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
ACCESSION NBR:8809010236 DOC.DATE: 88/08/26 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH".NAME AUTHOR AFFILIATION
- Rochester Gas a Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Revs to Emergency Plan Implementing Procedures;Rev 1,SC-321, f
"Mgt of Emergency Off-Site Radiation Survey Teams." /6 /8~
DISTRIBOTION CODE: A045D COPIES RECEIVED:LTR / ENCL 2 SIZE: +/
TITLE: OR Submittal: Emergency Preparedness Plans, Implement'g Procedures, C NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 8
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR, ENCL PD1-3 PD 1 1 STAHLEiC 1 1 h
INTERNAL: AEOD/DOA/IRB 1 1 RjjyClg PB 10 1 1 NUDOCS-ABSTRACT 1 1 REG FILE 01 1' EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 S
h TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9 pC,
/ BIM'Ij/IIIIIIIIIII u7rizz!//'zszzz i I/MKiP t/ Illllllll(7I ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 TELEPHONE AREA CODE 7IE 546.2700 August 26, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No. 1 Washington, D. C. 20555
Subject:
Revisions to Emergency Plan Implementing Procedures and to the Nuclear Emergency Information Plan R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
In accordance with 10 CFR 50.54, enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures and to the Nuclear Emergency Information Plan.
Very truly yours, Robert C. Me ed General Manager Nuclear Production Enclosures xc: USNRC, Region I (2 copies)
Resident Inspector, Ginna Station 8809 ~P236 8808P6 PDR, <DOCK P5Pppgy<I PNU 1',
ROCHESTER GAS AND ELECTRIC CORPORATION 8lNNA STATlON UNlT N$
GINNA STATION COMPLETED CONTROLLED COPY NUMBER DATE:-
Qg TlME' 0 PROCEDURE OS SC-321 REV. NO. 0 MANAGEMENT OP EMERGENCY OFF-SITE RADIATION SURVEY TEAMS TECHNICAL REVIEW Y)
'O PORC REVIEW D TE g-~-zG
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PLANT SUPERI TENDENT ~ N EFFECTIVE DATE QA NON-QA CATEGORY 1 ~ 0 REVIEWED BY:
THIS PROCEDURE CONTAINS 2 PAGES I
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SC-321:1 SC-321 MANAG OF EMERGENCY OFF-SITE RADIATION SURVEY TEAMS
1.0 PURPOSE
The ob) ective of the off-site radiation survey team director is to obtain meaningful plume information in a timely manner, This procedure provides guidance for the survey team director to efficiently manage the survey teams in the collection of plume infor-mation.
2.0 REFERENCES
2.1 SC-323, Emergency Off-Site Radiation Survey Teams 2 ' SC-420, Estimating Off-Site Doses 2 ' SC-442, Monitoring Site Radiation Level by TLD
3.0 INSTRUCTIONS
I 3.1 Directing teams prior to release.
3.1.1 Direct teams to complete primary survey routes. This will allow the teams to check out equipment. and put out additional TLDs at locations as described in procedure SC-442, Table III, or other locations as desired.
3.1.2 Position teams downwind at three different distances from the plant. This might be at one, three and five miles. Have teams survey back and forth across the area where the plume would be expected occurred.
if a release
- 3. 1.3 Inform teams of the projected location of the center-line of the plume and the wind speed and direction.
3 ~ 1.4 Obtain names o f team members and obtain exposure history for the current calendar quarter.
3 ' Directing teams during a release.
3.2 ~ 1 Inform teams when release begins and their location in relation of the plume centerline. Tell what the pro)ected dose rates are at the plume centerline.
1, SC-321:2 3.2.2 Inform teams as to need for respiratory 'protection and use of KI.
3.2.3 Position teams downwind at three different distances from the plant. This might be at one, two and five miles.
3.2 ' Direct teams to do a profile of the plume after arrives. They should be directed to drive across the it plume to determine the width and the maximum reading (centerline), recording dose rates every 1/10 miles.
More profiles of the plume are made as necessary to put the plume location on the map.
3.2 ' Direct teams to take an air sample (10 minutes) at the plume centerline.
3.2.6 Maintain record of dose to survey team members.
3' ' If teams need relic f for meals, etc., relieve one team at a time on a rotating basis.
3.2 ' Teams on standby should be located in low background areas.
GINNA STATION UNIT ROCHESTER GAS AND ELECTRIC CORPORATIO ¹'OMPLETED GINNA STATION DATa:-
CONTROLLED COPY NUMBER TIME:-
PROCEDURE NO. SC-410 REV. NO. 26 INSPECTION OF EMERGENCY E UIPMENT TECHNIC L VI W PORC REVIEW DATE PLANT PERINTENDENT EFFECTIVE DATE QA NON-QA CATEGORY 1.0 REVIEWED BY:
THXS PROCEDURE CONTAINS ~5 PAGES
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SC-410'1 80-410 INSPECTION OP EMERGENCY E UIPMENT 1.0 %ROOSE:
The equipment required by the emergency plan and the means .of assuring procedure.
it is available is outlined in this Inspection will be made monthly as required by Technical Specifications and after each drill or use by the Health Physics Section.
2.0 F 1 Nuclear Emergency Response Plan 212 Tech. Specs, Table 4.1-1 3 ' INSTRUCTIONS:
3.1 Inspect each location using attached appendices.
Indicate number of items present in blank space on appendix.
3.1 ~ 1 Emergency Survey Center - Appendix A 3.1 ~ 2 Control Room - Appendix B 3.1 3 Health Physics Office, Auxiliary Building, Operational Support Center, Butler Building Warehouse - Appendix C
~
3.1 ~ 4 Technical Support Center - Appendix D 3.1 ~ 5 Monthly Inspection Log,- Appendix E 3 ' If any discrepancies are found make note on the Monthly Inspection Log (Appendix E). If there are no discre-pancies, enter NONE on Log Sheet.
3.2.1 Discrepancies are to be corrected (or a trouble card submitted) as soon as possible and so noted on the log sheet and filed per A-1701.
3.3 Notify Control Room and Dave Burke (71-8022) prior to initiating Survey Center and TSC Communication checks.
3 ' Send a copy of. completed Appendix <<E<< Emergency Equipment Monthly Inspection Log to Dave Burke at 49 East Ave., 5th floor.
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SC-410:2 APPENDIX <A<
EMERGENCY E UIPMENT IN SURVEY CENTER Assignment tag board all tags in place 2 ~ Survey team maps - Red, Green, Orange, Blue, Yellow 15 3 Survey team boxes - Red, Green, Orange, Blue,
~
Yellow, White - If seal is unbroken assume equipment is intact. Inventory boxes and change batteries in January and July.
NOTE: Each January update Source Check Data Card 4 ~ Low range survey instruments, RM-14 with HP-190 probe battery check. Source check per HP-7.31, and log on Attachment III.
5 ~ Mid range survey instruments RO2 (1 mR/hr to 5 R/hr) battery check, source check per HP-7.31, and check calibration date. Log on Attachment, I HP-7.31 '
~ High level dose rate meters - battery check, calibration check, source check per HP-7.31.
Xetex 305 series instruments (0.1 mR/hr to 99.9 R/hr) Xetex 302 series instruments may be substituted.
(24) spare AA batteries for replacement. Log on Attachment I HP-7.31. 24 7 ~ Extendable high level survey meter - battery check, source check, calibration check.
Xetex 302 series instruments (0.01 R/hr to 999 R/hr) or equivalent. Log on Attachment I HP-7.31.
8 ~ BC-4 sealer or equivalent, source check, efficiency calibration annually.
9 ~ Radiation monitor RM-3C or equivalent, with HP-260 probe or equivalent, source check, calibration check.
10 'rea radiation monitor, stationary change chart paper, operational check. Mark date on chart and submit to Central Records.
Dosimeter charger battery charger.
~ line operated.
t)'J ai<
SC-410:3 APPENDIX <A< (con't)
- 12. Dosimeter (High Range) - check calibration 0-5R 0-10R
- 13. Dosimeter (0-500mr) - check calibration 12 Dosimeter (0-1500mr) - check calibration 75
- 14. Thermal luminescent dosimeters (TLD) 100
- 15. Packages of (6) environmental TLD badges (off-site only)
- 16. Battery operated,
- calibration check.low volume air samplers Run air sampler several minutes to check operation.
- 17. Battery charger - operation check, disconnect
- 18. RADECO H 809 B2 air sampler - run 90 minutes.
Check that AG ZEO cartridge is in place.
Replace particulate filter at end of run.
- 19. RADECO H 809 C aix sampler run 1 minute
- 20. Filters for air samplers particulate 100
- 21. Filters for air samplers - silver zeolite 50
- 22. Envelopes for air samples - particulate 100
- 23. Envelopes for air samples - iodine 100
- 24. Envelopes for smear papers 100
- 25. Smear papers 1000
- 26. Decontamination kit (NMC - 3 piece)
NOTE PRECEDE ALL COMMUNICATION HZTH "THIS IS A TEST"
- 27. Radios, Handi-Talkie - radio check with security. Check that charge status lights are illuminated these are part of circuitry. 5
- 28. Radios, Porta-mobile ZZ - radio check with Security
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SC-410:4 APPENDIX <<A<< (con't)
- 29. Magnetic car mount antenna
- 30. Radio, stationary - radio check with security
- 31. Full face respirator inspect mask, mark bag with inspection date and initials. 22
- 32. Charcoal Respirator Filters - check expiration date 22
- 33. Voice emitters for respirators operational check 13
- 34. Contaminated clothing & waste containers) 55 gal drum
- 35. Anti - contamination clothing, sets
- 36. Step off pads 10
- 37. Masking tape rolls (replace January) 1 box
- 38. Plastic Bags, poultry 1 box
- 39. Plastic bags, clean, large 20
- 40. Radioactive material bags, yellow, large 1 roll 41.= Radiation rope 1 roll 42 hazard signs with inserts, 10 each.
'adiation (high radiation area)(radiation area)
(surface contamination area) {radioactive
'3 material) 10 Thyroid block tablets, bottles - check
'4 expiration date Pens and pencils 10
- 45. Batteries, D size 10
- 46. Batteries, 9V 10
- 47. Extension cord
- 48. NMC CAM Check flow CAM test (60 ), & check switch positions.
A 1
4
5 50
'C-4104 NOTE:
- 49. Intercom "A" Control PRECEDE Room.
have them plug survey center.
NRC Red "This is APPENDIX <A<
in Intercom telephone a Ginna
- lift A and (con't)
ALL COMMUNICATION CHECKS WITH "THIS IS A TEST" communication check with Call Control Room on GAI contact page, receiver, tell party Station Survey Center
'1 Communications Check."
York State Red telephone - Push button, lift New receiver, wait 10 seconds, state "This is Ginna Station Emergency Survey Center Communications Check, this is a test.>>
Then say "All Stations Standby for Roll Call"p
'2 then ask one at a time if New York State, Monroe County, Wayne County and the Control Room are, listening.
Telephone Books - Rochester 1, Wayne County 1
'3.
Wayne County (946-5663}
- 54. Monroe County (9-716-473-0710) 55, New York State (9-518-457-2200}
or (9-518-457-6&1)
- 56. National Weather Service, Rochester (9-716-328-7633)
- 57. National Weather Service, Buffalo (9-716-632-2223)
- 58. From Health Physics Network phone - call Control Room at 524-4984 and request they call you back at 524-0040
- 59. From 524-6711 call Control Room at 524-4984 and TSC at 524-4973 60 From extension 331 call TSC at 474
'1.
From extension 207 call TSC at 507 62 Scissors Disposable shaving razors
0
- 64. Shaving cream Initials Date
pl, SC-410:7 APPENDIX <A" (con't)
EMERGENCY E UIPMENT PER SURVEY BOX If box is sealed inventory not required. Boxes shall be opened in January and July for battery change and inventory.
- 1. Coveralls, disposable
- 2. Hoods, disposable
- 3. Gloves, pair
- 4. Booties, pair
- 5. Hats, Surgeon
- 6. Hoods, Rain
- 7. Coats, Rain
- 8. Boots, Rain, pair
- 9. Flashlight with Batteries
- 10. Plastic Bags
- 11. Masking Tape, rolls (replace January)
- 12. Pencils
- 13. Pencil Sharpener
- 14. Tablet, writing
- 15. Survey Route Maps
- 16. Air Sampler Filters - Particulate
- 17. Air Sampler Filters Silver Zeolite GY-130
- 18. Air Sample Envelopes (Iodine) 10
- 19. Air Sample Envelopes (Environmental) 10
- 20. Clipboard
- 21. Appropriate procedure for team (Remove survey route instructions in Appendix III that do not apply to that survey team)
I 1
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SC-410: 8 APPENDIX "A>> (con't)
- 22. Procedure SC-452, Sampling Snow, Grass, Soil and Vegetation.
- 23. Thyroid Block Tablets (bottle)
- 24. Suits, cold weather (earhart) (on-site team only)
- 25. Equipment Belts with Bags (on-site team only)
First Aid Room key (onsite team only) 1 26,
- 27. Backpacks - 2 (on-site teams only)
- 28. Respirator hip pouches (on-site only)
- 29. Quarters for Telephones (Off-site team only) 10
- 30. Hammer and 10 nails (off-site only)
- 31. HP-190 window clamp (off-site'teams only)
- 32. Garden Trowel
- 33. Tags with wire tie 10
- 34. Ruler, Scale inches
- 35. Scissors
- 36. Packet of screwdrivers Initials Date
I.
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SC-410:9 APPENDIX <B" EMERGENCY E UIPMENT IN CONTROL ROOM
- 1. Scott Air Pack (SCBA) - monthly inspection
- 2. Dosimeters 0-5R or 0-10R - check calibration 10
- 3. Dosimeters 0-500 mRem - check calibration 15
- 4. Dosimeter charger with battery - operability check
- 5. High range dose rate meter - battery check, source check per HP-7.31 and calibration check (RO2A)
- 6. Plant radiation survey maps (sets)
- 7. Smear papers 100
- 8. Envelopes for smear papers 10
- 9. Thyroid block tablets (bottle) check expiration date 10
- 10. Air sampler, low volume - operability check, calibration check
- 11. Air sampler filters particulate
- 12. Air sampler filters - silver zeolite
- 13. Radiation monitor RM-14 or equivalent with HP-190 probe, battery check, source check, calibration check
- 14. Masking tape, roll (replace January)
- 15. Anti-contamination clothing (sets)
- 16. Continuous Air Monitor Eberline AMS-3 check operation of unit and pump. Check calibration' due annually.
- 17. Head set, control box and minimum 15 feet of cord (for continuous communication with TSC) 1
- 18. AA Batteries Initial Date
4 SC-410'10 APPENDIX "C" EMERGENCY E UIPMENT OPERATIONAL SUPPORT CENTER
- 1. Full face respirators - inspect mask and then seal in a bag with inspection date and initials 6
- 2. Respirator charcoal filters - expiration date
- 3. Anti-contamination clothing (sets)
- 4. Flood lights, portable - operational check
- 5. Thyroid block tablets (bottles) - check expiration date 15
- 6. Dosimeters 0-500 mRem - check calibration 20
- 7. Dosimeters 0-10R - check calibration 10
- 8. Dosimeter charger with battery - operational check
- 9. Daily exposure record sheets
- 10. Pens ll. Rolls masking tape (replace January)
- 12. Battery operated low volume air samplers
- calibration check. Run air sampler several minutes to check operation. 4
'13. Filters for air samplers - particulate 50
- 14. Filters for air samplers - silver zeolite 10
- 15. Envelopes for air samples - iodine 50
- 16. Envelopes for air samples particulate 50
- 17. Clipboards with pens 4 INTERMEDIATE BUILDING
,1. Scott 'air pack (SCBA) - monthly inspection
i P
SC-410: 11 APPENDIX "C" (con't)
HEALTH PHYSICS OFFICE
- 1. Scott, air pack (SCBA) - monthly inspection
- 2. High range dosimeter - calibration check 20 3; Anti-contamination clothing (sets) 20
- 4. High range dose rate meter - battery check, source check per HP-7.31 and check calibration (RO2A, Radector III, Xetec 305 series or Eberline Teletector) 5 BUTLER BUILDING WAREHOUSE
- l. As per SC-3.16.15 and SC>>3.16.15.1, the moisture detector (located in the rear of the breathing air compressor in-line with the filter cartridges) is normally a light blue color. If color is found to be pink, DO NOT OPERATE THE COMPRESSOR. Turn in a Trouble Card and notify the Health Physicist responsible for respiratory protection. 1
- 2. For the three - 300 cubic foot breathing air bottles as part of the cascade system, at least one should have a pressure of at least 2200 psi. If none of the three have this minimum pressure reading, turn in Trouble Card and notify Health Physicist responsible for respiratory protection. 1 Initials Date
e I
SC-410:12 APPZNDI <<D>>
EMERGENCY E UIP&"NT IN TECHNICAL SUPPORT C
- 1. Radiation monitor RM-14 or equivalent with HP-190 probe battery check, source check, check calibration
- 2. Area radiation monitor - battery check, source check, check calibration
- 3. Full face respirator - inspect mask mark bag with inspection date and initials 10
- 4. Respirator charcoal filter check expiration date 10
- 5. Thyroid block tablets (bottles) check expiration date 25
- 6. Dosimeter, 500mr - check calibration 40
- 7. Dosimeter, high range - check calibration 20
- 8. Dosimeter charger with battery - operability check
- 9. RADECO H-809 B2 air sampler - run 120 minutes
- 10. Air sample filters - particulate ll. Air sample filters silver zeolite
- 12. Anti-contamination clothing (sets)
- 13. Step Off Pads 10
- 14. Daily exposure records sheets
- 15. Radioactive materials bags (yellow)
- 16. Masking tape, rolls (replace January)
- 17. Smear papers 100
- 18. Envelopes for smears 10
- 19. Envelopes for particulate air sample 10
- 20. Envelopes for iodine air samples 10
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SC-410: 13 APPENDIX <D< (con't)
- 21. Pens and pencils 5 ea.
NOTE: PRECEDE ALL COMMUNICATION CHECKS WITH n THIS IS A TESTir
- 22. Radio, Portable - radio check with security
- 23. Radio, Stationary - radio check with security book entry 1
- 24. NRC Red "This is telephone a Ginna
- lift receiver, tell party Station TSC Communication 4.
Check." Request the return call to Ginna Station 1 25 Answer NRC Red telephone on call back to
'6 verify check York State Red Telephone - push button,
~
lift New receiver, wait 10 seconds, ask if New York State, Wayne County, Monroe County, Control are listening'P Tell them "This is Ginna Station TSC Communication Check." 1
- 27. EOF Direct line (63PL5187) Telephone
- 28. From Health Physic Network phone - call Control Room at 524-4984 and request they call you back at 524-0040
- 29. Battery operated, low volume air sampler check calibration run for several minutes to check operation.
- 30. NMC CAM-check flow, CAM test (60 ), and check switch positions.
- 31. Head set, control box, and minimum 15 feet of'.cord (for continuous communication with Control Room)
'2. AA Batteries
- 33. Extension Cords Initials Date
)ef SC-410: 14 APPENDIX "E" GENCY E UIPMENT MONTHLY INSPECTION LOG DISCREPANCIES NOTED DISCREPANCIES CORRECTED Surve Center Date Xnitials Date Xnitials Control Room Date Znitiaas Date initials HP Office Date Initials Date Initials Auxilia B d Date Initials Date Initials
SC-410'5 APPENDIX "E" (con't)
Butler .Bldg.
Warehouse Date Initials Data Initials Technical Su ort Center Date Initials Date Znitials Operational Su ort Center Date Initials Date Znitials REVIEWED BX:
One copy af the completed Appendix "E" Emergency Equipment Monthly Inspection Log provided to Dave Burke (49/5)
Copy sent