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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210E0201999-07-16016 July 1999 Summary of 990629 Meeting with Util in Rockville,Md Re Ongoing Efforts in Planning Sf Storage Strategy,Including Licensing of Isfsi,At Plant.With Attendance List & TVA Handout ML20210D7801999-07-16016 July 1999 Summary of 990715 Meeting with TVA Re TVA Evaluation of Fee Structure Compared with Recent Actual Fees & NRC Guidance in Estimating Review Effort for Licensing Actions.List of Attendees & Matl Used in Presentation Enclosed ML20210D7601999-07-16016 July 1999 Summary of 990616 Meeting with TVA in Rockville MD to Brief Staff on Planned SG Replacement.List of Attendees & Handout Provided by TVA Encl ML20237E9811998-08-25025 August 1998 Summary of 980708 Meeting W/Tva & Framatome Cogema Fuel in Rockville,Md Re Ongoing Efforts W/Doe to Fabricate & Install Four Lead Test Assemblies in Plant,Unit 2 Core During Cycle 10 Refueling Outage in Spring of 1999.Attendance List Encl ML20216H5261997-08-26026 August 1997 Summary of 970822 Meeting W/Util in Rockville,Md Re Followup to Series of Conference Calls on 970418,discussing Results of Recent Steam Generator Insps at Sequoyah Unit 1.List of Attendees,Handouts & Staff Questions Encl ML20140B4701997-06-0404 June 1997 Summary of 970530 Meeting W/Tva in Rockville,Md to Discuss Status of Thermo-Lag Fire Barrier Corrective Action Program at Plant & Schedule for Completion of Program.W/Attendance List & TVA Handout ML20140G5621997-05-0808 May 1997 Summary of 970227 Meeting W/Tva in Rockville,Md to Discuss Sequoyah Conversion to Framatome Cogema Fuel.List of Attendees Encl ML20134J7451996-11-0808 November 1996 Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl ML20129H5211996-10-29029 October 1996 Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing ML20217D1931994-03-0707 March 1994 Summary of Sequoyah Restart Panel 940303 Meeting in Region II Ofc Re Status of NRC & Licensee Activities for Restart of Unit 1.Meeting Minutes & Unit 1 Restart Action Plan Encl ML20059K3131993-11-0505 November 1993 Summary of Operating Reactors Events Meeting 93-42 on 931103 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 ML20217D2111993-06-16016 June 1993 Summary of Sequoyah Restart Panel 930614 Meeting in Region II Ofc Re Plant Restart & Listed Items.List of Attendees & Checklists Encl.Next Meeting Will Be Held on 930622 ML20127D1321993-01-12012 January 1993 Summary of Operating Reactors Events Meeting 93-01 on 930106 ML20058J8621990-11-27027 November 1990 Summary of 901005 Meeting W/Util in Rockville,Md Re Cable Conduit Testing Program.Viewgraphs & Attendee List Encl ML20058K0311990-11-23023 November 1990 Summary of Operating Reactors Events Meeting 90-28 on 901114 Re Reactor Scrams for Wk Ending 901111.Attendees Listed 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 ML20059N2091990-09-21021 September 1990 Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements ML20059D8121990-09-0505 September 1990 Summary of 900817 Meeting W/Util in Rockville,Md Re Schedules of Certain Mods Committed for Completion in Unit 2 Cycle 4 Refueling Outage.Engineeering for Unit 2 Will Be Completed Before Restart from Outage ML20056B4101990-08-20020 August 1990 Summary of 900723 Meeting W/Util in Rockville,Md Re Plant Cable/Conduit Testing Program for safety-related Cable.List of Attendees,Tva & NRR Handouts & Transcript of Meeting Encl ML20055E2081990-07-0505 July 1990 Summary of 900531 Meeting W/Tva in Rockville,Md Re Plant safety-related Cable Inside Containment.List of Attendees, & Handouts Presented at Meeting Encl ML20246J8031989-07-12012 July 1989 Summary of 890609 Meeting W/Util in Rockville,Md Re Dissolution of Engineering Assurance Organization.List of Meeting Attendees,Util Handout,Agenda & Transcript Encl ML20245F9761989-06-22022 June 1989 Summary of 890614 Meeting W/Util & Westinghouse in Rockville,Md Re Future Work for Facility Cycle 4 Refueling Outage ML20247M1001989-05-26026 May 1989 Summary of 890511 Meeting W/Util in Rockville,Md Re Performance of Best Estimate Calculations for App K Analyses.Proposed Plan for LOCA Analyses,Meeting Handouts & List of Attendees Encl 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 ML20155A8081988-09-29029 September 1988 Summary of 880915 Meeting W/Util in Rockville,Md Re Microbiological Influenced Corrosion Program at Plant.List of Attendees & Viewgraphs Encl ML20154M9231988-09-21021 September 1988 Summary of 880913 Meeting W/Util at Site Re Unit 2 Shutdown Margin & Unit 1 Restart Readiness,Per Insp Repts 50-327/88-35 & 50-328/88-35.List of Attendees & Related Info Encl ML20154H4341988-09-16016 September 1988 Summary of 880908 Meeting W/Util in Rockville,Md Re Changes to Conditions Adverse to Quality Program.List of Attendees Encl ML20206B1961988-07-29029 July 1988 Summary of ACRS Subcommittee for TVA Organizational Issues 880722 Meeting in Washington,Dc Re Generic Lessons Learned from NRC Review of Util Concerning Restart of Facility ML20153A8371988-07-0101 July 1988 Summary of 880622 Meeting W/Util in Rockville,Md Re TVA Commitments on Facility.List of Attendees & Util Handout Encl ML20150E2321988-06-21021 June 1988 Summary of 880613 Meeting W/Util to Discuss Restart of Facility in Light of Recent Scrams from Power.Transcript of Meeting Encl ML20196A9201988-06-17017 June 1988 Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl ML20154A4061988-05-0404 May 1988 Summary of 880414 Meeting W/Util in Rockville,Md Re Differences Between Units 1 & 2 Nuclear Performance Plan. List of Attendees & Licensee Handout Encl ML20151D2701988-03-12012 March 1988 Summary of ACRS Subcommittee on TVA Organizational Issues Meeting on 880202-03 in Chattanooga,Tn Re Review of TVA Mgt Reorganization & Issues Re Restart of Unit 2 ML20149M6071988-02-22022 February 1988 Summary of 880211 Meeting W/Util Re Load Sequencing of Plant Diesel Generators.Attendance List & Handout Matl Used During Meeting Encl ML20195J5251988-01-21021 January 1988 Summary of 880120 Meeting Between Commissioner Bernthal & Admiral White of TVA Re Util Request to Retain Ofc of Special Projects as Overseer of Plants After Sequoyah 1 Restart & Invitation to Bernthal to Tour Sequoyah Plant ML20148Q0801988-01-21021 January 1988 Summary of Operating Reactors Events Meeting 88-03 on 880119.List of Events & Summaries of Presented Events & 1988 Scrams Encl ML20195J6011987-12-0303 December 1987 Summary of ACRS Subcommittee TVA Organizational Issues 871004 Meeting W/Nrc & Util in Washington,Dc Re Actions Being Taken on Plant Restart Issues ML20236X4741987-12-0202 December 1987 Summary of 871124 Meeting W/Util in Bethesda,Md Re Results of Testing of Silicone Rubber Insulated Cables for Unit 2. Transcript of Meeting Encl ML20236K8951987-11-30030 November 1987 Trip Rept of 871028-30 Site Visit to Gather Info from Files to Facilitate Updating Sims Database ML20235B2261987-09-15015 September 1987 Summary of 870910 Meeting W/Util in Knoxville,Tn Re Status of Cable Test Program.List of Attendees & Transcript Encl ML20235B1271987-09-15015 September 1987 Summary of 870911 Meeting W/Tva Re NRC Staff Presentation to TVA Findings from Integrated Design Insp.List of Attendees & Meeting Transcription Encl ML20239A6691987-09-0404 September 1987 Summary of 870901 Meeting W/Util,Bechtel & S&W in Bethesda, MD Re Criteria for Pipe Supports.List of Attendees,Handouts & SQN-DC-V-24.2 Supports for Rigorously Analyzed Category I Piping Encl ML20237G7631987-08-26026 August 1987 Summary of 870819 & 20 Meetings W/Util at Facility Re Status of Technical Issues Requiring Resolution Prior to Restart. List of Attendees,Agenda & Handouts Encl ML20235X0921987-07-16016 July 1987 Summary of 870713 Meeting W/Util,Franklin Research Ctr, Sandia,S&W & NUS Corp in Bethesda,Md Re Cable Testing Program.Util Proposing Revised Cable Testing Program to Test 380 Cables.Attendees List & Transcript Encl ML20234B9831987-06-26026 June 1987 Summary of 870619 Meeting W/Util in Bethesda,Md Re Util Proposed Program for Regeneration of Nonretrievable Pipe Support Calculations & Verification of Technical Adequacy of Existing Calculations.Attendees List & Util Handout Encl ML20216D0121987-06-19019 June 1987 Summary of 870601 Meeting in Bethesda,Md to Discuss Special Employee Concern Program.Attendee List & Handouts Encl ML20215A1881987-06-0909 June 1987 Trip Rept of 870520-22 Visit to Regional Ofc & Site to Discuss Ofc Procedures for Processing of Util Allegations & Status of Essential Elements of Restart Program ML20214L5911987-05-18018 May 1987 Summary of 870420 Meeting W/Tva in Chattanooga,Tn Re Review of Rev 4 to Vol 1 of TVA Nuclear Performance Plan & Status of Vol II of Plan.Agenda,Transcript of Meeting,List of Attendees & Viewgraphs Encl 1999-07-16
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210D7801999-07-16016 July 1999 Summary of 990715 Meeting with TVA Re TVA Evaluation of Fee Structure Compared with Recent Actual Fees & NRC Guidance in Estimating Review Effort for Licensing Actions.List of Attendees & Matl Used in Presentation Enclosed ML20210D7601999-07-16016 July 1999 Summary of 990616 Meeting with TVA in Rockville MD to Brief Staff on Planned SG Replacement.List of Attendees & Handout Provided by TVA Encl ML20210E0201999-07-16016 July 1999 Summary of 990629 Meeting with Util in Rockville,Md Re Ongoing Efforts in Planning Sf Storage Strategy,Including Licensing of Isfsi,At Plant.With Attendance List & TVA Handout ML20237E9811998-08-25025 August 1998 Summary of 980708 Meeting W/Tva & Framatome Cogema Fuel in Rockville,Md Re Ongoing Efforts W/Doe to Fabricate & Install Four Lead Test Assemblies in Plant,Unit 2 Core During Cycle 10 Refueling Outage in Spring of 1999.Attendance List Encl ML20216H5261997-08-26026 August 1997 Summary of 970822 Meeting W/Util in Rockville,Md Re Followup to Series of Conference Calls on 970418,discussing Results of Recent Steam Generator Insps at Sequoyah Unit 1.List of Attendees,Handouts & Staff Questions Encl ML20140B4701997-06-0404 June 1997 Summary of 970530 Meeting W/Tva in Rockville,Md to Discuss Status of Thermo-Lag Fire Barrier Corrective Action Program at Plant & Schedule for Completion of Program.W/Attendance List & TVA Handout ML20140G5621997-05-0808 May 1997 Summary of 970227 Meeting W/Tva in Rockville,Md to Discuss Sequoyah Conversion to Framatome Cogema Fuel.List of Attendees Encl ML20134J7451996-11-0808 November 1996 Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl ML20129H5211996-10-29029 October 1996 Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing ML20217D1931994-03-0707 March 1994 Summary of Sequoyah Restart Panel 940303 Meeting in Region II Ofc Re Status of NRC & Licensee Activities for Restart of Unit 1.Meeting Minutes & Unit 1 Restart Action Plan Encl ML20059K3131993-11-0505 November 1993 Summary of Operating Reactors Events Meeting 93-42 on 931103 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 ML20217D2111993-06-16016 June 1993 Summary of Sequoyah Restart Panel 930614 Meeting in Region II Ofc Re Plant Restart & Listed Items.List of Attendees & Checklists Encl.Next Meeting Will Be Held on 930622 ML20127D1321993-01-12012 January 1993 Summary of Operating Reactors Events Meeting 93-01 on 930106 ML20058J8621990-11-27027 November 1990 Summary of 901005 Meeting W/Util in Rockville,Md Re Cable Conduit Testing Program.Viewgraphs & Attendee List Encl ML20058K0311990-11-23023 November 1990 Summary of Operating Reactors Events Meeting 90-28 on 901114 Re Reactor Scrams for Wk Ending 901111.Attendees Listed 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 ML20059N2091990-09-21021 September 1990 Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements ML20059D8121990-09-0505 September 1990 Summary of 900817 Meeting W/Util in Rockville,Md Re Schedules of Certain Mods Committed for Completion in Unit 2 Cycle 4 Refueling Outage.Engineeering for Unit 2 Will Be Completed Before Restart from Outage ML20056B4101990-08-20020 August 1990 Summary of 900723 Meeting W/Util in Rockville,Md Re Plant Cable/Conduit Testing Program for safety-related Cable.List of Attendees,Tva & NRR Handouts & Transcript of Meeting Encl ML20055E2081990-07-0505 July 1990 Summary of 900531 Meeting W/Tva in Rockville,Md Re Plant safety-related Cable Inside Containment.List of Attendees, & Handouts Presented at Meeting Encl ML20246J8031989-07-12012 July 1989 Summary of 890609 Meeting W/Util in Rockville,Md Re Dissolution of Engineering Assurance Organization.List of Meeting Attendees,Util Handout,Agenda & Transcript Encl ML20245F9761989-06-22022 June 1989 Summary of 890614 Meeting W/Util & Westinghouse in Rockville,Md Re Future Work for Facility Cycle 4 Refueling Outage ML20247M1001989-05-26026 May 1989 Summary of 890511 Meeting W/Util in Rockville,Md Re Performance of Best Estimate Calculations for App K Analyses.Proposed Plan for LOCA Analyses,Meeting Handouts & List of Attendees Encl 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 ML20155A8081988-09-29029 September 1988 Summary of 880915 Meeting W/Util in Rockville,Md Re Microbiological Influenced Corrosion Program at Plant.List of Attendees & Viewgraphs Encl ML20154M9231988-09-21021 September 1988 Summary of 880913 Meeting W/Util at Site Re Unit 2 Shutdown Margin & Unit 1 Restart Readiness,Per Insp Repts 50-327/88-35 & 50-328/88-35.List of Attendees & Related Info Encl ML20154H4341988-09-16016 September 1988 Summary of 880908 Meeting W/Util in Rockville,Md Re Changes to Conditions Adverse to Quality Program.List of Attendees Encl ML20206B1961988-07-29029 July 1988 Summary of ACRS Subcommittee for TVA Organizational Issues 880722 Meeting in Washington,Dc Re Generic Lessons Learned from NRC Review of Util Concerning Restart of Facility ML20153A8371988-07-0101 July 1988 Summary of 880622 Meeting W/Util in Rockville,Md Re TVA Commitments on Facility.List of Attendees & Util Handout Encl ML20150E2321988-06-21021 June 1988 Summary of 880613 Meeting W/Util to Discuss Restart of Facility in Light of Recent Scrams from Power.Transcript of Meeting Encl ML20196A9201988-06-17017 June 1988 Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl ML20154A4061988-05-0404 May 1988 Summary of 880414 Meeting W/Util in Rockville,Md Re Differences Between Units 1 & 2 Nuclear Performance Plan. List of Attendees & Licensee Handout Encl ML20151D2701988-03-12012 March 1988 Summary of ACRS Subcommittee on TVA Organizational Issues Meeting on 880202-03 in Chattanooga,Tn Re Review of TVA Mgt Reorganization & Issues Re Restart of Unit 2 ML20149M6071988-02-22022 February 1988 Summary of 880211 Meeting W/Util Re Load Sequencing of Plant Diesel Generators.Attendance List & Handout Matl Used During Meeting Encl ML20148Q0801988-01-21021 January 1988 Summary of Operating Reactors Events Meeting 88-03 on 880119.List of Events & Summaries of Presented Events & 1988 Scrams Encl ML20195J5251988-01-21021 January 1988 Summary of 880120 Meeting Between Commissioner Bernthal & Admiral White of TVA Re Util Request to Retain Ofc of Special Projects as Overseer of Plants After Sequoyah 1 Restart & Invitation to Bernthal to Tour Sequoyah Plant ML20195J6011987-12-0303 December 1987 Summary of ACRS Subcommittee TVA Organizational Issues 871004 Meeting W/Nrc & Util in Washington,Dc Re Actions Being Taken on Plant Restart Issues ML20236X4741987-12-0202 December 1987 Summary of 871124 Meeting W/Util in Bethesda,Md Re Results of Testing of Silicone Rubber Insulated Cables for Unit 2. Transcript of Meeting Encl ML20235B2261987-09-15015 September 1987 Summary of 870910 Meeting W/Util in Knoxville,Tn Re Status of Cable Test Program.List of Attendees & Transcript Encl ML20235B1271987-09-15015 September 1987 Summary of 870911 Meeting W/Tva Re NRC Staff Presentation to TVA Findings from Integrated Design Insp.List of Attendees & Meeting Transcription Encl ML20239A6691987-09-0404 September 1987 Summary of 870901 Meeting W/Util,Bechtel & S&W in Bethesda, MD Re Criteria for Pipe Supports.List of Attendees,Handouts & SQN-DC-V-24.2 Supports for Rigorously Analyzed Category I Piping Encl ML20237G7631987-08-26026 August 1987 Summary of 870819 & 20 Meetings W/Util at Facility Re Status of Technical Issues Requiring Resolution Prior to Restart. List of Attendees,Agenda & Handouts Encl ML20235X0921987-07-16016 July 1987 Summary of 870713 Meeting W/Util,Franklin Research Ctr, Sandia,S&W & NUS Corp in Bethesda,Md Re Cable Testing Program.Util Proposing Revised Cable Testing Program to Test 380 Cables.Attendees List & Transcript Encl ML20234B9831987-06-26026 June 1987 Summary of 870619 Meeting W/Util in Bethesda,Md Re Util Proposed Program for Regeneration of Nonretrievable Pipe Support Calculations & Verification of Technical Adequacy of Existing Calculations.Attendees List & Util Handout Encl ML20216D0121987-06-19019 June 1987 Summary of 870601 Meeting in Bethesda,Md to Discuss Special Employee Concern Program.Attendee List & Handouts Encl ML20214H8681987-05-18018 May 1987 Summary of 870326 Meeting W/Util Re Diesel Generator Sequencing Calculations.Util Response to Questions in Form of Rev 5 to Calculations,Engineering Change Notification, List of Attendees & Other Related Documents Encl ML20214L5911987-05-18018 May 1987 Summary of 870420 Meeting W/Tva in Chattanooga,Tn Re Review of Rev 4 to Vol 1 of TVA Nuclear Performance Plan & Status of Vol II of Plan.Agenda,Transcript of Meeting,List of Attendees & Viewgraphs Encl ML20214F4431987-05-0808 May 1987 Summary of 870410 Meeting W/Tva in Bethesda,Md Re Status of Plant Restart Issues.Meeting Transcript & Related Documentation Encl 1999-07-16
[Table view] |
Text
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J. .
UNITED STATES 8
o NUCLEAR REGULATORY COMMISSION g h 9 $ WASHINGTON, D. C,20555
\ . . . . . *#g kOV 2 81986 i
Docket Nos.: 50-327 and 50-328 APFLICANT: TENNESSEE VALLEY AUTHORITY FACILITY: SEQUOYAH PLANT, UNITS 1 AND 2
SUBJECT:
MINUTES OF NOVEMBER 24, 1986 MEETING TO DISCUSS C0tiCRETE STRENGTH AT SE0VOYAH PLANT, UNITS 1 AND 2 On November 24, 1986, members of the staff met with representatives of the Tennessee Valley Authority (TVA) to discuss the results of recent investiga-tions performed by TVA on the concrete strength at the Sequoyah Plant, Units 1 and 2. Enclosure I is a list of attendees at the meeting. The TVA presen-tation is contained in Enclosure 2.
The meeting began with TVA presenting an overview of the program to date. This included a history of the issue of concrete strength and how it first arose.
Initially, the issue was identified as an employee concern at the llatts Bar Plant. It originally dealt with the fact that TVA did not follow the appropriate procedures for concrete strength, control and sampling frecuencies for concrete test specimens. The concern was made generic to all TVA nuclear plants since the construction procedure referenced was applicable to all units. Subsequent investigation by TVA into the problem at Sequoyah yielded a conclusion that the sampling frequencies used were acceptable. However, in several of the batch samples, over 10% of the measured strengths fell below the value specified in the procedure. It was required in the procedure that no more than 10% of the averaged test strengths of the last consecutive 30 samples be below the required strength.
As a result of this finding, TVA determined that for those concrete cours that did not meet the specified requirements, it would demonstrate that the actual strengths were acceptable for use. The TVA approach used to perform this demonstration was to calculate the equivalent specified strengths using the mean and standard deviation for the last 30 tests. This equivalent specified strength was then increased hased on an increase of strength which is expected to occur in concrete as it as~s. When this delta increase in strength was added to the equivalent specified strength, the resultant strength for most of the concrete in questien was above the minimum.value specified in the construction precedure. In addition to its discussion on the strength of concrete, TVA also discussed the sampling frequency of the strength tests and a bedding trortar evaluation it had perfonned as a result of the Watts Bar' concern.
A.ithough the staff found the method of calculating the equivalent specified strengths reasonable, it did not agree with the TVA approach of adding the additional strength which is expected to occur as a resu!t of aging. The reasons for this staff position were:
~~
8612050077 861128 PDR ADOCK 05000327 P PDR
NOV 2 31986 x (1) The test. data used to determine the expected increase in concrete strength were based en five test block pours. These values coulc be used for concrete that caree from the same mix; however, they ceu'd not be applied generally in the plant.
(?) The staff does not permit the use of this additional strength for concrete pours where the strengths dc, meet the required values. By allowing TVA to use this application would not be consistent with the normal staff practice. and (3) The American Concrete Institute Code spccifies that under conditions where the strength test do not meet the acceptance criteria additional non-destructive testing should be perforced in order to verify the adequacy of the inplace concrete.
Based on its review of the information presented at the meeting the staff identified to TVA two ways in which the staff believed the issue of con-crete strength could be resolved. One option was to use the equivalent strengths and verify that even with these lesser strengths the concrete could still perfonn its function. The second option was to perfonn some type of non-destructive strength test.
With respect to the other two issues discussed at the meeting, the staff concluded that, pending further arplification of the technical basis presented by TVA and submittal of additional information identified by the staff in the meeting, the TVA findings on the sampling frecuency and bedding mortar were acceptable. Additionally, the staff expressed a concern with some of the test data related to the slurrp and air content of the concrete. This staff concern arose as a result of the TVA investigation done at hatts Bor where it was discovered that there were deficiencies in the slump and air content of the concrete. The staff requested that TVA address this issue fcr Sequoyah and describe what, if any, deficiencies existed at Sequoyah and provide the basis for disposition of the deficiencies, as appropriate.
At the close of the neeting, TVA agreed to address the latter of the staff issues in its formal submittal. However, TVA stated that the method of calculating the equivalent concrete strength anc then adding to it the additional strength which occurs due to aging was a method that was being used for all of the TVA facilities. If the staff did not approve this approach, there would be a significant impact on the Uatts Bar Plant. Because of this, TVA would not cormit to change this approach and requested a nee ing on this subject for the-Watts Bar Plant. g(
Joseph J. Holonich, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A ,
PWR6 lR-A PW f / A PW p/EPWR-A PWI WR-A JHolo i h/ rad enyon CS ile BJYfuncblood 11 /86 11/ 86 11/g/86 11 86
,- ' MEETING SUtiftARY DISTRIBLITION NOV 2 81986 QDoEk~etTFilE*73 NRC Participants
.NRC POR J. Holonich L PDR G. Walton NSIC D. Jeng PRC System R. Ballard PWR#4 Reading File N. Reinhart M. Duncan H.'Asher OGC J. Partlow E. Jordan .!
B. Grires ACRS (10)
OTHERS bec: Licensee & Service List-I j
i I
Mr. S.A. White
., Tennessee Valley Authority Sequoyab Nuclear Plant CC: I Tennessee Departnent of Public Regional Administrator, Region II Health U.S. Nuclear Regulatory Connission, ATTN: Ofrector, Bureau of 101 Marietta Street, N.W., Suite 2900 Environn: ental Health Services Atlanta, Cecrgia 30323 Cordell Hull Building Nashville, Tennessee 37219 J. A. Kirkebo ATTN: D.L. Williams Mr. Michael H. Mobley, Director Ternessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive, W12 A12 T.E.R.R.A. Building Knoxville, Tennessee 37902 150 9th Avenue North hashville, Tennessee 37203 Mr. Bob Faas Westinghouse Electric Corp. Cou'nty Judge P.O. Box 355 Hamilton County Courthouse Pittsburgh, Pennsylvania 15230 Chattanooga, Tennessee 37402 R. L. Gridley Tennessee Valley Authority SN 157B Lcokout Place Chattanooga, Tennessee 37402-2801 M. R. Harding Tennessee Valley Authority Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 Resident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Caisy, Tennessee 37379 H.L. Abercror.bie Tennessee Valley Authority Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 f
l
1-
, *: Enclosure 1 LIST OF ATTENDEES i .
NRC
__ TVA i
G.'Walton N. Perry F. Rineldi R. Cullock
, D. Jeng R. Hernandez J. Holonich M. Cones ,
i R. Ballard M. Burzynski M. Reinhart W. Massie H. Asher i
Bhl R. Philleo 4
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Enclosure 2 TVA Presentation
.\ .
TENNESSEE VALLEY AUTHORITY
. SEQUOYAH NUCLEAR PLANT CONCRETE QUALITY EVALUATION PRESENTATION TO NRC ON SCOPE AND PROGRESS OF EVALUAll! ION NOVEMBER 24, 1986, 9:30 a.m. - 3:00 p.m.
BETHESDA, MARYLAND A. INTRODUCTION B. REVIEW PROGRAM C. CONCRETE STRENGTH EVALUATION D. SAMPLE FREQUENCY EVALUATION E. BEDDING MORTAR USAGE F. STRUCTURAL EVALUATIONS G. PROGRAM RESULTS i
H. CONCLUSIONS I
t 0438h 11/21/86 GC i i t
l l
e i
INTRODUCTION
N.
- INTERACTION WITH NRC STAFF
4
,i
{
6 9
l l
i l _ _ - . _ . _ . - . _ .
1 ,
i SCOPE OF EUALUATION
- Concrete Strength Test Reports
- Concrete Production Records OBJECTIVE:
Perform detailed assessment of deviations identified at WBN i
'~
~
i l
DOCUMENTED EUALUATIONS
~
- Memorandums, Design Deviations i
's. Requests, Etc.
Objective:
Identify all previous evaluations that have been performed.
k 8
. - - - - - , . - - - m . - - - - - _ . . - - - - - - _
_- . ,-y
i CONCRETE STRENGTH TEST REPORTS 100 % Review Test Reports -
Objectives Identify all mixes and s. periods time when deviations from ~
specification requirements occurred.
/
6 l
l l
4
.g 4
! CONCRETE PRODUCTION RECORDS
- Concrete Pour Card (4900+)
- Monthly Concrete Reports Objectives:
Identify all concrete pours made during periods that mix did not meet
., , specification requirements.
Determine if concrete sampling frequency requirements were met.
Investigate use of bedding mortar in concrete pours. , i
)
1 a
l i
4 STRENGTH EUALUATION ,
1 METHODS
- Determination of Equivalent Specified Strengths Same tec'hniques as used for WBN evaluation .
use mean and standard deviation for last 30 tests N s.
Calculate equivalent specified strength Special techniques
- for less than 30 tests l
l 8
)
1
s, i
. BOO.75BFW CReview 95 % Complete)
- FSAR documents evaluation for 7350 psi 8000 psi - 24 QA Pours -
7000 psi - 33 QA Pours 6800 psi - 20 QA Fours i
1 i
500.75AFW CReview SS % Complete)
N. 5000 psi - 210 QA Pours
( 4800 psi - 41 QA Pours
] 4600 psi - ES QA Pours i
i i
4 1
-,. _ - . . - , , - . - - . _ - - - - - - . - _ - - , . , . . . - - - , _ . . - - . - - - - ~ . . . . . . . . - - , - , . . - - . _ . . - - - . . ~ . . . . , _ . - . - _ - , ~ . . , . , . _ - - . ,
i 500.75AFWG CReview S5 % Complete) 5000 psi - 118 QA Pours.
4800 psi - 17 QA Pours
' ' 401.5AFW CReview 80 % Complete)
'w. 4000 psi - 53 QA Pours 3300 psi - 8 QA Pours 1
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.i 301.SAFW CReview 80 % Complete) 3000 psi - SOS QA Fours 2700 psi - 17 QA Pours 401.SAFWR1 CReview 100 % Complete)
N.
- FSAR documents deviation from specification was evaluated.
3500 psi - S11pformed #2 Shield Wall J #
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3OO.75AFW 1
(Review 80% Complete) 3000 psi - S18 QA Fours 2500 psi - 135 QA Pours i
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OTHER MIXES CReview SO % Complete)
N.
No Strength Reduction 2000+ QA Pours Note: Totals may not add up because some pours used 2 or more mixes.
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i SAMPLING FREQUENCY EUALUATION METHODS
,
- Review Monthly Concrete Reports -
Determine quantities placed per month
' Correlate to number of tests performed per mix
- Perform detailed review from pour cards for some critical mixes
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, . . _ ~ . _ _ . . _ - . , . ,- _ _ . - , - _ _ _ _ - . _ ~ . .-
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l BEDDING MORIAR EUALUATION l
METHODS.
j
- Evaluate mortar using,same a
methods as for WBN i
{ quantities in all concrete pours
~
i RESULTS s.
- Mortar used for pump lubrication Can l
acceptable practice)
- Mortar used in some congested, areas
- Not used as standard practice for, i bedding on joints i
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~
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STRUCTURAL EUALUATION EUALUATION OF POURS WITH STRENGTH LOWER THAN SPECIFIED METHODS
- Determine estimated inplace strength
- Determine appropriate concrete strength gain with age j -
Include affects of drying and l N. concrete temperature
- CMethods developed for WBN)
) -
Add conservative strength gain to
! equivalent specified strength Factor in mortar strength l
into evaluation
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'7 ,
. i STRUCTURAL EUALUATION EUALUATION OF POURS WITH STRENGTH LOWER THAN SPECIFIED RESULTS
- Evaluation on 8000 psi concrets
! -
- Reevaluation of 5000 psi concrete
- for which designs used strength
's. increase with age as allowed by Design Criteria
- Most 4000 psi concrete and all 3000 ,
psi will not require structural
. evaluation (Sufficient strength gain with age)
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- - - , - - - - - - - - - - - v-n. - -
e .._ -- , .---: --- .. -- , . .,
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i COMPARISON TO WBN RESULTS
- Compressive Strength Some deviations but only 5 % low tests
- Sampling Frequency Problem does n6t exist to significant degree ,
- Bedding Mortar N s' Mortar used differently.
. Lower volumes for pump lines, limited use in. congested areas.
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r-, -- .- . , - - - - - - .
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i CONCLUSIONS
- As identified in initial generic review, some deviations from concrete specification requirements occurred at SON
- The extent of the deviations at SQN ,
- while greater than initially identified was much less than at WBN
- Some deviations had previously been evaluated
'N-
- Inplace concrete strengths are acceptable and no modifications or
physical testing will be required.
S
. . . . , . . . . - . . - . .. . . . . .