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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999
Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)
ML20217M2871999-10-21021 October 1999
Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
ML20217H6231999-10-18018 October 1999
Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217J4331999-10-15015 October 1999
Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation
ML20217H6251999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld
ML20217H6341999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld
ML20217F4301999-10-14014 October 1999
Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1
ML20217G9791999-10-14014 October 1999
Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2
ML20217D3191999-10-12012 October 1999
Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon
U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999
Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)
ML20217C0871999-10-11011 October 1999
Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999
Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
ML20217F7891999-10-0808 October 1999
Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV
ML20217C1671999-10-0808 October 1999
Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2
U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999
Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station
U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999
Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld
ML20217A7601999-10-0606 October 1999
Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20217B6351999-10-0505 October 1999
Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in
ML20212L1791999-10-0505 October 1999
Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2
05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999
Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl
ML20212M0931999-10-0404 October 1999
Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff
ML20217A9881999-10-0101 October 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20217A7361999-10-0101 October 1999
Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs
ML20217B2991999-10-0101 October 1999
Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
ML20212J6751999-09-30030 September 1999
Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts
ML20217A6201999-09-30030 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl
ML20217J1421999-09-30030 September 1999
Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC
ML20217J1251999-09-30030 September 1999
Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC
ML20217A9311999-09-29029 September 1999
Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem
ML20217A5821999-09-29029 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20216H4301999-09-23023 September 1999
Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108
ML20212G6751999-09-22022 September 1999
Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station
U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999
Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl
ML20212E7171999-09-22022 September 1999
Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads
05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl
ML20212G6981999-09-20020 September 1999
Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability
U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999
Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
ML20212C0591999-09-17017 September 1999
Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97
ML20216F8051999-09-17017 September 1999
Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified
ML20216F7441999-09-17017 September 1999
Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424
ML20217H3421999-09-17017 September 1999
Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr
05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999
Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
ML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
ML20211Q9911999-09-10010 September 1999
Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring
ML20212A1141999-09-10010 September 1999
Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage
05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999
Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments
ML20212A6991999-09-10010 September 1999
Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P6171999-10-21021 October 1999
Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217H6341999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld
ML20217H6251999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld
ML20217F4301999-10-14014 October 1999
Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1
U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999
Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)
ML20217C0871999-10-11011 October 1999
Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999
Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
ML20217C1671999-10-0808 October 1999
Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2
U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999
Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station
U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999
Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld
05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999
Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999
Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl
U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999
Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
ML20212G6981999-09-20020 September 1999
Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability
05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl
05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999
Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999
Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed
05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999
Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments
ML20211Q9911999-09-10010 September 1999
Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl
ML20211M1151999-08-31031 August 1999
Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006
ML20211G1831999-08-27027 August 1999
Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS
ML20211G1221999-08-27027 August 1999
Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d)
U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999
Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl
U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7
U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999
Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage
ML20211B0871999-08-20020 August 1999
Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723
U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999
Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired
U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999
Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813
BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999
Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2
BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999
Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station
05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999
Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER
U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999
Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729
U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999
Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809
ML20210N2961999-08-0909 August 1999
Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend
U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999
Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999
Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999
Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS
ML20210J0541999-07-30030 July 1999
Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files
ML20210K0771999-07-30030 July 1999
Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46
ML20210J8951999-07-29029 July 1999
Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal..
U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999
Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS
U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999
Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131
BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999
Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990
Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry
ML20059K6741990-09-17017 September 1990
Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided
ML20059K5081990-09-14014 September 1990
Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990
JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990
Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump
ML20059H5321990-09-11011 September 1990
Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers
ML20059L6611990-09-10010 September 1990
Forwards Byron Station Units 1 & 2 Inservice Insp Program
ML20059H4271990-09-0707 September 1990
Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831
ML20059G0941990-09-0505 September 1990
Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp
ML20059C6891990-08-30030 August 1990
Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary
U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990
Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn
ML20064A3681990-08-24024 August 1990
Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA
ML20064A3751990-08-24024 August 1990
Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept
JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990
Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event
ML20056B4061990-08-21021 August 1990
Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements
U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990
Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71
ML20064A0181990-08-16016 August 1990
Submits Supplemental Response to NRC Bulletin 88-008,Suppls 1 & 2.Surveillance Testing Revealed No Leakage,Therefore Charging Pump to Cold Leg Outage Injection Lines Would Not Be Subjected to Excessive Thermal Stresses
ML20059A3991990-08-15015 August 1990
Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program
ML20059B8961990-08-14014 August 1990
Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed
ML20059D1731990-08-10010 August 1990
Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels
U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990
Forwards Reissued NPDES Permit IL0036919
ML20063Q1051990-08-10010 August 1990
Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2
U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990
Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators
ML20058N0551990-08-0707 August 1990
Provides Supplemental Response to NRC Bulletin 88-008, Suppls 1 & 2.Surveillance Testing Performed Revealed No Leakage,Therefore,Charging Pump to Cold Leg Injection Lines Would Not Be Subjected to Excessive Thermal Stresses
ML20058N2971990-08-0606 August 1990
Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21)
U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990
Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))
U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990
Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly
ML20056A3351990-08-0202 August 1990
Responds to NRC Bulletin 88-009 Requesting That Addressees Establish & Implement Insp Program to Periodically Confirm in-core Neutron Power Reactors.All Timble Tubes Used at Plant Inspected & 18 Recorded Evidence of Degradation
ML20056A7031990-07-27027 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring
ML20064A5491990-07-27027 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation
ML20055J1221990-07-25025 July 1990
Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary
ML20055J1261990-07-25025 July 1990
Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses
ML20055H7631990-07-25025 July 1990
Forwards Financial Info Re Decommissioning of Plants
ML20055H7661990-07-24024 July 1990
Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions
U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990
Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989
ML20055H0291990-07-17017 July 1990
Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990
ML20055G3251990-07-16016 July 1990
Responds to SALP Board Repts 50-454/90-01 & 50-455/90-01 for Reporting Period Nov 1988 - Mar 1990.Effort Will Be Made to Continue High Level of Performance in Areas of Radiological Controls,Plant Operations,Emergency Preparedness & Security
ML20044A9621990-07-13013 July 1990
Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc
ML20055G4631990-07-13013 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-456/90-08 & 50-457/90-08.Corrective Actions:Discrepancy Record for Cable Generated & Cable That Had Been Previously Approved for Use on Solenoid Obtained & Installed
ML20055G2011990-07-13013 July 1990
Forwards Corrected Monthly Operating Rept for June 1990 for LaSalle County Unit 1.Outage/Reduction 16 Corrected
ML20044B1411990-07-12012 July 1990
Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request
ML20044B2141990-07-11011 July 1990
Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification
ML20044B2081990-07-11011 July 1990
Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl
ML20044A9521990-07-10010 July 1990
Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage
ML20044B2871990-07-0909 July 1990
Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original Submittal
ML20044B1751990-07-0909 July 1990
Responds to NRC Request for Addl Info Re Util 890726 Proposed Amend to Tech Specs to Allow Continued Operation for Period of 12 H W/Main Steam Tunnel High Ambient Temp & High Ventilation Sys Differential Trips Bypassed
ML20055F1831990-07-0909 July 1990
Provides Status Rept on Breaker Replacements in Response to NRC Bulletin 88-010.Breaker Replacements for Plants Scheduled to Be Completed by 901031
ML17202L2861990-07-0202 July 1990
Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary.
U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990
Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20055D1921990-06-29029 June 1990
Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues
ML20055D4811990-06-29029 June 1990
Discusses Revised Schedule for Implementation of Generic Ltr 89-04 Re Frequently Identified Weaknesses of Inservice Testing Programs.All Procedure Revs Have Either Been Approved or Drafted & in Onsite Review & Approval Process
1990-09-07
[Table view] |
Text
N Commonwealth Edison
- / One First National Plaza. Chicago. Ilknois v / Address Reply to. Post Othce Box 767 j Chicago. Hhnois 60690 December 4, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Removal of Unqualified Instrumentation From The DG Engine and Engine Skid NRC Docket Nos. 50-373 and 50-374 References (a): Unit 1 License (NPF-11) Condition 2.C.(21).(c)
(b): Unit 2 License (NPF-18) Condition 2.C.(12).(a)
Dear Mr. Denton:
Reference (a) required that prior to startup after the first refueling outage, controls and monitoring instrumentation be removed from the DG engine and engine skid, except instruments that are qualified for this location. Reference (b) contained a similar condition and, in addition, required Comonwealth Edison t.o submit an evaluation, that confirmed the design objective, for Staff approval. This letter and the attachments are in compliance with the Unit 2 license condition, but are applicable to all ESF DC's at LaSalle. The report summarizes our evaluation of the controls and monitoring instrumentation and describes the modifications that are needed to comply with the design objective.
Based on a siesmic and environmental qualification program conducted by Stewart and Stevenson and Southwest Research Institute, we have determined that all safety-related electrical devices and instrumentation, except for GE control switches, located on the diesel generator engines and engine skids are qualified for their location and that the non-safety-related devices will not fall in a manner that will degrade any safety-related equipment.
Each DG engine skid has two GE control switches, and modifications have been initiated to remove them from the skid by either deleting them from the system or relocating them to one of the local DC control panels. These modifications will be completed prior to startup after the first refueling outage on the respective units.
Attachments A and B summarize the results of this qualification program. The two tables list all of the electrical devices and instruments located on the five ESF DG engine skids at LaSalle, their safety classifi-cation, method of qualification, and the corrective action initiated for the unqualificated devices. Unless specifically noted, the device was qualified for 40 years to the requirements of IEEE 323-1974, 344-1975, and 387-1977, and this qualification included non-seismic vibration aging.
0 8512110400 0 00373 PDft ADOCK O PDR I I(
i P
H. R. Denton December 4, 1985 The vibration aging tests simulated over 11,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of diesel engine operation. Attachment C describes the vibration aging test procedure, and Attachment D describes how the vibration levels of an EMD 645 diesel engine, the type at LaSalle, were determined. Attachment E contains a typical test report for a skid-mounted device. All test reports are on file at the offices of our Architect-Engineer.
To ensure that the qualification of these devices is maintained, the devices have been added to the LaSalle Equipment Q-List.
If you have any questions concerning this matter, please contact this office.
One signed original and ten (10) copies of this letier and the attachments are enclosed for your use.
Very truly youer, W .
H. L. Massin Nuclear Licensing Administrator im Attachments cc: Dr. A. Bournia - NRR NRC Resident Inspector - LSCS 0955K
t Attachment A Pcge 1 of 5 Skid Mounted Components on Diesel Generators O, IA, and 2A f
! Safet Qualification Comments Item Description Class { Method 2 IE Test and Seismic qual. and 01 Fuel Prime Pump Motor
- f Analysis vibration aging done by l
(Century 8-213514-01) Rest of qual.
test.
i 'e performed by analysis.
DC Soakback Oil Pump Motor
- IE Test B4 (GE 5BCC56KD63A)
Oil Cire. Pump Motor
- IE Analysis Analysis includes a fatique B7 evaluation on the long (Delco IT5727-SIA) term effects of exposure to normal engine vibration.
AC Soakback Oil Pump Motor
- IE Test and Seismic qual. and vibration 87A aging done by test. Rest Analysis (Delco 2J2224C1Y27) '
of qual. performed by ~
analysis. Item not installed, to be added per EMD MI 9644 lube oil mod.
IE Analysis Analysis includes a fatique G1 2600 KW Generator
- evaluation on the long (Ideal 293266N-268N) term effects of exposure to normal engine vibration.
Analysis Same as G1 G2 Exciter * (Ideal 293269N-271N) IE IE Test and Seismic qual. and vibration G3 Generator speed sensor Analysis aging only (Synchro SA-1540)
NT Test Only structural integrity H1 Immersion Heater
(Chromalox 155-115937-141)
Generator Space Heater
- NT Analysis Only structural integrity H2 was checked.
(furnished with generator)
- Cat a control or monitoring instrument
Cttachment A Pcgo 2 of 5 Skid Mounted Components on Diesel Generators O, 1A, and 2A Safety Qualification Item Description Class I Method 2 Comments KS, K17 DC Motor Starter (for Bl&B4) 1E Test (GE CR106-SO-OO-DEA)
Air Start Solenoid Values IE Test
- o. L1,L2 (Salem 912-055) 1E Test and Seismic qual. and vibration l L3 Governor * (Woodward 8520-288) analysis aging done by test. Rest of qual. performed by analysis.
M13 Tachometer (CE 50-103111FAFA1) NT Test Pyrometer - Exhaust Gas NT Test Only structural integrity M14 was checked.
(Alnor FND-21)
Gen. Stator Temp. Sensors NT Analysis Only structural integrity RTD 1-6 was checked.
(furnished with generator) 3 Environmental qual. did not S50 Governor Control Switch IE Test include vibration aging.
(GE SBM 10AAO66) SSA is to be deleted because another local gov.
control switch, SS, is located at the generator I control panel (DGO2JB).
I l' S6 Cranking Lockout Switch IE Test I (SQ D 9012-ACW-21)
I S8 Engine Overspeed Switch IE Test (EMD 84224490F)
- Not a control or monitoring instrument
Attcchment A Pcg2 3 cf 5 Skid Mounted Components on Diesel Generators 0, IA, and 2A Safety Qualification Item Description Class I Method 2 Comments S9 tow Oil Pres. Shutdown Sw. NIE Test (SQ D 9012-ACW-21)
.S10 tow Oil Pres. Alarm Sw. NT Test (SQ D 9012-ACW-21)
High Water Temp. Shutdown Sw. NIE Test S11 (SQ D 9025-BCW-32)
High Water Temp. Alarm Sw. NT Test S12 (SQ D 9025-ACW-32)
S10 Low Oil Temp. Alarm Sw. NT Test (EMD 8447100)
NT Test Only structural integri,ty S16 High Fuel Filter Diff. Pres.
was checked.
Alarm Sw. (SQ D 9012-AEW-25)
NT Test Only structural integrity S17 High Oil Filter Diff. Pres.
was checked.
Alarm Sw. (SQ D 9012-AEW-25)
Test 3 Environmental qual. did not S193 Emergency Stop Pushbutton Sw. IE include vibration aging.
(CE CR29400K2O3H) S19A is to be deleted because another local emergency stop switch, S19, is located at the
~ engine control panel (DGO3J).
- Not a control or monitoring instrument
= _ . . - - . - - . - - - . - . - _ . _ . - - - - . _ - . . ._.-....- - .-... .. ~-
- 6 l
Ottachment A Page 4 of 5 t I
Skid Mounted Components on Diesel Generators 0, IA, and 2A Safety Qualification Item Oescription Class 1 Method 2 Comments S2O High Crankcase Pres. Alarm Sw. NT Test Only structural integrity (EMD 8362040) was checked.
- . S21 High Oil Temp. Alarm Sw. NT Test (SQ O 9025-8CW-35)
S35 Immersion Heater Temp. Control NT Test Sw. (EMD 8447102) ;
S42 Low Soakback Oil Pres. Alarm NT Test Only structural integrity l Sw. (EMO 8341873) was checked. Item not i installed, to be added per !
EMD MI 9644 lube oil mod.) i S43 Low Circ. Oil Pres. Alarm NT Test Only structural integrity Sw. (EMD 8342487) was checked. Item not'.
installed, to be added per EMD MI 9644 lube oil mod.
i SSI Pyrometer Selector Sw. NT Test Only structural integrity l (for M14) (Daven Spec. 12070) was checked. ;
I TC 1-20 Exhaust Gas Thermocouple NT Test Only structural inegrity (Alnor 1118-M) was checked. j
- Not a control or monitoring instrument l
l t . . _ . ., , , _ _ - . _ _ . , _. _ . . , , _ . _ - . . . . . _ _ . . . _ _ . , _ . _ _ , , _ _ _ . _ . . . . _ _ _ . .. . _ . _ _ _ . _ . , _ _ , . . _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . _
=
Attachment A P093 5 of 5 Skid Mounted Components on Diesel Generators 0, IA, and 2A Qualification Description Safet{
Class Method 2 Comments 3 Item Notos:
- 1. Safety Classifications
'. 1E: Safety Related - item performs a safety function NIE: Safety Related - item does not perform a safety function but its failure could adversely affect DG operation.
NT: Non-Safety Related - failure of item will not affect DG operation.
- 2. Except for items SSA and S19A, the testing was performed by SWRI, and any analysis was performed by S&L.
- 3. The qualification of item SSA and S19A was based on existing test reports from the equipment manufacturer or other testing facilities.
C886L-6*
Attachnent B Pcg3 1 cf 5 l Skid Mounted Components on Diesel Generators IB and 2B i
Safety Qualification Item Description Classl Method 2 Comments 81 Fuel Prime Pump Motor
- IE Test and Seismic qual. and (Century 8-213880-02 for DG-1B Analysis vibration aging done by and Delco C992 for DG-28) test. Rest of qual.
performed by analysis.
l o.
B4 DC Soakback Oil Pump Motor
B7 Oil Circ. Pump Motor
- IE Analysis Analysis includes a fatigue (Delco IT5727-SIA) evaluation on the long term effects of exposure to normal engine vibration.
87A AC Soakback Oil Pump Motor
- IE Test and Seismic qual. and vibration (Delco 232224C1Y27) Analysis aging done by test. _ Rest of qual. performed by .
analysis. Item not installed, to be added per EMD MI 9644 lube oil mod.
G1 2600 KW Generator
- IE Analysis Analysis includes a (Ideal 289322N) fatigue evaluation on the long term effects of exposure to normal engine vibration.
G2 Exciter * (Ideal 289324N) 1E Analysis Same as G1 G3 Generator Speed Sensor IE Test and Seismic qual, and vibration (Synchro SA-1540) Analysis aging only.
H1 Immersion Heater
- NT Test Only structural integrity (Wiegand NWH6X47) was checked.
H2 Generator Space Heater
- NT Analysis Only structural integrity (furnished with generator) was checked.
KS, K17 DC Motor Starter (for Bl&B4) 1E Test (GE CR106-SO-26-DEA)
- Not a control or monitoring instrument
l
- Attachment B Pcga 2 of 5 Skid Mounted Components on Diesel Generators IB and 28 Safet Qualification Item Description Class { Method 2 Comments l
AC Starter Relay (for HI) IE Test Qualified for 13 years K2O only. Includes associated (GE CR207-DI-02-NCA) 480 UAC circuit breaker, CB2.
IE Test Qualified for 13 years K24, K24A AC Motor Starter (for 87 & only. Includes associated B7A) (GE CR207-B1-02-FCA) 480 UAC circuit breakers, l CB3 and CB3A. K24A not installed, to be added per EMD MI 9644 lube oil mod.
Air Stract Solenoid Values IE Test L1, L2 (Salem 912-054) 1E Test and Seismic qual. and vibration L3 Governor * (Woodward 8520-311) Analysis aging done by test. Re'st of qual. performed by analysis.
NT Test M13 Tachometer (GE 50-2503OOFAFA1)
NT Test Only structural integrity M14 Pyrometer (for exhaust gas) was checked. ,
(Alnor FND-31)
NT Analysis Only structural integrity RTD 1-6 Gen. Stator Temp. Sensors was checked.
(furnished with gen)
- Not a control or monitoring instrument l
l I
l
' Pcg2 3 cf 5
- Attcchment B Skid Mounted Compcnents on Diesel Generators 18 and 28 Safet Qualification Item Description Class Method 2 Comments S6 Cranking Lockout Switch IE Test (SQ D 9012-ACH-25)
'. C8 Engine Overspeed switch IE Test (EMD 8422449)
S9 Low Oil Pres. Shutdown Sw. NIE Test (SQ D 9012-ACW-1)
S10 Low Oil Pres. Alarm Sw. NT Test (SQ D 9012-ACW-1)
S11 High Water Temp. Shutdown NIE Test Sw. (EMD 8447099)
High Water Temp. Alarm NT Test Only structural integrity S12 was checked.
Sw. (EMD 8449678)
S13,S13A Low Air Pres. Alarm Sw. NT Test (SQ D 9012-ACW-2)
SIG Low Oil Temp. Alarm Sw. NT Test (EMD 8369218)
S16 Low Water Level Alarm Sw. NT Test (Murphy El-150K1)
- Not a control or monitoring instrument
Attechment B Pcg3 4 cf 5 Skid Mounted Components on Diesel Generators IB and 28 Safet Qualification Item Description Class { Method 2 Comments Test 3 Environmental qual. did not S18 Pushbutton Start Sw. for B1 NIE include vibration aging.
(GE CR29400A202D) To be relocated to engine
- o. control panel 1(2)E22-P3018.
S2O High Crankcase Pres. Alarm Sw. NT Test Only structural integrity (Static-O 12N-N66) was checked.
l S21 High Oil Temp. Alarm Sw. NT Test (SQ D 9025-BCW-35)
S22 Pushbutton Start Sw. for 84 NIE Test 3 Environmental qual. did not include vibration aging.
(GE CR2940UA2028)
To be deleted since it is l
I jumpered in the circuit.
S23 Low Service Water Pres. Alarm NT Test Sw. (SQ D 9012-ACW-2)
S230 Low Cooling Water Pres. Alarm NT Test Sw. (SQ D 9012-ACW-5)
- Not a control or monitoring instrument
,~
l l
i l
- Pcgo 5 cf 5 Ottechment B Skid Mounted Components on Diesel Generators 18 and 2B l Safety Qualification I Item Description Class i Method 2 Comments S35 Immersion Heater Temp. Control NT Test Sw. (EMD 8447102) l o, S41 Low Water Temp. Alarm Sw. NT Test (SQ D 9025-BCW-43)
S42 Low Soakback Oil Pres. Alarm NT Test Only structural integrity Sw. (EMD 8341873) was checked. Item not installed, to be added per EMD MI 9644 lube oil mod.
S43, S44 Low Fuel Oil Pres. Alarm Sw. NT Test (SQ D 9012-ACW-5)
S45 Low Circ. Oil Pres. Alarm Sw. NT Test Only structural integrity (EMD 8342487) was checked. Item not installed, to be added per EMD MI 9644 lube oil mod.
TCl-20 Exhaust Gas Thermocouple NT Test (Alnor 1118-M)
- Not a control or monitoring instrument Notos:
~
- 1. Safety Classifications IE: Safety Related - item performs a safety function NIE: Safety Related - item does not perform a safety function but its failure could adversely affect DG operation.
NT: Non-Safety Related - failure of item will not affect DG operation.
- 2. Except for items S18 and S22, the testing was performed by SWRI, and any analysis was performed by S&L.
- 3. The qualification of items S18 and S22 was based on existing test reports from the equipment manufacturer or other testing facilities.
C886L*-11