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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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-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-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-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-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-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 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 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 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 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 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-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-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-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-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 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 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 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-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) 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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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P O BOX 5000 - CLE% ELAND, OHIO 44101 - TELEPHONE (2161622 9600 ILLUutNAf tNG DLDG - SS PUBLIC SQUARE Serung Ttv Best local:on n the Nttoon MURMY R. EDRMAN VICE PatstotNT teUCLE A4 March 11, 1986 PY-CEI/NRR-0442 L l Mr. Harold R. Denton, Director Office of Nuclear Re.1ctor Regulation U. S. Nuclear Pegulatory Commission Washington, D. C. 20555 Perry Nuc1 car Power Plant Docket Nos. 50-$ A0; 50-441 Seismic Event Evaluation Report Supplemental Information
Dear Mr. Denton:
This transmittal provides additional information for your staff regarding seismic capability evaluations as noted in Attchment B to our letter PY-CEI/NRR-0440 L, dated March 3, 1986. In that letter we committed to providing by March 10, 1986 a list of equipment, schedule, and criteria for further seismic evalu-ations to assess the plant's capability to accommodate low en-orgy, high frequency, short duration earthquakes.
Attachment A lists and describes the criteria used for our se-lection of equipment which reflects comments made by your staff. This criteria results in a comprehensive seismic evalu-ation of many types of components.
Attachment D provides the resultant list of equipmert for fur-ther evaluation. This list contains both nuclear steam supply system (NSSS) components and balance of plant (BOP) components in various locations and reflects both qualification methods of testing and analysis. Evaluation of these items is already in progress as noted in the last column, anel we will complete our study with a final report by June 1, 1906.
S bco
^h0323Nc?298Q
Mr. Harold R. Denton March 11, 1986 Page Two Should you have k additional questions, please feel free to call..
Verytrulyy,ouys,
/Me % .
Murray . Edelman Vice President Nuclear Group MRE L Attachments cca Jay Silberg, Esquire John Stefano (2)
J. Grobe
ATTACllMENT A 4
PY-CEI/NRR-04 42 L I
EQUIPMENT SELECTION CRITERIA i
j ACTIVE SAFETY CLASS EQUIPMENT REQUIRED FOR SAFE SHUTDOWN.
EQUIPMENT LIST COMPILED BY LANRENCE LIVERMORE
- NATIONAL LABORATORY, WITH FREQUENCIES HIGHER THAN
- 14 Hz AND HCLPF VALUES LESS THAN 0.5g.
1 l SUPPLIED BY MULTIPLE VENDORS.
ACTIVE COMPONENTS QUALIFIED BY ANALYSES.
VALVES & MOTOR OPERATORS SUPPPORTED BY PIPING j SYSTEMS.
ELECTRICAL SWITCHGEAR & INSTRUMENT RACKS.
1 VERTICAL PUMPS.
. BATTERIES & BATTERY RACKS.
i CRITERIA RESULT IN MORE COMPREHENSIVE SAMPLES i
OF EQUIPMENT. ,
! APPROXIMATELY 75% OF SELECTED EQUIPMENT TYPES j HAVE ALREADY BEEN EVALUATED WITH AMPLE QUALIFICATION MARGINS.
BALANCE TO BE COMPLETED BEFORE JUNE 1986.
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ATTACIIMENT B f PY-CEI/NkR-0442 L Pag 21 I :
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i EQUIPMENT SELECTE D FOR EVALUATION FROM PFRDY U t ute F At tipLif t1T Af1 At ffit" AT1 Atf I tTT f
EQUlFMENT NAME MPL # SYSTEM LOCATION QUALIFIED SPEC. TYPE VENDORS EVALUATEG l two xreen wash vert Pwnp GP49ennn % s isnergerwy Seewge water 15W Pumphouse 586* Analyzed SP 501 Medt Gould no (Sw Vert Pwnp 1745C0001A.S Esnergerwy 5ervue water E5W Pumphouse 546* Andysed 5A501 Muh. Could No l
(5W Vert rusnp IP45C0002 Emergerwy 5erwwe water 85W Purnphouse 586* Anatyred 57-50s Meot Gould ,ho t%w Locat ControI Panee OH51P0077A.s tenergerwy servue water ESW Pumphouse 586* Analysed SP-95 Medt inwereu Seanard ,No SLC Tsansfer Pwnp & Motor OC41CD002A.B Standby Laquid Control Intermediate Bksg 62r Analyzed 5A506 Medt W; GE-Motor !ho 4H4 Water Leg Purnp & Motor 1112COOO3 men.dwas Heat memo.at Awa.hary 814g. 574* Analyzed 5A506 Medt ayeon Jadion Pusnp. imo ,
I GE4fotor t
LPC5 water Les Pwnp & Motor iE21CD002 Lous Pressure Core Sprmy Avaakary sksg 574* Analysed SP 506 M* st ' Pwne tengham-w.ilannette; 8no
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Motor-5.ementAn.s e water teg Pwn, a uotor it22Cn003 eogh Presue Co,e Sprer Av har,sids 574* Anasyned SP Sc6 Medt Pwno- s.ngha+wutamette; ;no
)
Motor-5.emen>AA84 GOCwater Leg Ptsmp & Motor 8151C203 neactor Core isolat.on a =% sids 574" Andymed SP 506 MedL Pwnp- B.ngham w.aaamette; .mo Cocieng Motor-5.emenerAnd l
Dieses Gen aksg 627
' 5A507 Muh. Gould-Pump pao 7 vee os Transfer Pump a45CD001 A.S.C Onenes Gert fuse Ont Anha:J Fwes Os Transfer sadup Pump Analysed SA507 Matt Goutdfump ho
) ia45CD002A.S.C Dieses Gen f ves Che Diesse Gen 8149 62 7 Ms.or Suppty Panee IM5150004 Come w- Gas Control ControlSadg 627 Test SP-628 Mah Westnghouse he po.er % ppeyPanes iustsc002 Combuia.ede cas Contras Controlsadg 627 Test SP428 MedL West.nghouse No l
! C G rurg.ng Comprenor a sustC000tAs Comanat.ede Gas Contros Conta.nment 664- Test 5P432 Medt Compressor Turbonet.u; 'No uotor Motor-Aekante i Cm w.ter Pa.mp . Moor 0,oC0=is..C Cor.t.o. Com,.e. C, Corg,o. .k,g 57.- w e. 5,*4 - w inger nd. to j wate, uotor-west.nghouse j 1
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Page 2 EQUIPMENT SELECTED fOR EVALUATION FROM pr onv (r (uir r na tioLarMT ni tal tricattnM I KT MPL # SYSTEM LOCATION QUALIFIED SPEC. TYPE VENDORS EVALUATED l EQUIPMENT NAME Oosed Cochng Pump & Motor iP4200001A.s Emergency Oosed Control ends. 574' Anaaymed SP-644 Mech. Pump ingersont-mand; .No Cochng Motor-westenghouse Air Darnper & Pneumatec OM25F0010A.8 Control Am.HVAC Cor. trol Eidg 679* Test SP449 HVAC Damper-Papco; iNo Actuator-ControiMatacs Actuator Convol Am.HVAC Control 81dg 679' Test 5P-049 HVAC Damper-Papco; lNo Air Damper APneumatec OM2510020A.8 Attuator-Controlmata(s A<tuator MCC.5wgr. & HVAC Control Bldg 479' Test SP-049 HVAC Papco & Powers peg Co. No OM23f0040A.S
Actuator Sattery Am. Enhaust Control Badg. 679' Test SP 049 HVAC Papco & Powers Reg. Co ,No Aer Damper & Pneumatsc OM24f 0011 A.8 Actuator Battery Am. Eshaust Control 8149. 679" Test SP449 HVAC Pmo S Powers Reg Co. iNo Air Damper & Pneumatic Chi 2470065A.B Actuator HVAC 5ystems ControlBidg 679* Test $P-049 HVAC Robert irsay Co !No Safety Related ConuoI Panel 0H51P0152 HVAC 5ystems Control 8tdg 679' Test $P 049 HVAC Robert issay Co iko Safety Related Conuc8 Panel 0H51 Pol 53 HVAC 5ystems Control Bidg 679' Test 5P-049 HVAC Robert irsay Co. [No Sarety Related Conuci Panet OH53P0164 Annulus tahaust Gas FuelHdig sadg 620' Test SP-091 HVAC Seson gNo Differentiai Pressure Sutch IM15N0061 A.8 Treatment HVAC 5ystems f uel Hdig Bldg. 707' Test $P491 HVAC Papco/tTT General Controlt .No Damper / Actuator /5upports IMI5f 0070A.S D esel Gen. 6a6' Tes: SP-09 8 HVAC Papco/ITT General Controis No Darnper/ Actuator / supports IM4370040A s HVAC 5ystems tmerg. Oosed Cool.ng Control Bldg. 574' Test SP-524 HVAC Controimatics/ .No 10* Sutterfly Valve @'ator OP42703 SA.s.C IIM Valve Controi Contsof Bidg 574' Test SP 64] HVAC Carrier Corp jNo
- cter Ch.llers OH51PC114 Control CPntled Water Controltidg 574' Test SP 64) HVAC Carner Corp lNo l W:ter Chillers CH51P0319 Control Outsed Water Controlasog 574* Test SP-643 HVAC Carr.er Corp. !No Water Chelters OH51P0320 Control Chiesed water
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EQUIPMENT 5ELECTE D FOR EVALUATION FROM l PFDDY TF eHff f amil:PfutFMT Af l at if tf ATt AM I t<T I
SYSTEM LOCATION QUALIFifD SPEC. TYPE VENDORS EVALUATED EQUIPMENT NAME MPL s MCC.5wgr. & HVAC Control tidg. 675' Test SP445 HVAC Fa& Westinghouse, *No Supply Aar Fa. & Motor 0M23C000l A.B Motor-Reliante Electrk 0M23C0002A,8 MCC,5=gt. 4 HVAC Controlslog 679' Test SP445 HVAC Far>Westanghouse; lNo Return Air Fan & Motor Motor-Reliance Electnc Control 8149. 587' Test & Anal. SP446 HVAC Far+ Carrier; lNo Air Hdig. Units Faru & Motors 0M2840001A,8 Emerg Cosed Cochng Motors-Rehance Electrk , i ECC5 Pump Rm. Cochng Aus.hary andg 574* Test & Anal. 5P446 HVAC Far+ Carrier; ;no Aar Hdig. Onsts . Fans & Motors IM3940001A.8 MotortRehanse Electnc ,
Availiary stdg 574' Test & Anal. $P446 HVAC Fans-Carner; No Fan & Motor 1M398002 ECC5 Pump Rm. Cooling Motors Rehance Elects.c E5W Pump House 614' . Andymed SP444 HVAC Fan > 8vf f alo f orge Co.; .No Air 5uppfy Fan 4 Motor IM32C0001A,8 Emerg. 5erv. Water Vent Motor-Westmghouse Analysed SP-550 EE Lemer+ Albs ;no 0G41C0003A,8 fuelPoolCochng & Intermed ate 574' i 200 HP Motor for fue4 Pool Cooling Pump Oeanup E5W Pump Huuse 586' Analysed SP-550 EE Leme<+ Alias !No 50 HP Motor for E5W 5creen OP49C0002A,e E5W 5cseenWash '
Wash Pump SP-552 Et Brown toven tie (tr.c ,yeg 4.16 KV Metai dad 5wgr. 1R2250006 416 KV Drstribution Controitidg 62& Test 416 KV Distnbution Control 81dg 627 Test SP 552 EE stown sovere Electnc ives 416 KV Metal cad 5.gr. IR2250007 Controisidg 62W Test SP-553 Et ITE lmpenas ,No Load Centers IR2350003 th.12 480Vicad Centers Test SP-553 EE
- sTE Smperial lNo Load Centers (300 KVA 1A2350015 480V toad Centers Controlside 627 '
Transforme<)
Controd sidg 613' Test SP 555 EE Power Corwervon ;no 8attery Chargers OA4250007 D C. 5ystem - Battenes D C. 5ystem - Batteries Contrea Bldg 638' Test SP 555 EE Power Conwervon lNo eattery Chargers 1R4250008 Inter'n*d' ate 627 Test 5P556 EE G E. Ives 1R2250012 tit 15 Reactor Cerculatang Re<irc. Puenp ino Contici Swgr.
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EQUIPMENT SELECTED FOR EVALUATION FROM DFDDY U Cants" r nt ttDaarklT ni' Af iftf ATinalI RCT MPL # SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDORS EVA[UATED EQUIPMENTNAME 480 V AC MCC Controieldg 62W Test SP-557 EE Cutler-Hammer 'No ig Motor Control Centers OR2450020 th44 IE Motor Controt Centert IR2450010tA29 480 V AC MCC Controls 8de 62W Test $P-557 EE Cutler-Hammer (No Control Panet & Components IH51P0055A.s Diesel Generator D. G. Sedg 627 Test SP-M2 EE Sasler lNo 1R45C0004A.B DewlGenerator D G aldg 62W Analyzed $P %2 El Delaval lNo D esel fr9ne Fuet Oil Pump 1R45N0140A.8 Desel Generatee D. G. 68dg. 62W Test SP-%2 EE Magnetrol lNo l D E. Fuet Oil teve4 5mitch D G *ket Water C. Pump 1R46C0004A 8 Desel Generator D G.S W 62W AnalRest 7%2 EE Delaval lNo 1A46C0005A.s Desel Generator D.G. 88dg 62W Anal / Test SP-%2 EE Pumg>Butfalo forget lNo f D.G hket Pump & Motor 5.emers-Alles j Desel Generator D G.81dg. 627 AnalMest SP.M2 EE DeLavau5 semens-Alhs .No f L 0 Keep Warm Pump & Motor la47C0002A.9 125 Volt DC Contsof Bldg.638' Test SP %5 EE Poweil Elec. Manuf. Co. 3No l Distnbution Panels 1R4250012 th.14 l I
IR2550025 Dstnbution Panets ControlBadg 627 Test SP M3 EE Power Conversson Prod :No t5 WA AC Line Regulator 1R1450012 120 V AC Vital ControlBidg 638' Test SP-793 EE Elgar lNo 120 V AC 5tatac inverter HydrogenIgniter Aeactor sidg. 642' th. Test $P-793 Et Comsip :No l H 1. Dstribution Panel 1M%P0003 th.S 652' ,
l Vanous Panels Coneral Sedg Test SP-793 EE Gould No 110. J t 3 Gould Relays (> 150) 125 Volt DC Controisadg 638' TesVAnal. SP-554 EE Emde Power 5ystem sNo Elettn( Sattenes & Racks IR4250002 I .
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EQUIPMENT 5ELECTE D FOR EVALUATION "
at titi FROM ATinM i tty DF DDY (F C tair" Fnt ilDeuiF MT nf l TYPE VENDOR 5 EVALUATED MPL # SYSTEM LOCATION QUAliflED SPEC.
EQUIPMENT NAME 301-A03 GE Vakor No IClif0009 Control Rod Dnve Contairwnent G2( Test CRD 5(ram Deuh.5olenced Valve Test J01 A04 GE Harnmer-Dahl INo IC11f0010 Control Rod Drive Containtnent 620' CRD vent valve Test 301-A04 GE Hammer-Dahl 'No 1CllF0100 Contsel Rod Dreve Conta.ntnent 620' CAD Vent Valve Test 301-A05 GE Vakor No IC11fol10 Control Rod Dewe Conta.nment 620' CRD Alt. Rod inL 5clenoid valve 301-C05 GE G E. sNo 1Dl7N0003A. Gamma Radiat.on Auu. 5 team T. 614' Test insulator Detector 8,C.D Morutor GE Dekk'ers sNo IB21F0041 Ma.n 54eam Drywell 599* Test 301-502 M 5. 5afety Relief valve Test 301 502 GE Dekkers INo 1821f0047 Main 5 team Drywell 599*
M 5. 5afety Relief valve Drywell 633' Yest 301 505 GE valve-Atwood & Morrill; lNo M 5. hotationValveAimit5mitch 1821f0022 Nudear losler Act.-H.ller.$heffer; SwitchNatsonal ACME GE Valve-Atwood & Mornfl; l No 1821f0028 Nudear Sonier Drrwell 633' Test 301-505 M 5. IsolationValve/UmstSwitch Act.-Hatler-Shefier; Swit(h Nat.onal ACME MSN Leakage Control Availsery 620' Test 301-506 GE G E AomPoC lNo MSN Leakage Control Heater if3250001A, EJ N MSN Leak age Control Austaary 620' fest 301-507 GE G E Acanpo( Wu M5N Leakage Ccatrol li32C0001
- Slower / Motor fest 301 507 GE G E Aompot jves 1E32C00028.7 MSN Leakage Control Aumi.ary 620' MSN teakage Control
- l Blower / Motor Terry Corp No ROC Aum.t.ary 599' TesVAnal. 30l-508 GE ROC Steam Turtune Auembly SE51C0002 a
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- I EQUIPMENT SELECTED FOR EVALUATION FROM l PFDDY U 'LAff FMt ftpsaFMT AfI A11(ff ATtAfJ f f(T MPL
- SYSTEM LOCATION QUALIFIED SPEC. TYPE VENDORS EVALUATED EQUIPMENT NAME 181300:24 Rod Control a Reactor P.V. 599* Test 301 553 GE G E. No CAD indicator Probe infoemation lHl3 (Manyl PGCC ControlSidg 654' Test 301 M01 GE G E. No Control Room Panels it22P0001 H.gh Pressure Core Sprav D.eset Gen. 620' Test 301-MJ3 GE Stewart & 5tevenson No HPCS Control Panels HPC5 8atteries, Rack Chargers 1E2250005 H4gh Pressure Core 5 pray ControlBldg 620" Test 301-M03 GE C&D No IC11D0001 Control Rod Drive Conta nment 625 Test 301 582 GE GE No Hydeavhc Control Unit Transnutters Many Vanous vanous Test 301-M05 GE GE No Many ' Varcus various Test 301-M05 GE G E. No teve4 5 witches Combust 4ble Gas Control Aus Ant. Badg 627 Test / Anal. SP418 ISC Delphi anc ; Motor-Rehance No Hy Analyter, sample Pump & lH51P0022A.8 Motor H.gh Range Rad Reactor 630~/689' Test SP421 l&C Kaman No Rad.asson Monetor ID19N0100A.8 Monitonng Post kodent Morwtonng ControlBidg 679' Test SP421 1&C Kaman No Motoritarter Assembly ID19P0300 1 Post Accident Monitoring Control 8tdg 638' Test SP421 4&C Kaman No Me<ro Computer 1Dl9J0100 l Post A(odent Mormtcring Contre 4 81dg 679" Test SP422 l&C Kaman No l Sample Panet 1D19P0300 , '
GE l Pump Urwon, G E.-Motor No -
% 5LC Pump & Motor l Standby Uquid Control l Reactor 644' Analyzed l 301510_l l
{IC41C0001 l I
P:ge 7 EQUIPMENT tuirSELECTED rnt noururFOR EV rv,ALUATION FROM Prnav(r aterte avin u tt<T EQUIPMENT NAME MPL# SYSTEM LOCATION QUALiflED SPEC. TYPE VENDORS EVALUATED Chloone Detector OM25K0200A,8 Control Room HVAC Contro4 86dg 679* Test SP-791 I&C MDA 5(ientsf*C No Lamet 5 witch OM23N0011 A,8 MCC5witchgear Control 88dg 679' Test SP-793 1&C Natsonal ACME ; No Litrut Switch OM24N0013A,8 Battery Rm Ishaust ControlBldg 679* Test SP 793 1&C National ACME ' No Instrument Panel IC61P0007 Remote 5hutdown Contro181dg 620' Analyzed SP-594 I&C Comsp l No instrument Panel OH5 tP0177A,8 MCC HVAC & Satt. ControlSidg 679' Analysed SP-594 B&C Comsip ! No instrument Panel 1H51P0039 Emerg Cooling 5ystem Intermed. ate 654' Anatyred SP 594 1&C Coms.p t No soleno.d Operated valve IP5370075 Penettation fuel Hdig. 642* Analyzed SP-597 A&C Target Rock j No a ressunsatson Solenoid Operated Valve 1G4370050A.8 Suppeess.on Pool Maheup Ausdiary 81dg 574* Analysed SP-597 IEC Target Roth No Level 5 witch OC41NO415A,8 Standby Liquid Control Intermed ate 620" Test $P-598 l&C Barton No Level 5 match CP45N0255A,8 (5 Water (m. 5ervece W. 586* Test SP 600 l&C Magnetrol I No Pressuse Transmitter 1821N0062A,8 t%nlear So.ler Control 83dg 620' Test SP404 ISC Rosemount i No Test SP406 4&C Gould Level fransmitter 1C11N0012A,8, C,D Controt Rod Dnve Drywee4 599' lNo Contro4 Valve 1833F0019 Reactor Retirculating Drywell 620' Analyzed SP407 ISC Issher Controls No Solenced Valve 1821F0451 Nuclear Bo.ler Dryweli 620' Test SP 607 l&C fisher Contaois No ASCO 5clenoid Valve 183370420 Reactor Recuculatang Drywell 620' Test SP407 IAC ASCO No Controlvalve OP47f0045A,8 Controi84dg Chelled Control 81dg 679" RAM SP407 l&C isaber Controls /ITT g No W ater i
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Pig 2 8 j EQUlPMENT SELECTED FOR EVALUATION FROM DFDDY U (RAfr* Ffit ffDPJf MT AlI At tf t/"ATIAfJ f f(Y EQUIPMENT NAME MPL # SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDORS EVkLUATED Contrui Valve II12f 0051 A,8 Rewdual Heat Removat Ausshary 625 RIM SP-607 4&C fesher Conteois No 10* Check Vafve 1M16f 0020A,8 Drywell Vacuum Rehef Reactor 664* Analyted $P-635 Valve GPE Contiois Dev.
No 24* Check Valve IMl7f 00to tit 40 Containanent Vacuurn Rea< tor 712' Analysed SP-635 Valve itelief GPE Conuois Div. l No 16* Condensate St. Valve 1E2270001 High Pressure Core Spray Ausehary 574' Analyzed SP 301 Valve ' Valve-Anchor /Darbog; Operator-Limitorque lNo 12* HPC5 Pump inge(tson Valve IE2270004 Hegh Pressure Core 5 pray Ausahary 620* Analysed $P-301 Valve Vaive-Anct)pr/Darhng; l No l Operator-timetorque 4* Conta.nment Isolation Va; e 1112f 0054A,8 Residual Heat Removal Awa>hary 574* Analyzed SP-521 Valve TRW Mession No 4* Drywellisciatsonvalve IM5tF0501A,8 Combust.ble Gas Cenisol Reactor 664*
Analyzed SP 521 Valve TRW Mispon No 8* flush Water to Cont. Spray
- IE1270044A,8 Rewdual Heat Removal Rea(tor 642 Analyzed valve SP-521 valve TRW M swon i No l j
6* Inboardisolatson Valve it51f0066 Reactor Core hotation Reactor 610' Analyzed $P-521 Valve Ror kweil e no 1* LPC5 5uctecn Valve IE21f0031 tow Pressure Core 5 pray Ausiliary 574* R34/ Anal. V-523 Valve Target Rock Corp 8 No 3* 5uctson Rehef Valve IE1270036 Rewdual Heat temoval Aus.hary 574' RAMIAnal. SP-523 Valve Target Ror k Corp. No 6* 5utterfly Valve wA4otor CP47f0295A,8 Controf Chdied Water Contice 679" Test 57-524 Valve ValveContiomat.cs; Oper. . No Operator-tienitorque I* Sall Valve wn/ Elect. Operator 1017f 00718 Plant Rad.ation Mon. Reactor 62W Test $P 524 Valve Valve-Contromat><s; No Operator-ITT General Cone l
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EQUIPMENT SELECTED FOR EVALUATION FROM 1 M any (r usic rnistpsterur rTil ar trit Avinu ity SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDORS EVALUATED EQUIPMENT NAME MPL #
Mined sed & Demen. Rextor 620' Anal / Test 5P-53 5 Valve valve-Deesser, No l U4* lsolat4on Valve wMA Oper. IP22f0015 Operator-Lametorque tP57f0524A,5 Safety Rel. instrument Air Reactor 620' Analysed SP 531 Valve Dresser No 1* Contaerunent isolation valve Rextor 63F Analyzed SP-531 Valve Kerotest No 1* Forst MSN Accum. Valve 1821f 0024A,5, Nuclear Bo ler CD Rextor 642' Test / Anal. 531/568 Valve Valve Rockwets; . No 4* 5torage Tank valve IC4tf0001A.8 Standby Liqued tevel Operator-Lemesorque
= O perator MSIV teakage contica Aua limy 620' Anal / Test 531/564 valve Valve Rockwell; No 2* holat on Valve with operator 1E32f0007 Operator-Lametorque Nuclear poeler Rextor 599* Ana!/ Test SP-629 Valve AndermGreenwood No 6* M S Rehef-Vacuum 8r. 1821f 0037A to V CV. & DrywetlPurge Rextor 664' Test SP441 Valve ASCO No k4* 5olerod valve IM14f0207 M51V Leakage Control Ausehary 624' Anal / Test SP-521 valve Valve-Rockwell; No 2-1/2* lso. Valve w/ Operator 1E32f0009 Operator-Lametorque Ausehary 568' Test 301-M02 GE G E. 6 Yes LPC5 8nstrument Rxk IH22PM1 Local Panels & Rxks AumAary 56s* Test 301-M02 GE G E. Yes l ROCInstrument Ruk IH22P0017 Local Panels & Racks Aus.huy 568' Test 301-M02 GE G E. Yes ,
RHR instrument Rxk IH22P0018 Local Panets & Ruks l Aumahary 568' Test 308-M02 GE G E. Yes !
RHR instrument Ruk IH22P0021 LocalPanets& Ax6s Av .hary S64* Test 301-M02 GE G E. ' Yes RHRinstrument Rxk IH22P0055 LocalParWs & Rx ks Aumakary 564" Test SP404 t&C Ro m m t Yes Ottferenteal Pressureirats IC6tN0008 Remote Rextor Shutdown
Page 10 EQUIPMENT SELECTED FOR EVALUATION FROM 15FDDY (F C RAlf F Of ff P18F MY nil At trif AYtAlf f f(T MPL # SYSTEM LOCATION QUALIFIED SPEC. TYPE VENDORS EVALUATED EQUIPMENT NAME Res6 dual Heat Removal Aumahary 568' Test SP404 1&C Rosemount Yes Differenua4 Pre 65ure iransmetter IE12N0007A.B Reudval Heat Removal Aumahary 568* Test SP 604 l&C Rosemount Yes Dif ferential Preuure Transmetter 1E12N0015A.8.C Residual Heat Removal Aum.hary 568' Test SP404 t&C Rosemount Yes Preuure iransmetter lE12N0026A.B Residual Heat Removal Ausiliary S68* Test SP 604 ISC Rosemount Yes Pressure Transmstter IEl2N0028 Resadual Heat Removal Aumahary 568' Test SP 604 ISC Rosemount Yes Pressure iransnutter IE12N0050A.B Residual Heat Removal Auniteary 568* Test SP404 t&C Rosemount
- Yes Preuure Trar smetter IE12N0051A.8 Reudual Heat Removal Ausshary 568' Test 57404 ISC Rosemount Yes Dif ferenhal Preuure Transmatter IE12N0052A.B.C Resedwal Heat pemoval Avashary S64' Test SP404 t&C Rosemount Yes Piessure itansnutter IE 12N0055A.B.C Ausshary S68* Test SP404 1&C Rosemount Yes Pressure Transnutter 1E 12N0056A.B.C Resdual Heat Removal Aua.kary 564' Test SP404 6&C Rosemount Yes Preuvre iransmitter IE12N0058C Resadual Heat Removal Low Preuure Core Spaay Aua hary 568" Test SP404 ISC Rosemount Yes Pressure Transmitter IE21N00C3 Low Preuure Core 5 pray Avanhary S64" Test $P 604 l&C Rosemount Yes Preuure Transnutter IE2tN0050 Low Pressure Core Spray Auashary 568" Test SP 604 t&C Rosemount Yes How Transmitter 1E21N0051 Low Preuure Core 5 pray Ausshary S64' Test SP404 t&C Rosemount Yes Pressure Tr=4tter IE2tN0052 Low Preuure Core 5 pray Aua hary S68" fest SP-604 l&C Rosemount j Ves Pressure Transnutter 1E21N0053 Low Preuvre Core Spray Aua.hary 568' Test SP 604 l&C Rosemount Yes Pressure Transnutter IE2tN0054 Aumahary $68' Test SP 604 ISC Rosemount Yes Preuvre Transnutter 1E31N0075A Leak Detett.on 0
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l EQUIPMENT $ ELECTED FOR EVALUATION FROM Pf DDY (F (mAfr" F Af ftPP.Af pJT At f At titr AYtAfJ f f(T i
MPts SYSTEM LOCATION QUAUFIED $PEC. TYPE VENDORS EVALUATED EQUIPM ENT NAME IE31N0077A Leak Detestson Au .l ary 568" Test SP404 l&C Rosemount Yes Prenure Tranwnstter 1131N0083A,8 teak Detecton Auuliary $68' Test SP-604 l&C Rosemount Yes Preuure Transatter 1E5tN0003 Rextor Core ho. Cool. AvaikuyS W Test SP404 l&C Rosemount Yes l Dif ferential Preuvre Trans.
) 1E51N0050 Rextor Core ho Cool. Aum.hary SW Test SP 604 B&C Rosemount *
Preuure Transmatter Rextor Core bo. Cool Aunihary 568" Test SP404 s&C Rosemount Yes C,iferential Preuvre Trans 1E51N0051 l
IE51N0053 Rextor Core Iso. Cool. Aunehary SW Test SP4C4 l&C Rosemount 1 Yes Pressure Transmitter 1E51N0055A,8 Rextor Con a b. Cool. Aua.lsery S68" Test SP404 l&C Rosemount ! Yes l Preuvre Transtrutter u
d IE51N0056A,E Reame Lore ho Cool. Ausstaary 568' Test $P-604 1&C Rosemount Yes j Preuwe Transatter Aua.l.ary 568' Test SP404 ISC Rosemount Yes Prenure fransmetter 1E12N0083 Res.dval Hea: Removal
' Low Prenure Core 5 pray Aums.ary S64" Test $P 604 l&C Rosemount Yes Preuure Transtrutter IE21N0070 P
Auaaleary S68' Test SP404 l&C Rosemount Yes Preuvre Tsansmitter 1E12N0053A.B.C Rewdval Heat Removal Aua hary 568' Test SP404 t&C Rosemount Yes Preuure Transm tter 1E12N0057 Re:4 dual Heat Removal Rextar Core ho. Cool. Avail.ary 568" Test SP404 l&C Rosemount i Yes Preuvre Transmetter IE51N0007 1E51N0052. Rextor Care lso. Cool Ave hary S68' Test SP404 l&C Roemunt i Yes Preuureiransmstier IM17F0015 Cont. Vuuum Rehef Cont Venel 689' Anal / Test SP441 Valve ValeHenry Pratt, ! Yes 23* Re6.ef Valve untActuator Operator 4sm torque 1Ml7f0025 Cont.Vuuum Redeef Cont. Veuei b89' Anal / Test SP441 valve Valve-Henry Pratt; ; Yes 24* Reteef Valve wm/ Actuator Operator-tim torque
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/ EQUIPMENT SELECTED FOR EVALUATION FROM PFDDY if (9Jttr F Af fipOtFMT Af f Af fTtf ATIAM t f(T MPL # SYSTEM LOCATION QUALiflED SPEC. TYPE VENDORS EVALUATED EQUIPMENT NAME IM1M0035 Cont.Vauum Ret.ef Cont. Vene1689" AnalRest SP-641 Valve Valve Henry Pratt; Yes
{ 24* Rel.el valve w/ Actuator Operator +ntorque 1M1M0045 Cont. Vuuum Rehef Cont.Venei 689* Analjiest SP441 Valve Valve Herwy Pratt; . Ves 24* Rehef Valve w/4tuator Operator-Lintorque IMl4f0040 Cont Vene4 Purge Cont. Vene1689' AnalRest $P441 Valve Valve-Henry Pratt; I Yes 42* Purge Valve w/4tuator Operator BettssCorp.
IMl470090 Cont. Venei Purge Cont, Veuel 689' Anai/ Test $P445 Valve Val.e Henry Pratt; Yes 42* Purge Valve wtActuator Operator 4etus Corp.
1R4250002 DC 5ystem-8atternes Controi 63F Anal / Test 5P-554 EE Eside Power system No 6 Sattenes & Rxks 1R4250003 DC5ystem tattenes Contre 8 634' AnalRest SP-554 EE E mede Power 5ystem No g Batteries & Rxks IE12C0002A,0,C Resedual Heat Removal Aua.hary %s" Analyzed 301 % s GE Pump eyron iukson; Yes RHP Pump & Motor Motor-G E.
LPC5 Pump 4 Motor IE21C0001 Low Preuure Core 5 pray Aussinary %s' Analysed 305-501 GE Pump 8proniukson. Yes Motor-G E.
Aus48 ary %e" Analyzed 301-501 Gt Pump tyron Akton. Yes HPC5 Pump 4 Motor 1E22C0001 HPC5 Power 5upply Motor-G E.
Test SP-5% EE GE Yes Re<w<. Pumpinp Cont Swgr. IR2250013 Reactor Cerculatsng Intermed4 ate 627 SP5% EE G E. Yes Recirc Pump Trip Cont Swgr. IR2250014 Rextor Cerculating Intermediate 62F Test l 11 G E. Yes !
Recuc Purnp TnpCont Swgr. 1R22500 5 Rextor Circulating intermediate 621 Test 5P-5%
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