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Category:CORRESPONDENCE-LETTERS
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action ML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee ML20212K9421999-10-0505 October 1999 Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 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 SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage ML20212J0451999-09-21021 September 1999 Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr ML20212D8231999-09-20020 September 1999 Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 ML20212C6961999-09-15015 September 1999 Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211Q7961999-09-0909 September 1999 Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q6511999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 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) ML20211F8251999-08-25025 August 1999 Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65 ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20211D1491999-08-19019 August 1999 Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20210R7451999-08-13013 August 1999 Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated ML20210R9541999-08-10010 August 1999 Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M5461999-08-0606 August 1999 Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L8371999-08-0202 August 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML20210M4691999-07-30030 July 1999 Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp ML20210H4661999-07-29029 July 1999 Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period ML20196F7921999-06-24024 June 1999 Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting ML20196E7131999-06-23023 June 1999 Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20196E4821999-06-21021 June 1999 Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee 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 SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys 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) SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-125, Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl1999-06-15015 June 1999 Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl ML20195E3491999-06-0707 June 1999 Withdraws Util Requesting License Change for Plant Security Plan Rev.Licensee Will re-evaluate Situation & May Request Approval of Change in Future ML20207G1451999-06-0707 June 1999 Forwards Rev 45 to Comed Quad Cities Nuclear Power Station Security Plan.Rev Includes Changes Listed.Security Plan Is Withheld from Public Disclosure Per 10CFR73.21 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs SVP-99-105, Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 9905291999-05-20020 May 1999 Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 990529 ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB SVP-99-111, Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-05-17017 May 1999 Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions SVP-99-098, Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i)1999-05-17017 May 1999 Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i) SVP-99-099, Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval1999-05-13013 May 1999 Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval SVP-99-096, Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 19991999-05-12012 May 1999 Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 1999 05000254/LER-1999-001, Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions1999-05-12012 May 1999 Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape SVP-99-108, Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 9903301999-04-30030 April 1999 Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 990330 SVP-99-036, Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions1999-04-29029 April 1999 Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions SVP-99-088, Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B1999-04-29029 April 1999 Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 SVP-99-065, Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License1999-04-14014 April 1999 Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License SVP-99-058, Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations1999-04-14014 April 1999 Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations SVP-99-063, Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval1999-04-0909 April 1999 Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick SVP-99-057, Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re1999-04-0505 April 1999 Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) SVP-99-062, Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-03-31031 March 1999 Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period 1999-09-30
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Commonw alth Edison ound Cities Nucteer Power Statort 22710 206 Awenue North i Cordova. Innoes 61242 9740
. Telephone 309454 2241 l ,
j LWP-95-005
- January 31, 1995 l U.S. Nuclear Regulatory Cosmission 4
Document Control Desk Washington, DC 20555 J
Reference:
Quad Cities Nuclear Power Station l Docket Number 50-254, DPR-29, Unit One ,
)
Enclosed is Licensee Event Report (LER)95-001, Revision 00, for Quad Cities l Nuclear Power Station. l I This report is submitted as a voluntary report only.
There are two additional connitments being made by this letter:
- 1. The Unit-2 RCIC governor valve (2-1303A) will be disassembled, i inspected, and repaired as necessary during the next unit refuel ;
i outage (Q2R13). The inspection will focus on possible valve stem
! degradation, and will inspect sub components for suitable l
- materials, i i
j 2. A supplemental report will be issued after testing is completed to I determine the exact cause of the governor valve stem corrosion.
)
l' If there are any questions or connents cor erning this letter, please refer
, them to Nick Chrissotimos, Regulatory Assurance Administrator at 309-654-2241,
- ext. 3100.
[ Respectfully,
- COMMONWEALTH EDISON COMPANY j QUAD f CITI CLEAR POWER STATION i,
] 0Alb
! L/ . Pearce i Station Manager i
LWP/TB/sa Enclosure I cc: J. Schrage C. Miller i INPO Records Center l NRC Region III i
STMORW595.LWP 9509190073 950907 PDR ADOCK 05000254
.. . S . __ . . . . PDR
LICENSEE EVENT REPORT (LDO Form Rev. 2.0 Facday Name O). Doctet Numoer G) Pigs (3)
Quad Cities Unit One Tide (4) 0l5l0l0l0l2l5l4 1 l of l 0 l 6 l
During Unit Startup The RCIC Governor Valve Failed To Meet Expected Capabilities Due To Valve Stem Corrosion Event Date (5) LER Number (6) Report Date tt) Other Facinties invoived (8)
Monni Day Year Year Sequennal Revtsson Moora Day Year Facthry Docket Numberta)
- Number Number Names Quad Ciues Unit 2 0l5l0[0l0l2l6l5 0l1 ol2 9l5 9l5 -
0l0l1 -
0l0 0l2 0l1 9l5 0l5l0l0l0l l l
. OPERAITNO TitL1 REPORT IS SUBMJ & 4 t.D PURSUANT TO TIIE RJQUIREMENTS OF 10CFR MODE (9) (Check one or more of the foUowing) (11) 3 20.402(b) 20.405(c) 50.73(a;G)(iv) 73.7t(b) power 20.405(a)(1)(0 50.36(c)(1) 50.73(a)C)(v) 73.71(c)
LEVEL 20.405(a)(1)(10 50.36(c)G) Tother (specify 50.73(a)G)(viD
, (10) 0 l0l 0 20.405(a)(1)6iD 50.73(a)G)0) 50.73(a)C)(viiD(A) an Abstruct 20.405(a)(1)6v) 50.73(a)G)(li) 50.73(a)C)(viiD(B) below and in i 20.405(a)(1)(v) 50.73(a)G)0iD 50.73(a)C)(x) Text)
LICENSEE CONTACT FOR T111S LER (12)
NAME TELEPHON E NUMBER
-y , 7cm AREA CODE Dan Brigl. System Engineering Departmect. Ext. 3115 3l0l9 6l5l4l-l2l2l4l1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS RER)RT (13)
CAU3E 5YSTD4 (X)MPONENT MANUFACTURER REPORTABM CAU3E S YSTEM LI)MION ENT MANUFACTURER RE.PORTABM TO NPRDS TO NPRD3
- X BlN FlClVl Dl2l4l5 Y l l l l l l [
i l i I I I I i I i l i I SUPPL.IMENTAL REPOR T EXPECTED 0 4) Espasad Mosua Day Year Submmason KYE3 (If yo.. counplsse EXPECTED SUBAG3310N DATE) 70 this 05) g j i l
. AasTRAcT o is i4co .-. i.e.. .eprma e t* . %r-.- un e> o6)
ABSTRACT:
At approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 01/2/95, Unit-1 startup was in progress with the mode
- switch in startup/ hot standby. During Reactor Core Isolation Cooling (RCIC) Periodic Pump Operability Test, the governor valve would not respond to the signals coming from the system Flow Controller. The governor valve was in the full open position and remained in that position.
At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on 1/3/95 a manual Reactor Scram was initiated per procedure and an ENS phone call made at 0244 hours0.00282 days <br />0.0678 hours <br />4.034392e-4 weeks <br />9.2842e-5 months <br />.
The cause of the event was attributed to corrosion on the governor valve stem. The exact cause of the corrosion could not be determined. Corrective actions to be completed will be disassembly and inspection of the Unit-2 RCIC governor valve and issuance of a supplemental report after testing is completed to determine the exact cause of corrosion.
Corrective actions completed involved trouble shooting activities, disassembly and repair i
of the RCIC governor valve on Unit-1, procedure changes to the system vacuum pump running time, adjustment of vacuum pump settings, and operability testing of the Unit-2 RCIC system.
LER254\95\001.WPF Q ^-
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LICENSEE EVENT REPORT (LER) TEXT CONTDfUATION Porm Rev. 3.o FACILITY NAM 5 (1) DOCKET NUMBER (2) LER NUnemen (6) PAGE (3)
) Year sequeamal Revueen l Number Number Quad Cities Unit One ol5lol0l0l2l5l4 9l5 .
0l0l1 -
0l0 2 lOFl o l 6 TEXT E.s.y ladustry idenu6cauoo Symens (EI15) codes are ideau6ed in the test se [XX]
PLANT AND SYSTEM IDENTIFICATION:
) General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
i EVENT IDENTIFICATION: During Unit startup the RCIC Governor valve failed to meet expected )
- capabilities due to valve stem corrosion.
4 A. CONDITIONS PRIOR TO EVENT:
- Unit
- One Event Date: January 2, 1995 Event Time: 2124 4
Reactor Mode: 03 Mode Name: Startup Power Level: 0
- This report was initiated by Licensee Event Report Ler 254\95-001.
4 STARTUP (3) - In this position, the reactor protection scram trips, initiated by 5
condenser low vacuum and main steamline isolation valve closure are bypassed, the low pressure main steamline isolation valve closure trip is bypassed and the reactor protection system is energized, with IRM and APRM neutron monitoring system trips and control rod withdrawal interlocks in service.
1 i !
- 8. DESCRIPTION OF EVENTS:
On 01/2/95, Unit-1 startup was in progress with the mode switch in startup/ hot
- standby. The unit had entered Tech Specs 4.5.E at 1142 hours0.0132 days <br />0.317 hours <br />0.00189 weeks <br />4.34531e-4 months <br /> which specifies a 12 l hour period to complete low pressure RCIC testing following maintenance.
At approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 01/2/95, reactor pressure was at 253 psig.
During performance of " Reactor Core Isolation Cooling (RCIC) Periodic Pump Operability Test" (QCOS 1300-1) [BN] the system governor valve (1-1303A) [FCV] would not respond to the signals coming from the Flow Controller. The governor valve was in the full open position and remained in that position.
! i At 2124 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.08182e-4 months <br /> RCIC was declared inoperable and Tech Spec 3.5.E.4 was entered. This Tech Spec requires that a shutdown be initiated and that Reactor pressure be reduced to less than 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 1 At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on 1/3/95 a manual Reactor Scram was initiated and applicable I procedures were entered. An ENS phone call was made at 0244 hours0.00282 days <br />0.0678 hours <br />4.034392e-4 weeks <br />9.2842e-5 months <br />.
The Unit-2 RCIC was operability tested at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on 1/3/95 with successful results.
4 LER254\95\001.WPF d
4 UCENSEE aVENT REPORT (LER) TEXT CONTINUATION Form Aav. 2.0 I
PAcnJrY NAME (1) DOCKET NUMBER G) LER NUMBER (6) PAGE (3)
Year sequeanal Revimon Number. Nuaiber j Quad Cities Unit One 0l5l0l0l0l2l5l4 9l5 -
0l0l1 -
0l0 3 lOFl 0 l 6 mA a Emergy laduary iden 36ceuon Syseem (EII5) codes are ideen6ed ta the text as (XX]
i After governor valve disassembly under Nuclear Work Request (NWR) #Q19538, the RCIC System Engineer inspected the valve stem and associated parts on 1/4/95. The stem
- was observed to have corrosion and pitting.
l- At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on 1/5/95 the Nuclear Work Request (NWR) #Q19538 work package was j closed after reassembly of the governor valve.
$ At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on 1/5/95 the Unit-1 RCIC system was ready to be put back into service for testing. The system was successfully tested on 1/10/95 during unit startup activities.
C. CAUSE OF THE EVENT:j g. , _ _ _ _ _ _ _.
}
This event is being reported as a voluntary LER.
, 1. The primary cause of the RCIC governor valve failing was corrosion on the
! valve stem.
- The corrosion caused pitting on the governor valve stem surface area. The corrosion and pitting caused the valve to bind in the open position during surveillance testing on 01/2/95.
! 2. The exact cause of corrosion has not been determined. Possible causes of the governor valve stem corrosion could be due to materials incompatibility between the valve stem, stem washers, and the stem carbon spacers. A
{ supplemental report will be issued for this LER after further testing is j completed to determine the cause of valve stem corrosion.
The governor valve stem was made of 400 series stainless steel (SS), and the stem washers found on the repaired valve were made of a mixture of 400 and 300 series SS flat washers. The last known maintenance to the governor valve that could have introduced the mixture of stem washers was on 4/8/94.
- Additionally, the material incompatibility between the valve stem carbon spacers
- (high sulfur content) and the stem washers could have created a subsequent acidic l solution in the presence of moisture in the standby mode.
3 Recent changes in the RCIC gland seal vacuum pressure system could have contributed
- to the governor valve stem corrosion. Further testing with respect to this issue will be included in the supplemental report.-
i ;
1 a
LER254\9N01.WPF
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1-
] LICENSEE EVENT REPORT (LER) T1 Der CON 11NUATION Pons Rev. 3.0 FAm__ rTY NAME (1) Dour.I NUMBER G) LJIR NUhsm (G) FAGE0)
Year seguemmel Revueon l Number Number Quad Cities Unit One ol5l0l0lol2l5l4 9l5 Irm E. . ,y Induary idenn6cence Symem (EII5) c are idean5ed in the tem se tui ol0l1 -
0l0 4 lOFl o l 6 l
l D. SAFETY ANALYSIS:
t The safety significance of this event was minimal. The effects the failure of the 1-1303A had on the RCIC safety functions are described below.
During startup and at low pressure conditions, the 1-1303A governor valve would
! remain in the full open position. Therefore, steam would still be allowed to enter
! the turbine. At the Reactor Pressure of 253 pounds, when the test was run, turbine
! speed reached 3500 rpm which was clearly well below the overspeed trip at 5600 rpm.
Due to the governor valve not responding to the system flow controller inputs, the control room declared the RCIC system inoperable. However, at the reactor pressure during this event the RCIC system remained available to perform its design basis in
! accordance with Tech Spec limits.
i l
E. CORRECTIVE ACTIONS:
The immediate actions completed for this event are as follows; l 1. A root cause investigation team was assembled at 0700 on 1/3/95. A plan of i
action was established by the investigation team, and trouble shooting was started.
- 2. At approximately 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on 1/3/95, data from performing calibration of the RCIC Electronic to Governor Mechanical (E-GM) Control Box indicated that j it was functioning in accordance with design specs.
l 3. A Procedure Field Change (PFC) was written to stroke the 1-1301-61 Turbine
- Steam Supply valve in order to verify the interlock contact switch was l functioning properly.
+
l 4. Due to past experience, the RCIC System Engineer contacted Riverbend,
- Arkansas Nuclear, LaSalle and INPO to let them know that Quad Cities had j experienced a similar event that these stations shared. After lengthy j
discussions, the common denominator of these industry events was valve I
binding attributed to corrosion and pitting of the valve stem.
- 5. The RCIC governor valve was disassembled and inspected to determine the cause of binding.
J
- 6. A Site Engineering Servica Request (SESR) was initiated to provide guidance for the repair of the RCIC governor valve. Site Engineering and Construction 3 (SEC) concurred with the conclusion of corrosion, and supported that the 1
I gland seal vacuum be increased to 12-15 inches (back to original setting)..
LER254\95WOI.WPF 4
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LICENSEE EVFNT REPORT (LER) TEXT CONTTNUATION Form Rev. 2.0 4 EILITY NAME (1) DOCKET NUMBER G) LER NUMBER (6) PAGE (3)
Year Sequennel
. g Revision Nunner. Number j Quad Cities Unit One 0l5l0l0l0l2l5l4 9l5 -
0l0l1 .
0lo 5 lOFl o l 6 TEXT E g industry idenu6catwo System (EES) codes are idenu6ed in the text as (XXI l
- 7. The governor valve stem was sent to Comed's System Material Analysis Department (SMAD) for further analysis of the valve failure.
- 8. The RCIC governor valve was repaired with more compatible materials (400 series stem and washers), low sulphur content carbon spacers, and increased 4
' gland seal vacuum (back to the original setting of 12-15 inches). The vendor approved the valve part changes. General Electric has been notified, and does not expect this vacuum setting to adversely affect RCIC system availability.
- 9. The Materials Management bepartment adjusted the Stores Item (SI) numbers and 4 parts descriptions for the governor valve washers and carbon spacers. Th.is action will ensure that correct series material of washers and sulphur content of the spacers are indicated during future procurement of valve parts.
- 10. Changes were made to RCIC testing procedures to increase the time the gland seal vacuum pump runs from 15 minutes to 30 minutes. This action will help to reduce moisture.
1
- 11. OPEX #7022 was sent out on 1/5/95 to document this event to the industry.
The RCIC system is tested for operability monthly (QCOS 1300-1) and quarterly (QCOS 1300-5). The station has a high confidence that the Unit-2 governor valve will remain operable until it can be disassembled and inspected during the next refuel outage.
Corrective actions to be completed are as follows:
} l
- 1. The Unit-2 RCIC governor valve (2-1303A) will be disassembled, inspected and '
j repaired as necessary during the next unit refuel outage (Q2R13). The l inspection will focus on possible valve stem degradation and will inspect l subcomponents for suitable materials. (NTS #25418095001092). )
%k s- '
- 2. A supplemental report will be issued after testing is completed to determine the exact cause of the governor valve stem corrosion.
(NTS#25418095001031)
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LDt234\95W01.WPF l
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1 UCENSEE EVENT REPORT nJiR) TEXT CONTINUATION Fore Rev. 2.0
} FACILJTY NAME(1) nXa.nzT NUMBER G) LER NUnsama (6) FAGE (3) j Yeat 5equemmel Revisese
- n s., n s.,
{ o 4 cas una o ol5lololol2l5l4 9l5 -
0lol1 ol0 s s.a s " ., '- '" - y . -
Sysesas @m) c are ideen6ed in the test as (XX]
6 lOFl o l 6 l l _
i l
l 1
l F. PREVIOUS OCCURRENCE:
j A review of the Nuclear Plant Reliability Data System (NPRDS) indicted that 2 plants ;
j in the industry (LaSalle and Hatch) have experienced RCIC valve stem binding. '
i Greater review indicated a common failure mode of valve stem binding attributed to
- corrosion, and pitting sometimes in the presence of excessive moisture.
5 Operating Experiences were reviewed, indicating that Riverbend 1 experienced an RCIC turbine trip due to corrosion on the governor valve stem.
- Quad Cities LER database as far back as 1988 were reviewed. Nothing was found relevant to this event.
G. CONPONENT FAILURE DATA:
i RCIC Governing Valve, HO-1303A, was manufactured by Terry Steam Turbine Co.,
Hartford, Conn. Dresser-Rand Co., Welsville, New York has purchased the Terry Steam
! Turbine Co.
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05000265/LER-1995-001, Informs of Commitments Being Made by Ltr Re Suppl Info Concerning LER 95-001 | Informs of Commitments Being Made by Ltr Re Suppl Info Concerning LER 95-001 | | 05000254/LER-1995-001, Informs of Two Addl Commitments to Be Made Re LER 95-001,rev 0 | Informs of Two Addl Commitments to Be Made Re LER 95-001,rev 0 | | 05000265/LER-1995-003, Forwards LER 95-003 Re Shutdown Cooling Not Being Available | Forwards LER 95-003 Re Shutdown Cooling Not Being Available | | 05000254/LER-1995-004, Forwards LER 95-004.Listed Commitments Made,Including Updating Vendor Technical Manual CO099, GE Protective Relays & Accessories | Forwards LER 95-004.Listed Commitments Made,Including Updating Vendor Technical Manual CO099, GE Protective Relays & Accessories | | 05000265/LER-1995-004, Forwards LER 95-004-01 Re Condenser Vacuum Scram Switches Found Out of TS Limits Due to Apparent Setpoint Drift | Forwards LER 95-004-01 Re Condenser Vacuum Scram Switches Found Out of TS Limits Due to Apparent Setpoint Drift | | 05000265/LER-1995-006, Forwards LER 95-006-00 Re Feed Breaker for Motor Control at Switchgear Tripped from Current Overload | Forwards LER 95-006-00 Re Feed Breaker for Motor Control at Switchgear Tripped from Current Overload | |
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