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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] |
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Docket Nos. 50-313
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50-368 License Nos. DPR-51 NPF-6 J Entergy Operations, In ATTN: J. W. Yelverton, Vice President 1 Operations, Arkansas Nuclear One Route 3, Box 137G Russellville, Arkansas 72801 Gentlemen:
SUBJECT: NRC INSPECTION REPORT NO. 50-313/92-11; 50-368/92-11 (NOTICE OF VIOLATION)
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Thank you for your letter, dated December 7, 1992, in response to our letter, dated November 25, 199 We have no further questions at this time and will review your .arrective actions during a future inspectio
Sincerely,
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A. Bill Beach, it ct r DivisionofRea.orPo')ects cc: ,
Entergy Operations, In !
ATTN: Donald C. Hintz, President &
Chief Operating Officer P.O. Box 31995 Jackson, Mississippi 39286 Entergy Operations, In ATTN: John R. McGaha, Vice President Operations Support P.O. Box 31995 Jackson, Mississippi 39286
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Entergy Operations, In i
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Wise, Carter, Child & Caraway l
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ATTN: Robert B. McGehee, Es !
P.O. Box 651 Jackson, Mississippi 39205
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Entergy Operations, Inc.
ATTN: R. A. Fenech, General Manager Plant Operations Route 3, Box 137G Russellville, Arkansas 72801
- Entergy Operations, Inc.
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ATTN: James J. Fisicaro 1 Director, licensing i Route 3, Box 137G i
Russellville, Arkansas 72801 Honorable Joe W. Phillips
. County Judge of Pope County
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Pope County Courthouse Russellville, Arkansas 72801 l Winston & Strawn
- ATTN: Nicholas S. Reynolds, Esq.
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1400 L Street, Washington, Arkansas Department of Health
, ATTN: Ms. Greta Dieus, Director Division of Radiation Control and Emergency Management 4815 West Markham Street Little Rock, Arkansas 72201-3867 B&W Nuclear Technologies ATTN: Robert B. Borsum Licensing Representative-1700 Rockville Pike, Suite 525
- Rockville,-Maryland 20852 Admiral Kinnaird R. McKee, USN (Ret)
214 South Morris Street Oxford, Maryland 21654
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Entergy Operations, In ABB Combustion Engineering Nuclear Power ATTN: Charles B. Brinkman Manager, Washington Nuclear Operations
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12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852
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Entergy Operations, In DEC I 51992 l
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bec to DMB (IE01)
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bec distrib, by RIV:
J. L. Milhoan Resident Inspector DRP Section Chief (DRP/A)
Lisa Shea, RM/ALF, MS: MNBB 4503 MIS System DRSS-FIPS RIV File Section Chief (DRP\TSS) DRS G. F. Sanborn, E0 J. Lieberman, OE, MS: 7-H-5
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December 7, 1992 , 'E E 'l l
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OCAN129204 DEC 1 1 P "
I U. S. Nuclear Regulatory Commission *
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I Document Control Desk ' -- J'
l Mail Station P1-137 i Washington, DC 20555 Subject: Arkansas Nuclear One - Units 1 and 2
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Docket Nos. 50-313 & 50-368 License Nos. DPR-51 & NPF-6 il Supplemental Response to Inspection Report 50-313/92-11; 50-368/92-11
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Gentlemen
Pursuant to the provisions of 10CFR2.201, attached is the j supplemental response requested in a letter from Mr. Bill Beach dated November 25, 1992, to the violation identified during the inspection of activities associated with the
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failure to follow the instructions contained in Radiation Work Permits.
Our assessment of the' nature of these deficiencies indicates
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that broader improvements are needed in this area. We are
taking actions to improve performance including hands-on i radiation worker training and communicating expectations to line-management regarding the importance of being actively
- involved to monitor the performance of their personnel and
- ensure that individual radiological practices are being properly implemented. Special emphasis by ANO executive management has been placed on improvements in radiological
- work practice The corrective actions currently in progress are designed to improve radiation worker practices. We are committedoto
ensure that ANO's radiological work practices meet all regulatory requirements and Entergy Operations' standards of
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excellenc Should you have questions or. comments, please call me at 501-964-860 Very truly yours, nw NM James . Fisicaro
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U. S. NRC December 7, 1992
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Page 2 cc: Mr. James L. M11hoan U. S. Nuclear Regulatory Commission Region IV l 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike l Rockville, Maryland 20852 Mr. Roby B. Bevan, Jr NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852
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. Attachmont to OCAN129204 Page 1 NOTICE OP VIOLATION
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Unit 1 Technical Specification 6.8.1.a required, in part, that
" Written procedures shall be established, implemented and i
maintained covering ... the applicable procedures recommended in l 1 Appendix A of Regulatory Guide 1.33, November, 1972." Safety Guide 33, Appendix A, recommended that personnel monitoring and radiation work permits be covered by written procedure Procedure 1000.031, Revision 15, " Radiation Protection Manual,"
required that " Radiologically controlled areas at Arkansas
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Nuclear One are identified with yellow and magenta (purple)
ropes, flags, posting signs, tape, etc. which shall not be used for any other purpos All personnel are required to adhere to these postings."
Similarly, Unit 2 Technical Specification, 6.8.1.a. required, in part, that " Written procedures shall be established, implemented and maintained covering ... the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February
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1978." Regulatory Guide 1.33, Appendix A, recommended that radiation work permits be covered by written procedure Procedure 1000.031, Revision 15, " Radiation Protection Manual,"
required that " individuals are responsible for ... adherence to radiological protection requirements ..." and "... being knowledgeable of and understanding the requirements and contents of the Radiological Work Permit (RWP) under which work will.be performed."
Radiation Work Permit 920993, Revision 1, required workers to perform a whole body frisk when exiting a radioactive material are Radiation Work Permit 921438, Revision 1, required workers to wear surgical gloves for electrical penetration work within a radioactive materials area.
I contrary to the above, the following three examples of failure to follow radiation work permit requirements were identified:
, On August 26, 1992, an operator and an escorted visitor failed to adhere to a radiological posting for a radioactive mctorials area, which ir.dicated a radiation work permit and contamination monitoring was required for entr On September 4, 1992, the resident inspector observed that two main steam safety valve workers failed to
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perform whole body frisks when exiting a radioactive material area as required by Radiological Work Permit 920993, Revision On September 8, 1992, the resident inspector observed that two Electrical Penetration 2E-22 workers failed to wear surgical gloves when performing work within a radioactive materials area as required by Radiological Work Permit 921438, Revision These three examples constitute one Severity Level IV violatio (supplement IV) (313/9211-02; 368/9211-03)
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, Attachmsnt to:
OCAN129204 Pcgn 2
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Response to violation 313/9211-02; 368/9211-03
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(1) Reason for the violation:
Example A Cited example A was caused by a personnel error. The operator and escorted visitor were undergoing an operations license examination, and they did not recognize that the area they were entering was a posted radiologically controlled area (RCA). The RCA is also a security area and two (2) separate informational (radiation and security) postings are located on the access door. The unauthorized entry into the RCA was not detected until the escorted visitor noticed the rsdiation area posting as they egressed through the security doo Eyample B Cited example B was caused by a personnel error. The two (2)
main steam safety valve workers were aware that whole body frisking was required. They did not perform a whole body frisk before egressing the RCA because the portable frisker
was located in a poorly lighted area and was not readily visible to the workers. They exited the RCA and proceeded to a known frisker location where a successful whole body frisk was completed. Additionally, a common RCA ingress / egress point had not been established which would have placed the frisking equipment in a readily accessible are Example C Cited example C was caused by a personnel error. A crew of contract workers were pulling electrical cables into an electrical penetration device which caused frequent tearing of the surgical gloves. Additionally, the contract workers experienced difficulty in maintaining a grip on the cables due to excessive sweating in the gloves. Thus, the gloves were removed to get a better grip on the cable (2) Corrective steps taken and results achieved:
Example A The operator and escorted visitor self-reported the unauthorized entry into the RCA to the Health Physics (HP)
Departmen Immediate actions were taken by HP to assess radiation exposure to the individuals and contamination control measures in the area in question. Additionally, the operator and escorted visitor were counselled on the required radiological control requirement An evaluation of the relationship between radiological control barriers and other barriers, i.e., security and fire doors, was performed to determine if additional improvements in identification of radiological control barriers are necessar The results indicated that current postings and warnings are in compliance with governing document _
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Attechmont to OCAN129204 Pago 3 T'his incident was discussed with Arkansas Nuclear One (ANO)
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Unit One Operations personnel and radiological control requirements reemphasized during operations rotational requalification training. This was completed on November 6, 199 Example B The two (2) main steam safety valve workers were aware that whole body fricking was required. When the workers could not locate a frisker in the area in which they were working, they exited the RCA and proceeded to a known frisker location where a successful whole body frisk was completed. The frisker was relocated so that it is clearly visible and accessible, and the individuals involved were counselled on the required radiological control requirements for frisking prior to leaving the RC Strategic placement of friskers is critical especially when RCAs are established on a temporary or infrequent basi Personnel in such areas must be able to recognize where friskers are located. To assure the consistent placement of friskers in the most ideal locations, an evaluation of frisker placement practices was performed and a memorandum to Health Physics Technicians was issued on November 6, 1992, providing guidance on proper frisker placemen Example C
. Health Physics Department management and the electrical penetration worker's supervisor counseled the contract crews involved in the electrical penetration wor Emphasis was placed on reading and understanding the radiation work permit, complying with the instructions contained in the RWP, monitoring techniques and control of contamination method (3) Corrective steps which will be taken to prevent recurrence:
Example A Since this cited example was caused by a personnel error and corrective actions were completed, no specific corrective steps to prevent recurrence were identified; however, common corrective measures outlined on page 4 of this response were identifie Example B Since this cited example was caused by a personnel error and corrective actions were completed, no specific corrective steps to prevent recurrence were identified; however, common corrective measures outlined on page 4 of this response were identifie _ _ _ - - _ - _ _ _ - _ _ - _ _ _ - _ _ _ _ _ _ .
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, Attachment tos
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OCAN129204 Pcgn 4
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Example C
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Since this cited example was caused by a personnel error
involving contract crews who are no longer working on site, no specific corrective steps to prevent recurrence were identified; however, common corrective measures outlined on page 4 of this response were identifie :
i Corrective Measures Common To All Three (3) Examples A memorandum issued on November 3, 1992, emphasized the requirement and need to have ANO supervision routinely monitor the performance of their personnel during work activities
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involving radiological hazards to ensure that proper radiological I work practices are being implemented. This oversight is important during periods in which HP coverage is not required and I for job activities that are repetitive in nature or involve j extended periods of tim '
Two assessments were conducted during the weeks of September 21, j 1992 and November 16, 1992 to identify improvement areas of the I ANO radiological protection program and practice Both I assessments were based on Insticute of Nuclear Power Operation Objectives entitled " Radiological Protection Organization and Administration" and " General Employee Knowledge and Ability in Radiological Protection" und others. Based on the results of these assessments, several recommendations for improvements to
- radiation work practices and the radiological protection program were identified. The following summarizes the key general areas requiring increased emphasis
- Line management needs to be more actively involved in supporting implementation of the Radiological Protection l Program.
l l Better communication and training to radiation workers on l radiological work practice Enhance the radiological infraction reporting system for better reporting, trending and analysis.
Currently, a special radiation work practice training course has
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been developed and is being provided for ANO health physics, maintenance, selected on-site contractor radiation workers and
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management personnel. This training, conducted by health physics
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and training personnel, provides both basic and practical hands-
! on instruction in radiological work practices. This training began on November 23, 1992, and is expected to be completed by
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December 31, 1992.
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OCAN129204 Page 5 j
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'As a result of the detailed assessment results, the Vice
- President, ANO Operations met directly with the affected plant management and supervisory staff to place special emphasis on i
expectations regarding radiological work practice These
- discussions focused on cultural changes required to facilitate
' improving the implementation of the radiological protection ,
l program at ANO. This included individual ownership, self- I j checking, professionalism and more management involvement and j oversight at the department level. Applicable managers reviewed i the assessment results and developed specific action plans to j improve their performance within their area of responsibility
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under the radiological protection program. Further review of i individual department action plans is being performed by plant )
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! management to insure consistency and appropriate
. Inter-departmental plan integration. This integrated corrective l j action plan will be reviewed by December 15, 1992.
(4) Date when full compliance will be achieved:
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!- These three (3) examples-of failure to follow RWP instructions
did not cause any measurable increase in personnel exposures j nor resulted in any spread of contamination. Upon counselling i of the individuals involved, ANO was in compliance with its j radiological protection program.
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act distrib. by RIV:
J. L. Milhoan Resident Inspector DRP Section Chief (DRP/A)
Lisa Snea, RM/ALF, MS: MNBB 4503 MIS S, stem
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DRSS-FIPS RIV File Section Chief (DRP\TSS) DRS
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Gi F Sanborn, EO J. Lieberman, OE, MS: 7-H-5
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