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
REGULAT INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR: 8108310479 DOC. DATE i 81/08/20 NOTARIZED: NO DOCKEiT ¹ FACILC50'44 Robert AUTH',NAME'UTHOR AFFILIATION Emma't Ginna Nuclear Planti Unit ii Rochester G 05000244 ivIA IERr J ~ E ~ Rochester Gas L Electric Corps RECIP ~ NAMEI RECIPIENT AFF ILiIATION CRUTCHFIELOPD, Operating, Reactors Branch 5
SUBJECT:
-. Updates 8 supp;ls 810415 submittal re SEP Topic II isC'P.
"Potential Hazards Due to Nearby Tr ansportationi Industrial S Military Activities,"
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>~ IIIigrZ(~~ZZ I fil4/8 ZEiZIZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MA IER 'TEI.EPHONC V I CK PRES I OEIIT ARL'A CODE Tls 546-2700 August 20, 1981
- o. liUQ 28 1981~ 3 Director of Nuclear, Reactor Regulation VISI NIICLEAg REGIII ggg)
Attention: Dennis M. Crutchfield, Chief COMMJQJpg Operating Reactors Branch No. 5 U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
SEP Topic II-1.C, "Potential Hazards Due to Nearby Transportation, Industrial, and Military Activities" R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
This letter will serve to update and supplement our April 15, 1981 'submittal relative to this SEP topic. The following additional information should be added where noted:
After paragraph 5 of the "Description," the following paragraph should be added:
"The potential effect of the gas line service to the Ginna house heating boiler was discussed during the Ginna Fire Protection review. This 4-inch gas line comes into the plant underground until the east end of the screenhouse.
it penetrates the ground surface at This routing ensures separation from all other safety-related structures and systems. At this point, a metering station and a gas shutoff valve are lo'cated (the gas meter was relocated as a result of the Fire Protection review, item 3.1.13). The gas line is buried underground again after the gas meter regu-lator station, and enters the building through the basement wall under the house heating boiler area. The gas pipe is of welded steel construction up to the boiler. There is continuous ventilation of the areas that the gas line passes through within the building. The gas line service to the boiler and the boiler controls were reviewed and compared to NFPA-85, as requested in the staff's Fire Protection SER, dated February 14, 1979 (item 3.1.46). This installation was accepted by the NRC in Supplement No. 2 to the Fire Protection SER, issued on February 6, 1981. Based on the resolution of all gas line items during the Fire Protection review, it can be concluded that,no safety hazard results from the existence of the gas line on the plant site."
o~
PDR8310479 R ADOCK 810820-,h 0800024'4 )
PD~
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ROCHESTER GAS AND ELECTRIC RP. SHEET NO.
August 20, 1981 Mr. Dennis M. Crutchfield, Chief These above-referenced documents will be added as references to the" safety assessment for this SEP Topic II-l.C.
- 2. The following discussion should be added into the present first paragraph on page 4, following the phrase ". . . at least 23 miles or more from the plant "The possibility of damage to the service water intake structure was also considered. Section III-B.27 of RG&E's "Technical Supplement Accompanying Application for a Full-Term Operating License," August 1972 discusses the design of the intake system. As noted in this report, the intake system is completely submerged below the surface of the lake. A ten-foot reinforced concrete lined tunnel, driven through bedrock, extends 3100 feet northerly from the shoreline. The tunnel rises vertically and connects to a reinforced concrete inlet section. The occurrence of historical low water level will result in a depth of water of 30 feet at the inlet and with 15 feet of cover over the inlet structure. This is sufficient, to prevent damage from any boating which might pass in the vicinity of the structure.
Further, plugging of inlet water flow by a single large piece of material is prevented by the design of the in/et structure, in that water enters on a full 360'ircle.
Another design feature at Ginna to ensure continued avail-ability of essential service water is that service water intake can be directly drawn from the discharge canal, which is located on the plant site, protected from any potential lake- boating. Thus, lake navigation is not considered to be a hazard to the plant."
This referenced document will be added as a reference to the safety assessment for this SEP Topic II-1.C.
- 3. The following sentence should be added at the top of the present page 5, after the words ". . . and training space described above."
"There is also a slow-speed low altitude military training route (SR-826) which passes about 6 miles west of the plant."
An updated assessment of this SEP Topic, including all changes noted in this letter, is included as an Attachment.
Very truly yours, Attachment
Attachment:
SEP ~To ic II-l.C Potential Hazards Due To T~rans ortation, Institutional, Industrial and Militar Facilities, R.E. Ginna Nuclear Plant
~Pur ose The safety objective of this topic is to ensure that the Ginna Nuclear Plant is adequately protected and can be operated with an acceptable degree of safety with regard to potential accidents which may occur as the result of activities at nearby industrial, institutional, transportation, and military facilities. The review was conducted in accordance with the guidance of SRP's 2.2.1, 2.2.2, 2.2.3 and 3.5.1.6, as well as Regulatory Guide 1.91, Rev. 1.
There is little industrial activity in the vicinity of the Ginna plant. Wayne County, where Ginna is located, is primarily a rural area. Typical industries for Wayne County are shown in Table 2.5-1 of the FSAR, reproduced here as Table 1. The nearest concentration of industrial activity is located in the town of Webster, about 6 miles from the site, and consists primarily of light manufacturing (Xerox copiers). No industrial development is expected to occur in the vicinity of the Ginna site.
The nearest transportation routes -to the plant: are Lake Road and u
U.S. Route 104, which pass about 1700 feet and 3 1/2 miles, respectively, from the plant at their closest point of approach.
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The guidance of Regulatory Guide 1.91, Revision 1, was utilized to evaluate the consequences of postulated explosions on Lake Road. Regulatory Guide 1.91, Revision 1, has been specifically identified by the NRC's Regulatory Requirements Review Committee as needing consideration for backfit on operating reactors. The highway separation distances at Ginna exceed the minimum distance criteria given in the Regulatory Guide and, therefore, provide reasonable assurance that transportation accidents resulting in explosions of truck-size shipments of hazardous materials will not have an adverse effect on the safe operation of the plant.
It is important to note that no hazardous cargo would be expected to be transported along Lake Road. This road is used primarily for local traffic, such as that relating to the apple processing plants.
No industry using large quantities of explosives is located along
'I this route. Any large quantities of hazardous material would be shipped via U.S. Route 104 which, at 3 1/2 miles from the plant site, is sufficiently distant not to be of concern.
Highway accidents on Lake Road involving certain hazardous chem-icals could theoretically exceed toxicity limits in the plant control room assuming an optimum set of spill parameters and atmospheric dispersion conditions. However, the highway separation distances and the lack of any indication of frequent shipment of hazardous chemicals past the plant (since shipment would be along U.S. Route 104), provide reasonable assurance that the likelihood of a hazardous chemical spill affecting the operation of the plant is low. However it cannot be precisely determined what the proba-bility of a hazardous chemical accident would be, because detailed
1 i'
information on the size, type, and frequency of hazardous chemical shipments past the plant is not. available. Although it is con-sidered that the probability of a hazardous chemical transportation accident affecting plant operation is low, we believe that the possibility of such an accident should be one of the factors considered in the final evaluation of the adequacy of the control room habitability systems for the Ginna Plant. This matter will be evaluated further under NUREG-0737, item III.D.3.4, "Control Room Habitability".
The nearest railroad to the plant is the Ontario Midland railroad about 3 1/2 miles to the south. Comparing this distance with the guidance provided in Regulatory Guide 1.91, it is apparent that potential railroad accidents involving hazardous materials are not considered to be a credible risk to the safe operation of the plant.
The nearest large pipelines'to the plant are a 12" gas line located about'six,miles southwest of the plant, and a 16" gas line located about 10~ mile's so'uth of the plant. These pipelines are far enough removed to assure that pipeline accidents will not affect the safety of the nuclear plant. Figure 3 shows a portion of the residential gas lines serving homes along Lake Road, as well as the house heating boiler at the Ginna plant itself.
There are no gas or oil production fields, underground storage facilities, or refineries in the vicinity of the plant.
The potential effect of the gas line service to the Ginna house heating boiler was discussed during the Ginna Fire Protection review. This 4-inch gas line comes into the plant underground
l A 'I 3 I
I '
ak V
until it penetrates the ground surface at the east end of the screenhouse. I This routing e'nsures separation from",all, other I~
ll Jt safety-related'tructures and systems. At this point, a metering station and a gas shutoff valve are located (the gas meter was relocated as a result of the Fire Protection review, item 3.1.13).
The gas line is buried underground again after the gas meter regulator station, and enters the building through the basement wall under the house heating boiler area. The gas pipe is of welded steel construction up to the boiler. There is continuous ventilation of the areas that the gas line passes through within the building. The gas line service to the boiler and the boiler controls were reviewed and compared to NFPA-85, as requested in the staff's Fire Protection SER, dated February 14, 1979 (item 3.1.46). This installation was accepted by the NRC in Supplement No. 2 to the Fire Protection SER, issued on February 6, 1981.
Based on the resolution of all gas line items during the Fire Protection review, it can be concluded that no safety hazard results from the existence of the gas line on the plant site.
There are no large commercial harbors along the southern shore of Lake Ontario near the plant. Some freight is shipped through Rochester harbor about 20 miles to the west. Major shipping lanes in the lake are located well off-shore, at least 23 miles or more, from the plant. 7 The possibility of damage to the service water intake structure was also considered. Section III-B.27 of RG&E's "Technical Supplement Accompanying Application for a Full-Term Operating License," August 1972 discusses the design of the intake system. As noted in this report, the intake
system is completely submerged below the surface of the lake. A t
ten-foot reinforced concret'e lined tunnel,,driven, through bedrock, extends 3100 feet northerly from the shoreline. The tunnel rises vertically and connects,to a reinforced .concrete inlet section.
The occurrence of historical low water level will result in a depth of water of 30 feet at the inlet and with 15 feet, of cover over the inlet structure. This is sufficient to prevent damage from any boating which might pass in the vicinity of the structure.
Further, plugging of inlet water flow by a single large piece of material is prevented by the design of the inlet structure, in that water enters on a full 360'ircle. 13 Another design feature at Ginna to ensure continued availability of essential service water is that, service water intake can be directly drawn from the discharge canal, which is located on the plant site, protected from any potential lake boating. Thus, lake navigation is not considered to be a hazard to the plant.
The closest airport to the plant is the Williamson Flying Club Airport, a small privately-owned general aviation facility located approximately ten miles ESE. Monroe County Airport, in Rochester, New York, located about 25 miles southwest of the plant, is the nearest airport with scheduled commercial air service. Low altitude federal airways V2 and V2N pass about 10 miles south and 2 1/2 miles southwest of the plant, respectively.
An Air Force Restricted Area R-5203 is located about eight miles north of the plant site. Whenever flight activity is conducted by the Air Force within R-5203, radar surveillance is maintained by the 21st NORAD Region, the 108th Tactical Control Group, or
b k possibly the Cleveland Air Route Traffic Control Center. Pilots rely upon on-board navigational equipment to maintain their presence within the specified limits of the restricted area.
Pilots can also be advised if their, aircrafts stray beyond their limits by the radar surveillance unit covering the area at the time. The restricted area is used daily for military flight training which includes high-speed interceptor training maneuvers, operational flight checks, and air-to-air refueling. The current altitude ranges from 2,000 to 50,000 feet. above the surface. 5 A portion of the Detroit, Sectional Aeronautical Chart, reproduced as Figure 1, shows the airports, air routes, and training space described above. There is also a slow-speed low altitude military training route (SR-826) which passes about 6 miles west of the plant.
The Williamson Flying Club Airport has one paved runway. This runway, designated 10-28 and thus oriented in an almost east-west direction, is 3377 feet long and 40 feet wide. The main runway is equipped with low intensity runway lights. The airport has instrument approach capability to runway 28 from the Rochester VORTAC. Figure 2 shows the instrument flight path. There is no control tower at this airport. The airport is used for general aviation activities such as business and pleasure flying, and for agricultural spraying operations. There are currently about 5,000 operations per year at the facility, and about 30 based aircraft, including part-time based .crop dusters. The great majority of the aircraft are single-engine propeller airplanes which typically weigh on the order of 1500 to 3600 pounds. 8
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The low altitude federal airways, V2 and V2N, serve about 19 flights per day. Almost all flights use V2, with V2N being used only occassionally. At most, 10% of airline traffic would use 9
V2N. The width of these airways are eight miles.
Evaluation Based on distance from the reactor, it has been determined that truck and seaway traffic, railway transportation, and large gas and oil pipelines are not of concern to the Ginna safety-related equipment, with respect to the potential for detonation of explosives. With respect to hazardous chemical shipments and the potential effect on control room habitability, the Ginna plant will be further evaluated through NUREG-0737, item III.D.3.4.
Aircraft hazards to Ginna were reviewed against the criteria in SRP 3.5.1.6. Acceptance criterion II.2 states that, for military air space, a minimum distance of five miles is adequate for low level training routes, except those associated with unusual activities, such as practice bombing. Air Force Restricted Area R-5203 is about eight miles from at its closest boundary, and no unusual activities such as practice bombing take place. The slow-speed low altitude military training route SR-826 is about 6 miles from the plant. Therefore, this criterion is met.Section III.2 of SRP 3.5.1.6 states that the probability of an aircraft crash into the plant should be less than about 10
-7 per year.
This probability can be evaluated using the relationship:
J h
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J I"
PFA = C x N x A/w where:
inflight crash rate per mile for aircraft using
-9 airway (assumed to be 3 x 10 )
width of airway (plus twice the distance from the airway edge to the site when the site is outside the airway) in miles, N number of flights per year along the airway, and effective area of plant in square miles = 30 acres /
0.5 miles 2 For airway V2, P
FA
= (3x 10
-9 x (19 x 365)
) x-.05 = 5.1x 10
-8 20 where W = 20 is derived from an air width of 8 miles + twice the six-mile distance from the airway edge to the site.
For airway V2N (assuming 10% of the 19 flights),
P FA
= (3 x 10
-9 x (2 x 365) x
)
.05 = 1.4 x 10 -8 8
Since these values are below 1 x 10 , it is apparent that commercial air traffic over Ginna is not of concern.
Section III.3 of SRP 3.5.1.6 states that the probability of an aircraft crashing into the site should be estimated for cases where either of the following apply:
- a. An airport within five miles of the site.
t ll II
- b. An airport with projected operations greater than 500d 2 movements per year is located within ten miles of the site, or an airport within projected operations greater than 1000d 2 movements per year is located beyond ten miles from the site, where "d" is the number of miles from the site.
The only airport potentially of concern is the Williamson Flying Club Airport. This airport is about 10 miles from the site, with expected operations of 5000 per year. This is substantially 2 =
fewer than the 500d 2 = 500 (10) 50,000 movements per year which would be of concern. There is therefore no need to evaluate the probability, of an aircraft crash from this airport.
Conclusions R.E. Ginna site meets a I'he current regulatory criteria for "Potential"'Hazards
' Due to Transportation, Institutional, Industrial fl i i(
and Military Facilities", except possibly for the consideration of hazardous chemical highway transportation accidents on Lake Road. Although this latter issue is not expected to be of concern, since hazardous materials would be expected to be transported along U.S. Route 104, which is 3 1/2 miles from the site, the issue will be further considered in the evaluation of Control Room Habitability as part of, the NUREG-0737 item III.D.3.4 review.
Since the only potential deviation from current regulatory criteria is to be addressed outside of'the SEP, it is considered that SEP Topic II-1.C is complete for Ginna, and no additional evaluation will be required for this topic within the SEP.
I'I ll
'\
10 References
- 1. Rochester Gas and Electric Corporation, Robert Emmett Ginna Nuclear Power Plant Unit No. 1 Final Facility Description and Safety Analysis Report (FSAR), Sections 2.2 and 2.5.
- 2. Rochester Gas and Electric Corporation, R.E. Ginna Nuclear Power Plant Unit No. 1, Environmental Report, Volume 1, Sections 2.1 and 2.2.
- 3. Nuclear Regulatory Commission NUREG-75/087, Standard Review Plan, Sections 2.2.1, 2.2.2, 2.2.3, and 3.5.1.6, September 1975.
- 4. Code of Federal Regulations, Section. 10, Part 100 (10 CFR
- 5. Sterling Power Project Nuclear Unit No. 1 Preliminary Safety Analysis Report. Addendum,,Rochester Gas and Electric, Volume l
1, Sections 2.1 and 2.2. ',
N
- 6. U.S. Nuclear Regulatory Commission Regulatory Guide 1.91, Rev. 1, February 1978.
- 7. Conversation with Chief, U.S. Coast Guard Station, Rochester, New York, 4/8/81.
- 8. Conversation with Vern Tyrrell, manager of the Williamson Flying Club Airport, 4/7/81.
- 9. Conversation with FAA controller, Monroe County Airport, 4/ 8/ 81.
- 10. Fire Protection SER, Dennis L. Ziemann to Leon D. White, Jr.,
February 14, 1979.
- 11. Fire Protection SER, Supplement No. 2, Dennis M. Crutchfield to John E. Maier, February 6, 1981.
11
- 12. Letter, Dennis M.. Crutchfield, NRC, to John E. Maier, RG&E, SEP Topics II-3.A, II-3.B, II-3.B.1, II-3.C, dated April 10, 1981.
- 13. Rochester Gas and Electric Corporation, "Technical Supplement Accompanying Application for a Full Term Operating License,"
August 1972.
II II I J C II I II IS
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7~pi~ I FSAQ TABLE 2.5-1 TYPICAL INDUSTRIES IN WAYNE COUNTY Com an and Product Distance from Site Direction from Site National Distillers L Chemical Corp.
(Kordite Div.), Macedon Polyethclene Products '4-1/2 mi. South Duffy-llott Co., Inc. Williamson Baby Foods 8-1/2 mi. Southeast Garlock, Inc. Palmyra Mechanical Packings 15 mi. Southeast Bloomer Bros. Co. Newark.
Foldi'ng Paper Boxes '19 mi. Southeast Jackson Perkins Co. Newark Nurserymen 19 mi. Southeast Sarah Coventry, Inc. Newark Direct-nail sales of costume jewelry 19 mi. Southeast National Biscuit Co. (Dromedary Co. Div,)
Lyons, Cake mixes, dates and peels 19 mi. Southeast General Electric Co., Clyde Electronic Equipment 27-1/2 mi. Southeast Comstock Foods Inc., Red Creek Canned Foods 31 mi. East Kenmore Machine Products, Inc.
Lyons Refrigerant Products 22 mi. Southeast Olney Ec Carpenter, Inc. Wolcott Canned Foods 27-1/2 mi.
C. W. Stuart h Co. Newark Nurserymen 19 mi. Southeast Francis Leggett Co., Sodus Canned Foods 12-1/2 mi. East The Waterman Food Products Co.
Food Processing 3-4 miles South Ontario Kraut Corp.
7 Railroad Ave.
Food Processing 3-4 miles South SW Victor Preserving Co.
Food Processing 3-4 miles South Ontario Cold Storage Food Processing 3-4 miles South SW Waterman Fruit Products Co.
Food Processing 3-4 miles South SW Ontario Food Products Food Processing 3-4 miles South SW Lyndan Products Co.
Food Processing 3-4 miles South SW
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FXGURE 2 instrument Landing Path to WFC Airport WILUsN((SON-SQDUS YOR/DME RVfY 10 ~~21< IEAAI SODUS, le YORK 1 N(A 2200 No(r(
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o 110i E(Ettt 425 AVSSED ARPROACH HoMiny (tottern C(knb(ny (e(t turn to 2200 I to R4B4 20 D(AE ond 2200
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I st glt @ 00 E(ev i25 5-10 1300-1 1300-1 Vi 1300-1 6 1300-1%
875 ((F00 I 875 900.1(4 875 (t001H 875 9001%
CIRC UHG 1300.1 1300-1 % 1300-1 6 1300.2 875 9001) 875 (900 1 V 875 (900 1 12) 875 (t00.
Use Rochester, New York ott(meter settiny.
V D NA UR( Rwy 1028 Knots 80 (20 120 150 I 80 tninsSec
'Ijt'OR/DME RWY 10 SODUS, NEW YORK WILUAhkSCH+SODVS Si1
Sy w4 FIGURE 3 Small Gas Lines in the Vicinity of Ginna LAKE D/SC///PAVE C/AViYFl SCREE//
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