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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:INCOMING CORRESPONDENCE
MONTHYEARML20217L0101999-10-18018 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 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 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 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 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 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 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-1999-010, 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 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 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 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 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 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos 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 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 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 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 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 ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits1999-06-24024 June 1999 Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits ML20196G5731999-06-24024 June 1999 Forwards Operator Licensing Exam Outlines Associated with Exam Scheduled for Wk of 991004.Exam Development Is Being Performed in Accordance with NUREG-1021,Rev 8 ML20212J4121999-06-23023 June 1999 Responds to NRC Re Reconsideration of EA 98-022. Details Provided on Actions Util Has Taken or Plans to Take to Address NRC Concerns with Ability to Demonstrate Adequate Flow Availability to Meet Design Requirements ML20196E9371999-06-22022 June 1999 Forwards Revs Made to EP Training Procedures.Procedures NTC-217 & NTC-217 Have Been Deleted.Procedure NTP-203 Was Revised to Combine Requirement Previously Included in Procedures NRC-216 & NTC-217 ML20196A1021999-06-17017 June 1999 Provides Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Per 990513 Request of NRC Project Manager ML20195F3671999-06-0909 June 1999 Forwards Rev 21,Change 0 to EP-001-010, Unusual Event. Rev Reviewed in Accordance with 10CFR50.54(q) Requirements & Determined Not to Decrease Effectiveness of Emergency Plan ML20195C7801999-06-0303 June 1999 Submits Response to Violations Noted in Insp Rept 50-382/99-08.Corrective Actions:All Licensee Access Authorization Personnel Were Retrained Prior to Completion of Insp ML20195C2951999-05-28028 May 1999 Forwards Annual Evaluation of Changes & Errors Identified in Abb CE ECCS Performance Evaluation Models Used for LOCA Analyses.Results of Annual Evaluation for CY98 Detailed in Attached Rept,Based Upon Suppl 10 to Abb CE Rept ML20195C0241999-05-28028 May 1999 Notifies NRC of Operator Medical Condition for Waterford 3 Opertaor Sp Wolfe,License SOP-43723.Attached NRC Form & Memo Contain Info Concerning Condition.Without Encls ML20196L3281999-05-24024 May 1999 Informs That Entergy Is Withdrawing TS Change Request NPF-38-205 Re TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection Submitted on 980629 ML20206S4691999-05-17017 May 1999 Requests Waiver of Exam for SRO Licenses for an Vest & Hj Lewis,Iaw 10CFR55.47.Both Individuals Have Held Licenses at Plant within Past Two Year Period,But Licenses Expired Upon Leaving Util Employment.Encl Withheld 05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.31999-05-14014 May 1999 Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3 ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J1471999-05-0606 May 1999 Requests That Implementation Date for TS Change Request NPF-38-211 Be within 90 Days of Approval to Allow for Installation of New Monitoring Sys for Broad Range Gas Detection Sys ML20206J1721999-05-0606 May 1999 Notifies That Proposed Schedule for Plant 1999 Annual Exercise Is Wk of 991013.Exercise Objective Meeting Scheduled for 990513 at St John Baptist Parish Emergency Operations Ctr ML20206G8021999-05-0404 May 1999 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-382/99-01.Licensee Denies Violation as Stated.Change Made Is Denoted by Rev Bar & Does Not Materially Impact Original Ltr ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20205T2531999-04-22022 April 1999 Forwards LER 99-S02-00,describing Occurrence of Contract Employee Inappropriately Being Granted Unescorted Access to Plant Protected Area ML20205R2611999-04-20020 April 1999 Forwards Rev 19 to Physical Security Plan,Submitted in Accordance with 10CFR50.54(p).Plan Rev Was Approved & Implemented on 990407.Rev Withheld,Per 10CFR73.21 ML20205Q3241999-04-16016 April 1999 Submits Addl Info Re TS Change Request NPF-38-215 for Administrative Controls TS Changes.Appropriate Pages from New Entergy Common QA Program Manual Provided as Attachment to Ltr 1999-09-07
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_ __ _ __ _.
g yggy Ente y Operations, Inc.
""' ** Kibona. LA 700060751 Tel 504 739 0660
, Mike Sellman ggni.owaims
- . I' W3F1-96-0033 A4.05 g PR July 17,1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 ;
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Request For Additional Information Regarding Technical Specification Change Request NPF-38-172 Gentlemen: ;
By letter dated November 7,1995, Waterford 3 proposed a change to Technical Specification (TS) 3/4.8.1 " Electrical Power Systems - AC Sources" and the 3 associated TS BASES. The NRC review staff requested additional,'nformation regarding the proposed changes to TS 4.8.1.1.2a.4, TS 4.8.1.1.2c, TS 4.8.1.1.2di, i and TS 4.8.1.1.2d 2. This information is included in the attached report entitled l
" Additional Inforrr.ation Regarding Technical Specification Change Request NPF-38-172" This additional information has no affect on the previously provided no significant hazards determination. However, the attached report also proposes to increase the pore size of the filters (from .8 to 3.0 microns) which are used during the performance of the testing which determines the level of Emergency Diesel Generator (EDG) fuel oil particulate contamination. A significant hazards determination for this change is provided in the attached report.
- /kLTl' 9607190202 960717 *-
DR ADOCK0500g2 10007G
Request For Additional Information Regarding Technical Specification Change Request NPF-38-172 W3F1-96-0033 Page 2 July 17,1996 Should you have any questions or comments concerning the additional information, please contact Robert Kullmann at (504) 739-6404.
Very truly yours, M m
k.L<fdL '
M.B. Sellman Vice President, Operations Waterford 3 R
. MBSIRTK/ssf .-
Attachment:
Affidavit Additional Information Regarding NPF-38-172 cc: L.J. Callan, NRC Region IV C.P. Patel, NRC-NRR R.B. McGehee - y N.S. Reynolds NRC Resident' inspectors Office Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers I
J
' l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION !
In the matter of ) l
)
Entergy Operations, incorporated ) Docket No. 50-382 )
Waterford 3 Steam Electric Station )
AFFIDAVIT i M.B. Sellman, being duly sworn, hereby deposes and says that he is Vice President, Operations - Waterford 3 of Entergy Operations, incorporated; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Additional Information Regarding Technical Specification Change Request NPF-38-172; that he is familiar with the content thereof; and that the matters set -
forth therein are true and correct to the best of his knowledge, information and
)
belief.
- j. A i M.B. Sellman Vice President, Operations Waterford 3 STATE OF LOUISIANA )
) ss PARISH OF ST. CHARLES ) 1 Subscribed and sworn to before me, a Notary Public in and for the Parish and State above named this 0"' day of J uc1 .1996.
hl&- S .-
Notary Public My Commission expires W ' "' " ' "
1 I
! ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST NPF-38-172 ,
- L l l
- 1. Item 4.8.1.1.2a.4 ,
The letter requesting additional information states that this proposed change is not consistent with Standard Technical Specifications (TS) which require a fast start test of the Emergency Diesel Generators (EDGs) once every 184 days. Another concern expressed in this letter was that the proposed change would delete the upper voltage and frequency limits of the diesel generator i fast start test acceptance criteria.
1 With regard to the concerns listed above, the NRC staff asked that Waterford l 3 explain: (a) why the proposed change does not contain a requirement to perform a fast start test of the diesel generators at least once every 184 days and why this requirement should not be included in the proposed change; (b) what, if any, trending of generator performance is used to identify or anticipate problems with the diesel generators; and (c) if closure of the '
generator output breakers is to be used to verify voltage and frequency limits, the frequency of calibration for the relays which provide diesel generator output breaker permissives and the calibration tolerances permitted in calibrating these relays. )
Response
(a) Upon further review, Waterford 3 has determined that a fast start test should be performed every 184 days and has modified the proposed amendment to require this testing. Waterford 3's )
original intent was to eliminate the 184 day fast loading ;
requirement and had interpreted Generic Letter (GL) 93-05 as ;
allowing both the 184 day fast start requirement and the 184 day fast loading requirement as not being necessary. This interpretation was anived at by comparing the current wording in TS 4.8.1.1.2a.5 and the wording in GL 93-05.
i (b and c) The NRC staff also expressed a concern with what was l perceived by the NRC staff as the elimination of the upper
- acceptance limit for the generator output voltage and frequency l during fast start testing in accordance with TS 4.8.1.1.2a.4.
The proposed amendment states that "the generator voltage :
and frequency shall be at least 3920 volts and 58.8 Hz within 10 seconds after the start signal" The upper voltage and frequency limits were eliminated from this statement. However, 1
this TS has also been revised to require the steady state voltage and frequency to be within the same limits currently in
,. e, this TS. This change was requested solely to clarify when the 10 second start time is satisfied. The values listed in the proposed amendment were conservatively chosen. The EDG l output breaker permissives are satisfied at lower values than l the values listed in the proposed amendment and on detection of a loss of offsite power, the EDG output breakers would close reenergizing the respective safety bus. Waterford 3 does not .
intend to use the closure of the output breakers to verify voltage I and frequency limits. The steaoy state upper limits for voltage and frequency have not been changed and will continue to be I
monitored. Therefore, the original intent of TS 4.8.1.1.2a.4 has not been changed by the proposed amer &ent and additional trending of EDG performance as a result of the proposed amendment is not warranted.
- 2. Item 4.8.1.1.2c The proposed amendment modified TS 4.8.1.1.2c to state " Maintain properties of new and stored fuel oil in accordance with the Fuel Oil Testing Program" and deletes all previous information and requirements in this section with the exception of the last sentence in subsection three as modified.
With regard to the information listed above, the NRC staff requested that '
Waterford 3 explain: (a) why the standard words " Verify fuel oil properties of new and stored fuel oil are tested in accordance with, and maintained within
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the limits of, the Fuel Oil Testing Program" were not used; (b) why a j requirement to test in accordance with the Fuel Oil Testing Program was not incorporated into the proposed change; and (c) why no completion times 1 were proposed to restore fuel oil total particulates to within limits (i.e., 7 days) 1 or other fuel oil properties to within limits (i.e., 30 days) similar to those contained in Standard Technical Specifications.
Response
(a and b) Waterford 3 believes that the wording in the proposed amendment meets the intent of the wording specified by the NRC staff. However, the proposed amendment has been modified to incorporate the recommended wording. The recommended wording specifically specifies testing in j accordance with the Fuel Oil Testing Program.
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1 (c) TS 4.8.1.1.2c currently does not contain the completion times specified in the Standard Technical Specifications. However,
,. e the proposed amendment has been modified to incorporate three new Action Statements. The first new Action Statement requires that new fuel oil properties found not to be within limits to be restored within limits within 30 days. The secord new i Action Statement requires that stored fuel oil total particulates !
that are not within limits to be restored within limits within 7 days. The third new Action Statement requires the affected l diesel generators to be immediately declared inoperable if either or both of the completion times of the other two Action Statements cannot be met. In addition, Administrative Controls section 6.8.4.h has been modified to also specify the required completion times listed above. Also, the last sentence of TS 4.8.1.1.2c.3 which states " Failure to meet this requirement shall i not affect diesel generator OPERABILITY; however, corrective action shall be initiated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to return the fuel oil i supply to within acceptable limits." has been deleted from the '
proposed amendment. These changes are consistent with the I Standard Technical Specifications. The current TS 4.8.1.1.2c requires a sample of fuel oil to be obtained and tested at least once per 92 days. The provisions of section 4 of the TS allows a i 25% deviation from the 92 day requirement. This allowance will also be applied to the once every 31 day testing j requirement for total particulate concentration specified in the proposed amendment.
- 3. Items 4.8.1.1.2d.1 and 4.8.1.1.2d.2 Technical Specification 4.8.1.1.2d.1 currently states in part "At least once per 18 months during shutdown by verifying the generator capability to reject a load of greater than or equal to 498 kw (HPSI pump).. " The proposed change would delete the reference to the HPSI pump. In addition, the proposed amendment would add "an indicated 4000" to the 18 month full load rejection test criteria in TS 4.8.1.1.2d.2.
The NRC staff expressed a concern that the proposed changes are not I consistent with Standard Technical Specification testing requirements which I
specify a power facter at which the load rejection tests should be performed.
With regard to the information listed above, the NRC staff requested that Waterford 3 provide: (a) a description of how these two load rejection tests will be performed in the future if the requested TS change is granted; (b) the amount of reactive load that will be rejected in order to verify proper 3
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operation of the voltage regulator and the bases for the amount chosen; and l
(c) a comparison of these future tests to tests performed in the past so that I
. any changes in the proposed testing method can be readily identified.
Response (a. b. c) '
i The intent of TS 4.8.1.1.2d.1 is to require the EDG to reject the largest single load while maintain:ng specific voltage and frequency constraints. In the past, Waterford 3 satisfied this TS by requiring the EDGs to successfully reject a HPSI pump while maintaining the specified voltage and frequency constraints. During a subsequent review of this TS, Waterford 3 personnel 3 determined that a HPSI pump only represents a load of 415 kw and that this load did not satisfy the requirements of this TS. Licensee Event Report (LER) 94-017-00 addresses this issue and was submitted to the NRC on December 21,1994. As a result, Waterford 3 personnel developed an alternate method of rejecting a load greater than or equal 498 kw. The alternate method of rejecting a load greater than or equal to 498 kw utilizes I an appropriate number of Dry and Wet Cooling Tower Fans. The proposed !
change would correct this TS by eliminating the reference to the HPSI pump and modify the BASES to clarify the 498 kw load rejection requirement. No '
changes to the actual load rejection requirement or the specified voltage and frequency constraints during the load rejection testing currently in the existing TS are being requested. In addition, the amount of reactive power required by the Dry and Wet Cooling Tower Fans is greater than the reactive power required by a HPSI pump during the performance of the load rejection ,
test specified by TS 4.8.1.1.2d.1. Therefore, the alternste test methodology 1 is more conservative than the previously performed test methodology. j Technical Specification (TS) 4.8.1.1.2d.2 currently requires the verification of the EDGs capability to reject a load of 4400 kw without tripping. This TS d does not currently specify an amount of reactive power to be rejected by the EDGs during the full load rejection test. The proposed change provides for a range (4000 kw to 4400 kw) to conduct this test. This revised loading range is intended to avoid inadvertent overloading of the EDGs. This inadvertent overloading creates unnecessary wear and mechanical stress that adversely affects the reliability and longevity of the diesel generators. Waterford 3 does not intend to change the test methodology for performing the full load rejection test. The current test methodology was developed in response to information Notice 91-13 " Inadequate Testing of Emergency Diesel Generators". Waterford 3 currently loads the EDGs with as much reactive power as is practical without exceeding the EDGs design specifications l during the performance of the full load rejection testing. The only change will be that a range for the real load rejected by the EDGs will be provided to i
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improve the EDGs reliability by reducing unnecessary wear and mechanical stress. Providing a range for the real load rejected is in accordance with the
,. S.tandard Technical Specifications.
- 4. KW Load of a HPSI Pumo and a Essential Chiller
- in reviewing the proposed amendment the NRC staff identified an apparent discrepancy in the kw load used to represent a HPSI pump and an Essential Chiller. Table 8.3.1, " Emergency Diesel Generator A Loading Sequence (Steady State)," of the Waterford 3 Final Safety Analysis Report (FSAR) lists the real load of a HPSI pump as 371.5 kw and that of an Essential Chiller as ,
416.37 kw. Page seven of the proposed amendment states these loads are 415 kw and 430 kw respectively.
The NRC staff requested that Waterford 3 explain the reason for the apparent discrepancy.
Response +'
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The kw values listed in the proposed amendment (415 kw for the HPSI pump and 430 kw for the Essential Chiller) represent maximum values for these two ;1
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loads. :These maximum load values would be obtained when the HPSI pump l and the Essential Chiller are supplying maximum output. This is not to be 4 confused with the maximum load the HPSI pump and the Essential Chiller >
would represent when supplying output for the specific events listed in FSAR Table 8.3.1 (i.e.,371.5 kw for the HPSI pump and 416.37 for the Essential Chiller operating after a Loss of Offsite Power concurrent with a Loss of Coolant Accident). 1 1
- 5. Particulate Test Filter Pore Size Increase !
Testing for particulates in EDG fuel oil will be performed as specified in i Administrative Controls section 6.8.4.h.3. This testing utilizes the process described in ASTM D2276-78, " Standard Test Methods for Particulate Contamination in Aviation Turbine Fuels". The basis of this surveillance process is that when a known amount of fuel oil is passed through a filter of known weight, particulates larger than the filter pore size will not pass l through the filter. The filter is then dried and reweighed to determine the mass of the trapped particulates. The mass of particulates per unit volume of fuel oil is verified to be within the acceptance criteria of 10mg/ liter. This proposed change does not involve a change to this 10mg/ liter limit, it only will ,
change the filter pore size.
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9 Particulate testing as described above does not actually reduce the level of particulate contamination present in the fuel oil because only a small amount
' of the fuel oil is passed through the test filter. The test does, however, provide an indication of fuel oil quality by providing information on the quantity of particulates present in the fuel oil which are larger than the test -
filter pore size.
The current filter pore size specified in ASTM D2276-78 is 0.8 microns. The proposed change would increase the filter pore size used during the testing from 0.8 microns to 3.0 microns. This proposed change would prevent the entrapment of particulates in the size range of 0.8 to 3.0 microns during the testing. Entrapment of particulates in this size range is unnecessary as the in-_line filters,' which are the final step in the fuel oil filtration process prior to the fuel oil entering the EDGs, currently only trap particulates above 15 microns in diameter. Waterford 3 will be replacing these in-line filters with filters that have pore size of 5 microns in the future per a recommendation
- from the vendor.
The proposed change has been previously reviewed and approved by the NRC for Peach Bottom Atomic Power Station Units 2 and 3 and the Limerick Generating Station Unit 1.
Safety Analysis The proposed increase of the filier pore size used during particulate testing of the EDG fuel oil from 0.8 microns to 3.0 microns will not adversely affect EDG
. operability. The use of a filter with a 3.0 micron pore size in lieu of a filter with a 0.8 micron pore size is acceptable since it more closely approximates the fuel oil filtration accomplished by the in-line filters during EDG operation. This increase in filter pore size will not result in harm to the fuel injectors or otherwise degrade diesel engine performance. Therefore, while a population of particulates between 0.8 and 3.0 microns would not be detected in the fuel oil as a consequence of using a larger
, test filter pore size, this is not of consequence because these particulates will pass into the diesel engine fuel injection system and subsequently into the diesel engine without any adverse consequences.
The proposed change described above shall be deemed to involve a significant hazards consideration if there is a positive finding in any of the following areas:
- 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No ,
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4 1 The proposed change will not result in an increase in the quantity of 4
particulates larger than 3.0 microns. The possible consequences of Implementing the proposed change could be an increase in the concentration of particulates in the 0.8 to 3.0 micron size range. Although particulates
- smaller than 3.0 microns will pass through the in-line fuel filtering system, i there will be no adverse consequences on the operability of the EDGs.
Accordingly, this change will not result in any increase in the probability of l any accident previously evaluated in Chapter 15, " Accident Analyses" of the Waterford 3 Final Safety Analysis Report. Therefore, the proposed increase in the test filter pore size does not involve a significant increase in the j probability or consequences of an accident previously evaluated.
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- 2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different type of accident from any accident previously evaluated. 'l I
l Response: No The proposed change is limited to the test filter pore size for determining the level of particulate contamination of the EDG fuel oil. This change will not affect the operability of the EDGs. The presence of particulates below the
- size of 3.0 microns are of no consequence in the operation of the EDGs.
l Since the proposed change only affects the concentration of particulates in
! the 0.8 to 3.0 micron size range, the proposed increase in the test filter pore size does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change does not result in an increased concentration of particulates larger than 3.0 microns. The only particulate sizes which can be j affected by this proposed change are those smaller than 3.0 microns. These size particulates will pass through the in-line filters but will not affect EDG operability; therefore, there is no significant reduction in a margin of safety.
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Safety and Sionificant Hazards Determination Based.on the above safety analysis, it is concluded that: (1) the proposed change d6es not constitute a significant hazards consideration as defined by 10CFR50.92; and (2) there is a reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC final environmental statement.
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