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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] |
Text
),AC'f~ELERATED .
ISTB2BUTION DEME TPATION SYSTEM-REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9107230241 DOC. DATE: 91/07/11 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244-AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R
SUBJECT:
Forwards Rev 1 to EWR 5327, "Design Verification Ginna StatioContainment Foundation Mat Analysis," in response to 910625 request for addi info re contaa.nment integrity.
DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: Gen'eral Distribution Q ENCL Q SIZE: i + ,
G D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES REQIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 D JOHNSON,A 2 2 D
INTERNAL: NRR/DET/ECMB 7D 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC/LFMB 1 0 OGC/HDS1 1 0 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: -NRC PDR 1 1 NSIC 1 1
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A D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE Vice President AREA COOE7tB 546 2700 Cinna Nuclear Production July 11, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Ginna Containment Integrity Request for Additional Information R.E. Ginna Nuclear Power Plant Docket No. 50-244 (TAC No. 80494)
Dear Mr. Johnson:
This letter transmits to you the additional information requested by you in your June 25, 1991 letter (TAC No. 80494).
Table 1 presents all the load cases and parametric variations on properties and boundary conditions that have been analyzed in this evaluation. RG&E believes that the true behavior of the cylinder ring beam connection is bounded by "Run Names" RGE08 to RGE12 inclusive (refer to Table 2). These runs simulate resp-ectively a truly pinned connection, increasing variations in radial restraining moment, and a fully fixed condition. The fully fixed condition is judged not to exist based on the physical examination of the neoprene and based on the historically consistent results of the tendon lift off tests.
As an additional means of judging the integrity of the containment, RG&E compared the results of the analyses for the condition of fully pinned to fully fixed for the assumption of sliding and no sliding (Run Names RGE08 to RGE12 and RGE14 to RGE20 respectively). Table 3 presents the results of all those compar-ison of the critical moments considered in the UFSAR load combin-ations to the ultimate section capacities.
Figure 1 is a graph of radial displacements vs moment for the full range of base rotational resistance due to internal pressure.
They demonstrate the response of the structure for the sliding and non-sliding boundary conditions. As can be seen, the upper bound for both deflection and moment is at the pinned condition, and decreases as rotational resistance increases.
Figures 2 is a plot of radial displacements of the containment for RGE08 (pinned), RGE12 (fixed), and the results of the original Structural Integrity Test (SIT). Also shown are the displacements 910723024l nporr, nrnooK 9l07ll onooo24+
T7~
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for was RGE03. RGE03 is the lower bound for displacements because run with the hoop stiffness assumed to be based on an uncracked it concrete section. RGE08 and RGE12 are predictably higher than this case since these analyses were done with the hoop stiffness based on the reinforcing steel alone, which is orders of magnitude less than an uncracked section. ,As expected, the,SIT results are between these values because the actual stiffness at the test condition, is a combination of cracked and uncracked sections.
With this as an introduction, the specific issues will now be addressed.
Issue 1
- cases, In reference 2, it is stated (p. 5 of the report), "For all the results have shown no more than 10> increase from the original design value". The staff review of attachment 1 of reference 1 indicates that at 3 ft. above the base, the magnitude of the meridional moments can be larger than twice the original design value and under some conditions (fixed) they could be in the opposite direction. Provide justification for 10~ claim in the statement.
~Res ense Table 2 presents a comparison of the meridional moments obtained from the parametric analyses to the values listed in the UFSAR. The results of these analyses were compared to the moments at the critical section in the cylinder which are listed in the UFSAR. The critical section for the cylinder is ten (10) feet above the ring beam. The results of those comparisons for all analyses are shown in Table 2. As can be seen, the effect of increasing rotational stiffness is a decrease in moment at the critical section. The results for the bounding cases (cases RGE08 to RGE012) are shown to be below the UFSAR values. A review of all other computer runs shows that the maximum increases is about 10%
which occurs in run RGE14. This case is similar to RGE12 except that additional conservatism is added. Elastic elongation of the tension rods is not permitted which is not considered represen-tative of actual behavior. The 104 increase stated in the January 28, 1991 letter was intended to apply to those moments at the critical section only.
below.
A discussion of the response at the 3 ft. level is given Issue 2 Provide interaction diagrams for negative meridional moments (liner in tension). Provide comparison of meridional moments found in the reanalyses that you have already performed for various base conditions against the capacity at 3 ft. and 6 ft. above the base.
(>
5
~Res onse The interaction diagram for negative meridional moment was transmitted to you in our April 8, 1991 letter. The "Tendon Only" curve is applicable for resisting negative moments. Table 3 presents the comparison of meridional moments to section capaci-ties. As can be seen in Table 3, the capacity of the section is exceeded for only two cases, both of which are a fully fixed condition. RG&E does not consider this a concern because the "fixed" condition with no sliding cannot be physically achieved and the load combinations in which they occur include a factored internal pressure of 90 psi (504 greater than design).
Issue 3 In the above comparisons where the capacity falls short of the demand induced by the appropriate load combination, provide the necessary justification for assuring containment integrity and propose what physical evidence can be obtained about the true base condition during an integrated leak rate test.
~Res onse The subject of capacity versus induced moments is discussed above.
The results of the original Structural Integrity Tests have been reviewed. One data point at which radial displacement was measured was at 4 inches above the base. A second data point for the same measurement was at 72 inches above the base. The measured displacements at the 72 inch point and all points above are positive outward. The displacement at the 4 inch point is negative inward. The tension bars at the joint are located approximately 12 inches above the base. These measured displacements above and below the tension bars would imply that a rotation about the bars had occurred. Although the rotation itself was not measured, we have extrapolated a value, based on the radial displacements to be approximately 0.20 degrees.
The analytical results for a fully pinned condition indicate a rotation at the base of less than 0.20 degree. Since a fully pinned condition is achieved with this small rotation, the extrapolated rotation from the SIT implies that the response of the containment was as designed and no negative moments can be developed in the section.
The graph, Figure 2, displays the expected behavior of three models in relation to the SIT results. RGE03 (pinned, sliding base, uncracked concrete) matches fairly closely the SIT results near the base where you would not expect much cracking due to the presence of the radial tension bars. At higher elevations, RGE03 understates the displacements because there is cracking. The results of RGE09 (pinned, sliding base, cracked concrete) and RGE12 (fixed sliding base, cracked concrete), overstate the displacements
~ ~
at all locations, as expected, but are closer to the SIT values at higher elevations.
~Issue 4 Provide calculations (or results of computer output) for maximum shear stresses in the basemat of the containment under hydrostatic pressure due to highest groundwater level to be considered in the design, and how the thinnest basemat sections can withstand the shear stresses.
R~es ouse Attachment A transmits the analysis of the base slab in which concrete shear stresses are checked and are shown to be within allowable values.
Very truly yours, Robert C. Me redy LAS/231.ADD xc: Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road Ginna Senior Resident Inspector
4
'Fr Case Reference Chart- Shell Model Run Name Load . Applicabto Base Boundary Conditions Material Pro rtios Cases Loads Modulus Poisson (1) (I) Tie-Rods Tangential Vertical Rotational Radial Meridional Ciicumforencial Domo Ratio ft-Ibs/ft Sl sl si RGEOI D,PS,P,2E 2E Inacbvo Fixed Fixod Frco Fixed 4.10E+06 4.10E+06 Un cracked 0.15 SEISMIC ONLY RGE02 D,PS,P,2E 2E inactive Free Fixed Froe Fixed 4. IOE~06 4.10Ei06 Uncra eked 0.15 RGE03 D PS,P,2E 2E Acbve Free Fixed Free Free 4.10EG06 4 IOEG06 Uncracked 0.15 CONSTANT HOOP ,PS;P,2~8. nacbvo Fixed Free Fixed 4.10EE06 3btBISi9 ncracked REINFORCEMENT RGE05 D.PS,P,2E D.PS.P Inactive Free Fixod Free Fixed 4. IOE~06 3418@9 Uncrackod RGE06 D,PS(P,2E D PS P Ac6ive Free Fixod Froo Froo 4,10EEO6 SSIS 9 Uncrackcd SEISMIC ONLY 07 5,)sS.)',2E 2 Acbve Unor 2 Fixod Froe Free 4.10E+06 4.10E+06 Uncrackod 0.15 PINNED 08 ,P5;P,Z~ S,P Acdvo Fix Fixed Free Froe 4.10E>06 R ebar Vanos racked RADIAL ROTATIONAL IEGEDF D.PS,P,2E D,PS,P Active Fixed Fixed 3.00Etpt Free 4.IOEt06 R obar Varies Cracked RESISTANCE RGE10 D,PS,P.2E D,PS.P Acdivo Fixod Fixed 9.00EGOI Free 4. IOEG06 R ebar Varies Cracked SLIDING INCREASING ) RGEI I D.PS,P,2E D,PS,P Active Fixod Fixed 3.00EG02 Free 4. IDES 06 R char Varies Cracked FIXED FiWIEO AGEI2 IIGE44 D PS,P,2E OPS,P,2E D,PS.P D,PS,P Activo Inacdvo Fixed Fixed Fixed Fixod Fixed Fmo fiee Fixed 4JGE 4.10Et06 DA R obar Varies R obar Varios Cracked Cracked NO ROTATIONAL RGE15 D.PS,P,2E D,PS,P Inactive Fixed Fixed 3.DOE+01 Fixed 4.10EG06 R char Varios Cracked RADIAL RESISTANCE RGE16 D,PS,P,2E D,PS,P Inactive Fixed Fixed 9.00E<OI Fixed 4.10E ~06 R ebar Varlos Cracked INCREASING RGE17 D,PS,P,2E D.PS.P Inactive Fixed Fixod 3.00EI02 Fixed 4. IOE<06 R obar Varies Cracked SLIDING FIXED RGEIE DPSP2E .I DPSP Inactive Fixed Fixod Fix d Fix d 0 0 R ba Vaiio Cracked RGE20 lpga Active Free Fixod Froo (90-180')Fxd 4.10Er06 4 IDEAS Uncrackcd 0.15 SEISMIC ONLY RGE21 D,PS,P,2E 2E Inacbve Free Fixed Free (72-180o)Fxd 4.10Ei06 4 IOEE06 Uncracked 0.15 RGE22 D,PS,P,2E 2E Inacbvo Free Fixed Free (81-180')Fxd 4.10EI06 Rebar Varies Cracked 0 (I) D Dead Weight (2) Uner ~ The tangenbal stiHnoss associated with tho PS To Tendon prestress stool containment liner P 60 psi Intomal Prosuro TABLE 1
TABLE 2 (60 PSIG INTERNAL PRESSURE ONLY)
MERIDIONAL HOMENT (FT-KIPS/FT)
COHPUTER I MOHENT I PERCENT OF I MOMENT I PERCENT OF I RUN AT (
UFSAR I AT I UFSAR COHMENT I NAME I 10 FT I VALUE I 15 FT I VALUE I I
-I I RGE01 I 129 8 I 53-3 I 101.5 I RGE02 129.8 (
53.3 I 101.5 I RGE03 99.3 4o.s (
7s.5 I 32.2 I RGE04 258 I 105.9 I 249.7 I 102.5 RGE05 258 (
105.9 (
249.7 I 102 ~ 5 I P
I I RGE06 223.8 I 217.1 I 89.1 I-RGE07 99.4 40.8 I 12.7 I 5.2 I RGE08 231 ~ 8 I 95.2 I 223.8 (
91 ~ 9 I PINNED CONDITION I
-I RGE09 217. 7 I 89.4 I 216 I 88.7 ( ORIG. DESIGN COND. (ODC)
RGE10 191.5 I 78.6 I 202.5 I 83.1 (
THREE (3)X(OOC) HOHENT RGE11 100.1 I 41.1 I 155.3 I 63.8 (
TEN (10)X(ODC) MOHENT RGE12 -26.2 (
-10.8 (
90.9 (
ROTATION FIXED RGE14 268.8 ( 110.3 I 259.5 I 106.5 I SIHILAR TO RGE08 NO SLIDING I
-I RGE15 254.4 104.4 I 206.8 I 84.9 ( SIHILAR TO RGE09 NO SLIDING RGE16 234.7 I 96.3 (
244 ' 100.2 ( SIHILAR TO RGE10 NO SLIDING (
-I RGE17 1SS 63 6 I 208.3 I 85.5 I slHILAR TQ RGE11 No sLIDING
-I RGE18 -3s.1 I 15.6 I 121.3 I 49.8 I SIHILAR TO RGE12 NO SLIDING
-I RGE20 46.4 I '88.7 I 36 ~ 4 I UFSAR - 243.8 FT-K/FT AT 60 PSI AT TEN FEET
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~
~ TABLE 3 LOAD COHBINATION 29 "a" MERIDIONAL MOMENT FT-K/FT (1.0*DL) + (1 ~ 0*VP) + (1.0*OTw) + (1.5*IP) + (1.0*AT90)
I ROTATIONAL ILOCATION I HOHENT- PERCENT I MOMENT- PERCENT I I BASE I ABOVE I SLIDING IULTIMATE I NO SLIDING IULTIMATE I FIXITY IBASE(FT) PERMITTED ICAPACITY PERMITTED CAPAC I TY I I I I
I 3 158 I 24.7 I 185 28.9 I FREE 6 I 282.9 I 32.5 I 328. 1 37.7 I (PINNED) 10 I 373.2 I 42.9 I 428.7 49.3 I
I 15 401 I 46.1 I 454.5 I 52.2 I
I I 120 I 18.8 I 149 I 23.3 I I
0 FT-K/FT I 252.5 I 29 I 301.1 34.6 I I
I 10 351 ~ 9 I 40.4 I 411.6 47.3 I
I 15 389.3 44.7 I 446.8 51.4 I 3 46 I 72 I 78 12.2 I
90 FT-K/FT I 6 I 194 3 I 22.3 I 246.9 2s.4 I I
I 10 I 312.8 I 36 I 377.4 I 43.4 I I-I 15 I 369 I 42.4 I 431.4 I 49.6 I 3 -212 I 33.1 I
-173 I 27 I
I300 FT-K/FT 6 9.5 I 1.5 I 57.55 6.6 I
I 10 I 20.2 I 257.9 I 29.6 I I 15 I 298.2 I 34.3 I 377.6 43.4 3 -574 I 89.7 I
-780 121.9 I FIXED 6 I -293.4 I 45.8 I 401 ' I 62.7 I 10 I
-14 I 22 I
-31.9 I 5 I 15 I 201.6 I 23.2 I 247.2 I 28.4 I DL = DEAD LOAD IP = INTERNAL PRESSURE (60PSI)
VP = TENDON PRESTRESS AT90 = ACCIDENT PRESSURE (90PSI) T = 312 F OTw = OPERATING TEMPERATURE WINTER 1/4
TABLE 3 LOAD COHBINATION 31 "b" HERIDIONAL MOHENT FT-K/FT (1.0*DL) + (1.0*VP) + (1.0*OTs) + (1.5*IP) + (1.0~AT90)
I ROTATIONAL ILOCATION I HOHENT- I PERCENT I MOHENT- PERCENT I BASE I ABQVE I SLIDING IULTIHATE I NO SLIDING IULTIHATE FIXITY IBASE(FT) I PERMITTED I CAPAC I TY I PERMITTED I CAPACITY I I
I 3 184 I 28 ' I 211 33 I I I- ----I I FREE I 6 312.4 I 35.9 I 357.6 (PINNED) I I I 10 I 385 I 44.3 I 440.5 50.6 I I I-I 15 I 372.2 I 42.8 I 425.7 48.9 I I 3 146 I 22.s I 175 27.3 I I
I 30 FT-K/FT 6 I 282 I 32.4 I 330.6 I 38 I I
I 10 I 363.7 I 41.8 I 423.4 I 48.7 I I
I 360.5 I 41.4 I 418 I 48 I I
I I 72 I 11.3 I 103 I 16.1 I I
I 90 FT-K/FT 223.8 I 25.7 I 276.4 31.s I 10 I '24.6 I 37.3 I 389.2 44.7 I I-I= 15 340.2 I 39. 1 I 402.6 46.3 I
I 3 I -186 I 29.1 25.9 I I I I300 FT-K/FT I 6 2OI 23I 87 I 10 I I I I 10 I 187.4 I 21.5 I 269.7 31 I I I
- ---I I I 15 269.4 I 31 I 348.8 40.1 I I
3 I
-548 I 85.6 I
-754 117.s I FIXED I 6 I 263.9 I 41 ~ 2 I 372.3 I 58.2 I 10 I -2.2 I 0.3 I 20 I 2.3 15 I 172.8 I 19.9 I 218 I 25.1 I DL = DEAD LOAD IP = INTERNAL PRESSURE (60PSI)
VP = TENDON PRESTRESS AT90 -" ACCIDENT PRESSURE (90PSI) T = 312 F OTs = OPERATING TEMP. SUHHER 2l4
TABLE 3 lg LOAD COHBINATION 41 "c" MERIDIONAL MOMENT FT-K/FT (1.0*DL) + (1.0*VP) + (1.0*OTw) + (1.0*IP) + (1.0*AT60) + (2.0*E)
ROTATIONAL i LOCAT ION MOHENT- PERCENT )
HOHENT- PERCENT BASE I ABOVE SLIDING IULTIMATE I NO SLIDING iULTIMATE 1
FIXITY /BASE(FT) PERHITTED ICAPACITY I PERMITTED ICAPACITY I I I I 00 I 15.6 I 118 I 18.4 I
FREE I 6 I 184.3 21.2 i 214.5 24.7 )
(PINNED) I- I 1
253 29.1 ) 290 ) 33.3 1 I I 15 286.4 32.9 i 322.1 37 I 75 94 I 14.7 I
30 FT-K/FT 18.9 i 196.4 22.6 I
I 10 238.8 I 27.4 I 278.6 )
32 )
I I I 15 278.6 i 32 )
317 I 36.4 25 t 3.9 )
46 I 7.2 90 FT-K/FT 125.2 14.4 160.3 .18.4 l-I 10 212.7 (
24.4 255.8 I 29.4 I
I 15 265.2 I 30.5 I 306.8 35.3 (
-I I
"147 i 23 -120 18.8 l-300 FT-K/FT I 6 -10.7 1.7 I 34.1 3.9 f I -I 10 121.2 13.9 I 176.1 20.2 I-15 217.9 I 25 I 270.9 l 388 I 60 6 I
-525 82 )
I- I FIXED I -199.9 31.2 )
-272.2 I 42.5 I-I 10 -5.2 I 0-8 I
-17. 1 I 2.7 I I-I 15 153.6 183.9 21.1 DL = DEAD LOAD IP "-INTERNAL PRESSURE (60PSI)
VP = TENDON PRESTRESS AT60 = ACCIDENT PRESSURE (60PSI) T -" 286 F OTw = OPERATING TEMPERATURE WINTER E
"-0.10 G EARTHQUAKE HORIZONTAL + VERTICAL sl4
TABLE 3 LOAD COHBINATION 43 "d" HERIDIONAL HOMENT FT-K/FT (1 '*DL) + (1.0*VP) + (1.0~OTs) + (1.0*IP) + (1.0*AT60) + (2.0*E)
I ROTATIONAL I LOCATION HOHENT I PERCENT HOHENT- I PERCENT I BASE ABOVE SLID I NG I ULT IMATE NO SLIDING IULTIHATE I I FIXITY IBASE(FT) PERMITTED ICAPACITY PERMITTED ICAPACITY I I I I I 125.8 I 19.7 I 144 22.5 I I I-I FREE I 213.8 I 24.6 244 I 28 I I (PINNED) I-I I 10 264.8 I 30.4 301.8 34.7 I I I- -I I I 15 . 257.6 I 29.6 293.3 33.7 I I
-I I 3 100 I 15.6 119 18.6 I I I- -I I 30 FT-K/FT I 6 I 193 ' I 22.2 225.9 26 I I I- -I I I 10 250.6 I 28.8 290.4 33.4 I I- -I I I 15 249.8 I 28.7 288. 2 I 33.1 I I- I I I 51 I 8 I 72 I 11.3 I I I-I 90 FT-K/FT I 154.7 I 17.8 189.8 21.8 I I I- -I I 10 224.5 I 25.8 267.6 I 30.8 I I- -I I 236.4 I 27.2 278 I 32 I
-I 3 121 I 18.9 -95 I 14.8 I I- -I I FT K/FT I 6 18.8 I 2.2 63.6 I 7.3 I I I- -I I I 10 133 I 15.3 187.9 21 ~ 6 I I I-I I 15 189.1 I 21.7 242.1 I 27.8 I I- -I I 3 363 I 56-7 -500 78.1 I
I- -I I FIXED 6 170 ' I 26-6 -242.7 37.9 I I I- -I I I 10 6.6 I 0.8 -5.3 I 0.8 I I I- -I I
'l5 124.8 I 14.3 155.1 I 17.8 I DL = DEAD LOAD IP = INTERNAL PRESSURE (60PSI)
VP = TENDON PRESTRESSS AT60 "- ACCIDENT PRESSURE (60PSI) T = 286 F OTs = OPERATING TEHPERATURE SUMMER E = 0.10 G EARTHQUAKE HORIZONTAL + VERTICAL 4/4
p ~ ~
DISPLACEMENT. (IN.)
37 Gl m
mL lO 4% C..-
A fg" .0 0 Q,o r
o
~Q ITI 0 Q 2 Zl
(
Q)
~
0 R
0 o A
m 0 Zr <(n I
'go 0 0 0 g O'9Z l7l m <
ITl m 2 z - Ql XI A
m
'g I
O 0 A m
C) m G)
O 27 ITl A
m ITl Vl 0K A m
FIGURE 1
STRUCTURAl INTEGRITY TEST
~ RGE03 RGE08 o RGE12 I 5 LLL M5 LLl O4 Cl X4 I
C9 LLJ 10 A2 S3 .4 S5 RADIAL DISPLACEMENT (IN.)
CONTAINMENT RADIAL DISPLACEMENT FIGURF 2
t 'J