|
---|
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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20065D0511990-09-17017 September 1990 Forwards Objectives & Scope of 901205 Emergency Plan Exercise ML20064A7091990-09-14014 September 1990 Forwards Endorsement 133 to Nelia Policy NF-187 & Endorsement 116 to Maelu Policy MF-54 ML20059F4891990-09-0404 September 1990 Forwards Listing of Changes,Tests & Experiments Completed During Month of Aug 1990 for Plant ML20059B9721990-08-28028 August 1990 Forwards Reactor Head & Upper Shell Insp Plan,Per 900419 Meeting.Insp Plan Does Not Encompass Uppermost shell-to- Shell Weld Due to Technological Limitations ML20059F0311990-08-27027 August 1990 Provides Schedule for Completion of Installation of Mods to Plants Reactor Water Level Instrumentation,Per Generic Ltr 84-23.Penetrations Will Be Installed During Outage 13 for Dresden & During Outage 12 for Quad-Cities ML20059E9531990-08-27027 August 1990 Forwards Summary of Fabrication History for Upper Reactor Vessel,Per 900419 Technical Meeting.Summary Indicates That Fabrication Mismatches,Considered to Be Significant for Development of Insp Plan,Identified at head-to-flange Weld ML20059C7201990-08-23023 August 1990 Forwards Effluent & Waste Disposal Semiannual Rept,Jan-June 1990 Gaseous Effluents-Summation of All Releases & Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste ML20058P3481990-08-0909 August 1990 Forwards Summary of Fuel Performance,End of Cycle 10,May 1990. No Leakage or Fuel Failure Noted ML20058M8221990-08-0707 August 1990 Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20058M8041990-08-0606 August 1990 Advises That W/Completion of Operator Training Program,Plant SPDS Meets Requirements Delineated in NUREG-0737,Suppl 1 ML20058M8591990-08-0606 August 1990 Forwards Rept of Metallurgical Exam That Revealed No Evidence of Defects,Porosity or Slag in Weld Overlay. Rept Responds to IGSCC Insp Performed on Facility IGSCC Susceptible Piping ML20058M4101990-08-0101 August 1990 Forwards Listing of Changes,Tests & Experiments Completed During Month of Jul 1990 for Plant ML20058M8291990-07-31031 July 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements of Corrective Actions. Status of Implementation of Generic Safety Issues Encl ML20055J1631990-07-26026 July 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Quad-Cities Nuclear Power Station Unit 2,900427-28, & Related Apps Describing Type a Test,Per 10CFR50,App J, Section V.B.1.Next Test Scheduled for Fall 1991 ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055G6331990-07-18018 July 1990 Responds to Generic Ltr 89-06 Re SPDS to Meet Requirements of Suppl 1 to NUREG-0737.SPDS Lesson Plan Incorporated Into Initial License Class Training Program 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. ML20055D4741990-06-29029 June 1990 Forwards Annual FSAR Update for Quad-Cities Station ML20055D4341990-06-29029 June 1990 Forwards Comm Ed Rept on Evaluation of Cracking in Quad- Cities Unit 2 Reactor Head, Per Commitment Made at 900419 Meeting W/Nrr.Rept Concludes That Cracks Caused by Interdendritic Stress Corrosion Cracking Mechanism ML20055C8551990-06-15015 June 1990 Forwards Special Neutron Attenuation Test for High Density Spent Fuel Racks (Wet), Final Rept.Rept Provides Results of Neutron Radioassay Measurement Program Conducted During Fall,1989 Refueling Outage ML20043D7661990-06-0404 June 1990 Responds to J Lieberman 900501 Ltr Re Rl Dickherber. Confidence in Dickherber Performance in Future for Nonlicensed Duties Can Be Based Upon Demonstrated Record of Good Past Performance ML20043D7691990-06-0404 June 1990 Responds to 900501 Ltr Re Work Hours for Dickherber.During Outage,Dickherber Worked Extended Hours Traditionally Associated W/Refueling Activities ML20043G4251990-06-0202 June 1990 Forwards Listing of Changes,Tests & Experiments Completed During May 1990 ML20043D3201990-06-0101 June 1990 Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043B6681990-05-22022 May 1990 Forwards Proposed Changes to SER Re Hot Shutdown Repairs in Event of Fire,Per 10CFR50,App R Section Iii.G Covering Spurious Operations & High Impedance Faults & Electrical Isolation Deficiency ML20043A4681990-05-10010 May 1990 Forwards Proposed Changes to 880721 SER Re App R Section Iii.G Exemption for Fire Zones 1.1.1.1S & 1.1.1.2,southern & Northern Torus Level in Unit 1 Reactor Bldg Column & Unit 1 Reactor Bldg Elevations 623 Ft & 647 Ft ML20042H0011990-05-0303 May 1990 Forwards Listing of Changes,Tests, & Experiments Completed During Apr 1990 ML20042G3501990-05-0202 May 1990 Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-254/90-02 & 50-265/90-02.Corrective Actions:Continuous Fire Watch Initiated & Training Conducted on Procedure Rev ML20042F1181990-05-0101 May 1990 Advises of Listed Value for Secondary Containment,Per NRC Request for Addl Info Re LER 50-254/87-025.Value Based on Info Contained in Plant FSAR ML20042F0691990-05-0101 May 1990 Responds to Generic Ltr 83-28,Item 4.5.3 Re Reactor Protection Sys on-line Functional Test Intervals.Endorses Two BWR Owners Group Topical Repts NEDC-30844 & NEDC-30851P Generic Evaluations ML20042F1221990-05-0101 May 1990 Forwards Preliminary Rept of IGSCC Insp Results.Flaw Indication Detected in Weld Overlay Matl of Weld 02J-S3 & Removed by Boat Sample & Std Weld Overlay Thickness Restored.Final Rept Will Be Forwarded within 30 Days ML20042E4491990-04-11011 April 1990 Forwards Request for Rev to Previous NRC Exemption Approval on 860625 Re Combustible Load Values ML20042F0351990-03-23023 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML19330D5161990-03-14014 March 1990 Advises That Revs to Inservice Testing Program & Implementation Procedures Will Be Completed by 900629,per Generic Ltr 89-04 ML20012C0721990-03-0808 March 1990 Comments on SALP Board Repts 50-254/89-01 & 50-265/89-01 for Oct 1988 to Nov 1989.Util Appreciates NRC Recognition of Overall Improvements in Areas of Operation & Emergency Preparedness & Good Performance in Area of Security ML20012B5921990-03-0202 March 1990 Forwards Listing of Changes,Tests & Experiments Computed During Month of Feb 1990 for Plant ML20006F3361990-02-0808 February 1990 Responds to NRC Ltr 900110 Ltr Re Violations Noted in Insp Repts 50-254/89-25 & 50-265/89-25.Corrective Actions:Safety Evaluations Submitted Via 900116 Ltr & Table of Content Will Be Completed for 1989 FSAR Update to Be Submitted by 900630 ML20012A9551990-02-0808 February 1990 Responds to Violations Noted in Insp Repts 50-254/89-26 & 50-265/89-26.Corrective Action:Procedure Qis 47-1 Revised to Include Requirement That Equalizing Valve Be Open During Isolation of Transmitter ML20011E7131990-02-0606 February 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test,Quad Cities Nuclear Power Station,Unit 1,891114-15. Next Type a Test Scheduled for Fall 1990 ML20006E1721990-02-0202 February 1990 Forwards Listing of Changes,Tests & Experiments Completed During Jan 1990,including Items Completed in 1989. Interlocks Installed on Refuel Bridge Fuel Handling Machine to Prevent Raising Hoist While Hoist Loaded ML20006C5071990-01-30030 January 1990 Identifies Schedular Change for Completion of Corrective Actions Associated W/Human Engineering Deficiencies 159,187 & 489 Re Escutcheon Plates for Control Switches Which Need Replacement.Plates Will Be Replaced During Outages ML20006C7401990-01-22022 January 1990 Advises of Receipt of Accreditation Renewal by INPO in Sept 1989 for Operator Requalification Training Program,Per Generic Ltr 87-07 Requirements & Informs That Programs Developed Using Systematic Approach to Training ML19354E8591990-01-16016 January 1990 Responds to NRC 891128 Ltr Re Violations Noted in Insp Repts 50-254/89-17 & 50-265/89-17.Corrective Actions:Procedure NSWP-E-01, Electrical Cable Installation Insp, Will Be Revised to Enhance Human Factor Aspect ML19354D8131990-01-11011 January 1990 Forwards Corrected App C to Monthly Operating Rept for Dec 1989 for Quad Cities Units 1 & 2 ML20005F6441990-01-0303 January 1990 Forwards Listing of Changes,Tests & Experiments Completed During Dec 1989.Summary of Safety Evaluations Being Reported in Compliance w/10CFR50.59 & 10CFR50.71(e) Also Encl ML20005E1691989-12-22022 December 1989 Forwards Rev 22 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facility.Rev Withheld (Ref 10CFR73.21) ML20043A5741989-12-21021 December 1989 Responds to NRC 891124 Ltr Re Violations Noted in Insp Repts 50-254/89-23 & 50-265/89-23.Corrective Actions:Compressed Gas Cylinder Bottles Secured W/Chain & Fire Marshall Will Increase Tours of Plant Re Transient Combustible Matl ML20005E1211989-12-18018 December 1989 Forwards Final Rept of Fall 1989 IGSCC Insp Plan,Discussing Items Such as Overlay Repair on Weld 02G-S4,mechanical Stress Improvement & Piping Mods ML19332G3401989-12-0808 December 1989 Forwards Response to Generic Ltr 89-21, Implementation Status of USI Requirements. Actions to Resolve USI A-9 Re ATWS Will Be Completed in June 1990 & USI A-42 Re Pipe Cracks in BWRs Will Be Completed in Dec 1990 ML19332F9091989-12-0101 December 1989 Forwards Listing of Changes,Tests & Experiments Completed During Nov 1989 1990-09-04
[Table view] |
LER-2085-007, Responds to NRC Re Violations Noted in Insp Rept 50-265/85-18.Corrective Actions:Four Pressure Transmitters Will Be Returned to Original Configuration by 851031 & Work Request Sys Revised.Rev 1 to LER 85-007 Encl |
Event date: |
|
---|
Report date: |
|
---|
2652085007R00 - NRC Website |
|
text
l P~(
4 Commonwealth Edison One First N:tioncsl Pirza, Chicrgo. Illinotjs Address Reply to. Post Office Box 767 Checago. filinois 60690 August 2, 1985 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 [
\
Subject:
Quad Cities Station Unit 2 Response to Items of Noncompliance in I.E. Inspection Report No. 50-265/85018
Reference:
R. L. Spessard letter to Cordell Reed dated July 5, 1985.
Dear Mr. Keppler:
The reference provided results of a routine safety inspection g conducted by Messrs. D. S. Butler and S. M. Hare of your office during the \
period of May 25 through June 24, 1985 of activities at Quad Cities Nuclear Power Station Unit 2.
During the course of that inspection, certain activities appeared to be in noncompliance with tEC requirements. Attachment I to this letter contains our response to the Item of Noncompliance.
In addition, your letter requested a response to Unresolved Item No.
265/85018-04 regarding leaking containment isolation valves. Attachment 2 provides a copy of Revision 1 to Licensee Event Report 85-007 which contains the information requested in your letter.
Very truly yours,
/
L. O. DelGeorge u
Assistant Vice President im cc: NRC Resident Inspector - Quad Cities Attachments 8508160042 850802 51985 PDR ADOCK 05000265 G PDR ,
I 0448K ,l
/N t
9
, 5
.?
,-s
.+,
RESPONSE TO NOTICE OF VIOLATION s
T g
4 i,
W 3 , . . _ _ , - - - - - ---- - -
l
, < l 1
COMMONWEALTH EDISON COMPANY l l
RESPONSE TO NOTICE OF VIOLATION As a result of an inspection conducted during May and June of 1985, the following violation was identified:
10 CFR 50, Appendix B, Criterion XVIII requires in part that sufficient recoros shall be maintained to furnish evloence of activities affecting quality and that they be identified and retrievable. 10 CFR 50, Appendix B, Criteria III requires in part that design changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and approved by the responsible organization.
Contrary to the above, six safety-related pressure transmitters were modified between April and May, 1979, without adequate documentation and approval. In addition, external calibration Jacks and a calibration test resistor were installeo without implementing required design controls.
DISCUSSION Test Jacks with one ohm precision resistors were installed at Quad-Cities in instruments in the late 1970's to facilitate normal calibration checks and recalibrations. Most instrument models at that time came from the manufacturer with resistors already installed for calioration purposes.
This allowed calibration without removing the instrument cover and breaking the internal current loop to install a test resistor in the internal wiring. Pressure transmitters, supplied by Rosemount Inc., were delivered with a diode installed in series with the current loop that could be used to measure the current in the loop with an ampere meter.
Testing equipment used by the Instrument Maintenance Department during the late 1970's did not include an ampere meter function. Since it was not possible to use the diode in the loop to measure the current, and since the installation of a resistor in a current loop in no way affects the design intent of a current loop, a precision resistor was installed in series in the current loop. This allowed the ability to measure the voltage drop across the resistor and the calculation of the current in the loop. The actual voltage drop around the entire loop in no way affects the function or cesign of the pressure transmitter. All failure modes of the resistor will have no affect on the safe operation of the pressure transmitter. A short across the resistor will not change the value of the current in the current loop. An open circuit failure of the resistor will cause a zero value for current and cause a trip of the pressure transmitter trip unit. The addition of the test jacks and resistor poses no problems with respect to overall reliability or safety. Twenty-two of these units have been in service for many years and none have ever failed or caused any problems associated with calibration. Table I lists all the applications where these resistors have been installed. Only four of the installations are used in safety-related applications.
The interpretation of the threshold of routine maintenance which constitutes a design change is always subject to change. During the late 1970's when these installations were performed, it was determined that this work did not constitute a design change. As the interpretation of the design change threshold has evolved over the years, the Station finds itself accountable for decisions maoe without post TMI hindsignr.
CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED Since the date of the occurrence, the Commonwealth Edison Nuclear Work Request System has evolved to match the pace of changing interpretations.
Currently each work request is scrutinized to preclude the classification of design changes as routine maintenance. We therefore feel that changes in practice to resolve this concern have already been implemented. In order to assure continuing compliance, the following step will be taken:
- 1) The four safety-related classified pressure transmitters in which test facilities were added, will be returned to their original configuration by the removal of the test jacks and precision resistors. This will be accomplished by October 31, 1985.
CORRECTIVE ACTION TAKEN TO AVOID FURTHER NONCOMPLIANCE As described above, enhancements in the Work Request System implemented since 1979 are sufficient to prevent further noncompliances.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED As stated previously, full compliance will be achieved by October 31, 1985 when the four safety-related classified pressure transmitters will be returned to their original configuration.
0448K
^&
TABLE I
. Instrument' Test Jack List
~EPN SYSTEM USE CLASSIFICATION 2-261-5 A/B Recirc Pump DP Non-safety Related 1-1602-8 8 Press Sup Torus Level Non-safety Related 1-1602-9 B Press Sup Torus Press Non-safety Related s
'2-1602-8 B Press Sup Torus Level Non-safety Related 1-5441-31 AA Off Gas Condenser Level . Non-safety Related 1-8941-418 HRSS Waste Tank Level Non-safety Related 1-8941-419 HRSS Waste Tank Level Non-safety Related 2-8941-418 HRSS Waste Tank Level Non-safety Related 2-8941-419' HRSS Waste Tank Level Non-safety Related 1-645 D Feed Water Steam Flow Non-safety Related 1-646 B Feed Water Rx Level Non-safety Related 2-645 A/D Feed Water Steam Flow Non-safety Related 2-2541-11 A/B ACAD D.W. Press Safety Related 2-2541-12 A/B ACAD D.W. Press Safety Related 2-2541-8 A/B ACAD Dllution Alr Press Non-safety Related
=
45rven
cf--
e g
ATTACHENT 2 RESPONSE TO UNRESOLVED ITEM 265/85018-04(DRS) l- -- m
Commonwealth Edison ound Cition Nuclear Power Station 22710 206 Avenue North Cordova, ll!!nois 61242 Telephone 309/654-2241 NJK-85-193 July 15, 1985 U.S. Nuclear Regulatory Commission Document Control Desk Hashington, D.C. 20555
Reference:
Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Enclosed please find Licensee Event Report (LER)85-007, Revision 01, for Quad Cities Nuclear Power Station.
This report is submitted to you in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73 (a)(2)(ll), which requires reporting of any event or condition that resulted in the condition of the nuclear power plant, including its principle safety barrier, being seriously degraded.
The original Licensee Event Report (LER)85-007 stated that the Local Leak ,
Rate Testing (LLRT) program had found leakage in excess of Technical l Specification limits, but did not provide a complete summary pending completion of the testing program and corrective actions. This report addresses all valves and penetrations that had repairs performed to reduce the leakage total to within the Technical Specification limit.
Respectfully, l l
COMMONNEALTH EDISON COMP Y Quad Cities Nuclear P e Station N. J. Kallvianakis I
Station Manager NJK/eem/e ,
Encl.
cc: J. Hojnarowski # j'~/ * ] ; % M A. Madison INPO Records Center c)//y.
NRC Region III 0257H/0136Z
4 ,
EVENT DESCRIPTION During the Unit Two end of cycle seven refueling outage, the following valves required repairs or adjustments (RA's). Note that some of the RA's were not due to excessive leakage, but were the result of preventative maintenance or modifications. The valve leakage before and after the RA's and an explanation of the work performed is provided in Table 1. For valves where the RA's were initiated due to local leak rate test (LLRT) results, notes are shown in the comment section with details provided in the corrective action section of this report.
I
_1_
0257H/0136Z
LEAKAGE (SCFH) .
- DESCRIPi10N VALVE NO. COMPONENT DESCRIP..ON AS FOU W AS LEFT CORAENTS t e 1 Main Steam Line Drain M0 2-220-1 Crane 3" Gate Valve 75.50 6.42(c) Note 1, Table 2 as Left ,
Leakage (7830) is Total for 220-1,2 Main Steam Line Drain M0 2-220-2 Limitorque Type She 40.20 Note 2, Table 2 "A" Reactor Feedwater CV 220-58A Crane Tilting Disc CV 1921.66 16.00 Note 3, Table 2 "B" Reactor Feedwater CV 220-62B Same as Above 789.50 5.42 Note 4, Table 2
- "A" Drywell Spray M0 2-1001-23A 0.63(c) 0.84(c) New EQ Limitorque
- and 26A Operators installed
(
l "A" RHR Return M0 2-1001-29A 4.50 9.00 New EQ Limitorque Operators Installed i
! "B" Drywell Spray M0 2-1001-23B 15.12(c) 15.67(c) l'ew EQ Limitorque l
and 268 Operators installed 1
i "B" RHR Return MD 2-1001-29B 4.14 4.14 New EO Limitorque Operators Installed
. RCIC Steam Supply MO 2-1301-16,17 4.10(c) 2.00(c) New EQ Limitorque l
Operators Installed
! Dry =oll/ Torus Purge A0 1601-23 Pratt 18" Butterfly 342.00(c) 0.00(c) Note 5, A0-1601-23, j Exhiust (D 1200G) 24,60,61,62,63 valves Test as one Volume i Drywell/ Torus Purge A0 1601-24 Same as Above Note 5, Table 2 Exh:ust i Dry ell / Purge A0 1601-60 Same as Above Note 5, Table 2 j Exhrust (D 1200G)
! Dry =oll/ Purge A0 1601-63 Pratt 6" Butterfly Note 5 j Exhaust (D 1200G) t J
0258H
TABLE 1 (Cor*inu'ed) LEAKAGE (SCFH)
DESCRif JN VALVE NO. COW 0hENT DESCRIP- N_
AS FOUW AS LEFT CO M NTS .'
"B" Terus Vent A0 1601-20B Prctt 20" Buttcrfly 13.99(c) 13.99(c) Noto 6, Tabla 2 .
CV 1601-31B ,
HPCI Steam Exhaust CV 2301-45 24" Mission Duo Check 33.80 0.00 Note 7, Table 2 HPCI Drain Pot Exh. CV 2301-34 2" Kerotest Lift Check 14.20 12.50 Note 8, Table 2 0xygen Analyzer A0 8801C Blaw Knox 3/4" Globe 36.50 13.00 Note 9, Table 2 Valve Oxygen Analyzer A0 8802C Same As Above 9.70 6.50 Note 10, Table 2 0xygen Analyzer A0 8804 Same as Above 6.50 3.50 Note 11, Table 2 TIP Ball Valve 737-1 General Pneumatics Corp 0.25 0.80 Retested after 608 KWJ06-3 Preventative Maintenance TIP Ball Valve 737-2 Same as Above 0.40 0.80 Retested After Preventative Maintenance TIP Ball Valve 737-3 Same as Above 0.10 1.30 Retested After Preventative Maintenance TIP Ball Valve 737-4 Same as Above 0.00 0.30 Retested After Preventative Maintenance TIP Ball Valve 737-5 Same as Above 1.70 0.50 Note 12, Table 2 ACAD System A0 2599-2A 1" A0 Gate Valve 7.80 2.30 Note 13, Table 2 WKM Valve Div., ACF Ind.
ACAD System A0 2599-4B Same as Above 6.50 0.90 Note 14, Table 2 CAM System SO 2499-1A Target Rock 1/2-SMS-S 0.00 0.00 EO Valve Modification j CAM System SO 2490-2A Same as Above 0.00 0.00 EO Valve Modification CAM System SO 2499-18 Same as Above 0.00 0.00 EO Valve Modification CAM System SO 2499-28 Same as Above 0.00 0.00 EQ Valve Modification Core Spray X-16B Metal Bellows 0.00 0.00 Outer Test Bellows Added i
P;natration (Inner Bellows Replaced Last Outage) 0258H .
i CAUSE The first step to a good corrective action or maintenance program is to determine why the valve in question leaked. The answer to that question is not always obvious when dealing with valves that are sometimes quite large or when the air leakages are small but require repair due to regulatory limitations. At Quad Cities, we believe that we have a good program for diagnosing valve problems and facilitating repairs through the use of Station Procedure QhP 800-18 and the checklist QMP 800-S15. When any safety related and/or primary containment isolation valve is disassembled, a Quality Control inspector performs a thorough inspection of the valve in order to determine the root cause of the valve leakage (or any other problems mandating the repair). An additional inspection is performed during re-assembly of the valve. A copy of the procedure and checklist is included in Appendix A. He believe that this method of diagnostics and control on these types of repairs meet or exceed any prevailing standard within the industry.
In addition, Quad Cities maintains on file the LLRT results for every primary containment isolation valve and penetration dating back to plant startup and trends those results. The station's willingness to repair valves or penetrations that exhibit low, but equipment specific high or increasing leakages over past LLRT results, demonstrates a sincere effort to meet the requirements of 10 CFR 50, Appendix J.
Because of the stringent testing requirements of the above regulation and problems encountered industry-wide in meeting those requirements, the corrective action portion of this report has been prepared to identify
" chronic" problems experienced at Quad-Cities. Actions taken in the past and future plans are discussed.
The specific action taken this refuel outage on all valves with RA's due to LLRT leakage is given below in Table 2. The note numbers can be referenced back to Table I to identify the valves.
0257H/0136Z
Notn No. Div.JSSION -
1 Work Request No. 041003. Repairs to this valve included cleaning the internals of rust-like dirt and lap- ~
ping the seat.
Leakage History:
07/26/71 0.00 SCFH(c) 01/18/75 0.00 (c) 10/17/75 1.70 (c) 09/11/76 5.42 (c) 01/15/78 6.55 (c) 11/26/79 1.72 01/23/80 8.45 (c) 09/07/81 66.30 12/23/81 8.63 (c) 09/05/83 39.27 (c) 01/12/84 07.46 (c) 03/17/85 75.50 05/21/85 6.42 (c)
Note: (c) = combined leakage of both 220-1 valve and the 220-2 valve.
Conclusion:
While this valve performed well for the first 10 years of plant operation, chronic problems with valve leakage have been experienced recently. Reference the corrective action section of this report.
2 Work Requests No. 039984 and 041911. During operation, this valve had a small steam leak from the bonnet seal ring that only leaked when the MD 2-220-1 was open. After the as found LLRT, this valve was disassembled, inspected, and cleaned with no observed defects that would explain the through leakage.
Subsequent LLRT showed little improvement in leakage. Subsequent investigation determined that Limitorque operator was not closing the valve completely and that torque switch setting could be increased. This corrective action eliminated most of the valve leakage.
Conclusion:
Valve inspection and corrective action required do not indicate that this valve has a chronic problem requiring further corrective action at this time.
0258H
l Noto No. DISCUSSION
- 3 Work Request No. 041492. No problems were found with seat or seals. Valve was disassembled and put back .
together with new o-rings on disc / seat assembly and seal ring. One of the hold down clamp set screws had 4
a cracked tack weld but no probable affect on valve leakage.
Leakage History:
l 07/13/71 4.60 SCFH 12/30/74 97.00
! 02/08/75 8.80 l 10/12/76 1.70 10/19/76 0.00 02/03/78 1.56
- 12/26/79 Could Not Pressurize
, 01/16/80 7.80 j 09/21/81 1.03 j 10/05/83 267.30 1 01/09/84 0.52
! 04/10/85 1921.66 2 05/04/85 16.00 l
Conclusion:
The feedwater check valves are large, 18" check valves on the feedwater lincs and
! have an erratic test history. The main reason for this is that the valve does not seat when tested with 48 PSIG of air. All feedwater check valves are considered a chronic problem. Reference the corrective action section of this report.
0258H
. . . ..ued )
Notq No. Dis,,sSS10N -
4 Work Request No. 041492. This valve was found to have a hinge pin missing even though the set screw, lock '
nut, and tack weld to hold the hinge pin were still in place. Future valve repairs will include modifications to better secure the hinge pins. This is the first failure of this kind at Quad Cities.
Subsequent repairs to the valve to make it leak tight included machining a slight valley out of the valve body where the seat ring is clamped down.
Leakage History:
08/21/71 7.50 SCFH 12/30/74 2647.00 02/18/75 1.36 09/14/76 811.00 10/11/76 6.78 01/17/78 Unable to Pressurize
- 03/02/78 16.50 11/27/79 406.80 01/28/80 14.90 09/17/81 1018.00 l 11/13/81 13.60
! 09/14/83 362.00 '
1 12/30/83 23.50
. 03/22/85 789.50 05/31/85 5.42 i
Conclusions:
Same as for CV 220-58A i
i i
0258H
~ lflilflTIMETUT555]D ,
Noto No. u.oCUSSION -
~
5 Work Request No. 041926 Replaced A0 1601-23
- Work Request No. 042341 Replaced A0 1601-24 Work Request No. 041927 Replaced A0 1601-60 Work Request No. 042345 Replaced A0 1601-63 Leakage History: Volume Boundary - A0 1601-23, 24, 60, 61, 62, 63 08/24/71 3.20 SCFH 08/22/72 0.70 04/16/73 11.25 10/18/73 4.55 10/03/76 0.00 02/25/78 12.52 12/05/79 27.00 02/12/80 18.00 10/18/81 17.99 09/30/83 9.00 04/29/85 342.00 05/24/85 0.00
Conclusions:
The above valves all have vulcanized rubber seats and are Pratt butterfly valves.
Inspections on disassembly revealed that all of the valves were dirty and the seats were hard and non-resilient. These valves were original equipment from when the plant was built (1971).
The 23-valve was disassembled and cleaned in February, 1980. The 24-valve was disassembled and cleaned in April, 1981. This is the only maintenance performed on the internal seating surfaces of these valves since plant startup. While the valves 9 ave little warning of impending failure (excessive leakage), the inspections showed that the seating surfaces were at the end of their useful life. The valves were replaced with new valves and the old ones will be decontaminated and sent out for-seat replacement (re-vulcanizing).
The leak rate history shows that these valves do not constitute a chronic problem.
The fact that so many valves (4) failed simultaneously is, however, reason for concern. Reference the corrective action section of this report.
0258H
TAtsLE 2 (Continued) .
Noto No. o AUSSION 6 Work Request No. 41665. CV 1601-318 was disassembled and cleaned. Was found to be dirty. A0 1601-208 ~
had packing on shaft replaced.
Leakage History:
08/19/71 0.08 SCFH 04/16/73 1.91 10/17/73 0.00 01/28/75 0.00 09/12/76 2.29 01/18/78 110.74 02/15/78 0.73 12/03/79 0.76 09/23/81 19.90 09/30/81 10.70 09/12/83 07.10 03/23/85 13.99 05/30/85 13 99
Conclusions:
Repairs performed did not reduce leakage from the volume. Probable source of leakage is through A0 1601-208. This is a rubber seated Pratt butterfly valve. While no chronic problem has been experienced with this valve, reference the corrective action section of this report.
0258H
. - _. _~ - . - _ .
' TABLE 2 (Continued)
Nota No. b.dCUSSION 7 Work Request No. 042118 and Modification M-4-2-85-27. .
This valve is a TRW Mission Duo Chek on the HPCI turbine exhaust. The inspection on this valve showed damage to tho rubber seat and a bent stop pin. The valve was new in October, 1981. The valve was replaced this outage with a nearly identical valve.
Leakage History:
i 07/21/71 2.20 SCFH 01/30/75 0.40 09/13/76 57.23 10/13/76 0.00 01/16/78 1.56 i 11/26/79 16.90
! 09/08/81 165.00 10/06/81 12.04 09/05/83 0.00 03/18/85 33.80 05/23/85 0.00 I
Conclusions:
The life expectancy of this valve appears to be approximately 3 cycles. Because of the severe damage found during valve inspections and problems encountered in the industry with these valves used for this application, this is considered a chronic problem. Reference the corrective action section of this report.
i 1
i 1 l
0258H
{
~' ^' ~ - -- "
TABLE'2 (Continued)
Noto No. DISCUSS 16.
- 8 Work Request No. 041548. Modification M-4-2-85-19. ,
While this valve has not had a bad LLRT performance, maintenance records showed that the valve did not have much stelIite left on its seat from previous seat lapping repairs. Since the valve leakage did increase over previous values, the decision was made to replace the valve. ,
Leakage History:
12/31/70 0.19 SCFH
! 04/15/74 0.41 01/04/76 0.26 03/22/77 0.00 01/19/79 1.90 08/31/80 4.50 09/09/82 0.00 03/08/84 0.00 03/18/85 14.20 06/02/85 12.50
Conclusions:
The leakage history of this valve does not indicate a chronic problem with leakage.
The new valve, a Kerotest lift check valve, exhibited some leakage when installed.
The performance of this new valve will be carefully trended.
l 0258H
TABLE 2 (C< inued) ,
Note No. DISCUSS 10N ,-
9 Work Requests No. 041308 and 042167.
The valve was originally found to have very dirty (rusty) internals with a piece of paper or gasket-material across the seat. Cleaning the valve and seat surfaces reduced the leakage from 36.5 to 17.0 SCFH. The valve was disassembled again and the seat surface lapped reducing the leakage to its final value.
l Leakage History:
i 01/02/75 1.49 SCFH (c) 09/16/76 1.20 01/18/78 10.50 12/06/79 11.00 09/29/81 4.40 10/03/83 6.00 03/29/85 36.50 05/21/85 11.00
Conclusions:
These oxygen analyzer valves do not represent a serious source of containment leakage because the lines go to a sample rack and are manually isolated at this point. In fact, recent changes to the containment monitoring systems (CAM and HRSS) have made the lines with A0 8801-1, 2A and A0 8801-1, 28 and A0 8801-1,20, obsolete and no longer used. A modification will be started to remove these valves and cap the lines.
i 0258H
~ ' ~ ~ '
TABLE 2 (' Continued) ~ .
Note No. L. A SSION Work Request No. 041309 10 ,
This valve was found to have dirty internals with a rust-like build up. It was cleaned and re-assembled.
1 Leakage History:
01/02/75 1.49 SCFH (c) 09/16/76 13.00 01/18/78 >30 (limit of fIowmeter)
- 02/09/78 0.05 12/06/79 0.60 09/29/81 0.40
! 10/03/83 16.00 11/29/83 1.40 03/29/85 9.70 05/03/85 6.50
Conclusions:
Same as for Note 9 above.
l 11 Work Requests No. 041307 and 042167.
i On the first Work Request, the valve was cleaned of dirty, rust-like material. Subsequent to reassembly, the leakage rate increased slightly. On re-inspection, small scratches on the valve seat were observed.
The seat was lapped and the leakage was reduced to its final value.
- Leakage History
01/28/75 3.87 SCFH
! 09/27/76 4.00 01/30/78 3.90 12/06/79 2.90 10/01/81 9.50 10/14/83 10.00 03/29/85 6.50 j 05/22/85 3.50
Conclusions:
This valve does not have a chronic problem. No further action is required.
i i
j :
l
] 0258H
TABLE 2 (Continued)
Nota No. L.oCUSSION 12 After preventative maintenance, consisting of cleaning valve internals and replacing / lubricating valve .
seals and 0-rings, the leakage of this valve increased from 1.70 to 4.00 SCFH. Since this is an unusually large leakage for these valves, it was replaced with a new valve.
Leakage History:
01/26/78 0.80 SCFH 12/05/79 0.10 09/25/81 0.00 02/02/83 0.00 i
11/07/83 4.50 03/21/85 1.70 i 06/02/85 0.50
Conclusions:
No chronic problems, no further action required.
l 13 Work Request No. 041662 On disassembly, the bonnet to body gasket was discovered to be improperly installed allowing some slight leakage. Valves had not been worked on since their original installation in 1980.
Leakage History:
02/29/80 0.00 SCFH (c) 09/28/81 0.20 (c) 10/07/83 5.00 04/01/85 7.80 05/03/85 2.30 l
Conclusions:
This is not a chronic problem and no further action is required.
l 1
14 Work Request No. 041663 1
Rust and dirt was cleaned from the internals of this valve. In addition, the body-to-bonnet gasket was found to be improperly installed (same as 13 above)
I
)
l 4 1 0258H I
Notn No. L. M ION .~
4 Leakage History:
02/29/80 0.00 SCFH (c) 09/28/81 Unable to Pressurize 12/18/81 9.50 09/23/83 6.50 04/02/85 6.50 05/03/85 0.90
Conclusions:
The leakage from this valve had been nearly constant since 1981. Valve would appear to be tight now. No further action would seem required at this time.
0258H
' CORRECTIVE ACTION The immediate action taken for many of the RA's is sufficient corrective action because the leakages involved were small and no pattern of chronic failure exists. The items of special concern, however, are valves that have a history of excessive leakage and/or large leakage rates. These problems are identified as follows:
- 1) Main steam line drain valve 220-1;
- 2) All feedwater check valves 220-58A, B; 220-62A,8;
- 3) Drywell purge butterfly valves 1601-23, 24, 60, 61, 62, 63;
- 4) HPCI Steam exhaust 2301-45.
The above problems will be discussed in detail here concerning future corrective actions required to prevent further re-occurrences.
MAIN STEAM LINE DRAIN VALVE (220-1)
As noted from the leakage history of this valve, the valve performed reasonably well for the first 10 years of plant operation. Since 1981, however, this valve has caused problems requiring repair each refuel outage.
During the 1983 refuel outage, fairly extensive repairs were performed by replacing the valve disc and disc guide, as well as lapping the seat. The following additional actions are warranted at this time:
- 1) Replace the valve during the next refuel outage;
- 2) Investigate a better valve for this application (e.g. a globe type valve instead of a gate valve);
- 3) Investigate the possibility of relocating this valve in the drywell (under the steam lines) to a location that would make future repairs easier to perform and possible result in less dirt or rust being deposited on valve internals.
ALL FEEDWATER CHECK VALVES (220-58A, B: 220-62A, 8)
The failure of these valves to give good LLRT results is well documented at Quad Cities and at other stations throughout the industry. While modifications have been performed to reduce the potential of valve leakaga (e.g. modifications to the disc / seat assembly seals and hold down clamps),
the primary problem continues to be that these valves are intended to isolate a high pressure water line and we are testing them with low pressure air. The test method does not include a way to firmly seat the disc prior to testing.
The testing does not simulate either normal operating or accident conditions that would act to seat these valves, and normally the feedwater lines would not act as a leakage path because they are water filled.
0257H/0136Z
. . While other stations, with NRC approval, have attempted to use water and/or water / air oixtures to seat the valves prior to testing with air, Quad Cities has not found this technique to be effective. The quantity of water that can be introduced into an 18-inch line through a 1-inch test tap does not seem to affect closure of the valve, and at times can be counter-productive by washing rust and dirt into the seat. The water velocity that can be developed seems inadequate to either move the disc or keep the surface free of crud.
While the station continues in its efforts to develop a better maintenance program and test procedure for this valve, we believe that the problem is to a great extent generic with these particular valves. Unfortunately, recent industry experience with a newly designed dual seat valve offered by Anchor Darling Corp. has not been totally successful as documented in NRC IE Bulletins.
The station has initiated an Action Item Request (AIR NO. 85-12) to Station Nuclear Engineering Department (SNED) to investigate this problem and determine a solution.
DRYWELL PURGE BUTTERFLY VALVES As stated in the previous section, the vai.'es that developed excessive leakage have a history of good performance. The concern of the station, however, is that these valves, because of their soft rubber seats, might be reaching the end of their useful life in terms of the vulcanized seat material. There are a number of other containment valves with this same valve manufacturer and design. The additional valves are listed below and they will be disassembled during the next refuel outage for seat inspection, maintenance, and/or replacement:
A0 1601-20A A0 1601-20B A0 1601-21 A0 1601-22 A0 1601-56 A similar inspection maintenance / replacement program will be established on Unit One.
HPCI STEAM EXHAUST VALVE There is an existing AIR to SNED to investigate a replacement for this valve. The station does not feel that the Mission Duo Check valve, while it does give adequate service for more than one cycle, is the best choice for this application. Further engineering will be performed to determine if a more suitable valve is available, or if modifications to the existing valves will make them more reliable.
0257H/0136Z
S e
- 6 G
APPENDIX A 0257H/0136Z
l
- -. QMF 800-18 Revision 3 l July 1984 1 USPECTION OF SAFETY.M LATEN VALVES i DURDG DISAS N Y, REPAIR, AND RI-AMNRLY OF VALVIS ID/10
! A. PURP0gE .
1 j The purpose of this procedure is t.o outline the requirements for. the i
inspection of safety-related valves, including primary containment isolation valves, during disassembly, repair, and re-assembly for" maintenance. This procedure also is intended to verify that foreign materials are not introduced into the valve which may affect future valve performance or testing, j s. RarzassCas
- 1. ANSI 18.7 (1972 Edition). FOR REERENCE ONLY C. PasmsgarsITas
- 1. lihan valve or valve components such as pilots or bonnet, stam, and disc assemblies are to be removed from the system area for repair, obtain a hold tas(s) 1.f needed from Quality Control and place the hold tag (s) on the valve and/or parts.
- 2. Infer to meanfacturer's repair maanal or instructions, etc., if available la system file for recommendation for replacements parts, bolt torque ;
procedare orders and for cleanias solvents and lubricants (Ceco approved i prodnets). This is to achieve optimum valve operation and perforssace
. se that Technical Specification operability and timing requirements are met. ,
- 3. Primary containment isolation valve disassembly during a refueling outage must not be undertaken until an "as-found" Local Leak Rate Test (LLRT) is performed first by the Technical Staff.
D. PRECAUTIONS
- 1. Use extra precautions when hanging rigging. Some climbing may be required to rig in some areas.
E. LIMITATIONS AND ACTIONS
- 1. This procedure is intended to be used in conjunction with a develeped work package for the proposed maintenance on safety-related valves.
l
. 2. The maintenance foreman responsible for the repair shall discuss with the mechanics the proper techniques for the disassembly, inspection, repair, and reassembly of safety-related valves. This discussion shall include the specific cleaning solvents and lubricants to be p utilized during the repair and the application and amounts to be used.
h ARRROVED AU601884
-1 M 0.,1 R.
~' '
@tP 800-18
.'* Revir, ion 3
- 3. Quality Control shall inspect every safety-related valve upon disassembly and prior to reassembly to verify that foreign materials are not present on valve seating surfaces.
- 4. The checklist QtiP 800-815 shall be reviewed by QC and QA prior to use to include hold points as deemed necessary to verify maintenance performance. -
F. PROCED13tE -
- 1. Before disassembly of the valve, survey the entire exterior of the valve for corrosion, cracks, wear and pits etc. (Remove valve insulation only if there is evidence of valve leakage.) Record specific data such as loose bolting, fittings, packing, condition of the stem and the above inspection information on @lP 800-815.
- 2. Contact Quality control for inspection of valve int;rvals (seating surfaces, etc.) immediately upon disassembly.
- 3. When disassembly is complete, briefly describe the condition of.the valve internal parts (including surfaces, stem, disc, seat,' etc.).
Also note the valve leakage source on QtiP 800-815.
- 4. Repair and replace parts as identified in the accompanying work package.
If changes are required to the approved work package, the package revision anst be approved prior to work proceeding.. Note all repair and replacement parts en the checklist.. Also,. list the spacific masafecturer's product name for lubricants and cleaning solvents used on valve componaat surfaces (i.e., o-rings, gaskets, sealing surfaces, stems,etc.). The product used shall be in accordance with the valve manufacturer's recommendations and/or good maintenance practices; for, purposes of assuring smooth and res.istance-free valve operation.
Describe the type application used for cleaning solvents, lubricants and the, proper amounts.
t 5. Contact Quality Control ismisdiately prior to valve closure to inspect the internal seating surfaces for cleanliness and to verify that foreign material is not on the seating areas.
l 6. Complete the reassembly of the valve in accordance with maanfacturers reca===adations and good maintenance practices. Add the bolt torquing ragairements and rotational and sequential orders on the checklist.
G. CHECKLISTS
- 1. QldP 800-S15, Safety-Related Valve Inspection Checklist (Includes Primary Containment Isolation Valves).
i H. TECIDIICAL SPECIFICATION REFERENCES l
- I*
l --
APPROVED
- 1HdIE DAr AU601984 Q.C.O.S.R.
! (flaal) .
l -.
. i . .
HOLD POINTS INCLUDED O QC QA INITIAL /DATE SAFETY-RELATED VALVE INSPECTION CEECELIST (INCLUDES PRIMARY QMP 800-815 Revision 1 July 1983 CONTATEMENT ISOLATION VALVES)
ID/IP UNIT EPN WORE REQUEST No. <
l VALVE DESCRIPTION (I.E., MAEE, MODEL, SIZE, ETC.)
A. VALVE EETERNAL INSPECTION: QC/QA BOLD POINTS fX IF REQUIRED)
(NOTE CONDITIONS FOUND) _ QC QA YES NO SIGN DATE CORROSION CRACES M
PITS h
IF TES, DESCRIBE CONDITIONS FOUND:
l I
- 8. VALVE DISASSEMBLY QA NOLD POINT (I 17 REQuuu.u) i QUALITY CONTROL INSPECT VALVE l lQAl l l ON DISASSEMBLY. NOTE ANT SIGN DATE
, FOREIGN MATERIAL ON SEATING l
SURFACES. /
l QUALITY CONTROL INSPECTOR DATE DESCRIBE ANY DISCREPANCIES BELOW:
i l
l f
l i
i- APPROVED !
AJG 0 51053 1 Q.C. O. S. H.
l
QMP 800-S15
, ,. Rwision 1 C. IDENTIFT VALVE LEAEAG SOUR G QC/QA HOLD POINTS (I IF REQUIRED)
. .C -
QA l SIGN DATE TES N0 4
~
- MAIN SEAT / POPPET -
PILOT SEAT / POPPET STEM PAGING S= una/>0Dr->0N=T GAS =T FOR REFERENCE ONLY .
OTHER - '
IF TES, DESCRIBE CONDITIONS FOUND:
' IF UNINOWN AFTER INSPECTION INCLUDE OBSERTATIONS AND POSSIBILITIES OF LEAKAGE SOURG:
D. VALVE INTERNAL INSPECTION QC/QA BOLD POINTS (I IF REQUIRED)
NOTE ENERAL CONDITION OF:
QC GA INTERNAL VALVE BODY SURFAGS VALVI SEAT GUIDE DISC i GASKET AND SURFAGS1 PACKING / FOLLOWER STEM BOLTING LUBRICATION (I.E., DRT, NORMAL ETC.)
OTHER CONDITIONS NOTED E. REPAIRS,IF NECESSART, SHALL BE IDENTIFIED ON A WORK PACKAGE (I.E., MAINTENANG / MODIFICATION PROCEDURE AND STATION TRAVELER).
4 p p g g.,, g .'.
NOTE: NO DATA REQUIRED ON THIS FORM.
" ~
~
C: 0 5 E23 Q.c a s. a.
.** * @lF S00*S15 Revision 1 F. REPLACEIENT DATA: QC/QA 502 PO UTS G U 0UIRED)
QC
. QA J SIGN DAR PART NO. (IF AFFLICAME)
VALVE ASSEHRLT Snu i- ,
i -
MA N DISC APPROVED AUG 0 51983 PILOT DISC y a ggar - Q. C. O. & R.
OIEER -
${&{fff O G. LUBRICANT AND SOLVINTS QC/QA EOLD PO UTS 3 U 52 *T**n)
QC CA SIGN DATI HFG NAtB TYPE LUERICANT AFFLICATION At900NT*
MFG MARIE -
TTFE SOLVENT AFFLICATION ARIOUNT*
.*AN00NT: DESam COATUG OF LUERICANT OR SOLVENT (I.E., LIGNT FII2, EEAVT USE ETC).
DESCRIM ANT ADDITIONAL USES OR POTENTIAL PROBLEHS WITE LUBRICANT OR, SOLVENTS:
E. VALVE REASSIMBLY .QA 30 2 PO UT CI IF IdQUIRED)
QUALITY CONTROL INSMCT I IQAl 1 l 1 VALVE PRIOR TO CIASURE SIGN DATE (VALVE REASSEISLT). NOTE ANT EEGSSIVE OR UNAUIBORIZED FOMIGN MATERIAL ON SEATING SURFAGS.
MCLEANUG IS MQUDED FRIOR'TO PROCIEDDG WITE TM CLOSURE, IF F0MIGN HATERIALS AIE NOTED.
C0ADITION /
QUALITT CONTROL INSPECTOR DATE -
3
r -
( . . , .
~
s.,, QMP S00-515 Revicion 1 1
I. VALVE CLOSUM QC/QA HOLD POINTS (E IF REQUIRG)
QC SIGN DATE BOLTING: SEQUENTIAL ORDER ROTATIONAL ORDH TORQUE VALIE l TORQUE WRENG NUMMR CALIBRATION DATE
, a SETG:
O s
V FOR REFERENCE ONJ FINAL SIGNATURES:
4 MECHANIC /
SIGNAruus DATE FOREMAN REVIEW /
SIGNATURE DATE MASTER MEC.teNIC REVIEW /
SIGNATURE DATE QUALITY,, CONTROL REVIEW /
SIGNATURE DATE NOTE: TR ABOVE SIGNATURES MUST E COMPLETE PRIOR TO RETURNING THE VALVE TO SERVICE (REEASE FOR TEST).
APPROVED AUG 0 51053 J '
Q.C.O.S.R -
-4.(final)
,