|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196J4111999-06-30030 June 1999
Summary of 990524 Meeting with Util in Rockville,Md to Discuss Technical Issues Re Proposed Rerack of Spent Fuel Pool at Plants.List of Attendees & Handouts Encl
ML20217H8081998-03-31031 March 1998
Summary of 980306 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.List of Attendees Encl
ML20199A5071998-01-16016 January 1998
Summary of 971211 Meeting W/Comed in Rockville,Maryland Re Additional Justification for Proposed Methodology for Estimating voltage-dependent Growth Rates of Outer Diameter Stress Corrosion Crack Indications Left in Service
ML20211P3421997-09-23023 September 1997
Summary of 970904 Meeting W/Commonwealth Edison Co in Rockville,Md Re Methodology for Calculating Radiation Doses in Control Room & at Eab & LPZ in Event of Msb Outside Containment.List of Attendees & Licensee Presentation Encl
ML20210Q1281997-08-25025 August 1997
Summary of 970723 Meeting W/Util in Rockville,Md Re Util Assessment of Spring 1997 Eddy Current Insp of Plant SG Tubes.List of Attendees & Handouts Presented Encl
ML20141F3641997-06-27027 June 1997
Summary of 970430 Meeting W/Licensee in Rockville,Md to Discuss Various Aspects of SG Eddy Current Insp Conducted at Plants During Spring 1997 Refueling Outage.List of Attendees & Licensee Handouts Encl
ML20138L0741997-02-18018 February 1997
Summary of 970123 Meeting W/Commonwealth Edison Co to Discuss Plant Amend Request to Convert Current TSs
ML20134M3841997-02-13013 February 1997
Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl
ML20134G7011997-02-0707 February 1997
Summary of 970122 Meeting W/Util Re Program for Replacement of SG at Licensee Facilities.List of Attendees & Matl Used in Presentation Encl
ML20133J0641997-01-13013 January 1997
Summary of 960821 Meeting W/Comed to Discuss Status of SG Replacement Program W/Nrc Staff.List of Attendees & Util Presentation Encl
ML20149M3131996-12-10010 December 1996
Summary of 961114 Meeting W/Representives of CE in Rockville,Md to Discuss Status of Ongoing Braidwood,Unit 1, SG Tube Insp.List of Attendees & Slides Encl
ML20129F9431996-10-25025 October 1996
Summary of 961004 Meeting W/Representatives of CE in Rockville,Md to Discuss Technical Basis for Licensee Pending Proposal to Delete Braidwood Unit 1 mid-cycle SG Eddy Current Insp.List of Attendees & Matls Discussed Encl
ML20129G8501996-07-0505 July 1996
Summary of ACRS Joint Subcommittee Matl & Metallurgy & Severe Accidents Meeting on 960603-04 to Gather Info on Status of Activities Associated W/Development of Proposed Rule Re SG Integrity
ML20217D4661995-12-0404 December 1995
Summary of 950911 Meeting W/Commonwealth Edison Re Util Commitment to Improving Dresden,Matl Condition at Zion, Declining Performance at Braidwood & Comed Resources
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20062C8111990-10-16016 October 1990
Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl
ML20247M7961989-05-24024 May 1989
Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl
ML20206L9831988-11-25025 November 1988
Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20245D8411988-09-28028 September 1988
Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl
ML20148S3821988-03-31031 March 1988
Summary of Operating Reactors Events Meeting 88-13 on 880329.List of Attendees,Discussion of Events & Summary of Reactor Scrams Encl
ML20235Z5891987-10-0808 October 1987
Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl
ML20236F4571987-07-13013 July 1987
Summary of 870620 Meeting W/Util,Isham,Lincoln & Beale & Business & Professional People for Public Interest in Bethesda,Md to Provide Info to Assist in Determination of Significant Hazards Consideration Re Transfer of Ownership
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214P0201987-05-28028 May 1987
Summary of 870513 Meeting W/Util,Inel & Environ Sys Corp in Bethesda,Md Re Essential Svc Water Cooling Tower Test Program.List of Attendees & Viewgraphs Encl
ML20214F6731987-05-18018 May 1987
Summary of 870514 Meeting W/Util Re Review of Status of Pending Licensing Actions on Util Plants.Meeting Agenda & List of Attendees Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20206J9221987-04-0606 April 1987
Summary of 870318 Meeting W/Util in Bethesda,Md Re Util Proposal to Transfer Ownership of Facilities.Attendees List & Description of Agreement Between Util,Govt Entities & Industrial Users Encl
ML20205K7591986-12-31031 December 1986
Summary of ACRS 320th Meeting on 861211-13 in Washington,Dc Re New Requirements for BWR Mark I Containments in Regard to Severe Accidents & Proposal for Commission Policy Statement on Deferred Plants (SECY-86-359)
ML20215C9961986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-41 on 861124.List of Attendees,Events Discussed & Significant Event Elements & Summary of Events That Will Be Input to NRC Performance Indicator Program Encl
ML20215N6001986-11-0303 November 1986
Summary of 861021 Meeting W/Util & Sargent & Lundy in Bethesda,Md Re Design of Diesel Generators to Ensure Testing Does Not Impair Capability of Providing Emergency Power. Facility Design Unacceptable
ML20206P9561986-08-0808 August 1986
Summary of 860725 Meeting W/Util & Westinghouse Re Program to Reduce Hot Leg Temp at Facility.List of Attendees & Slide Presentation Encl
ML20203H6561986-07-28028 July 1986
Summary of 860708-09 Meetings W/Util & Eg&G in Bethesda,Md Re Program for Inservice Testing of Pumps & Valves.List of Attendees & Questions & Answers Encl
ML20207E2811986-07-16016 July 1986
Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20211G9361986-06-0606 June 1986
Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20202J2231986-04-0404 April 1986
Summary of 860204 Meeting W/Util,Sargent & Lundy & Carboline Co in Bethesda,Md Re Mods to Containment Liner Coating Sys. Util Will Submit Test Repts Supporting Conclusion That Sys Meets ANSI Stds.W/O Stated Encls
ML20154K2171986-03-0505 March 1986
Summary of Allegation Review Board 860210 Meeting.Listed Actions to Close Allegations RIII-86-A-002,RIII-86-A-0007, RIII-86-A-011,RIII-85-A-0188,RIII-85-A-0208 & RIII-86-A-003 Agreed Upon
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20137P2591986-01-24024 January 1986
Summary of 851203 & 06 Meetings W/Util,Bnl & Westinghouse in Bethesda,Md to Review Limiting Conditions for Operation Relaxation Program.Attendance Lists & Meeting Viewgraphs Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20141E5521985-09-26026 September 1985
Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl
ML20134G4121985-08-20020 August 1985
Summary of 850815 Meeting W/Bnl,Util,Westinghouse & Bechtel in Bethesda,Md Re Limiting Conditions for Operation Relaxation Program.Attendance List & Slide Presentation Encl
ML20128A9061985-05-13013 May 1985
Summary of 850507 Operating Reactors Events Meeting.List of Attendees,Events Discussed & Assignments Encl
ML20127N2591985-03-25025 March 1985
Summary of ACRS Subcommittee 850129 Meeting in Washington,Dc Re Review of Util Application for License.Schedule of Presentations & List of Attendees Encl
ML20205T5371983-02-15015 February 1983
Trip Rept of 830126 Meeting in Bethesda to Discuss Question of Corrective Actions to Be Required of Util Re Finding of Uncertified QC Inspectors at Site
1999-06-30
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20196J4111999-06-30030 June 1999
Summary of 990524 Meeting with Util in Rockville,Md to Discuss Technical Issues Re Proposed Rerack of Spent Fuel Pool at Plants.List of Attendees & Handouts Encl
ML20217H8081998-03-31031 March 1998
Summary of 980306 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.List of Attendees Encl
ML20199A5071998-01-16016 January 1998
Summary of 971211 Meeting W/Comed in Rockville,Maryland Re Additional Justification for Proposed Methodology for Estimating voltage-dependent Growth Rates of Outer Diameter Stress Corrosion Crack Indications Left in Service
ML20211P3421997-09-23023 September 1997
Summary of 970904 Meeting W/Commonwealth Edison Co in Rockville,Md Re Methodology for Calculating Radiation Doses in Control Room & at Eab & LPZ in Event of Msb Outside Containment.List of Attendees & Licensee Presentation Encl
ML20210Q1281997-08-25025 August 1997
Summary of 970723 Meeting W/Util in Rockville,Md Re Util Assessment of Spring 1997 Eddy Current Insp of Plant SG Tubes.List of Attendees & Handouts Presented Encl
ML20141F3641997-06-27027 June 1997
Summary of 970430 Meeting W/Licensee in Rockville,Md to Discuss Various Aspects of SG Eddy Current Insp Conducted at Plants During Spring 1997 Refueling Outage.List of Attendees & Licensee Handouts Encl
ML20138L0741997-02-18018 February 1997
Summary of 970123 Meeting W/Commonwealth Edison Co to Discuss Plant Amend Request to Convert Current TSs
ML20134M3841997-02-13013 February 1997
Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl
ML20134G7011997-02-0707 February 1997
Summary of 970122 Meeting W/Util Re Program for Replacement of SG at Licensee Facilities.List of Attendees & Matl Used in Presentation Encl
ML20133J0641997-01-13013 January 1997
Summary of 960821 Meeting W/Comed to Discuss Status of SG Replacement Program W/Nrc Staff.List of Attendees & Util Presentation Encl
ML20149M3131996-12-10010 December 1996
Summary of 961114 Meeting W/Representives of CE in Rockville,Md to Discuss Status of Ongoing Braidwood,Unit 1, SG Tube Insp.List of Attendees & Slides Encl
ML20129F9431996-10-25025 October 1996
Summary of 961004 Meeting W/Representatives of CE in Rockville,Md to Discuss Technical Basis for Licensee Pending Proposal to Delete Braidwood Unit 1 mid-cycle SG Eddy Current Insp.List of Attendees & Matls Discussed Encl
ML20129G8501996-07-0505 July 1996
Summary of ACRS Joint Subcommittee Matl & Metallurgy & Severe Accidents Meeting on 960603-04 to Gather Info on Status of Activities Associated W/Development of Proposed Rule Re SG Integrity
ML20217D4661995-12-0404 December 1995
Summary of 950911 Meeting W/Commonwealth Edison Re Util Commitment to Improving Dresden,Matl Condition at Zion, Declining Performance at Braidwood & Comed Resources
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20062C8111990-10-16016 October 1990
Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl
ML20247M7961989-05-24024 May 1989
Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl
ML20206L9831988-11-25025 November 1988
Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20245D8411988-09-28028 September 1988
Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20151N0521988-07-26026 July 1988
Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl
ML20148S3821988-03-31031 March 1988
Summary of Operating Reactors Events Meeting 88-13 on 880329.List of Attendees,Discussion of Events & Summary of Reactor Scrams Encl
ML20235Z5891987-10-0808 October 1987
Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl
ML20236F4571987-07-13013 July 1987
Summary of 870620 Meeting W/Util,Isham,Lincoln & Beale & Business & Professional People for Public Interest in Bethesda,Md to Provide Info to Assist in Determination of Significant Hazards Consideration Re Transfer of Ownership
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214P0201987-05-28028 May 1987
Summary of 870513 Meeting W/Util,Inel & Environ Sys Corp in Bethesda,Md Re Essential Svc Water Cooling Tower Test Program.List of Attendees & Viewgraphs Encl
ML20214F6731987-05-18018 May 1987
Summary of 870514 Meeting W/Util Re Review of Status of Pending Licensing Actions on Util Plants.Meeting Agenda & List of Attendees Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20206J9221987-04-0606 April 1987
Summary of 870318 Meeting W/Util in Bethesda,Md Re Util Proposal to Transfer Ownership of Facilities.Attendees List & Description of Agreement Between Util,Govt Entities & Industrial Users Encl
ML20205K7591986-12-31031 December 1986
Summary of ACRS 320th Meeting on 861211-13 in Washington,Dc Re New Requirements for BWR Mark I Containments in Regard to Severe Accidents & Proposal for Commission Policy Statement on Deferred Plants (SECY-86-359)
ML20215C9961986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-41 on 861124.List of Attendees,Events Discussed & Significant Event Elements & Summary of Events That Will Be Input to NRC Performance Indicator Program Encl
ML20215N6001986-11-0303 November 1986
Summary of 861021 Meeting W/Util & Sargent & Lundy in Bethesda,Md Re Design of Diesel Generators to Ensure Testing Does Not Impair Capability of Providing Emergency Power. Facility Design Unacceptable
ML20206P9561986-08-0808 August 1986
Summary of 860725 Meeting W/Util & Westinghouse Re Program to Reduce Hot Leg Temp at Facility.List of Attendees & Slide Presentation Encl
ML20203H6561986-07-28028 July 1986
Summary of 860708-09 Meetings W/Util & Eg&G in Bethesda,Md Re Program for Inservice Testing of Pumps & Valves.List of Attendees & Questions & Answers Encl
ML20207E2811986-07-16016 July 1986
Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20211G9361986-06-0606 June 1986
Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl
ML20197F1691986-05-0808 May 1986
Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20141F4091986-04-10010 April 1986
Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl
ML20202J2231986-04-0404 April 1986
Summary of 860204 Meeting W/Util,Sargent & Lundy & Carboline Co in Bethesda,Md Re Mods to Containment Liner Coating Sys. Util Will Submit Test Repts Supporting Conclusion That Sys Meets ANSI Stds.W/O Stated Encls
ML20154K2171986-03-0505 March 1986
Summary of Allegation Review Board 860210 Meeting.Listed Actions to Close Allegations RIII-86-A-002,RIII-86-A-0007, RIII-86-A-011,RIII-85-A-0188,RIII-85-A-0208 & RIII-86-A-003 Agreed Upon
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20137P2591986-01-24024 January 1986
Summary of 851203 & 06 Meetings W/Util,Bnl & Westinghouse in Bethesda,Md to Review Limiting Conditions for Operation Relaxation Program.Attendance Lists & Meeting Viewgraphs Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20141E5521985-09-26026 September 1985
Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl
ML20134G4121985-08-20020 August 1985
Summary of 850815 Meeting W/Bnl,Util,Westinghouse & Bechtel in Bethesda,Md Re Limiting Conditions for Operation Relaxation Program.Attendance List & Slide Presentation Encl
ML20128A9061985-05-13013 May 1985
Summary of 850507 Operating Reactors Events Meeting.List of Attendees,Events Discussed & Assignments Encl
ML20127N2591985-03-25025 March 1985
Summary of ACRS Subcommittee 850129 Meeting in Washington,Dc Re Review of Util Application for License.Schedule of Presentations & List of Attendees Encl
ML20054F2861982-05-27027 May 1982
Summary of 820506 Meeting W/Util & Sargent & Lundy in Bethesda,Md Re Program for Seismic Qualification of Equipment
1999-06-30
[Table view] |
Text
. - . .-. _ . - . _ _ - _ .- - . _ _ _ - _ . . _ _ _ - - - - . . - - - _ . _ - _ _ _ _
pio "~N t UNITE 3 STATES j
gg ]%E ,g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C 80MH001 p
, 9 , , , , *#., September 23, 1997 LICENSEE: Commonwealth Edison Company FACILITIES: BYRON STATION, U"lT 1, AND BRAIDWOOD STATION, UNIT 1
SUMMARY
SUMMARY
OF SEPTEMBER 4, 1997, MEETING ON COMED'S METHODOLOGY FOR CALCULATING RADIATION EXPOSURE DOSES IN THE EVENT OF AN MSLB OUTSICE CONTAINMENT.
A meeting between members of the NRC staff and representatives of Commonwealth Edison Company (comed, the licensee) was held in Rockville, Maryland on September 4, 1997. A list of attendees is provided as Enclosure 1. A copy of Comed's slides presented at the meeting is provided as Enclosure 2.
The purpose of the meeting was to discuss Comed's methodology for calculating radiation doses in the control room, and at the exclusion area boundary (EAB) and at the low population zone (LPZ) in the event of a main steamline break (MSLB) outside containment. This discussion represented part of the staff's review effort on Comed's pending license amendment request dated January 31, 1997. This request would reduce the maximum allowable value in the Byron Station Technical Specifications (TS) of the dose equivalent (DE) iodine-131 concentration in the primary coolant from 0.35 to 0.20 microcuries per gram.
This reduction in the DE I-131 concentration is necessitated by the increase in the end of cycle (EOC) projected steam generator tube leakage in the present fuel cycle under MSLB conditions over that estimated for prior fuel ;
cycles.
The Comed presentation focused on both the methodology for determining the meteorological dispersion of primary coolant activity released outside l containment and the subsequent calculation of the radiation exposure doses in ;
the control room, and at the EAB and LPZ. Comed concluded in its assessment l that at the proposed Byron. Unit 1. TS value of 0.20 microcuries per gram for '
the DE I-131 concentration, General Design Criterion (GDC) 19 requirements for l control room personnel are met. Comed also concluded that in the event of an l MSLB at Byron, Unit 1, the radiation doses at the EAB and LPZ would not exceed !
a small fraction of the guideline values for radiation exposure in 10 CFR l Part 100.
While the meeting was primarily focused on Byron, Unit 1 Comed also presented a discussion of the radiation doses at Braidwood, Unit 1, since it had proposed a similar license amendment request to reduce the TS limit of the DE I-131 primary coolant concentration in Braidwood from 0.35 to 0.10 microcuries per gram. (This license amendment request for Braidwood, Unit 1, was submitted in a letter dated September 2,1997.) \
At the conclusion of this meeting, the staff stated that based upon its QD b 1 independent calculations and its understanding of the material presented at this meeting, it believed that the Comed license amendment for Byron, Unit 1, I
[, 0 v ) ,' O , , n 9710200169 970923 PDR ADOCK 05000454 m,p P PDR QQ f ff&
}
i could be found acceptable. The staff also stated that to the extent that the pending Braidwood, Unit 1, license amendment used the same methodology for j calculating radiation exposures as contained in the pending Byron, Unit 1, i license amendment request, it could also find the similar Braidwood, Unit 1 I license amendment request to be acceptable. Finally, the staff requested Comed to clarify certain portions of its submittals dated August 21 and August 22, 1997.
NelntjSinnedBT.
. l l M. David Lynch, Senior Project Manager
! Project Directorate 111-2 Division of Reactor Projects - !!!/lV l Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-456
Enclosures:
- 1. List of Meeting Attendees
- 2. Licensee Presentation cc w/encis: See next page DISTRIBUTION:
Docket (w/ enc 1 1 and 2)
PUBLIC (w/ enc 1 1 and 2)
PDill-2 r/f (w/enci 1 and 2)
OGC, 015B18 ACRS. T2E26 R. Lanksbury, RDL (w/ enc 1 1 and 2)
D. Lynch, MDL (w/ encl 1 and 2)
E-JiAIL:
S. Collins /F, Miraglia, SJC1/FJM R. Zimmerman, RPZ E. Adensam R. Capra, RACI C. Moore, ACM G. Tracy, GMT T. Martin (e-mail to SLM3)
C. Miller R. Emch S. Bailey C. Ilinson L. Brown DOCUMENT NAME:G:\CMNTJR\ BRAID-BY\BB0904. SUM in receive a cop / of twt, Irvi'cate in k boa 4*
- Copy without enclosures *E' s Copy with e nclosures *N" = No copy 0FFICE SM2Q%P h I l 1,A:M3-/ l60:PD3-2 ls NAME 4DrffM deiO0iW/{ RCAPRA &
OATE 09&C/97 09/h(/97) ,09/25/97 0fTICIAL RECORD COPY o
a could be found acceptable. The staff also stated that to the extent that the pending Braidwood, Unit 1 license amendment used the same methodology for calculating radiation expo,sures as contained in the pending Byron, Unit 1, license amendment request, it could also find the similar Braidwood, Unit 1, license amendment request to be acceptable. Finally, the staff requested Comed to clarify certain portions of its submittals dated August 21 and August 22, 1997.
M o h l $10M d B T-M. Uavid Lynch, Senior Project Manager Project Directorate 111-2 Division of Reactor Projects - !!!/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-456
Enclosures:
- 1. List of Meeting Attendees
- 2. Licensee Presentation I
cc w/encis: See next page )
DISTRIBUTION:
Docket (w/ enc 1 1 and 2)
PUBLIC (w/ enc 1 1 and 2)
PDill-2 r/f (w/ enc 1 1 and 2)
OGC, 015818 ACRS, T2E26 R. Lanksbury,-RDL (w/ enc 1 1 and 2)
D. Lyr h, MDL (w/ enc 1 1 and 2)
E-MAIL:
S. Collins /F. Miraglia, SJC1/FJM R. Zimmerman, RPZ E. Adensam R. Capra, RACI C. Moore, ACM G. Tracy, GMT T. Martin (e-mail to SLM3)
C. Miller R. Emch S. Bailey C. Hinson L. Brown DOCUMENT NAME:G:\CHNTJR\ BRAID-BY\BB0904. SUM T3 receive a cepr of tede <bcument. Indicate in khon: PC* a copy without enclosures *E' = Copy with enclosures si,= a 160 copy
~
0FFICE J+i22&P T T l 1, A: P.03-1 lL-8: P03-2 ls NAME 49f h Otm6ftr/l RCAPRA >
DATE 09 R /97 09/N/9M 09/25 /97 0FTICIAL RECORD COPY
Duld be found acceptable. The staff also stated that to the extent that the
)ndin0 Braidwood, Unit 1, license amendment used the same methodology for 31culating radiation exposures as contained in the pending Byron, Unit 1
) cense amendment request, it could also find the similar 13raidwood, Unit 1,
) cense amendment request to be acceptable. Finally, the staff requested q smEd to clarify certain portions of its submittals dated August 21 and sgust 22, 1997.
\
m0 -
M. David Lynch, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation cket Nos. STN 50-454, STN 50-456 belosures: 1. List of Meeting Attendees
- 2. Licensee Presentation (
(c/encis: See next page
.i --
I. Johnson Byron /Braidwood Power Stations Comonwealth Edison Company cc: ,
Mr. William P. Poirier, Director George L. Edgar Westinghouse Electric Corporation Morgan, Lewis and Bochius Energy System. Business Unit 1800 M Street N.W.
Post Office Box 355, Bay 236 West Washington, DC 20036 Pittsburgh, Pennsylvania 15230 Attorney General Joseph Gallo 500 South Second Street Gallo & Ross Springfield, Illinois 62701 1250 Eye St., N.W.
Suite 302 EIS Review Coordinator Washington, DC 20005 U.S. Environmental Protection Agency 77 W. Jackson Blvd.
Michael I. Miller, Esquire Chicago, Illinois 60604-3530 Sidley and Austin One First National Plaza Illinois Department of Chicago, Illinois 60603 Nuclear Safety Office of Nuclear Facility Safety Howard A. Learner 1035 Outer Park Drive
- Environmental law and Policy Springfield, Illinois 62704 l
Center of the Midwest 203 North LaSalle Street Comonwealth Edison Company Suite 1390 Byron Station Manager Chicago, Illinois 60601 4450 North German Church Road Byron, Illinois 61010 U.S. Nuclear Regulatory Comission Byron Resident inspectors Office Kenneth Graesser, Site Vice President 4448 North German Church Road Byron Station Byron, Illinois 61010-9750 Comonwealth Edison Station 4450 N. German Church Road Regional Administrator, Region III Byron, Illinois 61010 U.S. Nuclear Regulatory Comission 801 Warrenville Road U.S. Nuclear Regulatory Comission Lisle, Illinois 60532-4351 Braidwood kosident Inspectors Office Rural Route #1, Box 79 Ms. Lorraine Creek Braceville, Illinois 60407 Rt. 1, Box 182 Manteno. Illinois 60950 Mr. Ron Stephens Illinois Emergency Services Chairman, Ogle County Board and Disaster Agency Post Office Box 357 110 East Adams Street Oregon Illinois 61061 Springfield, Illinois 62706 Mrs. Phillip B. Johnson Chairman 1907 Stratford Lane .Will County Board of Su)ervisors Rockford Illinois 61107 Will County Board Court 1ouse Joliet, Illinois 60434 r
__ _ _ _ _ . _ _ _ - _ _ _ _ - - _ . . . - _ . _ _ _ _ _ _ _ _ _ _ _ - ~ . . . _ - _ _ _ _ _ _ _ . _ _
Commonwealth Edison Company Braidwood Station Manager Rt. 1, Box 84 Braceville, Illinois 60407 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Mr. H. G. Stanley Site Vice President Braidwood Station Commonwealth Edison Company-RR 1, Box 84 Bracev111e, IL 60407 l
4
_ _s,_ . _ . , . _ , , - . - - - -----.- , ,- - -
,. - ,. - - - - ~ --
. ATTENDANCE AT THE 09/04/97 COMED HEETING 4
t@_E AFFillATION M.D. Lynch NRR/PDill-2 R. Emch NRR/PERB C. Miller NRR/PERB R. Capra NRR/PC?.ll-2 S. Bailey NRR/PDill-2 C. Hinson NRR/PERB
.. Brown NRR/PERB G. Lahti Comed J. Bradley Murray & Trettel M. Sears Comed D. Saccomando Comed J. Meister Comed D. Wozniak Comed M. Marchiunda Comed G. Gaydes Bechtel J. Hosmer Comed J. Blomgren Comed i
ENCLOSURE 1
Comed /NRC Steam Generator Dose Assessment Meeting September 4,1997 Rockville, hO l
Agenda Introduction J. Blomgren Meeting Objectiv5s J. Blomgren Control Room Assessment J. Lahti Site Boundary Assessment J. Lahti Conclusions J. Blomgren ENCIASURE 2
~
Objectives
- Defme Byron & Braidwood Licensing Basis for Dose Assessment
- Demonstrate that Byron 1 & Braidwood 1 are Within their Licensing Basis for Full Cycle Operation with:
< 0.2 pei/gm DE l 131 in RCS Byron 1
< 0.1 pei/gm DE I 131 in RCS Braidwood 1
- Provide Inputs to Allow NRC to Develop Independent Calculations
- Obtain Concurrence of the NRC Staff for Reduced RCS DE l-131 Limits for Remainder of Current Cycle Assessment Conclusions
- At Proposed RCS DE I-131 Limits Byron 1 and Braidwood 1
- Meet GDC 19 (Control Room) Requirements with Margin
- Meet 10 CFR 100 (Offsite Dose) Requirements with Margin
- Meet Current Licensing Basis
- Byron 1 and Braidwood I are safe to Operate Full Cycle
l Licensing Basis 10 CFR 50 Appendix A (GDC 19) )
- ControlRoom(CR) Habitability
- Exclusion Area Boundary (EAB)
- Low Population Zone Boundary (LPZ)
Event Duration
- CR Duration of the acc; J .mt (LOCA 30 days)
- EAB 2 hrs
- LPZ 30 days or duration of accident I
a Control Room Requirements Meet 10 CFR 50 Appendix A (GDC 19)
- 5 Rem to Whole Body
- 30 Rem to Thyroid
=
~w g.s,me . w w en -v-- .+,ew .w- o o wwe - o ww. 4 . _ , .
t 4
ControlRoom Approach Evaluate MSLB by Comparison to Existing Plant Licensing Basis, LOCA
Conclusion:
MSLB Accidents Are Conservatively Bounded by Existing LOCA Scenarios for Control Room Dose;
. Therefore, Meet GDC 19 Dose Calculation Dose = [ DE I-131 Curie Release ]
x [ X/Q ]
x [Other Factors Including Breathing Rate, DCFs, HVAC Filters]
- = - - - - - - -
m eowo - ---e - m-vm w 4-w e4,~--,-mew-w"~~-.* -
w w - - n---,-
..-W --o- . - ,- c2-,-- w-
4 I
Dose Calculation Dose = [ DE I-131 Curie Release ] '
x [ X/Q ]
x [Other Factors Including Breathing j Rate, DCFs, HVAC Filters]
)
Curie Release Methodology Accident Initiated Spike Ci = LR
q,6,3 x;iw x 3 y 6 *a' "*->
C(t)
Aw r9 73 spm Letdown Clean-up now (Accideni Sphe Only) t = Yime After Accident (sec) C1 - Total Curie Release (Ci) l LR = Primary to Secondary Leak Rate (gpm) C(t) = Primary Coolant Concentration (pcus)
Concentration varies with Time
Conclusion:
LOCA Release is Limiting m er 4 -. , -. ----m --_w , e wy-
l 1
Dose Calculation Dose = [ DE I-131 Curie Release ] ;
x [ X/Q ]
x [Other Factors Including Breathing Rate, DCFs, HVAC Filters]
LOCA Vs MSLB Leakage Locations 7
bim a
/
t
,,,,,_, e , r==e- - . ,
= 3, -
1 I
Murphy - Campe Conditions 1
- Leaks From Many Points on the Surface of I Containment (Diffuse Source)
- Single Point Receptor l
l LOCA Control Room X/Q Model
- Murphy - Campe Paper (1974)
- Equation 6 (Diffuse Source - Point Receptor)
+ X/Q = (K + 2) / U A U = Wind Speed A = Building Cross Sectional Area K = 3 / (S / d)14 S = Distance from Containment Surface to Receptor Location d - Diameter of Containment
- Licensing Basis for Byron and Braidwood
LOCA Control Room X/Q Parameters
- (Reference UFSAR Table 6.4 - 1a) )
l A = 2700 m2 S = 100 ft d = 147 ft K = 5.169 1
U = 0.67 m/sec (Byron)
(0 - 8 hr) X/Q = 4.05 x 10 3 s/m3 (Byron)
U = 0.43 m/sec (Braidwood) !
3 (0 - 8 hr) X/Q = 6.24 x 10 2 s/m (Braidwood)
Dose Calculation .
}0Se = [ DE I-131 Curie Release ]
x [ X/Q ]
x [Other Factors Including Breathing Rate, DCFs, HVAC Filters]
e-" e -m%,
eee..e em m mee-w- ..-...mams4..,<.~. -
. r e
(
LOCA Control Room Habitability :
Assessment !
/
/
Marv hemes j Ym -
..- io.. e 6.
i m u., T- f- -
- c. oe - ds t
- l i,l PAan%e Tumme Dies Fisse 88'*** Casseillass in Tuneas fuMme bids me,<w a ese ties nia ese r3 C
. l l Ceness usensies beds I. Cwie Release = 389 Ci DE l 131 (0-2 Hn)
- 2. TW Does = 18J een (30 Dey),2 49 rein (2 How) a i
~ MSLB Control Room Habitability Assessment (Design Basis Case)
M MslY h-me (Deuen /
tue usta seek mM e 8- m.m>
0 N
--x- ,
,,, o eum.
Semen Las Tummel [ ,
TuSee tids Fluer h
\
Censul name lamhe e Tue as tweems D4 '
me,4w a ese ties am enen l I
- l. Total Cune Release = 206 Cl DE l-131 1
' 2. 2 Hour. Accidset $s a s,npoid Dose = 1J rem
Conclusions:
1)<GDC 19 Requirements 2) Done Bounded by LOCA Case
~ v< E av.43 W, W
-y 4-, _ ,. _u-- -h+- w -aunaae>-seem- ~ ---- a-+ + - - + - - 2- ' - -
=4e=4.aehm---t-ww+-, wen-*m-r-+sw-.r-- e r e -- es----ew-e--+g --se - r=e-^ -na ---w we w -m u v-w*,-<u. --ws-www,,,Ws,---- tir w we --ri:w en- wa=& 4 7 e---------f-- * *rs v e w - ( -'e'** *-
Control Room Thyroid Doses l
l l
LOCA Dose Regulatory Dose From Containment Limit From MSLB Leakage Rem Rem Rem l Byron 18.20 (30 Day)* 30 NA l
2.49 (2 Ilour) 30 1.3 (2 Hour)
Braidwood 16.40 (30 Day)* 30 NA
, 2.17 (2 Hour) 30 0.9 (2 Hour)
'(Reference UFSAR Table 6 4. la)
{
Control RoomHabitability Conclusions Meet GDC 19 Limits Byron 1 MSLB Accidents Are Conservatively Bounded by Existing LOCA Braidwood 1 MSLB Accidents Are Conservatively Bounded by Existing LOCA
Site Boundary Requirements )
per Standard Review Plan 15.1.5 Exclusion Area Boundary (EAB) and Low l
Population Zone (LPZ) Requirements
- With Pre-Existing lodine Spike (10 CFR 100 Limits)
300 Rem Thyroid
- With Accident Initiated Spike
. Small Fraction of 10 CFR100 Limits (10%)
- 2.5 Rem Whole Body
- 30 Rem Thyroid l
' Accident Initiated Spike Limiting Event '
Byron / Braidwood Approach Evaluate MSLB by Comparison to Existing Plant Licensing Basis (10 CFR 100)
Conclusions:
- Both Byron 1 and Braidwood 1 Are Within Small Fraction (10%) of 10 CFR 100 Limits for a MSLB
- MSLB is Bounded by Current LOCA Licensing Basis
= -
L
Byron Offsite Dose Consequences :
LQCA MSLB
! EAB (445 m)
Thyroid Dose 115 Rem 29.6 Rem **
Part 100 Limit 300 Rem 30 Rem
- LPZ (4848 m) l Thyroid Dose 16 Rem 7.45 Rem **
I Part 100 Limit 300 Rem 30 Rem *
- Accident initiated Spike is Limiting
" Based on Dose at 0.20 pci/gm DE I.131 and RCS Leakage of 63.1 gpm at Operating Temperature and Pressure Con 91 usions:
- <Part 100 Limits
- Dose Bounded by Existing LOCA Analysis for Offsite Dose Braidwood Offsite Dose Consequences LOCA MSLB EAB (485 m)
Thyroid Dose 156 Rem 28.2 Rem **
Part 100 Limit 300 Rem 30 Rem
Thyroid Dose 74.2 Rem 26.2 Rem **
Part 100 Limit 300 Rem 30 Rem *
- Accident Initiated Spike is Limiting
" Based on Dose at 0.10 pel/gm DE l 131 and RCS Leakage of 87.7 gpm at Operating Temperature and Pressure
Conclusions:
- <Part 100 Limits
- Dose Bounded by Existing LOCA Analysis for Offsite Dose
I I
Site Boundary Conclusions Both Byron 1 and Braidwood 1 Are Within Small Fraction (10%) of 10 CFR 100 Limits for a MSLB Accident MSLB Dose Bounded by Existing LOCA Analysis Assessment Conclusions At Proposed RCS DE I-131 Liraits Byron 1 and Braidwood 1
- Meet GDC 19 (Control Room) Requirements with Margin
- Meet 10 CFR 100 (Offsite Dose) Requirements with Margin
- Meet Current Licensing Basis -
Byron 1 and Braidwood 1 are safe to Operate Full Cycle
-aw.y,,.,wm 4
0 Schedule Original Submittal Byron 1 1/31/97 Braidwood 1 T.S. Submitted 9/02/97 Byron 10.2 pCi/gm Approval Required by 10/01/97 l
- Byron 150 Replacement 11/07/97 !
Braidwood 10.1 pCi/gm Approval Required by 10/10/97- i Braidwood 1 SO Replacement 9/98 e
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