures.Procedures NTC-217 & NTC-217 Have Been Deleted.Procedure NTP-203 Was Revised to Combine Requirement Previously Included in Procedures NRC-216 & NTC-217
ML20196A1021999-06-17017 June 1999
Provides Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Per 990513 Request of NRC Project Manager
ML20195F3671999-06-0909 June 1999
Forwards Rev 21,Change 0 to EP-001-010, Unusual Event. Rev Reviewed in Accordance with 10CFR50.54(q) Requirements & Determined Not to Decrease Effectiveness of Emergency Plan
ML20195C7801999-06-0303 June 1999
Submits Response to Violations Noted in Insp Rept 50-382/99-08.Corrective Actions:All Licensee Access Authorization Personnel Were Retrained Prior to Completion of Insp
ML20195C2951999-05-28028 May 1999
Forwards Annual Evaluation of Changes & Errors Identified in Abb CE ECCS Performance Evaluation Models Used for LOCA Analyses.Results of Annual Evaluation for CY98 Detailed in Attached Rept,Based Upon Suppl 10 to Abb CE Rept
ML20195C0241999-05-28028 May 1999
Notifies NRC of Operator Medical Condition for Waterford 3 Opertaor Sp Wolfe,License SOP-43723.Attached NRC Form & Memo Contain Info Concerning Condition.Without Encls
ML20196L3281999-05-24024 May 1999
Informs That Entergy Is Withdrawing TS Change Request NPF-38-205 Re TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection Submitted on 980629
ML20206S4691999-05-17017 May 1999
Requests Waiver of Exam for SRO Licenses for an Vest & Hj Lewis,Iaw 10CFR55.47.Both Individuals Have Held Licenses at Plant within Past Two Year Period,But Licenses Expired Upon Leaving Util Employment.Encl Withheld
05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.31999-05-14014 May 1999
Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3
ML20206N1921999-05-10010 May 1999
Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1
ML20206J1471999-05-0606 May 1999
Requests That Implementation Date for TS Change Request NPF-38-211 Be within 90 Days of Approval to Allow for Installation of New Monitoring Sys for Broad Range Gas Detection Sys
ML20206J1721999-05-0606 May 1999
Notifies That Proposed Schedule for Plant 1999 Annual Exercise Is Wk of 991013.Exercise Objective Meeting Scheduled for 990513 at St John Baptist Parish Emergency Operations Ctr
ML20206G8021999-05-0404 May 1999
Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-382/99-01.Licensee Denies Violation as Stated.Change Made Is Denoted by Rev Bar & Does Not Materially Impact Original Ltr
ML20206E7811999-04-29029 April 1999
Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested
ML20205T2531999-04-22022 April 1999
Forwards LER 99-S02-00,describing Occurrence of Contract Employee Inappropriately Being Granted Unescorted Access to Plant Protected Area
ML20205R2611999-04-20020 April 1999
Forwards Rev 19 to Physical Security Plan,Submitted in Accordance with 10CFR50.54(p).Plan Rev Was Approved & Implemented on 990407.Rev Withheld,Per 10CFR73.21
ML20205Q3241999-04-16016 April 1999
Submits Addl Info Re TS Change Request NPF-38-215 for Administrative Controls TS Changes.Appropriate Pages from New Entergy Common QA Program Manual Provided as Attachment to Ltr
1999-09-07
[Table view]
Category:UTILITY TO NRC
MONTHYEARW3P90-1505, Forwards Proposed Operator Licensing Exam Schedule & Proposed Requalification Exam Schedule,Per Generic Ltr 90-071990-09-17017 September 1990
Forwards Proposed Operator Licensing Exam Schedule & Proposed Requalification Exam Schedule,Per Generic Ltr 90-07
W3P90-1163, Forwards Relief Requests Associated w/10-yr Inservice Insp Program Per Section 50.55a(g)(6)(i) of 10CFR501990-09-0606 September 1990
Forwards Relief Requests Associated w/10-yr Inservice Insp Program Per Section 50.55a(g)(6)(i) of 10CFR50
W3P90-1191, Responds to Violations Noted in Insp Rept 50-382/90-15. Corrective Actions:Tech Spec Surveillance Procedure PE-005-004 Will Be Revised to Ensure That Normally Closed Valves Opened & Verified to Close for Toxic Gas Signal1990-08-31031 August 1990
Responds to Violations Noted in Insp Rept 50-382/90-15. Corrective Actions:Tech Spec Surveillance Procedure PE-005-004 Will Be Revised to Ensure That Normally Closed Valves Opened & Verified to Close for Toxic Gas Signal
W3P90-1194, Submits Fitness for Duty Performance Data for 6-month Period from Jan-June 19901990-08-29029 August 1990
Submits Fitness for Duty Performance Data for 6-month Period from Jan-June 1990
W3P90-1184, Responds to Violations Noted in Insp Rept 50-382/90-14. Corrective Actions:Local Leak Rate Test Activities Shall Be Administratively Controlled to Require Use of Test Method Other than Pressure Decay1990-08-20020 August 1990
Responds to Violations Noted in Insp Rept 50-382/90-14. Corrective Actions:Local Leak Rate Test Activities Shall Be Administratively Controlled to Require Use of Test Method Other than Pressure Decay
W3P90-1187, Forwards Booklet Entitled, Safety Info - Plans to Help You During Emergencies, Recently Distributed to General Public1990-08-17017 August 1990
Forwards Booklet Entitled, Safety Info - Plans to Help You During Emergencies, Recently Distributed to General Public
W3P90-1189, Forwards Waterford 3 Steam Electric Station Emergency Preparedness Exercise for 901024. Annual Exercise Will Be Performed Using Control Room Simulator1990-08-17017 August 1990
Forwards Waterford 3 Steam Electric Station Emergency Preparedness Exercise for 901024. Annual Exercise Will Be Performed Using Control Room Simulator
W3P90-1162, Forwards Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-19951990-08-16016 August 1990
Forwards Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-1995
W3P90-1174, Forwards Rev to Emergency Plan & QA Program,Consisting of Chart Indicating Changes to Util Organization1990-08-0707 August 1990
Forwards Rev to Emergency Plan & QA Program,Consisting of Chart Indicating Changes to Util Organization
W3P90-1177, Forwards Revised Objectives for Emergency Preparedness Exercise Scheduled for 9010241990-08-0303 August 1990
Forwards Revised Objectives for Emergency Preparedness Exercise Scheduled for 901024
W3P90-1164, Forwards Waterford Steam Electric Station Unit 3 Basemat Monitoring Program Special Rept 3. Rept Documents Continued Integrity of Basemat as Verified by Program from Time of Inception of Monitoring in 1985 Through Mar 19901990-08-0303 August 1990
Forwards Waterford Steam Electric Station Unit 3 Basemat Monitoring Program Special Rept 3. Rept Documents Continued Integrity of Basemat as Verified by Program from Time of Inception of Monitoring in 1985 Through Mar 1990
W3P90-1167, Forwards Rev 12 to Emergency Plan Implementing Instruction EP-001-001, Recognition & Classification of Emergency Conditions, Reflecting Name Change of State Agency to Louisiana Radiation Protection Div1990-07-19019 July 1990
Forwards Rev 12 to Emergency Plan Implementing Instruction EP-001-001, Recognition & Classification of Emergency Conditions, Reflecting Name Change of State Agency to Louisiana Radiation Protection Div
W3P90-1148, Responds to NRC 900503 Submittal Concerning Review of Util Rev 6,Change 1 to Inservice Testing Program for Pumps & Valves1990-07-17017 July 1990
Responds to NRC 900503 Submittal Concerning Review of Util Rev 6,Change 1 to Inservice Testing Program for Pumps & Valves
W3P90-1143, Advises That 900404 Request for Addl Info Re Tech Spec Change Request NPF-38-103 Will Be Provided by 900803.Change Will Extend Test Frequency of Channel Functional Tests for ESF Actuation Sys & Reactor Protection Sys Instrumentation1990-07-0606 July 1990
Advises That 900404 Request for Addl Info Re Tech Spec Change Request NPF-38-103 Will Be Provided by 900803.Change Will Extend Test Frequency of Channel Functional Tests for ESF Actuation Sys & Reactor Protection Sys Instrumentation
W3P90-1379, Provides Notification That Util Has Consolidated Operation of All Nuclear Facilities,Effective 9006061990-07-0202 July 1990
Provides Notification That Util Has Consolidated Operation of All Nuclear Facilities,Effective 900606
ML20044A5541990-06-26026 June 1990
Forwards Response to Generic Ltr 90-04 Requesting Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions
ML20044A5551990-06-22022 June 1990
Describes Changes Required to Emergency Plan as Result of Transfer of Operations to Entergy Operations,Inc. Administrative Changes to Plan Necessary to Distinguish Support Functions to Be Retained by Louisiana Power & Light
W3P90-1365, Provides Notification of Change in Operator Status Per 10CFR50.74 Due to Entergy Corp Consolidating Operation of All Nuclear Generating Facilities,Including Plant Under Util1990-06-19019 June 1990
Provides Notification of Change in Operator Status Per 10CFR50.74 Due to Entergy Corp Consolidating Operation of All Nuclear Generating Facilities,Including Plant Under Util
ML20043G3431990-06-14014 June 1990
Requests That All NRC Correspondence Re Plant Be Addressed to RP Barkhurst at Address Indicated in 900523 Ltr
ML20043F5121990-06-0808 June 1990
Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606
ML20043F2621990-06-0606 June 1990
Requests Withdrawal of 900504 Request to Extend Implementation Date of Amend 60 Re Transfer of Operations to Entergy,Inc.All Necessary Regulatory Approvals Obtained & License Conditions Implemented
ML20043C1861990-05-29029 May 1990
Submits Response to 900426 Comments Re Investigation Case 4-88-020.Util Issued P.O. Rev Downgrading Order of Circuit Breakers & Eliminating Nuclear Requirements
ML20043E5441990-05-24024 May 1990
Forwards Public Version of Change 1 to Rev 2 to EPIP EP-002-015, Emergency Responder Activation. Release Memo Encl
ML20043B3501990-05-23023 May 1990
Forwards Response to Concerns Noted in Insp Rept 50-382/90-02.Response Withheld
ML20043B3781990-05-23023 May 1990
Requests Change in NRC Correspondence Distribution List, Deleting Rt Lally & Adding DC Hintz,Gw Muench & RB Mcgehee. All Ref to Util Changed to Entergy Operations,Inc.Proposed NRC Correspondence Distribution List Encl
W3P90-1314, Requests NRC Concurrence That Design/Controls/Testing to Minimize Potential for Common Header Blockage Acceptable Per 900510 Meeting.Tap Alternatives for Shutdown Cooling Level Indication Sys Discussed1990-05-21021 May 1990
Requests NRC Concurrence That Design/Controls/Testing to Minimize Potential for Common Header Blockage Acceptable Per 900510 Meeting.Tap Alternatives for Shutdown Cooling Level Indication Sys Discussed
ML20043B3271990-05-21021 May 1990
Forwards Justification for Continued Operation Re Taped Splice for Use in Instrument Circuits,Per 900517 Request
ML20042F5251990-05-0404 May 1990
Requests Extension of 90 Days to Implement Amend 60 to License NPF-38 in Order to Provide Securities & Exchange Commission Time to Review Transfer of Licensed Activities to Entergy Operations,Inc
ML20042E5501990-04-17017 April 1990
Responds to Request for Addl Info Re Feedwater Isolation Valve Bases Change Request Dtd 891006
ML20012F4551990-04-10010 April 1990
Forwards Rev 10,Change 4 to Physical Security Plan.Encl Withheld
ML20012F5491990-04-0606 April 1990
Advises That Util Installed Two Addl Benchmarks for Use as Part of Basemat Surveillance Program to Increase Efficiency of Survey Readings.New Benchmarks Will Be Shown on FSAR Figure 1.2.1 as Part of Next FSAR Rev
ML20012F3181990-04-0606 April 1990
Forwards Util,New Orleans Public Svc,Inc & Entergy Corp 1989 Annual Repts
ML20012E8971990-03-30030 March 1990
Submits Results of Evaluation of Util 900414 Response to Station Blackout Rule (10CFR50.63).Station Mod May Be Required to Change Starting Air Sys to Accomodate Compressed Bottled Air
ML20012E2551990-03-27027 March 1990
Responds to Violation Noted in Insp Rept 50-382/90-01. Corrective Actions:Qa Review of Licensed Operator Medical Exam Records Conducted & Sys Implemented to Track Types & Due Dates of Medical Exams Required for Operators
ML20012E0511990-03-27027 March 1990
Forwards Rev 10,Change 3 to Physical Security Plan.Rev Withheld
ML20012D5461990-03-22022 March 1990
Forwards Documentation from Nuclear Mutual Ltd,Nelia & Nuclear Electric Insurance Ltd Certifying Present Onsite Property Damage Insurance
ML20012D4911990-03-21021 March 1990
Responds to NRC 900208 Ltr Re Violations Noted in Investigation Rept 4-89-002.Corrective Action:Proper Sequence of Insp Hold Point Placed in Procedure Under Change Implemented on 880425
ML20012C0691990-03-14014 March 1990
Advises That Util Intends to Address Steam Generator Overfill Concerns (USI A-47) Utilizing Individual Plant Exam Process,Per Generic Ltr 89-14
ML20012C0421990-03-12012 March 1990
Forwards Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Results Not Reflective of Particular Calendar Yr
ML20012B6731990-03-0707 March 1990
Responds to NRC Bulletin 88-011,Action 1.a Re Insp of Surge Line to Determine Discernible Distress or Structural Damage & Advises That Neither Surge Line Nor Affiliated Hardware Suffered Any Discernible Distress or Structural Damage
ML20006F5321990-02-22022 February 1990
Forwards Payment for Order Imposing Civil Monetary Penalty in Response to Enforcement Action EA-89-069
ML20011F1401990-02-21021 February 1990
Responds to Violations Noted in Insp Rept 50-382/89-41. Corrective Action:Review of Independent Verification Requirements Re Maint Activities Performed
ML20006F1731990-02-19019 February 1990
Forwards Corrected Pages 9.2-21 & 9.2-22 of Rev 3 to FSAR, Per 891214 Ltr
ML20006E5781990-02-13013 February 1990
Forwards Third Refueling Inservice Insp Summary Rept for Waterford Steam Electric Station Unit 3.
ML20006D0571990-02-0202 February 1990
Responds to SALP Rept for Aug 1988 - Oct 1989.Contrary to Info Contained in SALP Rept,Civil Penalty Not Assessed by State of Nv for Radioactive Matl Transport Violations.Issue Resolved W/State of Nv W/O Issuance of Civil Penalty
ML20006C1631990-01-30030 January 1990
Requests Extension of Commitment Dates in Response to Violations Noted in Insp Repts 50-382/89-17 & 50-382/89-22 to 900222 & 19,respectively.Violations Covered Use of Duplex Strainers & Missing Seismic Support for Cabinet
ML20006C1581990-01-29029 January 1990
Forwards Response to Generic Ltr 89-13 Re safety-related Open Svc Water Sys.Instruments in Place on Component Cooling Water Sys/Auxiliary Component Cooling Water Sys HXs Which Connect to Plant Monitor Computer
ML20006C1611990-01-29029 January 1990
Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Instructions for Determining Acceptable Refueling Boron Concentration Provided in Procedure RF-005-001
ML20006B4121990-01-26026 January 1990
Informs That Photographic Surveys Discontinued,Per Basemat Monitoring Program.Monitoring Program Implementing Procedure Will Be Revised to Reflect Change
ML20006A7091990-01-22022 January 1990
Forwards List of Individuals That No Longer Require Reactor Operator Licenses at Plant
1990-09-06
[Table view] |
Text
_ __ _ _
l Louisiama ,.. o m ec~oeer e.,
P O W E R & L 1 G H T ! NEW oALE ANS 7017
. .m eoxecee LoutslANA 4000 . (50.)388-2345 MIDDLE SOUTH UTIUTIES SYSTEM August 5 ,1983 W3P83-1853 Q-3-A20.16 L.09.02 Director of Nuclear Reactor Regulation Attention: Mr. G. W. Knighton, Chief Licensing Branch Number 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555
SUBJECT:
Waterford 3 SES Docket Number 50-382 Environmental Qualification Rosemont Transmitters Model 1153A
Reference:
W3P83-0320 dated January 27, 1983
Dear Mr. Knighton:
As indicated in Enclosure 3, page 71 of the reference submittal, additional information is required to resolve the aging and operability issues of the subject transmitters. The purpose of this letter is to supply the neces-sary information.
A resolution and supporting reports, which are included as attachments, provide an explanation on how the conclusion was reached that these transmitters are qualified for 6.5 years in containment or 19.3 years out-side containment. These attachments are also intended to represent our justification for interim operation for the Rosemont ll53A transmitters.
If you have any questions on this submittal, please advise.
Sincerely,
(. Q m ,
F. J. Drummond Manager Engineering & Technical Services FJD/SJD/ch Attachments cc: Jim Wilson, Hukam Garg, E. L. Blake, W. M. Stevenson 800I 8308110198 830805 PDR ADOCK 05000382 A PDR
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Attachments i
1: Resolution 2: Justification'for Interim Operation 3: EDS Report No. 03-0490-1037 Rev. O, Nov. 1982 4: Westinghouse " Qualification Testing of Rosemont Model 1153 Series A Electronic Transmitters",
December 1978 5: " Post-test analysis of 1153 Series A Pressure Transmitters for Westinghouse PWR Systems Division."
RMT Report No. 179912A t
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Resolution Attachment 1 The qualification lifetime for safety related transmitters used at the Waterford-3 Steam Electric Station has been questioned by the NRC.
The present objective is to establish a qualified life for the Rosemont 1153 Series A transmitters presently installed at various locations in the containment and reactor auxiliary buildings at Waterford-3.
The Rosemont Model 1153 A transmitters used in containment and in the reactor auxiliary building were purchased to IEEE 323-1971 qualifications through the NSSS and Ebasco contacts for Waterford-3.
Subsequent to this purchase, the IEEE 323-1974 was issued which required thermal aging as part of the qualification testing. The Rosemont 1153 A transmitters are not qualified to the 1974 methodology.
Although the purchase orders predate the IEEE Standard, Louisiana Power
& Light Company has elected to comply, where feasible, with the more conservative requirements. Therefore, we contracted EDS Nuclear to provide an analysis for the qualified life of the Rosemont 1153 A transmitters.
The basis of the EDS analysis is a qualification test performed by Westinghouse and calculations which use Arrhenius techniques. The question of qualification has arisen since the issuance of the Westing-house Report in which three out of four 1153 A transmitters failed in post-LOCA environment.
The thermal portion of the Westinghouse test is considered valid because the three failed samples did not fail as a result of common mode. The first of the three failed test units presented erratic readings and was considered a random failure which was not attributed to testing. The second failure was caused by a degraded cable entry seal which allowed caustic boric acid spray to enter the dye cavity and caused output errors. The third failure was due to a cable entry seal fitting which leaked and allowed the boric acid spray to enter the terminal side of the electronic housing. The fourth test specimen passed the LOCA test.
Since two of the three failures were attributed to degraded cable entry seal, which were not within the scope of the test, and since Ebasco is providing cable seals which are environmentally qualified I for incontainment services and the third failure is considered random, EDS concludes that the 1153 A transmitters are qualified based on the successful testing of the fourth sample.
Using the Arrhenius methodology, the calculated lives of the ethylene-propylene o-rings used in the 1153 A transmitters are 149 and 644 years for inside and outside containment, respectively. The limiting sub-component of the transmitter was found to be the epoxy glasa laminate circuit board. The conclusions of the EDS analysis are that incontain-ment transm i tters have a qualified life of 6.5 years, and those in the
RAB have a qualified life of 19.3 years. The.EDS analysis also recommends that these transmitters be replaced prior to the end of their qualified life and that they be periodically maintained using the manufacturer's procedure.
The recommended maintenance and surveillance program includes the following:
- 1) Calibration and maintanance procedures provided in the Rosemont Instruction Manual #4295.
- 2) The cover gaskets should be replaced each time the transmitter's cover is removed.
- 3) Should random transmitter failures occur, it is desirable to replace these transmitters with ones which have greater qualified life.
- 4) These transmitters will be replaced individually prior to the end of their qualified life.
LP&L concurs with the EDS conclusions and recommendations.
+
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Facility: WATERFORD SES UNIT NO. 3 Utility: LOUISI ANA POWER & LIGHT A'E: EBASCO SE RVICES NSSS: COMBUSTION ENG Capacity: 1165 MW(e) Type: PWR Page 1 of __3._
JUSTIFICATION FOR INTERIM OPERATION Purchase Order NY-403402 EQ Doc Pkg: 8.lW3 Major Supplier: Cmbustion Engineering Spec: 9270-ICE-0005 Manufacturer: PosetTount, Inc. Equip Type: Transmitters OU ALIFICATION STATUS:
Qualified - For Interim Operation TAGS MODEUSERIAL COMPONENT 0588 CAT SEE SEE SEE SEE ATTACHED ATTACHED ATTACHED ATTACHED SU8 JECT See Attached Letter W3P83-1853 For Interim Operation Justification l
I r
l Prepared By: @ h f/3 gy ReviewedBy:h ((3[83 LOUISIANA POWER & LIGHT CO*
JUSTIFICATION FOR INTERIM OPERATION Waterford Steam Electric Station
l Page 2 of 3 l
TAG MODEL COMPONENT 0588 CAT SERIAL LT-FW-1113A 1153DA4 Level XMTR A 177030R LT-FW-lll3B ll53DA4 Level XMTR A 177031R LT-FW-lll3C ll53DA4 Level XMTR' A
- 177033R LT-FW-1123A ll53DA4 ,
Level XMTR A 178486R LT-FW-ll23B ll53DA4 Level XMTR A 178487R LT-FW-1123C ll53DA4 Level XMTR A 178488R LT-FW-1123D 1153DA4 Level XMTR A 178489R PT-MS-1023A ll53GA9 ., Pressure XMTR A 167980R PT-MS-1023B ll53GA9 Pressure XMTR A 167981R PT-MS-1023C ll53GA9 Pressure XMTR A 167982R PT-MS-1023D ll53GA9 Pressure XMTR A 167983R PT-RC-0101A ll53GA9 Pressure XMTR A 105992 PT-RC-0101B 1153GA9 Pressure XMTR A 105993 PT-RC-0101C 1153GA9 Pressure XMTR A 105994 PT-RC-0101D 1153GA9 Pressure XMTR A 105995 PT-RC-0102A ll53GA9 Pressure XMTR A 137411R PT-RC-0102B 1153GA9 Pressure XMTR A l 137412R l
l PT-RC-0102C 1153GA9 Pressure.XMTR A 137413R PT-RC-0102D 1153GA9 Pressure XMTR A 137414R PT-RC-0103 ll53GA9 Pressure XMTR A 167984R
Page 3 of 3 TAG MODEL COMPONENT 0588 CAT.
SERIAL PT-RC-0105 ll53GA9 Pressure XTMR A 121826 t
LT-RC-0110X 1153HA5 Level XMTR A 167015R LT-RC-0110Y ll53HA5 Level XMTR A 167016R PT-MS-1013A ll53GA9 Pressure XMTR A 137415R PT-MS-1013B ll53GA9 Pressure XMTR A 137416R PT-MS-1013C 1153GA9 Pressure XMTR A 137417R PT-MS-1013D ll53GA9 Pressure XMTR A 137418R PT-SI-0311 ll53GA8 .. Pressure XMTR A 105971 PT-SI-0321 1153GA8 Pressure XMTR A 105972 PT-SI-0331 ll53GA8 Pressure XMTR A 105973 PT-SI-0341 ll53GA8 Pressure XMTR A 105974 LT-SI-0311 1153DAS Level XMTR A 106050 LT-SI-0321 ll53DAS Level XMTR A 106051 LT-SI-0331 1153DAS Level XMTR A 106052 LT-SI-0341- 1153DA5 Level XMTR A 106053 LT-FW-lll3D ll53DA4 Level XMTR A 177033R l
l l
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Fa:iiity: WATERFORD SES UNIT NO. 3 Utility: LOUISI ANA bon EP & LIGHT A E: EBASCO SERVICES NSSS- COMBUSTION ENG Ca:,acity: 1165 MW(e) Type: PWR Pa;e 1 of 5 JUSTIFICATION FOR INTERIM OPERATION Purchase Order NY-403502 EQ Doc Pkg: 8.lW3 Major Supplier: Not Applicable Spec: 100 1564.402 Manufacturer: Posemount, Inc. Equip Type: Transmitters OU ALIFIC ATION STATUS:
Qualified - For Interim Operation TAGS MODE L/SERI AL COMPONENT 0588 CAT SEE SEE SEE SEE ATTACHED ATTACHED ATTACHED ATTACHED SUBJECT See Attached letter W3P83-1853 for Interim Operation Justification l
Prepared By://y).M 'f/3/f 3 Reviewed By h. % h h d LOUISIANA POWER & LIGHT CO.
JUSTIFICATION FOR INTERIM OPERATION Waterford Steam Electric Station
Page 2 of 5 TAG MODEL COMPONENT 0588 CAT SERIAL FT-AC-5030AS ll53DA4 Flow A 171808R Transmitter FT-AC-5030BS ll53DA4 Flow A 171809R Transmitter FT-AC-5030CS ll53DA4 Flow A 171810R Transmitter PT-AC-5011AS ll53GA7 Pressure A 106104 Transmitter PT-AC-50llBS 1153GA7 Pressure A 121824 Transmitter PT-AC-5011CS 1153GA7 Pressure A 106106 Transmitter PT-AC-5020AS 1153GA7 Pressure A 106107 Transmitter PT-AC-5020BS 1153GA7 Pressure A 106108 ., Transmitter PT-AC-5020CS ll53GA7 Pressure A 106109 Transmitter PT-CA-670lSMA ll53AA6 Pressure A
- 185856R ~
Transmitter-PT-CA-670lSMB ll53AA6 Pressure A 185857R Transmitter PT-CA-670lSMC 1153AA6 Pressure A 185858R Transmitter PT-CA-670lSMD ll53AA6 Pressure A 185859R Transmitter PT-CA-6702SMA ll53AA6 Pressure A 185860R Transmitter PT-CA-6702SMB ll53AA6 Pressure A 123648 Transmitter PT-CA-6702SMC ll53AA6 Pressure A 123649 Transmitter PT-CA-6702SMD 1153AA6 Pressure A 123650 Transmitter PT-CA-6750AS 1153AA6 Pressure A 164118R Transmitter PT-CA-6750BS ll53AA6 Pressure- A 164117R Transmitter 1
Page 3 of 5 TAG MODEL COMFONENT 0588 CAT SERIAL FT-CC-5070AS 1153DA5 Flow A 106076 Transmitter FT-CC-5070BS 1153DA5 Flow A 106077 Transmitter FT-CC-5070CS 1153DAS Flow A 106078 Transmitter FT-CC-5570AS ll53DAS Flow A 106055 Transmitter FT-CC-5570BS ll53DA5 Flow A 106056 Transmitter FT-CC-7570Als ll53DAS Flow A 106062 Transmitter FT-CC-7570A2S ll53DAS Flow A 106063 Transmitter FT-CC-7570B1 1153DAS Flow A 106064 Transmitter FT-CC-7570B2 ll53DA5 Flow A 106065 Transmitter PT-CC-5060AS 1153GA7 Pressure A 106112 Transmitter PT-CC-5060BS 1153GA7 Pressure A 105961 Transmitter
.PT-CC-5060CS ll53GA7 Pressure A 121825 Transmitter PT-CC-5070AS ll53DA7 Pressure A 106097 Transmitter PT-CC-5070BS ll53DA7 Pressure A 106098 Transmitter PT-CC-5070CS ll53DA7 Pressure A 106099 Transmitter
. LT-CD-9013AS 1153DA5 Level -A 106030 Transmitter LT-CD-9013BS ll53DA5 Level A 106029 Transmitter PT-CS-7111AS 1153GA8 Pressure A 105975 Transmitter PT-CS-7111BS 1153GA8 Pressure A 105976 Transmitter
-FT-CS-7122AS ll53DAS Flow -A 106066 Transmitter
Page 4 of 5 TAG MODEL COMPONENT 0588 CAT SERIAL FT-CS-7122BS 1153DA5 Flow A 106067 Transmitter FT-FW-8330AS 1153DA5 Flow A 106068 Transmitter FT-FW-8330BS 1153DAS Flow A 106069 Transmitter PT-FW-8322AS ll53GA9 Pressure A 105909 Transmitter PT-FW-8322BS 1153GA9 Pressure A 105910 Transmitter PT-FW-8322S 1153GA9 Pressure A 105911 Transmitter DPT-HV-5051AS ll53DA3 Differential A 184706R Pressure Transmitter DPT-HV-5051BS 1153DA3 Differential A 211564 Pressure Transmitter DPT-HV-5054AS 1153DA3 Differential A 106033 Pressure Transmitter DPT-HV-5153AS ll53DA3 Differential A 161142 Pressure Transmitter DPT-HV-5153BS 1153DA3 Differential A 161143 Pressure Transmitter DPT-HV-5158AS 1153DA3 Differential A 161144 Pressure Transmitter DPT-HV-5158BS ll53DA3 Differential A 161145 Pressure Transmitter DPT-HV-5257AS 1153DA3 Differential A 164116R Pressure Transmitter DPT-HV-5257BS ll53DA3 Differential A 164115R Pressure Transmitter DPT-HV-5258AS 1153DA3 Differential A 240724 Pressure Transmitter PT-MS-8340S ll53GA Pressure A 105914 Transmitter i
PT-SI-0390AS 1153GA9 Pressure A 105917 Transmitter PT-SI-0390BS 1153GA9 Pressure. A 105918 Transmitter l
l Page 5 of 5 TAG MODEL COMPONENT 0588 CAT SERIAL.
a PT-MS-0303AS ll53GA9 Pressure A 105915 Transmitter
, PT-MS-0303B5 ll53GA9 Pressure A 108916 Transmitter FT-SI-0390AS ll53DA6 Flow A
-153836 Transmitter FT-SI-0390BS ll53DA6 Flow A
, 158837 Transmitter
. FT-MS-0300AS ll53DA5 Flow A 106070 Transmitter FT-MS-0300BS 1153DA5 Flow A 106071 Transmitter e'
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Attachment 3 i
F 6
