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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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
[Table view] |
Text
_ _ _ _ _-
f THE CLEVELAND ELECTRIC P.O. BOX 5000 - CLEVELAND. CHIO 44101 -
TELEPHONE (216) 622-9800 - ILLUMINATING BLDG - SS PUBLIGSoVARE Serving The Best Location in the Nation MURRAY R. EDELMAN VtCE PRESIDENT NUC LE A R April 10, 1986 PY-CEI/NRR-0448 L Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation {
U.S. Nuclear Regulatory Commission I Washington, D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Seismic Event Evaluation Report i Supplemental Information Submittal of Omitted Pages '
Dear Mr. Denton:
Our letter dated March 11, 1986 (PY-CEI/NRR-0442 L) transmitted supplemental information to the Seismic Event Evaluation Report. Twelve pages were inadvertently omitted from that submittal. A copy of these pages (Attachment B) is attached.
Please feel free to contact me if you have any questions concerning this matter.
Very truly yours, ttt3 y s Murray R. Edelman Vice President Nuclear Group MRE:nje Attachment ec: Jay Silberg, Esq.
John Stefano (2) ,
J. Grobe j I
8609140160 860410 PDR ADOCK 05000440 A PDR
ATTACIIMENT B PY-CEI/NRR-0442 L' - -
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{, EQUIPMENT NAME MPL # SYSTEM LOCATION QUALKIED SPEC. TYPE VENDOR 5 EVAi.UATED (5W Screen Weeh Vert Pump OP49C0002A.8 (mergerwy Seewice Water ($W Pumpheute 546* Analyzed $P 508 Mects Gaule ese p'
cp -i (5W Vert Pump 1P45C0001A.S Emergency 5ervicewater E5W Pumpheune 586' Analysed SP 501 Mech. Gould No Jnz, -[- (5W vert Pump IP45C0002 Emergency Serwi<e Weter (SW Pumphewee 586' Anatyred SP 50t MedL Gould .see iU E5W .tr;' - -- 586*
.1' E5W Local Centret Penel CH5tP0077A,8 Ennergenry SerW<e weser Analysed SP 505 MedL Enviree mesmerd esse t .), -
).9 35' . * , SLC TrorWer Pump 4 Meter OC41C0002A.s Standby M Centrol Intermediate Beds. 62g' Analysed 5p 506 Medt L1c. Pr;; GE-Meter itse
, y(r > AHR WWet Leg Pump & h 11IX0003 aseidual Meet memoval Ammhery Bldg. 574* Ansayeed SP-506 Mech. Dyren urhee* Pump; eese S. . '*-
GE M LPC5 Water Les Pump & Meter t(2tC0002 Law Pressure Care Spray Availiary Sids 574' Analysed $P-506 MedL- Pump eengham-Willamette. 8see 3 .. . . Meter.5.emer
, , HPG Water Leg Pump & Meter If22C0003 High Pressure Care Spray Ausiliary5343 574' Anseysed SP 506 Meth. Pump Singham-Wistemette; jsee
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. ~( Power suppey Penel IM5tS0008 th=a ha= Gas Centrol Centroltide 62F Test SP428 Mode. WreJ -- tse Power Supply Penet 1M5150002 r.-a .ha= Gas Centres Control elds. 62F Test $P42g Medt .- _;4 -- . pse CG Purgsag t- , - - -- & IM51C0001A.5 Combuststie Ges Centrol Centesnment 464' Test $P432 MedL C- ; ;.x -Turtenetaa; 'see
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Air nasS units.t= & Meeers 1Mase000lAs ICO Pwn, nnt Ceehas Au=hary88de SM Test
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Air 5uppfy Fan & Moser IM32C0001A,8 Emerg.5erv. Water vent E5W Pwnp House 614' Analysed SP-648 HVAC Fantuffale ferge Co.; , Iso Meter-W; ._ ; m 200 HP Motor for fuel Pact OG41C0003A,8 fuel Pool Cooling & Iritermertiate 574* Anser iod SP 550 tt Seemeno-Alles ipse Cool.ngPwnp Oeanup i
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4.16 KV Metal cad 5=gr. 1A2250006 4.16 KV Destributeen Centret tedg. 62f Test SP 552 ft Brown severi flects c :ves i
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. EQUIPMENTNAME MPL # $YSTEM LOCATION QUA1NIED $PEC. TYPE VENDOA5 EVALUATED CAD 5 cram Drids.5eiene d valve IClif0009 ControI Aod Drwe Containment 620' Test 301-A03 GE Vaker 'No CAD Vent Valve IClif0010 Centrol Aad Drwe Containment 620' Test 301 A04 GE Nammer-den INc CAD Vent valve IClif0180 Centrol Aed Drive Conta.nment 620' Test 301 A04 CE Hemmer-den 'No CAD Art.Rodine Saleno.dvalve ICllfelle Control Red Drwe Contamment 620' Tout 301-405 GE vascer he insulater Detector 1Dl?N0003A, Gamma Radiation Ava. Steam T. El4' Test 3014 05 GE G E. eNo 8.C.D Monitor .
E15afety Rehef valve IS2tF004I Main 54eam DrywelI 599' Test 301-502 GE Dders iNo
. uk 5afety Relief valve 1821f0047 Main 5 team Dryweg 599" Test 301-502 GE Dikkers INe EL isolation valvedmit 5antch 192370022 leudearSeiler Drywe4 633* Test 301-505 GE ValeAtwood & Memil; No ActAnller-Sheffer; SantchNetional ACME M i tentationValveUmit Suntch 182170028 Nudear Seiler Drywee 633' Test 301-505 GE ValwAswood & MornN; No ActAtiller-Sheffer; l SMNetional ACME I an5N Leakage Control Hester SE3280001A, MSN Leekage Centrol Aemihary 620' Test 301-506 GE G.EAmmpec the f.LN s aA5N Leakage Control SE32C0008 MSN teekage Control AumEary E20' Test 301-507 GE G.EAmmpoc lyes aso-erssotar a mASN Leahage Control IE32C0002SJ MSN Lookage Control Aussisery 620' Test 301-507 GE, G.EAempec jYes slower / Motor .
ROC Steam Tur%ne As.emtdy 1E58C0002 SOC Auniliary 599* Test, Anal. 301-50s CE Terry Corp. -No 4
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8 EQUIPMENT SELECTED FOR EVALUATN)N FROM oreov er < amie rna tionararr tu i me iriravinna n ser l EQUIPMENTNAME MPL s SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDOft5 EV."1UATE D
- CAD an6caterProbe 18 300124 med Cenuot e meecter P.V. 599* Test 301 513 GE G E. 8ee Informatiest Conuei mesm Pene4 IH13 lManyt PGCC Centrolgidg 454' Test 301 486i GE G E. - 8se HPC5 Centrol Panets 1E22P0001 MigliPressure Care Sprer Diesel Gert 620' Test 3014s03 GE Saewart 4 Seewonnen see HPC5 Sattenet. Rack Ch. If2250005 Higit Pretoure Core Spray ControlBeds 620' Test M14403 GE C40 fee Hydrous.c Cantret unt ICt100009 Centrel Aod Delve Centa.nment 6W Test 301-512 GE G t. See fransamtters Many various Vaneus Test 3014405 GE G T. See tevel5=atees Many
- Various Vaneus Test 3014a05 GE G E. 80e H2 Analyser,5ampie heste 4 1HS1P0022A,8 Caettustatie M-asCentrol
- Aus Ant. 88ds. 620' Test / Anal. SP411 I4C Desp8eInc. Meter-Aeliance see Motor l ta6ateen Memaer ID19es010M,8 High aange med aeacter 6W489* Test SP421 84C Kamen fee l Meat *nas l Mater Starter Aasentfy 1019P0300 Post Acodont Monstering l
Centrol 88ds 64 Test SP421 I4C Kaman fee u.cro Computer 10ISSIce post Accident Monitoring CentrolBeds 63s" Test W428 14C Kaman see si Sample Penel 1019P0300 Post Accident Monstering CentrolOlds 64 Test W422 ISC Kamen see j5LC Pump 4 Motor l IC41C000t l 5tandtry Ugued Control l Reactor 644* Analysed 301-510 l GE l Purnp Union;G.E.-Motor l No -
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Page 7 EQUlPMENT SELECTED FOR EVALUATION FROM prany tr c amer rns stomarast ns i as nrar Arnasi n KT EQUtPMENTNAME . MPL # SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDOR $ EVhlUATED CNona. oeinter GM25x0200A.: Canites noem avAC C.nt,es e.dp 6& ion SP ni isC M oA Sc.enor.c No Lernet Sutch OM23se0011A,8 MCC 5=tchgear Controltidg 6W Test SP 793 s&C asateenal ACMt ; ese LWt S-sch OM24ss00 3A,8 Satsery an tahaint Contref 84dg. 64 Test SP 793 toc Nonenal ACME e see arstr_c: % Paned 1C6tP0007 Semote 5hutdomst Centree tles. 6W Anseynod SP-594 84C C --l; j seo instrument Panel OM5170177A.S MCC HVAC & Sett. Control Dedg 6W Analysed $P-594 8&C Caen p ! see wet-t- 4 Panse IM5tP0039 Emerg Coehag 5p Anaerved hetenseskate 654* SP 594 seC C M; s sao Solene d Operated Walve IP53f0075 Penet.atiere Fwst Mdig 642' Analysed $P-597 14C Target hod f Pressuriaatson l see Solenood Operated valve IG43F00$0A,8 ' ;, _ r Pea 6 Makeup Ausshary 8845574* Analysed SP 597 I&C TargetAe d see
! Level Satch OC418804iSA.8 Standtsy Utguid Control intermediate EN Test SP-598 14C Bartort sao teves5. itch OP45asc255A.s t5 water t= 5m.ce w. 5a6* Ten 5P-400 sac " ;=es i see I Pressure Trr_m.tser IE21asansta a soucseer te.nor Central aseg 620' Test SP-404 14C Rosemount i see
- LevelTr n m.tter ICitas0012A.S. Centrol mod 0nve Dryessel 599' Test SP-606 8&C Gould C.O l see Contrad Vafwe 1833F0019 Reacter Aecirculatang Ory=e# 620' Analysed SP407 seC rnher Contsoes see t Solenced VaM 1821F0451 seuclear Soder Drywe4 6W Test SP-e07 I4C Faher Centroes
- Ice ASCO $aleased valve 18317G420 Seactor Aecirculsong Orywest $20' Test SP-407 ISC ASCO see Contres va#we Open0045A.s contres ends oened contres sede. 6W asM SP4e7 sec Faher ControMTT see watee S
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Page 8 EQUIPMENT 5 ELECTED FOR EVALUATION EROM ornov tr c uer rru ttomaruY ru i at trarattruu e ser EQUIPMENTNAME MPL # SYSTEM LOCATION QUAURED SPEC. TYPE i Control valve VENDOA5 EVALUATED 1E12 0051A8 Renal Heat Removal Aumisary 627 RIM $P407 10' Check Vdve B&C fesher Coctrois 1M1670020AS C ;;;!:Vacuuna pelief seactor 664" No .
24* Check Valve ?-2,2ed SP435 Valve tM17F0010 tiL40 GPE Controls Dev, Cort r- .: Vacuum Seactor 712" feo Relief ?:_9ed SP435 Valve GPE Contress Dev. No 1&* Cc. A ate SL Vatre 1t2270001 Hegh Pressure Core Sprey Aumhary 574* -;
?rd,2ed SP 301 Vdve' VWwo-Ancherre.O g peo tt* HPC5 PumpirigectonVdve Operstor-Umitorque 1122F0004 tsgh Pressure Core 5 pray ,
Aumhary 620' ?-d, sed SP-301 valve valve-Anchpr4E*4.
4* Containment NAation Valve Operator-Lunitorque l No I(1270054AB Residual Heat ?:ra.at Ausil6ary 574' 4*C i ; Isolation Valve Analyzed SP-52i Vafve 1M5170501A.3 C&_Mbie Gas Control Tawunsion peo asactor 664* Analysed 8* Flushwater to Cont. 5 pray SP 521 valve tt12f0044At TRWA&ssion peo Valve AewtualHeat t ra.at Reactor 642 Analysed 5A521 valve TRwMession i peo 6* anboard hosation valve 1E5170066 Reactor Care holatum Reactor 630' Analysed SP-521 Valve l' LPC5 Suction valve it21F0031 Rockwe41 Low Pressure Core Sprey Ausiliary 574*
[ peo RMAnal. SP 523 Valve 3* Suctson Reteet Valve it1270036 Target acck Corp. I peo Aesadual Heat Removal Aumliary 574*
6* sutterey valve mowetar RMAnal. SP-523 Valve OP47f0295AS Target Rock Corp. peo Oper. Centrol Chilled water Control 679*
Test SP-524 Valve Valve <anaromatics; i No t* saa Va#ve mvtsect. c.,...ar tottf0071s Operator-Umitorque Piant nadiation m a. actor 62r Test SP-524 VWwe VW+C= .at.cs: .
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, , _ Operator-ITT General Cont.
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Page 9 EQUIPMENT SELECTED FOR EVALUATION FROM i Dre e Y (F r ulf Fnt t19harMT fu I A t istf ATIAM iIt? '
EQtRPMENTNAME MPL # SYSTEM LOCATION QUALFIED SPEC. TYPE VENOOR5 EVALUATED s-ud nam.en vahe mmO, IP22f00:5 u. e eed & oe.n.n. a.= = sw AndAe. w SiI vd,e vuo,e se,; No Operator-Linneteregue t* Conta nment hotas.en va8vo IP57f0524A,e Safety ass. anstrwnent Air aeacier 6N Analysed SP 531 vehe creener No t* r.asthe5N Accune.v d e is2170024A,s. sowieer se.ner seector sw Anseysed y 53: Ver :3 C,0 Kerosen No 4* 5torage Tar
- Vale IColf000 tA,8 Staney taquid tevel aeacter 642' TesedAnot. 538/548 Valve
=sCperator val + aerhuse.
- No Operater-theastergue 2* hotat+en valve meth operaser it32f0007 hs5N teekage Cantrol Aum.liary &W ' AnalMest 531/548 Valve Valve-aockwee; No Operater-tkuisterspue e as i A.e.es-vannasi nr. is2troonA v v hucs.n so.se neuter Sw AastAest 5P429 vdve weer oed No L4* 5ceered Vdve taalef02C7 CV. & Drywee Purge P eac'ior W t' Test SP44 Valve ASCO No 2-U2*Ine vaiwe ==Cperaner it32f0009 M5lv Leakage Control Avail.ary E24' AnalAest SP 521 valve vahe-Rockwee; No 1 Operator-tini torque LPC5 4rstn. ment mact IM27 4001 Local Paness a Aacts Aum tsary 548' Teu 301-48C2 GE G t. s Yes aOCkstrwnent Aact IM2270012 LocalPaneh a muts Aun.Eary S68* Test 301-8402 GE G E. Yes treainstrummie AactL 1M22Pe31s Lacal Panees & Aacts Avana.ary 56s" Test 301-aa02 , G4 G t. Yes arta erstrwne*.t Aart 1M2290021 Localahne's & Amts . , Nanisary 544' Test 30'*Q2 GE G t. Yes Area katrument Ract i 1H2290055 Lacas Panees & Ra As Aumis.ary 56s" Test 301-gac2 GE G t. ' Yes omflerental Pressure Tram ICStes0003 memote Beecter Audary See' Test SP M 84C Assemount Yes Pvedene6 _
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Page 10 EQUtPMENT SELECTED FOR EVALUATION FROM prDRV (r (RJtr rnt trptArtJT Af l
I At IflJ'ATiths f ICT l, EQUtPMENTNAME MPL # SYSTEM LOCATION QUALIFIED SPEC. TYPE VENDORS EVALUATED ,
Differenual Preuure Trarwnstter stI2N0007A,8 Revdual Hea: Removal Ava hary 568" Test $P404 ISC Aosemount Yes
@ Differential Preuure Trarwnitter 1(12N0015A,5,C Rewdual Heat nemoval Auseliary 568* Test 9-604 ISC Rosemount Yes Prenure fransmitter IE12N0026A,8 Residual Heat Removal Ava.htry S68" Test SP404 ISC Rosemount Yes j ,
Pressure Transmitter til2N0028 Residual Heat Removal Aumisary S64' Test $P404 14C Rosemount Yes I
k Pressure Trammitter 1E12NCC50A,8 Residual Heat memoval Aumliary 564* Test 57-604 14C posemount Yes Prenure Transmetter lit 2N005tA,3 Residual Heat Removal Aumliary S64" Test SP404 ISC Rosemo. nt
- Yes Differential Pressure Transestter 1E12N0052A,3,C Residual Heat Re wwal Auxiliary See" Test $P404 ISC nosemount Yes
, Preuvre Tranimitter 1t 12N0055A,3.C newdual Heat memoval Ausiliary 568* Test SP404 1SC Rosemount Yes Preuure fransnutter . It12N0056A.B.C Residual Heat Removal Availiary S64* Test $P404 ISC Actemount Yes f Pressure Transmitter til2N005aC Residual Heat temoval Aunisiary 548' Test $P404 s&C posemount Yes f Pressure fransmitter tf2tN0003 Low Pressure Core spray Aumliary 544' Test SP404 ISC aciemount Yes Pressure Transmitter 1128N0050 tow Prenure Core Spray Aumhary 564" Test SP404 84C Rosemount Yes Flow Transnutter 1821N0058 Low Preuure Care $ pray Aa.m hary S68' Test $P404 8&C Rosemount Yes
, Preuure Tranimetter 1E21N0052 Low Preuure Core Sprey Ausihary 564" Test $P404 ISC Rosemount Yes Pressure Tracemetter IE2tN0052 tow Pressuro Core 5 pray Austiary S64' Test SP404 B&C posemount l Yes Pressure Transnutter st2tN0054 Low Pressure Core 5 pray Aumhary S64* Test $P-604 IEC Aotemount Yes Pressure Transnutter IE3tN0075A Leak Detect on Aemiliary 568* Test SP404 18C Rosemount Yes s _
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M l EQU1PMENT SELECTED FOR EVALUATION FROM presrv er (uir" rnitrt*urur nel as trtravinu e ter EQUIPMENT NAME MPL # SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDOR 5 EVALUATED .
'I.
(l Pressure Trarumtter if31N0077A Leak Detection Avail ary 56r Test SP-604 ISC Sosemount Yes Pressure Transenitter It31N0083A.B teak Detection Auniliary 568* Test SP404 ISC Rosemount Yes y- , ; Differentia: Pressure frane. It31N0003 Reactor Core ho. cool. Auxiliary S6a* Test SP404 8&C Rosemount Yes i s l'; q Pressure Transatter It51N0050 Reactor Core lso. Cool. Aun.liary 544' Test SP404 14C Aosemount
L C.f ferential Pressure itans. 1E5fN0058 Reactor Core lio. Cool. Availiary 564* Test SP 604 ISC Rosemount Yes Pressure f ransmitter it5tN0053 Reactor Core l* Cool. Auxiliary S6F Test 5P-604 B&C Rosemount 1 Yes 4 Pressure Transatter it31N0055A,8 Reactor Core he. Cool. Availiary 56F Test SP404 14C Aoiemount ! Yet hi E.F Ii l l Pressure Trannetter l!5fM0056A,t Aeactor Core Iso. Cool. Auxiliary 56e" Test SP-604 ISC Rosemount Yes
] Pressure Transmitter SE12N006) Residual Heat Removal Availiary 568' Test SP404 ISC Rosemount Yes Pressure Transmitter If21N0070 tow Prethare Core 5 pray Ausiliary S6r Test SP404 84C Rosemount Yes
Pressure Transatter 1E12N0057 Revdual Heat Removal Aunaisary 568* Test SP-604 ISC Rosemount ' Yes Pressure Trammtter If51N0007 Reactor Core lio. Cool. Ausiliary S6F Test 5P404 14C Rosemount i Yes Pressure fransmitter 1E51N0052 Reactor Core he. Ceel. Ausiliary S6F Test SP-604 14C Sosemount i Yes 24' Relief valve wActuator IMIN0015 Cont. Vacuum Relief Cont.Vesse8 6a9* Anal / Test SP441 valve Valve-Henry Pratt; ' Yes Operator 4em. torque 24* Relief Valve wActuator IM17f0025 Cont. Vacuum Retief Cont. Vessel 649" Anal / Test SP441 Valve Valve-Henry Pratt; i Yes Operator-timitorque
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Page 12 .
r EQUIPMENT 5 ELECTED FOR EVALUATION FROM prony (r usu rnt vtpuruv nti n trt_ artnu e t<T EQUIPMENTNAME MPL # SYSTEM LOCATION QUAUFIED SPEC. TYPE VENDORS EVALUATED 24' Relief Valve wdActuator IMl?f0035 Cont.Vocuum Releet Cont.VesseI 64s' AnalAsst SP-641 Valve VWwe. Henry Prett; Yes Operator-Umitorque 24
- ReGef Valve WActuator IM17f0045 Cont. Vacuum 9eGef Cont.Vessef 609' AnalAest SP-641 valve ValeHenry Pratt; e Yes Operator-Umitarque 42* Purge Valve WActuator IM14F0040 Cont. Vessel Purge Cont.VesseI 649' AnalMest SP-649 Valve Valve-Henry Pratt; I Yes Operator-settis Corp.
42 Purgevdve.sAounter IM14r00s0 Cont.vene: Purge Cont.vesses ses- AnasAnt SP-64: vdv. vdve-Henry Pratt; Yn Operator 4ettes Corp.
sattenes 4 Racks 1R4250002 DC5ystern-eatteries Control 634' AnalRest $P 554 EE Eside rsmer 5ystem No satteries & Racks IR4250003 DC 5ystem-eatteries Control 634' AnalAest SP 554 EE Eside Power 5, stem No RHP Pump & Motor IEl2C0002A,3,C Residual Heat Removal Availiary 564' Analysed 308 501 GE Pumpeyron sackson; Yes Motor-G E.
LPC5 Putnp & Motor IE2tC0005 Low Pressure Core Sprey Availiary 564" Analysed 301-501 GE Pump eyeonJackson; . Yes Motor G E.
HPC5 Pump & Motor 1E22C0005 HPC5 Power Supply Auniliary 564' Andymed 301-501 GE Pumpeyron sackson; Yes Motor 4E. .
Recirc.PumpTripCor*.s Swy. tR2250013 Reactor Grculatmg intermediate 62F Test SP 554 EE G E. Yes
- Retirc. Pump Trip Cont. Swgr. 1R2250014 Reactor Grculating intermediate 62F Test SP-556 EE G E. Yes '
RetirC. Pump Trip Cont. 5wgr. IR2250015 Reactor Circulating intermediate 62F Test SP-556 EE G E. Yes k_
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