Similar Documents at Perry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20217E7111999-09-30030 September 1999 Documents Telcon Conducted on 990929 Between M Underwood of Oh EPA & D Tizzan of Pnpp,Re Request to Operate Pnpp Sws,As Is,Until Resolution Can Be Obtained ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 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 ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 ML20210Q7981999-08-10010 August 1999 Informs That Intention to Utilize Sulfuric Acid in Pnpp Circulating Water Sys to Lower Ph Is Anticipated to Be Completed in Nov ML20210Q5831999-08-10010 August 1999 Requests Permission to Chemically Treat CWS for Algae Due to Cooling Water Basin Becoming Infected with Algae of Various Types PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions 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 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPY-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 PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 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 ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions 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 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records PY-CEI-NRR-2404, Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology1999-06-0707 June 1999 Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology ML20195E4561999-05-25025 May 1999 Submits Petition Per Other Actions Provision of 10CFR2.206,requesting That Radiation Protection Manager at Perry NPP Be Banned by NRC from Participation in Licensed Activities at & for Any NPP for at Least Five Yrs PY-CEI-NRR-2401, Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars1999-05-20020 May 1999 Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars PY-CEI-NRR-2402, Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs,1999-05-18018 May 1999 Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, PY-CEI-NRR-2394, Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested1999-05-0505 May 1999 Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested PY-CEI-NRR-2397, Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.51999-04-30030 April 1999 Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.5 PY-CEI-NRR-2396, Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-en1999-04-28028 April 1999 Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-end Weld 05000440/LER-1999-002, Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available1999-04-26026 April 1999 Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available PY-CEI-NRR-2388, Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits1999-04-22022 April 1999 Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits 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 PY-CEI-NRR-2371, Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted1999-04-21021 April 1999 Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted PY-CEI-NRR-2392, Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette1999-04-19019 April 1999 Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette PY-CEI-NRR-2387, Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 1051999-04-14014 April 1999 Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 105 PY-CEI-NRR-2386, Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing1999-04-0606 April 1999 Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20206N3361999-04-0505 April 1999 Informs NRR of Continued Events Re Transfer of Generation Assets Between Duquesne Light Co & Firstenergy.No Negotiated Settlement Between Firstenergy & Local 270 Pertaining to Generation Asset Swap Has Been Reached PY-CEI-NRR-2383, Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed1999-04-0101 April 1999 Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed PY-CEI-NRR-2384, Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC1999-04-0101 April 1999 Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC L-99-052, Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding1999-03-30030 March 1999 Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding 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) ML20205H6171999-03-29029 March 1999 Forwards Util Consolidated Financial Statements for Twelve Month Period Ending 981231 & Internal Cash Flow Projection, Including Actual 1998 Data & Projections for 1999 PY-CEI-NRR-2380, Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure1999-03-25025 March 1999 Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARPY-CEI-NRR-1226, Forwards LERs 90-018-00 & 90-019-00 for Plant1990-09-14014 September 1990 Forwards LERs 90-018-00 & 90-019-00 for Plant PY-CEI-NRR-1218, Responds to Generic Ltr 90-07 Re Proposed OL Exam Schedule, Operator Requalification Schedule & Generic Fundamental Exam Schedule for Plant.Licensee Will Continue to Train & Requalify Operators on Annual Basis1990-09-10010 September 1990 Responds to Generic Ltr 90-07 Re Proposed OL Exam Schedule, Operator Requalification Schedule & Generic Fundamental Exam Schedule for Plant.Licensee Will Continue to Train & Requalify Operators on Annual Basis ML20059E8741990-09-0505 September 1990 Forwards Fourteenth Quarterly Rept Cleveland Electric Illuminating Co Seismic Monitoring Network Jan-June 1990. Five Microevents Originating within Network & Three Other Events Originating Outside of Network Recorded PY-CEI-NRR-1216, Forwards Perry Nuclear Power Plant Unit 1 Semiannual Radioactive Effluent Release Rept,1990 Quarters 1 & 2. Response to Recommendations from NRC Re Range of Dilution Flows Will Be Submitted W/Next Effluent Rept1990-08-29029 August 1990 Forwards Perry Nuclear Power Plant Unit 1 Semiannual Radioactive Effluent Release Rept,1990 Quarters 1 & 2. Response to Recommendations from NRC Re Range of Dilution Flows Will Be Submitted W/Next Effluent Rept PY-CEI-NRR-1201, Forwards First Semiannual fitness-for-duty Rept for Plant for 900103-0630,per 10CFR26.71(d) Requirements1990-08-28028 August 1990 Forwards First Semiannual fitness-for-duty Rept for Plant for 900103-0630,per 10CFR26.71(d) Requirements PY-CEI-NRR-1211, Responds to NRC Re Violations Noted in Insp Rept 50-440/89-26.Corrective Actions Noted:Necessary Engineering Design Mods Which Evaluation Found Necessary Contained in DCP 90-00861990-08-23023 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-440/89-26.Corrective Actions Noted:Necessary Engineering Design Mods Which Evaluation Found Necessary Contained in DCP 90-0086 PY-CEI-NRR-1210, Proposes Date of 901207 to Provide Updated Status & Schedules,Per 900604 Request for Addl Info on Disposition of Bulletin 88-005 Product Forms Other than Pipe Fittings & Flanges Received at Plant1990-08-17017 August 1990 Proposes Date of 901207 to Provide Updated Status & Schedules,Per 900604 Request for Addl Info on Disposition of Bulletin 88-005 Product Forms Other than Pipe Fittings & Flanges Received at Plant PY-CEI-NRR-1208, Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl1990-08-10010 August 1990 Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl PY-CEI-NRR-1203, Provides Estimate Duration Schedule Re Installation of post-LOCA Neutron Monitoring Sys.Util Will Evaluate Effect of Resolution on Schedule & Confirm or Revise Installation Date as Needed,When Appeal & Criteria Questions Resolved1990-07-27027 July 1990 Provides Estimate Duration Schedule Re Installation of post-LOCA Neutron Monitoring Sys.Util Will Evaluate Effect of Resolution on Schedule & Confirm or Revise Installation Date as Needed,When Appeal & Criteria Questions Resolved PY-CEI-NRR-1200, Forwards Decommissioning Repts on Financial Assurance for Plant1990-07-25025 July 1990 Forwards Decommissioning Repts on Financial Assurance for Plant PY-CEI-NRR-1196, Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan1990-07-24024 July 1990 Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan PY-CEI-NRR-1205, Forwards LERs 90-014-00 & 90-015-00 for Plant1990-07-20020 July 1990 Forwards LERs 90-014-00 & 90-015-00 for Plant PY-CEI-NRR-1193, Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues1990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues ML20043H7371990-06-19019 June 1990 Forwards Individual Plant Exam Project Milestones.Milestones Subj to Change from Project or External Causes & Will Not Be Docketed Again Unless Significant Impact on Final Rept Contents or Submittal Date Exists ML20043H1711990-06-14014 June 1990 Discusses Util Radiological Safety Board of Ohio 900614 Comments on Notice of Opportunity for Hearing Re Rev to Previously Submitted License Amend Application.Licensees Would Welcome Opportunity to Consult W/State of Oh ML20043E5771990-06-0808 June 1990 Provides Info Re Implementation of Administrative Controls & Training Related to Use of Tech Spec 3.0.4.Util Intends to Implement Amend 30 Changes by 900618.All Licensed Operators Would Receive Training to Generic Ltr 87-09 ML20043B6981990-05-21021 May 1990 Forwards Info Re Activation Energy Values Utilized for Brand-Rex Co Cable at Facility.Encl Includes Rept, Qualification Tests of Electric Cables for Class 1E Svc in Nuclear Power Plants. ML20043A7041990-05-18018 May 1990 Forwards LERs 90-007-00 & 90-008-00 ML20043A4771990-05-16016 May 1990 Provides Justification Re Events Leading to Declaration of Alert on 900403 Due to Loss of Emergency Svc Water When Manway Flange Gasket Leak Developed at Pump a Discharge Strainer,In Response to Ocre 900406 Petition ML20042F4931990-05-0404 May 1990 Forwards Response to Generic Ltr 89-19 Re Reactor Vessel Overfill Protection 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 ML20042F8051990-04-19019 April 1990 Forwards 1989 Financial Repts for Centerior Energy Corp, Cleveland Electric Illuminating Co & Toledo Edison Co & Supplemental Sec Form 10-K ML20012F3521990-04-0202 April 1990 Suppls Response to NRC 891215 Ltr Re Deviations Noted in Insp Rept 50-440/89-26.Corrective Actions:Profile of Heat Generation from Stored Fuel Vs Time for First Four Fuel Load Discharges Calculated & Design Changes Implemented ML20012E7811990-03-30030 March 1990 Confirms Basis for 890417 Submittal Re Station Blackout ML20012E9431990-03-26026 March 1990 Forwards Correction Pages to Semiannual Radioactive Effluent Release Rept 1989:Quarters 3 & 4. Changes Affect Liquid Effluent Data Only.Corrections Made Due to High Contribution of Sr-89 to Liquid Effluent Dose ML20012B9851990-03-0909 March 1990 Responds to Generic Ltr 90-01 Re Regulatory Impact Survey ML20012B5931990-03-0808 March 1990 Responds to Open Item Noted in Insp Rept 50-440/89-29. Corrective Actions:Plant Health Physicist & Operations Superintendent Met W/Health Physics & Operations Crews to Discuss Better Methods of Access Control ML20012A1561990-03-0202 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Addl Info in Response to NRC 890605 Ltr Re Offsite Dose Calculation Manual ML20012B9801990-03-0202 March 1990 Responds to 890810 Request for Addl Info on Util 890306 Tech Spec Change Request Re MSIV Leakage Limits.Change Does Not Request Increase in MSIV Leakage Beyond Currently Assumed in Updated SAR Chapter 15 ML20006E5131990-02-12012 February 1990 Lists Suggestions on Subj Areas to Be Addressed During Proposed 1990 Licensee Info Conference,In Response to 900117 Ltr ML20006E3211990-02-0909 February 1990 Discusses Implementation of Facility Revised Inservice Testing Program,Per Generic Ltr 89-04.Improvements Listed, Including sign-off Matrix Deletion at End of Instruction & Movement of Comments Section ML20006D0971990-02-0202 February 1990 Provides Update to 880721 Ltr Re Performance of Seismic Margin Evaluation.Util Awaiting Issuance of Individual Plant Exams of External Events Generic Ltr Prior to Proceeding W/ Seismic Margins Study ML20011E1841990-02-0202 February 1990 Forwards LERs 90-001 & 90-002 ML20006D5731990-01-30030 January 1990 Forwards Response to NRC 900112 Request for Addl Info Re 891121 Request for Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii).Qualification Plan for Certification of Existing Simulator Approved in Aug 1987 ML20006B5131990-01-26026 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of Type 410 Stainless Preloaded Bolting in Swing Check Valves.No Bolts Subj to Bulletin in Use at Facility ML20006B5571990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Procedures in Place for Underwater Insp of Intake Structures in Lake as Well as on-shore Pump Houses Annually ML20006A0781990-01-16016 January 1990 Responds to NRC 891215 Ltr Re Deviations Noted in Insp Rept 50-440/89-26.Corrective Actions:Profile of Heat Generation from Stored Fuel Vs Time for First Four Fuel Discharges Calculated & Updated SAR Change Request Will Be Submitted ML20005F9331990-01-0909 January 1990 Provides Inadvertently Omitted Inequality Signs from Util 891213 Response to NRC Bulletin 88-004 Re RCIC Pump Min Flow Limitations from Operating Instructions ML20042D5051990-01-0303 January 1990 Informs That Licensee Implemented fitness-for-duty Program at Plant on 900103,per 10CFR26.More Stringent cut-off Levels Imposed by Util than Required by 10CFR26 ML20005E1391989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Each motor- Operated Valve Will Be Stroke Tested to Verify Valve Operability at no-pressure & no-flow Conditions ML19332F7941989-12-13013 December 1989 Responds to NRC 890531 Request for Addl Info Re NRC Bulletin 88-004, Safety-Related Pump Loss. Info Covers pump-to-pump Interaction That Could Result in Deadheading & Adequacy of Min Flow Bypass Lines Against Pump Damage ML19332E6921989-12-0707 December 1989 Responds to Violations Noted in Insp Rept 50-440/89-12 on 890627 & 1023.Corrective Actions:Flange Leakage of Relief Valve Repaired During First Refueling Outage & Design Mods to Enhance Testability of Gasketed Flanges Being Developed ML19332F3851989-12-0606 December 1989 Forwards Twelfth Quarterly Rept Cleveland Electric Illuminating Seismic Monitoring Network,Jul-Sept 1989. Rept Describes Area in Vicinity of Two Waste Injection Wells Located 3 Miles South of Plant Site ML19332E7971989-12-0101 December 1989 Responds to Generic Ltr 89-21 Re Implementation Status of USIs ML19332E3611989-11-28028 November 1989 Submits Supplemental Info Re Tech Spec Change Request Proposing Addition of Requirement to Verify Trip Setpoint of Intermediate Range Monitor Control Rod Block Instrumentation During Performance of Weekly Channel Functional Testing ML19332D5771989-11-27027 November 1989 Submits Supplementary Info to 880520 Tech Spec Change Request,Changing Setpoints for Turbine First Stage Pressure to Reflect Values Actually Measured During Startup Test Program at 40% of Rated Reactor Power.Table Encl ML19332C7341989-11-22022 November 1989 Forwards Executed Amend 3 to Indemnity Agreement B-98 ML19332C4041989-11-22022 November 1989 Responds to NRC 891025 Ltr Re Violations Noted in Insp Rept 50-440/89-23.Corrective Actions:Work Stopped on Div III & Restoration Began to Return to Operation & All Actions Required by Tech Spec 3.0.3 Completed ML19332C8321989-11-21021 November 1989 Forwards Inservice Insp Summary Rept NP0059-0001, Results for Outage 1 (1989),First Period,First Interval, Vols I & Ii,Covering Insp Period 871118-890805 ML19332C4531989-11-21021 November 1989 Requests Exemption from Requirements of 10CFR45.(b)(2)(iii), to Allow for Submittal of NRC Form 474, Simulation Facility Certification, After 910326 Deadline 1990-09-05
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5 THE CLEVELAND ELECTP,1C ILLUMIN ATING C016PANY ettumaims stoc. . rusue sovant . ettvataNo. omo anoi . titer,.oN ami sn.use . ud soc,ntss e.o sox sooo Serving The Best Location in the Natyn Dahyyn R. Davidson
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- - May 1, 15ff8 _ i -
4 Mr. James G. Keppler, Director U.S. Nuclear Regulatory Co ission Region III Office of Inspection and Enforcement 793 Roosevelt Road Glen Ellyn, niinois 600137
Dear Mr. Keppler:
This letter is our response to your Icmediate Action letter of yebmary 8, 1978. The Imediate Action Ietter addressed eight areas of concern.
Tne first five ite=s have been resolved with the members of your staff, as a result of inspections on site and review of the actions taken on our part. In order that this letter be co:plete, I have attaebe5 as Appendix 1 a brief su-y of the first five itecs and resolution status.
Vith respect to Items 6, 'l and 8 of your letter, a thorcrash review was uniertaken both interns.ny and s-ith the use of an cratside auditing team, it crder for us to aSdress these concerns.
Ite- 6 of the 7ebruary B,1978 Tr: mediate Action letter in part identifies tu teed to establish an effective contract specificLtionr control syste=.
It response to this concern, the syste= vas reviewed including auditing er t.11 project and sr.fety-related contractors files.
It the audit of the existing files deficiencies which vere ferand, have beer. corrected and au files updated including control copies. The
" Specifications" include attachment Specificatiens, Engineering Change Estices, and Field Varis,nce Autberizations. .
The system was then reviewed and several rodifications vere made. In
- Eeneral these consisted of the :follcuing: ,
A. The syste= nw utilizes a control number distribution with l return receipts required. All distribution responsibilities l are nw at the Site Document Control Centar.
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- 2. The specifications status system is in part monitored on a
> (7 ' '/ T co:Puterited/ ten.inal system identified as EEWSPEC. Field i Variance Authorizations are presently monitond manuaHy.
A maintenance system was established which centralizes the responsibility for inputting of all new or change in-
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formation through the Site Document Control Center. The 8309290080 830622 PDR FOIA HIATT83-199 PDR .
6 Mr. James G. Keppler May 1, 1978 i:
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system provides for continuous monitoring of specification <;
status, bovever, periodically, at a minimam quarterly a status reviev vill be conducted as spelled out in a pr,oject procedure. In addition, audits by Site Quality Assurance - a vill be performed to verify correctness.
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C. The project and contractor files were updated including elimination of xerox copies.
D. Procedures were developed to define the syste= and spell crat the me banics to operats it. In addition, instructions have been developed for personnel operating the system.
E. All project and construction personnel received training and indoctrination presentations. Included were the familiarization with the procedures and scoping of responsibilities.
With the implementation of the above ve consider we have in place an effective syste= for assuring the timely and controlled distribution of specifications. All safety-related construction contracts are included and non-safety and equipment contracts vill follow.
An evaluation was perfomed to deter =ine the acceptability of the concrete batched by Fational Hobile Co=pany to a superseded design specification during the time period from August 5,1977 to Tetruary,1978. roe result of this evaluation by the cognizant design engineer concluded that the concrete produced to revision VI of EP-14-45hn-CXXO vill satitty the.
design recrairements. Each of the 31 notifications that were cade in revision VII of SP-lh-h5h9-0000, vere evaluated. These modificationc vere in the following general e.rer.r:
- 1. Expansion and clarification to rcrovt redundencies and resolve conflicts.
- 2. Fodification of certain procedural changet that do not affect quality.
3 Modification of certain requiremente to facilitate field conditions withcrat sacrificing quality.
Most of these modifications incorporated into revision VII had been previously issued as ECN's applicable to revision VI. It is our opinion and that of the responsible design engineer, that production of quality concrete at the Perry Plant vac not affected by any re-vision of the specification being held by the batch plant contractor.
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3- May 1, 1978 ,
d s -i Item 7A. An evaluation of the indoctrination and trainirig program
<f was made. It was concluSed that the program needs improvement.
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Accordingly CEI will restructure the indoctrination and training program to include a unifom appromeh to indoctrination w25 training - .
for various organizations, including contractors. Outlines sill be ccc:pleted by mid-May and the schedule for implementing training sessions vill be co=pleted by the third week of May. Regular in- ,
doctrination sessions vill be started during May and vill continue on a regular basis as defined in the indoctrination and training outline.
Item 73. Daring our evaluation it was determined that the noncon-formance reporting system as implemented on the site, is an effective system. There have been occasions however vbere documents other than nonconformance reports have been used to note problem areas. Effective imediately, a policy statement has been issued that only noncon-fomance reports will be utilized in defining nonconfoming conditions.
Item B. To evaluate our program effectiveness, a special quality Assurance Task Force was established consisting of representatives from Gilbert Associates, Inc., Kaiser Engineers, CEI and an independent QA consultant Mr. J. P. Jackson of Management Analysis Company. The Epecial QA Task Force has performed a thorough evaluation including on-site and off-site audits.
This Task Force issued an Interim and a Final Report evaluating the overall effectiveness of our program. Tne methodology of the Task Force was to conduct indepth interviews with all key project personnel plus audit selected contractors and site elemen's (CQA, CQO and FCbD),
and the home office departments (NED, Purchasing, and KQAD).
Tne Tash Force then evaluated the results of these audits end interviews with respect to the effectiveness of the progrs=. This translated into specific findings relative to the appropriate 100TR50, Appendix 3 criteria and the FHFp PSAR Chapter 17 cc.__itseents.
Recoc=,endations vere provided and a plan has been established based on these findinge in order of priority which addressed relative significance to the action necessary to improve our progran effectiveness. The priorities themselves were based on:
- a. Those items which were critical to the overall corrective action progra= and required top canagement priori.ty,
- b. Those actions which vere required for QA program implementation,
- c. Those actions required for improves'ent to the QA program.
The following conditions were identified as a result of crar evaluations as those that have contributed to the causes of the items identified I
as Items 1 through 6 in the Immediate Action Letter.
'J Mr. James G. Keppler -%- May 1, 1978 '
A. The CEI QA Program is de' fined in many different manuals. 7 There is no single nanual that defines critical controls necessary to implement the QA program on a corporate basis. This lack of definition as to vbo is responsibla ,
bas resulted in confusion as to primary responsib,ility in implementing the program.
- 2. The techniques for resolution of conflicts has not provided timely response to noted problem areas. Additionally, the degree of r.anagement involved in resolving problem areas within the CEI QA program has ncrt been co=:ensurate with the need for resolution of QA program issues.
C.
The reorganization of 1977 vbich merged the Site QA/QC .
activities, created voids in certain areas of the QA pro-gram vbich should have included redefinition of responsibilities, particularly in the area of surveillance / inspection and audits.
3.
Each contractor is held totally responsible for total QA pro-gram, with: rat consideration for the integration of CEI QA/QC functions with those of those contractors.
Comensurate with the priority of the recomendations CEI bas acco:plished those items vbich were identified as critical to the overall corrective action program and required top r.anecesent priority. Tne following su=arines the changes initiated and co=pletti.
Item 1 -- The M/QO organization at the site has been re-organized to unify it under tbt direction of a Ge:ertl Supervising Evinee:. 1:. oddition the, assignments be.ve been revised so as to provide
- e. single rer;casible quality engineer for each contrLeter.
Ite::. 2 -- Tne Sitt C atlity Enutls are it the process of being consoliitted reflecting the redefined responsibilities and procedures of the site @/QO organize. tion.
i Item 3 -- A QA Advisory ccrJ- ttee has been established to assist '
the CEI Nuclear Quality Assurance Department Manager with inputs and reco=endations to key program de-cisions, orientation of QA concepts and methods as well asaccessingoverallcorporatesupportbyCEI/GAI/EEI to the direction taken by the Nuclear Quality Assurance 1 Department Manager.
This committee vill te co= prised of Mr. M. R. Edelman,-
Manager of the Nuclear Quality Assurance Department, Mr. R. R. Barker, Manager of Construction QA at Gilbert Associates, Mr. E. V. Knox, Corporate QA Manager of l Kaiser Engineers. '
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, Mr. James G. Keppler May 1,1978 Item h -- The Nuclear Quality Assurance Department Manager 'I has established a plan thieb provides a schedule for completing modification to the QA program.
Weekly meetings have been scheduled to track and ,
report progress to upper management. ,
Additionally, the Nuclear Quality Assurance Depart-ment Manager has established a program of quarterly reviews to CEI top management to incorporate the inputs from the Advisory Co=ittee, as well as, re-view the QA program through evaluation of audits, corrective action reports and other management tools.
Item 5 -- ne nuclear Quauty Assurance Department has been reorganized to reflect the findings and reco=mendations of the Audit Task Force. Attachment 2 depicts the revised organization and lists the primary responsi-bilities of the key individuals involved.
Item 6 -- CEI has established a schedule for the restructuring of the audit program, both at the Site, our con-tractors and our QA agents.
Item 7 -- CEI has established and has started the i=plementation at the Site of an integrated inspection / surveillance progra=. The progra= includes witness points tied to contractors inspection planning documents and includes in-process surveillance inspections, as well as, surveillance inrpection of completed work, he surveillu.ce intpection planning vill be approved by a respontitle Quality Engineer. Co:plete i=ple entEtion is anticiptted by rid-Jun?..
Ite= 8 -- Tne receiving inspection program has been expanded beyond e. count and ds= age check and is nov based en input of quality engineering to deter =ine on a ca.se by case basis the necessary inspection required.
Implementation has been started with co=plete imple=entation anticipated by mid-June.
i Item 9 -- The NQAD Manager vill use the formal management chains to resolve conflicts, with the corporate QA program clearly indorsing his authority to resolye quality issues. The corporate quality assurance management co= ittee has been redefined as a communication vehicas.
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. i Mr. James G. Keppler
- 6 h y 1, 1978 ,
In addition, actions that were identified by the Task Force and deemed ,.
necessary, but not yet cotqpleted, are as fonows: ,
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1.
CEI has strengthened our quality assurance program, by .
- co:qpleting the items described previously. In addition ve purpose to reissue our Corporate Raality Assurates htraal to reflect these improvements as ven as clearly define the interfaces between an departments performing quality related functions. This manual win reiterate the strong CEI co:r.itment to the @ program indicating that the u.anual wast be followed by au persons involved with respect to the Perry Project, and that changes will be considered and processed immediately if the situation varrants. The manual win clearly provide guidance on how CEI will address with liegulatory Guides identified in the PSAR. Sebeduled cecpletion date for issuance of this r.anual is August,1978.
- 2. CEI will evaluate the effectiveness and erpertise of pre-sently available in-house personnel, consistent with the revised departmental organization. CEI wi n e= ploy ex-perienced quality assurance personnel in the key supervisory roles as defined on the revised organization chart as shown in Attaebment ccepleted 2 1.
by June of this let.::. This evaluation vin be CEI vin continue to draw upon Gilbert '
Associates and Kaiser perro.nel fer support as deemed necessary by the Nuclear QA Department h*.tger.
3 CEI will restructure the t.uiit yrogra= and coordinate the audit review reports fro = all ele .setr . The audit program win cover all arpects of tbc prg :e including agents, design e.ctivities, construction e.etivities as well as internal CEI e.etivitie t . Tnis revised tudi, progra= vin . serve as the backbone f er the Nuclear Raality Assurance Depe.rtment Manager as e tool to e.ecess the effectiveness of cr.tr overe.11 E pro-crte . Tr.it iE anticipated to bt implemented by June 1.
- h. CEI vin Irovide direct support to selected contractors in the QA/E t.rea vbere it is deterr.ined by the responsible quality engineer that such support is needed. This vin prevent der. suds on contractors to establish @ programs that are beyond their capabiMties to implement effectively.
This will be implemented on as needed basis. ,
- 5. Additional detailed reco==endations for improvement in the CEI QA Program based on the Special QA Task Force have been reviewed and win be included as aIpropriate in the revised QA Manual. These are anticipated to be completed by August 1,1978.
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- Mr. James G. Keppler May 1, 1978 ,
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In sumary the three month accessEent made of our program'by the out- <.
side auditing team plus our own evaluations as to our effectiveness ,
bave provided beneficial input to au parties involved. gignificant inprovements have been made and win continue to be made to make our - +
program overall more effective. I will provide close attentfon to the development of the revised QA Eanual and review the effectiveness of our overall quality assurance progrs=. With the co=itments that we have made and, the changes that have been i=plemented, we feel that our quality assurance progra= vill provide a effective means of controlling quality on the Ferry Project to insure the plant is built to applicable standards and designs.
Very truly y:rars,
/ 1 *]
Dalvyn Davidson Vice President - Engineering DRD:ge Attachments m
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ATTAGOENT 1
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SU!FJJtY OF ACTION TA}ri ON IJCTDIfE ACTION IMR ITnG 1-5 RAC) GROUND Based on concerns noted in Iteu l-5 of the liRC Imediate Action 14tter of February 8,1978, numerous actions have been taken and these actions have received concurrance during various ERC' inspections. The following is provided as a su:r:utry of these activities. IrnC letter of March 31, 1978 Inspection Report 2io. 50-Wo/78-03, 50-M1/78-02 provide additional detail and liRO evaluation on these actions.
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.. Item.1 and 2. Safety-Related Piping Tabrication and Installation
' ' Deficiencies noted by the NRO, prompted CEI QA Elements to st.op work on Pullman Power Products in the areas of safety-related pipe fabrication, yard piping installation, and Plant piping. Several modifications to the specifications 't and the quality program requircents were initiated by CEI, GAI, and PPP. ibese measures included Pullman initiat-ing procedures for " Document Control" and " Design Control" ' -
vbich were sub:titted to and approved by the CQA Element.
Pullman fabrication and erection drawings have be'en submitted to GAI Design Ingineer for review and approval in accordance v' these procedures. Gilbert Engineering has issued an EU to SP-W vhich establishes the requircents for the Design Ingineer's review of contractor's piping drawings.
This area has been monitored by CQA to assure that these requirements are being met.
Pullman has implemented a procedure for "Pield Handling of Materials and Equipment" which was approved by the CQA
- Ilement. CQA has vitnessed Indoctrination and Training classes conducted by Pullman on QA Program Requirements. These
/ classes were documented and are to continue on a regular basis.
Pullman has since e= ployed a training officer on site to conduct these classes.
One hundred percent surveillance inspection was implemented by the GAI Resident Inspector at Pullman's Williamsport, Pennsylvania shop. On March 16, 1978, Mr. R. L. Spessard of ERO Region III approved the use of a sa=pling plz.n per MSP-033, Rev. 3, and CEI letter dated Mareb 9,1978.
CEI letter dated February 18, 1978 established the retaire-ment for the GAI Design Engineer to:
- 1. Review 10D% safety Clast I rpool drawingt.
- 2. Sa=pling per MSP-033, Part.. C.3d applied to spool dravings or.ly for refety Class II an".
III.
Subsequent KRO review of there corrective action mer.rares resulted in the release of P@n Power Products for safety-related work.
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Item 3. PBI Industries sarety-Related structural steel and Ibbeaments ,
The installation procedural controls on safety-related ested='ents and structural steel have been todified to assure co:pliance to AWS D.1.1-1972 prior to placement. The CQC element-bas superimposep an inspection program of 100% verification of the vendor's and our manufacturing assurance inspection programs.
These additional inspection measures include 100% recei'ving in-spection of au new embedments and structural steel delivered to the site,10$ inspection of all e. bed:ents and structural steel currently in inventory prior to their issuance to contractors, and for those ite=s previourly issued,100% inspection of all e= bed =ents and structural steel prior to their placement.
These currently established zeacures have been reviewed and found acceptable by 23C inspectors as indicated in the March 31, 1978 report (50-40/78-03,50-W1/78-02).
To establish cocpliance at the vendor's facilities the CEI vendor assurance progra= bas been increased to include 100% surveillance of all e= bed =ents and structural steel being fabricated. Finally, the vendor's inspection program has been altered to include the additional detailed acceptance criteria provided by the Design Engineer.
' When FBI and its subsidiaries are released to resume shi Irnents, and all existing inventory has been inspected, an evaluation shall be performed to deterrine the future procedural controls for assuring co plience to AWS D.1.1-1972. This evaluation and reco= ended course of action sban be discussed with the NRO prior to being i=plemented.
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Item h. ' O. B. Connon Nuclear Coatings As a result, of the deficiencies noted by the NRC, C@ issued a Stop Work Notice and Corrective Action Request (CAR) to 0. B. Cannon.
ne CAR identified five deficient conditions in their E program 't and inplementing procedures in the areas of verification of r.aterials prior to use, qualifications of personnel, and performance of audits.
De contractor's response to the Corrective Action Request , included .
(1) the correction of coating applicators' qualification l records in accordance with 0. B. Cannon procedures; (2) the inspection status tagging of all cans and cartons of coating raterials in the storage area; (3) the r.issing physical ex- '
ar.ination record was returned to 0. B. Cannon's site QC file; (4) the O. B. Cannon QC manual was revised to include the re-view and approval of manufacturers' material certification; and (5) the contractor's first internal project audit was perfonned. -
ne contractor's implementation of these corrective actions was verified by CM and a partial stop work release for Class II coating work (non-safety related) was issued.
D en February 18, 1978, the NRC reviewed O. 3. Cannon's E program and procedural improve =ents and observed the corrective actions taken.
As a result of this review and observation, the NRC inspector concluded that safety-related coating work could be pemitted to rer.nne. - Sub-sequentially, a full stop work release was e.pproved and issued by CM. -
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's Item 5. Safety-Related Concrete Placement '
prior to resuming safety-related concrete placement by each of our four placement contractors, several QA program adjustment's were made. V These changes included a new slump testing procedure Wich requires, upon detection the higb/ low slump, the suspension of placement and the sagling of each truck until slump is back within specified limits. ~
An indoctrination and training meeting was held with contractor's vibrator operators and a proce$ ural requireaent was added to rebrief and provide attestation of vibration operator training prior to each placement.
The CQO detailed procedures and inspection plans were re-vised to reflect ireplementation of 100% CQO inspection of contractor preplace ent inspection activities. CQA performed detailed program audits of each contractor and CEI r.anagement met with contractor ranagement to e=phasize their contractural obligations with respect to quality control. t I
t Upon co=pletion of these activitieg and the review and inspection lof preplacements by KRO inspectors, contractors were individually released to place safety-related concrete. Th;n,inadditiontocontinued100%
i CQO inspection, CQA performed audits of preplacement and placement activities by both the contractor and CQO on all safety-related pours.
A subsequent CQA evaluation of these audits was reviewed by and agreed to by the ERO on April 14, 1978 and the CQA audit freguency on two of i the contractors (National Engineering and Great Iakes) vas reduced to one audit per week.
t As of this response date, the other two contractors (S & M and MCK ___ _
Corporation) shall continue under the CQA audit of every placement progra: until several pours can be made by each organization and a level of confidence is established.
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ATTACHMENT _2 OR3ANI7ATIONAL RESPONSIBILITIES 4 i
'i (A) Construction Quality Section - GSE " -
- 1. Coordinate all site quality functions 2.
Primary contact Nuclear Regulatory Ccc:::ission inspections ,
3 Responsible for all line supervisory functions (3) Raality Ingineering (Construction Qaality Section)
- 1. Contractor quality assurance programs
- 2. Establishing inspection requirements Coordination and disposition of nonconformance reports 3 -
- h. Obtain correction action 5
Contractor; procedure review
- 6. Receiving inspection plan 7.
Audit contractors / site organization B. Review procurement documents 9 Analysis Establish and reports trends site quality assurance records require =ent 10.
- 11. Coordinator off site quality infort:.ation requests (C)
Quality Administration (Construction Raality Section)
- 1. Audit tracking
- 2. Indoctrinatica and training 3 Quauty manual control
- k. Quality assurance records 5
Eonconfomance Report controa. ,
(D)
Inspection (Construction Quality Section)
- 1. Surveillance inspection
- 2. Receipt inspections 3 I)o:a=entation of inspections
- h. Prepare Konconfomance Reports (E) Program Quality Section - GSE 1.
Coordinate all design, procure =ent, manufacturing activities Primarily
- 2. Resp,onsible for agents quality assurance efforts, inc.
GAI/QA Program
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3 Responsible for all line supervisory functions t
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.. , q ATTACHMDIT 2
(~)
F Quality Engineering (Program Quality Section) ;
Review of contracts
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,- 1. ,,
- 2. Vendor preavard meetings '
- 3. support audit program
- 4. Quality engineering support to Nuclear Engineering Department '
- 5. Quality engineering support to Purchasing '
- 6. Safety Analysis Report reviews *
(G) Quality Assurance Administration (Program Quality Section)
- 1. Audits
- 2. Indoctrination and training
- 3. Procedures
- 4. Records ,
- 5. Sebeduling and expediting .
, (B) Operational Quality Assurance (Program Quality Section)
- 1. Operations " quality assurance progrs= planning
- 2. Startup and Test quality assurance support (I) Quality Assurance Advisory Co=:ittee _
- 1. Input on quality assurance progra= policy
- 2. Input on quality atsurance methods and techniques 3 Quality assurance 2:anagement for GAI/KEI support G
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.F .
Nuclear Q.u;2t1 As'suranca Program 020CI Page 3 of 4 1Rev. _M_ Effective _7/ 7 /
% 1.4 . Management Review and Evaluation
~
l Overall assessment of the scope, implementation and adequacy of the Quality Ass'urance Program shall be made by the QA Advisory Committee. This commit-tee consists of the CEI Nuclear QA Department Manager as chairman with QA management representatives from Kaiser Engineers, Gilbert Associates, an-d other agents, as approved by the chairman. This committee is chartered to perform quarterly reviews of the program and to report the results through the QA Department Manager, to top CEI management through corporate reporting channels. These reviews shall be documented and shall incorporate the Input
. provided by:
.a. The personal assessments of QA agent representatives on the.committei.
- b. Audit trend analysis provided by PQS Quality Administration.
t
- c. Nonconformance trend analysis provided by CQS Quality Engineering.
- d. Corrective Action Request evaluations providsd by PQS and CQS General Supervising Engineers.
- e. Evaluations provided by outside audit groups or QA Task Forces which may be organized by the QA Advisory Committee to provide specialized ,
input. ~,
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- f. Conventional management appraisal and analysis techniques. /
1.5 Resolution of Program Impasses Disputes arising from the interpretation of the Nuclear Quality Assurance Program shall be resolved at the lowest possible level. '
, I
,The hierarchy of each project department provides for squa4 interfaces from
' department specialists through various levels of supervision. This organi-
' zational consistency should provide ample opportunities for problem resolu-tion through simple escalation. /
V Those conflicts which cannot be resolved at lower levels shall be referreck to the NQA Department Manager. The Nuclear QA Department Manager shall attempt to resolve the problem with the Manager of the other concerned ^
department, or, if ::= % escalate to the executive level, using the advice of his QA Advisory Committee as appropriate.
1.6 Indoctrination and Training .
~
,. Procedures shall be established tc assure that personnel performing quality
.. related activities are suitably trained and qualified to perform their' work.
, Each project Department is'. responsible for organizing, implementing, and
, f/ documenting appropriate training measures necessary for their project 7' functions.
/// Procedure $and Records sevrew p abost t ITs aud eh opNw;; eld /MocSSS1-of trainin o.u gw ,
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Corporate Nuclear Qutlity Assur:nca Progrca 0200 Rev. 1 Effective n/JQ88 Page 3 of 4 1.4 Management Review and Evaluation Overall assessment of the scope, implementation and adequacy of the Quality Assurance Program'shall be made by the QA Advisory Committee. This commit-tee consists of the CEI Nuclear QA Department Manager as chairman with QA management representatives from Kaiser Engineers, Gilbert Associates, and other agents, as approved by the chairman. This committee is chartered to perform quarterly reviews of the program and to report the results through the QA Department Manager, to top CEI management through corporate reporting channels. These reviews shall be documented and shall incorporate the input provided by:
- a. The personal assessments of QA agent representatives on the committee.
- b. Audit trend analysis provided by PQS Quality Administration.
- c. Nonconformance trend analysis provided by CQS Quality Engineering,
- d. Corrective Action Request evaluations provided by PQS and CQS General Supervising Engineers.
- p. Evaluations provided by odtside audit groups or QA Task Forces which may be organized by the QA Advisory Committee to provide specialized input.
- f. Conventional management appraisal and analysis techniques. ,
e' l.5 Eesolution of Program Impasses f pisputes arising from the interpretation of the Nuclear Quality Assurance rogram shall be resolved at the lowest possible level.
The hierarchy of each project department provides for. interfaces from department specialists through various levels of supervision. This organi-pational consistency should provide ample opportunities,for problem resolu-pion through simple escalation. -
r Those conflicts which cannot be resolved at lowe'rvlevels shall be referred to the NQA Department Manager. The Nuclear QA Depa tment Manager shall attempt to resolve the problem with the Manager of the other concerned department, or escalate to the executive level, using the advice of his QA Advisory Committee as appropriate.
1.6 Indoctrination and Training
,, Procedures shall be established to assure that personnel performing quality related activities are suitably trained and qualified to perform their work.
Each project Department is responsible for organi' zing, implementing, and i documenting appropriate training measures necessary for their project l functions. Procedures and Records through its review process of training l
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1 Corporata Nuclear Quality I
Assurance Program 0200 Rev. 2 Effective 11/5 7 79 Page 3 of 4 All procedures and instructions shall be approved and established, with training accomplished, prior to the start of the activities being con-trolled. Issuance, distribution, and revisions shall be controlled to
- preclude the use of obsolete documents.
Reference indexes, demonstrating the Quality Assurance program's address i with respect to the guidelines provided by Quality Program Regulatory l j Guides and American National Standards (ANSI) are presented in Appendix I.
1.4 Manaaement Review and Evaluation O'jrall assessment of the scope, implementation and adequacy of the Quality Assurance Program shall be made by the QA Advisory Committee.
This committee consists of the Manager, NQAD, as chairman with QA management representatives from Kaiser Engineers, Gilbert Associates, and other agents, as approved by the chairman. This committee is chartered to perform quarterly reviews of the program and to report the t
' results through the Manager, NQAD, to top CEI management through corpo-rate reporting channels. These reviews shall be documented and shall incorporate the input provided by:
- a. The personal assessments of QA agent representatives on the committee.
- b. Audit trend analysis provided by the Program Quality Section (PQS) Quality Administration.
- c. Nonconformance trend analysis provided by~ the Construction Quality Section (CQS) Quality Engineering.
- d. Corrective Action Request evaluations provided by the General Supervising Engineers, PQS and CQS.
- e. , Evaluations provided by outside audit groups or QA Task Forces which may be organized by the QA Advisory Committee to provi e
$specializedinput. ... ' e
~
f.
. Conventional management appraisal and analysis p tecN,gue((,.'(
1.5 Resolution of Program Impasses
Disputes arising from the interpretation of th uclear Quality Assurance
- Program shall be resolved at the lowest possibl -revel.
The hierarchy of each project department provides for interfaces from 4
department specialists through various levels of supervision. This
. ,. organizational consistency should provide ample opportunities for problem resolution through simple escalation.
i i
Those conflicts which cannot be resolved at lower levels shall be referred to the Manager, NQAD. The Manager, NQAD shall attempt to resolve the problem with the Manager of the other concerned department, or escalate to the executive level, using the advice of the QA Advisory Committee as appropriate.
7 Corporate Nuclear Quality Assurance Program 0200 Rev. 3 Effective 4/ -~~
6 /81 Page 3 of 4 References cre addressed in detail in the eighteen sections which comprise this Manual. The requirements of this program shall be implemented in accor-dance with detailed procedure and instruction manuals.
All procedures and instructions shall be approved and established, with training accomplished, prior to the start of the activities being con-trolled. Issuance, distribution, and revisions shall be controlled to preclude the use of obsolete documents. ,
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$$8h kh.YN$kh5EAE55h5N 1.t.krespectrJewethewgtritleMddW CMdawnMA=ANieusv4M1_?c'%ynagideddydydj.tMJpgram Regulator <
ifaaiMANSIL are pre $e' rite 713Yl%peIt. ,;p 1.4 MANAGEMENT REVIEW AND EVALUATION Overall assessment of the scope, implementation and adequacy of the Quality Assurance Program shall be made by the QA Advisory Committee.
This committee consists of the Manager, NQAD, as chairman, the Managers, Nuclear Engineering and Perry Plant Departments; with QA management representatives from Kaiser Engineers, Gilbert Associates, and other agents, as approved by the chairman. This committee is chartered to perform quarterly reviews of the program and to report the results through the Manager, NQAD, to top CEI c.anagement through corporate
' reporting channels. These reviews shall be documented and shall incorpqrate the input provided by: .K. .
t
- a. The personal assessments of QA agent represen the p [.o e fve. .so committee.
- b. Audit trend analysis provided by the Prog Quality Section (PQS) and Training / Administration Section.
- c. 'lonconformance trend analysis provided by the Construction Quality i
Section (CQS), Training /Adminiatration Section and PrpRram Quality i 9ection-
~
l d. I Corrective Action Request evaluations provided by the General '
kSupervising Engineers, lqS and ] .
- c. Evaluations provided by outside audit groups or QA Task Forces which may be organized by the QA Advisory Committee to provide specialized input.
"f. Conventional management appraisal and analysis techniques.
i 1.5 RESOLUTION OF PROGRAM IMPASSES Disputes arising from the interpretation of the Nuclear Quality Assurance Program shall be resolved at the lowest possible level.
I l
4 Corporate Nuclear Quality AssuranceProgramy00Ef Rev. 4
/_ fective _/_.L Page 3 of 4 References the corresponding safety-related activities are addressed in detail in the eighteen sections which comprise this Manual. The requirements of this program shall be implemented in accordance with detailed procedure and instruction manuals.
All procedures and instructions shall be approved and established, with training accomplished, prior to the start of the activities being con-trolled. Issuance, distribution, and revisions shall be controlled to preclude the use of obsolete documents.
Reference indexes demonstrating the Corporate Nuclear Quality Assurance Progra'm's address with respect to the guidelines provided by Regulatory Guides and American National Standards Institute (ANSI) are presented in Appendix I.
1.4 MANAGEMENT ASSESSMENT Management assessment of program effectiveness shall be through j regular and documented reporting channels on a month by month basis, 1 and through a Quality Assurance Quarterly Evaluation.
t In addition, a Quality Assurance Ar'visory Committee (QAAC) 'has been established as an independent group to conduct regular review and evaltyition of the QA Program for the Perry Nuclear Power Plant (PNPP).
) The committee shall advise the Vice President - System Engineering
) and Ccinstruction on the adequacy of scope, implementation and D effec;iveness of the PNPP QA Program, and on CEI QA policy matters
! as thEy relate to PNPP.
The QAAC shall have an approved charter addressing frequency, membepship, and responsibilities.
1.5 RESOLUTION OF PROGRAM IMPASSES Disputes arising from the interpretation of the Corporate Nuclear Quality Assurance Program shall be resolved at the lowest possible level.
The hierarchy of each project department provides for interfaces from department specialists through various levels of supervision. This organizational consistency should provide' ample opportunities for problem resolution through simple escalation.
<- Those conflicts which cannot be resolved at lower levels shall be referred to the Manager, NQAD. The Manager, NQAD shall attempt tc, resolve the problem with the manager of the other concerned department, or escalate to the executive level, using the advice of the QA Advisory Committee as appropriate.