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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:NRC TO UTILITY
MONTHYEARML20062F0481990-11-19019 November 1990
Advises That SR Peterson Replacing C Poslusny as Project Manager for Facility,Effective 901105
ML20216K0001990-11-13013 November 1990
Forwards Insp Repts 50-313/90-30 & 50-368/90-30 on 900905- 1016 & Notice of Violation
IR 05000313/19900321990-11-0808 November 1990
Ack Receipt of Outlining Steps to Provide Addl Technical Support for Radiation Protection Manager.Planned Actions Acceptable as Documented in Insp Repts 50-313/90-32 & 50-368/90-32
ML20058G8471990-11-0808 November 1990
Forwards Insp Repts 50-313/90-32 & 50-368/90-32 on 900924-29.No Violations or Deviations Noted
ML20058G1631990-11-0707 November 1990
Forwards Summary of Current Status of Unimplemented Generic Safety Issues at Plant
ML20058E2881990-11-0101 November 1990
Rejects 900302 Request for Amend to Tech Specs to Revise Power Calibr Requirements for Linear Power Level & Core Protection Calculator delta-T Power & Nuclear Power Signals
ML20062D5631990-10-31031 October 1990
Forwards Insp Repts 50-313/90-37 & 50-368/90-37 on 901015-19.No Violations Noted
ML20062D5761990-10-31031 October 1990
Forwards Insp Repts 50-313/90-40 & 50-368/90-40 on 901015-19.No Violations Noted
ML20062D5511990-10-31031 October 1990
Forwards Insp Repts 50-313/90-31 & 50-368/90-31 on 901001-04.No Violations Noted
ML20059P0441990-10-16016 October 1990
Authorizes Use of Inconel 690 (I-690) as Alternate to I-600 in Steam Generator Tube Sleeves/Plugs Per 10CFR50.55a(a)(3)
ML20058A5211990-10-16016 October 1990
Forwards Insp Repts 50-313/90-38 & 50-368/90-38 on 901001- 05.Violation Considered for Escalated Enforcement Action
ML20058A0811990-10-15015 October 1990
Forwards Questions Re 900808 License Amend Request to Increase Reactor Power to 100% for Response
ML20062A5511990-10-10010 October 1990
Forwards SER Re Util 890403,13 & 0717 Responses to Station Blackout Rule.Issue of Conformance Still Open
IR 05000313/19900011990-10-0404 October 1990
Ack Receipt of 900420 & 0914 Ltrs Re Validation of Nonlicensed Operator Staffing Per Insp Repts 50-313/90-01 & 50-368/90-01
ML20059M0441990-09-26026 September 1990
Approves 900809 Request to Withhold 86-1179795-01, ANO-1 HPI Flow Rate Requirements (Ref 10CFR2.790(b)(5))
ML20059K3851990-09-14014 September 1990
Forwards Insp Repts 50-313/90-28 & 50-368/90-28 on 900827-31.No Violations or Deviations Noted.Some Weaknesses Identified in Areas of Alternate Safe Shutdown Procedure & Associated Training for Unit 2
ML20059J2431990-09-14014 September 1990
Discusses Programmed Enhancements for Generic Ltr 88-17, Loss of Dhr. Changes in Completion Schedule Should Be Submitted to NRC
ML20059J9901990-09-13013 September 1990
Forwards Info Re Generic Fundamentals Exam of Operator Licensing Written Exam to Be Administered on 901010.W/o Encl
ML20059G2951990-09-0606 September 1990
Advises That Rev 10 to Emergency Plan,Contained in ,Acceptable.Rev Consists of Changes Resulting from Reorganization,Relocation of Personnel from Little Rock Ofc & Improvements from Annual Emergency Preparedness Exercise
ML20059E8621990-08-31031 August 1990
Forwards Insp Repts 50-313/90-27 & 50-368/90-27 on 900813-17.No Citations Issued for Violation
ML20059D1551990-08-30030 August 1990
Forwards Request for Addl Info to Continue Review of 891019 Application for Amend Extending Insp Frequency of Spent Fuel Pool from Once Per 18 Months to Once Per 60 Months.Response Requested within 45 Days
ML20059E5901990-08-29029 August 1990
Forwards Summary of 900823 Quarterly Performance Meeting at Plant Re NRC Authorized Activities.Meeting Provided Better Understanding of Current Implementation Status of Program Changes at Plant.List of Attendees & Viewgraphs Encl
IR 05000313/19900161990-08-29029 August 1990
Discusses 900823 Meeting Re Unresolved Item Concerning Missed Surveillance Tests,Per Insp Repts 50-313/90-16 & 50-368/90-16.Violation of Tech Spec Requirements Noted But Not Cited Due to Listed Reasons
ML20059F3441990-08-29029 August 1990
Forwards Insp Repts 50-313/90-23 & 50-368/90-23 on 900716-20.No Violations or Deviations Noted
ML20059D6381990-08-29029 August 1990
Ack Receipt of Re Proposed Changes to Unit 1 Tech Spec 6.12.2.6(b) & Unit 2 Tech Spec 6.9.3.1.Proposed Changes Appear to Improve Quality of Semiannual Radioactive Effluent Release Repts
ML20059B8461990-08-23023 August 1990
Responds to Re Violations Noted in Insp Repts 50-313/89-33 & 50-368/89-33.Violations Remain Applicable
ML20056B4921990-08-22022 August 1990
Forwards Request for Addl Info Re Util 900618 Response to NRC Questions on Condensate Storage Tank Seismic Qualification.Response Should Be Provided within 45 Days to Facilitate Completion of NRC Effort
ML20056B4131990-08-21021 August 1990
Forwards Summary of 900718 Meeting Re Exercise Weaknesses Noted in Insp Repts 50-313/90-08 & 50-368/90-08
ML20056B4641990-08-21021 August 1990
Ack Receipt of Advising NRC of Current Status of Security Perimeter Improvements,Per Insp Repts 50-313/87-31 & 50-368/87-31.Implementation of Design Change DCP 90-2001 for Perimeter Lighting Will Be Monitored for Adequacy Later
ML20059A7011990-08-17017 August 1990
Forwards Sser Concluding That Rochester Instrument Sys Model SC-1302 Isolation Device Acceptable for Use at Plant for Interfacing SPDS W/Class IE Circuits
ML20058P2601990-08-13013 August 1990
Forwards Insp Repts 50-313/90-26 & 50-368/90-26 on 900730-0803.No Violations or Deviations Noted.Rept Does Not Include Specific Insp Followup for Any Diagnostic Evaluation Team Findings
ML20058N9741990-08-10010 August 1990
Forwards Insp Repts 50-313/90-19 & 50-368/90-19 on 900601- 0715 & Notice of Violation.Util Should Respond to Failure to Adequately Implement Surveillance Test Required by Tech Specs
IR 05000313/19900041990-08-0909 August 1990
Ack Receipt of 900611 & 0731 Ltrs Re Steps Taken to Correct Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04
ML20056A7491990-08-0707 August 1990
Forwards Safety Evaluation Accepting Licensee Fire Barrier Penetration Seal Program & Commitment to Complete 100% Review of All Tech Spec Fire Penetration Seals by 911231
ML20055J3571990-07-31031 July 1990
Forwards Review of C-E Topical Rept Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Per NRC Bulletin 88-011.Adequate Basis Not Provided for Meeting Pressurizer Surge Line Code Limits
ML20055J3981990-07-31031 July 1990
Discusses Util 890602 Response to Item 1.b of NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification. Sufficient Info Provided to Justify Continued Plant Operation Until Final Rept for Unit 1 Completed
ML20056A0211990-07-30030 July 1990
Ack Receipt of 890307 & s Informing NRC of Steps Taken to Correct Violation Noted in Insp Repts 50-313/88-47 & 50-368/88-47
ML20055J1201990-07-24024 July 1990
Advises That Operational Safety Team Insps 50-313/90-24 & 50-368/90-24 Scheduled at Plant Site on 900910-21
ML20055H9511990-07-23023 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/90-01 & 50-368/90-01
ML20055H9471990-07-20020 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/89-02 & 50-368/89-02
ML20058P7261990-07-19019 July 1990
Forwards Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 900606
ML20055G1801990-07-17017 July 1990
Confirms 900718 Mgt Meeting in Region IV Ofc Re Exercise Weaknesses Noted During Mar 1990 Emergency Exercise
ML20055F8011990-07-13013 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/89-27 & 50-368/89-27.Security Officer Training Will Be Evaluated During Future Insps
ML20055E5171990-07-0909 July 1990
Advises That 900607 Control Element Assembly Failure at Maine Yankee Not Applicable to Facility.Nrc Understands That Util Does Not Plan to Use Any old-style Control Element Assemblies in Future
ML20055D5081990-06-29029 June 1990
Forwards Insp Repts 50-313/90-18 & 50-368/90-18 on 900521-25.No Violations or Deviations Identified.Two Open Items in Areas of Procedures & Personnel Dosimetry Noted
1990-09-06
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Category:OUTGOING CORRESPONDENCE
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See also: IR 05000313/1990008
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In Reply Refer To:
Dockets: 50-315/90-08
50-368/90-08
Entergy Operations, Inc.
ATTN: Neil S. Carns, Vice President
Operations, Arkansas Nuclear One
P.O. Box 551
Little Rock, Arkansas 72203
Gentlemen:
This refers to the meeting held at our request in the Region IV office on
July 18, 1990. This meeting related to activities authorized by NRC License
Nos. DPR-51 and NPF-6 for Arkansas Nuclear One (ANO), and was attended by
yourself and others listed in the Attachment to the Enclosure of this letter.
The subjects discussed at this meeting are described in the enclosed Meeting
Summary.
It is our opinion that this meeting was beneficial and has provided a better
understanding of the issues involved. In accordance with Section 2.790 of the
NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a
copy of this letter will be placed in the NRC's Public Document Room.
Should you have any questions concerning this matter, we w'111 be pleased to
discuss them with you.
Sincerely,
Originni sicnc:1 DY.
Samuel J. Collins, Director
Division of Reactor Projects
Enclosure:
Meeting Summary, w/ Attachment
ec w/ enclosure:
Entergy Operations, Inc.
ATTN: Donald C. Hintz, Executive
Vice President
P.O. Box 31995
Jackson, Mississippi 39286
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Entergy Operations, Inc. -2-
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Entergy Operations, Inc.
ATTN: Gerald W. Muench, Vice President
Operations Support
P.O. Box 31995
Jackson, Mississippi 39286
Wise, Carter, Child & Caraway
ATTN: Robert B. McGehee, Esq.
P.O. Box 651
Jackson, Mississippi 39205
Arkansas Nuclear One
ATTN: Early Ewing, General Manager
Technical Support and Assessment
Route 3, Box 137G
Russellville, Arkansas 72801
'
Arkansas Nuclear One
ATTN: Jerry Yelverton, Director
Nuclear Operations
Route 3, Box 137G
Russellville, Arkansas 72801
Arkansas Nuclear One
ATTN: Mr. Tom W. Nickels
Route 3, Box 137G
Russellville, Arkansas 72801
Combustion Engineering, Inc. I'
ATTN: Charles B. Brinkman, Manager l
'
Washington Nuclear Operations
12300 Twinbrook Parkway, Suite 330
Rockville , _ Maryland 20852
Honorable Joe W. Phillips
County Judge of Pope County
Pope County Courthouse
Russellville, Arkansas 72801 t
Bishop, Cook, Purcell & Reynolds
ATTN: Nicholas S. Reynolds, Esq.
1400 L Street, N.W.
Washington, D.C. 20005-3502
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Entergy Operations, Inc. -3-
Arkansas Department of Health
ATTN: Ms. Greta Dicus, Director
Division of Environmental Health
Protection
4815 West Markam Street
Little Rock, Arkansas 72201
Babcock & Wilcox
Nuclear Power Generation Division
ATTN: Mr. Robert B. Borsum
1700 Rockville Pike, Suite 525
Rockville, Maryland 20852
U.S. Nuclear Regulatory Commission
ATTN: Senior Resident Inspector
1 Nuclear Plant Road
Russellville, Arkansas 72801
.
U.S. Nuclear Regulatory Commission
ATTN: Regional Administrator, Region IV
611 Ryan Plaza Drive, Suite 1000
Arlington, Texas 76011 '
'
Chief, Technological Hazards Branch
FEMA Region 6
Federal Center .
800 North Loop 288 ,
Denton, Texas 76201<3698
bec to DMB (IE45) w/ Licensee's Handout ,
bec distrib. by RIV:
R. D. Martin Resider t Inspector
Section Chief (DRP/A) GFSanborn
Lisa Shea, RM/ALF RIV File
DRP MIS System
RSTS Operator Project Engineer (DRP/A)
DRS
T. Alexion, NRR Project Manager (MS: 13-E-21)
C. Posiusny, WRR Project Manager (MS: 13-D-18)
ABBeach DAPowers
NMTe:c SEPS File
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