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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Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217G9201999-10-14014 October 1999 Discusses Utils Request for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 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 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 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 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 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 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 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 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 ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves 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 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 ML20207E2521999-05-28028 May 1999 Forwards Rev 18,App A,Change 1 to Davis-Besse Nuclear Power Station,Unit 1,industrial Security Plan IAW Provisions of 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 1999-09-07
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H6411990-11-0909 November 1990 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 ML20059A6721990-08-10010 August 1990 Forwards Safety Insp Rept 50-346/90-13 on 900605-30 & 0709. Violation Noted But Not Cited 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 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 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 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 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 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 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 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 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 ML20011F0051990-02-13013 February 1990 Forwards Safety Insp Rept 50-346/89-27 on 900108-12.No Violations Noted ML20011E5491990-02-0808 February 1990 Advises That NRC Audit of Util Boric Acid Prevention Program Resulted in Acceptable Finding & Now Consider Issue to Be Closed,Per 890911-13 Site Visit.Trip Rept Encl ML20006D4341990-02-0202 February 1990 Forwards Safety Evaluation Accepting Licensee 810505 Responses to Generic Ltr 81-21 Re Natural Circulation Cooldown,Per Multi-Plant Action B-66 ML20006D5391990-02-0202 February 1990 Forwards Safety Evaluation Supporting Util 900115 Request for Approval of Revised Reactor Capsule Withdrawal & Insertion Schedule ML20006B0021990-01-24024 January 1990 Grants Discretionary Enforcement for Tech Spec 3.3.1.1 Re Plant Operation W/One or Four flux-delta flux-flow Instruments in Channel 2 of Reactor Protection Sys Declared Inoperable.Discretion in Effect Until 900201 ML19354E7121990-01-23023 January 1990 Forwards Safety Insp Rept 50-346/89-26 on 891107-900102 & Notice of Violation.Attachment to Rept Withheld (Ref 10CFR73.21) 1990-09-04
[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 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 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 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 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 ML20196G1621998-12-0303 December 1998 Submits Response to Request for TS Interpretation Re Surveillance Interval Extension Allowances 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 ML20153F8081998-09-23023 September 1998 Forwards Operator Licensing Exam Rept 50-346/98-301OL on 980803-07.Written Exam Administered to Six License Applicants.All Six Applicants Passed All Sections of Exams & Issued SRO License IR 05000346/19980091998-09-22022 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/98-09 Issued on 980728.Corrective Actions Will Be Examined During Future Inspections 1999-09-07
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NRC PDR L PDR ORB #4 Rdg Docket No. 50-346 DEisenhut 0 ELD AE0D IE Hr. Richard P. Crouse ACRS-10 ORAB Vice President, Nuclear Toledo Edison Company ADe Agazio Edison Plaza RIngram TBarnhart-4 300 Madison Avenue Toledo, Ohio 43652
Dear Mr. Crouse:
RDiggs
SUBJECT:
INSERVICE INSPECTION AND TESTING PROGRN1 - RELIEF FROM CERTAIN HYDROSTATIC TESTING REQUIREMENTS i
The Davis-Besse Nuclear Power Station Inservice Inspection and Testing Progran for the initial 120 aonth interval was submitted on May 15, 1980, and was amended and supplanented by Toledo Edison Company letters dated December 15,1980, March 31,1981, June 10,1981 and February 16, 1 982. The NRC staff evaluation of Sections 3 and 4 of that program 4
was provided with our letter of May 5,1982 By that letter, the i
Commission also granted relief from certain ASME Boiler and Pressum Vessel Code, Section X1, requirements.
Toledo Edison Company, by letter of June 22, 1982, requested further relief from the ASME Code Section X1, requirements.. Specifically, relief-is requested from the requirement to perfonn a hydrostatic test on certain piping system welds that with be added to the auxiliary feedwater system during the steam generator repair program. The ASME Code hydrostatic test requires pressurization at 1313 psig at a temperature between 130 and 200'F with a 10 minute hold time. Toledo Edison Company has proposed an alternate pressure testing program.
'~nis alternate test would require:
a.
Hydrostatic test of the sixteen riser subassemblies at 1313 psig for 10 minutes prior to installation, and b.
llydrostatic test of the completed repair systen at 929 psig (1.08 times the operating pressure) and operating temperature with a four hour hold time.
Toledo Edison Company has detennined that the Code required test is impractical and that the proposed reduced pressure test offers a more meaningful evaluation of the system.
In addition, there will be a substantial savings in personnel radiation exposure, manpower, and downttime.
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8208060331 820729 PDR ADOCK 05000346 G
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!fr. Richard P. Crouse We have evaluated the request for relief contained in your June 22, 1982 letter and agree with your detemination that it is impractical for you to meet the Code requirements. We agree that the alternate testing that you have proposed is acceptable.to provide assurance of structural integrity. We have detemined that life, property or the common defense and security will not be endangered as a result of not perfoming the examination in accordance with the ASIlE Code. We have reached the conclusion that relief should be granted as authoriged by 10 CFR 50.55a (g)(6)(1), and that granting such relief is in the public interest giving due consideration to the burden upon Toledo Edison Company if the requirmients were imposed.
Therefore, pursuant to 10 CFR 50.55a(g)(G)(1), we grant the requested relief from the ASilE Code required hydrotest and accept, as a substitute, your proposed tests as described in your letter of June 22, 1982 It is understoodythat Toledo Edison Company takes no exception to the Cdde required non-destructive examination of the 94 new welds and 8 supports. Toledo Edison Company remains committed to perfoming a hydrostatic test per Section XI requirements prior to the end of the initial 120-conth inspection interval.
The Safety Evaluation and a copy of the Federal R_ogister Notice is enclosed.
Sincerely,
,. vwolSIGNEDB44 J0ffN F. STOL47,
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosures:
1.
Safety Evaluation 2.
flotice cc w/ enclosures:
See next page ORB #4:DL ORB #4:DL C-0RB#4: L AD:0R D
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c et DEisenhut Docket No. 50-346 OELD AE0D IE j4 1/
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Hr. Richard P. Crouse ORAB Vice President, Nuclear ADeAgara;o,jj Toledo Edison Company Edison Plaza RIngram-TBarnhart-4 x,,
300 Madison Avenue OPA Toledo, Ohio 43652 SECY
Dear Hr. Crouse:
RDiggs f
SUBJECT:
INSERVICE fNSPECTION AliD TESTING PROGRN! - REl.IEF FROM d,
CERTAlli llYDR0 STATIC TESTING REQUIREMEflTS I
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The Davis-Besse fluclear Power Station Inservice Inspection and Testing 1
Program for the initial,120.aonth interval was submitted on May 15, 1980, i
t and was amended and supplaaented by Toledo Edison Company letters gQ;
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dated December 15,1980. March 31,1981 June 10,1981 and February 16,'
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1932. The NRC staff evaluation of Sections 3 and 4 of that program was provided with c,ur tatter of May 5,1982 By that letter, the y
Commission also granted relief,from certain ASME Boiler and Pressure s/
Vessel Code, Section X1, requirements.
.e Toledo Edison Company, by lettcr of June 22, 1982, requested further relief from the AS!!E Code Section X1s requirei.tonts. Specifically, jt,
relief'is requested from the requiranent to perfom a hydrostatic
,,;j test on certain pipiag systen welds that wiu be added to the auxiliary
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feedwater systsu during the steen generator repair program. The ASME Code hydrostatic test requires pressurization at 1313 psig at a temperature between 130 and 200*F nith a 10 minute hold time. Toledo Edison Company has proposed an alternate pressure testing program.
This alternate test would recpire:
a.
llydrostatic test of the sixte 3n riser subassemblies at 1313 psig for 10 minutes prtor to installation, and J
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b.
Ilydrostatic test of the conpleted repair system at 9?9 psig t
a four hour hold time, 7_,l (1.03 times the operating pressure) and operating temperature with f
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Toledo Edison Company has detemfned that the code required test: is impractical and that the proposed reduced pressure test offers a more meaningful evaluation of the systen.
In addition, there will be a x
substantial savings in personnel radtt. tion exposure', nanpower, and downtthe.
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. DIJTRIBUTION yf j
UNITED STATES
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RIngram NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D C. 20555 July 29,1982'
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Docket No. 50-346 Docketing and Service Section Office of the Secretary of the Commission 7
SUBJECT; DAVIS DESSE NUCLEAR POWER STATION c
3
- Two signed originals of the Federal Register Notice identified below are enclosed for your transmittal to tr.e Office of the Federal Register for publication. Additionalconformed copies (12 ) of the Notice are enclosed for your use.
O Notice of Receipt of Application for Construction Permit (s) and Operating License (s).
U Notice of Roceipt of Partial Application for Construction Permit (s) and Facility License (s): Time for Submissien of Views on Antitrust Matters.
1 O Notice of. Availability of Applicant's Environment'al Report.
O Notice of Proposed Issuance of Amendment to Facility Operating License.
0 Notice of Receipt of Application for Facility License (s): Notice of Availability of Applicant's 1y Environmental Report; and Notice of Consideration of issuance of Facility License (s) and Notice f'
ot Opportunity for Hearing.
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, O Notice cf Availability of NRC Draft' Final Environmental Statement.
c 0 Notice of Limited Work Authorization.
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.O Notice of Availability of Safety Evaluation Report.
l O Notice of issuance of Construction Permit (s).
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O Notice of issuance of Facility Operating License (s) or Amendment (s).
0 0ther: Notice _of Granting _RatiefJm A.mE Cee r-traments-1 s
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Division of Licensing, ORBf4 s
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Office of Nuclear Reactor Regulation As Stated s 6
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~ q Toledo Edison Company cc w/ enclosure (s):
Mr. Donald H. Hauser, Esq.
U.S. Nuclear Regulatory Comission The Cleveland Electric Resident Inspector's Office Illuminating Company 5503 N. State Route 2 P. O. Box 5000 Oak Harbor Ohio 43449 Cleveland, Ohio 44101 Mrs. Julia Baldwin, Libr'arian Gerald Charnoff, Esq.
Government Documents Collection Shaw, Pittman, Potts William Carlson Lib: ary and Trowbridge University of Toledo 1800 M Street, N.W.
2801 W. Bancroft Avenue Washington, D. C.
20036 Toledo, Ohio 43606 Paul M. Smart, Esq.
Fuller & Henry 30011adison Avenue P. O. Box 2083 Regional Radiation Representative Toledo, Ohio 43603 EPA Region V 230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois 60604 Babcock & Wilcox Nuclear Fower Generation Division 7910 Woodmont Avenue, Suite 220 Bethesda, !!aryland 20814 Ohio Department of Health ATTN: Radiological Health Program Director P. O. Box 118 President, Board of County Columbus, Ohio 43216 Comissioners of Ottawa County Port Clinton, Ohio 43452 Attorney General Department of Attorney General 30 East Broad Street Columbus, Ohio 43,215 Harold Kahn, Staff Scientist Power Siting Comission l
361 East Broad Street Columbus, Ohio 43216 Mr. James G. Keppler, Region; Adninistrator U. S. Nuclear Regulatory Comission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ted Myers Manager, Nuclear Licensing Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652
-