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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:NRC TO ENGINEERING/CONSTRUCTION/CONSULTING FIRM
MONTHYEARML20207E0771988-07-21021 July 1988 Final Response to FOIA Request for Documents Re Total Insp Hours & Total Number of Violations for Region IV Plants for CY87.Forwards App a Document.App a Document Also Available in PDR ML20147G8591988-03-0404 March 1988 Partial Response to FOIA Request for Documents Re Regional Evaluation of Plant.Forwards App B Documents.App a & B Documents Available in PDR ML20236G9031987-11-0202 November 1987 Partial Response to FOIA Request.Forwards Documents Listed in App A.Documents Also Available in PDR ML20237J5101987-08-14014 August 1987 Partial Response to FOIA Request.App a Documents Re EA-86-09 for Comanche Peak Electric Station Available in Pdr.App B Documents Encl & Available in PDR ML20211Q4011986-07-22022 July 1986 Advises That 841024 Verification of Cecor Coefficient Methodology for Application to PWRs of Middle South Utils Sys Will Be Withheld (Ref 10CFR2.790),per 840731 Request ML20235P2901985-06-11011 June 1985 Responds to Re Rejection of Transcript of in Camera Plant Proceeding Due to Matrix Plan Not Being in Compliance W/Terms of Section C.3.3.6.a of Contract NRC-17-85-394 ML20235P2061985-06-0404 June 1985 Informs That Per 850604 Telcon,Encl 850530 Transcript in Plant in Camera Proceeding Has Been Rejected.Matrix Type Used by Company Not in Compliance w/RS-SEC-85-394, Pages 7 & 8 & Unacceptable by Licensing Boards.W/O Encls ML20127G4611984-09-13013 September 1984 Requests Eg&G to Develop Sampling Plan for NRC to Followup on QC Inspector Qualification Issues.Requests That D Ross Chair Effort & Ensure Development of Sound Plan in Time for 841001 Effort ML20127C6251984-07-0202 July 1984 Replies to Re Licensing of Plant.Nrc Actions to Assure Protection of Public Health & Safety Listed. Rept of President Commission on Accident at TMI Encl. W/O Encl 1988-07-21
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 ML20196E6931999-06-22022 June 1999 Forwards Corrected Ltr Re Changes to Rev 19 to Emergency Plan.Original Ltr Had Error in Subject Line ML20196E0831999-06-21021 June 1999 Forwards Insp Rept 50-382/99-12 on 990524-27.No Violations Noted.Purpose of Insp Was to Conduct Assessment of Emergency Preparedness Program ML20196D9941999-06-18018 June 1999 Forwards Insp Rept 50-382/99-11 on 990524-28.No Violations Noted ML20195J8091999-06-17017 June 1999 Forwards Safety Evaulation Re First 10-yr Interval Inservice Insp Relief Request for Plant,Unit 3 ML20196C8711999-06-15015 June 1999 Discusses Insp Rept 50-382/99-08 & Forwards Notice of Violation Re Unescorted Access Which Was Mistakenly Granted to Individual Whose Background Investigation Indicated That He Had Failed Prior Drug Screening with Another Employer ML20196F3721999-06-0909 June 1999 Corrected Ltr Forwarding Rev 19 to Emergency Plan ML20195G3711999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981223,which Transmitted Waterford 3 Steam Electric Station Emergency Plan,Rev 24,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20207E8541999-06-0303 June 1999 Forwards SE Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressurizer Safety Valves at Plant,Unit 3 ML20207G3441999-06-0303 June 1999 Forwards Insp Rept 50-382/99-09 on 990411-0522 & Notice of Violation.One Violation Identified & Being Treated as Noncited Violation C ML20207D3771999-05-27027 May 1999 Ack Receipt of 990401 & 0504 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-01 on 990303 ML20207A5121999-05-24024 May 1999 Refers to Which Responded to NOV & Proposed Imposition of Civil Penalty Sent by .Violations A,B & E Withdrawn & Violations C & D Changed to Severity Level IV ML20206U7851999-05-18018 May 1999 Forwards Insp Rept 50-382/99-06 on 990405-09.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML20206N6961999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S4411999-05-10010 May 1999 Forwards Insp Rept 50-382/99-05 on 990228-0410.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3841999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamental Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam,With Answer Key,Encl for Info.Without Encl ML20206K0951999-05-0606 May 1999 Discusses Insp Rept 50-382/99-08 Issued 990503 Without Cover Ltr Documenting EA Number & Subject Line Indicated NOV Which Was Incorrect.Corrected Cover Ltr Encl ML20206F4701999-05-0303 May 1999 Forwards Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Re Failure to Review & Consider Derogatory Access Authorization Background Info as Required by PSP Identified & Being Considered for Escalated Enforcement Action ML20206K1211999-05-0303 May 1999 Corrected Cover Ltr Forwarding Insp Rept 50-382/99-08 on 990405-07.One Violations Noted & Being Considered for Escalated EA ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M0561999-04-0909 April 1999 Forwards Insp Rept 50-382/99-04 on 990301-19.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20205J8781999-04-0505 April 1999 Forwards Insp Rept 50-382/99-02 on 990117-0227.No Violations Noted.Inspectors Determined That Six Violations Occurred & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20205J0901999-04-0202 April 1999 Informs That Info Submitted by & 970313 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) ML20205A4681999-03-26026 March 1999 Forwards Insp Rept 50-382/99-03 on 990308-12.Two Violations of Radiation Protection Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205A6141999-03-25025 March 1999 Forwards SE Accepting Request to Use Mechanical Nozzle Seal Assemblies (Mnsas) as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Application at Plant,Unit 3 ML20205F3311999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Plant,Unit 3 PPR Review,Which Was Completed on 990211.Performance at Plant,Unit 3 Was Acceptable ML20204E4941999-03-17017 March 1999 Discusses TSs Bases Change Re 3/4.4.1,3/4.6.1.7,3/4.6.3, 3/4.7.12 & 3/4.8.4.Forwards Affected Bases Pp B 3/4 4-1, B 3/4 6-3,B 3/4 6-4,B 3/4 7-7 & B 3/4 8-3 ML20207F1251999-03-0303 March 1999 Forwards Insp Rept 50-382/99-01 on 990125-29 & 0208-12 & Notice of Violations ML20203H8501999-02-17017 February 1999 Forwards SE Accepting Licensee 970701 Submittal of Second Ten Year ISI Program & Associated Relief Request for Plant, Unit 3.Nine Relief Requests Had Been Authorized Previously & Proposed Alternatives Remain Authorized ML20203D7211999-02-11011 February 1999 Forwards Request for Addl Info Re Licensee 970317 & 990111 Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Response Should Be Provided within 60 Days 1999-09-09
[Table view] |
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ATTACHMENT 3 0 f800, UNITED STATES
- g NUCLEAR REGULATORY COMMISSION
3 j 799 ROOSEVELT ROAO
- GLEN ELLYN, ILLINOl5 601 M of September 13, 1984
$' MEMORANDUM FOR: Larry Kobichek, EG&G FROM: J. J. Harrison, USNRC - Waterford TASK Force
SUBJECT:
SAMPLING PLAN FOR WATERFORD TASK FORCE This letter is to document my request for EG&G to develop a sampling plan for the NRC to use at Waterford to follow up on the QC Inspector qualification issues. As we discussed on our telephone call, on September 13, 1984, I am requesting that Dave Ross be allowed to chair this effort and ensure
- - - development of sound plan in time for my review and NRC to use during our Waterford effort beginning on October 1, 1984. Please provide Dave with the assistance he may need from a statistician to allow this plan to be sound and provide the basis to meet attachment 1. Dave has copies of the total number that need to fill in the blank on the attachment.
If I can be of assistance, please feel free to contact me (FTS-388-5635).
J. J. Harrison s
%h B506250451 850411 PDR FOIA
, BERNABE85-123 PDR
ATTACHMENT 1 NRC Sampling Plan to Verify Inspector Qualifications:
Attributes: ,
- 1. 95% Confidence / Reliability Level
- 2. The lots to be sampled:
- a. T-8/ Mercury QC - Population
- b. Other QC Inspectors - Population - proportion total sample size to each contractor by total QC Inspectors.
~
- c. Other: QA Personnel for all - Population - proportion total sample to number of QA personnel.
- 3. Develop a random number basis for QA/QC personnel selection.
van!Nd f
a WATERFORD STEAM ELECTRIC STATION, UNIT No. 3 ,
ERRATA TO THE SAFETY EVALUATION REPORT SUPPLEMENT No. 9 -- NUREG-0787
, .- Appendix J, Section 2 Page 5 The first line of Item 11 should read, "The NRC Office of Investigations currently has twelver.open investigations of alleged wrongdoing."
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- 1. Introduction S ' '33-1 On October 1, 1984, the NRC staff issued Supplement 7 to the Waterford Unit 3 Safety Evaluation Report (SER) which provided the results to date of the staff's evaluation of approximately 350 allegations and concerns relating to poor construction practices at the Waterford 3 facility as well as the status of the operating license application review. As discussed in Supplement 7, the NRC's Executive Director for Operations, in order to assure that items needing resolution prior to staff consideration of an operating license were promptly addressed, directed complete management responsibility to the Office of Nuclear Reactor Regulation.
The principal areas needing resolution included: (1)completionand documentation of the review of the Final Safety Analysis Report (FSAR);
(2) response to the motion before the NRC Atomic Safety and Licensing Appeal Board to reopen the hearing because of cracks in the concrete basemat;(3) mptth*n. WC:
..J allegations. ns. edw
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Subsequent to the issuance of SSER J. a motion was filed by the Joint Intervenors to" reopen the hearing based on three contentions dealin with Moddhin (
Quality Assurance,Managemeat integrity,and the NRC staff effort dea ing A/
with allegations.'
. These and all other areas have been resolved to the staff's satisfaction to allow issuance of a license to Louisiana Power & Licht (LP&L) to operate Waterford Steam Electric Station, Unit No. 3.
In the staff's review of the Waterford 3 FSAR, an SER and eight supplements have been previously published. At this time no safety issues from the FSAR review remain unresolved.
The second item that needed resolution prior to a licensing decision concerned the common foundation, concrete basemat supportidg the safety class structures at Wr.terford. On August 7, 1984 the staff filed its response to a motion to reopen the hearings based.on cracks discovered in the basemet. The staff .
concluded that the observed cracking does not affect the safety of the Waterford facility. On October 2, 1984, the A) peal Board requested additional information on the filigg The staff us. filed its response on December 17, 1984.{5 %st sa @ ddh ionM information includes a discussion of the 7/
allegations concerning the construction of the basemat as resolved in this SSER. ,
! Completion of routine NRC Regional inspection actions was the third area that needed to be finished before a licensing decision could be reached. In memoranda from R. Martin, Region IV to H. Denton, NRR dated December 4, 1984 and from R. Martin, Region IV to D. Eisenhut, NRR dated December 13, 1984, the Pegion IV staff found that based on its inspections, they conclude that construction is complete, preoperational testing has not revealed any significant unresolved problems, and the licensee is ready and, in its ,iudge-ment, competent to operate the Waterford 3 plant. The licensee has sufficient trained and licensed staff to safely operate the Waterford 3 plant and they have no concerns regarding the fitness for duty of the Unit 3 operating staff.
Region IV has no items which would preclude issuance of a low power operating license.
($-Y"Y Waterford SSER 9 Appendix J
The fourth issue involves allegations concerning construction practices. SER No. 7, issued on October 1,1984, resolved many of the 350 technical allegations and concerns the staff had identified beginning in early 1984.
However, as a result of the staff's review, 23 areas of potential safety concern were identified. In a letter to the 4pplicant dated June 13, 1984, Louisiana Power & Light was requested to propose a program and schedule for a detailed and thorough safety assessment of the 23 concerns. LP&L gepppr)ded i to the staff's request by letter dated June 28, 1984. W. / '
After discussions with the staff the plan was revised and impro'ved, and as the uAnt.rA m 'innt reviewed the concerns more closely their program became more detailed and thorough. Revised program plans were submitted by letters of July 27, September 14, 18, and 28, October 10, 19. and 31, November 21, and December 6, 1984. As requested by the staff the program included plans to address root cause, and potential generic implications of each of the 23 concerns.
The : provided the results of their review and the corrective actions taken for each of the concerns by letters dated August 10 and 27, September 4, 14, 18,and 28, October 15, 19, and 31, November 21, and December 6, 1984.
. NRC N ers reviewed the 23 issues identified in/ C letter from \
Mr. Darrell G. Eisenhut to LP&L Mr. J. M. Cain dated _ June 13, 1984. The Lk 5c.
", specifically reviewed LP&L's responses, corruc Le actions, program plan, '
implementing procedures, and results. The 4HilrTa so evaluated the third party assessment, being perfonned by _the NUS Corporatfory, under contract to LP&L to wS944 reviewthgc ,
The NRC 4e8%pmj:tive action process on the 23 issues identified by the NRC.Tfrorts November 1984, with site visits being regularly;cydugegr ugtgpgod. .
In evaluating the corrective actions, the team reviewed the LPAL plan, A b h responses, corrective actions and inspection results. The-4esaT F6Tewed the actions and results taken on examples identified'by the NRC as well as sampling the total populations both within and outside of the licensee's evaluation j process. Where the licensee performed a one hundred g cent review,a ,1grge ~ (
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sample w gas 1so taken. The fiRC sampling process was*
staff t; -_. , a sufficient level of confidence to assure that the licensee had determined: (1) the extent and depth of the problem; (2) safety significance .
and generic implications; (3) adequacy of management controls; (4) adecuacy of corrective action; to correct the problem and = ti r to prevent recurrence; and (5) identified impact on hardware, if any.
The sstewteam reviewing the responses to the 23 issues and related information was comprised of 30 technical members, many of whom originally participated in April and May 1984 effort. Several other members were supplied from a similar effort recently conducted at the Comanche Peak site. Team members were drawn from NCR's Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, Office of Inspection and Enforcement, from NRC's Region III and IV Offices and from-the-staff-of-a-Nat4cnah-laboratory, /.Wud mwdhtr;h .
The Task Force also discussed with the NUS Corporation their independent review of the 23 concerns and LP&L's responses to them. NUS developed procedures to validate the infonnation contained in LP&L's responses to the NRC, as well as Waterford SSER 9 Appendix J
verify that corrective actions defined by LP&L in their responses were properly carried out. During the course of NUS's evaluation and validation activities they performed inspections of field installations where necessary.
The NRC has reviewed NUS's evaluations for each of the 23 issues. In some cases recoinnendations were made to LP&L for improving their programs but in each case NUS concluded that the concerns raised by the NRC iave been adequately addressed.
The staff, having reviewed the applicant's responses to the concerns raised and NUS's reports on LP&L's program, concludes that all concerns have been satisfactorally addressed. The staff's evaluations for e,ich of the 23 issue are included in this report. N (A.tes, A -109 , A-lh , A- lW , 4 2.W, A- 2.52. , A-2s's , A-53% -3MJ Also include are evaluations of nine allegations previously identified in
$$ER No. 7 The reviews of these allegations were still in progress when
, ,. : SSER No, was issued. These evaluations, now complete, are presented in this
- ' report.
The staff completed its review of an issue in Allegation A-19 requiring additional action by LP&L. The NRC staff had identified some issues pertaining to electrical support documentation deficiencies. These deficiencies were identified, trac ted, and resolved on LPAL site Survet.11ance Report W35-84-165.
~
These issues were resolved by LP&L and reviewed by the NRC staff and found acceptable.
One allegation, though documented in $$ER No. 7 as being resolved, required additional review. The staff's review of Allegation A-256 in SSER No. 7 indicated that the Waterford 3 paint application for inside the containment.
vessel did not have any documentation concerning certification, painter qualification, quality. control certification, or work activity inspection.
This does not meet Regulatory Guide 1.54, and therefore, paints inside containment are not considered qualified. The staff dispositioned Allegation A-256 as having no safety significance on the basis of LP&L's demonstration of coating adequacy throuch the use of an in-situ design basis, accident (DBA) test. ,
Upon more detailed review, the staff has determined that the demonstrated /
adequacy of coatings inside containment based on thtf particular type of V in-situ test is inconsistent with ANSI N 101.2. The in-situ DBA testing of the coatings inside containment at Waterford was limited to three test locations, which is not considered representative of the containment coating system, nor did it include the effects of radiation, and chemical spray solution. Because of the potential safety significance of failure of these coatings, and in order to gain confidence in the applicant's as-built configuration' of coatings, the staff will require that LP&L perform a plant-specific analysis demonstrating that failure of these coatings will not adversely impact the performance of post-accident fluid systems. This methodology is consistent with that in Revision 1 of SRP Section 6.1.2 (Dectmber 1978), acceptance criterion II.2.c. /.
which permits non-oualified coatings'pf "it can be justified that the debris V will not adversely affect the performance of post-accident fluid systems." A conditinn was placed in the operating license requiring that LP&L submit'the above plant-specific evaluation for staff review and approval one-month after
,issuerce of-the operating-license' p w r fr A m . 19, g6 Waterford SSER 9 Appendix J
The applicant has submitted a justification for interim operation of Waterford 3 up to 55 of rated power. The adverse environment for coating failure inside containment, by a break in thewhere sump reactor watersystem coolant is necessary(RCS)., could potentially The probability of an RCSonly be produce break of sufficient size to degrade containment coating is low during the period prior to exceeding 51 power. Moreover, the low levels of decay heat and fission products produced during this period would limit accident sonsequences to low levels in the unlikely event of an RCS break. The applicant has perfonned an analysis employing very conservative assumptions and has demonstrated that three hours following a large break LOCA, whe,n ECCS flow is first required to prevent core uncovery, the flow requirement is less than one- /
half of one percent of one loop of Low Pressure Safety Infisction TJ '), /
-
- approximately 20 gpm. An assumed sump blockage of 905 would still allow g sufficient coolant to the core. (gggAge,g.350)
. Three additional allegations concerning construction of the Waterford 3
-a facility were identified to the staff after the Waterford 3 Task Force had completed its six-week onsite review of t f ap roximately 350 1ations.
The Waterford 3 Task Force reviewed these n t e same manner)t legations discussed in SSER No. 7 were reviewed, and their evaluations are included in this report. .
'/ On November 8. 1984 the Joint Intevenors filed anotheLr motion with the Appeal poard to reopen the hearings. The motion consisted of three contentions concerning the applicant's quality assurance pro 9 ram, the applicant's character integrity and competence, and the NRC s effort to resolve the allegation's and concerns of poor construction practices at Waterford. The staff has reviewed the supporting materials and has not identified anything which would alter its previous conclusions concerning the basemat or the allegations discussed in this $$ER or in $$ER No. . The staff X. respond -
formally to the motion on December 21,1984. (au, Alo, f.)
- 3. Susunary y i .
Based on its review of the :;;M;;;;'; response and corrective action to the staff's 23 areas of safety concern. its review of the additional allegations -
and contentions not addressed in SSER No. 7. and other related information, the staff makes the following observations and conclusions:
w ig i 1. The WMr;'; program plan for resolving the staff's 23 areas of l potential safety concern was found to contain acceptable corrective action to resolve the safety concerns. .
} 2. The hN program plan also identified acceptable action taken to prevent recurrence in each specific case and as denoted in
! collective significance should be sufficient to ensure that the OA
- program breakdown does not recur.
i t l 3. The a.we.AU.pplicant utilfred appropriately qualified individuals to j implement the program plan. .
I
! 4. The implementation of the program plan was completed to the satisfaction of staff.
l f
- i. . 44 l Waterford SSER 9 .4 - Appendix J i
tA. :
- 5. The third party assessment performed by the,MNC/NUS group provided an(extensive and valuable audit, validation and inspection effort /
/
of the LP8L resperses to the 23 issues raised in the NRC letter to LP&L of June 13, 1984.
- 6. The nine allegations previously identified in SSER No. 7 were reviewed and found to have no safety significance or gengric implications.
- 7. The additional allegations that were identified after' the initial
, six-week onsite review were reviewed and found to have no safety significance or generic implications.
- 8. Allegation A-256 in SSER No. 7 was given additional review. As a result of this review the staff finds that this issue may have an impact on safety. A condition has been placed in the operatin
..- lice.1se requiring acceptable resolution of this issue e mc.;g W%
9 efter-isstrenw vi snw operating-license 0
}
- 9. Although LP8L did not fully implement their QA program, the impact on hardware was minimal. The plant design is adeouate and the final installed plant systems meet the design requirements. The few hardware deficiencies were reviewed and werg. found to have been satisfactorily corrected.
- 10. Potential violations of NRC regulations identified by the Task Force have been forwarded to the NRC Office of Inspection and Enforcement and to the Administrator. NRC Reginn IV Office for appropriate action. An escalated enforcement action package has , '
been prepared.
- 11. The NRC Office of Investigations is currently conducting ;L.7 /
investigations of alleged wrongdoing. 'AJfdttional potential .
violations may result from these investigations.
i Waterford SSER 9 Appendix J