ML19249A372
Letter Sequence Approval | |
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TAC:52156, (Approved, Closed) | |
Initiation Administration Results
Other: L-85-001, Comments on Generic Ltr 85-01, Fire Protection Policy Steering Committee Rept. Revised Interpretations of App R Requirements,Proposed Enforcement Action Guidance & Proposed Fire Protection License Condition Encl, ML13309B382, ML13310A255, ML13310B109, ML13310B303, ML13311A389, ML13316A877, ML13317A139, ML13317A430, ML13317B481, ML13317B484, ML13317B485, ML13323A455, ML13324A724, ML13324A726, ML13324A804, ML13324A807, ML13324A839, ML13326A740, ML13326A742, ML13330B160, ML13331A845, ML13331A954, ML13333B085, ML13333B918, ML17328B057, ML19249A376, ML19249A382, ML19256A614, ML19256A618, ML19317H481, ML19319D898, ML19319D903, ML19340B388, ML19340D243, ML19343B503, ML19343B506, ML19343C515, ML19350E266, ML20003D588, ML20009C888, ML20010E308, ML20024E960, ML20038A915, ML20039D540, ML20040C821, ML20041A980, ML20069N118, ML20076H115, ML20080G331... further results | |
MONTHYEARML19317G9761977-12-0808 December 1977
[Table View]Responds to NRC 770804 Request.Forwards Review of Requirements,Commitments & Procedures in Conjunction W/ Proposed Tech Specs Re Fire Protection.Util Has Complied W/Fire Protection Responsibilities During NRC Audits Project stage: Request ML19309A1261978-02-28028 February 1978 Double Bibbed Supplied-Air Hood, Prepared for Doe.Fr Notice Re Respiratory Protective Devices,Tests for Permissability & Fees Encl Project stage: Request ML19319D8981978-02-28028 February 1978 Amend 19 to License DPR-54,adding License Conditions to Completion of Fire Protection Mods Project stage: Other ML19319D9021978-02-28028 February 1978 Safety Evaluation for Fire Protection Sys Supporting Amend 19 to License DPR-54 Project stage: Approval ML19319D9031978-02-28028 February 1978 Notice of Issuance & Availability of Amend 19 to License DPR-54 Project stage: Other ML19319D8961978-02-28028 February 1978 Forwards Amend 19 to License DPR-54,safety Evaluation & Notice of Issuance & Availability.Requests Addl Info by 780301 Project stage: Approval IR 05000312/19780081978-06-19019 June 1978 IE Investigation Rept 50-312/78-08 on 780609.No Noncompliance Noted.Major Area Investigated:Allegation That Bechtel Neglected to Correct Significant Design Error in 1972 Project stage: Request ML19309B0561978-08-28028 August 1978 Submits Proposed Mod Design Details Re Fire Protection in Response to NRC 780228 Request for Addl Info Per Fire Protection Safety Evaluation.Revision of OL Amend 19 Requested to Delete Ref to Fire Area 50 Project stage: Request ML19269B7831978-11-14014 November 1978 Responds to NRC 780921 Rejection of Design Criteria for Installation of Ionization Detectors in Areas Containing Both Combustibles & Equipment/Cables Required for Safe Shutdown.Requests Approval of Schedule to Make Related Mods Project stage: Request ML20148T4491978-12-0101 December 1978 Application for Amend 61 to License DPR-54,reflecting Changes to Table 3.1 of Fire Protection Safety Evaluation Project stage: Request ML19256A6111978-12-14014 December 1978 Forwards Amend 25 to License DPR-54 in Response to 781201 Application.Revises Completion Date for Mods Intended to Improve Fire Protection at Facility.Also Forwards Suppl 1 to Fire Protection Safety Evaluation Supporting Amend Project stage: Approval ML19256A6141978-12-14014 December 1978 Amend 25 to License DPR-54 Revising Completion Date for Mods Intended to Improve Level of Fire Protection at Facility Project stage: Other ML20147H1371978-12-14014 December 1978 Approves Supplemental Info Re Section 3 of Fire Protection Ser,Including Installation of Thermal Insulation on Channel A,C & D Conduits,Mod of Lube Oil Pump Control Circuits Associated W/Hpis & Procedures for Diesel Generators Project stage: Other ML19256A6181978-12-14014 December 1978 Notice of Issuance & Availability of Amend 25 to License DPR-54 Project stage: Other ML19256A6151978-12-14014 December 1978 Safety Evaluation Supporting Amend 25 to License DPR-54 Project stage: Approval ML19261C5191979-02-27027 February 1979 Forwards Safety Evaluation Rept for Fire Protection Program. Concludes Program,W/Scheduled Mods,Meets General Design Criterion 3 & Is Therefore Acceptable Project stage: Approval ML19261C5211979-02-27027 February 1979 Fire Protection Safety Evaluation Rept. Until Scheduled Improvements Are Made,Present Fire Protection Tech Specs Provide Sufficient Protection Against Fire Threatening Safe Shutdown Project stage: Approval ML13317B4841979-04-26026 April 1979 Reactor Overpressurization System PT-425X1 & PT-425X2 Installation Detail Project stage: Other ML19249A3821979-07-26026 July 1979 Notice of Issuance & Availability of Amend 18 to License NPF-3 Project stage: Other ML19249A3761979-07-26026 July 1979 Amend 18 to License NPF-3,adding License Condition Re Completion of Facility Mod for Fire Protection & Modifying Tech Specs to Require Five Individuals W/Fire Protection Training on Site Project stage: Other ML19249A3721979-07-26026 July 1979 Forwards Amend 18 to License NPF-3,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML19249A3781979-07-26026 July 1979 Fire Protection Safety Evaluation Supporting Amend 18 to License NPF-3 Project stage: Approval ML19257D6631980-01-17017 January 1980 Advises of Acceptability of Designs Proposed for Implementing Mods Re NRC Fire Protection Safety Evaluation Sections 3.1.30(2) & 3.1.31(2).Makeup Pump Room & Penetration Valve Area Altered to Assure Safe Shutdown Project stage: Approval ML19317H4811980-05-19019 May 1980 Forwards Proposed Rule Entitled, Fire Protection Program for Nuclear Power Plants Operating Prior to 790101. Rule Adds New Section 50.48 & App R to 10CFR50 & Is Expected to Be Published in Fr by End of May Project stage: Other ML19340B3881980-09-25025 September 1980 Forwards Questions Re Proposed Amend 68 to Tech Specs Project stage: Other ML19351D6201980-10-0707 October 1980 Application for Amend to License NPF-3,providing Tech Specs for Fire Detection Sys Per License Condition 2.c(4) Project stage: Request IR 05000346/19800161980-11-18018 November 1980 IE Insp Rept 50-346/80-16 on 800609-11 & 1020-24.No Noncompliance Noted.Major Areas Inspected:Refueling Outage Maint,Plant Operations Review & Equipment Calibr Project stage: Request ML19343B5061980-11-18018 November 1980 Notice of Issuance & Availability of Amend 34 to License NPF-3 Project stage: Other ML19343B5031980-11-18018 November 1980 Amend 34 to License NPF-3,modifying Tech Specs to Include Fire Detection Instrumentation Mods Project stage: Other ML17328B0571980-11-24024 November 1980 Ltr to All Power Reactor Licensees W/Plants Licensed Prior to 790101.Forwards Revised Section 10CFR50.48 & App R Re Fire Protection Features in Nuclear Power Plants & List of Requirements for Resolution of Open Issues.W/O Encl Project stage: Other ML19340D2431980-11-24024 November 1980 Forwards Revised 10CFR50.48 & App R to 10CFR50 Re Five Protection Features of Nuclear Power Plants.Rules Take Effect 810217.Summary Listing of Open Items Re Fire Protection Features of Facility Encl Project stage: Other ML20151B3601980-12-26026 December 1980 Application for Amend of License NPF-3 Changing Tech Specs Re Fire Detection Sys,Decay Heat Removal Capabilities,Low Temp RCS Overpressure Event,Axial Power Shaping Rod Insertion Limits & Util Reorganization Project stage: Request ML20126F9621981-03-17017 March 1981 Ceramic Fiber Blanket Wrap for Fire Protection of Cable Trays & Conduits Project stage: Other ML19343C5151981-03-17017 March 1981 Discusses Util Plans for Implementing App R Requirements to 10CFR50 Re Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101,in Response to NRC 810220 Request.Reassessment of Each Fire Area Encl Project stage: Other ML20003D5881981-03-19019 March 1981 Responds to Re Submittal of Plans,Schedules & Design Descriptions of 10CFR 50,App R,Mod for Fire Protection.Forwards Design Description of Alternate Svc Water Capability Project stage: Other ML19350E2661981-06-10010 June 1981 Requests re-evaluation of Class III Fees Assessed for 810319 Proposal for Alternate Svc Water Capability.Review of Amend 18,Item B Requirements Stated No License Amend Fee Required for Response to Proposal.Class III Fee Encl Project stage: Other ML20009C8871981-07-10010 July 1981 Application for Amend of License NPF-3,revising Tech Specs for Auxiliary Feedwater Pump Turbine Speed Switches,Setpoint Index for Pressurizer Electromatic Relief & Code Safety Valves,Emergency Diesel Generator & Administrative Errors Project stage: Request ML20009C8841981-07-10010 July 1981 Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs Project stage: Request ML20009C8881981-07-10010 July 1981 Marked-up Revised Tech Specs 3.4.2,4.4.2,3.4.3,4.4.3, 3.8.1.2,4.8.1.2,4.8.1.1.2,4.8.1.1.2.C.2,3.1.3.6,3/4.2,3.2.1, 4.2.1,3.2.5,6.5.2.2,6.5.2.3,6.5.2.4,6.5.2.5,6.5.2.6, 3/4.7.10,3.7.10,4.7.10,Pages 3/4.7-5,B 3/4.4-19 & 3.8.1.2 Project stage: Other ML20010E3081981-08-20020 August 1981 Amend 35 to License DPR-54 Revising Tech Specs to Incorporate Newly Installed Fire Protection Sys Project stage: Other ML20010E3051981-08-20020 August 1981 Forwards Amend 35 to License DPR-54,safety Evaluation & Notice of Issuance.Amend Revises Tech Specs to Incorporate Newly Installed Fire Protection Sys Project stage: Approval ML20010E3111981-08-20020 August 1981 Notice of Issuance of Amend 35 to License DPR-54 Project stage: Approval ML20010E3091981-08-20020 August 1981 Safety Evaluation Supporting Amend 35 to License DPR-54 Project stage: Approval ML20038A9151981-11-19019 November 1981 Forwards Sketches of Raceway Layout in Fire Area 47 of Facility,In Response to Gage-Babcock Associates,Inc Request. Trays M39A1,M39AG1 & M39AD8 Have Been Insulated W/Kaowool Blankets.Table Re Function of Raceway Cables Encl Project stage: Other ML20039D5401981-12-14014 December 1981 Advises of Postponement Until 820122,for Installation of Control Room Emergency Lights Required by 10CFR50.48. Installation of Lights Requiring Outage for Placement Will Begin Sept 1982.Delays Due to Late Deliveries Project stage: Other ML20040C8211982-01-0707 January 1982 Special Rept:Due to TMI-related Mods,Several Fire Barrier Penetrations Have Been non-functional for Periods Greater than 7 Days Project stage: Other ML20040E2041982-01-12012 January 1982 Forwards Safety Evaluation of Westinghouse Basic Safety Rept.Transient Analysis for Startup of Inactive Reactor Coolant Pump,Excess Load & Loss of Normal Feedwater Acceptable Project stage: Approval ML20041A9801982-02-12012 February 1982 Advises That NRC Will Conduct Fire Protection Review on 820208 to Evaluate Util 810317 Request for Exemptions from Section III.G.2 & Iii.J of App R to 10CFR50.Social Security Info Withheld Per Privacy Act Project stage: Other ML20054C9511982-04-0808 April 1982 Submits List of Drawings Needed for Consideration Re Proposed Facility Mods for App R,Per 820323 Meeting Project stage: Meeting ML20053E5241982-06-0202 June 1982 Safety Evaluation Supporting Requested Mods to 10CFR50 & 10CFR50.48 App R Project stage: Approval 1980-12-26 |
ML19249A372 | |
Person / Time | |
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Site: | Davis Besse ![]() |
Issue date: | 07/26/1979 |
From: | Reid R Office of Nuclear Reactor Regulation |
To: | Roe L TOLEDO EDISON CO. |
Shared Package | |
ML19249A373 | List: |
References | |
TAC-52156, NUDOCS 7908220353 | |
Download: ML19249A372 (4) | |
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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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 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 05000346/LER-1998-001-01, Forwards LER 98-001-01,which Provides Addl Info Re 980407 Occurrence.Changes Are Marked with Rev Bar in Margin.List of Util Commitments,Encl1999-07-13013 July 1999 Forwards LER 98-001-01,which Provides Addl Info Re 980407 Occurrence.Changes Are Marked with Rev Bar in Margin.List of Util Commitments,Encl 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 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 PY-CEI-NRR-2377, 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 11999-06-16016 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 ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves 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 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 ML20207F4231999-06-0202 June 1999 Forwards Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504, IAW 10CFR50.4.NRC Evaluated Exercise Has Been Rescheduled for 991208,since NRC Did Not Evaluate 990504 Exercise 1999-09-07 Category:NRC TO UTILITY MONTHYEARML20058H6411990-11-0909 November 1990
[Table view]Forwards Final SALP Rept 50-346/90-01 Covering Mar 1989 to June 1990 ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058D6771990-10-25025 October 1990 Forwards Exemption Request for Reactor Operators Selected for NRC Requalification Exam ML20058F4811990-10-24024 October 1990 Forwards Safety Insp Rept 50-346/90-16 on 900814-1009.No Violations Noted ML20062C6811990-10-18018 October 1990 Forwards Safeguards Insp Rept 50-346/90-19 on 900924-28.No Violations Noted ML20059N6661990-10-0909 October 1990 Forwards Correction to SER Re Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements.W/O Encl ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L6041990-09-14014 September 1990 Confirms 901002 Meeting at Plant Site to Present Initial SALP 8 Rept for Facility ML20059J2511990-09-13013 September 1990 Forwards Safety Insp Rept 50-346/90-17 on 900827-31.No Violations Noted ML20059G1431990-09-0404 September 1990 Forwards Safety Insp Rept 50-346/90-15 on 900701-0813. Violation Noted But Not Cited.Util Implemented Corrective Actions as Result of Violation & Will Be Examined During Future NRC Insps ML20056B2701990-08-20020 August 1990 Forwards Safety Evaluation Granting 900710 Request for Relief from ASME Code for Class 3 Piping in Svc Water Sys. Request Granted Until Next Scheduled Outage Exceeding 30 Days But No Later than Dec 1991 ML20059A6821990-08-13013 August 1990 Forwards Safety Insp Rept 50-346/90-09 on 900417-0717. Violations Noted But Not Cited.Util Will Be Notified by Separate Correspondence of NRC Decision Re Enforcement Action Based on Findings of Insp ML20059A6631990-08-10010 August 1990 Forwards Enforcement Conference Rept 50-346/90-14 on 900601 & 900717 Telcon Re Violations Noted in Insp Repts 50-346/90-09 & 50-346/90-12 ML20059A6721990-08-10010 August 1990 Forwards Safety Insp Rept 50-346/90-13 on 900605-30 & 0709. Violation Noted But Not Cited ML20059A7161990-08-0808 August 1990 Provides Comments on 900105 Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance. Util Should Provide Description of Methodology for Periodic Verification of motor-operated Valve Switch Settings ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML17202U7701990-08-0101 August 1990 Forwards Exam Form a W/Answers & Individual Answer Sheets from Generic Fundamentals Written Exam on 900606 ML20055J2761990-07-24024 July 1990 Confirms 900731 Meeting in Region III Ofc to Discuss Util Response to Violation Re Instrumented Insp Techniques ML20055G6621990-07-20020 July 1990 Forwards Safety Insp Rept 50-346/90-10 on 900430-0518.No Violations Noted ML20055G3051990-07-13013 July 1990 Confirms 900718 Tour of Plant & Mgt Meeting to Discuss Sixth Refueling Outage & Other Items of Mutual Interest ML20055F2231990-07-0606 July 1990 Ack Receipt of Containing Scope & Objectives for 1990 Emergency Plan Exercise Scheduled on 900919 ML20055D3181990-06-29029 June 1990 Advises of Safety & Performance Improvement Program Implementation Audit Scheduled for Wk of 900716-20.Selected Samples of Technical Recommendations Encl ML20055D9781990-06-29029 June 1990 Advises That 900614 Changes to QA Program Meet 10CFR50,App B Requirements & Acceptable.Nrc Should Be Notified of Changes to QA Commitments Existing in Docketed Correspondence Outside QA Program Description ML20043H7241990-06-19019 June 1990 Forwards Requalification Exam Rept 50-346/OL-90-01 Administered on 900515-24.Requalification Program Rated Satisfactory.Weakness Noted in Knowledge of Steam Feed Rupture Control Sys.Next Exam Scheduled for Nov 1991 ML20059M8631990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043F6281990-06-11011 June 1990 Responds to 900205 Request for Changes to Bases of Tech Specs for Cycle 7 Reload Core.Plant Seismic & LOCA Analysis Acceptable & Coolable Geometry Maintained ML20043F7611990-06-0707 June 1990 Advises That Written & Oral Operator & Senior Operator Licensing Exams Scheduled for Wk of 901112.Approved Ref Matl Listed in Encl Needed to Meet Schedule ML20043E2991990-06-0505 June 1990 Forwards Correction to Misnumbered Encl to Re Unimplemented USIs at Plant ML20043F3521990-06-0404 June 1990 Advises That 900406 Rev 8 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20034D0091990-05-30030 May 1990 Confirms Plans for 900601 Meeting to Discuss Apparent Violations from Transport of Core Support Assembly & Refueling Canal Draining Events ML20043C2421990-05-25025 May 1990 Forwards Safety Insp Rept 50-346/90-12 on 900501-17. Violations Noted.Util Will Be Notified by Separate Correspondence of NRC Decision Re Enforcement Actions Based on Findings of Insp Following 900601 Enforcement Conference ML20043B4131990-05-24024 May 1990 Forwards Safety Insp Rept 50-346/90-06 on 900409-12 & 0514-16.No Violations Noted ML20043A8471990-05-16016 May 1990 Forwards Safety Insp 50-346/90-11 on 900430-0503.No Violations Noted ML20042G7621990-05-0909 May 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 900606.Map of Area Including Time & Location Where Exams Will Be Administered Also Encl ML20042G1881990-05-0404 May 1990 Forwards Safety Insp Rept 50-346/90-05 on 900301-0416.No Violations Noted ML20034A8581990-04-18018 April 1990 Forwards Understanding of Current Status of All Unimplemented USIs at Plant Re Generic Ltr 89-21 Based on Results of 900214 Meeting ML20034A8851990-04-18018 April 1990 Advises That Util 900213 Response to NRC Bulletin 89-003 Re Potential Loss of Shutdown Margin During Refueling Operations Acceptable,Based on Confirmation That Listed Actions to Address Bulletin Performed ML20034A7321990-04-18018 April 1990 Forwards Exemption from Certain Requirements of App R to 10CFR50 Re Fire Protection Features Sys & Components Important to Safe Plant Shutdown & Requirements for Emergency Lighting Units Inside & Outside Plant ML20034A5081990-04-13013 April 1990 Forwards Amend 147 to License NPF-3 & Safety Evaluation. Amend Deletes Table 3.6-2 in Entirety from Tech Specs & Revises Sections 1.8.a.2,4.6.1.1.a.1,3.6.3.1,4.6.3.1.1, 4.6.3.1.2 & Section 3/4.6.3 of Bases to Reflect Deletion ML20034A4461990-04-11011 April 1990 Forwards Insp Rept 50-346/90-08 on 900328-29 & Notice of Violation ML20012D9361990-03-22022 March 1990 Confirms Mgt Meeting on 900328 in Region III to Discuss Results of Interfacing Sys LOCA Insp During Period from 891030-1109 ML20012E8551990-03-21021 March 1990 Concurs That Using ASTM D4057-81 as Alternate Diesel Fuel Sampling Method to Tech Spec 4.7.9.1.2.b Acceptable.Ack That Tech Specs Remaining as Is Per Generic Ltr 86-10 ML20012D9331990-03-20020 March 1990 Forwards Safety Insp Rept 50-346/90-04 on 900220-23.No Violations Noted ML20033F4161990-03-15015 March 1990 Forwards Environ Assessment & Finding of No Significant Impact Re Util 870112 & 890731 Requests for Nine Exemptions from 10CFR50,App R Requirements Re Fixed Fire Suppression Sys,Alternate Shutdown Capability & Emergency Lighting ML20012C6021990-03-0808 March 1990 Advises That 900129 Rev 10 to QA Program Description,Updated SAR Chapter 17.2,Rev 0 Consistent w/10CFR50,App B & Acceptable ML20012A3451990-02-27027 February 1990 Advises That 891220 Rev 23 to Emergency Plan Consistent W/ 10CFR50.54(q) & Acceptable ML20006G2011990-02-22022 February 1990 Forwards Corrected Amends 145 & 146 to License NPF-3.Amend 145 Changes Tech Spec & Bases 4.0.3 in Response to Generic Ltr 87-09.Amend 146 Covers Type a Tests to Be Conducted During 10-yr Inservice Insp Interval ML20006F2461990-02-21021 February 1990 Approves Use of Alloy 690 as Proposed Alternative to Use of Alloy 600 in B&W Steam Generator Plugs,In Response to 900208 Request.Alloy 690 Has Superior anti-corrosion Properties & Provides Acceptable Level of Quality ML20012A0941990-02-21021 February 1990 Comments on Static Simulator Scenarios.Static Simulator Exam Must Consist of at Least One AT-POWER & One ESFAS Initiation Scenarios ML20011E7111990-02-14014 February 1990 Forwards Request for Addl Info Re 890602 Response to NRC Bulletin 88-011 on Pressurizer Surge Line Stratification. Response Should Be Submitted within 30 Days of Receipt of Ltr 1990-09-04 Category:OUTGOING CORRESPONDENCE 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 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 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 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 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 ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 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 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML17191B2221999-02-0202 February 1999 Informs That NRC Plans to Administer Gfes of Operator Licensng Exam on 990407.Authorized Facility Representative Must Submit Ltr to Appropriate Regional Administrator Identifying Individuals Taking Exam 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 |
Text
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UNITED STATES y
,, ( (,g NUCLEAR REGULATORY COMMISSION WASHWGTON. D. C. 20655 E
k..v July 26,1979 Docket No.: 50-346 Mr. Lowell E. Roe Vice President, Facilities Development Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652
Dear Mr. Roe:
The Conmission has issued the enclosed Amendment No.18 to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Sta Unit No.1 (08-1).
12, 1977, Specifications (TS) in response to your submittals of December January 11, April ll, May 3 June 22, July 27, September 7 and 25, Noventer 25, December 12, 1978 and January 10, February 28, April 12 and July 9, 1979.
This amendment adds a license condition relating to the completion of facility modifications for fire protection and modifies the TS to re-quire at least five individuals with fire protection training be on site The TS relating to the fire brigade are effective by start at all times.
We have discussed the contents and up after the first refueling outage.
conditions of this license amendment with members of your staff and wa Nevertheless, understand that you have agreed to this license amendment.
you understand that by the provisions of 10 CFR Part 2 paragraph 2.204, you may demand a hearing with respect to all or any part of the amendmentIf you d within twenty (20) days from the date of this letter.
a hearing,)this amendment will become effective on the expirati twenty (20 day period.
22, 1978, we issued TS to incorporate limiting con-By letter dated Marchditions for existing fire protection systems and administrative con You are requested to propose revised TS related to facility mcdifications listed in Item A.1 of Table 1 cf the enclosed Safety Evaluation within For the redifications listed 90 days after the issuance of this amendment.
in Item B of Table 1 of the Safety Evaluation, proposed revised TS should be submitted for review no later than 90 days before the implementation dates.
Ok q 9 os M0
. Toledo Edison Company We have determined that no license amendment fee is required to accompanyThis your response to the aforementioned request.
to those applications or requests to incorporate our recom Any other unrelated changes or requests have been added at our request.
that you might choose to include in the fire protection requests would be subject to amendment fees in accordance with Section 170.22 of 10 CFR Part 170.
A copy of the Notice of Issuance is also enclosed.
Sincerely, 4
/
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
Amendment No.18 2.
Safety Evaluation 3.
Notice cc w/ enclosures: See next page 847 2k
5 Toledo Edison Company cc w/ enclosure (s):
Director, Technical Assessment Mr. Donald H. Hauser, Esq.
Division The Cleveland Electric Office of pacion Prcgrams-Illuminating Company (AW-G j P. O. Box 5000 U. S. Environmental Protection Agency Cleveland, Ohio 44101 Crystal Mall #2 Arlington, Virginia 20460 Gerald Charnoff, Esq.
Shaw, Pittman, Potts U. S. Environmental Protection Agency and Trowbridge Federal Activities Branch 1800 M Street, N.W.
Washington, D.C.
20036 Region V Office ATTN: EIS COORDINATOR 230 South Dearborn Street Leslie Henry, Esq.
Chicago, Illinois 60604 Fuller, Seney, Henry and Hodge 300 Madison Avenue Mr. Samuel J. Chilk, Secretary Toledo, Ohio 43604 U. S. Nuclear Regulatory Comission Washington, D.C.
20555 Mr. Robert B. Borsum Babcock & Wilcox The Honorable Tim McConnack Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Ohio Senate Bethesda, Maryland 20014 Statehouse Columbus, Ohio 43216 Ida Rupp Public Library The Honorable Tim McCormack 310 Madison Street 170 E. 209th Street Port Clinton,0hio 43452 Euclid, Ohio 44123 President, Board of County Comissioners of Ottawa County Mr. Lowell E. Roe Vice President, Facilities Port Clinton, Ohio 43452 Development Toledo Edison Company Attorney General department of Attorney General Edison Plaza 300 Madison Avenue 30 East Broad Street Columbus, Ohio 43215 Toledo, Ohio 43652 Bruce Churchill, Esq.
Harold Kahn, (taff Scientist Shaw, Pittman, Potts & Trowbridge Power Siting Commission 1800 M Street, N.W.
361 East Broad Street Columbus, Ohio 43216 Vashington, D.C.
20036 Atomic Safety & Licensing Board Panel Docketing and Service Section U. S. Nuclear Regulatory Comission Office of the Secretary U. S. Nuclear Regulatory Comission Washington, D.C.
20555 Washington, D.C.
20555 Atomic Safety and Licensing Appeal Panel U. S. Nuclear Regulatory Commission Washington, D.C.
20555 f[z]
\\
/
Toledo Edison Company g
cc w/ enclosure (s):
Ivan W. Smith, Esq.
Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Wa hington, D.C.
20555 Dr. Cadet H. Hand, Jr.
Dir:ctor, Bodega Marine Laboratory University of California P. O. Box 247 Bodega Bay, California 94923 Dr. Walter H. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830 Ms. Jean DeJuljak 381 East 272 Euclid, Ohio 44117
- w/ enclosure (s) and incoming m
c:d.:
12/12/77, 1/11, 4/11, 5/3, 6/22, 7/27, 9/7&25, 11/25, 12/12/78, Ohio Otpartment of Health 1/10,2/28, ATTt;: Director of Health 4/12 & 7/9/79 450 East Town Street Colurbus, Ohio 43216 I
847 126