|
---|
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 UTILITY
MONTHYEARML20058E8621990-11-0101 November 1990 Forwards Understanding of Current Status of Unimplemented GSIs at Facility,Per 900626 Response to Generic Ltr 90-04. Timely Completion of Encl GSIs Urged ML20058G1561990-10-31031 October 1990 Requests That Matl Listed in Encl 1, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams, Be Furnished by 901207 for Retake of Operating Exams Scheduled for 910122 ML20058B3101990-10-23023 October 1990 Forwards Insp Rept 50-382/90-22 on 900905-1001 & Notice of Violation IR 05000382/19900231990-10-17017 October 1990 Submits Revised Schedule for Electrical Distribution Sys Functional Insp 50-382/90-23.Insp Team Will Arrive at Plant Site on 910107 ML20058B2681990-10-17017 October 1990 Informs That Util Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058A6711990-10-16016 October 1990 Forwards Insp Rept 50-382/90-21 on 900910-14.No Violations or Deviations Noted ML20058A4771990-10-16016 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-17 ML20062B6231990-10-12012 October 1990 Confirmation of Action Ltr CAL-90-06,confirming That Plant Will Not Enter Mode 2 Until NRC Confirms Actions Assuring That Adequate Safety Exists for Continued Power Operation IR 05000382/19900151990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-15.NRC Unable to Clearly Determine Actions Intended to Address Overall Retest & Program Weaknesses ML20059N7041990-10-10010 October 1990 Ack Receipt of Util 900717 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20059K8651990-09-14014 September 1990 Forwards Interfacing Sys LOCA Insp Rept 50-382/90-200 on 900730-0810.Deficiencies in Availability of Design Calculations,Check Valve Maint & Plant Equipment Labeling Noted ML20059K3601990-09-14014 September 1990 Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise ML20059D5901990-08-28028 August 1990 Forwards Insp Rept 50-382/90-17 on 900625-29.No Violations or Deviations Noted.Exercise Weakness Re Performance of Emergency Responders Noted ML20056B4841990-08-22022 August 1990 Forwards Errata to Amend 62 to License NPF-38,consisting of Revised Bases Page Re Time Intervals for Surveillance Requirements,Per 900717 Application & Generic Ltr 89-14 ML20056B2731990-08-16016 August 1990 Ack Receipt of 900720 & 0803 Ltrs Re Objectives & Guidelines for Annual Emergency Preparedness Exercise.Objectives Appear Reasonable.Exercise Scenario & Associated Matls Should Be Submitted at Least 60 Days Prior to Exercise for NRC Review ML20058P3441990-08-15015 August 1990 Advises That Although Adequate Info Provided to Justify Continued Plant Operation Until Plant Completes Final Rept Per Schedule Delineated by NRC Bulletin 88-11,adequate Bases Not Provided for 40-yr Plant Life ML20056A0301990-07-30030 July 1990 Forwards Insp Rept 50-382/90-11 on 900625-29.No Violations or Deviations Noted IR 05000382/19900021990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-02 ML20055G7951990-07-19019 July 1990 Forwards Insp Rept 50-382/90-14 on 900625-29 & Notice of Violation.Actions Taken Re Previously Identified Insp Findings Also Examined ML20055E6501990-07-0909 July 1990 Discusses Generic Implications & Resolutions of Control Element Assembly (CEA) Failures at Maine Yankee.Waterford Unit 3 Does Not Have Old Style CEAs Installed in Reactor Core & Does Not Plan to Use Any in Future ML20055C9751990-06-26026 June 1990 Forwards Page 6a for Insertion in Insp Rept 50-382/90-09 ML20055C7781990-06-15015 June 1990 Forwards Insp Rept 50-382/90-09 on 900501-31.No Violations or Deviations Noted.One Unresolved Item Identified.Licensee Test Acceptance Criteria Did Not Appear to Account for Effect of Flow on Valve Closing Time ML20059M9171990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4121990-03-0202 March 1990 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Imposed by NRC 900202 Order.Corrective Actions Will Be Examined During Future Insp ML20055C2991990-02-23023 February 1990 Advises That 890410 Changes to Emergency Plan,Acceptable ML20248G1871989-10-0202 October 1989 Forwards Insp Rept 50-382/89-25 on 890828-0901.No Violations or Deviations Noted ML20248C6531989-09-27027 September 1989 Forwards Insp Rept 50-382/89-23 on 890801-31.Violations Noted.Enforcement Conference Scheduled for 891011 in Region IV Ofc to Discuss Violation,Reason for Occurrence & Corrective Actions ML20248A4091989-09-26026 September 1989 Requests That Jl Pellet Be Removed from Distribution for Controlled Documents Updates & Revs ML20247Q4211989-09-22022 September 1989 Provides Results of Review of Amend to Rev 5 of Inservice Testing Program for Pumps & Valves.Amend to Rev 5 Acceptable for Implementation & That Testing Requirements Impractical for Item for Which Relief Being Granted ML20247R5681989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-92,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, for Signature ML20247J6851989-09-15015 September 1989 Forwards Insp Rept 50-382/89-16 on 890717-21 & Notice of Violation ML20247D4781989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-05 ML20247F2211989-09-0808 September 1989 Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62 ML20247H8501989-09-0808 September 1989 Ack Receipt of 890531 & 0821 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07. NRC Disagrees W/Licensee Denial of Violation.Implementation of Corrective Actions Will Be Reviewed During Future Insp ML20246P6081989-09-0606 September 1989 Forwards Summary of 890712 Meeting w/C-E Owners Group & Utils Re General Design Features of Diverse ESFAS to Be Installed,Per 10CFR50.62.Safety Evaluation on Plant Design Expected to Be Issued in Near Future ML20246N3131989-08-31031 August 1989 Ack Receipt of Re Violations Noted in Insp Rept 50-382/89-08 & 890516 Notice of Violation.Requests Supplemental Response Re Examples 1-3 of Notice ML20247A5841989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.Agenda & List of Attendees Also Encl ML20246M6491989-08-29029 August 1989 Forwards Amend 56 to License NPF-38 & Safety Evaluation. Amend Increases Frequency of Channel Calibrs from Quarterly to Monthly on Waste Gas Holdup Sys Explosive Gas Monitoring Sys ML20245J0021989-08-14014 August 1989 Confirms 890808 Conversation W/Rp Barkhurst Re Util Participation in NRC Impact Survey Scheduled for 891010 & Submits Info Re Survey ML20245L3311989-08-11011 August 1989 Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation IR 05000382/19890121989-08-11011 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-12.Excluding Incident 1,Violation 382/8912-02 Should Stand as Cited. Response W/Corrective Actions Requested within 30 Days ML20245J2451989-08-0909 August 1989 Advises That Requalification Exams Scheduled for Wk of 890911 Changed to Wk of 890905 to Accommodate New INPO Schedule Issued in May 1989 IR 05000382/19890051989-07-31031 July 1989 Discusses Insp Rept 50-382/89-05 on 890213-17 & Forwards Notice of Violation.No Addl Info Was Provided to Change NRC Position & Therefore Util in Violation of Requirements.Basis for NRC Determination of Violation Provided IR 05000382/19890061989-07-28028 July 1989 Ack Receipt of 890706 Supplemental Response Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-06 1990-09-14
[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 05000382/1989011
Text
, _ _ .
'. y{ ,
"
- [E'* JUN 2 81989
In Reply Refer:To:
Docket.: 50-382/89-11
' Louisiana Power & Light Company
ATTN: J. G. Dewease, Senior Vice President ;
Nuclear Operations
'
,
L-
'
317 Baronne Street
New Orleans, Louisiana 70160
f ;
. Gentlemen:
Thank you for your letter of June 9,1989, in response to our letter and
i. Notice of Violation dated May 10, 1989. We have reviewed your reply and find-
it responsive to the concerns raised in our Notice of Violation. We will
review the implementation of your corrective actions during a future j
1
. inspection to determ ae that full compliance has been achieved and will be
d
f
.." .i
maintained.
Sincerely,
Original Signed By
L L. Milhoan
i
James L.1 Milhoan, Director
'
Division of Reactor Projects
.
.
cc:
Louisiana Power & Light Company
ATTN: R. P. Barkhurst, Vice President
.
Nuclear Operations
P.O. Box'B '
K111ona:, Louisiana 70066
Louisiana Power & Light Company
ATTN: J. R. McGaha, Jr., Plant Manager
! P.O. Box B >
'
L Killona,' Louisiana 70066
, [<
1
fl
RIV:C:MQPS.#f
IBarnes/cjg
(I Callan'glN D:DRP G SM
JLMil an
J
j
l-
(ilq/ph/89
'
l
4 /27/89 g h /g 89 I
i s
1 \
i
!, D ADO K O [U
G
o _____ ..!
m . ym ,
,
M k,:$
..
'
dii.;.!N( ?c d
( ( >
r. . %q -E
'#',
., ,
c-
'
i
w ' !{
's
,' , 3:1.; <
_u
,4
,
,; e; .., ./(
$
0t
, ;,y. .
)
'
hk, '
'
'
h $.h-(
+
, .
,
,
7y , .
o'
- ii ., x . ,
,a
i
,
.
- . . .m;.
lf J< D, Louisian'alPowe'r?&TLight Company ~ -2- r
'
< ,
.4 ,
- - -
,
. j
,
. . .
U
6 .. . .
., .. .. .. 9
yg. . ..LouisianaiPower,& Light Company i
E! V ,
LATTN: J^R.: F. Burski, Manager, Nuclear i
7 .. Safety & Regulatory Affairs i '
F 317cBaronne Street'- *
,
1 '
-
P.O. Box-60340!
b.. ..n =New' Orleans, Louisiana' 70160
'
,' 4: .
.,
G ,' Louisiana Power & Light' Company'-
' ATTN:t L.' W. Laughlin, Site; L3
.
..
Licensing; Support Supervisor. ' ' '
"P.O.) Box B r
[i m g7,
.
K111ona, Louisiana'.70066
'
.. + / Q~ .
% . Louisiana Power,& Light Company
-
g' ' ATTN: G.'M. Davis, Manager, Events
.
. Analysis Reporting & Response.:
s P.O. Box B >
'
Killona, Louisiana 70066
,' c. Middle Southl: Services-
ATTN: Mr. R.:T.4Lally
'
P.O. Box 61000
'
New Orleans, Louisiana 70161
'
E . .
,.
l Louisiana Radiation Control Program Director. ,
,,
bec'toDMB(IE01)'
bec distrib. by RIV: .
RRI . ,R. D.. Martin,.RA' ,',
SectionChief(DRP/A). .DRP ..
- '
.
RPB-DRSS- .. MIS System .
'ProjectEngineer(DRP/A) RSTS.0perator
'
RIV File DRS'
='
LD.Wiggir$ ton,NRR.ProjectManager(MS:.:13-D-18)-
1 LLisa Shea, RM/ALF"
i
'
- I. Barriesi
s
.I'l
$
$
s
. .
?[,
p-
.
. - - .
L -
1 . .>
8
.
k;
LOUISIANA
POWER & LIGHT/ 317NEW BARONNESTREET + P. O. BOX 60340
ORLEANS, LOUISIANA 70160 *
(504)595 3100
NNYsUNU
June 9, 1989
W3P89-3048
A4.05
QA
ti.S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, D.C. 20S55
~g Q %\f [S,3,
-
li
'-
s
Subject: Waterford 3 SES JUN I 51989 ..
Docket No. 50-382 ,
License No. NPF-38
NRC Inspection Report 89-11
'
O'l !
_
Gentlemen:
In accordance with 10 CFR Part 2.201, Louisiana Power & Light hereby submits
in Attachment 1 the response to the Violation identified in Appendix A of the
subject Inspection Report.
If you have any questions concerning this response, please contact T.J. Gaudet
at (504) 464-3325.
Very truly yours,
"
R.F. urski
Manager
Nur. lear Safet.y f: Regulatory Affairs
RFB:TJG:ssf
Attachment
cc: -R.DT Martin,4NRC Region IV
F.J. liebdon, NRC-NRR
D.L. Wigginton, NRC-NRR
NRC Resident Inspectors Office
E.L. Blake
W.M. Stevenson
c r> J r I !U W ~ *
~ O T V 0 ' ' "" " '
.
NS100265D
"AN EQUAL OPPORTUNITY EMPLOYER"
_ _ _ _ _ _ - _ - _ _ _ .
ilf
h .4 s. ,u
Attachment to
pg 7, : o. W3P89-3048
LiL ,
Page 1 of 4
H . ATTACHMENT 1
lE LP&L Response ' to ' the Violation Identified in Appendix A'-
of Inspection Report 89-11
VIOLATION NO. 8911-01
Inadequate Design Control
Criterion IIIzof Appendix B to'.10 CFR Part 50 states,'in'part, " Measures
ihall be established to assure that applicable regulatory requirements and
the design basis, as defined in 10 CFR 50.2 and as specified in the license
application, for those structures, systems, and components to which this
appendix applies are correctly translated into specifications, . drawings,
procedures,-and instructions.... The design control measures shall provide
for verifying or checking the adequacy of design, such as by the
performance of design . reviews, by the use of alternate or simplified
calculational methods, or by the performance of a suitable testing
program ..." This is implemented by the-licensee's approved Quality
Assurance Plan.
l .
..
.
Contrary to the above, the following examples of the failure to control the
facility design adequately were identified:
1. Containment sump recirculation valves' backup air supply accumulators
' were not designed or tested to ensure proper system operation for all
conditions postulated by the design basis.
2. Static uninterruptible power supply 3A-S was mo'dified by the addition
'
of a nonsafety-related load to the distribution panel without
accounting for the effects of load faults on the inverter operation.
.These examples are a Severity Level IV violation.
P".SPONSE
(1) Reason For The Violation
Example 1
The root cause of the deficiency cited in example I was an inadequate
review of design requirements for the noted air accumulators.
Safety injection sump recirculation isolation valves SI-602 A&B are
air actuated, safety-related valves that are required to be closed
during the safety injection phase and to open on a recirculation
actuation signal (RAS) during a design basis event. The Instrument
Air System (IA) normally positions the valves. In the event of a loss
of IA, air accumulators are provided to supply air to operate these
valves. The installation specifications for the SI-602 A&B
NS100265D
- _ _ _ _ _ _ _ _ - _ _ _ _
&) ' u
'
'
i
' ~
, n.1 y n Attachment to
. # 4, W3P89-3048
{
'
L* .
Page 2 of.4
'; .
1
accumulators were based on a large break loss of coolant accident'
(LOCA) with IA not available and a RAS generated within one hour.
~
'Accordingly,-the accumulators were designed to maintain sufficient .
pressure to perform their function for one hour. The accumulators j
were not reevaluated during construction to ensure that they were
adequately designed for the,small break LOCA. During a small break
LOCA scenario, the valves may be required to operate longer than one
hour after the IA supply is-compromised. (Small break 10CA's are.the
limiting accident for determining the_ length of time after a LOCA that .
the valves must be-able to function.)
)
The possibility that these valves may need to operate beyond the
existing one hour limit was identified _ during LP&L's evaluation of
Generic Letter 88-14, " Instrument Air Supply System Problems _Affecting )
Safety Related Equipment." Thus, in January, 1989, Problem
'
Evaluation /Information Request (PEIR) 10673 was generated to further
evaluate this concern.
On March 30, 1989 a Nonconformance Condition Identification (NCI
262265) was. issued to expedite the engineering evaluation. Then on
March 31, 1989, the situation was determined to be reportable as in
unanalyzed-condition that has existed since initial startup. (Note:
This information has been submitted to the NRC in LER-89-007 via LP&L-
Letter No.'W3A89-0129 dated 5/1/89.)
Example 2
The root.cause of the deficiency cited in example 2 was a design
inadequacy that occurred during the design phase of the Waterford 3
j
static uninterruptible power supplies (SUPSs). A brief discussion on
the d(sign is provided below. At this point, it is important to note !
that.the inadequate design relates to the design philosophy of the
SUPS that was originally established by the Waterford 3 Architect
Engineer and not to a deficiency in meeting the regulatory
requirements. l
l
Typicallyr SUPS design incorporates an automatic static transfer <
switch for instantaneous transfer to a bypass source in the event of a j
fanlt on the SUPS output or on feeder circuits. This bypass source 1
provides high current for tapid clearance of the faulted circuit. ;
During the design phase of the Waterford 3 SUPS, a conscientious j
decision had to be made on whether or not to install this automatic j
static transfer switch feature. At that time, the NRC and the i
industry identified several concerns with the operation of
cointerruptible power supplies (UPSs) (Reference: NRC (AEOD) Case l
Study Report - Operational Experience Involving Losses of Electrical
Inverters, December 1986). In particular, several failures of static
transfer switches had occurred due to problems with solid state
devices used in these switches. These failures led to degradation of
the inverter and/or the entire UPS system, and the reliability of the
static transfer switch was in question. Based on the these concerns,
there appeared to be no advantage in providing the automatic static
NS100265D
- 1
.
. *t4
.
Attachment to
'*
- . . W3P89-3048
Page 3 of 4
'
,
transfer switch for fast fault clearances. Accordingly, Waterford 3
(and some other PWRs) chose not to incorporate this feature into the
SUPS design.
The IE SUPS at Waterford 3 (3A-S and 3B-S which are manufactured by
Elgar Corporation) are 10 KVA safety-related power supplies that feed
power distribution panels (PDP) 390-SA and 391-SB, respectively. The
SUPS are required for normal operation of the plant and safe shutdown
during a design basis accident condition. The existing design feature
is such that a fault on any load feeder circuit with an instantaneous
demand of 165% full load amps will drive the ZA-S/3B-S SUPS into
shutdown condition for 0.5 seconds before driving it into the current
limiting mode. The protective devices on the feeder may not trip fast
enough to isolate the faulted circuit.
During a design basis accident, non-1E loads are postulated to fail in
an adverse manner. PDP 390-SA has a non-1E load (Telephone Cabinet
PEC 2) on Circuit No. 65. (Note: At that time, the Architect
Engineer considered communications to be a vital part of the plant and
therefore elected to make such a connection.) Thus, a failure of the
non-safety telephone cabinet during a design basis accident has the
potential to momentarily shutdown the 1E SUPS and degrade the Class IE
system.
The original understanding of the design was that upon the inception 4
of a fault, the SUPS would supply up to 150% full load amps and then '
go into current limiting mode. In the event that the current limiting
mode failed, the 165% shutoff limit would protect the inverter from
severe damage. This arrangement was considered a backup protective
feature. The fact that the SUPS could overshoot to the 165% shutoff
limit befor'e getting into the 150% current limiting mode condition was i
not obvious and only realized after the vendor was persistently
questioned.
There are four more Class IE SUPS at Waterford 3, which are of similar
design but different manufacture. These SUPS do not have the backup
shutoff feature. Consequently, as far as LP&L was concerned, the
connecting loads associated with the SUPS had no bearing on the
design.
(2) Corrective Steps That Have Been Taken And The Results Achieved
Example 1
A detailed engineering evaluation was performed to address this
concern as documented in NCI 262265. The results of the evaluation
(as amended on 4/20/89) indicated that adequate operating pressure in
the accumulators could be maintained for the limiting small break LOCA
(0.01 ft )2 in which a RAS is predicted to occur within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. A
NS100265D
- - - _
i
l'
.
'
..;.4
Attachment to
', . '
,
W3P89-3048
. Page 4 of 4
graph of required IA header pressure versus maximum allowable
accumulator pressure decay rate was developed. Operations issued
Standing Instruction 89-04 to establish IA operation based on the IA
header pressure graph. Until a permanent solution is implemented, the ;
IA system pressure will be monitored and controlled by Operations '
Standing Instruction 89-04.
Example 2
A Nonconformance Condition Identification (NCI 262261) was generated
on 3/30/89 to formally address and document corrective actions for the
potential loss of power condition for SUPS 3A-S during design basis
accident conditions.
On 3/31/89, Circuit No. 65 of PDP 390 was disconnected from SUPS 3A-S
at the local terminals in the cabinet. Temporary power from a
non-safety supply (PDP 3014 Circuit No. 5) was then provided to
telephone cabinet PEC 2 under a temporary alteration (TA 89-009).
All loads on PDP 390-SA and PDP 391-SB were reviewed to ensure that no
other non-1E loads existed.
(3) Corrective Steps Which Will Be Taken To Avoid Further Violations
Example 1
Station Modification Request (SMR) SI-007 has been issued to propose
several solutions to ensure long term operation of valves SI-602 A&B
after a LOCA with a simultaneous loss of IA.
PEIR 71128 has been initiated to review the design basis of the air
and nitrogen accumulators with respect to small break LOCAs.
Example 2
A deaign change will be implemented to make TA 89-009 a permanent
installation. (Note: Station Modification Request No. SMR ID-003 has
been generated to accomplish this task). Also, the drawings for PDP
390-SA and PDP 391-SB will be marked to ensure that non-1E loads are
not added to them in the future.
(4) Date When Full Compliance Will Be Achieved
Example 1
The design basis review of the accumulators is expected to be complete
by December 31, 1989. Permanent installation of one of the proposed
solutions of SMR SI-007 is expected by Refuel No. 4, at which time
LP&L will be in full compliance.
Example 3
The design change (DC 3180) and drawing revision are scheduled for !
completion by 12/31/89, at which time LP&L will be in full compliance. I
i
NS100265D l
_ _ _ - _ _ _ .