Letter Sequence Meeting |
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|
|
MONTHYEARML20211P0031987-02-20020 February 1987
Proposed Tech Specs Re Steam Generator Tube Plugging Criteria in Tube Sheet Region
Project stage: Other
ML20211N9551987-02-20020 February 1987
Application to Amend License NPF-1,revising Steam Generator Tube Plugging Criteria in Tube Sheet Region.Fee Paid
Project stage: Request
ML20211N9411987-02-20020 February 1987
Forwards Application for Amend to License NPF-1,revising Tech Specs Re Steam Generator Tube Plugging Criteria & Nonproprietary & Proprietary Repts Re Tubesheet Plugging Criterion.Proprietary Rept Withheld (Ref 10CFR2.790)
Project stage: Request
ML20209D0251987-04-20020 April 1987
Proposed Tech Specs Re RCS Surveillance Requirements
Project stage: Other
ML20209D0031987-04-20020 April 1987
Supplemental Application for Amend to License NPF-1, Incorporating License Change Application 152 Re Unneccessary Plugging of Steam Generator Tubes Which Increases Personnel Exposure & Reduces RCS Flow
Project stage: Supplement
ML20214P8951987-05-14014 May 1987
Requests Summary of 870408 Meeting Between NRC & Util,Per Attached Notice
Project stage: Meeting
ML20214P8891987-06-0101 June 1987
Ack Receipt of 870514 Request for Summary of 870408 Meeting Between NRC & Util Re Plant.Summary Will Be Provided When Issued
Project stage: Meeting
ML20215J2291987-06-22022 June 1987
Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl
Project stage: Meeting
ML20236P6581987-08-0707 August 1987
Forwards Amend 133 to License NPF-1 & Safety Evaluation. Amend Revises Steam Generator Tube Plugging Criteria Based on Use of F* Distance Criteria
Project stage: Approval
1987-05-14
[Table View] |
|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20199E1051999-01-13013 January 1999
Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl
ML20198B7641998-12-16016 December 1998
Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List Encl
ML20155C5561998-10-28028 October 1998
Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl
NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998
Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl
ML20141H7051997-05-19019 May 1997
Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees Encl
ML20129E2231996-09-24024 September 1996
Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl
ML20129G2581996-04-11011 April 1996
Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo)
ML20059F2621994-01-10010 January 1994
Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility
ML20058B5681993-11-18018 November 1993
Trip Rept of 931102 Meeting Between NRC & Util Re Planned Research on naturally-aged Cables from Plant
ML20055G9391990-07-19019 July 1990
Summary of 900612 Meeting W/Util Re Reactor Protection Sys Walkdown Results & Proposed Mods.List of Attendees & Handouts Encl
ML20196C2491988-11-30030 November 1988
Summary of 881110 Meeting W/Util & B&W to Discuss Use of B&W Mfg Fuel at Facility.Handouts from Meeting & List of Attendees Encl
ML20155B8231988-09-20020 September 1988
Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams
ML20196L2221988-06-23023 June 1988
Summary of 880531 Meeting on Pressurizer Surge Line Movement & Pipe Whip Restraint Program.List of Attendees & Presentation Handouts Encl
ML20196F9951988-02-24024 February 1988
Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20235R3671987-09-30030 September 1987
Summary of 870820 Meeting W/Util Re Adequacy of Support Design Verification.List of Attendees Encl
ML20235G8061987-09-25025 September 1987
Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl
ML20237J6311987-08-13013 August 1987
Trip Rept of 870722-23 Site Visit to Gather First Hand Info Re Main Feedwater Line Pipe Wall Thinning Problem,Review Licensee Pipe Wall Thinning Monitoring Program & Evaluate Results of Licensee Failure Analysis
ML20236L3451987-07-30030 July 1987
Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl
ML20245B9271987-06-25025 June 1987
Summary of 870317-18 Meeting at Facility Re SPDS & Dcrdr. Dcrdr Discussions Centered on Certain Human Engineering Deficiencies Whose Resolution Required Addl Info &/Or in-plant Verification
ML20215J2291987-06-22022 June 1987
Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl
ML20204E4951987-03-19019 March 1987
Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20210L7201986-09-24024 September 1986
Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl
ML20214Q8211986-09-19019 September 1986
Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl
ML20203N0411986-09-18018 September 1986
Summary of 860513-14 Meetings W/Util at Site & in Portland, or Re Current Licensing Activities & to Meet W/Plant & Corporate Staff as Result of Appointment of New NRC Plant Manager.Attendees List Encl
ML20210S2271986-05-15015 May 1986
Trip Rept of 860510-11 Site Visit to Participate in Licensee Cold Walkdown of Reactor Coolant Loop Piping & Components, Including Supports,To Assess Whether Cause of LER 85-013, Rev 1 Determined
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20151Y0031986-01-29029 January 1986
Summary of 860108-09 Meetings W/Util in Bethesda,Md Re Current Licensing Activities & Reestablishment of Compatible Priorities & Schedules Since NRR Reorganization.Attendee List Encl
ML20137M6361986-01-14014 January 1986
Summary of 851126 Meeting W/Util at Site Re Five Requested Exemptions from Specific Requirements of Section Iii.G of App R (Fire Protection).List of Attendees & Request for Info Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20136C5141985-11-11011 November 1985
Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
IA-85-353, Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl1985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
ML20134A5161985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20062J7361980-10-20020 October 1980
Summary of 800930 Meeting W/Util & Westinghouse Re Lab Examination Results for Steam Generator Row 1 U-bend Tube Samples Removed from Plant
ML20125C1751979-12-19019 December 1979
Summary of 791205-06 Meeting W/Util & Bechtel Re Discussion of LER 79-15 Wherein Certain Problems W/Masonry Block Walls & Support Reactions of Equipment/Piping Attached Thereto Were Identified
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-01-13
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20199E1051999-01-13013 January 1999
Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl
ML20198B7641998-12-16016 December 1998
Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List Encl
ML20155C5561998-10-28028 October 1998
Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl
NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998
Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl
ML20141H7051997-05-19019 May 1997
Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees Encl
ML20129E2231996-09-24024 September 1996
Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl
ML20129G2581996-04-11011 April 1996
Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo)
ML20059F2621994-01-10010 January 1994
Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility
ML20055G9391990-07-19019 July 1990
Summary of 900612 Meeting W/Util Re Reactor Protection Sys Walkdown Results & Proposed Mods.List of Attendees & Handouts Encl
ML20196C2491988-11-30030 November 1988
Summary of 881110 Meeting W/Util & B&W to Discuss Use of B&W Mfg Fuel at Facility.Handouts from Meeting & List of Attendees Encl
ML20155B8231988-09-20020 September 1988
Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams
ML20196L2221988-06-23023 June 1988
Summary of 880531 Meeting on Pressurizer Surge Line Movement & Pipe Whip Restraint Program.List of Attendees & Presentation Handouts Encl
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20235R3671987-09-30030 September 1987
Summary of 870820 Meeting W/Util Re Adequacy of Support Design Verification.List of Attendees Encl
ML20235G8061987-09-25025 September 1987
Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl
ML20236L3451987-07-30030 July 1987
Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl
ML20245B9271987-06-25025 June 1987
Summary of 870317-18 Meeting at Facility Re SPDS & Dcrdr. Dcrdr Discussions Centered on Certain Human Engineering Deficiencies Whose Resolution Required Addl Info &/Or in-plant Verification
ML20215J2291987-06-22022 June 1987
Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl
ML20204E4951987-03-19019 March 1987
Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20210L7201986-09-24024 September 1986
Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl
ML20214Q8211986-09-19019 September 1986
Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl
ML20203N0411986-09-18018 September 1986
Summary of 860513-14 Meetings W/Util at Site & in Portland, or Re Current Licensing Activities & to Meet W/Plant & Corporate Staff as Result of Appointment of New NRC Plant Manager.Attendees List Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20151Y0031986-01-29029 January 1986
Summary of 860108-09 Meetings W/Util in Bethesda,Md Re Current Licensing Activities & Reestablishment of Compatible Priorities & Schedules Since NRR Reorganization.Attendee List Encl
ML20137M6361986-01-14014 January 1986
Summary of 851126 Meeting W/Util at Site Re Five Requested Exemptions from Specific Requirements of Section Iii.G of App R (Fire Protection).List of Attendees & Request for Info Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20136C5141985-11-11011 November 1985
Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
ML20134A5161985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
IA-85-353, Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl1985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20062J7361980-10-20020 October 1980
Summary of 800930 Meeting W/Util & Westinghouse Re Lab Examination Results for Steam Generator Row 1 U-bend Tube Samples Removed from Plant
ML20125C1751979-12-19019 December 1979
Summary of 791205-06 Meeting W/Util & Bechtel Re Discussion of LER 79-15 Wherein Certain Problems W/Masonry Block Walls & Support Reactions of Equipment/Piping Attached Thereto Were Identified
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-01-13
[Table view] |
Text
'
JUN 2 21987 Docket No. 50-344 LICENSEE: Portland General Electric Company (PGE)
FACILITY: Trojan Nuclear Plant
SUBJECT:
MEETING
SUMMARY
REGARDING THE APRIL 8, 1987 MEETING ON l F* - STEAM GENERATOR TUBE PLUGGING CRITERIA l l
' A meeting was held in Bethesda, Maryland on April 8,1987 with Portland General Electric Company to discuss the technical issues related to PGE's amendment request for F* steam generator tube plugging criteria. PGE's submittal LCA 152 dated February 20, 1987 provided background information on this topic. A list of attendees is provided in Enclosure 1.
PGE provided a presentation on the subject, and stated that the need for the amendment was due to " questionable" indications detected during the 1986 inspection of the steam generators (SG), in the region of the SG tubes where the F* criteria could be applied. The indications were labeled " questionable" !
since they could not be accurately characterized. Enclosure 2 contains PGE's presentation handouts.
Allen Nuclear Associates, Inc. followed with a presentation on the eddy current testing performed at Trojan, which included discussions on eddy current probe uncertainties, observed indications and inspection technique.
The meeting was then closed to the public during the presentation by I Westinghouse. Westinghouse presented proprietary information regarding the analytic aspects of the F* evaluation.
The staff's preliminary conclusion was that the amendment request was technically acceptable, subject to certain changes to the proposed Technical Specifications. PGE agreed that the changes were necessary, and would be formally submitted. These changes were submitted by letter dated April 20, 1987. j Original Signed by TL CllAN Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects
Enclosure:
As stated DRSP/PDV D ;PDV ;
TChan:cd ~ G 'hton 6/4/87 6)\'\ /87 0FFICIAL RECORD COPY
$[$ Nock P
Mr. David W. Cockfield Portland General Electric Company Trojan Nuclear Plant cc:
Senior Resident Inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Michael J. Sykes, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. David Kish Oregon Department of Energy Labor and Industries BJilding Room 111 Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. C. K. Lewe NUS Corporation 910 Clopper Road Gaithers burg, MD 20878 W. L. Pearl, President NWT Corporation 7015 Realm Drive San Jose, California 95119
I DISTRIBUTION Focket File NRC-& Local PDRs PD#5 Reading GWKnighton TChan OGC-Bethesda EJordan JPartlow NRC Participants ACRS(10)
HBClayton(RI)
T. O. Martin - EDO
Enclosure 1 LIST OF ATTENDEES APRIL 8, 1987 NAME ORGANIZATION T. L. Chan NRC E. J. Sullivan NPC C. Y. Cheng, NRC C. D. Sellers NRC E. L. Murphy NRC G. A. Zinnaerman PGE A. O. Wogen PGE B. L. Curtis Allen Nuclear Associates R. F. Keating Westinghcuse D. A. Lindgren Westinghouse C. K. Lewe NUS Corporation
_______________._____m
ENCLOSURE 2 l
w -
TUBE 0.876 0.D.
TUBE SHEET = I h h 1.4 F*
l 3.0 h
Initial Hard roll h
[l 1.56 Repair Hard Roll
- 1. 6
( u U U U h
0.22 -
- O'000 STEAM GENERATOR "B" gg. , ,,- HOT LEG M IMM% M P AIL DIMENSIONS IN INC'BES
O PREVIOUS EDDY CURRENT INDICATIONS IN TUBE SHEET REGION O TUBE SHEET (T/S) AREA INDICATIONS FIRST REPORTED IN 1985 O T/S INDICATIONS PRIMARILY S/G B HOT LEG O KNOWN INDICATIONS AFFECTED BY PROPOSED AMENDMENT ARE IN S/G B HOT LEG 1
l l
t
t
( ..
S/G B HOT LEG T/S INDICATIONS.
O- 111 T/S AREA INDICATIONS (UNK)
'O. 106 OF.THESE ARE WITHIN. SHOP HARD ROLL O ev 85 INDICATIONS ARE BELOW THE F* DISTANCE EXAMPLES OF HARD ROLL AREA INDICATIONS R 13 C 53 R 13 C 83 I
CHARACTERISTICS OF HARD ROLL AREAD INDICATIONS e OD ORIGINATED 8 AXIALLY ORIENTED 9 1/4" AXIAL LENGTH
W
\
\
CONCLUSIONS FROM PAST EDDY CURRENT DATA-I i
I 8 INSUFFICIENT PREVIOUS DATA TO ESTABLISH TREND
- OF" RATING EXPERIENCE IS NO DETECTABLE PRIMARY-TO-SECONDARY LEAKAGE l
l
5 I
l
\ l NEED FOR AMENDMENT O ELIMINATES TUBE END TRANSITION FROM CONSIDERATION O N 85 TUBES WOULD NOT REQUIRE CONSIDERATION FOR POSSIBLE PLUGGING
- - _ - _ _ - - _ -_-_____________________________ ____ _ _ _ _ _ . . _ _ _ . __ - ._ _
