Similar Documents at Perry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F3901999-10-14014 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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept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 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 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 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 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 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 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 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 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 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 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-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 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 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 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 PY-CEI-NRR-2377, Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 11999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 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 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 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 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 ML20207G3921999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of License DPR-58 & Issuance of Conforming Amend & Opportunity for Hearing Re 990505 Application 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H6511990-11-14014 November 1990 Forwards Maint Team Insp Rept 50-440/90-12 on 900917-21 & 1001-05 & Notice of Violation ML20028H2381990-11-0808 November 1990 Forwards Request for Addl Info to Continue Review of Proposed Rev 2 to Inservice Testing Program ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058D6001990-10-29029 October 1990 Requests Util Provide Ref Matls Listed in Encl 1, Ref Matl Requirements, for Licensing Exams Scheduled for Wk of 910218 ML20058D5141990-10-26026 October 1990 Requests That Util Furnish Items Listed in Encl 1, Ref Matl Requirements, for Requalification Program Evaluation Scheduled for Wk of 910211 ML20058D2081990-10-19019 October 1990 Forwards Safety Insp Rept 50-440/90-18 on 900730-0919 & Notice of Violation ML20062A8631990-10-15015 October 1990 Forwards Safety Insp Rept 50-440/90-19 on 900905-21.No Violations Noted DD-90-06, Forwards Directors Decision DD-90-06 Dtd 900925,for Info1990-09-27027 September 1990 Forwards Directors Decision DD-90-06 Dtd 900925,for Info ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L1571990-09-0707 September 1990 Forwards Exam Rept 50-440/OL-90-02 on 900806.Answer Key & Facility Comment Resolution Also Encl ML20059G8791990-08-29029 August 1990 Requests Final Analysis of Plant Combustible Gas Control Sys Addressing Key Elements Identified in Encl Ser,Section 8.0 Re Mark III Containment Hydrogen Control by 910301 ML20059B4801990-08-22022 August 1990 Forwards Safety Insp Rept 50-440/90-13 on 900625-0802 & Notice of Violation ML20058N4921990-08-0808 August 1990 Forwards Safety Insp Rept 50-440/90-16 on 900709-13.No Violations Identified ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20058M0531990-08-0202 August 1990 Forwards Safety Insp Rept 50-440/90-17 on 900709-13.No Violations Noted.Mobile Lab Located at Site During Insp to Perform Independent Measurements of Radioactivity ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20055G6561990-07-20020 July 1990 Forwards Safety Insp Rept 50-440/90-04 on 900305-0702.No Violations Noted ML20055J1381990-07-20020 July 1990 Recommends That Util Wait Until Generic Effort on NUMARC Proposal Completed Re Emergency Action Level Scheme Before Initiating Changes ML20055G3831990-07-17017 July 1990 Forwards Safety Insp Rept 50-441/90-01 on 900625-28.No Violations Noted ML20055G4061990-07-17017 July 1990 Forwards Safeguards Insp Rept 50-440/90-11 on 900611-19.No Violations Noted ML20055G3141990-07-11011 July 1990 Confirms 900717 Meeting to Discuss Current Plant Monthly Performance Indicators,Offgas Sys Corrective Actions Status,Tech Spec Changes & Refueling Outage 2 Planning ML20055E0291990-06-29029 June 1990 Forwards Safety Insp Rept 50-440/90-08 on 900416-0611.No Notice of Violation Will Be Issued for Violations Noted Because NRC Wants to Encourage & Support Licensee Initiatives for self-identification ML20043H9141990-06-22022 June 1990 Advises That Financial Info for Participants Submitted for 1990 in Satisfies Requirements of 10CFR140.21 That Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Operating Reactor Over 100 Mw(E) ML20043H8881990-06-20020 June 1990 Forwards Notice of Denial of Licensee 880418 Request to Modify Leakage Limits of Tech Spec 3.6.1.2.c for MSIVs from 25 to 100 Std Cubic Ft/H for All Main Lines Through Isolation Valves When Tested at Pa,11.31 Psig ML20043H7281990-06-19019 June 1990 Forwards Exam Rept 50-440/OL-90-01 on 900514-18 ML20043G9661990-06-13013 June 1990 Forwards Request for Addl Info Re Facility First 10-yr Interval Inservice Insp Relief Requests,Per ML20059M8651990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043D5241990-06-0606 June 1990 Provides Comments on 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Recommends Two Stage Approach in Meeting Schedule in Generic Ltr ML20043D5751990-06-0505 June 1990 Advises That Util Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow, Acceptable, Pending Approval of GE Correction Factors for Channel Box Bow ML20043F3671990-06-0404 June 1990 Informs That Util Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Util Reminded to Document & Maintain Evaluation of Actions Re Bulletin for Approx 2 Yrs ML20043E3561990-06-0404 June 1990 Requests Info Re Disposition of Piping Sys,Inc,West Jersey Mfg Co & Chews Landing Metal Manufacturers,Inc Fittings & Flanges,Per NRC Bulletin 88-005 ML20043D9731990-05-31031 May 1990 Advises That 900313 Revised QA Progam Meets Requirements of 10CFR50,App B & Acceptable.Nrc Should Be Notified of Changes to Other Operative QA Commitments Existing in Outside Docketed Correspondence ML20043B6501990-05-25025 May 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $100,000.Escalation of Civil Penalty by 100% Appropriate Since Five Separate NRC Info Notices Issued Re Asco Solenoid Valves ML20043B1281990-05-14014 May 1990 Advises That Info Required by 10CFR50.54(a)(3) Needed for Completion of Review of 900313 QA Program Changes within 30 Days.Update Failed to Include Info Re Reductions in Commitments Concerning Reg Guides ML20043A5831990-05-14014 May 1990 Expresses Appreciation for Invitation to Participate in Semiannual Meetings of Midwest Nuclear Training Assoc. Question Asked During 900427 Meeting Re Part a (Static Simulator) of Written Exam Re Procedures Clarified ML20042G5831990-05-0909 May 1990 Forwards Safety Insp Rept 50-440/90-09 on 900423-26.No Violations Noted ML20042G2141990-05-0707 May 1990 Advises That Util Response to Generic Ltr 89-08, Erosion/ Corrosion Induced Pipe Wall Thinning, Satisfactory.Requests to Be Informed When Implementation of All Actions Re Generic Ltr 89-08 Completed ML20042G1771990-05-0404 May 1990 Forwards Safety Insp Rept 50-440/90-05 on 900228-0416. Violations Noted ML20042F2761990-05-0202 May 1990 Advises of Arrangements Made for Administration of Operator & Senior Operator Licensing Exams During Wk of 900806.All License Applications Should Be Submitted 60 Days Prior to Exam in Order to Review Training & Experience of Applicants ML20034A4271990-04-0606 April 1990 Advises That Re Onsite Scope & Objectives for 1990 Emergency Preparedness Exercise Scheduled for 900620, Acceptable ML20033G7211990-04-0202 April 1990 Forwards Safeguards Insp Rept 50-440/90-07 on 900319-23.No Violations Noted ML20012D9371990-03-20020 March 1990 Forwards Safety Insp Rept 50-440/90-02 on 900103-0228.No Notice of Violation Will Be Issued Since Violation Noted Meet 10CFR2,App C,Section V.G.1 Criteria ML20012B3401990-03-0101 March 1990 Informs That Rev 3 (Temporary Change Notices TCN-5 & TCN-6) to ODCM Acceptable.Review of Util Responses to NRC Questions on Rev 3 Encl ML20033E5201990-02-26026 February 1990 Advises That 891218 Rev Tcn 3 to Emergency Plan Consistent W/Provisions of 10CFR50.54(q) & Acceptable ML20011F5161990-02-23023 February 1990 Advises That 900202 Request for Schedular Extension of Commitments Re Seismic Margin Evaluation for Plant Capability to Withstand Seismic Events Beyond SSE Acceptable ML20006E4711990-02-21021 February 1990 Advises That 900126 Response to Generic Ltr 89-13,re Svc Water Sys Problems,Acceptable.Util Should Document & Retain Appropriate Plant Records to Justify Course of Action Different from That Recommended by Generic Ltr ML20006E9061990-02-16016 February 1990 Advises That Util Confirmed That Neither Subj Valves Nor Valves of Similar Design Using Preloaded Type 410 Stainless Steel Bolt Matl Installed at Facility,Per 900126 Response to NRC Bulletin 89-002.Item Considered Complete for Plant ML20006E7411990-02-13013 February 1990 Discusses Requalification Program Evaluation Scheduled for Wk of 900514,per Telcon Between Me Bielby of NRC & J Mchugh ML20011E7681990-02-12012 February 1990 Advises That Schedule for Submission of Tech Spec Change Request in Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls Acceptable,Based on Review of 881117 Submittal ML20011E6371990-02-0606 February 1990 Forwards Safety Insp Rept 50-440/89-29 on 891227-28 & Notice of Violation 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes 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 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 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 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 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 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 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 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 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 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 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 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 ML20207G3921999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of License DPR-58 & Issuance of Conforming Amend & Opportunity for Hearing Re 990505 Application ML20207B7341999-05-26026 May 1999 Forwards Correction of Typo in TS Table 3.3.6.1-1 for Plant, Unit 1 ML20207B1251999-05-20020 May 1999 Discusses Investigation Rept 3-98-007 on 981210 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20206Q5181999-05-14014 May 1999 Responds to to SL Hiatt Re Fee Exemption Granted to Firstenergy Nuclear Operating Co,Operator of Perry Nuclear Plant.Action Consistent with Longstanding Policy & Practice,As Well as Legal Requirements ML20206Q0171999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20196F8081999-05-12012 May 1999 Partially Deleted Ltr Referring to Investigation Case 3-1998-007 Re Determination Whether Recipient Discriminated Against Radiation Protection Supervisor at Perry for Providing Testimony as Witness in DOL Hearing ML20206S5381999-05-12012 May 1999 Forwards Insp Rept 50-440/99-07 on 990412-16.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Interviews with Personnel & Observation of Activities in Progress ML20196A2961999-05-10010 May 1999 Discusses Investigation Rept 3-98-005 Conducted on 990129 Re Circumstances Surrounding Apparent Falsification of Training Records for Individuals Assigned Positions in Emergency Response Organization & Forwards NOV & Synopsis ML20206Q2111999-05-10010 May 1999 Discusses Investigation Rept 3-98-005,completed on 990129 & Forwards NOV & OI Rept Synopsis.Circumstances Surrounding Apparent Falsification of Training Records for Individuals Assigned Position in Er Organization Were Investigated ML20206N3161999-05-0606 May 1999 Responds to Ltr to NRC on Continued Events Re Transfer of Generation Assets Between Dl & Firstenergy.Info Will Be Considered as NRC Monitor Pending License Transfer Application of Bvps,Units 1 & 2 & PNPP ML20206H3981999-05-0606 May 1999 Forwards Insp Rept 50-440/99-06 on 990303-04 & 0412-16.No Violations Noted.Inservice Insp Activities Effectively Implemented with Several Aspects Demonstrating Good Safety Focus ML20206H6731999-05-0505 May 1999 Confirms Discussion Between Members of NRC & Recipient Re Meeting Scheduled for 990520 in Lisle,Il to Discuss Operational Issues & Related Topics of Interest to Licensed Operators at Nuclear Power Plants Located in Region III ML20206G6901999-05-0303 May 1999 Forwards Insp Rept 50-440/99-02 on 990225-0406.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206G6401999-05-0303 May 1999 Forwards Safety Evaluation Authorizing Relief Requests IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp.Relief Requests IR-36 & IR-41 Withdrawn ML20206D4701999-04-30030 April 1999 Informs That on 990428,FirstEnergy Submitted Post Exam Results of Weld Overlay Repair for Feedwater Nozzle to safe-end Weld at Perry Nuclear Power Plant,Unit 1 (PNPP) ML20206E2111999-04-29029 April 1999 Discusses Alternative Proposed by Licensee on 990325 & 990401 to ASME BPV Code,Section XI Repair Requirements Along with Separate Alternative to Ultrasonic Exam Acceptance Criteria.Forwards SE Approving Proposed Alternatives ML20205P4041999-04-15015 April 1999 Discusses GL 95-07 Issued by NRC on 950817 & Licensee Responses Submitted on 951016,960213 & 960624 for Perry NPP, Unit 1.Forwards Safety Evaluation Concluding That Licensee Adequately Addressed Actions Requested in GL 95-07 ML20205P0281999-04-12012 April 1999 Provides Individual Exam Results for Applicants Who Took Mar 1999 Initial License Exam.Information Considered Proprietary in Accordance with 10CFR2.790.Without Encls ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K5211999-04-0505 April 1999 Forwards Notice of Withdrawal of 970409 LAR on Refueling Interlocks,In Response to Util .Amend Request Will Be Replaced in Future by Similar Request,Based on Approved STS Change Traveler,Number TSTF-225 ML20196K8461999-04-0202 April 1999 Forwards Insp Rept 50-440/99-05 on 990301-05.No Violations Noted.Informs That Licensee Use of 10-Minute Rule & 4-Hour Rule Remains Under NRC Review.Expresses Re Practice Revising Unavailability Criteria on Recurrent Basis ML20205G3891999-03-31031 March 1999 Forwards Safety Evaluation Re Second ten-year Inservice Testing Program Relief Requests.Proposed Alternatives in Relief Requests VR-6,PR-3 & PR-6 May Be Authorized.Relief Request VR-8 Denied ML20205G0441999-03-26026 March 1999 Advises of Planned Insp Effort Resulting from Perry PPR Review,Which Was Completed on 990202.Overall,performance at Perry Was Acceptable ML20205C1611999-03-25025 March 1999 Discusses GL 96-05 Issued on 960918 & Firstenergy 961118, 970317 & 980930 Responses to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Perry Npp.Forwards RAI Re GL 96-05 Program ML20205F0011999-03-25025 March 1999 Responds to Re Safety of Perry Nuclear Power Plant & That Plant Operating with Limited Leaks in Three Fuel Rods for Several Months.Informal Public Hearing Re Leaks at Perry Facility Held in Rockville,Md on 990222 ML20204D8891999-03-17017 March 1999 Forwards Insp Rept 50-440/99-04 on 990222-26.No Violations Noted.Insp Focused on Radiological Planning for Spring 1999 Refueling Outage,On Assessments of Radiation Protection Program & on Radiological Training for General Employees ML20204E7791999-03-17017 March 1999 Forwards Insp Rept 50-440/99-01 on 990113-0224.Non-cited Violation Was Identified ML20207H9921999-03-11011 March 1999 Informs That Requirements to Pay Fee Under 10CFR170 for Review of Pilot Plant Application for Use of Revised Accident Source Term Methodology for Perry Nuclear Power Plant Unit 1,waived for Reasons Stated ML20207K1991999-03-0404 March 1999 Forwards List of Names of Those Individuals & Their Organizational Affiliation as Appropriate,Who Spoke at Informal Public Hearing Re Petitions Filed Pursuant to 10CFR2.206 for River Bend & Perry Plants on 990222 ML20203F8501999-02-11011 February 1999 Forwards Fr Notice to Be Published on 990219 Re Informal 10CFR2.206 Public Hearing Including Video Teleconferencing ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203A5131999-01-27027 January 1999 Forwards SE Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps 1999-09-09
[Table view] |
Inspection Report - Perry - 1978013 |
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W UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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M f 799 RooSEVEi ' Ro AD q' 4 o LE N E LLYN, ILLif.ols 60137
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OCT 2 6.378 50-440()
Docket No.
50-441 Docket No.
The Cleveland Electric Illuminating Company ATTN:
Mr. D. R. Davidson Vice President - Engineering Post Office Box 5000 Cleveland, OH 44101 Gentlemen:
This refers to the inspection conducted by Messrs. J. E. Konklin, E. W. K. Lee, G. F. Maxwell and J. Hughes of this of fice on September 20-22, 1978, of activities at the Perry Nuclear Plant Project, Units 1 and 2, authorized by NRC Construction Permits No. CPPR-148 and No. CPPR-149 and to the discussion of our findings with Mr. M. R. Edelman, Mr. G. W. Groscup and others of your staff at the conclusion of the inspection.
The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas, the inspection consisted of a selective examination of procedures and representative records, observations, and interviews with personnel.
No items of noncompliance with NRC requirements were identified during the course of this inspection.
In accordance with Section 2.790 of the NRC's " Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room, except as follows.
If this report contains information that you or your contractors believe to be proprietary, you must apply in writing to this of fice, within twenty days of your receipt of this letter, to withhold such information from public disclosure.
The application must include a full statement of the reasons for which the information is con-
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sidered proprietary, and should be prepared so that proprietary information identified in the application is contained in an enclosure to the application.
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The Cleveland Electric-2-OCT 2 6.378 Illuminating Company We vill gladly discuss any questions you have concerning this i
inspection.
Sincerely, o
R. F. Heishman, Chief Reactor Construction and Engineering Support Branch
Enclosure:
IE Inspection Reports No. 50-440/78-13 and No. 50-441/78-12
REGION III==
Report No. 50-440/78-13; 50-441/78-12 Docket No. 50-440; 50-441 License No. CPPR-148; CPPR-149 Licensee:
The Cleveland Electric illuminating Company Post Office Box 5000 Cleveland, OH 44101 Facility Name:
Perry Nuclear Power Plant, Units 1 and 2 Inspection At: Perry Site, Perry, OH Inspection Conducted:
September 20-22, 1978
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Inspectors:
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E. W. K. Lee
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Approved By:
D W. Hayes, f
/0 2 f[,9 Proj ects Section Inspection Summary Inspection on September 20-22, 1978 (Report No. 50-440/78-13; 50-441/78-12)
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Areas Inspected: Licensee action relative to previous items of noncom-pliance and unresolved items (Units 1 and 2); licensee action relative to RIII Immediate Action Letter of February 8, 1978 (Units 1 and 2);
ongoing construction activities (Units 1 and 2); concrete embedment
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inspection activity (Units 1 and 2); QA implementing procedures relative to electrical components and systems (Units 1 and 2); QA implementing procedures relative to electrical cables and termination (Units 1 and 2);
l work activities and quality records relative to electrical cables and
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terminations (Unit 1); QA implementing procedures relative to safety-related piping (Units 1 and 2); QA implementing procedures and work activities relative to safety-related piping welding (Units 1 and 2).
The inspection involved a total of 88 onsite inspector-hourc
.y four NRC inspectors.
Results:
No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted
Principal Licensee Employees J
- M. R. Edelman, Manager, Nuclear QA Department
- G. W. Groscup, Manager, Nuclear Engineering Department
- R. E. Boals, General Supervisor, Construction
A. Fitzpatrick, Site Construction Manager
- J. M. Lastovka, CQS General Supervising Engineer
- P. P. Narducci, CQS Quality Engineering Supervisor
- E. Riley, Manager, Contracts Administration Other Personnel
- W. J. Kacer, CQS Quality Control Supervisor (KEI)
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- P. L. Gibson, CQS Quality Administration Supervisor (KEI)
- T. L. Arney, CQS Lead Quality Engineer (GAI)
- G. J. Gibson, CQS Lead Electrical Quality Engineer (GAI)
- J. J. Connelly, QCS Lead Civil Quality Engineer (GAI)
- J. W. Mehaf f ey, CQS Lead Mechanical Quality Engineer (GAI)
- R. E. Crofton, CQS Lead Piping Quality Engineer (GAI)
- E. M. Wilcox, Senior QA Specialist (TECo)
- J. M. Pepp, Construction Quality Section (KEI)
The inspectors also contacted other licensee and contractor employees, including members of the quality, technical and engineering staffs.
- Denotes those who attended the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (440/77-02; 441/77-02) - Effects of CEI reorgan-ization.
The previous RIII Report noted that the effects of the CEI QA/QC reorganization at that time had not been addressed in the applicable QA documents.
Since the CEI QA Program and QA/QC organization have recently been restructured as a result of the RIII Immediste Action Letter of February 8, 1978, and since the restructured program and organization are under review by RIII with regard to the resolution of Item 8 of the Immediate Action Letter, this previous unresolved item from 1977 is no longer pertinent, and is hereby closed.
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(Closed) Unresolved Item (440/77-07-6; 441/77-07-6) - Temperature control in containments.
The previous RIII Report raised a question concerning provisions for temperature control in the containments during liquid pene-trant testing. During this inspection, the inspector reviewed NNIC Instruction 465-NC-N003, Revision C, dated August 15, 1977, titled " Liquid Penetrant Inspection." Section 7.2 of Instruction 465-NC-N003 requires that liquid penetrant examination be done within a range of 40 F to 125 F, and discusses the use of local heating or cooling as required to maintain the temperature within the specified range.
This item is considered to be resolved.
I (Closed) Noncompliance (440/78-02-02; 441/78-01-02) - Lack of Great Lakes indoctrination and training procedures.
The previous RIII Report noted that no indoctrination and training procedures had been established by Great Lakes Construction Company.
During this inspection, the inspector reviewed Great Lakes Procedure No. AQCP-16, Revision 1, dated April 6.
1978, titled " Indoctrination and Training of Personnel," which delineates the required training for specific levels of personnel capability.
This item is considered to be resolved.
(Closed) Noncompliance (440/78-02-21; 441/78-01-21) - Calibration require-ments for U.S. Testing weight scales. The previous RIII Report noted that U.S. Testing (UST) did not have procedural requirements regarding cali-bration of precision weight scales.
During this inspection, the inspector reviewed UST Calibration Instruction Nc. CI-16, Revision 0, dated February 13, 1978 and accepted by CEI QA on August 10, 1978, titled
" Laboratory Scales and Balances (Mechanical)." Instruction CI-16 contains requirements for calibration of weight scales, including frequency of calibration and traceability of reference standard weights to standards maintained by the National Bureau of Standards. This item is considered to be resolved.
(Closed) Noncompliance (440/78-04-02; 441/78-03-03) - Inadequate Dick Corporation procedures.
The previous RIII Report noted that there were inadequate Dick Corporation procedural provisions for review of QC inspection plans to ensure that required drawings and specifications are listed.
During this inspection, the inspector reviewed Dick Corporation l
Quality Control Procedure FQC-14.1, Revision 3, dated August 28, 1978, titled "FQC Inspection Report," and CEI letter to Dick Corporation, dated September 20, 1978, which accepts Revision 3 of FQC-14.1 with minor comments.
Revision 3 of FQC-14.1 now contains requirements to ensure that all required drawings, specifications, FVA's, ECN's and NR's are listed on the inspection report (plan).
This item is considered to be resolved.
It should be noted that the above discussion refers to Part b
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of the noncompliance.
Part a, which involved cold-forming of rebar with-an approved procedure, was previously resolved by RIII Report out (440/78-05; 441/78-04).
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Section I
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Prepared by J. E. Konklin Reviewed by D. W. Hayes, Chief Projects Section 1.
Review of Licensee Action on Previous Inspection Findings The Region III inspector reviewed the licensee actions relative to the resolution of specific noncompliances and unresolved items which had been identified in previous RIII inspection reports, and which were still in an open status prior to this inspection.
The items reviewed, and the licensee actions relative to the resolution of each item, are discussed in the foregoing section of this report.
2.
Review of Embedment Inspection Program Previous RIII Reports (78-11; 78-10) and (78-12; 78-11) discussed the embedment inspection program being conducted by CEI, and designated an Unresolved Item (440/78-11-01; 441/78-10-01), 52 and pending resolution of the findings of CQA Audit Report No.
completion of the evaluation of the adequacy of in-place embed-ments. During this inspection, the inspector reviewed, with the CQE and CQC Managers, the licensee actions to date relative to resolution of the findings of Audit Report No. 52.
At the con-
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clusion of the review, the licensee stated that all of the. Audit Report findings will be resolved and corrective actions implemented by October 15, 1978.
With regard to the evaluation of the adequacy of in-place embedments, the previously committed date of December 1, 1978 for completion of the analysis is still considered by the licensee to be attainable.
GAI has been requested by CEI to perform the evaluation.
On September 6, 1978 CEI provided to GAI, for use in the evaluation, J
a data package which includes inspection results of equipment foundation embed frames, survey results on fillet-welded studs, a summary of embed inspection reports, information regarding studs broken during bending, and studies of nonconformance reports issued on embedments.
To obtain additional technical data for use in the evaluation, CEI is planning to contract with Nelson Division of TRW for a stud tensile testing program, which will include pull tests on 60 to 70-5-
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I samples from embedments presently on-site, with all of the types of significant def ects which have been identified during the embedment
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inspection program.
This unresolved item regarding the embedment inspection program will i
remain open under the previous designation, noted above, pending further review during future inspections.
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3.
CEI Quality Control and Quality Engineering Surveillance of Concrete Contractors As a result of the RIII Immediate Action Letter of February 8,1978, I
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the licensee initiated 100% quality control (CQC) inspection of j
I contractor activities relative to safety-related concrete place-ments, and quality assurance (CQA, now CQE) audits were instituted on 100% of the contractors' and CQC's inspection activities with regard to these placements.
During an RIII inspection on April 13 and 14, 1978, as documented in Report (440/78-05; 441/78-04), it was agreed that the 100% CQC involvement would be maintained on the activities of all four con-crete placement centractors until a greater confidence level was achieved by the licensee with regard to each contractor.
In addition, it was agreed during that inspection that the 100% CQA (now CQE) involvement would be maintained for S&MC and Dick Corporation, and that the CQA audit schedule would be reduced to a normal level for the other two concrete placement contractors, Great Lakes Construction and National Engineering.
l During this inspection, the CQC..anager and the Lead Quality Enginecr discussed with the RIII inspector a planned reduction of CQC surveil-lance on the four concrete contractors to a normal level.
A total of 297 inspections and 63 audits were performed by CQE/CQC i
on the four safety-related concrete contractors during the period March 1, 1978 to September 20, 1978. The RIII inspector selected on a random basis, and reviewed, 50 of the inspection reports and 25 of the audit reports, and noted that the performance of the four contractors improved significantly during the six month period i
under review.
Based on this review, and on the discussions noted above, the inspector agreed with the planned return to normal inspection and audit levels by CQC and CQE.
4.
Status of Plant Construction Activities The inspector observed on-going work activities and equipment status in the Unit 1 and 2 containment buildings and auxiliary buildings,
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J the intermediate building, the control complex, the fuel handling building, and the rebar storage yards.
The safety-related structural concrete work is approximate 19 50%
complete for Containment No. 1, 45% complete for Containment No. 2.
55% complete for the Control Complex building, 62% complete for Auxiliary Building No. 1, 42% complete for Auxiliary Building No. 2, and 44% complete for the tunnel work by S6MC.
Safety-related structural steel fabrication work is approximately 45% complete for Containment No. 1, 30% complete for Containment No. 2, 63%
complete for the Control Complex, 8% complete for Auxiliary Building No. 1, and just recently underway for Auxiliary Building No. 2.
Safety-related piping fabrication and installation activities by Pullman are still at a low level, and the safety-related electrical work by Comstock is just beginning.
No items of noncompliance or deviations were identified.
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Section II l
Prepared by E. W. K. Lee Reviewed by D. H. Danielsen, Chief Engineering Support Section 2 1.
Saf ety Related Piping - Review of QA Procedures (Units 1 and 2)
j The inspector reviewed Pullman Power Products (PPP) Nuclear Quality Assurance Program tbnual dated May 16, 1978, included Supplements j
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dated August 23, 1978, (this manual was revised recently and has not been approved by the licensee or the Authorized Inspector), two
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Gilbert Associates Incorporated specifications and 15 PPP procedures re3ative to safety related piping work activities.
The procedures l
reviewed included document control; receiving inspection; identifi-cation; handling; storage; shipping and preservation; cleanliness control; erection and installation; hydrostatic testing; generation
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and record keeping.
The inspector determined that the QA Program
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Manual and the procedures meet the PSAR commitments, 10 CFR 50, Appendix B and the applicable code requirements.
It was further determined that the procedures meet the QA Program Manual and the l
specification requirements.
No items of noncompliance or deviations were identified.
2.
Saf ety Related Piping (Welding) - Review of QA Procedures (Units __1 and 2)
The inspector reviewed 19 Pullman Power Products (PPP) procedures related to welding of safety related piping. The procedures reviewed included control of weld data sheets including hold points;
qualification of welding procedures, welders, NDE and inspection personnel; calibration of equipment; control of preheat and interpass temperatures, post weld heat treating; repair of defects and control of welding materials. The inspector detennined that the procedures meet PSAR commitments, QA manual, 10 CFR 50, Appendix B, and the
applicable code requireeents, except that handling of returned welding materials needs to be clarified in either Procedure No.
VI-5 or No. VIII-3.
The inspector stated that the matter of handling of returned welding materials is considered unresolved pending a review of the revised procedure.
(50-440/78-13-01;
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441/78-12-01)
No items of noncompliance or deviations were identified.
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Safety Related Piping (Welding) - Observation of Work Activities (Unit 1 and Common to Units 1 and 2)
The inspector observed welding of the root pass of Unit 1 Essential Service Water System Weld No. 17 on Isometric No. 1-P45-19 and Common to Units 1 and 2 Essential Service Water Weld No. 11 on Isometric No. 0-P45-38.
It was determined that:
(1) proper welding procedures were used, (2) walders were currently qualified and (3) physical appearances were acceptable.
No items of noncompliance or deviations were identified.
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Section III Prepared by G. F. Maxwell
Reviewed by R. L. Spessard, Chief
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Engineering Support Section 1
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_CEI Action Taken Relative to RIII Immediate Action Letter of February 8, 1978 - Units 1 and 2 a.
Relative to Item 8 of the RIII Immediate Action Letter of February 8, 1978:
(1)
The inspector reviewed the CEI Corporate Quality Assurance Manual, which was submitted to RIII on August 8, 1978.
(a) The details of the manual were discussed with the CEI' Quality Assurance Manager who informed the inspector that CEI plans to make certain revisions to Sections 0100, 0200, 0900 and 1000 of the manual.
(b)
The inspector compared the contents of the tbnual (Policy statement, Sections 0100 through 1800 and Appendix I, II and III) with the requirements of
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10 CFR 50, Appendix B and ANSI N45.2-1971.
(c) The inspector noted that CEI has committed (through Appendix I of the CEI Corporate Quality Assurance Ibnual) to comply with Regulatory Guides 1.28, 1.37, 1.38, 1.54, 1.58, 1.64 and 1.74.
The inspector observed that the Project Administrative Procedures (PAPS), through which the commitments to Regulatory Guides 1.30, 1.39, 1.88, 1.94, 1.116 and 1.123 are made, have not yet been fully develpped.
It should be noted that the degree to which CEI has committed to comply with the above listed Regulatory Guides is delineated in the applicable PAP noted in Appendix I of the CEI Corporate Quality Assurance Program.
In general, the Regulatory Guides / Standards which CEI has imposed on their contractors will be and/or have been listed in the applicable contract specifications.
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(2) The inspector informed the licensee that Item 8 of the RIII Immediate Action Letter of February 8,1978 (the only item of the letter remaining open) will remain open pending receipt and satisfactory review of the approved PAPS 1001, 1002, 1301, 0202, 0901, 1003, 0301, 0201, 1701, 1004, 1005, 0401 and the revised Sections 0100, 0200, 0900 and 1000 of the CEI Corporate Quality Assurance Manual.
No items of noncompliance were identified.
Quality Assurance Program Review - Electrical - Units 1 and 2 2.
The inspector reviewed selective sections of the ERNST-COMSTOCK a.
QA/QC Manual.
ERNST-COMSTOCK (E-C) is an electrical contractor with installation / inspection responsibilities for Class 1E l
electrical equipment at the Perry Nuclear Plant.
Those sections l
which were selected and reviewed are as follows:
(1) Organization Structure and QA Personnel (reviewed E-C procedures 4.1.4 dated June 27, 1978, 4.1.2 dated June 1, 1978 and 3.2.1 dated June 1, 1978).
(2) Procurement Document Control (reviewed E-C procedures i
4.4.1 dated February 2, 1978, 4.11.1 dated August 1, 1978 and 4. 6.1 dated March 6,197 3).
(3) Work and Quality Inspection Procedures (reviewed E-C procedures 3.1.1 dated June 1, 1978 and 3.1.3 dated March 28, 1977).
(4) Material Control (reviewed E-C procedures 4.10.1 dated April 27, 1978, 4.10.2 dated June 1, 1978 and 4.11.1 dated August 1, 1978).
(5) Document Control (reviewed E-C procedures 3.1.1 dated i
June 1, 1978, 3.1.3 dated Fbrch 28, 1978, 4.2.1 dated June 1, 1978 and 4.2.2 dated June 1, 1978).
(6)
Special Processes (reviewed E-C procedures 4.7.0 dated April 27,1978 and QA 1.0.1, paragraph 4.7).
(7)
Test Control (reviewed E-C procedure QA 1.0.1, paragraph
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4.8).
(8) Control of Measuring and Test Equipment (reviewed E-C procedure 4.9.1 dated June 1, 1978).
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(9) Quality Records (reviewed E-C procedures 4.10.1 dated
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April 27, 1978, 4.13.1 dated June 1, 1978 and QA 1.0.1, paragraph 4.13).
(10) Corrective Action (reviewed E-C procedure 4.11.1 dated August 1, 1978 and CQAP 5.1C dated February 2, 1978.
The procedure addresses the processing / control of hardware nonconformances which require corrective action).
(11) Audits (reviewed E-C procedure 4.14.1 dated June 1,1978).
The inspector compared the above procedures with the Quality b.
Assurance requirements which are specified in the CEI/E-C contract specification, SP-709-4549-00 dated August 12, 1974; 10 CFR 50, Appendix B and ANSI N45.2-1972.
(1) The inspector had concurns about the procurement require-ments imposed on subcontractors, as prescribed in Comstock's procedure E-C 4.4.1, dated February 2, 1978.
Further review indicated that CEI Quality Assurance personnel had previously identified the same concerns in PNPP Audit Report No. 126 (dated August 4, 1978)
AR-001, AR-002 and AR-003.
At this time, the inspector has no further questions about this matter.
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(2) The inspector also had concerns about Ernst-Comstock's procedures for corrective action.
The inspector was informed, by CEI Quality Assurance personnel, that E-C has been instructed to revise the applicable procedures to assure that the requirements of SP-709-4549-00, paragraph 1:06.15.2 have been clearly addressed for both hardware and software conditions which are adverse to quality.
At this time, the inspector has no further questions about this matter.
The inspector was informed by the licensee that E-C will not c.
be responsible for the testing of Class 1E electrical equip-Rather, CEI will establish a test group that will be ment.
responsible for the testing of Class lE equipment.
No items of noncompliance were identified.
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Section IV Prepared by J. Hughes Reviewed by R. L. Spessard, Chief Engineering Support Section 1 1.
Independent Inspection A meeting was held by RIII inspectors with approximately 30 Quality Assurance / Control and Engineering personnel involved with instal-lation of Class lE electrical and instrumentation components at the Perry Plant. The personnel included were employed by Cleveland Electric Illuminating Company, Kaiser Engineering, Inc., Johnson Controls and Ernst-Comstock Company.
The purpose of the meeting was to discuss past electrical and instrumentation problems identi-fled by IE inspectors at other construction sites and to place into perspective the key role which QC inspectors and installers must play.
Through these discussions both public and plant safety may be enhan:ed and undue licensing delays may be avoided in the future.
The agenda included:
A brief description of the NRC's electrical and instrumentation a.
inspectors responsibilities to both the public and licensee; b.
A discussion of specific electrical and instrumentation problems previously identified by RIII inspectors at other construction sites.
A handout was provided; A discussion of generic quality program deficiencies, such as c.
records and documentation, audits, nonconformance reports, and training; and d.
A discussion on the importance of verifying the validity of supplier certificates, as delineated in Section 10.2 of ANSI N43.2.13.
2.
Review of Electrical Quality Assurance Implementing Procedures
_ Raceway Supports)
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Ernst-Comstock Electrical Contractors (E-C) is responsible a.
for the installation of Class 1E electrical components and equipment.
b.
The RIII inspector reviewed the following implementing pro-cedures:
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I (1) Control of Special Process, Section 4.7.0;
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l (2) Welding Procedure and Welder Qualifications for Struc-tural Attachments, Section 4.7.1;
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(3)
Storage, Issue, and Control of Welding ?bterials, Section 4.7.6; (4T Test and Inspection P.rocedure Magnetic Particle Exami-nation, Section 4.7.8'; and I
(5) Hanger Fabrication and Installation, Section 4.3.11.
No items of noncompliance were identified.
l 3.
Electrical (Raceway Supports) - Observation of Work Activities The RIII inspector made a tour of Ernst-Comstock (E-C) laydown a.
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areas. The inspector observed the following:
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(1) The material used for raceway supports (hangers), and conduit was protected from adverse environment and physical damage.
(2) Material identification and control of issue from storage.
(3) Nonconforming materials were identified by hold tags and segregated in a hold area.
b.
The RIII inspector observed the fabrication of seismic Class 1E raceway supports (hangers).
The observation included:
(1)
Fit-up of material; (2) Welding; (3) Magnetic Particle Examination test of the finished welds; and (4) Verification that the detail drawings in use were current revisions.
I The RIII inspector observed the installation of raceway c.
supports (hangers) located at the lower level of the Control Couplex Building.
The observation included:
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(1) Correct location by layout drawings; (2) Welding of the gussets to the building structural steel; (3) Welding of supports (hangers) to the gussets; (4) Magnetic particle Examination test of finished welds; (5) Weld rod control and. issue to the craft personnel; and (6) Verification that the installation drawings were current revisions.
No items of noncompliance were identified.
4.
Electrical (Raceway Supports) - Quality Records The RIII inspector reviewed QC records pertaining to fabri-a.
cation and installation of raceway supports (hangers).
(1) Welder's qualification tests are in accordance with E-C procedure, Section 4.7.1 and AWS D1.1-75.
(2) Weld rod is being issued and stored in accordance with E-C procedure Section 4.7.6.
(a) The inspector reviewed weld rod issue cards, for heat numbers, lot numbers and amount issued and re tu rned.
(b)
E-C QC is maintaining a log for the weld rod storage oven; the inspector verified that the temperature is being maintained at 250 1 25 F.
Rod type and heat and lot numbers are marked on the oven.
(c) The RIII inspector verified that the magnetic par-ticle equipment (MT-024) had a current calibration sticker, b.
The RIII inspector reviewed the qualification and training records for two Ernst-Comstock (E-C) Non-Destructive Exami-nation personnel.
The records shot; the personnel are qualified in accordance with E-C procedure, Section 4.1.5.
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The RIII inspector reviewed records pertaining to the fabri-c.
cation of raceway supports (hangers). These included:
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(1)
Cable tray support drawings 55-213-111, sheet No. T8,
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revision A; SS-213-lli, sheet No. T56, revision A; and SS-213-121, sheet No. T64, revision.
The drawings have the QC inspector's initial, welder's ID, fitup, visual and magnetic particle test results.
(2) Magnetic particle examination report was found to be in accordance with E-C procedure, Section 4.7.8; the accep-tance criteria is AWS D1.1-75.
The report identifies equipment, calibratio'n data, type of powder and test results.
No items of noncompliance were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or deviations.
An unresolved item disclosed during the inspec-tion is discussed in Section li, paragraph 2.
Exit Interview The inspectors met with site staff representatives (denoted under Persons Contacted) at the conclusion of the inspection on September 22, 1978.
The inspectors summarized the purpose and findings of the inspection.
The licensee acknowledged the findings reported herein.
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