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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
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NUCLE AR REGULATORY COMMISSION
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611 R v AN Pli.Z A L)RIV F SUIT E 400 t AH L6NG T ON 1 E v. AS 700118064
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December 26, 1996 EA 96-255 Michael B. Sellman. Vice President l Operations - Waterford l Entergy Operations. Inc.
! P.O. Box B l Killona. Louisiana 70066 SUBJECT: NDTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY -
$50.000 (NRC Inspection Report Nos. 50-382/96-09 and /96-20)
Dear Mr. Sellman:
This refers to the predecisional enforcement conference conducted on l November 20. 1996. with you and members of your staff in the NRC Region IV
! office in Arlington. Texas. The conference was held to discuss the l circumstances surrounding three apparent violations discussed in the subject
- inspection reports. These apparent violations were identified to your staff l during a telephonic exit meeting on October 9. 1996. The inspection reports were issued on July 24. 1996 (96-09) and October 24, 1996 (96-20).
l l Based on the information developed during the inspection and the information I
that you provided at the conference, the NRC has determined that violations of l NRC requirements occurred. These violations are cited in the enclosed Notice l of Violation and Proposed Imposition of Civil Penalty (Notice) and the circumstances surrounding them were described in detail in the subject l inspection reports.
l Violation I in the attached Notice involves the actual design configuration of l the containment vacuum relief (CVR) system being different from that described l in the Waterford 3 Final Safety Analysis Report (FSAR). The required written safety evaluation to substantiate that the change did not involve an unreviewed safety question was never performed. Specifically, the CVR
, instrument lines did not terminate at a location within the controlled i ventilation area system (CVAS) (or within any other filtration system) as l described in the response to FSAR Ouestion 480.36. As a result of the erroneous information. valves CVR 302A(B) and 402A(B) were inadequately test 1 to ensure they fulfilled the containment isolation function in accordance with
- General Design Criterion 56.
When appropriately tested in July 1996. valves CVR 302A(B) and CVR 402A(B)
failed to close. Thus, containment isolation would not have been adequate in the event of a design basis event. Due to its design. the failure of CVR 402A(B) had the potential to result in both control room dose limits and offsite dose limits being exceeded during a design basis loss-of-coolant 9612300050 961226 PDR ADOCK 05000392 l
l G PDR l
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Entergy Operations. Inc. -2- t Waterford 3 accident. Therefore, this violation is classified in accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy). NUREG-1600, as a Severity Level III violation.
Violation II.A in the Notice, involves a failure to promptly evaluate and correct known discrepancies in the IST program. The circumstances surrounding this violation involved known discrepancies between an Inservice Testing (IST)
Design Basis Document (DBD-024). issued in March 1994, and the IST )lan in existence at the time. In May 1994. Entergy formed an IST Plan Tasc Force to i
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resolve these discrepancies and to determine if the IST plan met all ASME Code requirements. In November 1994, the task force issued its final report stating that the addition of the 39 valves to the IST plan would be ,
" enhancements" and that the company was in compliance with applicable t requirements without the addition of these 39 additional valves. This determination was incorrect and the valves were not added to the IST plan. It was not until about December 1995 that this condition adverse to quality was I identified, when Waterford 3 personnel began identifying that these valves I should be included in the IST program and began developing a schedule for reviewing the discrepancies.
At the pre-decisional enforcement conference. Entergy personnel stated that the root causes for this violation involved: (1) the inappropriate assigning
- of responsibility for the IST program to the shift technical advisors (STA).
l (2) the perception that management was not receptive to additional testing.
(3) inadequate and ineffective corrective action tracking. (4) inadequate
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coordination between the IST bases document and the IST plan. (5) inadequate guidance concerning how long DBD open items may remain o)en, and (6) the failure to enter in the corrective action program the su) sequent items i
identified in an earlier review. At the conference, your staff stated that
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there was no saMy significance associated with the identified plan discrepancies, and that the violation should be classified at Severity Level !
IV. We agree that, exce)t for the CVR 402A(B) valves discussed in Violation ;
! I the consequences of t1is violation, with the valves in their as-found !
condition, would have been minimal. However, these IST issues involve known
- discrepancies in the IST program that were not addressed in a timely manner
! and, as a result, a larce number of valves were not being tested to assure they would perform their safety function. Therefore, this violation has been l categorized in accordance with the Enforcement Policy at Severity Level III.
l In accordance with the Enforcement Policy, a civil penalty of $50.000 is ;
! considered for a Severity Level III violation. Because your facility has been j the subject of escalated enforcement actions within the last 2 years , the NRC considered whether credit was warranted for Identification and Corrective
! EA 96-025 issued on March 25. 1996. invoh ed a $50,000 civil penalty for a failure to implement effective actions to preclude repetition of a significant condition adverse to quality.
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Entergy Operations. Inc. -3-Waterford 3 l l
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Action in accordance with the civil penalty assessment process in Section !
VI.B.2 of the Enforcement Policy. In reviewing the Identification factor for i Violation I. NRC noted an important missed opportunity to earlier :
identification of the violation. This occurred during the review of Condition !
Report CR-96-0272, initiated March 1,1996, involving the operability of certain valves, including CVR-302A(B). Also, during several discussions with i NRC inspectors through July 20 your staff continued to depend on the j erroneous information in the FSAR and stated the intent to remove the valves from the inservice test (IST) program. Although we recognize that your staff I i ultimately identified the FSAR discrepancy associated with the CVR 302A(B) and j 402A(B) valves. NRC has determined that it as unlikely_that your staff would have identified this violation absent NRC's involvement Therefore. the NRC l
has determined that credit for the Identification factor is not warranted for l Violation I. As to Violation II, the NRC has determined that credit for the Identification factor is warranted because Entergy identified the problem.
In evaluating the Corrective Action factor, the NRC has determined that credit is warranted for both Violation I and II because the corrective actions to these violations were sufficiently prompt and comprehensive. Corrective actions for Violation I included: (1) promptly replacing and retesting failed valves. (2) performing a root cause analysis. (3) isolating and administratively controlling the non-essential lines until a plant
! modification and license amendment could be implemented. (4) promptly submitting a license amendment request. (5) reviewing other containment penetrations'for similar problems, and (6) implementing a FSAR fidelity assessment. The corrective action for Violation II included: (1) developing a
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schedule to resolve the discrepancies between the IST plan and the DBD.
(2) testing the valves which had not been previously tested or which had been inadecuately tested. (3) controlling changes to the IST plan with the DBD by
- procecure and (4) comprehensively reviewing the ASME valves and current IST l
plan to facilitate development of a second 120-month interval plan.
l At the predecisional enforcement conference, your staff asserted that the NRC should exercise discretion for Violation I because it was an old design issue.
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, After careful consideration, we have determined that, because of the NRC's involvement in the identification of the violation, this problem was not identified by a voluntary initiative on Entergy's part (Entergy was moving to i
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remove the CVR 302A(B) valves from the IST 3rogram until NRC's questioning, and most likely would not have identified t1e same problem with CVR 402A(B)).
As such, the exercise of discretion is not warranted in this case.
Therefore, to emphasize the importance of ensuring that the plant is operated in accordance with its FSAR and the importance of prompt identification of l non-conforming conditions. I have been authorized. after consultation with the '
! Director. Office of Enforcement, to issue the enclosed Notice of Violation and
! Proposed Imposition of Civil Penalty (Notice) in the base amount of $50,000 i for the Severity Level III violation discussed in Section I of the Notice. In i addition to encourage your efforts to identify and correct problems and
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noncompliances. I have also been authorized to issue a Severity Level III ,
j violation without a civil penalty, for the Severity Level III violation ;
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! described in Section II.A of the Notice. However. significant violations of i this nature could, in the future, result in a civil penalty. ,
The third violation. discussed in Section II.B of the Notice, involved a
failure to fully close a centainment spray valve. Entergy personnel identified this condition in November 1995, promptly corrected it, and l performed en operability determination of the Containment Spray System.
During discussions concerning IST issues in March 1996. design engineering personnel realized that the earlier operability evaluation did not consider backleakage to the refueling water storage pool. This realization :
demonstrated a good questioning attitude by plant staff. Using very '
l conservative calculations. Entergy Jostulated the consequences of the i l condition to be that Control Room t1yroid dose limits would be exceeded. '
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However. a more realistic analysis including a review of the plant's routine monitoring program, showed that Control Room thyroid dose problems would have been identified before dose limits would have been exceeded. Given the circumstances of the violation. the NRC determined that this violation is appropriately classified at Severity Level IV.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence. After reviewing your response to this Notice. including your proposed corrective actions and the results of future inspections, the NRC will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice." a copy of this letter, its enclosure. and your response will be placed in the NRC Public Document Room (PDR). To the extent possible, your response should not include ,
any personal privacy proprietary, or safeguards information so that it can be I placed in the PDR without redaction. I
Sincerely
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f L. Callan l
Regional Administrator l
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Docket No. 50-382 License No. NPF-38 Enclosure: Notice of Violation and Proposed Imposition of Civil Penalty
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Entergy Operations Inc. -5-Waterford 3 cc (w/ enclosure):
Executive Vice President and Chief Operating Officer Entergy Operations. Inc.
P.O. Box 31995 Jackson. Mississippi 39286-1995 Vice President. Operations Support Entergy Operations. Inc.
P.O. Box 31995 Jackson. Mississippi 39286-1995 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 i Killona. Louisiana 70066 Manager - Licensing Manager 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 Waterford 3 SES Entergy 03erations. Inc.
P.O. Box 3 Killona. Louisiana 70066 l
William H. Spell. Administrator
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Louisiana Radiation Protection Division
- P.O. Box 82135
- Baton Rouge. Louisiana 70884-2135 i
- Parish President i St. Charles Parish
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P.O. Box 302 Hahnville. Louisiana 70057
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Entergy Operations. Inc. -6-Waterford 3 Mr. William A. Cross Bethesda Licensing Office 3 Metro Center Suite 610 Bethesda. Maryland 20814 Winston & Strawn 1400 L Street. N.W.
Washington. D.C. 20005-3502 i
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Waterford 3 bcc:
DISTRIBUTION:
PDR IE 14 LPDR Enforcement Coordinators SECY RI. RII. RIII CA JGilliland. PA (0-2G4)
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JMilhoan. DEDR (0-17G21) GCaputo OI (0-3E4)
JLieberman. OE (0-7HS) EJordan. AE00 (T-4018)
LChandler OGC (0-15B18) LTremper. OC/LFDCB (T-9E10)
JGoldberg. 0GC (0-15B18) OE: (0-7H5)
Director. NRR (0-12G18) OE:EA (2) (0-7H5)
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MVasqubz GFSdn66hf DPowers M KEBrockmanfin PGwynnly,,/e
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OFFICIAL RECORD COPY
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Waterford 3 !
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DISTRIBUTION:
PDR IE 14 l LPDR Enforcement Coordinators 1 SECY RI. RII. RIII ,
CA JGilliland. PA (0-2G4)
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LChandler. OGC (0-15B18) LTremper. OC/LFDCB (T-9E10)
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CHackney (CAH) WBrown (WLB)
JDyer(JED2) KPerkins(KEP)
AHowell (ATH) LKeller (LAK)
PHarrell (PHH) KBrockman(KEB)
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LEllershaw (LEE 1) GMVasquez (GMV)
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