|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 ML20209D8521999-07-0707 July 1999 Responds to Util 990706 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by TS 3.7.2, Auxiliary Electrical Sys. NOED Warranted & Approval Granted for Extension of Allowed Outage Time to 14 Days ML20209A8561999-06-25025 June 1999 Refers to Investigation Rept A4-1998-042 Re Potential Falsification of Training Record by Senior Licensed Operator at Arkansas Nuclear One Facility.Nrc Concluded That Training Attendance Record Falsified IR 05000313/19990071999-06-21021 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/99-07 & 50-368/99-07 Issued on 990514.Adequacy of Min Staffing Levels May Be Reviewed During Future Insps ML20196D4241999-06-21021 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp of License SOP-43716 Issued on 990325.Believes That NRC Concerns Have Been Adequately Addressed at Present ML20207H3551999-06-10010 June 1999 Forwards Insp Repts 50-313/99-05 & 50-368/99-05 on 990411-0529.No Violations Noted ML20195G3481999-06-0909 June 1999 Ack Receipt of ,Transmitting Changes to Facility Emergency Plan,Rev 25,under Provisions of 10CFR50,App E, Section V IR 05000313/19993011999-06-0909 June 1999 Discusses Arrangements for Administration of Licensing Exam During Wk of 991213,per Telcon of 990602.As Agreed,Exams Repts 50-313/99-301 & 50-368/99-301 Will Be Prepared Based on Guidelines in Rev 8 of NUREG-1021 ML20195F1631999-06-0808 June 1999 Forwards Insp Repts 50-313/99-06 & 50-368/99-06 on 990524-28.Violation Identified & Being Treated as Noncited Violation ML20207G3111999-06-0707 June 1999 Ack Receipt of Changes to ANO EP Implementing Prcoedure 1903.010,Emergency Action Level Classification,Rev 34 PC-2, Received on 981218,under 10CFR50,App E,Section V Provisions. No Violations Identified ML20207G7951999-06-0707 June 1999 Forwards Notice of Violation Re Investigation Rept A4-1998-042 Re Apparent Violation Involving Initialing Record to Indicate Attendance at Required Reactor Simulator Training Session Not Attended ML20207E7131999-06-0202 June 1999 Discusses EOI 990401 Request for Alternative to Requirements of Iwl for Arkansas Nuclear One,Pursuant to 10CFR50.55a(g)(6)(ii)(B) & ASME BPV Code Section XI & Forwards Safety Evaluation Accepting Proposed Alternative ML20207B9521999-05-26026 May 1999 Discusses GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. Staff Will Conduct Limited Survey in to Identify Sampling ML20207B4171999-05-24024 May 1999 Forwards Corrected Cover Ltr to Insp Repts 50-313/99-07 & 50-368/99-07 Issued 990514 with Incorrect Insp Closing Date ML20207A7771999-05-24024 May 1999 Forwards Insp Repts 50-313/98-21 & 50-368/98-21 on 981116-990406.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20206U4541999-05-17017 May 1999 Discusses Util & Suppl Re Changes to License NPF-06,App a TSs Bases Section.Staff Offers No Objection to These Bases Changes.Affected Bases Pages,B 202, B 2-4,B 2-7,B 3/4 2-1,B 3/4 2-3 & B 3/4 6-4,encl ML20206S4721999-05-14014 May 1999 Forwards Insp Repts 50-313/99-07 & 50-368/99-07 on 990426- 30.No Violations Noted.However,Nrc Requests That Util Provide Evaluation of Licensee Provisions to Maintain Adequate Level of Response Force Personnel on-site ML20207B4271999-05-14014 May 1999 Corrected Ltr Forwarding Insp Repts 50-313/99-07 & 50-368/99-07 on 990426-30.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program ML20206R4741999-05-13013 May 1999 Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC ML20206N7011999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206M7581999-05-11011 May 1999 Forwards SE Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 ML20206S1761999-05-11011 May 1999 Responds to Informing of Changes in Medical Condition & Recommending License Restriction for Senior Reactor Operator.No Change Was Determined in Current License Conditions for Individual ML20206N4161999-05-11011 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-related Logic Circuits, for Plant,Units 1 & 2 ML20206S4211999-05-10010 May 1999 Forwards Insp Repts 50-313/99-04 & 50-368/99-04 on 990228- 0410.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20206H1031999-05-0606 May 1999 Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407,to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheet & Results to Appropriate Individuals.Without Encl ML20206F0611999-04-29029 April 1999 Forwards SE Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205R6331999-04-20020 April 1999 Ack Receipt of Which Transmitted Rev 39 to ANO Industrial Security Plan,Submitted Under Provisions of 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined Changes Do Not Decrease Effectiveness of Plan ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M6881999-04-12012 April 1999 Forwards Safety Evaluation on Second 10-year Interval Inservice Insp Request Relief 96-005 ML20205L7711999-04-0909 April 1999 Forwards Insp Repts 50-313/99-03 & 50-368/99-03 on 990202- 17.No Violations Noted ML20205K7681999-04-0606 April 1999 Forwards RAI Re risk-informed Alternative to Certain Requirements of ASME Code 11,table IWB-2500-1 ML20205G8871999-04-0202 April 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 60 Days of Date of Ltr 1999-09-22
[Table view] |
See also: IR 05000313/1990008
Text
--
.
,
31 , .
y. ' + ';
'
,
. .
E 2 l- E M)- ,
.
.,
a' '
In Reply. Refer:To:-
' Dockets:' 50-313'90-08: ,
250-366/90-08 .,
'
,;
,
'
'
.Entergyl Operations, Inc.
-ATTN:. Nei.1 S.=Carns,-Vice President
-
-Operations,-Arkansas Nuclear One
-P.O. Box 551..
, + ,
i Little, Rock, Arkansas' 72203
,
Gentlemen: .
Thank you for your . letter of July 27, 1990, in' response to our letter l
' dated June 15,.1990. We found that the corrective measures taken and your d
proposed corrective measures effectively address the concerns identified:during'
the 1990' exercise and discussed in the July '8, 1990, management meeting-held- ;
' in: Region IV. 'We will review the implementation of.your corrective actions
during a future-inspection to determine that full compliance has been achieved
.and will be maintained.
Sincerely,. ;
Oristnal S15 nod BY
Samuel J. Collins, Director ~
Division' of Reactor . Projects '
i
cc:
Entergy Operations, Inc.
s ATTN: Donald C. Hintz,. Executive Vice
President & Chief Operating Cfficer
P.O. Box 31995
Jackson, Mississippi 39286
Entergy Operations,'Inc.
G.TTN: Gerald W.-Muench, Vice President
4 .
Operations Support ,
P.O. fm ~1995 -
.
- Jacku ,, i ssissippi 39286
"
IV: C:SEPSk :DRSS P
. /ch DAPowers BBeach JC ins
l g/(L/90. g ly,/90
f $/20/90
9008280228 900821 'M
%hv/9
A\
PDR ADOCK 05000313
$. Q-
'
PDC ,, g
.
(f w -
m y; , <
s
e, "
,
,
-
,
_
,
'
W y, ' ; -- li;, ,J , ,,
'"
s
,
==~t >
_
._. ;
i: (::
Entergy Operations, Inc. -2-
gic >
,I
. .i
.. Wise, Carter,: Child & Caraway ;
- ' ATTN:' Robert'.B. McGehee,-Esq.
1 .P.O. Box 651 i
,
l Jackson, Mississippi':39205
4
1 Arkansas Nuclear 0no-'
- ATTN:'- Early Ewing, General Manager-
Technical; Support and Assessment
Route 3, Box _137G .
.Russellville,LArkansas .72801 M
. .
Arkansas' Nuclear.One-
ATTN: ~ Jerry Yelverton, Director
Nuclear Operations
Route'3, Box 137G-
Russellville, Arkansas. 72801 .
Arkansas Nuclear One..
' ATTN:. Mr. Tom W. Nickt is -
1
Route 3, Box:137G
Russellville,' Arkansas 72801
.
'{
Combustion 4 Engineering, sinc.
ATTN: Charles B. Brinkr.an,_ Manager
Washington Nuclear Operations !
12300 Twinbrook Parkvay, Suite 330- 1
-
, Rockville,' Maryland 20852
b .H'onorableLJoe W. Phillips
'
,
County Judgefof Pope County- -r
Pope County Courthouse
'
LRussellville, Arkansas 72801
Bishop,. Cook, Purcell & Reynolds r
ATTN: =
Nicholas S. Reynolds, Esq. '
-1400 f Street, N.W.
-
Washington, D.C. 20005-3502
- Arkansas Department of Health i
' ATTN:- Ms.7 Greta Dicus, Otrector
. Division of Environmental Health '
~ Protection
4815 West-Markam Street
,
Little Rock, Arkansas 72201-
!
a,
d: 1
'fh
i
14
?
- - _ . .
v,. ,
- , -
--
' '
,i.i'
'
4
J ;,.
, . , n.? ., @
fl7 . ,3
, _.
,
-
< t .y
a ;,:n - Entergy Operations, Inc., -3
'
,
'
I . ,,.
v
EF ,
Babcock-& Wilcox.
, Nuclear Power Generation Division. *
c ATTN: Mr. Robert'B.-Borsum t
- p. .' 1700:Rockville' Pike, Suite 525
hp '
. Rockville, Maryland 20852
U.S. Nuclear Regulatory Commission 4
ATTN: Senior Resident; Inspector
1 Nuclear Plant Road- ,
e . ,Russellville, Arkansas 72801 i
U.S. Nuclear Regulatory. Commission'
! ATTN:H Regional: Administrator,-Region IV
611 Ryan Plaza Drive, Suite'1000 >
Arlington, Texas 76011,
Chief, Technological' Hazards Branch
uFEMALRegion 6. +
Federal Center . t
800. North Loop 288
'Denton, Texas 76201-3698
'
i
bec to DMB (IE35) - SEPS
bec;distrib. by RIV: :
.R. th Martin:
. Resident Inspector
- DRSS-FRPSL Section Chief (DRP/A)
LLisa Shea, RM/ALF RIV File
, DRP. .MISfSystem ..
q
RSTS Operator Project Engineer:(DRP/A) a-
- D3S-
1.tAlexion,NRRProjectManager'(MS: 13-E-21)-
'
C. .Poslusny,' NRR Project Manager (MS: 13-D-18)
ABBeach DAPowers
NMTerc- SEPS File
i
7
. .
'
g 4
-
, .
. . - .. . . - - _ _ _ _ _ - --- . . _ _ -
,
7
"*
,. .j
e3
,
.___ 1 Entergp =~.o ,.u .. ..
Rov'e 3 Eh 137G
. .: Oper81Ons n mn ns03
Te 50196: 3100
J'-
$ @ $ 0I[ ,
-
July 27, 1990 #E - 21990 .L
'
'OCAN079009 .
~
U.S.' Nuclear Regulatory Commission ,
'
Document Control-Desk
Mail Station P1-137
Washingten, 0.10. 20555
,
Subject: Arkansas Nuclear One - Units 1 & 2
'
Docket Nos.-50-313-and 50-368
L License Nos. DPR-51 and NPF-6
Follow-up Response to Items From the 1990
Radiological Emergency Preparedness Exercise
Inspection Report 50-313/90-08; 50-368/90-08
! Gentlemen:
L Entergy Operations: has reviewed your correspondence of June 15, 1990 (OCNA'
" 069009), regarding. the Arkansas Nuclear One 11990, radiological emergency
p preparedness exercise.
.As discussed withJ Mr. Samuel Collins, Director, Division c1 Reactor
i Projects, Mr. Bill Beach, Director. Division of Radiation Safety and
Safeguards ' and . staf f in- our meeting. of July 18, 1990, we believe that
t Arkansas Nuclear One has a very strong Emergency Preparedness Program and
the abnormal number of weaknesses identified in the 1990 e.x ercise are
, primarily attributable to the impact of the recent reorganization at ANO.
!- Nevertheless, we agree with the weaknesses identified by the inspection
L team as evidenced by the close agreement-between'the team's evaluation and-
our post exercise self assessment. We are, therefore, committed to the
plan for corrective action which we described during our rccent' meeting and
have set forth in detail in the attached.
The 1990 exercise was a successful and challenging experience which
identified several areas requiring further attention in order to enhance
our capabilities and effectively adjust to the recent plant reorganization.
Our detailed review identified several areas of corrective action,-
including 1) increasing the frequency of emergency response facility
drills, 2) allocation' of additional technical support for the emergency
L
response = organization, 3) improved information flow, 4) upgrading the
L notification method, and 5) enhanced training.
Arkansac Nuclear One is committed to a quality emergency preparedness
program. The' effectiveness of our program is evidenced by a number of
program strengths-such as our cooperative and productive relationship with
state.and local government, effective self-assessment, committed management
support and an experienced emergency planniig staff. ANO continues to have
.a' strong program'to assure the protection af the public health and safety.
9hi ( 'v
Tk'90-436 Wff
'
' ~ " ~ n.
'
_*%_ '.
~ 3'
'
- W
a ,3 ' '. -.
u .- ,? *
. . . .
@ ' U.5':NRC . ..
?
' ' '
JJuly 27; 1990'
, V.3 E , OCANB790091 Page'2'
' i d; ,
^Y
'
Yv
.
If you haveLany further questions, piease feel free to call me.'
~
- (
.
]
- Very truly yo'urs,
[
>
.
4 arly .-Ewing q
!
1 General Manager,.
Assessment
t
~
cc: RegionalsAdministrator 1
Region IV -!
- ' ;U. S. Nuclear. Regulatory Commission
'j 611 Ryan Plaza Drive, Suite 1000 J
' Arlington. Texss. 76011 l
q
1;
i
>
.-
f
!
.
.
!
,4 .
i
-
.!
(
!
.
J
\
f ; { -.
- l: .
s' \ ' l....>
,ql ,8) W
b
. :I: . . . .- . . , - . .
, . - . - . . .
,
T >
)
.-.
.
- -
-
t
?
a.f a, f; 'f' '
l4;
1
,
h~U.S. NRC . .
-
l
'
'i:' T July - 27. 1990 _ _
>
.
,.,.,
_ SCAN 679099JPage 2
-
.
>
s -
f
4
1
'
-I 1
!
-i
). '
4
<
'
'
'
,.
-;
$
.
,
i
5
ARKANSAS NUCLEAR ONE j
s
1990 RADIOLOGICAL EXERCISE :
,
RESPONSES TO EXERCISE WEAKNESSES
..
.
0
l-
Ie 4
l
t
t:
!
l
l,
<
3
1'
5
1
l'
i
!.
,
ATTACHMENT TO OCAN079009
i
'
<
-
. , ._- . _ ._. . _ _ . _ . -
, .
I
i
3f
x n
}i
.. ,
Weakness'(313/9008-01: 368/9008-011
The' licensee's failure to promptly detect and classify Site Area. Emergency
(SAE) and General Emergency (GE) conditions is considered to be an exercise
weakness..
,
Response. ,
Additional technical. resources have been allocated to support the Emergency-
Direction and- Control (ED&C) function in the Control Room (CR), Technical .
Support Center (TSC), and Emergency Operations Facility (EOF). This 1
support includes a procedural task entitica " Emergency Action Level (EAL)
~
"
Review", with the task being staffed by Senior Reactor Operators (SRO) in
support of the Shift Operations Supervisor-(505); TSC Director, and the EOF
7 Director.
The purpose of this assignment is to formulato recommendations for the
~
L'
individual with ED&C regarding emergency classification.
Action is completa and becomes effective on July 30, 1990. :
Arkansar Nuclear One will also implement a schedule of quarterly Emergency
Response Facility (ERF) drills, which will increase the number of drills
for activation and operation of the TSC, OSC, and EOF from 1 per year to 4
per year (in addition to the annual exercise). Objectives will include:
1. Emergency Action Level detection and classification.
2. Development of teamwork skills both within and between Emergency
,
Response Facility staffs.
3. Increase the effectiveness, efficiency and- accuracy of
information flow within the ER0i
.
Implementation of the ERF drills begin during the fourth ouarter of 1990.
Weakness (313/9008-02: 368/9008-021 ,
!
Examples of inadequate information flow within ~ and from the CR during the- )
exercise constitutes an exercise weakness.
l
o Resnonse
The Emergency Plan will be revised to more explicitly -define formal
l _ information flow paths. The Implementing Procedures will also be revised
to establish more precise guidelines for Emergency Response Facility (ERF)
information input and output points. These changes, along with requisite
-training, will achieve the following objectives:
1. F. educe parallel and uncoordinated information flow channeln '
between Emergency Response Facilities. I
!
l
L ATTACHMENT TO OCAN079009 PAGE 1
h 1.
1 T, ,
. . ~ . -
- .. .. . . . _ _ _ _ _ _ _ _ _ _ _
.
. ..
': .
+ ., s e i
s
'
.
..
~.
=2. Improve the fidelity of information exchanged between Emergency
Response Facflities. '
3. -Reduction of overall-communications load within tie ERO through
. improved efficiency of information transfer.
This revision is scheduled for November 30, 1990. 1
The previously described Quarterly Dr m Program will be the vehicle for-
+
developing skills in this area.
Weakness (313/9008-03: 368/9008-03) r
.
Inadequate technical analysis of all potential consequences when resp'iding
to the exercise accident events constitutes an exercise weakness.
Resnonse
The -position of Accident Assessment Mr. nager has been added to the EOF ;
staff. The primary duties for this position are to: ,
1. Develop projections of potential accident pathways and their
consequences and propose mitigation -strategies to .the. EOF 3
Director.
]
2. Review ongoing response activities to ensure work priorities'are
adequ te, correct and consistent with long-term recovery goals.
3. Explore alternative solutions.
4. Recommend job-priority changes to the EOF Director, as necessary.
Action is' complete and becomes effective on July 30, 1990.
The Quarterly' Drill Program will be the vehicle used to develop proficiency
in this area.
'
-
In addition to the above, the staff of ERO Technical Assistants, which was
predominantly staffed by- SR0s, has been _ expanded to include approximately
'
25 Engineering personnel. This approximately doubles the number of
Technical Assistants allocated to emergency response. Selected Technical .
Assistant functions will be formally assigned upon ERO activation.
.-
'
Additional Technical Assistants are available to any ERO member upon
request through the Support Manager or his staff. 1
L Action is complete and becomes effective on July 30, 1990,
h .
1
,
ATTACHMENT TO OCAN079009 PAGE 2
l
L
. , . ._ ,, . - ,_ -
. _ _ .. ._ _ _ _ _ . _ _
, ,
,v E ,
,
. j
-
.6 .
';. ,
,
.
-
,a
"'
,
~ Weakness (313/9008-04: 368/9008-04)
.The failure to assign priorities and. assure timely information flow within .I'
the TSC constitutes an exercise ;<akness.
,
Resnonse .c
The Engineering Manager has been assigned the responsibility to assist the
.TSC Director in eve'uat W of established priorities for response
activities on a' continuous basu throughout, the emergency. This will.
ensure that prior 9ies establisheid by the TSC staff ate appropriate and
responsive to changes in tne nature and/or severity of the emergency.
Furthermore, the new ERO position of Accident Assessment Manager has been
+
given the responsibility for oversight- of job prioritization with an
emphasis on long-term aspects of accident assessment and recovery (the ,
o
Engineering Manager's responsibilities . are to concentrate' more on . the -
immediate recovery efforts).
The position 'of Radiation- Protection and Radwaste Manager. has been
relocated from the 0,nrations Support Center (OSC) to the TSC. This action
provides more readily available Health Physics expertise to the TSC- staff
and . facilitates the - flow of radiological information to the TSC. First
line' supervision of the 'Onsite Monitoring Teams remains with. the health
' Physics Supervisor in the OSC. s
- Action is complete for the aMve changes to become effective on July 30,
1990.
i
Improvenent in the flo1 of information will be accomplished as discussed in
the response to 9008-02.
The Quarterly ERF Drills will be the vehicle for developing proficiency in
this area. Refer to the response to weakness 9008-01 for the
implementation schedule. !
Weakness (313/9008-05: 368/9008-05)
,_
Inadequate and delayed technical analysis in the TSC constitutes an
l exercise weakness. ,
Resnonse
To address this weakness, action has been completed to add the position of
Radiation Protection and Radwaste Manager to the TSC staff (see response to
,
n
i weakness 9008-04), anct this change will become effective July 30, 1990.
- ~ This will enhance the technical expertise available in the TSC to address
radiological concerns. In addition,. a means of determining release rate
information will be available in the TSC with the install: tion of a
terminal for the Radiological Dose Assessment Computer System (RDACS).
L
l
l
ATTACHMENT TO OCAN079009 PAGE 3
i________ ___- _ . . . . _ ,
.. -- - _- -- - - . - - - - - .
- . ,
~
.
.
,.
v. .
~
. e
,.
,
s
.
This addition will provide the.TSC staff with direct access to radiological. i
t release rate and offsite dose' projection information. Technical personnel
.
'
will be trained and located in the TSC to interrogate RDACS and interpret
this information.
. Implementation for RDACS is scheduled for November 30, 1990..
l
The' TSC staff will also have available additional Operations and
Engineering expertise provided by the ERO Technical Assistants- (see '
response to weakness 9008-03) to aid the staff in assessing plant
conditions (e.g., determination of primary leak rate and its correlation.to t
, release rate). ,
Proficiency in the response measures taken to address this weakness will be
enhanced and continuously evaluated through the Quarterly Drill Program._
'
Weakness (313/9008-06; 368/9008-06)
,'
Examples .of incorrect and delayed information on status boards in the EOF
conttitutes an exercise weakness. .
i
-- Resnonse
A more specialized grw. of communicators will be trained and used for the. H
maintenance of ERF plant status boards and, additionally,
'
explicit ;
procedural instructions will be developed for status -board maintenance. l
L Furthermore,- steps will be added to the Emergency Plan - and implementing )
,
- procedures to provide more precisely. defined' information flow paths (see i
L response to weakness-9008-02). H
Implementation for these changes is scheduled for November 30, 1990. .
'
l
The Quarterly ERF. Drills will be the vehicle for developing proficiency in .l
L this area (refer to response to weakness 9008-01). _
Replacement of the Gaseous Effluent Radiation Monitoring System (GERMS)
L with RDACS phase II- will result in a reduction of time required to process-
l release rate data =for dose pror t'9ns from 20-30 minutes to approximately
l- 10 minutes. As a result, mon. . rent- information will be provided for
L
"
display on the - offsite ' radiological status board. This replacement is
scheduled to occur by November 30, 1990.
Weakness (313/9008-07: 368/9008-07)
. The inspectors noted that-the Dose Assessment (DA) supervisor was not aware
that neither of the two trains of the emergency ventilation systems had
L . been activated. Iodine removal efficiency in one train was less than 80%,
h but the system had not been shifted to the other train to improve filtering
efficiency and minimize offsite release. The lack of DA personnel
proficiency in; the EOF for the evaluation of the radiological release and
l
the consequential dose constitutes an exercise weakness.
1
! '
, ATTACHMENT TO OCAN079009 PAGE 4
. [L m _- ,_ . _ _ , . .
.,, . - . _- .. . - - . ..
,
2
( ,
v
T. ,. ,
..
i
l.
Resoonse ,
Radiological / Environmental Assessment Managers (REAM) and Dose Assessment
Supervisors (DAS) ~will be required to receive Emergency Systems Overview
j. Training. This course will include . information on Emergency Ventilation
-Systems. and is provided to selected ERO. positions and conducted by
i
Operations Training . Instructors. This additional requirement, when
'
combined with the added capabilities provided by the Accident Assessment
Manager in the EOF, will improve our ability to identify and employ !
measures for. minimizing the consequences of a release to the off-site
environment.
Implementation is scheduled. for November 30, 1990.
Weakness (313/9008-08i 368/9008-08)
-The inspectors observed that the EOF staff was in a reactive mode,.
monitoring data, and carrying out routine activities instead of adopting a-
dynamic and aggressive accident management. posture.. The DA staff did not
clearly demonstrate their -ability to perform analysis and explore
alternative solutions . to take corrective and preventive actions. The
.- inadequate technical analysis in the EOF constitutes an exercise weakness.-
Resoonse ,
As' discussed in the response to weakness 9008-03, the position of Accident-
Assessment Manager has been added to the EOF staff. This addition will
serve to- give the EOF a focal point for the development of accident
management strategies and will place. the EOF staff in a more proactive
mode.
As nientioned in.the response to weakness 9008-07, the REAM and DAS will be
requiredEto receive Emergency Systems Overview training; however, the-
primary responsibility for this type of analysis will rest with the
Accident Assessment Manager.
<
The quarterly ERF drills will be utilized to measure effectiveness and
enhance-proficiency in this area.
Implementation schedule for these items are discussed above.
, Weakness (313/9008-09: 368/9008-091
The NRC inspectors found that the EOF emergoney ventilation system had been i
turned off during activation of the EOF, and that the EOF HP supervisor was
not aware that it had been shut off until questioned by an inspector, l
Also, EOF personnel were not issued personal dosimetry as required by
~
1
. procedure. i
I
l
,
ATTACHMENT TO OCAN019009 PAGE 5
l
. , .-
._.- -_- - -
. - - - - - _ _ . - - -
~ -
'hE t
-
y.
- ... .g,
.
E.' : ,
Resnonse
'
The EOF : Activation' Checklist- has been revised to establish a requirement
for the EOF Maintenance Coordinator to apprise the EOF HP Supervisor of any
change in the status of the EOF Ventilation: System. The effectiveness of
this corrective action will be evaluated through the quarterly ERF drills.
Evaluation of EOF dosimetry needs is currently being' addressed in response.
to Inspector Follow-up Item 313/9018-01;368/9018-01.
Weakness (313/9008-10: 368/9008-10)
The licensee's. failure to provide an accurate briefing to the NRC response >l
team upon arrival and.the lack of work space for the NRC response team is l
ccasidered to be an' exercise weakness. I
Resnonse
1
- Preparation for NRC briefings will be an objective of the Quarterly. ERF .
Drills scheduled to begin in the fourth quarter of 1990 (refer _ to response
to weakness 9008-01). ' Proficiency in this area will be enhanced ' and !
continuously evaluated through this drill program.
ANO has recently instituted- the concept of colocation which encourages
~ 1icensee and responding agency officials. (NRC and Arkansas. Department of
Health) to work side-by-side during emergencies. Emergency Planning will
perform an evaluation of the current application of~this concept in the EOF
and make modifications accordingly. Implementation of the evaluation
results will take place by March 1, 1991.
Weak' ness (313/9008-11: 368/9008-111
The licensee'.s failure to provide for prompt, offsite radiological
measurements is considered to be an exercise weakness.
kesconse
The delay.in deployment of offsite_ monitoring teams was directly related to
problems _ associated .with the off-hours call-out of Health Physics
personnel. 'ANO will utilize an automated-computer based emergency
notification system. The new system will achieve an increase in the speed,
efficiency, effectiveness and reliability of our capability to activate the '
'
.
ERO, particularly .during non-routine working hours. Implementation for
this new call-out system is scheduled for completion by January 1,1991.
Additionally, as a result of a review of the current ERO staffing levels
and since the 1990 exercise, the staff of the Emergency Radiation Team has
been increased by approximately 25%. Training was completed on June 8,
1990..
o
ATTACHMENT TO OCAN079009 PAGE 6
.
.,m-- g% A* 'A S ~~W.-
A *'""* ., , ,
-
4
. . -
, t
,3
g. --
...s
{ : .;
.,. ..
-
'
<
,
.- + l
., i
. Weakness (313/9008-12 368/9008-12) ,
The licensee's apparent failure to adequately train fire brigade personnel ;
on.SCBAs is considered to be an exercise weakness. ;
i-
Response
Following the exercise, an evaluation of the Fire Brigade Training -Program' t
was. conducted.- The . evaluation revealed that the. program did not- contain
instructions in the use of respiratory equipment nor protective clothing. . !
The Fire Brigade training program has since been revised to include:
1. The addition of objectives which address the proper use of SCBAs i
and protective. clothing.
s
2. The demonstration of this knowledge through practical factors ;
sessions.
.$
-
. Training was completed on May 10, 1990.
General Coments ,
In response to NRC concerns that many weaknesses appear to be related to ;
'
inadequate training of emergency responders, Emergency . Planning n
conducting a comprehensive review and evaluation of the Emergency Planning
Training program currently in use. .,
s
E At this ' point, we recognize the need to' provide increased emphasis in !
,
practical application of topics now _ covered in ~ classroom training,
_particularly for new personnel who staff the Emergency Response Facilities.
One such change is the Quarterly ERF Drills discussed above. -Additionally, 1
- prospective ERO members in all positions wil1 ~ participate in a practical ,
L session,. such as a facility walk-through or tabletop drill, prior to formal- ;
D assignment.
L i
'
This evaluation, along with an implementation schedule based on. the ;
results, will be completed by December 31, 1990. ;
p
L
1
I
.
'
!.
l ..
h
L
r
s
ATTACHMENT TO OCAN079009 PAGE 7 ,
l
. . >