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Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments 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) 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl 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 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 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested 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 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 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 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 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 ML20209D8521999-07-0707 July 1999 Responds to Util 990706 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by TS 3.7.2, Auxiliary Electrical Sys. NOED Warranted & Approval Granted for Extension of Allowed Outage Time to 14 Days ML20209A8561999-06-25025 June 1999 Refers to Investigation Rept A4-1998-042 Re Potential Falsification of Training Record by Senior Licensed Operator at Arkansas Nuclear One Facility.Nrc Concluded That Training Attendance Record Falsified IR 05000313/19990071999-06-21021 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/99-07 & 50-368/99-07 Issued on 990514.Adequacy of Min Staffing Levels May Be Reviewed During Future Insps ML20196D4241999-06-21021 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp of License SOP-43716 Issued on 990325.Believes That NRC Concerns Have Been Adequately Addressed at Present ML20207H3551999-06-10010 June 1999 Forwards Insp Repts 50-313/99-05 & 50-368/99-05 on 990411-0529.No Violations Noted ML20195G3481999-06-0909 June 1999 Ack Receipt of ,Transmitting Changes to Facility Emergency Plan,Rev 25,under Provisions of 10CFR50,App E, Section V IR 05000313/19993011999-06-0909 June 1999 Discusses Arrangements for Administration of Licensing Exam During Wk of 991213,per Telcon of 990602.As Agreed,Exams Repts 50-313/99-301 & 50-368/99-301 Will Be Prepared Based on Guidelines in Rev 8 of NUREG-1021 ML20195F1631999-06-0808 June 1999 Forwards Insp Repts 50-313/99-06 & 50-368/99-06 on 990524-28.Violation Identified & Being Treated as Noncited Violation ML20207G3111999-06-0707 June 1999 Ack Receipt of Changes to ANO EP Implementing Prcoedure 1903.010,Emergency Action Level Classification,Rev 34 PC-2, Received on 981218,under 10CFR50,App E,Section V Provisions. No Violations Identified ML20207G7951999-06-0707 June 1999 Forwards Notice of Violation Re Investigation Rept A4-1998-042 Re Apparent Violation Involving Initialing Record to Indicate Attendance at Required Reactor Simulator Training Session Not Attended ML20207E7131999-06-0202 June 1999 Discusses EOI 990401 Request for Alternative to Requirements of Iwl for Arkansas Nuclear One,Pursuant to 10CFR50.55a(g)(6)(ii)(B) & ASME BPV Code Section XI & Forwards Safety Evaluation Accepting Proposed Alternative ML20207B9521999-05-26026 May 1999 Discusses GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. Staff Will Conduct Limited Survey in to Identify Sampling ML20207B4171999-05-24024 May 1999 Forwards Corrected Cover Ltr to Insp Repts 50-313/99-07 & 50-368/99-07 Issued 990514 with Incorrect Insp Closing Date ML20207A7771999-05-24024 May 1999 Forwards Insp Repts 50-313/98-21 & 50-368/98-21 on 981116-990406.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20206U4541999-05-17017 May 1999 Discusses Util & Suppl Re Changes to License NPF-06,App a TSs Bases Section.Staff Offers No Objection to These Bases Changes.Affected Bases Pages,B 202, B 2-4,B 2-7,B 3/4 2-1,B 3/4 2-3 & B 3/4 6-4,encl ML20206S4721999-05-14014 May 1999 Forwards Insp Repts 50-313/99-07 & 50-368/99-07 on 990426- 30.No Violations Noted.However,Nrc Requests That Util Provide Evaluation of Licensee Provisions to Maintain Adequate Level of Response Force Personnel on-site ML20207B4271999-05-14014 May 1999 Corrected Ltr Forwarding Insp Repts 50-313/99-07 & 50-368/99-07 on 990426-30.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program ML20206R4741999-05-13013 May 1999 Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC ML20206N7011999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206M7581999-05-11011 May 1999 Forwards SE Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 ML20206S1761999-05-11011 May 1999 Responds to Informing of Changes in Medical Condition & Recommending License Restriction for Senior Reactor Operator.No Change Was Determined in Current License Conditions for Individual ML20206N4161999-05-11011 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-related Logic Circuits, for Plant,Units 1 & 2 ML20206S4211999-05-10010 May 1999 Forwards Insp Repts 50-313/99-04 & 50-368/99-04 on 990228- 0410.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20206H1031999-05-0606 May 1999 Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407,to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheet & Results to Appropriate Individuals.Without Encl ML20206F0611999-04-29029 April 1999 Forwards SE Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205R6331999-04-20020 April 1999 Ack Receipt of Which Transmitted Rev 39 to ANO Industrial Security Plan,Submitted Under Provisions of 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined Changes Do Not Decrease Effectiveness of Plan ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP 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 ML20205M6881999-04-12012 April 1999 Forwards Safety Evaluation on Second 10-year Interval Inservice Insp Request Relief 96-005 ML20205L7711999-04-0909 April 1999 Forwards Insp Repts 50-313/99-03 & 50-368/99-03 on 990202- 17.No Violations Noted ML20205K7681999-04-0606 April 1999 Forwards RAI Re risk-informed Alternative to Certain Requirements of ASME Code 11,table IWB-2500-1 ML20205G8871999-04-0202 April 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 60 Days of Date of Ltr 1999-09-22
[Table view] |
See also: IR 05000313/1997013
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UNIT E D ST AT ES
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,[* 611 RYAN PLAZA drive.SuliE 400
AR LINGToN. T E XAS 760114064
September 5,1997
i
C. Randy Hutchinson, Vice President
Operations
Arkansas Nuclear One
Entergy Operations, Inc.
1448 S.R. 333
Russellville, Arkansas 72801 0967
SUBJECT: NRC INSPECTION REPORT 50-313/97 13; 50 368/97 13 AND NOTICE OF
VIOLATION AND NOTICE OF DEVIATION
Dear Mr. Hutchinson:
Thank you for your letters of July 28 and August 25,1997, in response to our letter,
Notice of Violation, and Notice of Deviation dated June 28,1997, and telephone call on
August 21,1997. Our review of your reply found it responsive to the concerns raised in
our Notice of Deviation.
However, with respect to your initial response to the Notice of Violation, we found your
statement that full compliance was achieved on June 2,1997, was not correct.
Specifically, Arkansas Nuclear One, Unit 1, Valves CA 61, CA 62, BW 2, and BW 3 had
not been tested. As a result of our telephone call on August 21,1997, during which we
requested clarification, you responded by letter dated August 25,1997, Your response
stated that the above four valves would be tested under a work plan to meet the quarterly
testing frequency, and that test ' procedures would be developed and implemented by
Ceptember 30,1997. It is our understanding that all other valves identified in the Notice
of Violation have been appropriately tested and found to be acceptab e. Please inform us if
our understanding is not correct.
We will review the implementation of your corrective actions during a future inspection to
determine that full compliance has been achieved and will be maintained.
Sincerely,
/
l[/
Arthur T, How 1 Ill, Director *
Division of Reactor Safety
Docket Nos.: 50 313; 50 368
License Nos.: DPR 51; NPF-6
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Executive Vice President
& Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286 1995
~ Vice President
Operations Support
Entergy Operatior.s, Inc.
P.O. Box 31995 i
Jackson, Mississippi 39286
Manager, Washington Nuclear Operations
ABB Combustion Engineering Nuclear
Power
- 12300 Twinbrook ?arkway, Suite 330 - 1
Rockville, Maryland 20852 ~
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County Judge of Pope County '
Pope County Courthouse
Russellville, Arkansas 72801
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Winston & Strawn
1400 L Street, N.W.
- Washington, D.C. 20005 3502
David D. Snellings, Jr., Director
Division of Radiation Control and -
Emergency Management
Arkansas Department of Health
4815 West Markham Street, Mall Slot 30
Little Rock, Arkansas 72205 3867
Manager.
Rockville Nuclear Licensing
Framatome Technologies
1700 Rockville Pike, Suite 525
. Rockville, Maryland 20852
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E Mail report to T. Frye (TJF)
E-Mail report to T. Hiltz (TGH)
E Mail report to NRR Event Tracking System (IPAS)
E Mail report to Document Control Desk (DOCDESK)
bec to DCD (IE01)-
bec distrib. by RIV:
Regional Administrator Resident inspector
DRP Director MIS System
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Project Engineer (DRP/C) DRS PSB
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August 25,1997
OCAN089707
U. S. Nuclear Regulatory Commission -
Document Control Desk
Mail Station OPl 17
Washington, DC 20555
Subject: Arkansas Nuclear One- Units 1 and 2
Docket Nos. 50-313 and 50 368
License Nos. DPR-51 and NPF-6
SupplementalResponse To
Inspection Report 50-313/97-13; 50-368/9713
Gentlemen:
'
On July 28,1997, Arkansas Nuclear One responded to the notice of violation identified during
the inspection of activities associated with the Inservice Testing Program (IST). The violation
pertained to the failure to include requirad ASME Code valves in the IST program and a
failure to verify the ability of other valves, tvhich were included in the IST program, to fulfill
their closed safety function.
The response stated that full compliance was achieved on June 2,1997, when the affected
valves had been successfully tested or proven operable with an operability assessm.ent.
Ilowever, following discussions with .the region and upon further review, it has been
determined that full compliance will not be achieved until the affected valves are included in
the IST program.
To demonstrate continued operability, each valve is scheduled to be tested before the end of
its quarterly test interval.
Unit I valves BW-4A, BW-4B, CA-61, CA-62, BW 2, and BW-3 will be tested under a work
plan to meet the quarterly testing frequency, If the special test developed under the work plan-
-is not satisfactorily completed, an assessment will be performed to determine continued
operability of the valves. The results of the work plan will be used to develop test procedures
by September 30,1997,'
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Test procedures for Unit 2 valves 2FP-31, 2FP-46, 2SW-56, 2SW-5'i, 2SW-62, 2SW 67,
2SW-138,- 2BS-1 A, and 2BS-1B have been developed and the quarterly tests scheduled.
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August 25,1997 .
OCAN089707 Page 2
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g Full compliance for the notice of violation will be achieved on September 3.,1997, when the
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test procedures for each of the valves are developed, implemented, and included in the IST
program.
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Very truly yours,
b^*pW-W
Dwight C. Mims
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Director, Licern'ng
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- U. S. NRC
August 25,1997 .
OCAN089707 Page 3
cc: Mr. Ellis W. Merschoff
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Regional Administrator
- U. S. Nuclear Regulatory Commission
RegionIV
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611 Ryan Plaza Drive, Suite 400
Arlington, TX 76011-8064
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NRC Senior Resident Inspector
Arkansas Nuclear One
1448 S. R. 333
RusselMlle, AR72801
Mr. George Kaln.an
, NRR Project Manager Region IV/ANO-1 & 2
U. S. Nuclear Regulatory Commission
NRR Mail Stop 13-H-3
- One White Flint North
! 11555 Rockville Pike
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Rockville, MD 20852
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10CFR2.201
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July 28,1997
OCAN079709
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U. S. Nuclear Regulatory Commission ' '
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Washington, DC 20555 y
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Subject: Arkansas Nuclear One k':kgl{;
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Docket Nos. 50-313 and 50-368 %v
License Nos. DPR-51 and NPF-6
Response to Inspection Report
50-313/97-13; 50-368/97-13
Gentlemen: '
Pursuant to the provisions of 10CFR2.201, attached is the response to the notice of violation
identified during the inspection activities associated with the. Inservice Testing Program and
the response to the notice of deviation identified during the inspection activities associated
with commitments to perform radiographic and ultrasonic examinations.-
Should you have questions or comments, please call me at 501-858-4601.
Very truly yours,
k'*fC*ir?fi
Dwight C. Mims
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Director, Nuclear Safety
DCM/RMC
Attachments
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U. S. NRC
, July 28,1997--
OCAN079709 Page 2 '
cc: Mr. Ellis W. Merschoff
Regional Administrator
U. S. Nuclear Regulatory Commission
Region IV -
611 Ryan Plaza Drive, Suite 400
.
Arlington, TX 76011-8064
NRC Senior Resident Inspector
Arkansas Nuclear One
P.O. Box 310
London, AR 72847
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Mr. George Kalman
NRR Project Manager Region IV/ANO-1 J. 2
U. S. Nuclear Regulatory Commission -
NRR Mail Stop 13-H-3
One White Flint North
11555 Rockville Pike
Rockville, MD 20852
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Attachment to
OCAN079709
Page 1 of 6
NOTICE OF VIDLATION
During an NRC inspection conducted on May 12 through June 5,1997, one violation of
NRC requirements was identified. In accordance with the " General Statement of Policy
and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed
below:
10 CFR 50.55a(f) requires inservice tests to verify the operational readiness of
pumps and valves, whose function is required for safety, to comply with the
requirements set forth in Section XI of the appropriate edition and addenda of the
AShE Boiler and Pressure Vessel Code.
Article RVV-1100 of the AShE Code provides the rules and requirements for
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. inservice testing to assess operational readiness of certain AShE Code Class 1,2,
and 3, valves which are required to perform a specific function in shutting down a
reactor to the cold shutdown condition or in mitigating the consequences of an
l accident.
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Article RVV-3000 in Section XI of the AShE Code specifies the type of tests to
be performed on each category of valve, and Subarticle IWV-3412(a) states that
valves are to be exercised to the position required to fulfill their function (i.e., open
or closed).
Contrary to the above, the following conditions were identified:
1.
Seven Unit 2 AShE Code valves, which had a safety function to open and
were required to be tested in accordance with Section XI of the AShE
Code, were not included in the inservice test program. The normally closed
Category B valves were located irt the service water piping which provides
makeup water to the spent fuel,ind were identified as: 2FP-31; 2FP-46;
2SW-56; 2SW-57; 2SW-62; 2SW-67; and 2SW-138.
2. Eight AShE Code valves (six in Unit I and two in Unit 2) that were in the
inservice test program, were not being tested or exercised to verify their
ability to fulfill their closed safety function. The Unit I valves were
identified as: BW-4A/4B (Borated Water Storage Tank Outlet Check
Valves); CA-61/62 (Sodium Hydroxide Storage Tank Outlet Check
Valves); and BW-2/3 (High Pressure Injection Pump Suction Check
Valves). The Unit 2 valves were identified as: 2BS-1A/lB (Refueling
Water Tank Outlet Check Valves).
This is a Severity Level IV violation (Supp'ement 1)(50-313;-368/9713-01).
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OCAN079709
Page 3 of 6
Response to Notice of Violation 50-313: 368/9713 01
, (1) Reason for the violation:
(
On May 19,1997, the inspector noted that the Unit 1 Borated Water Storage Tank
(BWST) Outlet Check Valves BW-4A and BW-4B were included in the inservice
test (IST) program; however, they were identified as having an open safety
function only. These valves are the first isolation valves, of dual isolation valves,
in paths from the emergency core cooling system (ECCS). Since these valves
were not identified as having a closed safety function, they were not being tested in
the closed position. ANO 2 check valves 2BS-1 A and 2BS-1B, ANO-2 Refueling
Water Tank (RWT) Outlet Check Valves were similarly identified.
. In response, a condition report was initiated. The condition report noted that prior
to 1993, IST testing of BW-4A and BW-4B consisted of valve disassembly and
manually moving the valve disk to the open and closed position per approvec' elief
requests. Additionally, four other ANO-1 valves were identified as not having a
closed safety function, yet were considered to be part of a dual isolation
configuration (CA-61, CA-62 - Sodium Hydroxide Tank Outlet Check Valves and
BW-2, BW-3 - High Pressure Injection Pump Suction Check Valves). Another
condition report action was initiated to determine if a similar condition existed on
ANO-2. As a result of further review, seven additional ANO-2 ASME Code,
safety-related, normally closed valves that have an open safety function, but were
not in the IST program, were identified. The identified valves were 2FP-31, 2FP-
46,2SW-138,2SW-56,2SW-57,2SW-62, and 2SW-67, all Category B valves in
the service water piping which provide makeup water to the spent fuel pool.
These valves, except those providing service water make-up tc. the spent fuel pool,
were previously identified for inclusion in the IST program. In the fall of 1996, an
independent review of the ANO-1 and ANO-2 IST basis documents was
performed. One of the observations made during the review was that ANO-1
valves, BW-2, BW-3, BW-4A, BW-4B, CA-61, and CA-62, had a closed safety
function. A procedure improvement form was provided to ANO-1 Operations to
inform them that the subject valves had a closed function and test procedures
needed to be developed. Additionally, another observation from the review
identified ANO-2 valves, 2BS-1A and 2BS-1B as having a closed function and
discussions with ANO-2 Operations were ongoing.
The root cause of 2BS-1 A, 2BS-1B, BW-2, BW-3, BW-4A, BW-4B, CA-61, and
CA-62 not being reverse flow tested in the IST program was the failure to
recognize the closed safety function that these valves perform, i.e., the second of
two valves need to complete a closed system. The root cause of the seven ANO-2
service water valves not being within the IST program was not recognizing that
these valves had a safety function that fell within the scope of the IST program.
However, flow verification and preventive maintenance activities are performed on
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Attachment to
OCAN079709
Page 4 of 6 -
the seven ANO-2 service water valves which has been considered to more
adequately assess the valve's condition than manually stroking the valve quarterly.
(2) Corrective actions taken and results achieved:
Check valves BW-4A, BW-4B,2BS-1A, and 2BS-1B were successfully tested to
demonstrate their ability to close.
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An operability assessment for valves CA-61, CA-62, BW-2, and BW-3 was
performed and the valves were determined to be operable based on recent
surveillance test information and periodic maintenance.
The ANO-2 service water valves, 2FP-31, 2FP-46, 2SW-138, 2SW-56, 2SW-57,
,2SW-62, and 2SW-67, were tested successfully prior to heat-up from ANO-2
refueling outage 2R12.
(3) Corrective stens that will be taken to prevent recurrence:
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Test procedures will be developed by September 30,1997, to test the identified
ANO-l&2 valves in accordance with the IST program.
A review of engineering standards HES-17, ANO-1 IST Program Bases
Document, and HES-18, ANO-2 ISTProgram Bases Document, will be pezformed
by December 1,1997. '
An assessment of the IST program for both units will be completed by December
1,1997.
The IST program will be evaluated to determine the need for additional reviews by
other departments of changes to the IST program. This action is scheduled to be
completed by December 31,1997.
(4) Date when full compliance will be achieved:
Full compliance was achieved on June 2,1997, when the affected valves had been
successfully tested or proven operable with an operability assessment.
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Att:chment to
OCAN079709
Page 2 of 6
NOTICE OF DEVIATION
During an NRC inspection conducted on May 12 through June 5,1997, one deviation
from a commitment was identified. In accordance with the " General Statement of Policy
and Procedure for NRC Enforcement Action," NUREG-1600, the deviation is listed
below:
Arkansas Power & Light Co., letter ICAN048501, "HPI/ Makeup Nozzle
Component Cracking," dated April 22, 1985, submitted a fmal report titled,
"B&W Owners Group Safe-End Task Force." The letter stated that
Recommendation 3 in the report had been incorporated into the Arkansas Nuclear
One Unit 1 inservice inspection plan.
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Recommendation 3 addressed the following nozzle conditions and the associated
nondestructive examination schedule:
Unrepaired nozzles were to be examined by radiography and ultrasonics during
each of the next five refueling outages, then every finh refueling outage
thereaner,
Nozzler with the new sleeve design were to be similarly examined during the first,
third, and finh refueling outages, then every fifth refueling outage thereaner.
Nozzles that were re-rolled were to be examined by radiography during each of
the next five refueling outages, then every finh refueling outage thereafter.
Contrary to the above,12 of the 14 committed radiographic and ultrasonic
examinations scheduled for the 4 nozzles between Refueling Outage 5 and
Refueling Outage 9 were not performed.
This is a Deviation (50-313/9713-02).
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Attachment to
0CAN079709
Page 5 of 6
Response to Notice of Deviation 50-313/9713 02
(1) Reason for the deviation:
In response to a concern that cracking could occur in the ANO-1 high pressure
injection / makeup nozzles (HPI/MU), Arkansas Nuclear One (ANO) committed to
perform augmented radiographic and ultrasonic examinations on these nozzles per
Babcock and Wilcox (B&W) recommendations in 1985. The augmented
examinations were included in the Inservice Inspection Program (ISI) and were
scheduled for performance during five consecutive refueling outages (IRS through
IR9) and then during each finh refueling outage thereafter (IRl4, IR19, etc.).
The radiographic testing was to ensure no gap existed between the thermal sleeve
and the safe end and to detect nozzle degradation. The ultrasonic testing was to
. detect cracking of the safe end and the adjacent pipe.
The augmented examinations were performed during IR5 (November 1982 - May
1983) and IR6 (October 1984 - January 1985) and only partially completed during
IR7 (Septembei 1986 - December 1986) due to program scheduling errors. The
augmented radiographic examinations scheduled for 1R8 (October 1988 -
December 1988) were cancelled due to ALARA concerns without first evaluating
the NRC commitment to perform the examinations.
In September 1989, ANO self-identified the failure to perform the augmented
examinations during IR7 and IR8 as previously committed to the Nuclear
Regulatory Commission (NRC). An evaluation was performed to determine if the
augmented examinations should be performed during a mid-cycle outage or to
delay inspections until IR9 scheduled for October 1990. The evaluation
concluded that since the previous augmented examination results were satisfactory
and since the nozzle thermal shields were visually inspected during 1R8 and found
to be intact, the augmented examinations could be delayed until IR9 (October
1990 - January 1991). The examinations performed during 1R9 were deemed
satisfactory.
In response to the April 21,1997, HPI nozzle leak at Oconee 1, ANO reviewed
radiographs and ultrasonic examinations performed during IR9 on the ANO-1
HPI/MU nozzles and determined that the anomaly (gap between the thermal sleeve
and safe end) that caused the Oconee leak was not present in the ANO-1 nozzles.
The examiners of the HPI/MU nozzle radiographs taken during past refueling
outages did not document whether or not gaps existed between the thermal sleeve
and the safe end area, even though the radiographs specifically depicted the
thermal sleeve / safe end area.
Based on the 1997 evaluation of the past HPI/MU nozzle radiographs and
ultrasonic examination test results ANO determined that additional augmented
examinations were unnecessary and that the examinations could be performed on
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Attachm:nt to
0CAN079709
Page 6 of 6
the five refueling outage frequency as previously committed. The augmented
examinations for the HPI/MU nozzles are currently scheduled to be performed
during IR14 (Spring 1998) and every fifth refueling outage thereafter.
Since 1989 when this deviation occurred, the ANO procedure revision process and
the ANO commitment management program has undergone several enhancements.
The current ANO procedure revision process requires that pending procedure
changes that alter or delete existing regulatory commitments be resolved per the
ANO commitment management program prior to implementing the change. The
ANO commitment management program is currently based on the Nuclear Energy
Institute's GuidelinesforManaging NRC Commitments. Commitment changes or
deletions are periodically reported to the NRC based on these guidelines.
(2) . Corrective actions taken and results achieved:
The ANO 1 ISI Program was revised to include specific criteria for examination of
the thermal sleeve to safe end area for gaps on the HPI/MU nozzles.
The ANO-1 ISI Program was reviewed to ensure that the required augmented
examinations had been scheduled on the five refueling outage frequency.
(3) Actions taken to avoid further deviations:
Actions completed to date should avoid further deviations in this area.
(4) Date when corrective actions will be completed:
Corrective actions were completed on May 2,1997, when the evaluation of the
HPI/MU nozzle radiographs taken during IR9 determined that there were no gaps
in the thermal sleeve to safe end areas.
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