|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20138C8081997-04-25025 April 1997
Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20059J0261994-01-24024 January 1994
Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl
ML20058G7841993-12-0202 December 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059H9941993-11-0808 November 1993
Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
ML20058N0011993-09-30030 September 1993
Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20128C9371993-01-14014 January 1993
Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages
ML20126K5111992-12-30030 December 1992
Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20246E1531989-08-16016 August 1989
Summary of 890727 Meeting W/Util,Nus Corp,Conner & Wetterhahn,Bechtel,Bnl & State of PA in Rockville,Md Re Severe Accident Issues.Licensee Presented Info Re Comparison of Core Damage for Accident Classes in PRA
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20247R6001989-05-15015 May 1989
Summary of ACRS Subcommittee on Limerick Unit 2 Meeting on 890425 in Philadelphia,Pa Re Application for Ol.Statement of Limerick Ecology Action Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20206E3591988-11-10010 November 1988
Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program
ML20205P3121988-10-26026 October 1988
Summary of Operating Reactors Events Meeting 88-42 on 881025 Re Reactor Scrams.Three Significant Events Identified for Input to NRC Performance Indicator Program.List of Attendees Encl
ML20205C9601988-10-20020 October 1988
Summary of 881019 Meeting W/Util in Rockville,Md Re Util 880907 Submittal Re Protection from Degraded Voltage Conditions.List of Attendees & Agenda Encl
ML20151M0321988-07-28028 July 1988
Summary of 880519 Meeting W/Util in Rockville,Md to Discuss Licensee Plan for Facility Restart.List of Attendees, Agenda & Viewgraphs Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl
ML20196D3841988-02-10010 February 1988
Summary of Operating Reactors Events Meeting 88-05 on 880202 on Events Since 880126 Meeting.List of Attendees, Events Discussed,Tabulation of long-term Followup Assignments & 10CFR50.72 Rept Tabulation & Summary Encl
IA-88-478, Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting1988-01-0505 January 1988
Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting
ML20196A2161988-01-0505 January 1988
Trip Rept of Commissioner Carr & T Elsasser 871215 Site Visit to Util & 871216 Attendance at Region I Periodic Regional Resident Counterpart Meeting
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
IR 05000277/19850231987-09-14014 September 1987
Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20236F2181987-07-26026 July 1987
Summary of 870715 Meeting W/Util in Bethesda,Md Re Status of Util Recovery Program for Facility Operations.List of Attendees,Viewgraphs & Meeting Transcript Encl
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
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20206B0521987-04-0606 April 1987
Summary of 870115 Meeting W/Util in Bethesda,Md Re ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Classes 1,2 & 3 Piping Sections,Section Iii,Div 1. List of Attendees Encl
ML20205E7821987-03-25025 March 1987
Summary of 870323 Meeting W/Util & Bechtel in Bethesda,Md Re Proposal Made in Licensee 870113 Application Concerning Connection of Standby Gas Treatment Sys Svc to Refueling Floor Area.List of Attendees Encl
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20214K1961986-11-21021 November 1986
Summary of 861107 Meeting W/Util,Ge & Bechtel in Bethesda,Md Re Use of ASME Code Case N-411 Concerning Alternative Damping Values for Seismic Analysis of Class 1-3 Piping.List of Attendees & Viewgraphs Encl
ML20214A1351986-11-13013 November 1986
Summary of 861001 Meeting W/Util in Bethesda,Md Re Schedules for Licensing Actions.Adequate Preparation of License Amend Applications Emphasized
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20212K3101986-08-13013 August 1986
Summary of 860708 Meeting W/Util in Bethesda,Md Re Topical Reload Program for Plant.List of Attendees,Proposed Meeting Agenda & Slide Presentation Encl
ML20205Q4541986-05-13013 May 1986
Summary of 860506 Meeting W/Util in Bethesda,Md Re Special Circumstances for Util Requested Exemptions to 10CFR50, App R
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
1998-12-15
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20138C8081997-04-25025 April 1997
Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20059J0261994-01-24024 January 1994
Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl
ML20058G7841993-12-0202 December 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059H9941993-11-0808 November 1993
Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl
ML20059B0971993-10-20020 October 1993
Summary of Operating Reactors Events Meeting 93-39 on 931013
ML20058N0011993-09-30030 September 1993
Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20128C9371993-01-14014 January 1993
Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages
ML20126K5111992-12-30030 December 1992
Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20246E1531989-08-16016 August 1989
Summary of 890727 Meeting W/Util,Nus Corp,Conner & Wetterhahn,Bechtel,Bnl & State of PA in Rockville,Md Re Severe Accident Issues.Licensee Presented Info Re Comparison of Core Damage for Accident Classes in PRA
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20247R6001989-05-15015 May 1989
Summary of ACRS Subcommittee on Limerick Unit 2 Meeting on 890425 in Philadelphia,Pa Re Application for Ol.Statement of Limerick Ecology Action Encl
ML20235M1671989-02-17017 February 1989
Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl
ML20195H0271988-11-25025 November 1988
Summary of Operating Reactor Events Meeting 88-46 on 881122
ML20206E3591988-11-10010 November 1988
Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program
ML20205P3121988-10-26026 October 1988
Summary of Operating Reactors Events Meeting 88-42 on 881025 Re Reactor Scrams.Three Significant Events Identified for Input to NRC Performance Indicator Program.List of Attendees Encl
ML20205C9601988-10-20020 October 1988
Summary of 881019 Meeting W/Util in Rockville,Md Re Util 880907 Submittal Re Protection from Degraded Voltage Conditions.List of Attendees & Agenda Encl
ML20151M0321988-07-28028 July 1988
Summary of 880519 Meeting W/Util in Rockville,Md to Discuss Licensee Plan for Facility Restart.List of Attendees, Agenda & Viewgraphs Encl
ML20195B2211988-06-0808 June 1988
Summary of Operating Reactors Events Meeting 88-23 on 880607.List of Attendees,Events Discussed & Summary of Reactor Scrams Encl
ML20196D3841988-02-10010 February 1988
Summary of Operating Reactors Events Meeting 88-05 on 880202 on Events Since 880126 Meeting.List of Attendees, Events Discussed,Tabulation of long-term Followup Assignments & 10CFR50.72 Rept Tabulation & Summary Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
IR 05000277/19850231987-09-14014 September 1987
Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A0231987-09-10010 September 1987
Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl
ML20236F2181987-07-26026 July 1987
Summary of 870715 Meeting W/Util in Bethesda,Md Re Status of Util Recovery Program for Facility Operations.List of Attendees,Viewgraphs & Meeting Transcript Encl
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
ML20214J4991987-05-15015 May 1987
Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20206B0521987-04-0606 April 1987
Summary of 870115 Meeting W/Util in Bethesda,Md Re ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Classes 1,2 & 3 Piping Sections,Section Iii,Div 1. List of Attendees Encl
ML20205E7821987-03-25025 March 1987
Summary of 870323 Meeting W/Util & Bechtel in Bethesda,Md Re Proposal Made in Licensee 870113 Application Concerning Connection of Standby Gas Treatment Sys Svc to Refueling Floor Area.List of Attendees Encl
ML20214K1961986-11-21021 November 1986
Summary of 861107 Meeting W/Util,Ge & Bechtel in Bethesda,Md Re Use of ASME Code Case N-411 Concerning Alternative Damping Values for Seismic Analysis of Class 1-3 Piping.List of Attendees & Viewgraphs Encl
ML20214P9371986-11-21021 November 1986
Summary of Operating Reactor Events Meeting 86-39 on 861110.List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20214A1351986-11-13013 November 1986
Summary of 861001 Meeting W/Util in Bethesda,Md Re Schedules for Licensing Actions.Adequate Preparation of License Amend Applications Emphasized
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20212K3101986-08-13013 August 1986
Summary of 860708 Meeting W/Util in Bethesda,Md Re Topical Reload Program for Plant.List of Attendees,Proposed Meeting Agenda & Slide Presentation Encl
ML20205Q4541986-05-13013 May 1986
Summary of 860506 Meeting W/Util in Bethesda,Md Re Special Circumstances for Util Requested Exemptions to 10CFR50, App R
ML20210R3741986-05-0808 May 1986
Summary of 860430 Meeting W/Util in Bethesda,Md to Discuss Processes to Be Used to Review Issues Raised in Remainder of OL Review for Facility
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
ML20203M9431986-04-25025 April 1986
Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl
1998-12-15
[Table view] |
Text
_ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ -
YO E$
.: . y *g*%-4 SD .352/2G "y UNITED STATES
'2 j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 k.....,/ December 15, 1998 LICENSEE: PECO Energy Company FACILITIES: Limerick Generating Station, Units,1 and 2 Peach Bottom Atomic Power Station, Units 2 and 3
SUBJECT:
SUMMARY
OF NOVEMBER 18,1998, MEETING WITH PECO ENERGY l
COMPANY REGARDING AMPACITY VALIDATION ANALYSES l On November 18,1998, representatives of the PECO Energy Company (PECO, the licensee)
I met with members of the NRC staff in Rockville, Maryland. PECO requested this meeting as a follow-up to the telephone conference held on August 27,1998, in order to resolve outstanding staff concems on the use of their ampacity derating methodology for Thermo-Lag fire barriers of the Limerick and Peach Bottom Stations. A list of attendees is given in Enclosure 1. Copies l of the handouts provided by PECO are given in Enclosure 2.
l l The NRC staff's concems that pertained to the use of the PECO methodology for Thermo-Lag enclosed conduits were as follows: (1) Licensee model validation results did not appear to be conservative and consistent and (2) Licensee methodology did not appear to be consistent with the methodology for the industry standard procedure IEEE P848. PECO representatives discussed their heat transfer model validation efforts, which were based upon the Tennessee l Valley Authority (TVA) ampacity derating tests. The licensee pointed out the differences l
between the Limerick and Peach Bottom installed configurations and the TVA tested configurations. They stated that their ampacity derating methodology models the IPCEA/NEC industry standard calculated values for a given configuration to both cladded (with Thermo-Lag) and baseline (without Thermo-Lag) conditions. They presented new validation results (Table 2 of Enclosure 2) for the subject TVA tested configuration's iisiiid their methodology on a consistent basis to develop the ampacity dorating factor (ADF). The TVA validation results, which were previously submitted by PECO, used actual ampacity derating test results for the baseline configurations and estimated ampacity derating values based on their model for the cladded configurations to calculate the ADF values.
The licensee informed the NRC staff that they plan to extend the use of their methodology to Darmatt fire barriers, assuming the resolution of the staff's concems regarding implementation.
The NRC staff requested written confirmation of the new validation results for the TVA-tested l
t j 9812300103 981215 g
. PDR ADOCK 05000277 P PDR g
\
jW NBC RiE FadM MPV
! s ,
~
l 2-l l
l configurations and a detailed description of the licensee's ampacity methodology from PECO.
i Based on the information presented at the meeting, the NRC staff finds that, subject to submittal and verification of the requested information, the licensee's approach to resolving the NRC's concems appears reasonable.
LC Bartholomew C. Buckley, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-352,50-353,50-277 )
and 50 278 I L
l
Enclosures:
- 1. List of Attendees
- 2. Licensee's Handouts cc w/encis: See next page
a.'
configurations and a detailed description of the licensee's ampacity methodology from PECO.
~
Based on the information presented at the meeting, the NRC staff finds that, subject to submittal and verification of the requested information, the licensee's approach to resolving the NRC's concems appears reasonable, original signed by:
Bartholomew C. Buckley, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-352,50-353,50-277 and 50-278
Enclosures:
- 1. List of Attendees
- 2. Licensee's Handouts cc w/encis: See next page DISTRIBUTION Hard Coov Docket File PUBLIC PDI-2 Reading BBuckley OGC ACRS E-Mail SCollins/RZimmerman BBoger
- JZwolinski RCapra '
MO'Brien TMartin (e-mail SLM3)
JCalvo RJenkins BMcCabe CAnderson, RGN-l OFFICE PDI-2/PM2 % PDb2!LAYI PDI-2/D NAME BBucklehrh 'M RCapra #
DATE /21 7/98 /k/98 11/15/98 OFFICIAL RECORD COPY t j DOCUMENT NAME: Ll11-18.MTS
[ -
l .
t .
PECO Energy Company Limerick Generating Station, Units 1 & 2 l
CC:
I J. W. Durham, Sr., Esquire Chief Division of Nuclear Safety Sr. V.P. & General Counsel PA Dept. of Environmental Resources PECO Energy Company P.O. Box 8469 2301 Market Street Harrisburg, PA 17105-8469 Philadelphia, PA 19101 1
Manager-Limerick Licensing,62A-1 Director-Site Engineering PECO Energy Company Limerick Generating Station 965 Chesterbrook Boulevard P.O. Box A Wayne, PA 19087-5691 Sanatoga, PA 19464 Mr. James D. von Suskil, Vice President Limerick Generating Station I Manager-Experience Assessment l Post Office Box A Limerick Generating Statior Sanatoga, PA 19464 P.O. Box A l Sanatoga, PA 19464 Plant Manager Limerick Generating Station Library P.O. Box A U.S. Nuclear Regulatory Commission Sanatoga, PA 19464 Region 1 475 Allendale Road Regional Administrator, Region i King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission l
475 Allendale Road Senior Manager-Operations King of Prussia, PA 19406 Limerick Generating Station P.O. Box A Senior Resident inspector Sanatoga, PA 19464 U.S. Nuclear Regulatory Commission Limerick Generating Station Dr. Judith Johnsrud P.O. Box 596 National Energy Committee Pottstown, PA 19464 Sierra Club 433 Orlando Avenue Director-Site Support Services State College, PA 16803 Limerick Generating Station P.O. Box A Mr. Garrett D. Edwards Sanatoga, PA 19464 - Director-Licensing, MC 62A-1 PECO Energy Company Chairman Nuclear Group Headquarters Board of Supervisors Correspondence Control Desk j' of LimerickTownship P. O. Box No.195 646 West Ridge Pike Wayne, PA 19087-0195 Linfield, PA 19468
. - ~ . _ . - . - - . . . . ~ . . - . . . - . . - - - ._- .-. . -. . ~. _ - _-- - -. .._ - - - .
4 l
LIST OF ATTENDEES MEETING BETWEEN NRC AND PECO ENERGY COMPANY REGARDING AMPACITYVAllDATION ANALYSES LIMERICK GENERATING STATION, UNITS 1 AND 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 NAME ORGANIZATION B. Buckley NRC/NRR J. Calvo NRC/NRR R. Jenkins NRC/NRR T.Dogan PECO E. Sproat PECO D. Neff PECO l S. Thakur PECO W. Boyer PECO l J. Hufnagel PECO !
J. Hearn PECO S. Nowlen Sandia Laboratories l
l 4
9
)
! ENCLOSURE 1 4
e 1
)
4 i
AMPACITY DERATING METHODOLOGY
- Presented to
- The U.S. Nuclear Regulatory Commission
- Presented by: PECO Energy Company l, Limerick Generating Station Peach Bottom Atomic Power Station l
, November 18,1998 J
Attendees: E. F. Sproat W. J. Boyer l D. B. Neff I
S.Thakur 1
- T. Dogan i
}.~ ,
ENCMSURE 2
4 l
Purpose - Address XRC Comments
- Protected Cable Modelfor Ampacity Derating Not Conservative in Some Conduit Cases
- Method to Determine Ampacity Derating Factor Not Consistent withIEEE 848 Methodologyfor Conduit 1
2 i
~
i .
i 2 +
i l Heat Transfer Model Validation Seven Test Cases Modeled
{ - TVA Watts Bar Tests l-l Unistrut Frame Design not Used at PB or LGS i
4
- Cases 7.7a & 7.7b l Cases 7.7a & 7.7b Modeled Using Simplifying i Assumption
- Excluded Unistrut Frame Results Appear Non-conservative Based on ADF
'~
. 3
m_a- .,A_.,-4 .
. ad iw h m me a weh-w+umq O
$0 g e e
d
Y.
C m
O 1
O rA i
e
- m w
b O 4
J L 4 m
i H
- M H
> m j C H >< l
- m n sM j
Q O i m 2
4 $ n e
1
- E <s J L W 4 i $ 0 *
- 2 7 [
5 i
e
i Heat Transfer Model Validation
=
Protected Ampacity (I) Comparison
! - Critical Parameter of Concern i - I, Conservatively Calculated by Model Based on Industry l Standards When Compared to Test Results 4
i Ampacity Derating Factor
! - ADF = (I 34 py I 3 X 100 Baseline Ampacity minus Protected Ampacity divided by Baseline Ampacity & Converted to %
- ADF sensitive to values of both I 3& Ip i Model vs. Test
- IEEE 848 Requires Measurement of1 3
- Model Uses I from 3 Industry Standards to Calculate Unprotected
- Heat Transfer Parameter Values 5
_______________m._..- ___ . _ _ _ _ _ . _ -_ _ _ __ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ . - _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ . . . _ _ . _ _ _ _ _ _ _ _ _ - _ - _ . _ _ _ . . . . _ _ _ _ - _ _ . _ _ . _ _ _ . _ _ _ _ _ - . _ _ _ --__-_____._.________._______-.____________-.-__m- w 4 -
w-_ _ _ __ _ _ _ _ _ _ _ _
Table 1 - Comparison of Results of the Heat Transfer Model with Test Data (BaselineAmpacityfrom Tests)
Small Conduit in Large Conduit Three Conduits in Six Conduits in Six Conduits in Small Conduit in Small Conduit in Test Description a Round Enct in a Round Enct a Tight Box Enct a Tight Box Enct a Large Box Enct a Small Box Encl a Large Box Enct Test Case TVA7.6a TVA7.6b TVA7.4 TVA7.5 TVA7.8 I'VA7.7a TVA7.7b Raceway Size 1"RGS 4" RGS 1"RGS 1"RGS 1"RGS 1"RGS 1"RGS Raceway Emissivity 0.48 0.69 0.78/0.34/0.33 0.32/0.55/0.48/ 0.47/0.69/0.18 0.59 0.59 Cable Size 4/C #10 3/C #6 4/C #10 4/C #10 4/C #10 4/C #10 4/C #10 Percent Fill 33 % 40% 33 % 33 % 33 % 33 % 33 %
Bamer Thickne:,s (in) 2.90 2.60 1.00 0.94 0.99 1.00 1.00 Bamer Emissivity 0.99 0.99 0.99 0.99 1.00 0.99 0.99 Test Results Im.. 32.7 29.2 31.7 31.I 31.I 33.0 33.0 I-s 29.7 25.6 29.2 23.2 28.3 29.3 31.3 ADF l9.2% 12.5 % 7.7% 25.5 % 9.0% i1.3 % 5.2%
ModelResults with Imliased on Tests Iwa. 32.7 29.2 31.7 31.1 31.I 33.0 33.0 I-s 28.1 23.3 23.6 20.5 25.8 29.7 31.4 ADF 13.9 % 20.2 % 25.5 % 34.1 % 17.1 % 10.0 % 4.8%
Deviation (I-s) 5.3% 9.0% 19.2% 11.6% 8.8% -1.4 % -0.3%
Deviation (ADF) 4.7% point 7.7% point 17.8% point 8.6% point 8.1% point -1.3% point -0.4% point Deviation (I,.w) = Lma. - I,..w a x 100 Ip .a . .
Deviation (ADF)= ADFa - ADF.
. 6 e
4
l Table 2 - Comparison of Results of the Heat Transfer Model with Test Data 6
(Baseline Ampacity from industry Standards)
Small Large Three Six Conduits Six Conduits Small Conduit Small Conduit Test Description Conduit in Conduit in a Conduits in a in in in in l a Round Round Encl. Tght Box a Tight Box a Large Box a Small Box a Large Box Encl. Encl. Encl. Encl. Encl. Encl.
Test Case TVA7.6a WA7 6b TVA7.4 TVA7.5 TVA7.8 TVA7.7a TVA7.7b Test Results _
/m 32.7 29.2 31.7 31.1 31.1 3:.7 33.0
/m 29.7 25.6 29.2 23.2 28.3 29.3 31.3 ADF 9.2% 12.5 % 7.7 % 25.5% 9.0% 11.3 % 5.2%
Model Results with twua,. Based on Industry Stendards 1,xm,m, 40 69 40 40 40 40 40 ATCF 0.91 1.0 0.91 0.91 0.91 0.91 0.91 MCCF 0.80 0.40 0.80 0.80 0.80 0.80 0.80 CGF 1.0 1.0 0.91 0.84 0.84 1.0 1.0
/w,,, 29.1 27.6 26.5 24.4 24.5 29.1 29.1
/m 25.9 22.5 21.2 18.1 21.6 26.7 28.0 ADF 11.2 % 18.5 % 20.1 % !26.0% 11.9 % 8.2% 4.0%
Deviation (Im) 12.8 % 12.0 % 27.5% 21.9 % 23.9% 8.3% 10.6%
Deviation (ADF) 2.0% point 6.0% point 12.4% point 0 5% point 2.9% puint -3.2% point -1.2% point im Nominal Ampacity of the Cable (IPCEA P-46-426 for 3/C #6, NEC Table 310-16 for 4/C #10)
ATCF Ambient Temperature Correction Factor (NEC Table 310-16)
MCCF Multiple Conductor Corcection Factor (MEC Article 310-15, Paragraph 8a)
CGF Conduit Grouping Factor (IPCEA) 1% = ImX ATCF X MCCF X CGF
~
.- ]
. t
~
'*O e s'i
1 4 .
t i
i 9
1 5
- Table 3 - Test vs. Model Comparison ofI,/(ADF) t Small Conduit in Large Conduit 11ure Conduits in Six Conduits in Six Conduits in Small Conduit in Small Conduit in Test Description a Round Encl. in a Round Enct a Tight Box Encl. a Tight Box Enct a Large Box Encl a Small Box Encl. a Lag
- e Box Enct 4
Test Case TVA7.6a TVA7.6b TVA7.4 TVA7.5 TVA7.8 TVA7.7a TVA7.7b 4
Test Results 29.7 /(9.2%) 25.6 /(12.5%) 29.2 /(7.7%) 23.2 /(25.5%) 28.3 /(9.0%) 29.3 /(11.3%) 31.3 /(5.2%)
4 ModelResults(4 based 28.1 /(13.9%) 23.3 /(20.2%)' 23.6 /(25.5%) 20.5 /(34.1%) 25.8 /(17.1%) 29.7 /(10.0%) 31.4 /(4.8%)
on Tests)
I ModelResults(4 based 25.9 /(11.2%) 22.5 /(18.5%) 21.2 /(20.1%) 18.1 /(26.0%) 21.6 /(11.9%) 26.7 /(8.2%) 28.0 /(4.0%)
on IndustryStandasds 1
1 W
. . 8 9
j .
. ~ _ . . . . ..~. -. _ _ . . - - . . . . _ _ - ~ . .. _.-._- --
l Heat Transfer Model Validation
=
Sigmficance ofLower ADFfor Calculated vs.
i Test Cases 4
l - Not Significant ifI p Resulting from Application of i
ADF is Conservative i
4
!.. 9
i l Installed Design i
i i
TVA Case 7.4 Most Closely Aligns With Installed Design
- -I p Moc el vs. Test
! 21.2 vs. 29.2 amps
! - ADF Model vs. Test j 20.1 vs. 7.7%
i l
a
.- . 10
__._[___..,--__~ . _ _ . - , _ . - . , . . _ . . , _ . . _ _ . - _ , _ _ . , - . _ , , , _ _ _
i Figure -Test Case 7.4 1" CONDUIT
! l 1.315" AVAW///////////AM
<= 4.95" => <>-- 1 "
<- 6.95" =>
TVA TEST CASE 7.4 ADF (MODEL) = 20.1%
ADF (TEST) = 7.7%
I1
.j .
1 l .
Conclusion
=
Use ofIndustry Standards for Baseline j Ampacity to Model- Results in Conservative Protected Ampacities (Ip) i for Cables
- Applies to all test configurations l
Ip the Significant Parameter of Concern i
Model Calculates Conservative ADFs l When Compared to Tests for Applicable l -
Configurations
. 12 4
1 .j .
~
l Conclusion
! (Continued) l Use ofindustry Standards for Baseline l Ampacity Consistent with Standard Industry Practice for Ampacity Rating of
! Unprotected Raceways l
- - Use ofIndustry Standards is Appropriate as a Model
- Input i
=
Extend Use of Model to Darmat Model l Based on Validation Results 9
13 l; -
. . .
