Similar Documents at Ginna |
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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] Category:UTILITY TO NRC
MONTHYEARML20059L4481990-09-18018 September 1990 Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21) ML17309A4491990-09-13013 September 1990 Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld ML17262A1331990-09-11011 September 1990 Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion ML17261B1511990-08-29029 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively ML17261B1481990-08-28028 August 1990 Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant IR 05000244/19880261990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1501990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1371990-08-17017 August 1990 Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant. ML17309A4481990-08-16016 August 1990 Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records ML17261B1351990-08-15015 August 1990 Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function ML17261B1361990-08-14014 August 1990 Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts ML17261B1331990-08-13013 August 1990 Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002 ML17261B1261990-07-30030 July 1990 Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days ML20055H9291990-07-23023 July 1990 Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21 ML17261B1091990-07-20020 July 1990 Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp ML17309A4471990-07-17017 July 1990 Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b) ML17261B0881990-07-13013 July 1990 Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability. ML17261B0921990-07-11011 July 1990 Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723 ML20044B0481990-07-10010 July 1990 Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs ML17309A4461990-07-0909 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML17261B0931990-07-0909 July 1990 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs ML17261B0901990-07-0909 July 1990 Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion ML17250B2151990-06-29029 June 1990 Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries ML17261B0851990-06-28028 June 1990 Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21 ML17250B1991990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983 ML17250B1951990-06-0505 June 1990 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept ML17250B1851990-06-0101 June 1990 Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs ML17261B0691990-06-0101 June 1990 Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear ML17250B1811990-05-31031 May 1990 Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21) ML17250B1801990-05-29029 May 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity ML17250B1841990-05-29029 May 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined ML17261B0961990-05-29029 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred ML17250B1721990-05-18018 May 1990 Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage ML20042G8931990-05-0808 May 1990 Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3 ML17261B0611990-04-26026 April 1990 Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements ML17261B0591990-04-17017 April 1990 Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur ML17261B0461990-04-12012 April 1990 Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys ML17262A1431990-04-12012 April 1990 Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys ML17250B1451990-04-0606 April 1990 Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed ML17250B1441990-04-0505 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion ML17261B0401990-03-30030 March 1990 Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501 ML17261B0321990-03-28028 March 1990 Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp ML17261B0331990-03-28028 March 1990 Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date ML17261B0231990-03-26026 March 1990 Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated ML17261B0281990-03-23023 March 1990 Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods ML17261B0221990-03-22022 March 1990 Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828 ML17261B0411990-03-20020 March 1990 Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4) ML17261B0151990-03-19019 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses ML17261B0101990-03-15015 March 1990 Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies ML20012D2831990-03-14014 March 1990 Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl 1990-09-18
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (BIDS)
ACCESSION NBR 8709100204 .DOC. DATE: 87/09/01 NOTARIZED: NO DOCKET ¹ FAC IL: 50-244 Robert Emmet Ginna Nuclear Plant> Unit 1> Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION OBER> R. W. Rochester Gas 5 Electric Corp.
REC IP. NAME RECIPIENT AFFILIATION RUSSELL> W. T. Region 1> Office of Director
SUBJECT:
Responds to NRC 870730 ltr re deviations noted in Insp Rept 50-244/87-11. Corrective actions: pipe supports redesigned to use new Hilti Kwik-Bolts in place of existing shell-type anchor bolts. Revised support drawings encl.
DISTRIBUTION CODE:
TITLE: General IEOID COPIES RECEIVED:LTR (50 Dkt)-Insp Rept/Notice of J ENCL Violation gResponse SIZE:
NOTES: License Exp date in accordance with 10CFR2> 2. 109(9/19/72). 05000244 REC IP IENT COPIES REC I P IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDi-3 PD 1 1 STAHLE> C 2 2 INTERNAL: AEOD 1 1 DEDRO 1 1 NRR MORISSEAU> D NRR/DOE* DIR 1 1 NRR/DREP/EPB 1 NRR/DREP/RPB 2 2 NRR/DRIS DIR 1 1 NRR/PMAS/ ILRB 1 1 OE E - MAN> J 1 1 OGC/HDS2 1 RE FILE 1 1 RES DEPY GI 1 FILE 01 1 1 ERNAL: LPDR 1 . 1 NRC P DR 1 1 NSIC 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 20
>R.,>RAPIOr, ~ 89 EAST AVENUE, ROCHESTER, N,Y. 14649 0001 ROGF L'
'l"
, C~CP<<O'lC CIRC,>> ~ ~
..ig ~ <.oar:Ie 646-2700 September 1, 1987 Mr. William T. Russell, Regional Administrator U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406
Subject:
Inspection No. 50-244/87-11 R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Russell:
This letter is ROTE's response to Inspection Report 87-11, transmitted by the NRC's July 30, 1987 letter from William V. Johnston to Roger Kober. In the Inspection Report, RG&E was requested to respond to the two Notices of Deviation, and to: 1) document the scope and results of the static equivalent analyses performed for selected portions of the Standby Auxiliary Feedwater and Service Water systems, 2) provide the status of the anchor bolt replacements, and 3) provide the schedule for completion of the Ginna long-term Seismic Piping Upgrade Program. This information is provided in Attachments 1 and 2.
In addition to these two Notices of Deviation, Section 6 of the Inspection Report noted that "...the licensee's QA Manual and Qh. Procedures Manual could be improved in the area of addressing requirements imposed by NRC/IE Bulletins".
RG&E is evaluating our processes necessary, will revise our procedures.
for responding to NRC/IE Bulletins, and, if Ve truly yours, Roger W. Kober Attachments xc: U.S. Nuclear Regulatory Commission Document Control Desk (Original)
T. Polich Ginna Resident Inspector 8709'f00204 87090i PDR 6
ADOCK 05000244 PDR ~g bl
~hi
ATTACHMENT l RESPONSE TO NRC INSPECTION NO. 50-244/87-ll As a result of the inspection conducted on Nay 5-8< 1987I the following deviation was identified.
Deviation A:
I.E. Bulletin 79-02< Pipe Support Base Plate Design Using Expansion Anchor BoltsI Revision 1 Supplement 1 permitted continued plant operation given the following two conditions were satisfied:
- a. For the pipe support as a unitI the factor of safety compared to ultimate strength is equal to or greater than two.
- b. For the anchor bolts the factor of safety is equal to or greater than two and for the support steel the original design factor of safety compared to ultimate strengths xs'et.
This supplement further specified that "Any support not satisfying the criteria should be classed as inoperable and the Technical Specification action statement met..."
Action Item 2 of the Bulletin 79-02 required that the licensee verify that the concrete anchor bolts have minimum factors of safety of 4e0 for wedge type anchors and 5.0 for shell type anchors. The licensee committed in the July 6I 1979 response to provide verification of the factor of safety for all Seismic Category I support anchor bolts.
Contrary to the licensee's commitment< the licensee did not have calculations to demonstrate the factors of safety for all supports subject to the Bulletin requirements."
R~es ense=
Prior to July 6I 1987 Rochester Gas and Electric completed an interim assessment for concrete expansion anchor bolt factors of safety. This assessment was performed at the request of NRC Staf f and was a result of the findings of NRC Inspection No. 87-11.
Inspection 87-11 determined that the Service Water (SW) system in the screen house and the Standby Auxiliary Feedwater (SAFW) system were not included in the RGEE Seismic Piping Upgrade Program.
This Upgrade Program is the means by which RGGE addressed the long term concerns of NRC IE Bulletin 79-02. In order to determine whether potential problems might exist for the subject systems in terms of the 79-02 criteriaI an interim assessment was made of the factors of safety for the expansion anchor bolts of the subject pipe supports.
As was suggested by a Staff consultant< an equivalent static analysis was performed on two representative sections of piping.
The pipe support loads from this conservative analysxs were combined for a "worst case" condition of Deadweight + Maximum Thermal + SSE. These pipe support loads were then used to calculate anchor bolt factors of safety. For wedge-type anchor bolts with an initial calculated factor of safety less than 8> a base plate flexibility analysis was performed. Bolt loads were then re-evaluated to account for plate flexibility. For the supports with a factor of safety of 8 or greater< sufficient margin exists to ensure that the factor of safety is not reduced below 4 with plate flexibility effects and no plate analysis was performed at this time.
For the SN system in the screen house> the selection of the section of piping to be analyzed was made based on the physical configuration of the piping. This system consists of two parallel trains connected by a smaller cross-connect. The two trains are virtually identical in layout and have the same numbe'r of supports with expansion anchor bolts. The train with the slightly shorter pipe run was selected to reduce the time required for piping analysis modeling. The section of the SAFW systems chosen was based o'n the portion most important from a plant safety 'stand-point. Therefore> the portions of the system from the containment penetrations to the main feedwater piping were reviewed and the shorter section was selected to minimize the piping analysis modeling time and the time for completion of the interim assessment.
The analysis results for the calculated factors of safety for the expansion anchor bolts associated with the SW line range from 2.73 to 8.4. The range of anchor bolt factors of safety for the SAFN line were found to be from 2.48 to 27.0. A complete summary of the results of the analysis is attached. Based on the results of this assessment and the conservative approach taken in the analysis> RG6E has a high degree of confidence that the supports of the subject systems are acceptable in terms of the requirements of 79-02 for the interim condition. RGGE is currently in the process of making a complete evaluation of the piping of the subject systems. The supports associated with these lines will be evaluated to criteria which are similar to that of the completed Seismic Piping Upgrade Program. The initial engineering for this Seismic Piping Upgrade scope extension has been started but a detailed schedule has not yet been developed. It is currently expected that'ngineering will proceed on a schedule such that any support modifications can be started during the 1988 refueling outage. Completion of construction activities are expected to be completed by the end of the 1989 refueling outage.
U MARY OF E ULT F R I ER M AN H R B LT FAC OR OF SAFETY EVALU N Pipe Support Method of Anchor Bolt Factor of Safety Number ~stem Attachment t T eFS N732 SW Anchors set in concrete Note 1 N733 SW Anchors set in concrete See Note 1 N734 SW Expansion anchor bolts 3/wedge/8.4 1/shell/6.4 See Note 2 N735 SW Expansion anchor bolts 4/shell/2.73 See Note 2 N740 SW Anchors set in concrete See Note 1 N741 SW Anchors set in concrete See Note 1 N744 SW Expansion anchor bolts See Note 3 N745 SW Expansion anchor bolts See Note 3 AFW-3 SAFW Welded to str. steel AFW-4 SAFW Welded to str. steel AFW-5 SAFW Welded to str. steel AFW-6 Welded to str. steel AFW-7 SAFW Welded to str. steel AFW-8 AFW-9 SAFW SAFW Welded to Expansion bolts'ee str. steel anchor bolts 4/wedge/27.0 AFW-10 SAFW Expansion anchor bolts 2/wedge/5.24 See Note 2 AFW-ll SAFW Expansion anchor bolts 4/wedge/15. 96 AFW-12 SAFW Expansion anchor bolts 2/wedge/5.26 See Note 2 AFW-13 SAFW Expansion anchor 2/wedge/2.48 See Note 2 Notes:
- l. Not subject to 79-02 criteria.
- 2. Base plate analysis performed.
- 3. Per piping analysis, support is in compression only.
ATTACHMENT 2 RESPONSE TO NRC INSPECTION NO. 50-244/87-11 As a result of the inspection conducted on Nay 5-8I 1987I the following deviation was identified.
Deviation B:
I.E. Bulletin 79-02, Action Item 4I requires that each anchor bolt used in piping system supports must be inspected unless it can be
'established that tension loads do not exist. The licensee's July 6 and December 7I 1979 responses to Bulletin 79-02 committed to reanalyze supports within the scope of the bulletin prior to initiation of inspection and testing.,
Contrary to the licensee's commitmenti the licensee records disclosed that Seismic Upgrade Program modifications performed to some piping systems made it possible for some compression-only supportsi that had load changes> to be subjected to tension loads.
This situation exists in five supports of a Seismic Category I
.system. At the time of thzs NRC inspection the licensee had not inspected the anchor bolts in these supports for proper installation< specified size and type."
~Res ense:
At the time of the NRC inspection> the disposition of supports for IE Bulletin 79-02 was compared against the support modifications for the Seismic Upgrade Program. This comparison identified five supports which had not had the anchor bolts inspected for proper installation and which were now indicated as having tensile bolt loads. Subsequent detailed review of the latest support infor-mation determined that> in fact> one support still had no tensile loadsi while the remaining four supports remained unresolved.
Since the support configuration for these four supports did not allow adequate confirmation of the anchor bolt znstallationi the supports were re-evaluated to install new bolts.
The pipe supports were redesigned to use new Hilti Kwik-Bolts in place of the existing shell-type anchor bolts. This new bolt configuration was designed in accordance with the requirements of NRC IE Bulletin 79-02. The modifications of the four supports including new anchor bolts> have now been completed. Copies of the revised support drawings are attached. Note that the Inspection Report incorrectly identifies these supports as being in the Standby Auxiliary Feedwater system and the Service Water system in the screen house. These supports are actually located on systems which were modified as part of the original Seismic Upgrade Program scope. The attached drawings are for supports CCU 86I CCU 156I SWU 196 and SWU 198
I DESIGN DATA:
TYPE OF SUPPORT I3 PLATE AND SHELL REFERENCE DESIGN DRAWINGS 8 LINEAR Pi< ING 0->CI+-4Z,B Q COMPONENT STANDARD ISOMETRIC C +~I ~~ SHT. 9 STRUCTURAL CODE CLASS ANALYSIS CODE (-C- IOO ~
MAX.DESIGN TEMP.( F)
FORME.PLY pCQ-c)3 Z~
PREDICTED PIPE MOVEMENT (INCHES) 0 001 Y 0 OO(
DESIGN MECHANICAL LOADS +Y FORCE (LBS.) MOMENT (IN.-L85.)
Fx Fy Fx My Mz NORMAL UPSET tlat lo
+X EMERGENC FAULTED t R.2.6C)
C)
RIGHT HAND CAR 7 E SIAN COORDINATE SYSTEM TESTING C 0:i 8 'R (. C T I iI N NOTES: LIViil' ('~'" ",I ' )~ ~ >'q r,<(%IF'HE GENERAL-DESIGN, FABRICATION ANO ERECTION OF THIS PIPE SUPPORT IS AND SHAI.L BE IN ACCORDANCE WITH SPECIFICATIONS:
AGEE, SPEC. NCI2lg NA ALL WELDS SHALL BE MADE WITH ELECTRODES HAVING A MIN.TENSILE STRENGTH OF 60,000
/ NA PSI ~
MOVEMENTS AND FORCES ARE BASED ON NORMAL OPERATING TEMPERATURFS THE ABOVE NOTES DO NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THESE ITEMS WERE PURCHASED AND INSTALLED PRIOR TO I980.
6'XLSTlb4$ SA55 PL@ TV ) FEHCHQR BOLTS) CHQgNPLS) AND GROL)7 STI<V CTL) RALLY <GOVT B> I ITINCj HOL 6 5 ) td A<<-ORDA446 W~ TH KE Al - XVSreu. iaW &VS'Lh, TC.> H>LTI 5, CHgghlBL SEC.'Tlt)A& AND &HIM PLATE..
NUCLEAR SAFETY RELATED ALL SIGNATURES AHD REVISIOHS OH THIS SHEET PERTAIN TO ALL SHEETS ASSOCIATED AEV'0 Pf R RM C. COMM </'I i'3 yg~ I WITH THE PIPE SUPPORT INDICATED BELOW P.~V'D. PER 'IGNI-R6-l5<4- %Illy CONSTRUCTION
~A A5 SQ(UY HP CLlF 8-7 RE.LEAM fr/
REV. MADE CHKD. 0 E SC R I P T I 0 N ~~G'PIR DATE DATE RELEASED FOR. APPR R E V I SION 5 O 044824-005 SCALE: NONE L)KNT MADE CHKO. PIPING ENGINEERING APPROVALS N, H CHK,
~
'OCHESTER GAS ANO ELECTRIC CORPORATIO RLS e JECT HA STATION (E1VR-2512)
SIGN DATE 314 .') iLJ ~ I-8I IO-I-Sl PIPE SUPPORT GIL8ERT ASSOCIATES, IHC.
ENGINEERS 8 CONSULTANTS MK-C(-O B,( S 382- '55& OBG .A READING, PA. TITLE DRAWING NUMBER SHEET REV.
NO. PART MATERIAL ITEM REQD. D ESCRI P TI ON
'f NO. SPECS.
~E "ct) HILT l KwllC BOLT Hlo. EeS.= ZV "
I2."x l2" X>i' E'LATE. SA aH C4x 5.4. CHANNEL
" Flap T&NC-HLON "I ~ Co1 T4 soil 5ABS
~ 4 x 2 "2 ' G.
~ " PLATE 7"x Yz" L8 TE EF.'yZ'x 6 l 7Nx I q" x 8" x TELIC)c~CGS To SvIV S~le PLWWE..
FORHlF-R,'LY ACH-93
- 4. lO" PlPE FL. 2,72.'- lo~" (REF. )
C 0 "I 5 T R U C T I 0 N
+v 7a PAl BE 2
r=
IO-4o 0
l ~
(RE.F
,0 p SECTION A A LOCATION PLAN AoxILIAFIY BUILDING FOR SIGHATURES AHD REYISIOHS, SEE GAI SHEET A
.LIENT OCHESTER GAS AND ELECTRIC CORPORATIO OJECT NUCLEAR SAFETY RELATED NNA STATION (EWR-2512)
PIPE SUPPORT GILBERT ASSOCIATES, INC.
ENGINEERS E CONSULTANTS MK-ccu r S -382-G~ OS< 8 3 READING, PA. TITLE ORAWIHG HUIIBER SHEET REVS
Iz FOR ME.RLY ACH-9Z I'0'~p)~ (mI.) 5 STANCHION \ S, CEN 7ERKD ON PLATE, NO WE.'LD (mp)
I'/~
(TYF.')
I 8)-EXi~r. HOZE:S C
SECTION LOC4TE, I X Z 4 C.VT'GUT IN C HATCHEL RCLATIVE, jO QA'I STTN6-"
LVQ L,CWT'ID'. m N -]et SECTION C -C FOR SIGNATURES AHD REVI SIGHS, LIENT SEE GAI SHEET A l
ROCKESTER GAS AND ELECTRIC CORPORATIO NUCLEAR SAFETY RELATED
~M~A sTATIOH ( EWR- Zei2) PIPE SUPPORT GILBERT ASSOCIATES, INC.
EHGIHEERS & COHSULTAHTS M<-CCO- 8a S-52-~m 056 C RKAOIHG, PA. TITLE ORAWIHG HUNBER SHEET REY.
DESIGN DATA:
TYPE OF SUPPORT Ej PLATE AND SHELL REFERENCE DESIGN DRAWINGS
- 5) LINEAR P IP IN G 5 -3 0 '4 - o Z3 ISOMETRIC C-MI 3RSHT. 2 0 COMPONENT STANDARD STRUCTURAL +
CODE CLASS MAX.DESIGN TEMP.( P) ANALYSIS CODE Y~
PREDICTED PIPE MOVEMENT (INCHES) e ~D.
~ o.ozc e.
Pop<KR,u. ~(=H-Rz DESIGN MECHANICAL LOADS FORCE (LBS.) MOMENT (IN.-LBS.)
Fx Fy Fx My Mz I('o I NORMAL 4 UPSET + 0 CS EMERGENC +Z FAULTED + C)J RIGHT HAND CARTESIAN oB COORDINATE SYSTEM TESTING
(;
,CHANNEL),AND G Roui. 'STAvc ( RooT E.)(I M /A6- M<E 5 l q
/J C.('.OROhtuC E U>>TH M< IZ l.
Pw~, HI a.>'s ('.ehvnta SWT I oil S NUCLEAR SAFETY RELATED ALL SIGNATURES AHO REVISIOHS OH THIS AS EV' Cg L
~ CCIQM~75 NT. Fi.s SHEET PERTAIH TO ALL SHEETS ASSOCIATED WITH THE PIPE SUPPORT IHDICATED BELOW gE/'D E=L-R 13PII-Rb- i5Z'I CONSTRUCTION AS BuIL.T PFR FCR 25IC,- 5 I' l RLS ,'Ja e~ e
'/.~1.~ IE t/(7 CLlg,kl I EE.Lt A SF REV. MADE CHKD. DESCRIPTION I klT APPR DATE DATE RELEASED FOR APPR ~
R E V I SION S W.O. 044824-005 SCALE: NONE LIENT MADE CHKD PIPING ENGINEERING APPROVA 5 te
(
~
HSS I PS
'OCHESTER GAS AND ELECTRIC CORPORATIO SIGN 6 ~A PgZ)
JECT NA STATION (EWR-2512)
DATE 11 IB Sl Il ZS.81 gg /-7 I~ LL 'bZ PIPE SUPPORT GILSERT ASSOCIATES, INC.
EHGIHEERS 8 CONSULTANTS MK-CCU-I S(o S-382- BS(JD I SCc A 3 READING, PA. TITLE DRAWIHG HUHBER SHEET REVS
NO. PART MATERIAL ITEM REOD. O'ESCRIPTION NO. A SPECS.
+" SCV 4O PIPFX l2 ~i "LC.(REF;5
+ I I I
C~ x Q.R CHANNEL. X/I i/p "X 3" X I/z." PLATE
'I. u7 R.
SA 36 0 c.. EMQ=Z~
IO" x IO" W 3 " Pl ATC 5" X B" x I/2" PLATE, 5" X 6," X THiCK IO . UI I IMI ED I '- > +LL TIO."I: AS NQI'Elg
~ ig a ~ ~ ~,,a i 'nhl~Ti I
~ )
NOTE 'hLL ITEMS ,.C.EHTERED EXCEPT. AS NOTED FCI < M~WI Y ACH-97 CT YP) 4a
-)IU 0 EL,Z:7Z'"9" (aalu 5
/~/is bb NOT l gp 7 VlKLb
+
+
ll (mp) 2 (A) - 4HOLa Ib 5QZF; J.OCATE',.L",X R" SECT. B-B
.C.O TQ V.T IN .... (PA) GA CIIANnEL>ELhTlK Ines@
EL.2 7 I "o ln
( R.'EI'.>
( RR'F.) 4 O'.'o',
ia I 5'-9 t.'Q.Kv. )
SECT. A-A LOCATION PLAN AUXILIARY BUILDING FOR SIGNATURES AND REVISIONS, SEE GAI SHEET A LI EH T
'CHESTER GAS AND ELECTRIC CORPORATIO ECT NUCLEAR SAFETY RELATED A STATION (EWR-2512)
PIPE SUPPORT GILBERT ASSOCIATES, INC. ISG ENGINE E RS E COHSULTAH7 5 MK- CCU - I S6 S -382-35'(c 8 READING, PA. TITLE ORAWING NUMBER SHEET REY
D ESI GN DATA:
TYPE OF SUPPORT 8 PLATE AND SHELL REFERENCE DESIGN DRAWINGS K LINEAR I IPING Q COMPONENT STANDARD ISOMETRIC C-36( "358SHT.
CODE CLASS ILAA MAX.DESIGN TEMP.( F) ANALYSIS CODE SW - 100 0 PREDICTED PIPE MOVEMENT (INCHES) Fop-ME.R.LY SwAH. Z,2.
X-C.COG
'f OE OOO Zo obO DESIGN MECHANICAL LOADS FORCE (LBS.) MOMENT (IN.-L8S.)
Fx Fy Fr Mx My Mr NORMAL UPSET EMERGENC FAULTED RIGHT HAND CARTESIAN COO R D IN AT E 5 Y ST EM TESTING
~zf g CONSTRUCTION I+IT~ I 9 ('S,9 I iE s. ~ 9'w ~
9+TPP NOTES: (
~ ~ 9 ~
PS GENERAL-THE DESIGN, FABRICATION AND ERECTION OF THIS PIPE SUPPORT IS AND SHALL BE IN ACCORDANCE WITH SPECIFICATIONS:
.NA HA ALL WELDS SHALL BE MADE WITH ELECTRODES HAVING A MIN.TENSILE STRENGTH OF 60,000 PSI.
I NA MOVEMENTS AND FORCES ARE BASED ON NORMAL OPERATING TEMPERATURES THE ABOVE NOTES DD NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THES ITEMS WERE PURCHASED AND INSTALLED PRIOR TO 1990.
DISPOSITION R,E.hA~E E.XlST 'LM~ QPl5t. PI A'Te bACPOR BOLTS'HANNEl.h,)GR FILL E X I Sl l Qg HOLE, 451TH STOL)("TURAQ 4ROQ T.,lH ACCOBDA14C.E 041'T 8 l4E.-lZL ~ thLhtk44 El'ASE PLAH E.~ '4'iQ lE.'5 ~( CANNEL SECTlqhl&~
ASLlD SHIM, IDI AWE.e NUCLEAR SAFETY RELATED pe REV'D. PER. R6+ F (.OMNENW ALL SIGNATURES AND REVISIONS ON THIS
<<llhlASI PE5Z
~
8 'I 24 SHEET PERTAIH TO ALL SHEETS ASSOCIATED WITH THE PIPE SUPPORT INDICATED BELOW A5-EssuILI 4K<V'IJ hC.N-REV. MADE CHK 0.
<>- Ek) II i PF.R D E SC R I P T I 0 II
>5 APPR DATE
/C
-/.p ~/~l DATE CONSTRUCTION
/ CLlt=WW REUFP RELEASED FOR
~4 APPR.
RE VI SION 5 W.O. 044824-005 SCALE: NONE LIEN T MADE CHKD. PIPING ENGINEERING APPROVALS EW SEE C SR K ~
OCHESTER GAS AND ELECTRIC CORPORATIO SIGN OJKCT HA STATION (EWR-2512)
DATE 8.IO 8 SZ4 8I >8 Zi 9-23.SI QiZ4 I'5'I PIPE SUPPORT GILBERT ASSOCIATES, INC, ENGINEERS S CONSULTANTS MK-swU -l9Cc s-382-356 l9 ( A READING, PA. TITLE DRAWIHG NUMBER SHEET REV.
e NP. PART MATERIAL DESCRIPTION REQD. NO.
4 'C H'. 4O P I PE X 9 ~re," G . ( RE.P.
SPECS.
4,10+
"4 HILri K~iK. cl t l4iui~uw CoI4c,. ~.-ze L
iO" ~ LO" ~W "~TE, 6 "K5" K 3/ "EIL,VE'I
~ -W "4 QOI Z~
CHANNEL W O.'-I2." cur,yg z~i<
'.x,l'/z."xP/+" PLAT U THI(KNE.SS TO UI Q I LQ7 r + ~ P T I IMMIT"i3:" l'IS.'>O'IQ'I: A N
".~ '0f 'i .":;~T 0{ R (,AI.'QTRIJCTIOI'I
~ ~
FORME.RLY SWAH- Z.2.
N0TE.: vi I PLLITE.MS TO BE TNP. R, CE,N TERE D UNt NOTE D 655 F. '~
L r
0 g Zi. ZS<'-c" (~~1=,b r l4" )PE 1
I I/Z ih Wl~ I'/Z, S F Cv l O+ ' -B
+B l5P; 8
I + PLC-b.,a S
F~hf'TO MOVE. SA( PA FL.E,L 2.53 -o
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CUTOOT PI CH ~HEI ~L
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1 reELn TiVE,, TO %RATION,-
EXiSt I HS Lu&
SECTI ON LOCATION PLAN QUAILI AR.V BUILDING FOR SIGNATURES AND REVISIONS, SEE GAI SHEET A LIENT QCHESTER GAS AND ELECTRIC CORPORATIO JECT NUCLEAR SAFETY RELATED NA STATION (EWR-2512)
PIPE SUPPORT GILBERT ASSOCIATES, INC.
ENGINEERS E CONSULTANTS MK-Swu-19' s-382- 858 l9t B READING, PA. TITLE DRAWING HUNBER SHEET REVS
DESIGN DATA:
TYPE OF SUPPORT (8 PLATE AND SHELL REFERENCE DESIGN DRAWINGS 5f LINEAR PIPING 0-SO L-69+
0 COMPONENT STANDARD ISOMETRIC C ~l 3B3SHT.
CODE CLASS STRUCTURAL D 4++
MAX. D E SIGN T EMP. ( F) ANALYSIS CODE SW IOOO PREDICTED PIPE MOVEMENT (INCHES) FoRMCRLY SWAH- iQ X'.oC o Y O.ooo Z 0 OC)O DESIGN MECHANICAL LOADS +Y FORCE (LBS.) MOMENT (IN.-LBS.)
Fx Fy Fx Mx My Mz NORMAL UPSET +O EMERGENC FAULTED RIGHT HAND CARTESIAN COOR DI HAT E SYST EM TESTING CONS 8 RU(:Tl()N NOTES: L!'i'l".0 ~ '."!', "".', I.) '.: A5 Il')[t. )
GENERAL-THE DESIGN, FABRICATION AND ERECTION OF THIS PIPE SUPPORT IS AND SHALL BE IN ACCORDANCE WITH SPECIFICATIONS:
RC CE. SmC. ME-IZI NA NA ALL WELDS SHALL BE MADE WITH ELECTRODES HAVING A MIN.TENSILE STRENGTH OF 60,000 PSI.
MOVEMENTS AND FORCES ARE BASED ON NORMAL OPERATING TEMPERATURES THE ABOVE NOTES DO NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THESE ITEMS WERE PURCHASED AND INSTALLED PRIOR TD 9988.
~DIEPOEITIOSA: IKlAOVA= EAlSTSNSCN eYSNKE. F'LA'TE.ASSCHOR BOAT& CHANNELS II GRDLSi PlLL EX'IaT)>4% HOI 6, Vl)TH STPUCTURA< CqPOU'T lQ ACCORDANCE 44 lTH-hhE-l2i - Xt45WWLL MEW eASE, PI AWE., Ala'<Ga ~ C,4AN4K4 SKMIO&$,
A.E4Q Swam PI KTQ NUCLEAR SAFETY RELATED EV . PE~ R4v- tlM ALL SIGNATURES AND REVISIONS I- -L kN ON THIS I'4D 0'&PCS IGNI( Q~ IQ.+ SHEET PERTAIN TO ALL SHEETS ASSOCI ATED WITH THE PIPE SUPPORT INDICATED BELOW EV', h PI PI[ S h(-.vt 4a
'/-yi,
~
S F VOl RS~ Gy. E RWCR CONSTRUCTION V
~c AK- BU) I I C.LIEN,'7 RE~KS~
REV. MADE CHKD. 0 E SC RIP 7 ION 'PPR DATE DATE RELEASED FOR APPR.
R E VISIONS W.O. 044824 005 SCALE: NONE LIENT MADE CHKD. PIPING ENGINEERING APPROVALS SW 898 C PE K
'OCHESTER GAS AND ELECTRIC CORPORATIO sIGN lOJECT DATE 6'Gal B24 8I 0-23-8 9/Z4/6'i HHA STATION (EWR-2512)
PIPE SUPPORT GILBERT ASSOCIATES, INC.
ENGINEERS B CONSULTANTS MK-SWU-l98 S-382-~SS IQG A READING, PA. TITLE DRAWING NUMBER SHEET REV.
NOo PART ITEM REOD. NO. DESCRIPTION
'LJT'ATERIAL SPECS.
I' "WglIg< KWlY ~aT ~ P.'QIaim<~Qo~c li"XlZ.' >1 "PLATE, ~r'4 "p.7
SASS
'LATE
'.F 1 A Z" x l" x'Jh" PLATE C.$ ~4"l CORNEL/ t
~H.
" 4O PIPE, '7RNCH ON ) A-l066 1 l 3" X X,'C S ro O (Suim Rl A,TP FORMERLY SWAH 1C) 71 CO.: ..;.:r:,IrI I 'y$ ,'I<<> I ~ ~ ",'jIA I ~
PQ M<1,I.,)
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I I I
FREK ro I IYZ 9a hAow E.
3 r~ I/g SAI PAg FLOOR E.L-QA gA SECTION A A
~OT~'.. SWARF I mr~ CI~~ Z.> MOTE ROTKYEQ TO FRCILI TAT 2 HILTI INSThCCTIOH. LOCATIOH P LAH AUXII IAR'II BUILD IHG FOR SIGNATURES ANO REVISIONS, SEE GAI SHEET A LI EH T 1CHESTER GAS AHD ELECTRIC CORPORATIO JECT NUCLEAR SAFETY RELATED HA STATIOH (EWR-2512)
PIPE SUPPORT
,GILBERT ASSOCIATES, IHC.
EHGIHEERS B CONSULTANTS MK-5WU- I 9B S -382 -3~6 IRK, 8 READING, PA. TITLE DRAWING NUMBER SHEET REV.
FORNgP(LY 5VVAH l@
PLATE' PI@I=
QQ~~CHIDM gE. CEroTERE.D I" <top) 2,"(~v8
>'"(reap)
SE CT ION B B ~ 0"" S T R 0 C T I O g PU % p~
. EKE: LOCATE'. I" X Z'lz" CUTQOT IN CHANNEL RELATIVE TO EPISTIN&
LUG LOC,Al I 0 f4.
SECTION C C FOR SIGHATURES AHD REVISIONS, SEE GAI SHEET A LIGHT
)CHESTER GAS AND ELECTRIC CORPORATIO NUCLEAR SAFETY RELATED INHA STATIOH (FMR-ZQIZ) PIPE SUPPORT GILBERT ASSOCIATES, IHC.
ENGINEERS d, CONSULTANTS MK-SWu- Iee, l98 C READING, PA. TITLE DRAWING NUMBER SHEET REY.
'