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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 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 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 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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV 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 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 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 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 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 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 ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls 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 ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations 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 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 ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 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 ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category:NRC TO U.S. CONGRESS
MONTHYEARML20205C2831988-10-0505 October 1988 Informs That Staff Completed Review of Portions of Ofc of Investigations Rept Addressing fitness-for-duty Issues Re Senior Manager at Plant & Licensee Investigation of Issues. Forwards AB Davis Re Resolution of Issue ML20247A9201988-09-0101 September 1988 Forwards Addl Info Re Status of Allegations of Misconduct by Manager at Plant on 861231,per ML20247A3061988-08-0202 August 1988 Responds to Re NRC Response to Allegations of Misconduct by Plant Manager at Plant on 861231.Matters Raised Subj of Investigation by Ofc of Investigations. Responses to Specific Questions & Related Info Encl ML20246Q3391988-07-0606 July 1988 Responds to 880613 Request Re 861231 Incident at Plant & Rulemaking on Fitness for Duty.Documentation Requested on NRC & Util Investigation of Incident Presently Being Used by Ofc of Investigations to Prepare Final Report ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20215H9431987-06-0505 June 1987 Advises That Review of B&W Designed Nuclear Power Plants Will Not Satisfactorily Address Safety Issues Associated W/ B&W Design.Supports Efforts to Create Independent Safety Review Board ML20215M0791987-05-0606 May 1987 Responds to Forwarding a Jones Expressing Concern Re Operation of facility.B&W-designed Facilities Meet NRC Regulation Applicable to Power Reactors or NRC Will Take Action.Related Info Encl ML20212Q0581987-03-17017 March 1987 Responds to 870123 Request for Inquiry Into 870101 Automatic Shutdown of Plant,Plant History & Public Safety Factors.Shutdown Caused by Obstruction in Lubrication Oil Line & Damage to Turbine Bearing & Main Shaft ML20210N2161986-09-25025 September 1986 Discusses Governor Celeste Opposing Full Power Operations of Plants.Order Bars Commission from Voting Until Further Order by Us Court of Appeals.Served on 860930 ML20155K3201986-05-21021 May 1986 Responds to Re Mj Lacy Concerns on Proposal to Bury Potentially Radioactively Contaminated Wastes at Site. Removal & Burial of Waste Would Reduce Already Low Likelihood of Contaminating Lake Erie NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco1986-04-23023 April 1986 Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress1986-04-23023 April 1986 Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress ML20155F2201986-04-0808 April 1986 Responds to Addressing Council of Mayfield Heights & Council of Lyndhurst Concerns Re Proposal to Bury Potential Radwastes Onsite.Resins Removed from Ponds for Disposal Via Dredging Operations ML20210H9521986-03-26026 March 1986 Responds to Re Public Health & Safety Concerns Concerning Proposal to Bury Potentially Radioactive Contaminated Wastes at Facility.Matl Proposed Consists of 34,000 Cubic Ft of Very Low Level Sludge Every 5 Yrs ML20210H9881986-02-25025 February 1986 Forwards Commission 860220 Order Referring Hearing Requests Re Low Level Waste Disposal at Facility to Administrative Judge for Consideration in Informal Adjudicatory Proceeding. W/O Encl ML20210H9791986-02-19019 February 1986 Responds to .Various Hearing Requests Re Low Level Radwaste Disposal at Facility Currently Pending Before Commission.Commission Order Re Hearing Requests Will Be Forwarded When Issued ML20137P5121986-01-24024 January 1986 Provides Info Concerning Financial Qualifications of Utils Re Safety of Plants.Nrc Regulation of Commercial Nuclear Power Based on Responsibility of Licensees for Safe Operation.Addl Views of Asselstine Encl ML20133C8231985-09-30030 September 1985 Forwards Documents Re NRC Response to 850609 Davis-Besse Incident,Per 850920 Request.Ie & Region III Documents Will Be Forwarded Upon Receipt.Documents Should Be Withheld from Public Disclosure,Pending Review Completed on 851001 ML20133D3401985-07-24024 July 1985 Responds to Re Facility.Commissioner Asselstine Believes Independent Investigation Warranted Re 850609 Event.Recommendations Will Be Considered Prior to Restart Decision.Generic Implications Will Be Determined IR 05000409/20050311985-07-16016 July 1985 Forwards Notice of Violation Issued to Util Based on 850409-0531 Insp ML20140H6231985-07-15015 July 1985 Forwards Press Release 85-95 Re NRC Proposed Fine Against Util for Alleged Violations of Safety Requirements During Apr 1985 ML20140J0451984-12-0303 December 1984 Forwards Press Release 84-52 Re NRC Proposed Fine Against Util for Alleged Safety Violations,Including Failure to Follow Approved Procedures During Operation of Startup Feedwater Pump ML20140J0091984-11-28028 November 1984 Forwards Press Release 84-134 Re NRC Proposed Fine Against Util for Five Alleged Violations,Including Inadvertent Shutdown of Control Room Emergency Ventilation Sys 1988-09-01
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217P2061999-10-26026 October 1999 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 ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV 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 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 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 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 ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207G0621999-06-0404 June 1999 Forwards Insp Rept 50-346/98-21 on 980901-1201 & 990425-0513.Violations Identified & Licensee Being Provided Opportunity to Either Respond to Violations within 30 Days or Inform NRC That LER Rept Already Contain Info Requested ML20207B8161999-05-25025 May 1999 Confirms Discussion Between Members of Staffs to Have Mgt Meeting on 990608 in Oak Harbor,Oh to Discuss Recent Performance at Davis-Besse as Described in Plant Performance Review ML20207B3141999-05-24024 May 1999 Informs That in September 1998,Region III Received Revision 20 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) ML20206T0881999-05-18018 May 1999 Confirms 990517 Telcon Between Lindsey & M Bielby Re Arrangements Made for Administration of Licensing Exam at Facility for Week of 990913 ML20206N5311999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Aj Mendiola Will Be Section Chief for Davis-Besse Npp.Organization Chart Encl ML20206H2291999-05-0707 May 1999 Forwards Proposed Change to Plant,Unit 1,TS Bases Section 2.2.1, Limiting Safety Sys Settings - Reactor Protection Sys Instrumentation Setpoints - Rc Pressure - Low,High & Pressure Temp ML20206B8171999-04-27027 April 1999 Forwards Insp Rept 50-346/99-05 on 990405-09.No Violations Noted.Purpose of Insp Was to Examine on-line Maint Risk Assessment Program Recently Implemented in Response to Maint Work Control Weaknesses ML20205G5681999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990202 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl ML20207G1701999-03-0505 March 1999 Forwards Insp Rept 50-346/99-01 on 990102-0212.No Violations Noted ML20207D4351999-02-25025 February 1999 Forwards Insp Rept 50-346/99-02 on 990202-05.No Violations Noted.Examples of Deficiencies with Station Procedures, Similar to Those Identified Through Staff self-assessments & in Previous NRC Insps,Were Noted IR 05000346/19960141999-02-17017 February 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/96-14 on 970225.Ack That Due to Plant Events,There Has Been Delay in Completion of C/As for Violation 50-346/96-14c ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20206S0811999-01-22022 January 1999 Forwards Insp Rept 50-346/98-18 on 981110-990102.No Violations Identified.Conduct of Activities at Davis-Besse Generally Characterized by Conservative Plant Operations, & Effective Engineering Involvement in Plant Issues ML20199H5821999-01-20020 January 1999 Forwards SE Re Ampacity Derating Issues Due to Application of Thermo-Lag Fire Barrier Matl at Plant ML20198E6821998-12-17017 December 1998 Forwards Insp Rept 50-346/98-20 on 981116-20.No Violations Noted.Implementation of Licensed Operator Requalification Program Was Generally Characterized by Safety Conscious Operations & Sound Evaluation of Operator Performance ML20198C9881998-12-15015 December 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Assigned Two SRAs to Each Regional Ofc.Sras Will Routinely Assess Licensee Event Repts,Plant Event,Insp Findings & EAs from Risk Perspective ML20198B5391998-12-0909 December 1998 Forwards Insp Rept 50-346/98-17 on 980918-1109 & NOV Re Inadequate Maint Work Order Used by Electrician During Removal of Primary Water Storage Tank Temp Indicator ML20196G1621998-12-0303 December 1998 Submits Response to Request for TS Interpretation Re Surveillance Interval Extension Allowances ML20196H4411998-12-0303 December 1998 Confirms Plans to Hold Meeting on 981216 in Lisle,Il,To Discuss Recent Performance at Davis-Besse & Actions Being Implemented by Licensee ML20198B1511998-12-0202 December 1998 Forwards Insp Activity Plan for Next 6 Months & Plant Issues Matrix.Infor Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite ML20196J5111998-12-0101 December 1998 Fowards Year 2000 Readiness Audit Rept,Which Documents Results of NRR Audit Conducted at Facility from 981027-29 ML20196D4371998-11-25025 November 1998 Discusses Concerns Re Announced Asset Transfer Between Firstenergy Corp & Duquesne Light Co ML20196C6491998-11-20020 November 1998 Forwards Insp Rept 50-346/98-19 on 981014-23.No Violations Noted.Inspectors Reviewed Circumstances Surrounding Events Leading Up to & Following Reactor Trip IR 05000346/19983011998-11-0909 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/98-301OL Issued on 980923.Effectiveness of C/A Will Be Reviewed Following Submittal of Root Cause Investigation Results ML20155J1471998-11-0303 November 1998 Informs That on 981007,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Exam Answer Key for Forms a & B,Grading Results & Individual Answer Sheets Encl.Without Encl ML20155B6641998-10-28028 October 1998 Forwards Safety Evaluation Re Request for Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154Q6711998-10-16016 October 1998 Forwards Insp Rept 50-346/98-15 on 980914-18.No Violations Noted.Emergency Preparedness Program Effectively Implemented During 980624 Tornado Event & Station Personnel Responded Well to Event ML20154Q5891998-10-14014 October 1998 Forwards Insp Rept 50-346/98-14 on 980808-0918.No Violations Noted.Online Safety Equipment Outages Were Performed Well & IAW Established Procedures ML20154H0241998-10-0606 October 1998 Discusses Arrangements Made During 980924 Telcon for Insp of Licensed Operator Requalification Program at Davis Besse Nuclear Power Station During Wk of 981116 ML20154D1801998-09-30030 September 1998 Forwards Insp Rept 50-346/98-16 on 980831-0904.No Violations Noted 1999-09-07
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((so o g UNITED STATES o NUCLEAR REGULATORY COMMISSION g y WASHWGTON, D. C. 20665 APR 8 M k*****/
The Honorable John Glenn United States Senate Washington, DC 20510
Dear Senator Glenn:
Your letter of February 25, 1986, to the Nuclear Regulatory Commission has bt en referred to me to address the concerns of the Council of Mayfield Heights and the Council of Lyndhurst regarding the proposal to bury potentially radio-actively contaminated wastes at the Davis-Besse Nuclear Power Plant site.
However, before I address those concerns, I want to inform you that, in response to a Conunission order, a notice was published in the Federal Register on March 14, 1986, which offers an opportunity for interested parties to intervene in an informal hearing to be held on this matter.
The material proposed for disposal consists of approximately 34,000 cubic feet every five years of very low level radioactive sludge. The material would be deposited in shallow trenches and covered with topsoil. There are several pathways for exposure to the material that can be postulated. These include standing over the disposal area, eating food grown on the disposal area, inhalation of wind borne dried sludge, and drinking ground water.
Because the disposal site is on land owned by Toledo Edison Company, the first two paths are unlikely and t'he method of disposal virtually eliminates the third path. The total body dose for the remaining path, drinking ground water, is estimated to be less than 0.1 millirem per year. The U.S. EPA has issued standards for the exposure of individuals to radioactivity from the nuclear fuel cycle. These standards specify that no member of the public receive an annual dose in excess of 25 millirem from planned discharges from nuclear fuel cycle operations. This dose would be only 0.4% of that exposure. When compared to the U.S. EPA drinking water standards applicable to community water supplies, the dose is 2.5% of the 4 millirem standard.
This low level of exposure does not represent a threat to public health and safety nor will it damage aquatic and wildlife in the vicinity.
The Resolution of Mayfield Village also expresses concern that the burial of the dredgings on the Davis-Besse site could result in release of radioactivity into Lake Erie as a result of flooding of the burial location. It should be noted that the material presently is in open settling ponds. Removal and burial of the dredgings would reduce the already low likelihood of this material reaching the lake.
To understand why this waste material is acceptable for on-site burial, it is important to understand the source of the wastes. The waste material consists of water purification resin sludge which has been accumulating in two on-site settling ponds since facility operation was authorized in 1977. The resin is 60 8604210413 860408 PDR ADOCK 05000346 H PDR
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used in the plant in two separate but similar applications. One application, the one that produces the most waste, is to purify raw water before it is used in the plant. This application does not result in any radioactively contaminated waste. The other application is to purify secondary system water
, before it is returned to the steam gererators to produce steam for use in the
- power conversion cycle. Possible leaks through the steam generator tubes j from the primary water cooling the reactor will carry some radioactive
- material into the steam system which can be removed by the water purification 1 resins-located in the secondary system. Radioactive contamination of these
- resins is normally very low since Davis-Besse has had an excellent record
- with respect to steam generator tube leakage. The longest half-life
{ associated with the contamination does not exceed 30 years and about 65% of 1 the contamination has a half-life of 5 years or less.
i When the purification resins are no longer effective in performing the purification function, they are transferred to a holding tank for monitoring j- and are replaced with fresh resin. Samples are taken to measure the amount of radiation present on the used resin. If significant radioactivity is i present, the resins are transferred within the plant to be further processed
- ~and prepared for shipment to licensed radioactive waste disposal sites. If i
- no significant radioactivity is measured, the resins are discharged to the j settling ponds. This process provides assurances that only very low level wastes are transferred into the settling ponds.
The resins which are discharged to the settling ponds settle to the bottom of j the ponds where they accumulate along with resins discharged from the raw i water purification process. The water which is used to flush the resins to '
- the settling ponds is discharged to Lake Erie. Periodically, the accumulated resins must be removed from the ponds by dredging and disposed of.
We trust that this letter has been fully responsive to the issues raised.
Please contact us if we can be of further assistance. <
l j Sincerely, i
Original signed by l
Victor Stello Victor Stello, Jr.
! Executive Director i for Operations ;
I i
l l
1 i REVISED IN ED0 4/2/86 0CA i *See previous white for concurrences.
! 4)(/I/86 PBD-6 PBD-6 PBD-6 D-PWR-B DD:NRR D:NRR ED0 ADeAgazio;cf*CMcCracken*
JStolz* FMira ita DEisenhut HDenton .Ste 3/21/ 6 3/21/86 3/21/86 3/21 86 3/ /86 3/31/86 4/ /86
- . __ . - . . _ _ _ - ___ _________.___-,_.-...-_.._J
The Honorable John Glenn United States Senate Washington, DC 20510
Dear Senator Glenn:
Your letter of February 25, 1986, to the Nuclear Regulatory Commission has been referred to me to address your interest in the NRC's actions with regard to the concerns expressed in correspondence received from your constituents regarding the proposal to bury potentially radioactively contaminat'ed wastes at the Davis-Besse Nuclear Power Plant site. You asked us to refer to the Council of Mayfield Heights and the Council of Lyndhurst in r response.
A copy of a Resolution adopted by the Council of Mayfield ights was included with your letter, so I will address the issues raised i hat resolution.
However, before I discuss those issues, I want to inf m you that, in response ,
to a Commission order, a notice was published in t ederal Register on March 14,'1986, which offers an opportunity for ip erested parties to intervene in an informal hearing to be held on this matt r.
The material proposed for disposal consists p approximately 34,000 cubic feet every five years of very low level radfoactive sludge. Using an estimate of the amount of radioactivity in the waste at the time of disposal, the NRC estimated the maximum radiation exposur/to individuals from possible exposure paths including standing over the disposal area, eating food grown on the disposal area, inhalation of windborpe dried sludge, and drinking ground water from the nearest well. The total body dose from all these paths combined for a single individual is less than 4 millirem / per year. The average annual dose from naturally occurring radiatip'n in Ohio is about 100 millirem. These estimates were reported in the RC's notice in the Federal Register on October 9, 1985.
To understand why this wasty material is acceptable for on-site burial, it is important to understand the source of the wastes. The waste material consists of water purification res/n sludge which has been accumulating in two on-site settling ponds since faqility operation was authorized in 1977. The resin is used in the plant in twd separate but similar applications. One application, the one that producesjthe most waste, is to purify raw water before it is used in the plant. Jhis application does not result in any radioactively contaminated waste.f The other application is to purify secondary system water before it is retur ed to the steam generators to produce steam for use in the power conversion cle. Possible leaks through the steam generator tubes from the primar ater cooling the reactor will carry some radioactive material into the steam system which can be removed by the water purification resins located in the secondary system. Radioactive contamination of these resins is normally very low since Davis-Besse has had an excellent record with respect to steam generator tube leakage. The longest half-life associated with the contamination does not exceed 30 years and about 65% of the contamination has a half-life of 5 years or less.
~ '
When the purification resins are no longer effective in performing the purification function, they are transferred to a holding tank for monitoring and are replaced with fresh resin. Samples are taken to measure the' amount of radiation present on the used resin. If significant radioactifity is present, the resins are transferred within the plant to be f,urther processed and prepared for shipment to licensed radioactive waste di,sposal sites. If no significant radioactivity is measured, the resins ar,e discharged to the settling ponds. This process provides assurances that'only very low level wastes are transferred into the settling ponds. /
Theresinswhicharedischargedtothesettling'/ ponds settle to the bottom of the ponds where they accumulate along with resins discharged from the raw water purification process. The water which is used to flush the resins to the settling ponds is discharged to_ Lake Erie. Periodically, the accumulated resins must be removed from the ponds by dredging and disposed of.
/
The Resolution of Mayfield VillageMxpresses concern that the burial of the dredgings on the Davis-Besse site'could result in release of radioactivity into Lake Erie as a result of f'iooding of the burial location or seepage into the ground to contaminate driiking water. With regard to the effects of potential flooding, it sho opensettlingponds.Remoy[ufdbenotedthatthematerialpresentlyisin 1 and burial of the dredgings would reduce the already low likelihood of' this material reaching the lake. With regard to contamination of ground/ water, this is one of the exposure paths examined by the NRC. The dose frpm' this path is less than 0.1 millirem. The US EPA has issued standards for/the exposure of individuals to radioactivity from the nuclear fuel cycle./ These standards specify that no member of the public receive an annual nuclear fuel cycle,operations.
dose in excess This doseof 25 millirem would from be only planned 0.4% of that discharges from exposure. When dompared to the US EPA drinking water standards applicable to community water / supplies, the dose is 2.5% of the 4 millirem standard.
We trust that this letter has been fully responsive to the issues raised in your letter. Please centact us if we can be of further assistance.
/ Sincerely, l
)
Victor Stello Acting Executive Director for Operations
- See previous white for concurrences.
PBD-6 PBD-6 PBD-6 JStolz*
D-ia DD:NRR dei D:d ED0 ADe Agazio;cf* CMcCracken* FM ut HDMton VStello 3/21/86 3/21/86 3/21/86 3/q 86 /86 3/$//86 / /86 ,
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2 When the purification resins are no longer effective in performing the purification function, they are transferred to a holding tank for monitoring and are replaced with fresh resin. Samples are taken to measure the amount of radiation present on the used resin. If significant radioactivity is present,Nthe resins are transferred within the plant to be further processed and prepare ( for shipment to licensed radioactive wastefdisposal sites. If no significah radioactivity is measured, the resins are discharged to the settling ponds This process provides assurances that only very low level wastes are tran .rred into the settling ponds. .
The resins which ar sdischarged to the settling podds settle to the bottom of thepondswheretheyaccumulatealongwithresins/dischargedfromtheraw water purification process. The water which is u' sed to flush the resins to the settling ponds is disqharged to Lake Erie.
resins must Se removed from the ponds by dredgi[,
g and disposed of. Periodically, t The Resolution of Mayfield V lage expresses c'oncern that the burial of the dredgings on the Davis-Besse s'te could result in release of radioactivity into Lake Erie as a result of f oding of ths burial location or seepage into the ground to contaminate drinki water. ) tith regard to the effects of potential flooding, it should be n ted that the material presently is in open settling ponds. Removal and bu ial of the dredgings would reduce the already low likelyhood of this mater l reaching the lake. With regard to contamination of ground water, this i o the NRC. The dose from this path is les,ne than of 0.1 the millirem.
exposure paths The USexamined EPA has by d iduals to radioactivity from the issuedstandardsfortheexposureof1/pec1 nuclear fuel cycle. These standards s that no member of the public receiveanannualdoseinexcessof$$ mill em from planned discharges from nuclear fuel cycle operations. This/ dose wo d be only 0.4% of that exposure. When compared to the US PA drinkin water standards applicable to community water supplies the dose s 2.5% of th 4 millirem standard.
We trust that this letter has be fully responsi e to the issues raised in your letter. Please contact us f we can be of fu ther assistance.
Sincerely, l
Victor Stello , Jr. ,
Acting Executive Directo \
for Operations PBD-6 PBD- " 'D-PWR-B DD:NRR D:NRR ADe Agazio;cf CMcCracken JSt61z FMiraglia DEisenhut HDenton 3/2 //86 3/f//86 3/3//86 3/ /86 3/ /86 3/ /86
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p DISTRIBUTION FOR GREEN TICKET # 001502 Dduket File or Central File NRC PDR w/inc.
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EDO # 001502 EDO Rdg' H. Denton/D. Eisenhut-
. PBD-6 Rdg w/ copy of inc.
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?% e FDO PRINCIPAL CORRESPONDENCE CONTROL
&S FROM: DUE: 03/ b86 EDO CONTROL: 001502 DOC DT: 02/25/86 SEN. JOHN GLENN FINAL REPLY:
TO OCA FOR SIGNATURE OF: ** GRFFN ** SFCY NO: 86-202 EXECUTIVE DIRECTOR DESC: ROUTING:
l ENCLOSES LETTER FROM DONNA HEATH, MAYFIELD VIIt. AGE KERR, SP RE RESOLUTION 86-8 TO NRC OPPOSING APPLICATION OF DAVIS TOLEDO EDISON CO TO BURY RADIOACTIVE StUDGE AT KEPPLER DAVIS-BESSE PLANT GCUNNINGHAM
, DATE: 03/07/86 l ASSIGNED TO: NRR CONTACT: DENTON SPECIAL INSTRUCTIONS OR REMARKS:
Ch ,
h NRR RECEIVED:._ 03/07/86 ACTION: *s4ShpjE 6 7 f'
f' /
.NRR ROUTING: DENTON/EISENHUT PPAS M0SSBURG/ TOMS
- i
t OFFICE OF THE SECRETARY CORRESPONDFNCE CONTROL TICKET PAPER NUMBER: CRC-86-0202 LOGGING DATE: Mar 5 86 ACTION OFFICE: EDO l
AUTHOR: J. Glenn l AFFILIATION: U.S. SENATE LETTER DATE: Feb 25 86 FILE CODE: ID&R-5 Davis Besse l
SUBJECT:
Toledo Edison's appl for the disposal of l radioactive waste at the Davis-Besse plant ACTION: Direct Reply DISTRIBUTION: OCA to Ack SPECIAL HANDLING: None i NOTES:
l DATE DUE: Mar 14 86 SIGNATURE: . DATE SIGNED:
AFFILIATION:
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