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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Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217G9201999-10-14014 October 1999 Discusses Utils Request for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 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
[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 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
[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 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
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JUN - 7 DD Docket No. 50-346' Toledo Edison Company p
ATTN: Mr. Donald Shelton
'r Vice President Nuclear Edison Plaza 300 Madison Avenue b
Toledo, OH 43652 L'<
Dear Mr. Shelton:
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SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSlHG EXAMlHATIONS h,
in a telephone conversation between Mr. Rick Simpkin, and Mr. Tim Reidinger, arrangements were made for the administration of examination at Davis-Besse.
g The wtitten and oral exominations are scheduled for the week of November 12, 1990.
In order for us to meet = this schedule, it will be necessary for the facility to furnish the approved reference material listing'in Enclosure 1, " Reference H.'
Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations" at least 60 days prior to the examination date.
Any delay in receiving approved properly bound and indexed reference material will result in a delay in administering the examinations. Mr. Rick Simpkins has been advised of our reference material requirements,.the number ~of reference 1
material. sets that are required, and the examiners' names and a#resses where each set is to be mailed.
The facility management is responsible for providing adequate space and accomodations in order to properly conduct the written examinations.
Enclosure, " Requirements for Administration of Written Examinations,"
describes our requirements for conducting thises. examinations.
-Mr. Rich Simpkins has also been informed of these requirements.
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i containes the Rules and Guidelines,that will be in effect during the administration of the written examination. The f acility management is y
responsible for ensuring that all applicants are aware of these rules.
U The facility staff review of the written examination will be conducted in
-accordance with requirements specified in Enclosure 4, " Requirements for
- Facility Review of Written Examinations." Mr. Rick Simpkins has been informed -
of these requirements.
9006180093 900607 ADOCK0500gj6 PDR h
o, Toledo Edison Company 2
JUN 71930 All reactor operator and senior reactor operator license applications should be submitted at least 60 days prior to the first examination dates so that we will be able-to review the training and experience of the applicants, process the medical certifications, and prepare final examiner assignments after applicant eligibility has been determined.
If the applications are not received at-least 30 days prior to the examination dates, it is likely that a postponement will be necessary.
The request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992.
The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response,-including gathering, exeroxing and mailing the required material.
Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S.
Nuclear Regulatory (Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project 3150-0101), Office of Management and Budget, Washington, D.C.
20503.
Thank you for your consideration in this matter, if you have any question regarding the examination procedures and requirements, please contact T. D. Reidinger at 312 790-5551.
Sincerely, OP.'GmAL SiCNLD M CC01ICEY C. Wmy Geoffrey C. Wright, Chief Operations Branch
Enclosures:
1.
Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations 2.
Requirements for Administration of Written Examinations
-3~
NRC Rules and Guidelines For Written Examinations
- 4. -
Requirements for Facility Review Written Examinations See Attached Distribution RI RI 11
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EToledo Edison Company 3
g Distribution cc w/ enclosures L. Storz, Plant Manager DCD/DCBL(RIDS)-
' Licensing Fee Managerent Branch Resident inspector, Rill F
~ James W. Harris,' State of Ohio
' Robert E. Owen, Ohio' i~
Department of Health L
A. Grandjean, State of:0hio.-
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~Public Utilities Commission ec'w/o' enclosures:.
T. V. Womback, Project Manager, NRR K. E. Perkins, Branch. Chief, OLB
- 1. N. Jackiw, Section Chief,-DRP L,
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..e-ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS 1.
Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.)
A copy of the facility Job and Task Analysis (JTA), specifying the knowledges and abilities reouired of an operator at the facility.
Each particular knowledge and/or ;bility will include an importance rating correlating it to ensuring the health and the safety of the public.
If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG-1122 (1123) will be used to establish content validity for the examination.
AllJobPerformanceMeasures(JPMs)usedtoascertainthecompetenceof the operators in performing tasks within the control room complex and, as identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materials should include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material should include learning objectives and the details presented during lectures, rather than outlines. Training materials s1ould be identified by plant and unit, bound, and indexed.
FAILURE TO PROVIDE COMPLETE, PROPERLY B0UND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENTOFNUCLEAROPERATIONS). ACCOMPANYlHG THE MATERIAL WILL BE A~
COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include'the following should be provided:
System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
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OPERATOR LICENSING ENCLOSURE 1 (Cont'd)
Training material used to clarify and strengthen understanding of emergency operating procedures.
2.
CompleteProcedureIndex(includingsurveillanceprocedures,etc.)
3 '.
All administrative procedures (as applicable to reactor operation or safety)_
4.
All integrated plant procedures (normal or general operating procedures) a' ~
5._
Emergency procedures (emergency instructions, abnormal or special procedures) 6.
Standing orders (important orders that are safety-related and may supersede.the regular procedures) 7.
Surveillance procedures (procedures that are run frequently, i.e., weekly)
_ procedure, when appropriate) g procedures, ( nitial core-loading Fuel-handling and core-loadin
- 8. -
9.
Annunciator / alarm procedures
- 10.. Radiation protection manual (radiation control manual or procedures) 11._ Emergency plan implementing procedures
- 12. TechnicalSpecifications(andinterpretations,ifavailable)-
- 13. -System operating procedures
- 14. -Piping and instrumentation diagrams, electrical single-line diagrams, or: flow diagrams
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15.. Technical Data Book, and/or plant curve information as used by ~ operators and facility precautions, limitations, and set points (PLS) for the v
facility
- 16. Questions and answers specific to the' facility training program which may.
be used in the written or operating examinations
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OPERATORLICENSINGENCLOSURE1(Cont'd)
- 17. Additional material required by the examiners to develvp examinations that meet the requirements of these Standards and the regelations.
L The above reference material should be approved, final issues and should be so marked.. lf a plant has not finalized some of the material, the Chief Examiner I-shall verify with.the. facility that the most complete, up-to-date material is 4
- available=and that agreement has been reached with the licensee for limiting changes before the administration of the examination.- Alliprocedures and.
reference material should be bound with appropriate indices or tables of contents so that they can be used. efficiently.
Failure to provide complete, properly bound and indexed plant reference material could result in F
cancellation or rescheduling of the examinations.
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ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION Of WRITTEN EXAMINATIONS
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1.
A single room shall be provided for administration of the written examina-tion. The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor i
personnel during the written examination.
If necessary, the f acility should make arrangement for the use of a suitable room at a local school,
.t motel, or other building. Obtaining this room is the responsibility of the licensee.
2.
Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one applicant per table, with a three foot space between tables, r
3.
Suitable arrangements shall be made by the facility if the applicants are
- to have lunch, coffee or other refreshments.
These arrangements shall comply with item 1 above and shall be reviewed by the examiner and/or proctor.
4.
The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper' l
D in unopened packages for each applicant's use in completing the
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examination. The examiner shall distribute these pads to the applicants.
I 5.
Applicants may bring pens, pencils, calculators or slide rules into the examination room.
Only black ink or dark pencils should be used for 1
writing answers to questions.
6.-
The-licensee shall provide one set of steam tables for each applicant.-
The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference. material shall be allowed unless provided by the examiner, I
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ENCLOSURE 3
. PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS r
1.
Check identification badges.
r 2.
Pass out examinations and all handouts.
Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
-During the~ administration of this examination the following rules apply:
L 1
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
After the examination has been completed, you must sign the statement on the cover' sheet indicating that the work is your own and you _have not received or given assistance in completing the examination. This must be done af ter you complete the examination.
READ THE FOLLOWING INSTRUCTIONS:
1.
Restroom trips are to be limited and only one applicant at a time may leave.
You must avoid all contacts with anyone outside the examination room to avoid even the appearance or poscibility of cheating.
2.
Use black ink or dark pencil only to facilitate legible reproductions.
3.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
'4 Fill in the date on the cover sheet of the examination (if necessary).
5.
You may write your answers on the examination question page or on a
-separate sheet of paper. USE ONLY THE PAPER PROVIDED AND 00 NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 6.
If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and' insert it directly after the specific question.
DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
7.
Print your name in the. upper right hand corner of the first page of each
-section of your answer sheets whether you use the examination questior;
.j pages or separate sheets of paper.
Initial each page, iu
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L LICENSE EXAMINATIONS' ENCLOSURE 3 (Cont'd)
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- 8.
Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
9.
If you are using separate sheets, number each answer and skip at least 3 lines between answers to allow space for grading.
- 10. Write "Last Page" on the last answer sheet.
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- 11. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer.
Write it out.
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- 12. The point value for each question is indicated in parentheses af ter the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
- 13...Show all calculations, methods, or assumptions used to obtain an answer.
14 Partial credit-may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION 4
AND DO NOT LEAVE ANY ANSWER BLANK.
Partial credit will NOT be given on multiple choice questions.
- 15. Proportional grading will be applied. Any additional wrong information that is provided may count against you.
For example, if a question is L
worth one point and asks for four responses, each of which is worth 0.25 points, and you give five retponses, each of your responses will be L
worth.0.20 points, if one of your five responses is incorrect, 0.20 will be deducted.and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers. -
16.
If the intent of a-question-is unclear, ask questions of the examiner only..
- 17. When turning in your examination, assemble the completed examination'with i
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examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
To pass the examination, you must achieve an overall grade of 80% or 18.
. greater.
1
- 19. There is a time limit of (4) hours for completion of the examination.
- 22. When you are done and have' turned in your examination,1 cave the examination area (DEFINE THE AREA).
If you are found in this area
' while the examination is still in progress, your license may be i
danied or revoked.
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1.
At the option of the Section Chief, the facility may review the written examination up to two weeks prior to its administration.
This review may-take place at the facility or in the Regional effice. The Chief. Examiner will coordinate the details of the review with,ae facility. An NRC examiner will always be present during the review.
Whenever this option of examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the examination. The examination or written notes will NOT be retained by the facility, a..
Pre-Examination Security Agreement I
agree that I will not knowingly divulge any information concerning the replacement (or initial) examination-scheduled for to any unauthorized persons.
I understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to be administered the above replacement (or initial)_ examination from now until after the examination has been administered.
I understand that violation of this security agreement could result in the examination being voided, n
Signature /Date in addition, th acility staff reviewers will sign-the following.
statement after the written examination has been administered, b.
Post-Examination Security Agreement 1-did not, to the best of knowledge, divulge any information concerning the written examination administered on to any unauthorized persons.
I did not participate in provTding any instruction to-those reactor operator and senior reactor operator applicants who were administered the examination from the time that I was allowed 1
access to'the examination.
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-ENCLOSURE 4(Cont'd) 2.
Regardless of whether the above examination review option is exercised, imediately following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key.
The copy of the written examination shall include pen L
-and ink changes made to questions during the examination administration.
If the facility did'not review the examination prior to its administration, they will have five (5) working days from the day of the written examination to submit formal coments.
If the facility reviewed the examination prior to its administration, any additional coments must be given to an examiner prior to his/her leaving-the site at the end of the-week of the written examination administration.
In either case, the connents will be addressed to the responsible Regional Office by the highest onsite level of corporate management for plant operations e.g...
Vice President for Nuclear Operations. AcopyofthesubmittalwIllbe forwarded to the Chief Examiner, as appropriate.
Coments not submitted -
within the required time frame will be considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section Chief.
Should the-comment submittal deadline not be met, a long delay
'in grading the examinations may occur.
3.
The'following format should be adhered to or submittal of specific connents:
a.
Listing of NRC Question, answer and reference b.
. Facility connent/ recommendation c.
Reference (to support facility connent)
NOTES:
1.
No change to the examination will be made without submittal of-a reference to support the f acility connent. Any supporting Jocumentation that was not previously supplied, should be-provided.
2.
Cocnents made without a concise facility reconnendation will not be addressed.
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