ML19296D378
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| ML19296D378 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Arkansas Nuclear, Crystal River, Midland  |
| Issue date: | 02/26/1980 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Hanauer S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296D379 | List: |
| References | |
| NUDOCS 8003040484 | |
| Download: ML19296D378 (1) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999
[Table view]Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr 1CAN109906, 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 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 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 ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217F9941999-10-15015 October 1999 Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl 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 ML20217J5171999-10-13013 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 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 ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV 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 ML20212L0771999-10-0404 October 1999 Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii) 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made ML20217D6551999-10-0101 October 1999 Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025 ML20212J8481999-10-0101 October 1999 Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II 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 ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification 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 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 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 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls 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 ML20212F7251999-09-23023 September 1999 Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable ML20212F7331999-09-23023 September 1999 Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition 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) ML20212E6741999-09-21021 September 1999 Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 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 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief ML20212F3141999-09-13013 September 1999 Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations 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 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation 1999-09-09 Category:INCOMING CORRESPONDENCE 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
[Table view]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 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 ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl 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 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made 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 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 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 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 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 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 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls 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 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 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 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 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief 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 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation 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) 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 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 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) 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 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl 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 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant 1999-09-09 Category:VENDOR/MANUFACTURER TO NRC MONTHYEARML20059B5801990-08-23023 August 1990
[Table view]Forwards Signed Affidavit Committed in Licensee 900808 Revised Request for License Amend to Increase Reactor Power to 100% Full Power & Nonproprietary Calculation 86-1179795-02, Arkansas Nuclear One-1 HPI Flow Rate ML20005D6401989-11-30030 November 1989 Forwards Affidavit Supporting Proprietary Info in 891121 Ltr from Jj Fisicaro Re Amend to Increase Reactor Power Level to 100% Power ML19325E9001989-10-19019 October 1989 Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response ML20245K4861989-06-0606 June 1989 Advises That Valves in Photographs & Mfg Records Forwarded to Licensee Identified as Mfg by Velan,Inc.Marking Info Provided by Florida Power Corp Matches Perfectly W/Licensee Mfg Records ML19324C3151989-02-20020 February 1989 Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987 Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request LD-86-034, Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups1986-08-0101 August 1986 Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups LD-86-024, Forwards Proprietary & Nonproprietary Rev 0 to CEN-330,Rev 01 to CEN-304 & Rev 01 to CEN-305 Re Improvement Program. Proprietary Repts Withheld (Ref 10CFR2.790).Affidavit for Withholding Repts Encl.Fee Paid1986-05-21021 May 1986 Forwards Proprietary & Nonproprietary Rev 0 to CEN-330,Rev 01 to CEN-304 & Rev 01 to CEN-305 Re Improvement Program. Proprietary Repts Withheld (Ref 10CFR2.790).Affidavit for Withholding Repts Encl.Fee Paid LD-86-022, Forwards Proprietary Suppl 1,Rev 3 to CEN-39(A)-P & Nonproprietary Suppl 1,Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure. Affidavit Encl.Proprietary Rept Withheld (Ref 10CFR2.790).Fee Paid1986-04-0808 April 1986 Forwards Proprietary Suppl 1,Rev 3 to CEN-39(A)-P & Nonproprietary Suppl 1,Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure. Affidavit Encl.Proprietary Rept Withheld (Ref 10CFR2.790).Fee Paid LD-86-012, Forwards Revs 0 to Proprietary CEN-323-P & Nonproprietary CEN-323-NP, Reload Data Block... & Revs 3 to Proprietary CEN-39(A)-P & Nonproprietary CEN-39(A)-NP, CPC Protection Algorithm.... Proprietary Repts Withheld (Ref 10CFR2.790)1986-02-10010 February 1986 Forwards Revs 0 to Proprietary CEN-323-P & Nonproprietary CEN-323-NP, Reload Data Block... & Revs 3 to Proprietary CEN-39(A)-P & Nonproprietary CEN-39(A)-NP, CPC Protection Algorithm.... Proprietary Repts Withheld (Ref 10CFR2.790) LD-85-044, Forwards Proprietary & Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program. Proprietary Rept Withheld (Ref 10CFR2.790)1985-08-30030 August 1985 Forwards Proprietary & Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program. Proprietary Rept Withheld (Ref 10CFR2.790) LD-85-043, Forwards Nonproprietary Revs 00 to CEN-304-NP & CEN-305-NP & Proprietary Revs 00 to CEN-304-P & CEN-305-P,per NRC Request for Generic Design Specs.Proprietary Repts Withheld (Ref 10CFR2.790)1985-08-30030 August 1985 Forwards Nonproprietary Revs 00 to CEN-304-NP & CEN-305-NP & Proprietary Revs 00 to CEN-304-P & CEN-305-P,per NRC Request for Generic Design Specs.Proprietary Repts Withheld (Ref 10CFR2.790) ML20098C8591984-08-14014 August 1984 Alleges That Unqualified Suppliers Awarded Contracts from Plants to Provide Flexible Conduits Unqualified Under IEEE Stds 323 & 344 Despite IEEE Bid Requirements.Meeting Re NRC Position on safety-related Installations Requested LD-84-039, Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion1984-07-27027 July 1984 Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion ML20094C1431984-07-24024 July 1984 Forwards Extension of Retainer Lifetime to Four Cycles, for Oconee,Unit 3 W/Results of Exams of Two Retainers After Three Cycles.Approval of four-cycle Retainer Usage Requested Before Dec 1984 ML20023A7911982-10-0505 October 1982 Provides Preliminary Info as Result of Fuel Insp That Revealed Need to Modify Some Batch C Fuel Assemblies to Provide Addl Space for Axial Growth of Fuel Rods ML20039A7721981-12-0808 December 1981 Forwards Power Train - Hybrid Computer Simulation of B&W Nuclear Power Plant. Cross-reference Between NRC 790404 Questions on BAW-10070 & Topical Rept on Power TRAIN,BAW- 10149 Included ML20010F7391981-09-0202 September 1981 Forwards BAW-10149, Power Train - Hybrid Compuer Simulation of B&W Nuclear Power Plant. Rept Provides Addl Info Re Extent of Power Plant Modeling & Addresses NRC Question 4. W/O Encl ML19275J6791981-07-0808 July 1981 Informs of Interest in Continuing to Receive Info Re Facility,In Response to 810701 Ltr.Requests That Name Remain on Mailing List ML1119601291981-03-12012 March 1981 Advises of Potential Deficiency Affecting Transmitter Models N-E11,N-E13 or E11,E13 W/Suffix Codes Mca,Mca/Rrw or Mca/Rr. Possible Use of Incorrect Insulating Sleeving on Transistor & Zener Diode Lead Wires in Amplifier ML19347C0841980-10-0606 October 1980 Forwards Summary of 800908 Conference Call Re Soil Settlement Problem ML20064K1351980-10-0101 October 1980 Forwards Bending Stresses in Underground Piping Due to Differential Soil Settlement, Profiled in 800401 Response to NRC Request ML19309F5121980-04-16016 April 1980 Forwards Safety Sequence Diagrams,Event Trees Developed from Safety Sequence Diagrams & Auxiliary Diagrams on Behalf of B&W Owners Group,In Response to NRC 800222 Request.Diagrams Withheld (Ref 10CFR2.790) ML16245A7331980-03-17017 March 1980 Advises That B&W Prepared & Transmitted to Affected Utils Info Re Failure Discovered at Weld Attachment Between Collar & Thermal Sleeve on Auxiliary Feedwater Nozzles of Steam Generator.Nrc Should Contact Utils for Info ML19305A8421980-03-11011 March 1980 Forwards Preliminary Rept,Transient Assessment Rept,Reactor Trip on 800226, in Partial Response to NRC 800304 Request for Info Re Power Upsets at B&W Plants ML19296D3781980-02-26026 February 1980 Forwards Structural Effects of ATWS Overpressure Transients in Byron Jackson Primary Pumps, Addendum to Analysis of B&W Nuclear Steam Sys Response to ATWS Events. ML20126B9341980-02-12012 February 1980 Confirms 800207 Telcon Re Failure of Valves.Forwards Part 21 Rept ML19210D3021979-11-20020 November 1979 Responds to NRC 791114 Request Re Consideration of Effect of Employing NRC Ramp Rate Correlation as Contained in Draft NUREG-0630 to Determine Burst Temp Curve for Use in LOCA Analyses ML19210D3201979-11-19019 November 1979 Responds to 791117 Concern Re Structural Integrity of Facility Seismic Supports in Ref to Other B&W Plants. Evaluation Completed.Problem Is Not Generic.No Safety Concern Exists ML19210D3551979-11-16016 November 1979 Submits Evaluation of Potential Impact of Heating Rate Dependent Burst Temp on C-E Licensing Calculations.Peak Cladding for C-E Operating Plants Would Not Be Significantly Affected by Heating Rate Dependent Rupture Temp Model ML17207A3471979-08-29029 August 1979 Forwards Proprietary Version of CEN-115-P,in Response to IE Bulletin 79-06C Items 2 & 3.Response Withheld (Ref 10CFR2.790) ML19208A4061979-07-30030 July 1979 Notifies That Recently Shipped Batteries Probably Will Not Meet Requirements of IEEE Stds 323-74 & 344-75 ML19241B8871979-07-18018 July 1979 Responds to 790713 Ltr.Plant Operation Significantly Affects Employment Opportunities in Midland County,Mi.Govt Bureaucracy Should Not Cause Undue Delay in Facility Completion.Certificate of Svc Encl ML19270G4741979-05-30030 May 1979 Discusses Mod of Operating Guidelines for Small Breaks.Hpi Must Remain in Operation Until LPIS Is in Operation & Flowing in Excess of 1,000 Gallons/Minute in Each Line & Stable for 20 Minutes ML19242B5121979-05-30030 May 1979 Requests Meeting at Earliest Possible Date Between Util & NRC to Discuss Scheduled Completion Date of Plant ML19269E8261979-05-30030 May 1979 Requests Meeting to Resolve Differences Over Const Schedule & Completion Date.Opposes Delay in Licensing Proceedings ML19241B2231979-05-15015 May 1979 Responds to NRC 790316 Ltr Re Deviation Noted in QA Program Insp Rept 99900116/79-01.Corrective Actions:All Wires/Lugs Have Been Reinspected & Wires Requiring Rework Have Been Machined ML19291A5091979-05-11011 May 1979 Submits Schedule for Completion of Generic Licensing Topical Rept in Response to NRC 790426 Request ML19225D0371979-03-13013 March 1979 Responds to IE Bulletins 78-12 & 12A.Forwards Rept Records Investigation Rept Related to Off-Chemistry Welds in Matl Surveillance Specimens & Responses to IE Bulletins 78-12 & 78-12A Suppl. W/O Encl ML20114E7451979-03-13013 March 1979 Forwards Records Investigation Rept Related to Off-Chemistry Welds in Matl Surveillance Specimens & Responses to IE Bulletins 78-12 & 78-12A. W/O Encl ML17244A6941979-03-13013 March 1979 Forwards Response to IE Bulletins 78-12 & 78-12A, Records Investigation Rept Re Off-Chemistry Welds in Matl Surveillance Specimens & Responses to Bulletin 78-12&78-12A Suppl. Concludes Crystal River 3 Isolated Event ML20062D3881978-10-11011 October 1978 Reports That Addl Isolation Bar Must Be Added to Class IE Battery Racks Sent to Subj Facils in Order to Isolate Horizontal Momentum During Seismic Events.Design Is Being Worked Out & Will Be Ready in 60 Days for Retrofit ML19326C5481978-08-30030 August 1978 Ack Receipt of NRC 780613 Ltr & NRC Correspondence W/Utils. Response to NRC Request Re Control Rod Guide Tube Integrity Will Require Four Months.Utils Will Supply Info to NRC & Addl Info Requests Should Be Directed to Utils ML19326C6961978-03-0909 March 1978 Forwards Evaluation of Potential Safety Concern Re Nuclear Instrumentation/Reactor Protection Sys Failure Due to Loss of Ground ML19344D7991977-03-18018 March 1977 Confirms 770318 Telcon W/Beckhofer Re Dow Chemical Co Response to Mm Cherry Emergency Motion for Directed Certification.Dow Chemical Co Has No Position on Mm Cherry Motion.Svc List Encl ML19331A6171977-03-0909 March 1977 Discusses Effect of Midland Proceeding Delays on Dow Chemical Co Steam Supply.Dow Chemical Co Has No Views on CPC 770304 Motion to Continue Proceedings & Will Abide by ASLB Decision.Svc List Encl ML19331A5421977-03-0101 March 1977 Forwards Proposed Corrections to 770201 & 02 Transcript of Jg Temple Testimony.Certificate of Svc Encl.Related Correpondence ML19319B9701977-02-23023 February 1977 Advises of Potential Failure in 400 a Stab on Westinghouse Motor Control Ctrs.Info Re Retrofit to Be Provided ML19319D1441977-01-24024 January 1977 Forwards Proposed Revision to B&W ECCS Evaluation Model. Supersedes 761216 Revision.After NRC Approval,Change to Be Incorporated Into BAW-10104A,Revision 1, B&W ECCS Evaluation Model. ML19338C0491977-01-12012 January 1977 Forwards Three News Articles Re Interviews W/Members of EPA & Mi Air Pollution Control Commission.Dow Takes No Position Re Accuracy of Articles.W/O Encl.Related Correspondence 1990-08-23 |
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Babcock &Wilcox me, ceme, co c,co P.o. Box 1260. Lynchburg, Va. 24505 Telephone: (804) 384-5111 February 26, 1980 Dr. S. H. Hanauer Assistant Director for Plant Systems Division of Systems Safety Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
ATWS Letter Report Addendum
Dear Dr. Hanauer:
Attached is an addendum to B&W Co. letter report on ATWS," Analysis of B&W NSS Response to ATWS Events", BAW 1610, January 1980. This addendum, " Structural Effects of ATWS Overpressure Transients in Byron Jackson Primary Pumps", covers ceactor coolant pumps for Consumers Power Co's Midland 1&2, Arkansas Power & Light ANO-1, Florida Power Corp. Crystal River 3 and Toledo Edison Co, Davis Besse 1.
As can be seen from the table on page 4-6 of letter report, BAW 1610, this type pump represents the mid range of pump over stress reported at 3500 & 4000 psig in that report and may be considered fairly typical of other B&W plant / pump combinations.
Similiar reports to cover the o ..er B&W plant / pump vendor combinations shown in table 4-6 of BAW 1610 are under preparation and will be forwarded to you when completed.
Five copies of this addendum have been sent under separate cover to your office marked to the attention of Mr. Ashok Thadani. The remaining 36 copies, also, will be forward to Mr. Thadani within a week.
If you have any questions regarding this submittal, please call.
Very truly yours,
~, ,
,Q', . ,' I- . : j'j' 1 Manager of Licensing cc: R. B. Borsum 3 A. Thadani j, J. Ted Enos, Chairman, Owners Gruup ATWS Comittee // /
C The Babcock & Wilcox Company / Estabhsned 1867
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