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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
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...- JAN I 31994 Dockets: 50-313 50-368 Licenses: DPR-51 NPF-6 Entergy Operations, In ATTN: J. W. Yelverton, Vice President Operations, Arkansas Nuclear One Route. 3, Box 137G R:asellville, Arkansas 72801
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SUBJECT.- NRC INSPECTION REPORT 50-313/93-30; 50-368/93-30 Thank you for your letter of December 22, 1993, in response to our letter and Notice of Violation dated November 29, 1993. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation'of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
Sincerely,
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Dwight D. Chamberlain i Acting Director Division of Radiation Safety and Safeguards cc:
Entergy Operations, In ATIN: Harry W. Keiser, Executive Vice President & Chief Operating Officer P.O. Box 31995-Jackson, Mississippi 39286-1995
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Entergy.0perations, In Entergy Operations, In ATIN: John R. McGaha, Vice President ,
Operations Support P.O. Box 31995 Jackson,. Mississippi 39286 Wise, Carter, Child & Caraway ATTN: Robert B. McGehee, Es ,
P.O. Box 651 Jackson, Mississippi 39205
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Honorable C. Doug Luningham County' Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 ,
Winston & Strawn ATTN: Nicholas S. Reynolds, Es L Street, Washington, ,
Arkansas Department of Health ATTN: Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management t 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) ;
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214 South Morris Street 0xford, Maryland 21654 ABB Combustion Engineering Nuclear Power ATTN: Charles B. Brinkman ,
Manager, Washington i Nuclear Operations ;
12300 Twinbrook Parkway, Suite 330 '
Rockville, Maryland 20852
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.i Entergy Operations, In bcc.to DMB (IE06)-
bec w/ copy of letter dated December 22, 1993:
J. L. Milhoan A. D. Gaines, DRSS/FIPS AN0 Resident Inspector Section Chief (DRP/D)
Section Chief (DRP/TSS)
Project Engineer (DRP/0)
Lisa Shea, RM/ALF, (MS MNBB 4503)
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Entergy Operations, In bec to DMB (IE06)
bec w/ copy of letter dated December 22, 1993: :
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J. L. Milhoan A. D. Gaines, DRSS/FIPS AN0 Resident Inspector *
Section~ Chief (DRP/D)
Section Chief (DRP/TSS) ,
Project Engineer (DRP/D) l Lisa Shea, RM/ALF, (MS MNBB 4503)
DRSS/FIPS Files MIS System RIV File
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Ent;rgy Oper;tions, In '
c =- ENTERGY Route 3 Box 137G n ma no Tet 50196A8688
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Jerry W. Yelverton Vce Pescent 0: cam ANO December 22,1993 ; -
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OCAN129304 61
,w uEC 2 71993 $
U. S. Nuclear R gulatory Commission ,
Document Control Desk '
i;EG!CN IV Mail Station PI-137 '
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 Response to Inspection Report 50/313/93-30; 50/368/93-30 Gentlemen:
Pursuant to the provisions of 10CFR2.201, attached is the response to the violations identified during the inspection of activities associated with the failure to follow radiation work permit requirements and the failure to perform radiation survey '
Should you have questions or comments, please call Mr. Rick King at 501-964-861 Very truly yours,
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December 22,1993
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cc: Mr. James L. Milhoan 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 - ANO-l & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby B. Bevan, J 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, MD 20852 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 Rockville, MD 20852
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. NOTICE OF VIOLATION During an NRC inspection conducted on November 1-5, a routine, announced inspection of the radiation protection program, two violations of NRC requirements were identifie !
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed below:
A. Unit I and Unit 2 Technical Specification 6.8.1.a requires, in part, that written
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procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A, states, in pan, that radiation work permits be covered by written procedure Section 5.5 of Procedure 1000.031, Revision 16, " Radiation Protection Manual,"
states, in part, that " individuals are responsible for: adherence to radiological protection requirements " and " ..being knowledgeable of an understanding the requirements and contents of the Radiological Work Permit under which work will be performed."
Radiation Work Permits 930553 and 93031I state, " Alarming Dosimeters are required for entry on this Radiological Work Permit."
Contrary to the above, on November 3,1993, the inspector identified two individuals who entered the radiological controlled area under Radiation Work Permits 930553 and 93031I who had not been issued alarming dosimeter This constitutes a Severity Level IV violation (Supplement IV) (313/9330-01; 368/9330-01).
B.10 CFR 20.201(b) requires that each licensee make such surveys as may be necessary to comply with the requirements of Part 20 and which are reasonable under the circumstances to evaluate the extent of radiation hazards that may be present. As defined in 10 CFR 20.201(a), " surveys" means an evaluation of the radiation hazards incident to the production, use, release, disposal, or presence of radioactive materials or other sources of radiation under a specific set of condition Contrary to the above, the licensee identified that on August 18,1993, surveys were not made to assure compliance with 10 CFR 20.301, which describes authorized means of disposing oflicensed material contained in waste. Specifically, a radiation survey was not performed of two drums of solvent prior to shipment to an oilsite facility for disposal. Subsequent surveys identified radiation levels of between 0.02 to-2.6 millirem per hour on contact with the drum This constitutes a Severity Level IV violation (Supplement IV) (313/9330-02; 368/9330-02).
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. Response to violation 313/9330-01: 368/9330-01) Failure to Adhere to Radiation Work Permit Requirements (1) Reason for the violation Three events related to alarming dosimeter events had been previously identified by Radiation Pratection personnel and corrective actions with involved individuals were completed. However, the established Radiological Information Report (RIR)
threshold requiring funher trend analysis of alarming dosimeter infractions had not yet been met. A follow-up review of Arkansas Nuclear One (ANO) Radiation Work Permit (RWP) records and RIRs revealed similar instances of individuals ,
who entered radiological controlled areas (RCA) without either preparing the proper documentation for issue, or receiving the required alarming dosimeter The majority of these non-compliance's occurred during the Fall of 1993, in Arkansas Nuclear One (ANO) Unit I refueling outage 1Ril, by contract personne The reason individuals entered RCA without the required alarming dosimeters was inadequate compliance with the RWP regarding the proper radiation worker practice Additionally, the following contributing causes compounded the alarming dosimeter problem:
. Inadequate communication between Health Physics (HP) technicians and radiation workers concerning entry requirements during radiography sessions,
. Inattention to detail by radiation workers during preparation for entering, and working in high rad areas, t
. Inconsistent wording in RWPs relating to alarming dosirneter requirements, and,
. Inadequate performance by HP clerks in documenting the issue of alarming dosimeters (2) Corrective steps taken and results achieved:
On November 8,1993, a memorandum from ANO Executive management was issued outlining the management expectations and required accountability in adhering to RWP requirements of all ANO and contract radiation workers. Other weaknesses in radiation worker practices were also identified and discusse During Unit I refueling outage 1Ril, HP clerks were counseled on the procedural method of documenting the issue of alarming dosimeter .
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On November 10,1993, alarming dosimeter issuance requirements were discussed with HP technician (3) Corrective steps that will be taken to prevent further violations:
The Entergy Radiation Information Management System (ERIMS) is currently under development, and when implemented on January 1,1994, is expected to provide enhanced access control into the RCA. This system will replace the Radiation Exposure Management System (REM) currently in operation. ERIMS will include a simplified RWP form that clarifies and improves human performance factored requirements for radiation worker This also includes clearer requirements for the use of alarming dosimeters. Additionally, ERIMS will track radiation worker exposure histories, dosimeter issue, et General Employee Training (GET) will be enhanced prior to the Unit 2 refueling outage 2R10 to include additional emphasis on compliance to RWP instructions and the use of alarming dosimeter During ANO Unit 2 refueling outage 2R10, currently scheduled for the Spring of ;
1994, the ANO Quality Department will perform periodic observations of radiation worker practices to validate the effectiveness of corrective actions taken concerning the use of alarming dosimeter Any individual identified as violating RWP dosimetry requirements during the Unit 2 refueling outage 2R10 will be referred to the individuals appropriate level of :
I management for corrective action. This will enforce accountability for individual action ;
(4) Dale when full compliance will be achieved:
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ANO is cunently in compliance with requirements regarding the use of alarming l dosimeter !
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. Resoonse to violation 313/9330-02: 368/9330-02) Failure to Perform Radiation Surveys (1) Reason for the violatinD NRC Inspection Report (IR) 93-06, dated August 5,1993, issued a non-cited violation for the self-identified release of contaminated tools and equipment from the ANO RCA. As stated in IR 93-06, ANO took prompt and effective corrective actions to correct the problem. One corrective action was to perform a site-wide survey of maintenance tools and equipment. This survey identified contaminated maintenance tools and equipment stored outside of the RCA. ANO continues to perform periodic surveys of non-radiological areas to ensure that contaminated material is not inadvertently released from the RCA. However, the scope of the site-wide survey did not include surplus material stored outside of the RC Procedure 1052.025, revision 0, Drum Control addresses the storage, use, analysis of contents and disposal of drums, both radiological and non-radiological. This procedure also allows documented deviations from procedural requirements when
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justified, i.e. non-performance of radiological analysi In early 1993, two 55 gallon drums of what appeared to be new and unused freon based solvent were deemed surplus and scheduled for removal from ANO. Since the solvent had no record of use, was in full original containers, and stored since 1986 in non-radiological or hazardous material storage areas, the decision not to perform a radiological analysis before disposal was made as allowed by Procedure 1052.025. These drums were then shipped to an off-site vendor for disposal on ,
August 18,199 The reason the radioactive solvent was shipped to an off-site vendor for disposal, without radiological analysis was inadequate procedural guidance. Procedure 1052.025 was developed in early 1992, which addressed the issues associated with waste liquids, but did not address or recognize other avenues ofliquid use and controls at ANO. As a result, the solvent was not interpreted to be waste, but rather surplus liquid material which was not covered by procedural requirements.
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(2) Corrective steps taken and results achievei l On September 24, 1993, ANO was notified by the vendor of the potentially l contaminated solvent. ANO Health Physics technicians were dispatched to the - ,
facility and confirmed that the solvent was radioactive. The radioactive solvent j was recovered and returned to ANO. Additionally, dose calculations of the ;
vendors employees indicated that radiation exposures were less than 1.0 mr, and
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the off-site facilities were found to be free from contaminatio Radiation and contamination surveys were performed in the oil and hazardous ,
material onsite storage areas and in an off-site warehouse. The surveys did not identify any contaminated items. Liquid materials received in the hazardous materials area are now analyzed for contamination before storag Subsequent to the offsite shipment of radioactive solvera, this event was discussed with members of the Radiation Protection staffin late September 199 Procedure 1052.025, Dnim Control, was revised on December 14,1993, to include additional guidance concerning more definitive instructions on when ,
exceptions to the procedure can be made, and to analyze material in site issued ,
drums for radiological content before shipment offsit ANO Contract Managers are provided a checklist of procedural references and requirements / activities to consider when preparing contract request On December 7,1993, the Contract Manager Guidelines were revised to address activities involving the handling, sampling, or shipment ofliquid materials into or out of the ANO protected area. This will provide improved controls to assure that contractors are appropriately notified and adhere to ANO requirements concerning the handling, sampling or shipping ofliquid material (3) Corrective stens that will be taken to orevent further violations: ,
Procedure 1000.031, Radiation Protection Mamial, was revised to provide specific guidance for sampling ofliquids prior to disposal off-sit Procedure 1012.020, Radioactive Material Control, was revised to establish guidelines for liquid sampling requirements of materials removed from posted radiological area The above procedures will be implemented on January 1,1994, which coincides with the implementation of the revised 10CFR20 which is effective on January 1, 199 .
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' Training on this event will be incorporated into the Health Physics Continuing Training Program with emphasis on Health Physics management expectations on the performance of quarterly surveys. Specific emphasis will be placed on survey of all potential storage containers (i.e. drums, barrels, boxes, etc.), stockpiled j materials common to use in the RCAs (i.e. scaffolding, treated wood, lead, etc.),
and use of high sensitivity monitoring equipment. This training will be completed by April 1,199 Other liquid containers that have been identified by the Materials Management group and those currently stored in the HazMat area will be analyzed to identify any other containers which may contain contaminated material. This analysis will ;
be completed by March 1,199 :
An effectiveness review of the corrective actions performed to prevent recurrence ;
of this event will be completed by June 1,199 l
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(4) Date when full comoliance will be achieved:
For the subject container shipped offsite, full compliance with NRC regulations was satisfied when the radioactive material was recovered, and returned to AN Additionally, due to the low exposure rates, the shipment of this. radioactive material posed no undue risk to the health and safety of the general publi ;
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