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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:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20153F6111988-01-21021 January 1988 FOIA Request for Documents Re Reported Leak from Commissioner T Roberts Ofc Concerning QA Problems at Facility ML20235J1851987-05-0101 May 1987 FOIA Request for Status Rept & Documents Re Ofc of Investigation Investigations Involving Plant ML20209G9751987-04-24024 April 1987 FOIA Request for Commissioner Tm Roberts Memo Sent to Util Re Flaws at Plant ML20238B4981986-12-12012 December 1986 FOIA Request for Ofc of Inspector & Auditor Rept on Region Iv.Author Currently Studying Facility ML20210U8441986-03-21021 March 1986 FOIA Request for All Completed Ofc of Investigations Repts. Re Facility ML20134L4791985-07-17017 July 1985 FOIA Request for Biographical Data on Region III Resident Inspector,H Livermore & SALPs for Listed Plants for Specified Time Frames ML20133F8991985-05-0101 May 1985 Appeals Denial of FOIA Request for List of All Ofc of Investigation Reviews & Repts of Investigations of Facility ML20116E8101985-04-26026 April 1985 Notifies That on 840418,util Filed Suppl to Response to ALAB-801 Which Included Two Large Repts.Joint Intervenors Believe Filing Unauthorized & Request Addl 2 Wks to Respond to Repts If Considered by Aslab ML20126D9131985-03-18018 March 1985 FOIA Request for List of All Ofc of Investigations Reviews, Repts or Investigations Re Facility ML20133K1961985-03-18018 March 1985 FOIA Request for Documents Re NRC 850315 Meeting Concerning Facility ML20126D9831985-03-18018 March 1985 FOIA Request for Documentation Generated by Ofc of Investigations Re Investigations or Reviews Concerning Facility ML20111C4671985-03-11011 March 1985 Provides Corrected Paragraph to Replace Jumbled Paragraph in Re Joint Intervenors 841107 Motion to Reopen ML20111B1211985-03-0808 March 1985 Discusses Extension of Time Until 850315 for Commission to Review ALAB-797 Re Joint Intervenors 841107 Motion to Reopen Hearings on QA Contentions.If Aslab Has Not Jurisdiction, Identical Motion Will Be Filed W/Commission ML20133B9001985-03-0101 March 1985 FOIA Request for Documents Re J Wells ML20127F7821985-02-19019 February 1985 FOIA Request for Three Categories of Documents Re Decision to Grant Low Power License to Facility ML20140G4681984-08-29029 August 1984 FOIA Request for All Documents Re Ofc of Investigations Investigation Concerning Falsification of Records & Harassment of Qa/Qc Personnel at Waterford Site ML20106C2411984-08-29029 August 1984 FOIA Request for Documents Re Ofc of Inspector & Auditor Investigation or Rept Re Facility ML20107J1201984-08-29029 August 1984 FOIA Request for Documents Between NRC & Util Re Ofc of Investigation Investigation of Activities at Facility ML20096A4131984-08-29029 August 1984 Requests Commission Act Immediately in Oversight of Ofc of Investigations,To Ensure No Further Disclosure of Info About Targets & Substance of Investigation to Util.Svc List Encl ML20107A6441984-08-16016 August 1984 FOIA Request for All Info,Comments &/Or Reviews Re Integrated Program Developed to Outline near-term OL Workload,Per EDO 840625 Memo to Chairman Palladino ML20132F2021984-08-0606 August 1984 Responds to Refusing to Process FOIA 84-206 Due to Lack of Specificity.Records Requested Documenting Problems W/Subcontractors Work & Corrective Actions Taken ML20137U3941984-07-25025 July 1984 Urges NRC to Reject Util 840628 Proposed Plan to Correct Problems Found by NRC Special Review Team.Independent Third Party to Conduct Review of Problems Outlined in NRC & Development of Plan to Resolve Issues Requested ML20126D2711984-07-20020 July 1984 Appeals Denial of FOIA Request for Documents Re Const Assessment Team Insp of Facility ML20128L7001984-07-20020 July 1984 Appeals Lack of Response to FOIA Request for Documents Re Util Jan 1984 Memo Discussing Worker Concerns at Facility ML20126L5781984-07-20020 July 1984 Appeals Denial of FOIA Request for Documents Re 840608 Public Meeting in Bethesda,Md Re Facility ML20090H7851984-07-13013 July 1984 Requests Extension of Deadline for Responding to Util to NRC on Behalf of Citizens for Safe Energy ML20128G3621984-07-0606 July 1984 Appeals Lack of Response to FOIA Request for Info Re Basemat Cracking,Water Leakage & Seepage Problems ML20126L5711984-06-15015 June 1984 FOIA Request for NRC Records on 840608 Public Meeting in Bethesda,Md Re Facility ML20125C1711984-06-15015 June 1984 FOIA Request for Records Relevant to &/Or Generated in Connection W/Jan 1984 Memo Issued by Louisiana Power & Light Co Concerning Interviews,Surveys & Exit Interviews to Document Worker Concerns ML20127F2631984-06-15015 June 1984 FOIA Request for Records & Info,Including But Not Limited to Notes,Ltrs,Memos & Minutes Re NRC Preceding Sser, Concerning Problems at Plant ML20112J5071984-06-13013 June 1984 FOIA Request for All Records from State of La Congressional Delegation on Waterford 3 ML20114A6681984-05-31031 May 1984 FOIA Request for All Documentation Re Formation of Waterford 3 & Comanche Peak Task Forces ML20114A4321984-05-31031 May 1984 FOIA Request for Documents Re Review of Util Proposed Fuel Loading ML20105D2861984-05-31031 May 1984 FOIA Request for All Agency Records Relevant to &/Or Generated in Connection W/All Draft Ssers for Facility, Including All Proposals Made by Team Members for Inclusion in Rept ML20107H3871984-05-31031 May 1984 FOIA Request for All Records Relevant to or Generated in Connection W/Any Rept or Study of Basemat Cracking & Water Leakage & Seepage Problems at Facility Conducted or Issued Subsequent to Formation of Special Investigation Team ML20126D3461984-05-23023 May 1984 FOIA Request for All Documentation Re Creation & Issuance of Sser,Including All Submittals by Members of Special Insp Team & Input from Oeld & IE ML20127C2221984-05-14014 May 1984 Discusses Availability of Info on Shear That Is Applicable to Facility Basemat.No Excuse Found for Departing Radically from Code Provisions,But Advantage Should Be Taken of Provisions in Code Allowing Increase in Shear Strength ML20105C4521984-04-17017 April 1984 FOIA Request for Transcript of 840326 Meeting in Bethesda,Md Re Basemat Adequacy at Facility & All Related Memos,Working Papers & Correspondence from 840325 to Present ML20127E0521984-04-17017 April 1984 FOIA Request for All Documentation Requested & Produced by Ofc of Investigation in Review of QA at Facility ML20084R6591984-03-26026 March 1984 FOIA Request for Records Relevant to or Generated in Connection W/Meetings or Conversations Between D Eisenhut & Utils in Feb or Mar 1984 ML20105C5571984-03-21021 March 1984 FOIA Request for All Documents Connected W/Const Assessment Team Insp That Began in Feb 1984 ML20112E2921984-03-21021 March 1984 FOIA Request for All Records Re NRC Monitoring & Oversight of Eight Specified Contractors & All Records Re Problems, Deficiencies or Flaws Found in Specified Firms ML20084S0641984-03-21021 March 1984 FOIA Request for Records Generated in Connection w/840201 Meeting Between NRC & Util Re Facility ML20087A5281984-02-29029 February 1984 Requests G Hill 840110-11 Statement Re QA Deficiencies Be Forwarded to G Groesch & Author ML20086N9621983-10-24024 October 1983 FOIA Request for Documents Re 830714 Inquiry Team Rept on Facility QA Allegations & Insp & Util Response to Rept ML20082R0761983-05-31031 May 1983 Forwards Documentation Re QA Problems at Facility.Discovery of Most Recent Cracks in Foundation Indicates Seriousness of Problem ML20076M0661983-05-0404 May 1983 FOIA Request for SALP Documents,Written or Routed Since 1979,which Mention or Refer to Facility & Describe or Provide Info on SALP Insp Findings or Conclusions Based on SALP Reviews ML20081M0011983-05-0404 May 1983 FOIA Request for Documents Re IE Insp Rept 50-382/82-14 & Initially Proposed Penalty to Be Levied Against Util ML20081B9851983-03-31031 March 1983 FOIA Request for Documents Re Const & Operation of C-E Plants.List of Info Required Submitted ML20083N0531983-01-26026 January 1983 Forwards El Duncan Affidavit Re Emergency Info Brochure, Inadvertently Omitted from Duplessis & Hunter Affidavits 1988-01-21
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ROBERT E. PHILLEO. P.E. i CONSULTING ENGINEER
, 7410 ANNANWOOO COURT ANNANDALE. VIRG!NIA 22003 May 14,1984 s
i Mr. Lawrence C. Shao Deputy Director Division of Engineering Technology U.S. Ituclear Regulatory Commission Washin'gton, D. C. 20555 .
Dear Larry:
I have looked at what is available on shear that is applicable to' the Waterford basemat. I also talked to Dick White. He was of the opinion that his work on in-plane membrane shear stresses was not particularly applicable to the case in hand. We also agreed that there ,
is not much work that is specifically applicable to a 12-ft thick mat on' the ground.
I'erguson's work, cited in the ACI-ASE cor. ittee 426 report ead reproduced on the attached sheet, shows that for steel percentages'of 1 and above the data for shear strength, with one exception, were in the range of 2.1 to 2.5 % . Of perhaps greater interest is the fact that' Section 11.3.2.1 of the 1983 ACI Code allows shear stress in the concrete as high as 3.5 (Fc when the ratio of bending morent to shear at the critical cross-section is low.
The two papers distributed by Ma bear some consideration. The paper by Kani is discussed in the cotnmittee r9 port. The report tends to disregard its implicat. ions and to base -its conclusions relevant to deep beams on the depth .idth ratio rather 'han on the absolute depth. Kcni did perform one test which purported to show that it was depth, per se, which nattered. Ferguson makes two points. The first has to do with the ,
reduction in shear resistance . Sear points of inflection and apparently is not relevant to the present case. The second has to do with a reduction in strength when small percentages of high-strength steel are used. It may be worth examining. ,
In summary, I can find no 4xcuse for departing radically frcct code g provisions, but every advantage should be taken of special provisions in the code which allow an increaia in shear strength under certain 7 circunstances. ,
FREEDOR dF lbFORM ATiON Sincerely, .
ACTREQUES(
Robert E, Pt.111eo, St-4rr 62 1 850222 GARDE 84-455 PDR Consulting Engineer Ch%
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Comments on Chen Report pin The facts concerning soil support,' ground water level, and construction procedures are apparently correct, although I cannot verify them in detail from my own knowledge.
The major a;onclusion that cracks in the foundation mat "have been caused or further aggravated by differential settlement" is probably correct, but it gives no indication as'to the magnitude of the effect. While there were differences in the support offered by different parts of the foundation, a 12-foot deep besa could bridge over substantial regions with no support at all with only a minor effect or stresses. The most significant effect of foundation compressibility is the overall curvature in the north-south direction which produced a concave-downward final configuration of the sat with a maximum deflection in the middle strip of 2.5 inches. This shape was the natural result of placing the middle strip first and working toward the outside. The middle strip started to compress the foundation early and had nearly stabilized when the outer blocks were placed. The latter continued to settle with respe:t to the middle strip. Such a curvature would produce an average st ain of 70 x 10-6 in.the outer fiber of a 12-foot thick section. In the concave downward position this strain would be tensile in the top surface and compressive in the bottom surface. While this strain is not sufficient to crack the concrete, it would " aggravate" cracking from other causes. It would explain why cracking occurs preferentially in the east-west direction and'it would predict more cracking on the top surface than'on the bottom. The basic cause of the cracking is not dealt with except for a single reference to " thermal or shrinkage" on page 8.
I see no justification for the recommendation that a precisa measuring program for differential settlements be undertaken. The existing program is sufficient to demonstrate that the sat is stable. The precision of the existing system is adequate to~ demonstrate that stress in the concrete is not changing appreciably.
F Robert E. Philleo FREEDOW OF INFORMATION ACI REQUEST 9 '+- 455*
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Comments on Ma Report The reasoning in the report proceeds correctly from the assumption that there are very large discontinuities between adjacent blocks as a result of differential settlement, but this assumption requires examination. It is apparently based on the observation on Page 4, line 2 that "each newly poured block experienced an immediate settlement of about 3/4 of an inch while the existing blocks adjacent to it settled to a much lesser extent." There obviously is not a 3/4 inch discontinuty at the interface between two blocks because the top surface is continuous across the joint without offset and the steel crossing the joint would prevent any appreciable relative movement. The settlement readings I am familiar with were taken at the center of each block. The center to center distance between blocks is about 75 feet. A relative vertical displacement of 3/4 inch between the center of two adjacent 12-foot thick blocks could be accommodated in pure bending with negligible shear and an outer fiber strain of about 150 x 10 6 This calculation assumes no rotation by the existing slab, the worst condition. Any rotation or settlement by the existing block would reduce the strain below the calculated value. The value of 150 x 10 -61s approximately the value required to crack the concrete.
The above effect produces a concave downward shape. The final shape is also ~
concave downward with'a strain of about 70 x 10-6 If the above stresses did exist they were relieved as the sat achieved its final shape. In all cases the shape is such so as to produce tension in the top of the mat and compression in the bottom. Thus, it is difficult to understand the explanation of through cracks, as noted at the bottom of page 4, which postulates flexural cracks in the bottom of the mat. Flexural cracks should only exist in the top.
If cracking is to be attributed only to loads resulting from non-uniform foundation conditions, it is difficult to rationalize shear cracks in the ;
central portion of the mat. This should be in an area of low shear stress.
I do not think non-destructive testing should be undertaken until a stronger hypothesis can be established for shear cracking.
FRE2DOnt OF fMFORMATf0N AGE MQUESl i Robert E. Philleo p gy C-flS l
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Temperature Cracking in Basemat The basemat concrete contained 517 lb of cement per cubic yard. Assuming a heat of hydration of 126 BTU per pound during the period in which temperature is rising and a specific heat for the concrete of 0.2, the maximum temperature rise is:
AT= 517 x 126 = 81*F 0.2 x 4.00 , . -
Assuming a coefficient of thermal expansion of 6 x 10 -6 for the strain to be accommodated is b = 81 x 6 x 10 6 = 486 x 10 6 Because of the low modulus of elasticity and high creep capacity during its early life the concrete may be assumed to reach its peak termperature in a nearly stress-free condition. During the period of temperature drop tensile stress will develop, but this stress will also' be minimized by fairly high creep.
A reasonable assumption is an effective modulus of elasticity of 1.5 x 10 6 psi (which takes into account the effect of creep),a tensile strength of 400 psi, and a temperature drop to final stable temperature equal to the original temperature rise.
The strain which can be accommodated by the concrete is E " 400 1.5 x 10 6 = 267 x 10-6 Since the potential strain to be accommodated is 486 x 10 -6, cracking will begin when a little more than half the cooling has occurred, and ultimately a strain Of FREEL/CM OF INFGet. .. , yN 486 x 104 - 267 x 10-6 = 221 x 10-6 ACT REQUEST Swsr c [7su
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will be accommodated by cracking. In in unreinforced mat this would produce a 0.01 inch crack every
.01 = 45 inches 221 x 10 -6 in random directions. Each 1% of reinforcing steel will reduce the crack width by about 20% and will hold the structure tightTy together.
It should be noted that these strains must be added to any others present in the basemat. Outer' fiber strains a,ttributable to non-uniform foundation compressibility may be estimated at ' values from 70 to 150 x 10-6, depending on the assumptions made. Adding these strains to thermal strains would increase cracking potential somewhat in the top of the mat and cause cracking to occur preferentially in the East-West direction. It would
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greatly reduce cracking Jn the,Kott'om of 'the mat. ~
In addition to these major cracks which occur as the mass cools slowly to its final temperature, there are cracks which occur early and result from e
non-linear temperature gradients when the concrete cools at the surface while it is still subjected to temperature rise in the interior. These are shallow and are the cracks which were discovered on vertical surfaces when forms were stripped.
Robert E. Philleo FREEbuM ur IN r u n M.s iois AGI REQUEST T+-V rs' C-/ ~7 72 -
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b Caution Notice This standard is being pre.
2 pared or reviewed and has not been approved 3 by The American National Standards Institute.
4 It is subject to revision or withdrawal before 5 issue.
6 7 REQUIREMENTS FOR AUDITING
^
8 OF QUALITY ASSURANCE PROGRAMS .
9 FOR NUCLEAR POWER PLANTS 10 .
11 1. INTRODUCTION
- . , _ : ;. 2 12 1.1 Sco pe. This standard provides requirements and guidance for estab-13 11shing and implementing a system of internal and external audits of 14 quality assurance programs for nuclear power plants, including the i
15 preparation, performince, reporting, and followup of audits. of. quality.
16 assurance. programs .fo r.nuclea s. power . plants The activities.covesed.
17 by this standard include deelgaing, pn.rchas.Ing,. fabricating handling,
.-.. ..' , 18 shipplag .stosing, cleaatag,-exacting,. Lnstalling,. Inspecting., . tasting.,
(# 19 maintaining, .respaising, and.modliying of.Nucleas Power. 21 ants.
20 21 This star.dard amplifies the audit requirements of American -
22 , National Standard N45. 2 and shall be used in conjunction with that stand-23 ard. -
24 -
25 1. 2 Applicability. The requirements of this standard apply to both internal 26 and external audits performed by or for the plant owner, contractors, and 27 other organizations participating in activities affecting the quality of i 28 structures, systems, and components of nuclear power plants which are 29 s ec ecordance with requirments of ANSI N45,213ht rffer -c -
30 sta dard is not applicable to survelliance or inspections for the purpose e
, , 31 of process control or product acceptance.
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Draft 3. Rev. 4
((j 1- Februa ry 22, 1974
, FREEDOM OF INFORMATION
, ACT REQUEST ,
. ..C j!783
1 Intarnal Audits Audits of thcoa.portiens' of an organt' zation's Qua1Lty 2 Assurance quality assurance program retained under its direct control .,
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3 and within its organizational structure.
4 5 External Audits . Audits of those portions of an organization's Qua1Lty 6 Assurance quality assurance program not retained under its direct control 7 and not within its organizational structure.
8 9 Other terms and their definitions are contained in ANSI N45.2.10 10 NOTE: N45.2.12 Work Group has petitioned N45. 2.10 Work Group to 11 change the definitions as indicated above.
12 -
13 1.5 Referenced Documents. Documents that are required to be included as a 14 part of this' standard are identified at the point of reference and described 15 in Section 6 of this standard. The issue or edition of the referenced docu.
16 ment that is require ( will be specified either at the point of reference or in 17 Section 6 of this standard unless otherwise specified in the contract document.
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\"J 19 2. PERSONNEL
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20 .
21 2.1 General. The responsible auditing organization shall select and assign 22 qualified auditors who are independent of 'any direct responsibility for per.
23 formance of the activities which they will audit.
24 In the case of internal audits, the persons having direct responsibility for 25 performance of the activities being audited shall not be involved in the 26 selection of the audit team. j 27 I 28 2. 2 Personne1 Qualification. The responsible auditing organization shall establish 29 the audit personnel qualifications and the requirements for the use of technt.
30 cal specialists to accompitsh the auditing of the Quality Assu.rance quality 31 sssurance programs. Personnel shall be selected for Quality. A -----
32 quality assurance auditing assignments based on experience or training which 33 establish that their qualifications are commensurate with the complexity or s
.P 11 raft 3. Rev, 4 FREEDOM OF If60RMATION ACT REQUEST S Y -4sf c./7:3 . . .. . . . .
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I 2.4.2 Review and study of codes, standards, procedures. Instructions, 2 and other documents related to Quall.ty Assu.rance quality assurance
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.3 programs and program auditing.
4 5 , 2.4.3 Participation in training or orientation programs as described in Section 2. 3.
6 7 -
8 3. AUDIT SYSTEM 9 3.1 General. This section establishes requirements for a comprehensive audit
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10 system which shall be planned, documented,' and implemented to verify _ k 11 compliance with the elements of a quality assurance program. The audit 12 system shall be described in approved, written policies, plans, procedures, 13 instructions, or such other documents as appropriate.
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14 The. objectives of the audit system pe, storming. audits.et the. quality assusance.psogr.am are:
15 16 3.1.1' To determine that a quality assurance program has been developed 17 and documented in accordance with specified requirements; y,18 \ 3.1.2 To verify by examination and evaluation of objective evidence that
19 the' documented program has been implemented:
20 3.1. 3 To assess the effectiveness of the quality assurance program:_
21 3.1. 4 To identify program nonconformances; and 22 3.1. 5 To verify correction of identified nonconformances.
23 W _
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'24 3.2 Essential Elements of the Audit System. An effective audit system shall be 25 established and maintained and shall include the following essential elements:
26 3. 2.1 ~ A management policy statement or procedure which establishes 27 organizational Independence and authority and commits the organt.
28 sation to an audit system meeting the requirements of this standard.
. 29 3.2.2 Manpower, funding, and facilities to implement the audit system 30 os audits ,
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.q.',. Draft 3 Rev. 4
(:/ .5- . r-kruary 22, 1974 i
FREEDOM OF INFORM T10N "
ACT REQUEST
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$ 4-4-s r cf733
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1 3.4.2 Audits shall be regularly scheduled on the basis of the l 2 status and importance of the activities to assure the ade- !
"' ? quacy of, and conformance with, the program. Applicable
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4 elements of the QualLty Assurar.ca. quality assurance prograrn 5 shall be audited at least annually or at least once within the 6 life of the activity, whichever is shorter.
7 3.4.3 Regularly scheduled audits should e supplemented by audits 8
ss -
t conducted of one or more of t e following conditions: ;
9 3.4. 3.1 When it is neces sary to determine the capability 10 of a contractor's Quality Assuzance quality assur.
11 ance program prior to awarding of a contract or 12 purchase order.
13 3. 4. 3. 2 When, after award of a contract, sufficient time has 14 elapsed for implementing the Quall.ty Assurar.ca 15 quality assurance program and It is appropriate to 16 determine that the organization is adequately per.
17 forming the functions as defined in the Qua1Lty Assur.
y ,. . . 3 W 18 ' ance quality assurance program description, codes, 19 standards, and other contract documents.
20 3.4. 3.3 When significant changes are made in functional 21 areas of the Quality.# --"- u+ quality assurance 22 prograrn such as significant reorganization or pro-23 cedure revisions.
24 3.4. 3. 4 When it is sus pected that the quality of the item is 25 in jeopardy due to nonconformances In the Quality 26 Assurance quality assurance program.
l 27 3.4. 3.5 When a systematic, independent assessment of 28 -
program effectiveness is considered necessary.
29 3. 4. 3. 6 When it is necessary to verify implementation of
- 30 required corrective actions.
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7 FREEDOM OF INFORMATION ACI REQUEST T4 -4 ff C-[783 .. ..
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1-4.2.4 Audit Notification. Involvad organizations shall be notified of a ,
2
. t scheduled audit a reasonable time before the audit is to be performed. i
)D This notification should be in writing and include g-~1 such infor.
- 4 mation on as the scope and schedule 'of the audit vwie of. meetings 5
and. method.of audit. and the name of the audit team leader. Un.
6.
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announced audits may be performed with prior agreement of the 7 parties involved.
8 9 4. 3 Performanca..
10 4.3.1 Pre audit Conference. A brief pre-audit conference shall be con.
11 ducted at the audit site with cognizant organization management. The 1
12 purpose of the conference shall be to confirm the audit scope, present I
13 the audit plan, introduce auditors, meet counterparts, discuss audit i
- 14 sequence and plans for the post-audit conference, and establish I
.15 channels of communication. .
16 ~
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17 4.3.2 Audit Process.
,.,., 18 4.3.2.1 Checklist procedures shall be used to ensure depth and
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&. continuity of audits. The audit checklist is intended for use 7 '20 as a guide and should not restrict the audit investigation 21 when findings raise further questions that are not specifi-22 cally in'cluded in the checklist.
23 4.3.2.2 Objective evidence shall be examined for compliance with 24 quality assurance program requirements.
25 4.3.2.3 Selected elements of the quality assurance program shall' 26 be audited to the depth necessary to determine whether or 27 not they are being implemented effectively.
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28 4.3.2.4 When a nonconformance is Mentified as a result of an audit.
29 further investigation shall be condpcted by the audited 30 organization in an effort to identify the cause and effect of 31 the nonconformance and to determine the extent of the 32 corrective action required.
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- i" Draft 3 Rev. 4 A pMdtgju OF INfGW Al"Ji.
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, . . . . 'a I thirty days after the audit.
2 .
3 4. 5 Followup.
4 4.5.1 By Audited Organization. Management of the audited organization 5 or activity shall review and investigate the. any adverse audit 6
findings to determine and schedule appropriate corrective action 7
including action to prevent recurrence and shall respond to the 8
. report in writing within thirty days after receipt, giving results '
9 of the review and investigation. The response shall clearly state 10 the corrective action taken to prevent recurrence. In the event that 11 corrective action cannot be completed within thirty days, the audited 12 organization reply shall include a scheduled date for the corrective 4
13 action. The audited organization shall provide a followup report 14 stating the corrective action taken and the date corrective action 15 was completed. They shall also take appropriate action to assure 16 that corrective action is accomplished as scheduled-
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,.p 4.5.2 By Auditing Organization. Followup action shall be performed by the QB audit team leader or management of the auditing organization to:
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19 4.5.2.1 Asswe tha.t. Obtain the written reply to the audit report. :
20 la.. received
- 21 4.5.2.2 Evaluate the adequacy of the response.
22 4.5.2.3 Assure that corrective action is identified and scheduled 23 for each nonconformance. '
24 4.5.2.4 Confirm that corrective action is accomplished.as 25 '
s cheduled.
26 Followup action may be accomplished through written communicangn,_
, 27 reaudit, or other appropriate means.
g -A 29 5. RECORDS 3 30 5.1 General. Records shall be retained by the auditing organizations responsible 31 for activities associated with Impicmentation of this standard. The,se records 32 shall be collected, stored, and maintained in accordance with American
]3 National Standard N45. 2. 9.
PhEEDOM OF INFORMAtlON r .
ACi REQUEST W -tLf!"
c ['133 l'
_ _ - . , , ,_..___my. ,.-._,-..-.,.,.--,&, , . , ,,,- - . ,_sm,
pate: Oc t obe r 30, 1980 Address Writer care of:
United Engineers & Constivet ors lec.
To: William C. Black 30 South 17th Street Chairman - Working Croup philadelphia, Tenna. 19101 -
Phone No. (215) 422-3934
Committee: 359 Technical Committee on Concrete Pressure Components for Nuclear Service ^* * **""#
Working Croup on Reinforcing and Prestressing Systems
Subject:
Testing Frequency of Rebar Splices The 1980 edition of the code, Article CC-4000, sub-subparagraph CC-4333.5.2 and CC-4333.5.3 define the splice samples and the frequency of samples to be taken for tensile testing. If more than one splicing crew is,sorking on the job, it is possib.le, that always the same splicing crew's work will be sampled and the other crew's work'is not sam' pled, because of lack of instruction in the code.
I propose to submit a code change by the working group to assure the even sampling of each splicing crew by code requirement. .
The sub-subparagraph CC-4333.5.2 should read:
a CC-4333.5.2 Splice Samples. Samples shall be taken randomly representing all
. 5plicing crew's work. Splice samples may be production splices (cut directly from in-pl.=ce reinforcement) or sister splices (removable splices made in place next to production sp.lices and under the same conditions), in accordance with the schedule established in CC-4333.5.3.
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. FREEDOM OF INFORMAll0N ACI REQUEST 34-VTf c.,hst
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. .:L & <. I . L
ACI-ASME WORKING GROUP ON REINFORCING AND.PRESTRESSING SYSTEMS Meeting in New York City. ' June 17. 1981 ,
Meeting was called to order at 8':30 AM. Attached is the record of attendance. The agenda sent to members under letter of June 3rd was used and the following actions taken: ,
JC 9-40 (MCE 79-7) -
CC 3000/4000 Rebar Tolerances.
This item had previously been approved by the Working Group with changes as covered in letter of December 2,1980. Black to Allen. No further action required by Working Group.
JC 9-75 (MCE 78-48) -
CB/CC 2442.3.2 Corrosion Preventive Coatings.
This item previously approved by Working Group. Had been rejected by ACI Standards Board and returned to ACI-TAC. Will be acted on by TAC shortly. No further action required by Working Group.
JC 0-20 (MCE 80-16) - CB/CC 4432.5 Twisting and Coiling Tendons.
-This item previously passed by Working Group. No further action required by Working Group.
JC 0-64 (MCE 80-41) -
CB/CC 4323 and CB/CC 5340 Rebar Bending and Examina-tion of Bends.
This item had previously passed Working Group.
Discussion at this meeting resulted in recomendation for editorial " improvement." vis; CB-5340 proposed revision, last line, change "of" to "for".
MCE 80-25 -
General Requirements for Materials.
No action required by Working Group.
MCE 80-53 -
CC-4333.5.2 Splice Sample Frequency. ,
The Working Group reviewed this internal proposal and detemined that currently the Code requires 100%
visual inspection, all splicers prequalified.
< specified number of splices tested. The NRC Regulatory
< Guide specifies splicing crew as a variable. After much discussion a motion was made by Moore, seconded by Barry that proposal to revise Code be rejected.
The vote was 6 yes. O no. 10 members. It was subse-quently commented that requirements for crew identifica-
- ' tion can be handled on a job basis.
FREEDOW OF INFORMATlON -
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COMMITTEE CORRESPONDENCE SOCIETY / COMMITTEE: ADDRESS CORRESPONDENCE TO:
ASME/ACI-359 R. E. Lipinski Structural Engineering Branch P-1022
SUBJECT:
U.S. NUCLEAR REGULATORY COMMISSION Reinforcing Steel Splice Sampling WASHINGTON, D.C. 20555 ,
MCE 80-53 A EN ^
NO. DA'TE: 00T19iM TO: James Allen, Chairman Joint Committee ASME/ACI-359
Dear Mr. Allen:
I am sending this letter to you in view of Bill Black's resignation from his Chainnanship of the WG on Reinforcing and Prestressing Systems. I wish to comment on the decision of the Working Group regarding Item MCE 80-53, CC-4333.5.2, Splice Sample Frecuency, which was voted upon during the meeting in New York City on June 17, 1981. The issue was brought up by A. Valentenyi through his letter to W. Black dated October 30, 1980 in which he proposed a code change to assure the even sampling of each splicing crew.
The minutes to the meeting indicate that the proposal to revise the code was rejected.
It is my opinion that the recomendation of Mr. Valentenyi would contribute to improvement of quality control in concrete construction of safety related structures without undue hardship to meet the requirements of the code. The reasons for this are as follows:
- 1. A " splicing crew" is usually comprised of a certified operator (cadwelder) and one or two iron worker helpers to assist in preparation for splicing (i .e. , cleaning, lifting, etc.). The individual operator provides direct supervision of each step in the splicing process and is assigned a unique identification symbol which is applied to the completed splice for traceability during inspection and testing. The entire splicing crew need not be identified, only the qualified splice operator.
- 2. I recommend that the intended sample frequency include the operator variable since reinforcing steel splicing (cadwelding) is highly operator dependent and should include test samples for each operator in order to identify substandard operator performance.
FREEDOW OF MRMATON ACT REQUEST S4-Mr me ,o /
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James Allen, Chairman 3. Although I can appreciate the WG's concern with regard to accounting problems, it is my understanding that in the past compliance with the sampling requirements of Regulatory Guide 1.10 and ANSI N45.2.5 (1974) which required separate test cycles for mechanical splices based on position, bar size for each splicing crew did not present undue difficulties.
I hope that the above will be taken into consideration by the WG at the next meeting and that the vote will be reversed.
Sincerely, L a s.tAf +'
Romuald E. Lipinski, Member Working Group on Reinforcing and Prestressing Systems cc: R. Vollmer W. Morrison J. Knight
. F. Schauer
- G. Arndt R. Shewmaker R. Rohrbacker F. Rinaldi FREEDOM OF INFORMAIl0N -
ACT REQUESI 84 -WC c/786 L
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