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MONTHYEARML20236D6121989-03-0808 March 1989 Advises That Util 881223 Response to Generic Ltr 88-17, Loss of DHR Appears to Meet Ltr Requirements for Expeditious Actions.Several Items to Be Considered to Assure That Actions Adequately Addressed Listed Project stage: Other 1989-03-08
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:NRC TO 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 ML20059K3601990-09-14014 September 1990 Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise 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 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 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 ML20247F2211989-09-0808 September 1989 Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62 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 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 ML20245L3311989-08-11011 August 1989 Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation 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 ML20247J8481989-07-27027 July 1989 Requests Util Address Encl Concerns Re 890321 Application for Amend to License NPF-38.Amend Would Replace Tech Spec on Control Room Air Conditioning Sys W/Four Specs on Air Filtration,Air Temp & Isolation & Pressurization ML20247K5751989-07-27027 July 1989 Forwards Insp Rept 50-382/89-20 on 890705.No Violations or Deviations Noted.One Unresolved Item Identified in Paragraph 2 of Encl Rept Re Review of Findings of Lab Failure Analysis & Licensee Planned Response Actions IR 05000382/19890071989-07-21021 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07.Requests Response Encompassing Issues Discussed in 890713 Telcon Re Violation 382/8907-02 ML20247L6931989-07-18018 July 1989 Forwards Insp Rept 50-382/89-17 on 890601-30 & Notice of Violation.Util Will Be Requested to Address Concerns on Administrative Guidance for Inoperable Support Sys Effect on Safety Sys Operability ML20247K6491989-07-17017 July 1989 Forwards Insp Rept 50-382/89-18 on 890626-30.Violations Noted.One Unresolved Item Identified in Paragraph 3 of Rept ML20246M9061989-07-14014 July 1989 Forwards Exam Rept 50-382/OL-89-01 Administered During Wk of 890515.All Candidates Passed Exams & Appropriate Licenses Issued 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
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_ _ _ _ _ - - - - - ______ __ _ _ - _ _ - _ _ - _ _ _ - _ _ _ __ _ _ -
n l' # o osag'o g UNITED STATES 8 n . NUCLEAR REGULATORY COMMISSION l
7; E .
WASHINGTON, D. C. 20555
/ March 8, 1989 Docket No. 50-382 Mr. J. G. Dewease Senior Vice President - Nuclear Operations l Louisiana Power and Light l 317 Baronne Street, Mail Unit 17
- New Orleans, Louisiana 70160
Dear Hr. Dewease:
SUBJECT:
COMMENTS ON THE LOUISIANA POWER AND LIGHT RESPONSE TO GENERIC LETTER 88-17 FOR THE WATERFORD UNIT 3 FOR EXPEDITIOUS ACTIONS FOR LOSS OF DECAY HEAT REMOVAL (TAC NO. 69791)
The NRC staff has reviewed the Louisiana Power and Light (LP&L) letter of December 23, 1988 to response to Generic Letter (GL) 88-17. We find that LP&L appears to meet the intent of the generic letter with respect to expeditious actions.
The LP&L response includes some indication on scheduling, however, all expeditions actions addressed by GL 88-17 are to be implemented in advance of any requirement for part loop operation. We note that the next anticipated requirement for part loop operation at Waterford 3 should not occur before the refueling outage in October 1989.
Your overall response is generally conplete and more detailed than the average response we have reviewed. However, in a few areas, your response is sufficiently vague that we cannot fully understand your actions taken in response to GL 88-17. You may wish to consider several observations in order to assure yourselves that the actions are adequately addressed:
- 1. You mention discussion of the Diablo Canyon event with operations personnel and training for specific mid-loop operation and cooldown/draindown with your staff. It is not specifically stated that maintenance personnel are also included. The item was intended to include all personnel who can affect reduced inventory operation and preventive as well as mitigative training.
- 2. Your training program includes a review of the previous Waterford mid-loop events of 7/86 and 5/88. There are also a number of other mid-loop events that occurred at other plants that would be beneficial for review such as Arkansas Nuclear One, Unit 1 (October 26,1988),
Surry Unit 2 (September 19,1988), and Sequoyah (May 23,1988).
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- 3. You have identified penetrations of concern in Section 3.1 as those "providing direct access from the containment atmosphere to the outside atmosphere...." However, we are concerned with all containment penetrations I that could cause a release (e.g., penetrations from the containment into a I fuel handling or auxiliary building). l
- 4. You have not addressed problems associated with remaining in containment j once boiling initiates with large openings in the RCS pressure boundary. l Loss of shutdown cooling (SDC) could lead to boiling in 30 minutes and core uncovery in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. ~ All personnel may have to. leave containment or don special gear 30 minutes after the loss because of steam inside of containment. If you are assuming 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in which to work inside containment, then this may require special equipment.
- 5. In your addressing of containment closure, no information is provided regarding how you will keep track of and control the many potential j openings which rey have tu be closed simultaneously. Your procedures and administrative controls should address this topic.
- 6. In Section 3.1.1 you have stated that'"if the RCS is open on the cold leg side due to a major disassembly or removal of an RCP, the pressure I increase in the upper plenum (hot side) will depress the water level in (
the core and the steam generator outlet pipe. This will force water out i of the RCS through the RCP opening." You further state that " vent paths '
are available but not credited to equalize pressure between the hot and cold sides of the RCS - e.g., leakage paths around the het leg nozzles and other in-vessel leakage paths." Although these paths exist, they provide minimal pressure equalization.
- 7. In Section 3.1.1 you state that if the RCS is closed and a steam generator !
(SG), initially at 70% wide range level for secondary side inventory, is !
available it should be able to cool for more than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> before boiling away the secondary side inventory (assuming no credit for makeup). You have not identified a requirement that SGs be maintained filled during mid- J loop nor is provision for SG steaming addressed. You do state that one SG .j will be available if SG maintenance is not being performed.. The dynamics j of steam boiling in the SG and the effects on the RCS temperature, pressure, ,
and level are not addressed although some assumption is made that the RCS pressure shall not exceed 35 psig.
The methods to be used for low pressure secondary side steaming to maintain RCS pressure less than 35 psig have not been discussed. Analyses and '
procedures should be in place which justify any methods you choose.
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- 8. In Section 3.1.1 you also stated that steam exiting the SG tubes.would be vented thrcugh the loop seal and condensed by water in the vertical' suction leg between the RCP and loop seal. We assume that you have l performed analyses which demonstrates this condensation process as well '
as determining the amount of water which would remain under various allowed system configurations.
- 9. In Section 3.3.1 you state that "The critical path to closing containment is closure of the equipment hatch." .You say that " Conservatively 2 ,
hours is needed to adequately close the hatch (closure can actually be l effected in 1-1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)." This is based on Figure 2 which shows the time after initiation of a loss of SDC by which containment' closure activities must begin, as a function of time after reactor shutdown.. Has the possibility of large quantities of steam in the containnient, from boiling l
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in the reactor with large openings in the RCS pressure boundary, been i factored into the time to close the equipment hatch? See also number 4 l above. '
- 10. In Section 5.1.1 you discuss the features of the refueling water level indicating system (RWLIS) for which a diagram is given in Figure 3. The l RWLIS system uses stainless steel piping and has narrow and wide range i pressure transinitters. As shown in Figure 3 these pressure transmitters l show a comion top on the drain line below hot leg #1 in the vicinity of l the shutdown cooling suction line. Also, the pressure transmitters share !
the common reference high point tap near the top of the pressurizer.
Therefore, if a comparison is made for a region where the wide and narrow range readings overlap, precautions must be taken in justifying the accuracy because of the dependence on common taps.
- 11. In Section 5.1.1, Figure 3, the RWLIS system shows downward slopes for the lower top horizontal runs but no slope is indicated for the upper top i
horizontal runs. It may not be practical for slopes.in the upper horizontal runs. However, there should be means addressed for insuring that there is no water in these upper reference legs. Also, Figure 3 a' shows closed valves RC-215A and RC-215 leading to the boron management
, system to which the lower reference leg for the RWLIS is connected to.
What would be the effect of opening these valves on the accuracy of the RWLIS readings?
- 12. In Section 5.1.2 the refueling level indication system (RLIS) is described as consisting of one inch rubber (ortac) tubing including a length of hardened tygon tube as a sight glass. The schematic is given in Figure 4. You state that the tubing runs from the bottom of hot leg
- 1 (from the same tap-off as the.RWLIS), through the sight glass, and into the top of the pressurizer. No mention is made of cross checks between the RLIS and RWLIS level systems. This would be desirable. However, since both have the same bottom tap, care would be needed to avoid a common error. You do mention the ability to check the RLIS level measurement where it overlaps a pressurizer level indication prior to draining below the pressurizer. There is no indication of a potential level problem if the pressurizer surge line is not empty and pressurizer
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.Mr. J. G. Dewease -
air pressure is not equilibrated with the remainder of the RCS. Also, you later indicate in Section 5.1.3 a check against the HJTC system at several discrete elevations which is desirable as a cross check.
- 13. Figure 4 of Section 5.1.2 shows clear hose below the level of the hot
. leg. You indicate that there is a wide range of measurement from the bottom of the hot leg to'an elevation overlapping the bottom of the pressurizer. It is not clear what you consider the actual lower end of the range. A value below the bottom of. hot leg would be misleading.
- 14. In Section 5.1.2 you mention that the rubber hose for RLIS is rated for a l working pressure of 300 psig at.180*F and the. sight glass is rated for a working pressure of 15 psig at 180'F. If the system were to reach 1 boiling, it would appear that these. properties would not be sufficient. 1
- 15. Walking the rubber /tygon tube following installation to verify lack of kinks or loop seals is necessary.. Experience shows that periodic 'l walkdowns are needed after installation. We recontend daily walkdowns )
when the rubber /tygon tube is in use, with an additional walkdown immediately prior to its being placed in use. -Your preventive training for all affected personnel should address this, as well as procedures, to avoid the reoccurrence of the May 1988 events.
- 16. The HJTC method for level measurement is described.in Section 5.1.3 with a schematic showing the eight discrete elevations for a probe in Figure 1
- 5. You state that two independent and redundant probe assemblies are installed. Three of the elevations are located at heights approximately equivalent to the bottom, middle and top of the hot leg. This system is only effective for reduced inventory _ conditions'when the reactor vessel head is in place and the HJTC instrumentation is connected. You state.
that the HJTC system can be utilized for cross checks with the RWLIS and RLIS systems within the resolution capability of the HJTC system and that the sensor located at the hot leg centerline provides some indication of potential LPSI pump cavitation. Also, you indicate that the HJTC can be used as a backup in the event of the loss of the other level measurement l
capability. The HJTC should never be used as the primary level detection i system. The HJTC uses discrete points which are too widely separated to be useful for lowered inventory operation in any capacity other than for cross checking of other instruments.
- 17. In Section 5.2 you discuss the November 1988 draindown in which you state that the RLIS and HJTC systems-were designated as the primary level measurement instruments. The RWLIS system was available but undergoing further acceptance tests. The operators were instructed to predicate any l actions based on the lowest level indicated by the RWLIS/RLIS/HJTC embination which is a good conservative approach. This instruction H ould be part of the procedures and/or-training.
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Mr. J. G. Dewease
- 18. In Section 5.3 you state that you are evaluating the degree of independence of the RWLIS and RLIS systems sir ce they have a common tap-off from the RCS hot-leg. We will accept a common tap for instrument systems which have alreaoy been installed. You also state that you are making an evaluation to de:termine the extent to which the RLIS system, a rubber.
hose /tygen tube sight glass combination, can be crdited in the long term.
Rubber hose /tygon tube will not be acceptable for the long tenn instru-mentation needs. For the long term enhancements and because you have common taps for the RLIS and RWLIS, provision should be made for testing the taps before each use to assure they are open and free of restrictions.
- 19. In Section 7.3 'ycu state that when in a reduced inventory condition that 2 of the 3 HPSI pumps will bE operable and available for hot and Cold leg injection in addition to the SDC (LPSI) pumps. Also you state that "While the SDC pump may be unavailable for SDC purposes (e.g., pump cavitation, inadvertent SDC valve isolation, etc.) the pump will.still function to restore RCS level through an alternate valve lineup and appropriate sthrtup procedure." You indicate that OP-901-046 will be amended to credit a LPSI (SDC) pump as a second alternate means of RCS addition..
This is not responsive to GL 88-17 ff this action is taken for alternate lineup after one of the SDC pumps fails since a failure due to vortexing of one LPSI pump could easily affect the other LPSI pump. However, if the second LPSI pump is aligned up as a second available means before entering a reduced inventory condition it would be acceptable. Alternately it !
would be desirable to have other sources of'RCS water make-up pumps lined i up in preparation for SDC purposes if effective. . ;
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- 20. In Section 8.2.1 (page 24) related to nozzle dams you stcte that "if a l steam generator was not blocked or did not have a manway onn it was assumed to be available as a heat sink for steam condensation." There is no follow-up in your discussion to indicate that there would be provisions for making sure water was in the SG and that steam could be relieved on the secondary side (see Item 7). A steaming path is mentioned later on page 25 but the means are not previoed.
- 21. In Section 8.2.1 you mention a review in which a pressurizer manway (a i relief area of 1.40 ft2) is open. We note that relatively large hot side I openings in the RCS, such as a presurizer manway, can still lead to a I pressure of several psi. The large steam flow rate in combination with I flow restrictions in the surge line and lower pressurizer hardware may j lead to pressurization. A: curate calculations should be performed to l verify the effectiveness of the opening.
- 22. It is noted that in many of your responses you have a section called "Long-Range Expeditious Actions." The Generic Letter 88-17 does not have such a category in expeditious actions. .As we not9d above, all expeditions actions should be impleniented in advance of arty requirement for part loop operation.
Mr. J. G. Dewease- 23. You appear to be attempting to work within existing technical specifications in meeting the. generic letter recommendations. We note that technical specification changes will be considered if existing specifications are f overly restrictive. I There is no need to respond to the NRC on the above observations at this-time.
As you are aware, the expeditious actions you have described are an interim !
measure to achieve an imediate reduction in risk associated with reduced .
inventory operation, and these will be' supplemented and in some cases replaced -l by programmed enhancements. We intend to audit both your resp')nse to the i expeditious actions and your programmed enhancement program. The areas where we do not fully understand your responses as indicated above may be covered in the audit of expeditious actions.
If there are any questions on the above observations or the intent of GL 88-17 and expected actions, please let us know. ;
Sincerely, ORIGINAL SIGilED BY JOSE A. CALVO Jose A. Calvo, Director i Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: See next page DIST'tIBUTION DE ket File NRT. PDR Local PDR PD4 Reading G. Holahan ,
L. Rubenstein l J. Calvo l P. Noonan ;
D. Wigginton J OGC-Rockville i E. Jordan i B. Grimes H. Balkujian, SRXB W. Hod , SRXB ACRS (
PD4 Plant File !
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MEMO CALV,0 WATERFORD GL8817 PD4/L/$ Q PD4/PM SRXB PD4/D PNo Wi DWi inton:bj WHod es. JCalvo !
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4 Mr. J. G. Dewease . i
- 23. You appear to be attemrtfvi to work within existing technical specifications l in meeting the generic 1+b,er recommendations. We note that technical i specification changes will be considered if existing specifications are overly restrictive.
There is no need to respond to the NRC on the above observations at this tirne.
As you are aware, the expeditious actions you have described are an interim measure to achieve an imediate reduction in risk associated with reduced i inventory operation, and these will be supplemented and in some cases replaced i by programmed enhancements. We intend to aucit both your response tc the i expeditious actions and your programed enhancement program. The areas where we do not fully understand your responses as indicated above may be covered in l the audit of expeditious actions.
, If there are any questions on the above observations or the intent of GL 88-17 l and expected actions, please let us know.
Sincerely, l 4 6- laka
'f Jose A. Calvo, Director Project Directorate - IV i
i Division of Reactor Projects - III, I IV, V and Special Projects Office of Nuclear Reactor Regulation cc: See next page
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Mr. Jerrold G. Deweas~e Waterford 3 Louisiana Power & Light Company cc:
W. Malcolm Stevenson, Esq. Regional Administrator, Region IV Monroe & Leman U.S. Nuclear Regulatory Comission !
1432 Whitney Building Office of Executive Director'for New Orleans, Louisiana 70103 Operations 611 Ryan Plaza Drive, Suite 1000 Mr. c. Blake Arlington, Texas 76011 e She.., Pittman, Potts & Trowbridge l 2300 N Street, NW Mr. William H. Spell, Administrator, Washington, D.C. 20037 Nuclear Energy Division Office of Environmental Affairs Resident Inspector /Waterford NPS Post Office Box 14690 Post Office Box 822 Baton Rouge, Louisiana 70898 Killcna, Louisiana 70066 .j Mr. Ralph T. Lally President, Police Jury l Manager of Quality Assurance St. Charles Parish Middle South Services, Inc. Hahnville, Louisiana 70057 Post Office Box 61000 j New Orleans, Louisiana 70161 l Chairman William A. Cross Lcuisiana Public Service Comission Bethesda Licensing Office One American Place, Suite 1630 3 Metro Center Baton Rouge, Lcuisiana 70825-1697 Suite 610 Bethesda, Maryland 20814 :
Mr. R. F. Burski j Nuclear Safety and Regulatory Affairs Manager Louisiana Power & Light Company 317 Baronne Street ..
New Orleans, Louisiana 7011c j l
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