|
---|
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] |
Text
-_ . - . ~
-/
X}_x1400 Opus Place C:mm:nwealth Edis:n Downers Grove, Illinois 60515 -
l April-11, 1990: ,
Dr. Thomas E. Murley, Director.
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission y Washington, DC 20555- -
Subject:
. Quad Cities. Units 1 and 2 -
Request forl Revision to Appendix R Exemption Approval NRC Docket 50-254/50 :
.t
Reference:
-(a) Letter frem J.R. Wojnarowski to H.R. Denton dated June 25, 1986 ,
s (b) Letter from T. Ross to H. Bliss dated July. 21, 1988.
Dr. Murley:
Reference (a) transmitted a request for approval of exemptions to Appendix R requirements. .The exemption requests were presented in sections for clarity of review. Reference (b) transmitted the Safety Evaluation' Report (SER) for granting the' exemption request.-
As a result,of a Quality Assurance Audit and the initiation'of'a computer tracking program for combustible materials at Quad Cities, Commonwealth Edison identified that insufficient' flexibility is contained in-the combustible loading limits subinitted in reference (a) 1 Additional details are contained in Attachment A. Commonwealth Edison, therefore, is requesting revision to the combustible load limits. contained in reference (a).
+
Justification for these revised limits is contained in Attachment B.
If there are any further questions or comments, please direct them to this office.
Very truly yours, Rita'Stols I
, Nuclear Licensing Administrator I i
cc: ~L.. 01shan, NRR Project Manager ll D. Notley, NRR A. Bert Davis, Regional Administrator, NRC '
Senior Resident Inspector, Quad Cities
/Imw:RS:0RRIT l 9004230054 900411 / '
PDR F
ADOCK 05000254 Mt?
PDC !
lll'
ATIAUIEElfLA Backgrsund On March 21, 1990, a Quality Assurance Auditor identified that the combustible load in a Fire Zone had exceeded the value contained in an Appendix R exemptien request. An investigation of all fire zones was initiated to identify areas in which Appendix R exemption limits were exceeded. Compensatory' measures, in the form of fire; watches, were immediately instituted for Fire Zones where values were exceeded.
Commonwealth Edison is reviewing.this event to-identify the root cause for !
exceeding combustible load values and that the values were not properly t controlled.
The reasons why Appendix R exemption combustible loadings were exceeded fall into three categories:
l 1. Combustible loads were recalculated.due to revisions in the heat of combustion values for various combustibles. No change in physical combustible loads was made.
- 2. Approved combustible load limits were exceeded due to increasec in the fixed combustibles (e.g. Anti-contamination clothing hamper) in the area. ,
-3. Approved combustible load limits were exceeded due to the introduction of transient combustibles in the area.
These categories were discussed with NRR-Staff and the following conclusions were achieved:
- 1. No revision to the exemption approval-or. compensatory measures are required for those fire zones in which the limit was exceeded soleiv due to revised calculations performed to accommodate revisions to the- '
heat of combustion values.
- 2. If the Safety Evaluation Report (SER) provides a limit associated ,
with the exemption request approval-(e.g.' fire severity does not
- exceed 23 minutes for any zone), the individual zone may. exceed the submitted combustible loading up to the limit defined in the SER. A technical review must be performed for the individual-zone to demonstrate the acceptability for adopting-the higher limit contained in the SER. The-justification is not. required to be submitted to the NRC; however, the justification must be maintained in.an'auditable file. Compensatory measures can be removed.
- 3. Request for exemption approval revision is required for areas for which the above discussion does not apply. Attachment 'B' contains the justification for the revised combustible-loading for such areas.
Commonwealth Edison is currently reviewing the limits defined in the '
Appendix R exemption requests to assure sufficient flexibility exists in the ,
' defined exemption values to accomodate future, expected, operating and maintenance activities. Following this review, additional requests for exemption revision will be submitted as neede6.
/0881T12
1,
.i ATTACMENT B l 4
' REQUEST FOR REVISION TO PREVIOUS s
NRC EXEMPTION APPROVAL i
i
-r
'b
+
l i.
t 5 l
l~
a F
3-1 f
b i
4 1
+w A + 4
i '
13.0 AEEENDIX R EXEMEIION EQUEST TO REVISE COMBUSTIBLE LOAD VALUES CONTAIED
.lN_AEERQVED EXEMPTION.P1 QUESTS.
Per the provisions of 10 CFR 50.12, Commonwealth Edison Company (CECO) had requested exemption from the requirements of Sections III.G.2. III.G.3 and III.L of Appendix R to 10 CFR 50. In justifying exemptions'from the requirements of these sections, an evaluation was performed to demonstrate i that adequate fire protection measures exist for the fire zones that do not '
meet the Appendix R: requirements and a combustible load limit was established to demonstrate that the amount of combustible materials in these fire zones was lov.
A review of these combustible load values has shown that sufficient flexibility is not provided to perform routine operation and maintenance activities, particularly during an outage. Therefore, CECO is submitting this request to revise exemptions previously approved in the Safety Evaluation-Report (SER) dated July 21, 1988, to reflect higher combustible load values.
-Table 13.0-1 lists each fire zone, the original combustible load _value and the new combustible load value.
To determine the new combustible load, a reev91uation of each fire zone' '
was performed based on the fire barriers in the fire zone, the type of combustibles, and sound fire protection-judgment. The following conservative '!
approach was used to establish the new limits: i
- 1. The evaluation was performed assuming-outage activities when transient combustible loads should be at their highest point.
- 2. A fire severity limit was set for the fire zone based on whether fire !
detection or automatic fire suppression existed in the zone. For fire l
zones without fire detection or suppression, a fire severity limit of 15 minutes was established and for those with fire-detection or suppression, a 30 minute limit was established. Using these fire. (
severity limits, the new combustible load limit was derived. These limits were conservatively set well below the NFPA test data for fire ;
severity by assuming the combustibles are flammable liquids.
- 3. For areas with extremely low limits, the existing values-for each fire ,
zone were' increased to the expected combustible loadings required and '
reviewed against the individual characteristics of each' fire zone. For most of the fire zones, this proved to be an adequate solution since ;
original limits were extremely low to begin with and the increase on ;
fire severity was negligible.
- 4. The additional loading would not increase the probability of' initiating- ,
a fire since ignition sources, if any, in the fire zones are not being !
changed.
I 13.0-1
. -1 The justification for increasing the combustible load value for each of the previously approved exemptions are presented in the-following sections..
Affected SECIl0H ~ JUSTIFICATION FOR fitt_ZQDB -
13.1 Lack of complete 3-hour fire barrier 8.2.10 between Southern and Central Zone Groups.- .8.2.1.A.
14.1.1-11.1.1.B.
13.2 Lack of complete .3-hour barrier between 8.2.1.A Northern and Southern Zone Groups. 8.2.7.D 11.1.1.B 13.3 Lack of complete suppression and detection- 8.2.7.D for enclosure of cable in fire barrier having a 1-hour rating.
13.4 Lack of complete 3-hour fire barrier 11.1.1.B between Fire Zone-11.1.1.B and Southern 8.2.1.A Zone Group.
-i 13.5 Lack of complete _3-hour fire barrier 8.2.7.D-between equivalent Fire Area 8.2.8.D and Northern Zone Group.
1 i
i I
j i
l 1
13.0-2
~"~
- TABIX 13.0-l' .,
Sumneary For Exemption Request ~ Revision .
Fire Zone Approved' Combustible Exemption SER~ ..
Requested Load Limit (BTU /ft2 ) Request .Section- Load Value (BTU /ft2) 8.2.10 2500 5.2 9.0 '5000 14.1.1 1000 5.2 9.0 5000 8.2.1.A 1000 5.2- 9.0 2000
- 5.3 10.0 5.9 8.2.7.D 30000 .5.3 10.0 40000
.5.7 6.0 5.10 14.0-
~
11.1.1.B 2500 5.2 9.0 10000 5.3 -10.0 5.9 13.0-
,,. ,E
__ __= :-_ .. _ _ - - _ - - . _ = _ - _ _ - . . _ _ _ . _
f 13.1 LACK OF COMPLETE 3-HOUR FIRE _ BARRIER BE'IVEEN THE SOUTHERN AND CENTRAL.
-ZONE CROUIS. .
I
-The following exemption request contained in-the June. 25, 1986 submittal is affected by the revision to the combustible loadings in Fire Zones 8.2.10.
14.1.1. 8.2.1.A and 11.1.1.B: i Section 5.2: Lack of a complete 3-hour fire barrier between the Southern and Central Zone Groups t'
Fire Zone 8.2.10 (Central- Zone Group) and Fire Zone 14.1.1 (Southern '
Zone Group) share a boundary on the-626'-6" elevation, where the fire zones are separated by a substantial reinforced concrete shield wall that is not ,
specifically fire rated. Personnel access between the zone groups is through substantial. unlabeled, metal doors. There are no safe shutdown cables or ;
equipment in either of the fire zones. The principle concern in either the Central or Southern Zone Group is- that a fire could develop, spread to an adjacent zone group and damcge the necessary safe shutdown system components. (
Fire Zone 8.2.1.A and 11.1.1.B are located.in-the Southern Zone Group.
These fire zones do not share a common boundary with any fire zone-contained' in the Central Zone Group, however, are discussed in the NRC's SER.
The NRC subsequently granted the proposed exemption. The' basis for the Staff's approval of the exemption request contained in the. July 21, 1988 Safety Evaluation Report (SER) included:
- 1. The two fire zones are separated by a reinforced concrete shield wall with metal, personnel access. doors that are locked shut.
- 2. Fire zones 8.2.10 and 14.1.1 contain no safe shutdown cables; 3.
~
The fire load is low and therefore a postulated fire in either area is expected to develop slowly and remain small. The heat would dissipate to surrounding areas without spreading to an adjacent zone group.
t The SER concluded since a fire in either the Central or Southern Zone Group would not damage an alternative safe shutdown path located out of the zone groups and/or spread to the adjacent zone group, the complete.3-hour fire rated barrier would not significantly upgrade the level of fire protection. i Since the submittal.of the exemption request, no safe shutdown systems or components have been added and the physical configuration of the fire zones remains unchanged; however, the need to increase the allowable combustible loading has been identified.
13.1-1
4
- Commonwealth Edison, therefore, requests that the allowable comb'ustible loading be increased as follows:
ApptovedLimgt Enqunated Limit Zone 8.2.10 2500 BTU /ft 5000 BTU /ft Zone 14.1.1 1000 BTU /ft2 '2000 BTU /ft Zone 8.2.1.A 1000 BTU /ft2 2000 BTU /ft2-Zone 11.1.1.B 2500 BTU /ft2 10,000. BTU /ft2 The increased loading meets the.basisoof the exemption approval in that the fire load remains low and well within the capability of the concrete shield wall to contain the fire. -(NFPA Handbook defines low combustible loading to be less than 100,000 BTU /ft .) 2 Neither Fire Zone 8.2.10 nor 14.1.1 contain safe shutdown equipment. The combination of the shield walls-and the low combustible loading continues to assure that a fire cannot 1 propagate between the Central and Southern Zone Groups at this elevation and, therefore, the revision to the exemption should be granted. J i
i l
.i i
l 13.1-2 l
4 . ..
13.2 LACK OF COMPLEIE_3-J10UR BARRIER BE'DfEEN NORTilERN AND SOUTHEBN ZONE GRQUfE.
The following exemption request contained in the June 25, 1986 submittal is affected by the revision to the combustible loadings in Fire Zone 8.2.1.A.
E1LD and 11.1.1.B Section 5.3 Lack of complete 3-hour barriers between Northern and' Southern Zone Groups. -
Fire Zones 8.2.1.A and 11.1.1.B are located in the Southern Zone Group.
Fire Zones S.2.1.A and 11.1.1.B do not share a common boundary with the Northern Zone Group and Fire Zone 8.2.7.D is located -in the Northern Zone Group and does not share a common boundary with the Southern Group. These Fire Zones, however, are discussed in the July. 21, 1988 SER for this exemption request. The Northern and Southern Zone Groups share a common boundary- only.
along positions of the Unit 2 Cable tunnel (Fire Zone 8.2.5) and in the radwaste pipe tunnel. The principle concern for the lack of a 3-hour barrier is that a fire in either Zone Group could develop and spread to an adjacent; zone group and damage necessary cable or equipment necessary for safe shutdown.
The Staff's basis for the approval of the exemption request contained in the July 21, 1988 SER primarily focused on the Northern and Southern Zone ,
group interface configuration and' existing fire protection systems in the !
interface zones. Since the Staff's SER also references.the non-interface areas, Commonwealth Edison-is formally requesting a revision to the exemption approval to reflect increased combustible loadings as follows:
i' APPIneLLimp Resuaaleiligli Fire Zone 8.2.1.A 1000 BTU /ft 2000 BTU /ftz 8.2.7.D 30000 BTU /ft2 40000 BTU /ft2.
11.1.1.B 2500 BTU /ft2 ~ 10000 BTU /ft2 j i i
The increased loading meets the basis for the exemption approval since !
loading remains low. In addition, none of these zones share a.-common boundary 1 with-the Northern or Southern Zone Group; therefore, the spread of a fire ]
originating in the Fire Zones to the other Zone Group is limited. The !
increased loading should, therefore, be approved. I i
1
]
I 13.2-1
13.3 JUSTIFICATION FOR LACK OF COMPLETE SUPPRESjl0N AND DIIECTION FOR ENCLOSURE OE_C&BLE IN A ElRE RARRIER HAVING A 1-HOUR RATING.
i The following exemptien request contained in the June 25, 1986 submittal e is affected by the revision to the combustible loadings in Fire Zone 8.2.7.Dt i Section 5.7 Justification for Lack of Complete Suppression and Detection l for Enclosure of Cable in a Fire Barrier having a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Rating The turbine building contains certain cables which are required to be !
wrapped in a 1-hour fire barrier because they are routed through fire zones !
which have alternative shutdown methods that take credit for equipment fed by the cable running through the zone. The 4KV bus duct to switchgear 23-1 is wrapped in a 1-hour barrier where it passes through the Fire Zone 8.2.7.D of the Northern Zone Group.
- The Northern Zone Group uses alternate shutdown path C for hot shutdown. l Shutdown Path C uses equipment powered by switchgear 23-1. This bus duct is ,
protected with complete automatic suppression where it passes through Fire !
Zone 8.2.7.D and partial detection is provided. There are also hose reels and i portable extinguishers in the fire zone which could be used by the fire brigade to fight the fire. The principle concerm with a fire in the fire zone having a bus duct penetration is that a fire could spread through the bus duct penetration.
The NRC subsequently approved the exemption request. The following basis for the Staff's approval is contained in the July 21, 1988 SER:
- 1. The fire loading is low and a fire of major proportions is not expected to occur.
- 2. Fire Zenes 8.2.7.D has automatic sprinkler protection, t
- 3. The bus duct metal enclosure would be resistant to small fires and would not likely fail inr up to a ene hour time period. ,
t The SER concluded that the installation of a 3-hour rated bus duct '
penetration would not significantly increase the level of fire protection in this fire r.one. .
Since the submittal of the exemption requeat, no safe shutdown equipment ;
or componente have been added and the physical configuration of the fire zone 3 remains unchanged; however, the need to increase the allowable combustible loading has been identified. Commonwealth Edison, therefore, requests that the allowable combustible loading in Fire Zone 8.2.7.D be increused from 30,000 to 40,000 BTU /ft ,2 The increased loading meets the basis of the exemption approval in that '
the combustible loading remains low and well within the capability of the bus !'
duct to withstand the postulated fire. The combination of complete automatic suppression and I hour cable wrap provides a level of protection to switchgear 23-1 that is equivalent to that prescribed in Appendix R Section III.G.2.
13.3-1
s 13.4 ElRE EARRIER EllWEEN FIRE ZONE 11.1.1.B AND SOUTHERN ZONE CAQUE.
The following exemption request contained in the June 25, 1986 submittal i is affected by the revision to the combustible loadings in Fire Zone 11.1.1 3 ;
and_LLLA:
Section 5.9 Lack of complete 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire barrier between Fire Zone 11.1.1.B and Southern Zone Group.
Fire Zone 11.1.1.B contains one Division I and one Division II Residual Heat Removal (RRR) service water pump, the swing (1/2) diesel generator [
cooling water pump and their auxiliaries. The floor, ceiling and all walle ;
are 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire barriers. The east wall contains a nonlabeled.
- watertight door that opens to Fire Zone 8.2.1.A of the Southern Zone Group.
Fire Zone 8.2.1.A contains the main and reserve power feeds to the swing- '
diesel generator cooling water pump. The reserve feed is protected with a 1-hour rated fire wrap. Fire protection systems contained in these areas include a complete fire detection and suppression system in Zone 11.1.1.B and ;
a complete automatic wet pipe sprinkler system in Fire Zone 8.2.1.A. The r principal fire protection concern for these fire zones is that a fire could start in either fire zone and spread to the unaf fected fire zone through a nonrated metal watertight door.
The NRC subsequently granted the proposed exemption. The basis for the '
Staff's approval of the exemption request is contained in the July 21, 1988 SER and can be summarized as follows:
- 1. The fire load in either zone is negligible.
- 2. Both zones have automatic fire suppression systems.
- 3. The watertight deor 29 of substantial steel construction and sufficient to withstanc any expected fire in these zone.
l
- 4. In the event of fire damage to safe shutdown components in either zone, an alternate safe shutdown path is available, independent of j these fire zones.
l The SER concluded that upgrading the exiating watertight door to a 3-hour fire rating does not significantly increase the level of fire protection. <
Since the submittal of the exemption request, no safe shutdown systems or l
components have been added and the physical configuration of the fire zones remain unchanged; however, the need to increase the allowable combustible
(
loading has been identified.
r 13.4-1
Commonwealth Edison, therefore, requests that the allowable combustible loadings be increased as follows:
Regues.ted Zone 11.1.1.B Approndlingt 2500 BTU /Ft 10000 BTU /ftgiali Zone 8.2.1.A 1000 B1V/ft2 2000 BTU /ft2 The increased loading meets the basis of the exemption request approval in that the fire loading remains low and well within the capability of the watertight door to contain the fire. Fire Zone 11.1.1.B has complete detection and fixed water suppression and Fire Zone 8.2.1.A has complete water suppression. The level of protection _provided by the existing fire protection features ensures that damage from a fire in Fire Zone 11.1.1.B would be limited in duration and intensity and would not adversely impact the capability to shut down the plant. The revision to the exemption approval is therefore warranted.
13.4-2 i
^
j
R I
13.5 1AtrJIlotitLETEl-110VR BARRIERJElyEEN EOUIVALENLIlRE AREA JAAD ANILKORIKEAli30NEJtt0Ul'.
D e following exemption request contained in the June 25, 1986 submittal is aftweted by the revision to the combustible loadings in Fire Zog 1 L l J t Section 5.10 1.ack of complete 3 heur barrier between equivalent Fire Area 8.2.8.D and Northern Zone Group i Northern Zone Group Fire Zone 8.2.7.D is located directly below equivalent Flte Area 8.2.8.D. The floor of equivalent Fire Area 8.2.8.D is not fire rated and separates the fire zone from the equivalent fire area. Fire Zone 8.2.7.D has a floor area of approximately 6100 ft2 and beiling height of l approximately 24 feet. Fire Zone 8.2.7.D is protected by an automatic vet pipe sprinkler throughout, except over the low pressure heaters and in the corridor along row C. Separate detection is provided only around cable risers in the high pressure heater bay. The area directly below equivalent Fire Aron 8.2.8.D is protected by automatic suppression and partially covered by detection. The principle concern is that a fire could develap in the Northern Zone Group (Fire Zone 8.2.7.D) and spread to the turbine building operating floor (equivalent Fire Area 8.2.8.D) and vice versa.
The NRC subsequently approved the request for exemption in a SER dated July 21,1988 from the requirements of Appendix R Section 111.G.2.a based on the following:
- 1. Hazards located below the operating floor are contained in reservoirs and are protected with automatic fire detection and fire suppression systems. The expected Iire would be detected early and controlled / extinguished by the fire suppression systems.
- 2. The areas are open and accessible. to the fire brigades.
The SER concluded that the provisions of a complete 3-hour itre rated barrier between c.e subject fire zones would not significantly upgrade the level of fire protection.
Since the submittal of the exemption request, no safe shutdown equipment or components have been added and the physical configuration of the fire zones remains unchanged; however, the need to increase the allowable combustible loadings has been identified.
Connonwealth Edison, therefore, requests that the fire loading for Fire Zone 8.2.7.D be increased from 30,000 BTU /ft2 to 40,000 BTU /ft2 . The increase in the combustible loading does not impact the basis of the exemption request approval. The low combustible loadirg coupled with the existence of .j automatic suppression in the area beneath equivalent Fire Area 8.2.8.D l' provides a high level of assurance that a fire in this zone would not spread to the equivalent fire area.
13.5-1