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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr 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) 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 ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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) 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 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray 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 ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created 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 ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy 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 ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem 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 ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures 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) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr 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) 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 ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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 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 ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs 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 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 ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem 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 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) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154M4291998-10-15015 October 1998 Forwards 1998 Third Quarter 10CFR50.59 Rept of Completed Changes,Tests & Experiments.Completed SEs Compared to Previous Quarterly Repts as Docketed ML20154J4951998-10-0707 October 1998 Forwards Revised Security Plans for CE Listed Nuclear Power Stations,Per 10CFR50.4(b)(4).Changes Do Not Decrease Effectiveness of Station Security Plans.Encl Withheld ML20151Y5101998-09-11011 September 1998 Provides Results of drive-in-drill Conducted on 980804 & Augmentation Phone Drills Conducted Between 980601 & 0831 ML20151Y2931998-09-0909 September 1998 Notifies NRC of Results of Feasiblity Study of Seismically Qualified or Verified Path to Obtain Water from Ultimate Heat Sink & Deliver It to Shell of Isolation Condenser for Each Unit ML20238F7571998-08-28028 August 1998 Forwards fitness-for-duty Program Performance Data for Each of Util Nuclear Power Stations for Six Month Period Ending 980630 ML20237D9771998-08-21021 August 1998 Forwards Proposed Changes to Quality Assurance Topical Rept (QATR) CE-1-A,rev 66,modifying Ref Submittal & Clarifying Certain Changes to QATR Proposed in Util .Page A-1, 6 of 6 of Incoming Submittal Not Included ML20237A8611998-08-0707 August 1998 Requests Approval of Enclosed Qualified Unit 1 Supervisor Initial & Continuing Training Program, Which Ensures That Qualifications of Personnel Are Commensurate W/Tasks to Be Performed & Conditions Requiring Response ML20237A8871998-08-0707 August 1998 Documents Completion of Util Action Items Discussed at 980529 Meeting W/Nrc.Updated Proposal to Consolidate Near Site Emergency Operations Facilities Into Single Central Emergency Operations Facility,Provided ML20236W1311998-07-27027 July 1998 Forwards Response to NRC Re Violations Noted in Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18, Respectively.Encl Withheld ML20236T7241998-07-24024 July 1998 Forwards Revised Epips,Including CEPIP-2000 Series Table of Contents & Rev 7 to CEPIP-2121-01, Augmentation Caller Instructions ML20236R2531998-07-16016 July 1998 Summarizes Results of drive-in Drill as Well as Preceeding call-in Drills Conducted Between Each drive-in Drill,As Committed to in 980326 Meeting Between Util & NRC ML20236F8041998-06-29029 June 1998 Forwards Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co, Per Requirements of 10CFR50.71(e)(4).Decommissioning Program Plan Is Being Reformatted & Revised Into Defueled SAR SVP-98-170, Advises That AL Misak,License SOP-30832-1,is No Longer Required to Maintain Operator License1998-05-0101 May 1998 Advises That AL Misak,License SOP-30832-1,is No Longer Required to Maintain Operator License ML20247B6521998-04-30030 April 1998 Forwards 1997 Repts for Braidwood,Byron,Dresden,Lasalle,Quad Cities & Zion Nuclear Power Stations.Repts Being Submitted Electronically on Magnetic Tape.W/O Encl ML20217G8841998-04-23023 April 1998 Forwards Proposed Changes to QATR CE 1-A,rev 66.Change Constitutes Major Programmatic Rev to Onsite & Offsite Review Processes as Presently Described in Rept ML20246Q1391998-04-20020 April 1998 Provides Response to Violations Noted in Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08.Corrective Actions: Described in Attachment Which Contains Safeguards Matl.Encl Withheld ML20217N3461998-03-31031 March 1998 Provides Basis for Plant Conclusion That Dam Failure Coincident W/Loca Is Beyond Design Basis of Dresden,Units 2 & 3.Licensing Amend Is Not Necessary & Clarifications to UFSAR May Be Made Through Provisions of 10CFR50.59 ML20216H4041998-03-13013 March 1998 Forwards Revs to Byron,Dresden,Lasalle & Zion Station OCDM, Current as of 971231,ODCM Manual & Summary of Changes Included ML20203L2911998-02-27027 February 1998 Provides Revised Schedule for Hazardous Matl Response Drill Described in 971121 Response to Insp Repts 50-010/97-13,50-237/97-13,50-249/97-13 & NOV 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059F0311990-08-27027 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 ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants 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. ML20043D3231990-06-0101 June 1990 Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C8181990-05-30030 May 1990 Forwards Rev 1 to Core Operating Limits Rept,Dresden Station Unit 2,Cycle 12. Rev Reflects MCPR Limit Adjustment for Cycle 12 Due to Number of Reused Channels,Per Discussion of Channel Bow Effects in BWRs in NRC Bulletin 90-002 ML17202G7741990-02-0505 February 1990 Forwards Core Operating Limits Rept,Dresden Station Unit 2,Cycle 12,Rev 0 & Core Operating Limits Rept,Dresden Station Unit 3,Cycle 12,Rev 0. Cycle 12 Startup Expected on 900210 ML19332D3011989-11-15015 November 1989 Provides Update Concerning Evaluation of long-term Improvements to Unit 2 & 3 Isolation Condenser Shell Side Clean Demineralized Water Supply Sys ML19324C2271989-11-0909 November 1989 Forwards Response to Regulatory Effectiveness Review Insp on 890731-0804.Response Withheld ML17285A8081989-10-18018 October 1989 Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 70 ML20248D0881989-09-21021 September 1989 Forwards Rev 56 to QA Program Topical Rept CE-1-A ML19325C5601989-09-13013 September 1989 Forwards Response to Allegation RIII-87-A-0074 Re Employment Discrimination,Per Eg Greenman 890801 Ltr to C Reid ML20245H3771989-08-0909 August 1989 Forwards Listed Policies,Including Endorsements 24 & 25 to Nelia Policy NF-294,Endorsements 19 & 20 to Maelu Policy MF-128,Endorsements 36 & 37 to Nelia Policy NF-277 & Endorsements 29 & 30 to Maelu Policy MF-114 ML20246L8141989-07-0101 July 1989 Forwards Dresden Nuclear Power Station Monthly Operating Summary Rept for June 1987.Info Previously Submitted on Annual Basis Now Included in Monthly Summary Rept ML20245L6831989-06-29029 June 1989 Forwards Addl Info on Emergency Planning & Fuel Handling Accident,Per E Erickson & R Beck Request ML20245G2411989-06-19019 June 1989 Forwards Endorsements 55,28,205,179,55,37,117,100,108 & 97 to Nelia & Maelu Policies NF-227,MF-114,NF-43,MF-22,NF-253, MF-104,NF-187,MF-54,NF-201 & MF-64.respectively ML20247J1051989-05-17017 May 1989 Responds to Items from SALP 8 Board Repts 50-237/89-01 & 50-249/89-01 for Feb 1988 - Jan 1989.Plant Security Program Now Implements All Aspects of Reporting All Events Identified,Per App E & Section 5.7,to NRC within 1 H ML20246B9501989-04-28028 April 1989 Forwards Rev 55 to CE-1-A, QA Program for Nuclear Generating Stations. Rept Reflects Organizational Changes Resulting from Current Self Analysis Performed in Effort to Improve Effectiveness ML20245J2421989-04-25025 April 1989 Forwards Rev 27 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20247B6021989-04-13013 April 1989 Forwards Results of Util Investigation of Allegation RIII-88-A-0147 Re Fitness for Duty.Encl Withheld (Ref 10CFR2.790(a)(7)) ML20245A1521989-04-12012 April 1989 Forwards Monthly Performance Rept for Mar 1989.W/o Encl ML20244B5081989-04-10010 April 1989 Forwards Addl Info Re Accident Analysis & Protective Action Plans During Emergency Conditions ML20244A7421989-04-0303 April 1989 Responds to 890201 Telcon Request for Addl Info Re Item 2.2.1.3, Use of Info Handling Sys & Item 2.2.1.4, Mgt Control of Generic Ltr 83-28 ML20244D1101989-03-28028 March 1989 Forwards Corrected Radioactive Effluent Rept for Jul-Dec 1988 for Plant.Final Data for Sr-89,Sr-90,Fe-55,tritium & Gross Alpha Included in Rept ML20248D9741989-03-27027 March 1989 Forwards Response to Requests for Addl Info Re Emergency Plan,Tech Specs & Decommissioning Plan.Info on Emergency Plan Requirements Will Be Provided by 890410,per 890323 Discussion W/P Erickson ML20247B2791989-03-23023 March 1989 Forwards Endorsements 23,18,34,27,202,176,54,36,114,97,105 & 93 to Nelia Policies NF-294,MF-128,NF-277,MF-114,NF-43, MF-22,NF-253,MF-104,NF-187,MF-54,NF-201 & MF-64, Respectively ML20246P2311989-03-20020 March 1989 Forwards Endorsements 203 & 204 to Nelia Policy NF-43, Endorsements 177 & 178 to Maelu Policy MF-22,Endorsements 115 & 116 to Nelia Policy NF-187 & Endorsements 98 & 99 to Maelu Policy MF-54 ML20247G5311989-03-20020 March 1989 Forwards Overheads Used at 890301 Meeting W/Region III Personnel in Working Group Level to Discuss Dc Ground Policy & How It Applies to Facilities ML20235V2721989-03-0101 March 1989 Forwards Corrected Rev 54 to Topical Rept CE-1-A, QA Program for Nuclear Generating Stations, Incorporating Pages 1-38 & 1-44 ML20235V5921989-02-28028 February 1989 Informs That Response to 880707,0927 & 890107 Requests for Addl Info Re Emergency Plan,Tech Specs & Decommissioning Plan Will Be Submitted by 890327,per 890228 Telcon W/P Erickson ML20235U4251989-02-28028 February 1989 Forwards Rev 26 to Security Plan.Rev Withheld ML20247E7771989-02-24024 February 1989 Forwards Radwaste & Environ Monitoring,Annual Rept 1988 ML20235Y6321989-02-22022 February 1989 Forwards Occupational Radiation Exposure Portions of Plants Operating Repts for 1988,per Reg Guide 1.16 ML20235Y8731989-02-14014 February 1989 Forwards Occupational Radiation Exposures Rept for 1988,per Reg Guide 1.16 ML20235Y6481989-02-14014 February 1989 Forwards Occupational Radiation Exposure Rept for 1988,per Reg Guide 1.16 ML20235U3411989-02-13013 February 1989 Forwards Corrected Radioactive Effluent Rept for Jan-June 1988.Final Data for Sr-89,Sr-90,Fe-55,tritium & Gross Alpha Included ML20235Y6541989-02-0606 February 1989 Forwards Occupational Radiation Exposure Rept for 1988,per Reg Guide 1.16 ML20235Y8491989-02-0202 February 1989 Forwards Occupational Radiation Exposure Rept for 1988,per Reg Guide 1.16 ML20235Y8571989-02-0101 February 1989 Forwards Occupational Radiation Exposures for 1988,per Reg Guide 1.16 ML20235Y6401989-01-27027 January 1989 Forwards Occupational Radiation Exposures Rept for 1988,per Reg Guide 1.16 ML20206K1501988-11-21021 November 1988 Provides Addl Info Re Util Decommissioning Plan & Tech Specs Per NRC 880927 Request.Info Provided Discussed W/P Erickson of NRC on 881117 ML20205P9231988-11-0101 November 1988 Discusses Proposed 881116 Meeting Re Dcrdr Mods & Enhancements,Including Program Overview,Summary of Completed & on-schedule Human Engineering Discrepancy Corrections & More Detailed Discussion of Items ML20154N8291988-09-23023 September 1988 Forwards Rev 25 to Security Plan.Rev Outlines Declassification of Unit 1 Reactor Sphere,Core spray/post- Incident Room & Cribhouse.Rev Withheld (Ref 10CFR73.21) ML20154D2881988-09-0808 September 1988 Responds to NRC Bulletin 88-005 & Suppls 1 & 2 Re Piping Supplies,Inc & West Jersey Mfg Co Matls Complying W/Asme Code Requirements.Itemized List of Components Received Encl ML20205A7531988-09-0202 September 1988 Responds to 880707 Request for Addl Info Re Emergency Plan Requirements for Facility Fuel Storage.Response Re Worst Case Skin Doses Projected Onsite & Worst Case Fuel Rod Rupture Provided ML20207F7261988-08-16016 August 1988 Forwards Endorsements 198 & 199,110 & 111 & 101 & 102 to Nelia Policies NF-43,NF-187,NF-201,respectively & Endorsements 172 & 173,93 & 94 & 89 & 90 to Maelu Policies MF-22,MF-54 & MF-64,respectively ML20155D2241988-06-0202 June 1988 Forwards Response to NRC Re Violations Noted in Insp Repts 50-010/88-02,50-237/88-07 & 50-249/88-08. Corrective Actions Withheld ML20154L8391988-05-27027 May 1988 Forwards Rev 24 to Security Plan to Correct & Make Current Identification on Number of Vital Area Doors on Various Levels.Rev Withheld (Ref 10CFR73.21) ML20154L7711988-05-19019 May 1988 Forwards Endorsements 197 to Nelia Policy NF-43,171 to Maelu Policy MF-22,50 to Nelia Policy NF-253,32 to Maelu Policy MF-104,109 to Nelia Policy NF-187 & 92 to Maelu Policy MF-54 ML20153G6091988-04-29029 April 1988 Forwards Environ Rept of Current Decommissioning Status of Dresden 1 & Decommisioning Program Plan for Dresden Nuclear Power Station Unit 1. Fee Paid ML20151U6961988-04-25025 April 1988 Forwards Endorsements 195 & 196 to Nelia Policy NF-43, Endorsements 169 & 170 to Maelu Policy MF-22,Endorsements 99 & 100 to Nelia Policy NF-201 & Endorsements 86 & 87 to Maelu Policy MF-64 1990-08-27
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. .. _ _ . . _ _ _ . _ _ - - - _
g _ .
G(C Commonwealth Edison '*
, ) One First N:tional Plaza. Chicago, Illinois G Addrgss R:pfy to. Post Office Box 767 Chicago, Ilhnois 60690 April 7, 1986
. Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Convaission Washington, DC 20555
Subject:
Dresden Station Units 2 and 3 Use of ASME Code Case N-411 NRC Docket Nos. 50-237 and 50-249
- References (a): Letter from J. R. Wojnarowski to H. R.
Denton dated April 1, 1986.
(b): Letter from J. R. Wojnarowski to H. R.
Denton dated September 30, 1985.
(c): ' Letter from E. G. Adensam to D. L. Farrar dated April 1, 1986.
Dear Mr. Denton:
4 On April 1, 1986 Commonwealth Edison Company issued Reference (a) to describe recently identified concerns regarding a re-analysis of the
- scismic loads for snubbers supporting the Recirculation Pumps for Dresden Units 2 and 3. This letter also documented that we had demonstrated ,
I compliance with FSAR requirements for the Safe Shutdown Earthquake (SSE) for the Dresden Unit 2 recirculation pump. supports using dcaping values from c.'
ASME Code Case N-411. The NRC Staff verbally concurred with the use of the damping values from ASME Code Case N-411 for this particular application during a conference call on March 25, 1986. Reference (a) documented that ,
conversation.
During a subsequent conversation on April 2, 1986, Messrs. B. D. i Liaw and R. LaGrange of your Staff expressed concerns that advanced !
analytical techniques from our September submittal (Reference (b)) were used in conjunction with ASME Code Case N-411. They stated that their previous concurrence had assumed FSAR methodologies would be used with N-411 damping.
They also questioned whether FSAR seismic spectra or spectra resulting from
^
the Systematic Evaluation Program (SEP) should be utilized for this evalua-tion, and indicated that they would pursue this question within the NRC
. Staff.
1 In response to the Staff's concerns regarding analytical techniques, Commonwealth Edison Company reanalyzed the Recirculation System piping using N-411 damping with FSAR methodologies and requirements. This reanalysis confirmed the original conclusion that the Recirculation Pump supports meet FSAR requirements for the SSE. The reanalysis also ccnfirmed that the first analysis, which used N-411 damping plus certain techniques from Reference r .(b), was conservative with respect to the analysis using N-411 damping plus 8604170237 860407 -
PDR ADOCK 05000237 P. PDR
H. R. Denton April 7, 1986 FSAR requirements. _The results of these two analyses are documented in Attachment A and were discussed with Messrs. Liaw and LaGrange on April 3, 1986. During that conversation Mr. Liaw again questioned the use of the FSAR seismic ground spectra rather than the seismic ground spectra developed during the SEP seismic re-evaluations performed for Dresden Unit 2. He stated that, since Dresden Unit 2 is an SEP plant, concurrence with the Recirculation Pump support evaluations should be pursued with staff members who are responsible for SEP.
During the April 3 conversation, Conunonwealth Edison Company indicated that the Recirculation Pump supports were also being evaluated on Dresden Unit 3. Mr. Liaw stated that the Staff concurred with the use of ASME Code Case N-411 in conjunction with FSAR requirements for the Dresden Unit 3 evaluations provided that these evaluations are consistent with the conditions described in References (a) and (c). Attachment B enumerates these conditions, and describes how they are satisfied by the Dresden Unit 3 evaluations of the Recirculation Pump supports.
Subsequent to the conversation with Messrs. Liaw and LaGrange, Conunonwealth Edison Company contacted Mr. J. Zwolinski, Director of BWR Project Directorate No.1, to discuss the questions regarding seismic ground spectra for Dresden Unit 2. Mr. Zwolinski agreed that the question of whether FSAR or SEP ground spectra should be used to evaluate compliance with the design bases is a larger issue which should be addressed at a later
-date during conversion of the Dresden Unit 2 Provisional Operating License into a Full Term Operating License. He also concurred that SEP seismic requirements are not the basis for determining operability of Dresden Unit 2 at this time. Accordingly, he agreed that the Recirculation Pump supports meet FSAR requiremente based on the analysis using M-411 damping with FSAR techniques and FSAR spectra. He indicated that this evaluation was acceptable in light of the Staff's concurrence with similar applications on Dresden Unit 3 and LaSalle Units 1 and 2.
The Dresden Unit 2 evaluation, using B-411 damping is similar to the applications at Dresden 3 and LaSalle. The same piping system is analyzed in both Dresden units, namely the Recirculation System, using similar analytical models. The major difference between these Dresden models is that the crossover piping from Loop A to Loop B has been removed on Dresden Unit 3. Further, the analyses for all units, including Dresden 2, satisfy all of the conditions described in References (a) and (c) regarding the use of N-411 damping for piping sections. Based on these correlations to similar applications, Mr. zwolinski further concurred with returning Dresden Unit 2 to service following its current outage, and stated that the Recirculation Pump support evaluation is satisfactory for continued operation.
Following this telephone conversation, Mr. Zwolinski confirmed the above conclusions with Mr. C. Grimes from the Integrated Safety Assessment Project Directorate. Mr. Grimes also felt that the relationship between SEP i
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H. R. Denton - April 7, 1986 l
seismic requirements and the FSAR needs to be ultimately resolved. Regarding this issue, it is Edison's position that the current design basis for seismic analyses and qualifications is ss described in FSAR Section 12.1.1.3. It is our understanding that the SEP seismic evaluations were intended to assess safety marsins available in plants designed prior to promulgation of the current seismic regulations. Accordingly, we believe SEP requirements do not replace the FSAR as the plant design basis. We believe that the final resolution of the relationship between SEP evaluations and the design and licensing basis for the plant will be resolved upon completion of the Systematic Evaluation Program and in conjunction with the conversion to a full term operating license.
This letter is being provided as requested by Mr. Zwolinski to document the evaluations performed in support of continued operation of Dresden Unit 2. We request your concurrence that the use of ASME Code Case N-411 is acceptable for this application when it is applied in conjunction with FSAR requirements and spectra, and when it is used within the limitations described in Attachment B. We are available for continued conversations with your Staff regarding the SEP requirements and the plant design basis as described in the FSAR. Any SEP requirements that are ultimately concluded to be appropriate licensing basis requirements would be documented in revisions to the updated FSAR such that the original and updated FSAR continue to reflect the licensing basis for Dresden Unit 2.
If you have any further questions regarding this matter, please contact this office.
Very truly yours, 4 * /
J. R. jnarowski Nuclear Licensing Administrator l
im Attachments cc: J. A. Zwolinski - NRR B. D. Liaw - NRR R. A. Gilbert - NRR J. J. Harrison - Region III Region III Inspector - Dresden 1504K
ATTACHMENT A DRESDEN UNIT 2 -- COMPARATIVE' ANALYSES The purpose of this attachment is to sunmarize two analytical techniques used to evaluate the Recirculation Pump supports on Dresden Unit
- 2. The model shown in Figure 1 was used for each analysis. Essentially, this model consists of two pumps, four major risers, two loop headers, and crossover piping between the Loops A and B headers. Boundary conditions for this model were as follows:
- Anchored at the Reactor Vessel (12 places)
- Supportod with snubbers on both loops and the discharge risers (4 places)
- Supported at six points on each pump with six snubbers and three constant hangers Each Recirculation Pump was modeled as shown on Figure 2. These pumps were included in the piping model in order to obtain pump snubber loads. A lumped mass model of the pump was used with masses distributed along the length of the model to most accurately distribute loads into the pump supports. The pump, as modeled, has a least natural frequency of approximately 25 hertz. Thus, the pump does not respond within the range of frequencies affected by Code Case N-411 (i.e., O to 20 hertz).
Both analyses used the same FSAR/N-411 spectra as input. Analytical techniques used for each of these methods are summarized below.
Method A -- Y-411 plus FSAR All FSAR analysis techniques, with the exception of N-411 damping, were followed for thic option. This method reflects the current design basis for Dresden Unit 2. Those techniques corresponding to Method A are listed below.
- 1) PVRC damping (ASME Code Case N-411) ii) Modal combination by SRSS iii) Direction combination using the largest horizontal response added absolutely with the vertical.
iv) Dynamic analysis of all modes up to 33 hertz.
v) Enveloped spectra for the piping center of mass.
vi) FSAR stress criteria.
Method B -- N-411 plus September submittal The techniques used for this analysis were consistent with the September submittal, Alternate 2, Piping Analysis Option (c), with one exception. Technique (c)vil (peak shifting) was not used. Those techniques that were used are as follows:
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- 1) PVRC damping (ASME Code Case N-411)
- 11) Modal combination by SRSS iii) Direction combination by Regulatory Guide 1.92.
iv) Modal analysis to 33 hertz, with higher frequency effects, v) Enveloped spectra for the piping system.
vi) FSAR stress criteria.
Results from these two analyses are provided in Table A-1. These results show that Method B, the September submittal, is more conservative than Method A which is the current design basis.
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TABLE A-2 COMPARATIVE ANALYSIS RESULTS METHOD A METHOD B ITEM (FSAR/N-411) (submittal /N-411)
Loop A Loop B Loop A Loop B Pump Snubber Loads (k)
-SS1' 7 12 16 20
-SS2A 12 15 13 16
-SS2B 22 17 35 29
-SS3A 16 17 34 39
-SS3B 5 10 39 44
-SS4 14 9 22 14 Pipe Stresses (ksi)1 18 18 Pump Nozzle Loads (k. ft)2
- FK 8 12
- FY 8 10
- FZ 6 7
- MK 42 54
- NY 71 76
- NZ 48 56
- 1) Maximum stress from ASME Equation 9(e) which occurs at a different location with Method A versus B
- 2) Loop B discharge SSE inertial loads 4
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ATTACHMENT B CONDITIONS FOR ACCEPTANCE OF N-411 ON DRESDEN UNITS 2 AND 3 Reference (c) to this letter documents the NRC Staff authorization to use ASME Code Case N-411 on LaSalle Units 1 and 2. Some specific conditions apply to its use, pending a revision to Regulatory Guide 1.61.
These conditions are repeated below:
(1) The application of the Code Case shall be limited to piping systems analyzed by the response spectrum method only.
(2) The alternate damping criteria of the Code Case shall be used in their entirety in any given analysis. Mixed application of the Code Case and Regulatory Cuide 1.61 is not permitted.
(3) Due to the increased flexibility of the system, the user shall check all recalculated displacements to verify there is adequate clearance between the piping system and adjacent structures, components, and equipment, and to verify the ability of mounted equipment to withstand the increased motion.
(4) The user shall clearly indicate whether the Code Case will be used for new analyses, for reconciliation work, or for support optimizations.
Reference (c) contains one other condition for acceptance relative to application of N-411 damping for the Recirculation Pump Supports evalua-tions on Dresden Units 2 and 3. This additional condition stipulates that the Code Case is applicable only to piping sections. In other words, the NRC Staff does not consider N-411 damping to be applicable to major components. If major components are modeled with the piping, the l applicability of Code Case N-411 to such a model will be determined by the '
Staff on a case-by-case basis.
Conformance to each of these conditions is demonstrated in the following paragraphs specifically for the Recirculation Pump Supports on l Dresden Units 2 and 3. I Condition (1) - Response Spectrum All dynamic analyses have been performed using standard, response spectrum methods.
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Condition (2) - Consistent Damping Criteria The seismic anlayses use Code Case N-411, only. Other damping criteria, such as Reg. Guide 1.61, are not mixed with N-411 damping.
Condition (3) - Effect of Increased Flexibility These analyses are being performed to evaluate seismic loads developed in the Recirculation Pump supports. The existing support system is being reconciled, so there is no change to the flexibility of that system.
It is our understanding that this condition applies particularly to support optimization evaluations, which are not being done for this application.
Condition (4) - Application Purpose As stated above, these evaluations are being performed only to <
reconcile the existing configuration. Code Case N-411 is not being used as I the design basis for the recirculation pipe replacement effort on Dresden Unit 3.
Additional Condition - Major Components Attachment A discusses the Dresden Unit 2 model and provides justification for including the Recirculation Pumps in the N-411 evaluation.
The same justifications apply to the Dresden Unit 3 model. As for Dresden Unit 2,the Dresden Unit 3 pump model has a fundamental natural frequency beyond the range of frequencies influenced by Code Case N-411.
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Based on the above discussion, Commonwealth Edison feels that the use of ASME Code Case N-411 is appropriate for application to the Recirculation Pump supports on Dresden Units 2 and 3.
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