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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20196E6931999-06-22022 June 1999 Forwards Corrected Ltr Re Changes to Rev 19 to Emergency Plan.Original Ltr Had Error in Subject Line ML20196E0831999-06-21021 June 1999 Forwards Insp Rept 50-382/99-12 on 990524-27.No Violations Noted.Purpose of Insp Was to Conduct Assessment of Emergency Preparedness Program ML20196D9941999-06-18018 June 1999 Forwards Insp Rept 50-382/99-11 on 990524-28.No Violations Noted ML20195J8091999-06-17017 June 1999 Forwards Safety Evaulation Re First 10-yr Interval Inservice Insp Relief Request for Plant,Unit 3 ML20196C8711999-06-15015 June 1999 Discusses Insp Rept 50-382/99-08 & Forwards Notice of Violation Re Unescorted Access Which Was Mistakenly Granted to Individual Whose Background Investigation Indicated That He Had Failed Prior Drug Screening with Another Employer ML20196F3721999-06-0909 June 1999 Corrected Ltr Forwarding Rev 19 to Emergency Plan ML20195G3711999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981223,which Transmitted Waterford 3 Steam Electric Station Emergency Plan,Rev 24,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20207E8541999-06-0303 June 1999 Forwards SE Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressurizer Safety Valves at Plant,Unit 3 ML20207G3441999-06-0303 June 1999 Forwards Insp Rept 50-382/99-09 on 990411-0522 & Notice of Violation.One Violation Identified & Being Treated as Noncited Violation C ML20207D3771999-05-27027 May 1999 Ack Receipt of 990401 & 0504 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-01 on 990303 ML20207A5121999-05-24024 May 1999 Refers to Which Responded to NOV & Proposed Imposition of Civil Penalty Sent by .Violations A,B & E Withdrawn & Violations C & D Changed to Severity Level IV ML20206U7851999-05-18018 May 1999 Forwards Insp Rept 50-382/99-06 on 990405-09.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML20206N6961999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S4411999-05-10010 May 1999 Forwards Insp Rept 50-382/99-05 on 990228-0410.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3841999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamental Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam,With Answer Key,Encl for Info.Without Encl ML20206K0951999-05-0606 May 1999 Discusses Insp Rept 50-382/99-08 Issued 990503 Without Cover Ltr Documenting EA Number & Subject Line Indicated NOV Which Was Incorrect.Corrected Cover Ltr Encl ML20206F4701999-05-0303 May 1999 Forwards Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Re Failure to Review & Consider Derogatory Access Authorization Background Info as Required by PSP Identified & Being Considered for Escalated Enforcement Action ML20206K1211999-05-0303 May 1999 Corrected Cover Ltr Forwarding Insp Rept 50-382/99-08 on 990405-07.One Violations Noted & Being Considered for Escalated EA ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M0561999-04-0909 April 1999 Forwards Insp Rept 50-382/99-04 on 990301-19.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20205J8781999-04-0505 April 1999 Forwards Insp Rept 50-382/99-02 on 990117-0227.No Violations Noted.Inspectors Determined That Six Violations Occurred & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20205J0901999-04-0202 April 1999 Informs That Info Submitted by & 970313 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) ML20205A4681999-03-26026 March 1999 Forwards Insp Rept 50-382/99-03 on 990308-12.Two Violations of Radiation Protection Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205A6141999-03-25025 March 1999 Forwards SE Accepting Request to Use Mechanical Nozzle Seal Assemblies (Mnsas) as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Application at Plant,Unit 3 ML20205F3311999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Plant,Unit 3 PPR Review,Which Was Completed on 990211.Performance at Plant,Unit 3 Was Acceptable ML20204E4941999-03-17017 March 1999 Discusses TSs Bases Change Re 3/4.4.1,3/4.6.1.7,3/4.6.3, 3/4.7.12 & 3/4.8.4.Forwards Affected Bases Pp B 3/4 4-1, B 3/4 6-3,B 3/4 6-4,B 3/4 7-7 & B 3/4 8-3 ML20207F1251999-03-0303 March 1999 Forwards Insp Rept 50-382/99-01 on 990125-29 & 0208-12 & Notice of Violations ML20203H8501999-02-17017 February 1999 Forwards SE Accepting Licensee 970701 Submittal of Second Ten Year ISI Program & Associated Relief Request for Plant, Unit 3.Nine Relief Requests Had Been Authorized Previously & Proposed Alternatives Remain Authorized ML20203D7211999-02-11011 February 1999 Forwards Request for Addl Info Re Licensee 970317 & 990111 Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Response Should Be Provided within 60 Days 1999-09-09
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_, ,. ._-. - - - - .- - - - - - - - - - - - - -
Mr. Chirl:s M. Dugg:r Februtry 11, 1999
- Vics President Op: rations i Entergy Operations, Inc. 4 P. O. Box B ;
Killona, LA 70066 '
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC ,
LETTER (GL) 96-05 PROGRAM AT WATERFORD STEAM ELECTRIC -
STATION, UNIT 3 (TAC NO. M97117) ;
Dear Mr. Dugger.
On September 18,1996, the Nuclear Regulatory Commission (NRC) issued GL 96-05,'
" Periodic Verification of Dasign-Basis Capability of Safety-Related Motor-Operated Valves," to j request that nuclear power plant licensees establish a program, or ensure the effectiveness of an existing program, to verify on a periodic basis that safety-related motor-operated valves (MOVs) are capable of performing their safety functions within the licensing basis of the plant.
On March 17,1997, and January 11,1999, you submitted responses to GL 96-05 indicating the intent to implement the provisions of a Joint Owners Group (JOG) program on MOV Periodic Verification. Participation in the JOG program provides a benefit in reactor safety by licensees sharing expertise and information on MOV performance and minimizes the information needed ;
by the NRC staff to review your response to GL 96-05. As a result of your commitment, the NRC staff requires only limited information to complete its GL 96-05 review for Waterford !
Steam Electric Station, Unit 3 (Waterford 3). l Enclosed is a request for additionalinformation regarding the GL 96-05 program at Waterford 3. The additionalinforrnation needed by the staff and the schedule to provide this information was discussed with your staff in a conference call on January 28,1999. You are requested to provide your response within 60 days of the receipt of this letter.
Sincerely, ORIGINAL SIGNED BY:
Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation l Docket No. 50-382 (
3
Enclosure:
As stated cc w/ encl: See next page i DISTRIBUTION:
gameutdilla PUBLIC PD4-1 r/f OGC C. Patel J.Hannon C.Hawes ,
i K. Brockman, RIV E. Adensam (EGA1) ACRS ,
I Document Name: RAl97117.WPD D OFC PM/PD4-1,s LA/PD4-1 PD/Pb-1 ,
NAME CPate CHaN JHannon
! DATE 1 /I /99 M/ $ /99 /99 COPY ,N/NO YES/NO hO
, , , , ,, f OFFICIAL RECORD COPY /
- /"$i L w] h',di %f l' 9902160311 990211 PDR ADOCK 0500 2 f{[ h g .'44e l
m erg p k,. UNITED STATES j
2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 p%;'*****/ February 11, 1999 Mr. Charles M. Dugger Vice President Operations
- Entergy Operations, Inc.
P. O. Box B Killona, LA 70066
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER (GL) 96-05 PROGRAM AT WATERFORD STEAM ELECTRIC STATION, UNIT 3 (TAC NO. M97117)
Dear Mr. Dugger:
On September 18,1996, the Nuclear Regulatory Commission (NRC) issued GL 96-05,
" Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves," to request that nuclear power plant licensees establish a program, or ensure the effectiveness of an existing program, to verify on a periodic basis that safety-related motor-operated valves (MOVs) are capable of performing their safety functions within the licensing basis of the plant.
On March 17,1997, and January 11,1999, you submitted responses to GL 96-05 indicating the intent to implement the provisions of a Joint Owners Group (JOG) program on MOV Periodic Verification. Participation in the JOG program provides a benefit in reactor safety by licensees sharing expertise and information on MOV performance and minimizes the information needed
- by the NRC staff to review your response to GL 96-05. As a result of your commitment, the NRC staff requires only limited information to complete its GL 96-05 review for Waterford Steam Electric Station, Unit 3 (Waterford 3).
Enclosed is a request for additional information regarding the GL 96-05 program at Waterford 3. The additionalinformation needed by the staff and the schedule to provide this information was discussed with your staff in a conference call on January 28,1999. You are requested to provide your response within 60 days of the receipt of this letter.
Sincerely, Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
As stated cc w/ encl: See next page 1
~
Mr. Charles M. Dugger Entergy Operations, Inc. Waterford 3 cc:
Administrator Regional Administrator, Region IV Louisiana Radiation Protection Division U.S. Nuclear Regulatory Commission Post Office Box 82135 611 Ryan Plaza Drive, Suite 1000 Baton Rouge, LA 70884 2135 Arlington, TX 76011 Vice President, Operations Resident inspector /Waterford NPS Support Post Office Box 822 Entergy Operations, Inc. Killona, LA 70066 P. O. Box 31995 Jackson, MS 39286 Parish President Council St. Charles Parish Director P. O. Box 302 Nuclear Safety & Regulatory Affairs Hahnville, LA 70057 Entergy Operations, Inc.
P. O. Box B Executive Vice-President Killona, LA 70066 and Chief Operating Officer Entergy Operations, Inc.
Wise, Carter, Child & Caraway P. O. Box 31995 P. O. Box 651 Jackson, MS 39286-1995 Jackson, MS 39205 Chairman General Manager Plant Operations Louisiana Public Service Commission Entergy Operations, Inc. One American Place, Suite 1630 P. O. Box B Baton Rouge, LA 70825-1697 i Killona, LA 70066 l l
Licensing Manager Entergy Operations, Inc.
P. O. Box B l Killona, LA 70066 '
Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005 3502 i
I
O REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE OF WATERFORD STEAM ELECTRIC STATION, UNIT 3 TO GENERIC LETTER 96-05
- 1. In the Nuclear Regulatory Commission (NRC) Inspection Report No. 50-382/94-23, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at Waterford Steam Electric Station, Unit 3 (Waterford 3)in response to Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance," based on the results of the inspection and the licensee's commitment to resolve outstanding MOV issues as described in a letter dated November 11,1994. In the inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term. For example, the inspectors noted that (1) the licensee agreed to update thrust calculations to include load sensitive behavior and stem friction coefficient test results that exceeded assumed values; and (2) the licensee's trending program was rudimentary and required additional enhancements. In addition to the NRC inspection report items, the licensee committed in its November 11,1994, letter to take specific actions, including updating its Planning Information Guide Notebook (PIGN) to identify maintenance activities that would require performance of a post-maintenance differential pressure test. The licensee should describe the actions taken to address the specific long-term aspects of the MOV program at Waterford 3 noted in the NRC inspection report and its letter dated November 11,1994.
- 2. In a letter dated March 17,1997, the licensee stated that it is participating in the Joint Owners Group (JOG) program on MOV Periodic Verification in response to GL 96-05.
On August 6,1997, the Combustion Engineering Owners' Group submitted Revision 2 of Topical Report MPR 1807 on the JOG program on MOV Periodic Verification. On October 30,1997, the NRC staff completed a safety evaluation concluding that the JOG program is an acceptable industry-wide response to GL 96-05, with certain conditions and limitations. The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee. In its letter dated March 17,1997, the licensee stated that static diagnostic testing would be based, in part, on an expert review and the Probabilistic Safety Assessrnent (PSA) for Waterford 3. The licensee should describe its methodology used for risk ranking MOVs at Waterford 3 in more detail. Although Waterford 3 is a pressurized water reactor (PWR) designed by Combustion Engineering, the licensee could obtain insights from the methodologies for MOV risk ranking provided by the Boiling Water Reactor Owners' Group (BWROG) in Topical Report NEDC 32264 (Revision 2, dated September 1996) and by the Westinghouse Owners Group (WOG) in Engineering Report V-EC-1658-A (Revision 2, dated August 13,1998), and the NRC safety evaluations on the BWROG and WOG methodologies dated February 27,1996, and April 14,1998, respectively. For example, key aspects of the BWROG and WOG methodologies are the comparison of the licensee's MOV risk-ranking results to a sample list of MOVs identified as high risk at other plants designed by the applicable Nuclear Steam System Supplier, and the determination of the bases for differences in the MOV rankings.
- 3. The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30,1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV ENCLOSURE
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- motor actuator and its potential degradation. The licenses should describe the plan at Waterford 3 for ensuring adequate ac and de MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its l Supplement 1. -
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