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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N2321999-10-15015 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 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 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation 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 ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) 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 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 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl 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 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 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 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 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 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 ML20207E9561999-05-28028 May 1999 Forwards Update to NRC AL 98-03,re Estimated Info for Licensing Activities Through Sept 30,2000 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 ML20207E7801999-05-21021 May 1999 Forwards Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capacity.Proprietary & non- Proprietary Version of Rev 2 to HI-981933 Re Cask Pit Rack Installation Project,Encl.Proprietary Info Withheld ML20206N0231999-05-0606 May 1999 Forwards License Renewal Applications for Davis-Besse Nuclear Power Station,Unit 1 for ML Klein,Cn Steenbergen & CS Strumsky.Without Encls ML20206D2421999-04-28028 April 1999 Forwards Combined Annual Radiological Environ Operating Rept & Radiological Effluent Release Rept for 1998. Rev 11, Change 1 to ODCM & 1998 Radiological Environ Monitoring Program Sample Analysis Results Also Encl PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl ML20206B8831999-04-17017 April 1999 Forwards 1634 Repts Re Results of Monitoring Provided to Individuals at Davis-Besse Nuclear Power Station During 1998,per 10CFR20.2206.Without Repts ML20205K5641999-04-0707 April 1999 Forwards Response to NRC 980415 RAI Re GL 96-06, Assurance of Equipment Operability & Ci During Design-Basis Accident Conditions. Rept FAI/98-126, Waterhammer Phenomena in Containment Air Cooler Swss, Encl ML20205K3871999-04-0707 April 1999 Forwards Copy of Application of Ceic,Oec,Ppc & Teco to FERC, Proposing to Transfer Jurisdictional Transmission Facilities of Firstenergy Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20205J1171999-03-29029 March 1999 Forwards Rev 1 to BAW-2325, Response to RAI Re RPV Integrity, Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rev Includes Corrected Values in Calculations PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) ML20205F5961999-03-27027 March 1999 Forwards Comments on Preliminary Accident Sequence Percursor (ASP) Analysis of 980624 Operational Event at Dbnps,Unit 1, as Transmitted by NRC Ltr ML20205D4791999-03-26026 March 1999 Forwards Rept Submitting Results of SG Tube ISI Conducted in Apr 1998.Rept Includes Description of Number & Extent of Tubes Inspected,Location & Percent wall-thickness Penetration for Each Indication of Imperfection ML20205L2031999-03-26026 March 1999 Submits Correction to Dose History of Tj Chambers.Dose Records During 1980-1997 Were Incorrectly Recorded Using Wrong Social Security Number.Nrc Form 5 Not Encl ML20205C7371999-03-25025 March 1999 Certifies That Dbnps,Unit 1,plant-referenced Simulator Continues to Meet Requirements of 10CFR55.45(b) for Simulator Facility Consisting Solely of plant-referenced Simulator.Acceptance Test Program & Test Schedule,Encl ML20205E3551999-03-19019 March 1999 Requests That Proposed Changes to TS 6.8.4.d.2 & TS 6.8.4.d.7 Be Withdrawn from LAR Previously Submitted to NRC ML20204J6361999-03-17017 March 1999 Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities PY-CEI-NRR-2375, Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage1999-03-15015 March 1999 Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage ML20204E6821999-03-12012 March 1999 Requests That Listed Changes Be Made to NRC Document Svc List for Davis-Besse Nuclear Power Station,Unit 1 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20065D0491990-09-14014 September 1990 Forwards Operator & Senior Operator Licensing Exam Ref Matl for Exam Scheduled for Wk of 901112,per 900607 Request ML20065D4951990-09-14014 September 1990 Forwards Updated Exam Schedule for Facility,In Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule ML20059K4681990-09-14014 September 1990 Provides Supplemental Info Re Emergency Response Data Sys (Erds).Data Transmitted by Util ERDS Will Have Quality Tag of 4 & Point Identification for ERDS Renamed ML20059G2341990-09-10010 September 1990 Provides Response to Request for Addl Info Re Interpretation of Tech Spec 3/4.7.10, Fire Barriers. Interpretation Is Implemented & Unnecessary Compensatory Measures Removed.List of Fire Barriers Inspected on One Side Only Encl ML20059G4961990-09-0606 September 1990 Submits Voluntary Rept of Svc Water HX Testing During Sixth Refueling Outage.Expected Flow Rates Not Achieved.Periodic Tests Developed to Check Efficiency of Containment Air Coolers ML20064A6271990-09-0606 September 1990 Requests That Requirement Date for Installation & Testing of Alternate Ac Power Source & Compliance w/10CFR50.63 Be Deferred Until Completion of Eighth Refueling Outage ML20028G8611990-08-28028 August 1990 Forwards Davis Besse Nuclear Power Station Semiannual Rept: Effluent & Waste Disposal,Jan-June 1990. ML20059D4121990-08-28028 August 1990 Forwards Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20059D5521990-08-24024 August 1990 Forwards Semiannual Fitness for Duty Rept for Jan-June 1990 ML20059B5291990-08-23023 August 1990 Forwards Updated Fracture Mechanics Analysis of Hpi/Makeup Nozzle,Per 900510 Meeting W/Nrc.Util Believes That Addl Analysis to Assess Structural Integrity of Nozzle Using More Conservative Fracture Model Supports Previous Analysis ML20058Q3911990-08-16016 August 1990 Requests NRC Concurrence on Encl Interpretation & Technical Justification of Tech Spec 3/4.7.10, Fire Barriers ML20058P7801990-08-10010 August 1990 Advises of Intentions to Revise Testing Requirements for Fire Protection Portable Detection Sys at Plant & Functional Testing of auto-dialer & Telephone Line Subsys from Daily to Weekly Testing ML20063P9981990-08-0909 August 1990 Submits Supplemental Response to Insp Rept 50-346/89-21. Util Rescinds Denial & Accepts Alleged Violation ML20056A5341990-08-0303 August 1990 Confirms Electronic Transfer of Payment of Invoice I0942 Covering Annual Fee for FY90,per 10CFR171 ML20058M7791990-08-0303 August 1990 Forwards Rev 10 to Industrial Security Plan & Rev 6 to Security Training & Qualification Plan.Revs Withheld ML20058L1821990-08-0101 August 1990 Forwards Davis-Besse Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1, Per NRC Audit Team Request ML20056A8341990-07-23023 July 1990 Forwards Revised Monthly Operating Rept for June 1990 for Davis-Besse Nuclear Power Station Unit 1 ML20055H4601990-07-20020 July 1990 Discusses Resolution of Draft SER Open Item on Voluntary Loss of Offsite Power.Util Preparing License Amend Request Per Generic Ltrs 86-10 & 88-12 to Relocate Fire Protection Tech Specs & Update Fire Protection License Condition ML20055F9681990-07-17017 July 1990 Forwards Application for Amend to License NPF-3,adding Centerior Svc Company as Licensee in Facility Ol.Change Allows for Improved Mgt Oversight,Control & Uniformity of Nuclear Operations ML20055F8561990-07-17017 July 1990 Discusses Util Planned Activities Re Instrumented Insp Technique Testing Performed at Facility in View of to Hafa Intl.Relief Requests Being Prepared by Util for Sys on Conventional Hydrostatic Testing ML20044B3001990-07-12012 July 1990 Provides Written Confirmation of Util Electronic Transfer of Funds to NRC on 900711 in Payment of Invoice Number I1050 ML20044B1841990-07-10010 July 1990 Requests Approval of Temporary non-code Repair & Augmented Insp of Svc Water Piping,Per 900626 Telcon ML20055D9701990-06-29029 June 1990 Provides Written Confirmation of Util Electronic Transfer of Funds for Payment of Invoice 0111 Covering Insp Fees for 890326-0617 ML20043H5291990-06-14014 June 1990 Forwards Plans Re Reorganization & Combining of Engineering Assurance & Svc Program Sections ML20055C7521990-06-14014 June 1990 Responds to NRC Bulletin 89-002, Potential Stress Corrosion Cracking of Internal Preloaded Bolting in Swing Check Valves & Justification for Alternate Insp Schedule for One Valve. No Anchor Darling Swing Check Valves Installed at Plant ML20055F2261990-06-14014 June 1990 Forwards 1990 Evaluated Emergency Exercise Objectives for Exercise Scheduled for 900919 ML20043G5661990-06-14014 June 1990 Forwards Rev 9 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G7811990-06-12012 June 1990 Forwards Info Re Implementation of NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation, Per NRC 900214 Safety Evaluation.Item II.B.1 Issue Re Reactor Vessel Head Vent Also Considered to Be Closed ML20043F6091990-06-11011 June 1990 Forwards Util Comments on NRC Insp Rept 50-346/90-12, Per 900601 Enforcement Conference Re Core Support Assembly Movement & Refueling Canal Draindown.Refueling Canal Draindown Procedure Provides Specific Draining Instructions ML20043E1301990-06-0101 June 1990 Withdraws 870831 & 890613 Applications to Amend License NPF-3.Changes Requested Addressed by Issuance of Amend 147 or Can Now Be Made as Change to Updated SAR Under 10CFR50.59 ML20043D5601990-05-31031 May 1990 Forwards Application for Amend to License NPF-3,revising Tech Spec 3/4.6.4.1, Combustible Gas Control - Hydrogen Analyzers. Request Consistent W/Nrc Guidance,Generic Ltr 83-37,dtd 831101,NUREG-0737 Tech Specs & Item II.F.1.6 ML20043D5691990-05-31031 May 1990 Forwards Application for Amend to License NPF-3,requesting Extension of Expiration Date of Section 2.H to Allow Plant Operation to Continue Approx 6 Yrs Beyond Current Expiration Date ML20043D1451990-05-31031 May 1990 Forwards Rev 11 to Updated SAR for Unit 1.Rev Updates Table 6.2-23 Re Containment Vessel Isolation Valve Arrangements ML20043D1621990-05-29029 May 1990 Documents Util Understanding of NRC Interpretation of Plant Tech Spec 3.7.9.1,Action b.2 Re Fire Suppression Water Sys, Per 891206 Telcon.Nrc Considered Electric Fire Pump Operable Provided Operator Stationed to Open Closed Discharge Valve ML20043C2331990-05-25025 May 1990 Forwards Summary of 900510 Meeting W/B&W & NRC in Rockville, MD Re Hpi/Makeup Nozzle & Thermal Sleeve Program.List of Attendees & Meeting Handout Encl ML20043B1701990-05-18018 May 1990 Forwards Revised Exemption Request from 10CFR50,Section III.G.2,App R for Fire Areas a & B,Adding Description of Specific Limited Combustibles That Exist Between Redundant Safe Shutdown Components in Fire Area a ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A2311990-05-11011 May 1990 Responds to Violation Noted in Insp Rept 50-346/90-08. Corrective Actions:Results of Analysis of Radiological Environ Samples & Radiation Measurements Included in 1989 Annual Radiological Environ Operating Rept ML20043A4901990-05-10010 May 1990 Forwards Summary of Differences Between Rev 5 to Compliance Assessment Rept & Rev 1 to Fire Area Optimization,Fire Hazards Safe Shutdown Evaluation, Vols 1-3.Rept Demonstrates Compliance W/Kaowool Wrap Removal ML20042F9801990-05-0404 May 1990 Provides Written Confirmation of Util Electronic Transfer of Payment of Invoice Number 10716 to Cover Third Quarterly Installment of Annual Fee for FY90 ML20042F5781990-05-0303 May 1990 Provides Status of Hpi/Makeup Nozzle & Thermal Sleeve Program.Nrc Approval Requested for Operation of Cycle 7 & Beyond Based on Program Results.Visual Insp of Thermal Sleeve Identified No Thermal Fatique Indications ML20042F0951990-04-30030 April 1990 Responds to Violations Noted in Insp Rept 50-346/90-02. Corrective Actions:Maint Technician Involved in Tagging Violation Counseled on Importance of Procedure Adherence W/ Regard to Personnel Safety ML20042F0841990-04-27027 April 1990 Responds to Violations Noted in Insp Rept 50-346/89-201 for Interfacing Sys LOCA Audit on 891030-1130.Corrective Actions:Plant Startup Procedure Will Be Revised Prior to Restart from Sixth Refueling Outage ML20042E7311990-04-27027 April 1990 Forwards Application for Amend to License NPF-3,deleting 800305 Order Requiring Implementation of Specific Training Requirements Which Have Since Been Superseded by INPO Accredited Training Program ML20042F1961990-04-27027 April 1990 Informs of Adoption of Reorganization Plan Re Plants on 900424.Reorganization Will Make No Changes in Technical or Financial Qualifications for Plants.Application for Amends to Licenses Adding Company as Licensee Will Be Submitted ML20043F7261990-04-20020 April 1990 Requests Exemption from 10CFR55.59(a)(2) to Permit one-time Extension of 6 Months for Reactor Operators & Senior Reactor Operators to Take NRC 1990 Requalification Exam. Operators Will Continue to Attend Training Courses ML20042E7091990-04-17017 April 1990 Forwards Annual Environ Operating Rept 1989 & Table 1 Providing Listing of Specific Requirements,Per Tech Spec 6.9.1.10 ML20012F5091990-04-0303 April 1990 Forwards Completed NRC Regulatory Impact Survey Questionnaire Sheets,Per Generic Ltr 90-01 ML20012F6001990-04-0202 April 1990 Submits Supplemental Response to Station Blackout Issues,Per NUMARC 900104 Request.Util Revises Schedule for Compliance W/Station Blackout Rule (10CFR50.63) to within 2 Yrs of SER Issuance Date ML20012E0181990-03-22022 March 1990 Forwards Application for Amend to License NPF-3,changing License Condition 2.C(4) Re Fire Protection Mods to Fire Extinguishers,Fire Doors,Fire Barriers,Fire Proofing,Fire Detection/Suppression & Emergency Lighting 1990-09-06
[Table view] |
Text
Docket No. 50-346
>y
. CO License No. NPF-3 e Scrial No. 1-81
% EDISDN Mr. James G. K." la r Regional Director. Xegion III JAMES S. GRANT Office of Inspection and Enforcement v.c. er...o.m E""S' S***
United States Nuclear Regulatory Commission "85'-5*'*
Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
IE Bulletin No. 79-14, dated July 2, 1979, requested that we develop and implement an inspection program to verify that the Davis-Besse Nuclear Power Station Unit 1 seismic analysis input for safety related piping system conforms to their actual field configuration.
Attached is our response to Item No. 1 of Bulletin No. 79-14.
In our response we have color-coded a set of Piping and Instrumentation Drawings which identify the accessible redundant and non-redundant system and the inaccess-ible systems to be it;.2pected. A list of the design documents which each system will be inspected against is included in the inspection package for that system.
In order to neet the submittal date for our response to Item No. I we have only enclosed the detailed inspection package for the high pressure injection systen.
Similar inspection packages for the remaining syetems will be available for your raview at the site- This approach was reviewed with Mr. E. L. Jordan of the Office of Inspection cnd Enforcement, Washington, by Bechtel Power Corporation, our architect engineer, on July 19, 1979.
We have reviewed the time required to perform the inspection and report the results under Item No. 2 of Bulletin No. 79-14. The ear ~iest proj ect completion date is October 1, 1979.
As indicated in our attachment, based upon our findings from Item No. '. c'.i the piping in the inaccessible areas will be scheduled for inspection by the end of the first refueling outage, currently planned for March, 1980, and a report submitted under Item No. 3 of Bulletin No. 79-14.
Yours very truly, W#
JSG:CLM cc:
United States Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C. 20555 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactors Washington, D. C. 20555 THE TOLEDO EDISON COMPANY EOtSON PLAZA AUG g;94 300 MADISON AVENUE TOLEDO. OHIO 43652 801 301 roosecold .
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Docket No. 50-346 License No. NPF-3 Seria] No. 1-81
. August 1,1979
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Seismic Analysis for As-Built Safety Related Piping System:
Response to NRC IE Bulletin No. 79-14 Davis-Besse Nuclear Power Station Unit 1
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I. INTRODUCTION NRC IE Bulletin 79-14, dated July 2,1979 and Revision 1, dated July 18, 1979 require all power reactor facility licensees and construction permit holders to verify that the seismic analysis applies to the actual co figuratian of the safety-related piping systems. The action items identified in the bulletin apply to all safety reldted piping, 2-1/2 inches in diameter and greater, and to Seismic Category I piping, regardless of size which was dynamically analyzed by computer.
This report is a response to Item 1 of the bulletin and a description of the program planned for Items 2 and 3.
II. Action Item 1:
Identify inspection elements to be used in verifying that the seismic analysis input information conforms to the actual configuration of safety-related systems.
For each safety-related system, submit a list of design documents, including title, identifimation number, revision and date, which were sources of input information for the seismic analyses. Also submit a description of the seismic analysis input information which is contained in each document. Identify systems or portions of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3. Submit all of this information within 20 days of the date of this bulletin.
Response
, Analysis Input In seismic stress analyses the piping system is mathematically modelled as a series of lumped masses connected by massless elastic members. The primary physical parameters that influence the analyses are the actual configuration of piping, concentrated masses, such as valves, and the type and location of pipe supports.
A. The actual configuration of the piping is identified by means of a piping isometric or physical piping drawing. This document shows the piping geometry, pipe size, location of fittings such as bends, elbows, tees and reducers; components su~h as valves, inline strainers, etc.; and equipment such as punps; heat exchangers, etc.
801 302
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B. Concentrated masses are modelled in the seismic analysis considering their location, weight, center of gravity and orientition with respect to the piping. This information is obtained from the manufacturers' equipment drawings and the physical piping drawings.
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C. Pipe support detail drawings show the complete design of the support.
These documents, which were used for fabrication and installation, provide the location, type, direction and other details of the supports.
The current revision of each of the documents noted above will be used in the inspection walkdowns. In addition, each floor and wall penetration wif* be checked to determine if it binds the piping or allows free movement through the penetration.
Safety Related Systems The bulletin requires that the actual configuration of the safety-related piping systems conforms to the seismic analyses. The following systems or portions of systems are considered safety related as defined in the bulletin and within the. scope of this response:
- 1. Main Steam System
- 2. Auxiliary Feedwater System
- 3. Staam Generator Drains System
- 4. Main Feedwater System
- 5. Hydrogen Dilution System
- 6. Reactor Coolant System
- 7. Pressurizer Relief System
- 8. Make-up and Purification System
- 9. Decay Heat Removal and Low Pressur - 11jection System
- 10. High Pressure Injection System
- 11. Core Flood System
- 12. Containment Spray System
- 13. Spent Fuel Pool Piping System 14 Component Cooling Water Syste '
- 15. Caseous Radwaste System
- 16. Service Water System
- 17. Sump Pump Discharge System (ECCS Rooms)
- 18. Fuel Oil and Diesel Generator Systems
- 19. Miscellaneous Containment Penetrations
- Attachment 1 to this response is a complete set of Piping and Instrumentation Diagrams (P&ID's). These diagrams have been color-coded to identify the accessible redundant and non-redundant systems and the inaccessible systems to be inspected by this program.
It is planned to inspect and report on all the piping in the accessible areas within 90 days from the bulletin issue date.
If a high degree of confidence is established o*n the conformance of the as-built installation with the design in the accessible areas, all the piping in the inaccessible areas will be. inspected and a re" port submitted under Item 3 of ,
the bulletin at the first scheduled refueling outage. This outage is currently scheduled for March, 1980.
- 80) 303
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If non-conformances are identified, a schedule for evaluation and resolution will be provided in accordance with the requirements of Item 4 of the bulletin.
In addition, the inaccessible piping will be inspected subsequent to a shutdown planned for not later than 120 days from the date of the bu?.letin.
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Inspection Package For each safety-related piping system, an inspection package will be used by the walkdown team to check the conformance of the physical arrangement in the plant to the design documents. This package and the level of detail to be inspected will include:
- 1. The current revision of the physical piping drawing and a checklist to verify the piping run geometry and the location of pipe fittings, tees, elbows, branch connections and concentrated masses, such as valves.
- 2. A valve drawing for each different valve on the piping drawing and a checklist to verify thct the valve installed in the piping system is the valve indicated on the valve drawing and that the orientation of the valve and operator with respect to the pipe axis is as shown on the piping physical drawing. Subsequent to the as-built verification, a comparison of the valve weight shown on the valve drawing will be made with the valve weight used in the analysis.
- 3. A inspection checklist for each floor and wall penetration will be used for checking the type of penetration closure (grout, rubber, etc.) against the design drawing. If the penetration is open, the clearances will be checked.
- 4. The pipe support detail drawing and a checklist for each pipe support and pipe anchor in the piping system will be used to verify locatien, orientation (direction), type, proper size, and that the support installa-tion is in accordance with the design document. Attachment of the support to the pipe will also be checked. Proper installation of concrete expan-sion anchors has been verified under the response to NRC IE Bulletin No.
79-02, and therefore, will not be an inspection element in this effort.
Attachment 2 to this response is the inspection package for' the High Pressure Injection System which is a safety-related piping system. This complete package is being submitted as an example of the information to be utilized for all systems, in lieu of the requested list of design documents, to expedite submission of the response to Item 1 of the bulletin. Inspection packages for each system to be inspected will be available for NRC review upon request.
Upon completion of the facility inspection effort, a comparison of the existing piping physical arrangment as recorded in the walkdown will be made against the seismic stress analysis problem input data. Any deviations and nonconformances will be evaluated in accordance with the guidelines established in Item 4 of the bulletin.
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Color Coded Piping and Instrumentation Diagran,,s
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The P&ID's have been color coded to identify the different systems or portious of systems that will be inspected under Items 2 and 3 of the bulletin.
- 1. Yellow signifies all accessible non-redundant systems and one train of accessible redundant systems.
- 2. Green signifies the other accessible train in the redundant system.
- 3. Blue signifies systems that are in the inaccessible areas.
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- ATTACHMENT 2 High Pressure Injection System Inspection Package
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Part A - Piping and Instrumentation Diagram Decay Heat Removal System and Emergency Core Cooling Systems Drawing No. 7749-M-033, Rev. 33, April 20, 1979 Part B - List of Piping Physical Drawings Piping Physical Drawing Checklist Floor and Wall Penetration Checklist Four Isometric Drawings Part C - List of Valves Valve Checklist Eleven Valve Drawings Part D - List of Pipe Anchors Pipe Anchor Checklist Seven Pipe Anchor Drawings Part E - List of Pipe Support Pipe Support Checklist 114 Pipe Support Drawings
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0 801 306
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ATTACHMENT 2 Part B
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_High Pressure Injection System List of Piping Physical Drawings
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Piping Revision Revision Drawing No. No. Date Title 7749-M-233B 16 Mar. 2,1978 Emergency Core Cooling Systems - Pump Suction Piping 7749-M-233D 13 Feb. 2, 1977 H. P. Injection System Auriliary Building 7749-M-233E 5 Nov. 6, 1975 H. P. Injection System Containment Building 7749-M-233F 10 Mar. 3, 1977 Low Pressure Injection System Auxiliary Building *
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801 307
Attachment 2 Part B
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PIPING PHYSICAL DRAWING CHECKLIST SYSTEM:
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Piping Drawing No. Rev. No.
- 1. Does the piping installation agree with the isometric?
- 2. Is all of the piping physically accessible?
If no, indicate on drawing what portion was not inspected and give the reason here:
- 3. Do the valve installations afree with the piping drawing?
If no, list valve numbers her,:
- 4. Are all floor and wall penetrytions shown on the piping drawing?
If no, indicate locations on piping drawing.
Note any deviations on the piping drawing.
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IN3PECTION TEAM NAME Date ,
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NAME Date 801 308
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Attachment 2 Part B
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e FLOOR AND WALL PENETRATION CHECKLIST SYSTEM:
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Piping Drawing No. Rev. No.
Penetration Sequence No.
- 1. Is the penetration shown on the piping drawins,7 If no, indicate on the piping drawing tF.e location of the penetration and identify floor or wall penetrated.
- 2. Indicate penetration clesure method Grout Bisco Foam Bisco rubber (hard)
Bisco boot Open (no closure)
Other
- 3. If open, indicate clearances less than 2". gp N e
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S EN IMOKING D&%'ARD IDOKING DIRECTION:
- 4. If for any reason, this penetratior is inaccessible, indica.te here . ---- --
and give the season why.
i, INSPECTION TEAM 5 NAME Date NAME Date
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- ATIACHMENT 2 High Pressure Injection System Part C List of Valves Vendor Valve Valve Foreign Vendor No. Description Manufacturer Print No. Drawing No. Rev. Date Piping Drawing No. 7749-M-233B B25-1 6"-GCB-GT Velan M-212-8-8 P3-1012-N-41 F Feb. 20, 1974 B25-2 6"-CCB-GT Velan M-212-8-8 P3-1012-N-41 F Feb. 20, 1974 B26-1 6"-GCB-CK Velan M-212-6-8 P3-1012-N-6 J Feb. 05, 1976 B26-2 6"-CCB-CK Velan M-212-6-8 P3-1012-N-6 J Feb. 05, 1976 Piping Drawing No. 7749-M-233D B59-3 4-HCB-GT Velan M212-3-6 P3-1012-N-2 E Feb. 10, 1977 B59-2 4-HCB-GT Velan M212-3-6 P3-1012-N-2 E Feb. 10, 1977 B59-4 4-HCB-GT Velan M212-3-6 P3-1012-N-2 E Feb. 10, 1977 B59-5 4-HCB-GT Velan M212-3-6 P3-1012-N-2 E Feb. 10, 1977 HV HP2D 2 1/2" Control Viv Velan M525-006 P-3521L-3A D Sep. 25, 1972 HV HP2C 2-1/2" Control V1v Velan M525-006 P-3521L-3A D Sep. 25, 1972 B7-3 4-CCB-CT Velan M212-26-4 P3-1012-N-18 C Aug. 08, 1973 B9-1 3-CCB-CL Velan M212-25-5 P3-1012-N-23 C May 14, 1979 B93-1 3-CCB-CK Velan M212-33-3 P3-1012-N-24 C Aug. 14, 1973 HV1556 3" Control V1v Hammel Dahl M314-042 V510L-9A 3 Sep. 07, 1973 B10-18 2 1/2-CCB-GT Velan M212-11-8 P3-1012-N-11 H Mar. 15, 1974 B7-2 4-CCB-GT Velan M212-26-4 P3-1012-N-18 C Aug. 08, 1973 B6-2 4-CCB-CK Velan M212-33-3 P3-1012-N-24 C Aug. 14, 1973 B7-4 4-CCB-GT Velan M212-26-4 P3-1012-N-18 C Aug. 08, 1973 B7-1 4-CCB-GT Velan M212-26-4 P3-1012-N-18 C Aug. 08, 1973 B6-1 4-CCB-CK Velan M212-33-3 P3-1012-N-24 C Aug. 08, 1973 HV HP2B 2 1/2" Control Viv Velan M525-006 P-3521L-3A D Sep. 23, 1972 HV HP2A 2 1/2" Control V1v Velan M525-006 P-3521L-3A D Sep. 23, 1972 B47-1 3-HCC-CK Velan M212-5-7 P3-1012-N-5 F Feb. 10, 1974 Piping Drawing No. 7749-M-233E B96-4 2 1/2 "-CCA-CK Velan M212-3-3 P3-1012-N-24 C Aug. 14, 1973 B2-4 2 1/2"-CCA-SCK Velan M212-10-7 P3-1012-N-10 H Sep. 16, 1974 B2-3 2 1/2"-CCA-SCK Velan M212-10-7 P3-1012-N-10 H Sep. 16, 1974 B96-3 2 1/2-CCA-CK Velan M212-33-3 P3-1012-N-24 C Aug. 14, 1973 B96-1 2 1/2-CCA-CK Velan M212-33-3 P3-1012-N-24 C Aug. 14, 1973 B2-1 2 1/2-CCA-SCK Velan M212-10-7 P3-1012-N-10 H Sep. 16, 1974 B2-2 2 1/2-CCA-SCK Velan M212-10-7 P3-1012-N-10 H Sep. 16, 1974 B96-2 2 1/2-CCA-CK Velan M212-33-3 , P3-1012-N-24 C Aug. 14, 1973 Piping Drawing No. 7749-M-233F ,
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No Valves
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801 310
Attachment 2
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Part C
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VALVE CHECKLIST
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SYSTEM Piping Drawing No. Rev. No.
Valve Item No. (from Piping Drawing)
Valve Item No. (from Valve Tag)
Valve Drawing No. (Bachtel Foreign Print No.)
- 1. Do the two valve item numbers agree?
- 2. Does the valve location agree with the piping drawing?
- 3. Does the orientation of the valve and operator (if any) agree with the piping drawing?
If any deviation is found, indicate it on the piping drawing.
- 4. If for any reason this valve or any portion of it is inaccessible, indicate here and give the reason 5,hy.
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INSPECTION TEAM
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NAME DATE NAME DATE 801 311
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ATTACHMENT 2
- High Pressure Injection System Part D List of Pipe Anchors Anchor No. Drawing No. Rev No. Rev. Date Title
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A040 07749-C-839 8 May 21, 1976 Emergency Core Cooling System A046 07749-C-841 3 Nov. 26, 1975 High Pressure Injection System t.047 07749-C-841 3 Nov. 26, 1975 High Pressure Injection System A048 07749-C-841 3 Nov. 26, 1975 High Preasure Injection System A049 07749-C-841 3 Nov. 26, 1975 High Pressure Injection System A050 07749-C-841 3 Nov. 26, 1975 High Pressure Injection System A051 07749-C-844 9 Oct. 17, 1977 High Pressure Injection System A052 07749-C-844 9 Oct. 17, 1977 High Pressure Injection System A053 07749-C-848 9 Nov. 18, 1975 digh Pressure Injection System A054 07749-C-848 9 Nov. 18, 1975 High Pressure Injection System A055 077'49-C-849 11 July 18, 1977 High Pressure Injection System A056 07749-C-842 4 Oct. 8, 1974 High Pressure Injection System A190 07749-C-842 4 Oct. 8, 1974 High Pressure Injection System A191 07749-C-842 4 Oct. 8, 1974 High Pressure Injection System A255 07749-C-885 5 Aug. 19, 1976 High Pressure Injection System A2S6 07749-C-885 5 Aug. 19, 1976 High Pressure Injection System A257 07749-C-885 5 Aug. 19, 1976 High Pressure Injection System A?58 07749-C-885 5 Aug. 19, 1976 High Pressure Injection System A392 07749-C-885 5 Aug. 19, 1976 High Pressure Injection System
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0 801 312
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Attachment 2
- Part D
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PIPE ANCHOR CHECKLIST SYSTEM:
- Piping Drawing No. Rev. No.
Anchor No.
Anchor Drawing No. Pev. No.
- 1. Does the anchor configuration agree with the design?
- 2. Do the sizes of the structural and load carrying memberc agree with the design? (including the wrapper plate, if any)
- 3. Are the welds per the design?
If no to any of the above questions, indicate any deviations below or on the d2 tail drawing.
- 4. If for any reason, this anchor or any portion of it is inaccessible, indicate here and give the reason why.
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INSPECTION TEAM
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NArfE DATE
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NAME DATE
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. Attachment 2
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Part E
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- PIPE SUPPORT CHECKIIST SYSTEM:
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Piping Drawing No. Rev. No.
Pipe Support Park No.
- 1. Does the pipe support configuration agree w!th this design?
- 2. Does the type of support agree with the design?
(ie: snubber, spring, sway strut, rigid frame)
- 3. Answer the fallowing, if applicable.
a) Do the sizes of the structural and load carrying members agree with the design?
b) Are the welds per the design?
c) If there are any welded attachments to the pipe, are they per the design?
d) Are clearances (other than the 1/16" gap provided in the direction of support) in agreement with the design?
e) Is the size of the snubber / spring / sway strut according to the design?
f) Is the spring or snubber within its travel range? (non-Q snubbers only) g) Has the apring travel stop been removed?
If no to any of the above questions, indicate on the detail drawing any deviations.
- 4. If for any reason, this support or any portion of it is inaccessible, indicate here and give the reason why.
- 5. If the support does not look like the design, or if the design drawing is not available, or if the support has not been identified as inspection element, indicate here and explain. ,
INSPECTION TEAM
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NAME DATE
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NAME DATE 001 314