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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: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] |
See also: IR 05000382/1997005
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NUCLEAR REGULATORY COMMISSION
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REGION IV
S b'8- [ 611 RYAN PLAZA DRIVE, SUITE 400
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8 AR LINGTON, TE X AS 760118064
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July 25, 1997
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Charles M. Dugger, Vice President
Operations - Waterford 3
Entergy Operations, Inc.
P.O. Box B
Killona, Louisiana 70066
SUBJECT: NRC INSPECTION REPORT 50-382/97-05
Dear Mr. Dugger:
l Thank you for your letter of July 8,1997, in response to our letter and Notice of Violation
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dated May 23,1997. We have reviewed your reply and find it responsive to the concerns
raised in our Notice of Violation regarding Examples 1,2, and 3 of the' violation. -We will i
review the implementation of your corrective actions during a future inspection to
determine that full compliance has been achieved and will be maintained regarding
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4 Examples 1, 2, and 3.
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- As a result of our review of Example 4 (involving welding on a containment spray line as 1
opposed to a safety injection line), we have.found that additional information is needed. j
This need was discussed with Mr. T. Gaudet during a telephone call on July 22,1997. l
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Specifically, the proposed corrective action for Example 4 was only to counsel the team !
leader. However, we identified in our inspection report that Example 4 revealed many
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breached barriers. The additional information that we are requesting should address your
proposed corrective actions to remedy the ca ases that led to all of the barrier failures.
. As agreed during our telephone call, please provide the additional infermation by
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August 22,1997. This time extension will enable your completion of the root cause
analysis and the finalization of corrective actions.
- Sincerely, 1
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Arthur T. Howell 111, Director
Division of Reactor Safety
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Docket No.: 50-382
License No.: NPF-38 ,.
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Executive Vice President and
Chief Operating Officer I
Entergy Operations, Inc. i
P.O. Box 31995 l
Jackson, Mississippi 39286-1995
Vice President, Operations Support
Entergy Operations, Inc. l
P.O. Box 31995 ,
Jackson, Mississippi 39286-1995 l
Wise, Carter, Child & Caraway
P.O. Box 651
Jackson, Mississippi 39205
General Manager, Plant Operations
Waterford 3 SES
Entergy Operations, Inc.
~ P.O. Box B
Killona, Louisiana 70066
Manager - Licensing
Waterford 3 SES
Entergy Operations, Inc.
P.O. Box B
Killona, Louisiana 70066
Chairman -
Louisiana Public Service Commission
One American Place, Suite 1630
Baton Rouge, Louisiana 70825-1697
Director, Nuclear Safety &
Regulatory Affairs
Waterford 3 SES
Entergy Operations, Inc.
P.O. Box B
Killona, Louisiana 70066
William H. Spell, Administrator
Louisiana Radiation Protection Division
P.O. Box 82135
Baton Rouge, Louisiana 70884-2135
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Parish President l
St. Charles Parish
P.O. Box 302
Hahnville, Louisiana 70057 ,
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Mr. William A. Cross
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Bethesda Licensing Office
3 Metro Center
Suite 610
Bethesda, Maryland 20814
Winston & Strawn
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1400 L Street, N.W.
Washington, D.C. 20005-3502
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Regional Administrator Resident inspector
DRP Director
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Project Engineer (DRP/D) . RIV File i
Branch Chief (DRP/TSS) Leah Tremper (OC/LFDCB, MSi TWFN 9E10) !
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Ente perations Inc.
KWona LA 70CE6 i
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Early C. Ewing,111
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July 8,1997
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U.S. Nuclear Regulatory Commission e I
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Washington, D.C. 20555
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Subject: Waterford 3 SES
Docket No. 50-382
License No. NPF-38 l
NRC Inspection Report 97-05
Reply to Notice of Violation
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Gentlemen:
In accordance with 10CFR2.201, Entergy Operations, Inc. hereby submits in
Attachment i the response to the violation identified in Enclosure 1 of the subject
Inspection Report.
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if you have any questions concerning this response, please contact
me at (504) 739-6242 or Tim Gaudet at (504) 739-6666
Very truly yours,
C
$1./
E.C. Ewing
Director,
Nuclear Safety & Regulatory Affairs
ECE/GCS/tjs
Attachment
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, NRC Inspection Report 97-05
Reply to Notice of Violation
W3F1-97-0182
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Page 2
July 8,1997 l
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cc: E.W.'Merschoff (NRC Region IV) .
C.P. Patel (NRC-NRR)
J. Smith
N.S. Reynolds l
NRC Resident inspectors Office
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ATTACHMENT 1
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l ENTERGY OPERATIONS. INC. RESPONSE TO THE VIOLATION IDENTIFIED IN
- . ENCLOSURE 1 OF INSPECTION REPORT 97-05
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VIOLATION NO. 9705-03
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i Criterion IX of Appendix B to 10 CFR Part 50 states, in part, " Measures shall be
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established to assure that special processes, including welding.. .. are controlled
i. and accomplished..... in accordance with applicable codes, standards,
i specifications, criteria, and other special requirements."
Contrary to the above, measures did not assure that welding was controlled in -
i accordance with requirements in the following examples that were identified by the
l, licensee's correction program:
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l 1. Weld rod was not discarded in accordance with the requirements in
Procedure MM-001-053, in that, on five occasions from April 16-23,1997,
unattended and unaccounted for weld rods were found.
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4' 2. Stainless steel welds were contaminated contrary to the requirements in
- Procedure MM-001-050 on two occasions, March 6 and April 15,1997, when
! carbon steel wire brushes, chains and work tables came into contact with
l weld surfaces. .
- 3. Final quality control inspections of stud welds were not performed as required ~
by Procedure NOECS-100 on April 16,1997.
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p 4. A coupling was not welded on a safety injection line, as required by Work
Order 001153561. The coupling was erroneously welded on April 20,1997,
- - to a containment spray line.
} . These examples constitute a Severity Level IV violation (Supplement 1) (50-
!' --382/9705-03).
, RESPONSE
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(1)- Reason for the Violation
k- All four examples of failure to control the welding program were identified by
- Waterford 3 and entered into the corrective action program. Each example
i was evaluated in concert with other program deficiencies to draw conclusions
regarding process control. Evaluation results indicate the process, in general,
i is well defined and controlled. Moreover, the corrective action program
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continues to provide feedback and corrective actions that promote process
. improvement.
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Analysis of each example indicated a need for both specific and broad
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- corrective actions. Specific root causes and corrective actions for each
violation were formulated to preclude the recurrence of similar examples. The
j root causes and corrective actions for each example are identified below.
j included within those actions, where appropriate, are plans to conduct
additional training. We believG additional training is warranted to address the
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, brcader implications of this violation; namely, to ensure that welding activities
]- - are accomplished in accordance with program controls.
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!- Example 1
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l The root cause of this example is inadequate training. Personnel using
welding material were not properly trained on plant requirements related to
l disposal and control of filler material. During the outage, many of the
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individuals using welding material were contractors who were temporarily 1
- _ assigned to Waterford 3. These individuals were provided reading material
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! on the proper control of filler material but were never given formal classroom '
[ training.
I Contributing to this example is inadequate administrative controls. There
j' were no administrative controls to ensure that welders did not check out
!- excessive quantities of welding filler material. According to site Administrative
l Procedure MM-001-053, " Control of Welding Consumables (Filler Material),"
j' welders could request any quantity of welding filler material as long as they
- were qualified to use that filler material. As a result, excessive quantities of
j welding filler material were sometimes requested for minor welding activities,
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and the unused filler material was not always returned.
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f' Also contributing to this example is poor work practice. The use of rod stub
i- disposal barrels as a means of disposing welding filler material proved to be
- . inadequate. The rod stub disposal barrels were not properly maintained and
j' were not emptied when they became full. As a result, rod stubs were
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sometimes falling out of the barrels.
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l Example 2
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[ The root cause for this example is an inadequate procedure. Site
l Administrative procedure MM-001-050, " General Welding Requirements,"
does not specifically state that carbon steel wire brushes should not be used
- on stainless steel material. The procedure states that tools used on one type
[ . of base material such as carbon steel are not to be used on another type of
i material such as stainless steel. This statement does not preclude using
- carbon steel brushes on stainless steel material, but prohibits using the same
l tool on both carbon and stainless steel materials.
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Contributing to this example is inadequate administrative controls. Stainless
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steel wire brushes are required to be color coded red to distinguish them from
carbon steel brushes. . It was discovered in some instances that carbon steel
brushes were incorrectly color coded red.
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Regarding stainless steel welds contacting carbon steel surfaces, it was
determined, as documented in engineering input to condition report CR-97-
0527, that casual contact between the stainless steel and the carbon steel
surface of the work table and the chainfall will not contaminate the stainless i
steel welds.
Example 3 I
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The root cause of this example is inadequate procedure. The Weld j
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Specification Documentation Sheet (WSDS) in procedure MM-001-054,
" Control and Documentation of Welding," which specifies when QA visual j
examination of welds is required did not clearly indicate that all the stud welds j
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associated with the work should be examined. Initially only two of the
preproduction testing welds were inspected by QA. !
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Contributing to this example is poor communication. The Quality Assurance l
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Inspectors were aware that stud welds were being placed on the gantry crane
rail holddown bolts and that they were required to inspect the welds after
installation. However, the lead engineer on this task was not on site when
this activity was completed and notification that the welds had been :
completed and ready for inspection was not communicated to QA. As a
result, the work was completed and nuts and plates were placed over the stud
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welds before QA could inspect them.
Example 4 .
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The root cause for this example is inattention to detail. The individuals tasked
to weld a coupling on a safety injection line were provided with isometric
drawings showing the location of the line to be welded on. They incorrectly
welded on the containment spray line which was in the vicinity of the safety
injection line. Had these individuals paid closer attention to detail and
matched the penetration number on the isometric to the penetration number
on the containment wall, they would not have made this error.
(2) Corrective Steps That Have Been Taken and the Results Achieved
The corrective steps that have been taken for each example of failure to
control the welding process at Waterford 3 are provided below:
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Example 1
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Filler material training was conducted on April 25 and April 28,1997.
, Welding foreman and tool room attendants were required to attend the l
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training. Those welders who did not attend the training were not allowed to l
check out welding material. j
A satellite filler material issue facility was established to be used during heavy I
welding periods for issuing filler material outside the protected area to ,
enhance the filler material issue process. )
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Tighter controls have been placed on the issuance of filler material. j
Individuals requesting filler material are required to jus (n'y reason for usage. 1
l The quantity of filler material requested and used is tracked. Unused material
and rod stubs are returned to storage. l
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All covered electrodes or welding rods are issued in either a rod caddie, a ;
leather pouch or equivalent container. i
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Rod stub cans are issued to welders when they request filler material.
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Rod stub disposal barrels will no longer be used for general disposal of
welding filler material.
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Example 2
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Quality Assurance issued a Stop Work Order to place a hold on activities
where there was a potential for carbon steel brushes to be used on stainless i
steel material.
The Filler Material Data Base was reviewed to identify stainless we: ding l
activities in order to determine the work packages involved.
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Engineering evaluated the effect of using carbon steel brushes on various
stainless steel components and determined that they were not adversely j
affected.
Wire brushes were verified to be properly color coded.
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Carbon steel brushes were removed from job locations, tool rooms, and the l
plant warehouses.
Tighter controls have been placed on the issuance of wire brushes.
Individuals requesting wire brushes are required to justify reason for usage.
Welders were instructed on the proper use of wire brushes. This included the j
use of wire brushes on joints constructed of dissimilar material.
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) Appropriate Management personnel discussed his issue with their
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supervisors who held discussions with their employ 6es.
L Example 3
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l The nuts and plates were removed from the gantry crane rail holddown bolts
l and the welds were inspected. ]
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' A discussion of this event was held with appropriate' personnel to ,
- reemphasize the requirement for QA inspections of welds. I
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i Example 4
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[ The individual leading the team responsible for welding on the incorrect line
was counseled.
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I (3) Corrective Steos Which Will Be Taken to Avoid Further Violations - .
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l- The corrective steps which will be taken to avoid further violations for each
!. example of failure to control the welding process at Waterford 3 are provided
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Example 1
- Administrative procedure MM-001-053, " Control of Welding Consumables,"
- .will be revised to specify training requirements for the tool room lead, tool
i room filler material issue personnel, and welders. This revision will be
completed by 10/31/97.
! - Example 2
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- _ Mechanical Maintenance procedure MM-001-050, " General Welding
l Requirements" and MD-001-012, " Tool Control,"_will be revised to include a
i- statement that only stainless steel brushes should be used on stainless steel
- components. This revision will be completed by 10/31/97.
f- Formal training will be developed for workers and contractors that normally
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use or issue wire brushes and grinding wheels. Training will be developed by
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12/31/97. New workers and contractors will receive training before attempting
[ any welding activities.
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j Example 3
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t - Mechanical Maintenance procedure MM-001-054, " Control and
[ Documentation of Welding," will be revised to enhance administrative controls
i regarding Weld Specification Documentation Sheet preparation. This revision
- . will be completed by 12/1/97.
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Example 4
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l- Waterford 3 believes that the corrective action taken for example 4 is
j adequate to prec;ude this type of occurrence.
(4) Date When Full Comoliance Will Be Achieved
' Full compliance will be achieved by December 31,1997,
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