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] |
Text
CATEGORY 1 I gal REGULATORY INFORMATION DISTRIBUTION TEM (RIDE)
ACCESSION NBR:9707170007 DOC.DATE: 97/07/08 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G '05000244 At tH,NAME AUTHOR AFF I.'>IATION MECREf)Y,R.C. Rochester Gas & Electric Corp.
g~ce~+
RECIV.NAME RECIPIENT AFFILIATION VISS'.NG,G.
SUBJECT:
Provides addi info to assist in exam of 970318 ltr to NRC re "Reactor Coolant Pump Flywhell Insp Interval Change."
Also forwardsSection XI,rev 0 & revised Section XI,rev 1 C which contains updated RCP requirements 6 exams performed.
A DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL f SIZE:+L~/
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: ILE 1 1 1 NRR/DE/ECGB/A, 1 1 NRR/DE/EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 EXTERNAL: NOAC 1 1 NRC PDR .1 1 D
0 U
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, RooM owFN 5D-5(EXT. 415-2083) To ELIMINATE Y0UR NAME FRQM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
",TOTAL'UMBER OF COPIES REQUIRED: LTTR 13 ENCL 12
(
4ND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EASTAYENUE, ROCHESTER, N. Y Idhf9-0001 AREA CODE716 54rS-2700 ROBERT C. MECREDY Vice President July 8, 1997 Nod eor Operotions U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Reactor Coolant Pump Flywheel Inspection Interval Change Additional Information R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): Letter from Robert C. Mecredy, (RG&E), to Guy S. Vissing, (NRC), "Reactor Coolant Pump Flywheel Inspection Interval Change," dated March 18, 1997.
Dear Mr. Vissing:
The purpose of this letter is to provide additional information to assist you in the examination of the referenced transmittal.
The reactor coolant pump (RCP) flywheel inspection was not part of the previous R.E. Ginna Technical Specifications. As such, not been carried into the Improved Technical Specifications.
it has The previous Inservice Inspection (ISI) program document related to RCP flywheel inspections isSection XI Revision 0. The revised ISI program .document isSection XI Revision 1 which contains the updated RCP requirements.
Copies of these two documents are enclosed. In addition, a copy of the examinations performed during the second period of the third interval are enclosed.
Should you have any questions, please call George Wrobel at (716) 724-8070.
Very truly yours, Robert C. Mecredy Enclosures REJi470 9707f 70007 tt70708 't l, PDR ADQCK", 05000244 t e '
PDaLI llllllllllllllllllllllllllllllilllllllll
xc: Mr. Guy Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
9707170007 SECTION 11 ADDIT,IONAL Revision 0 PROGRAM Page 1 of 9
1.0 General
The purpose of this section is to provide information and clarification on additional inspection programs being performed at R. E. Ginna Nuclear Power Plant.
These inspection programs may be due in part to ASME Section XI program requirements or to other commitments made by Rochester Gas and Electric.
The following list identifies additional inspection programs being performed at R. ED Ginna Nuclear Power Plant:
- Reactor Vessel Augmented Program, Category B-A 2.0
2.1 General
2.1.1 The Steam Generator Tube Inspection Program incorporates the requirements of ASME Section XI Code, under'ategory B-Q, Item Number B16.20. The Code requires that Steam Generator tubing in U-Tube Design be volumetrically (Eddy .Current) examined to the extent and frequency governed by the plant Technical Specifications. In accordance with this Code requirement and R. E. Ginna Station Technical Specifications, eddy current examinations shall be performed. Steam Generator Tubing shall be examined their full length, at least once every five years.
SECTION t 1 ADDITIONAL Revision 0 PROGRAM- Page 2 of 9 2 ' ' The Steam Generator Tube Inspection Program also incorporates the requirements of USNRC Regulatory Guide 1.83, Revision 1, dated July, 1975, "Inservice Inspection of Pressurized Water Reactor . Steam Generator Tubes" and the recommendations of the Electric Power Research. (EPRI)- PWR Steam Generator Inspection Guidelines, X'8t885~8gpxevkPgx'8li8xCiag 2.2 Xasyectx'cek"'pxogram~
2.2.1 The program for each Xeegeet'y'en'may'C9~8 of the five-years shall include, as a minimum, .the following requirements:
A rotating random sampling of 20% of all operational tubes for their full length.
g'h'S'Surrngi~lllR~!'PO<'.'~O@iuh'e!e jg8ha'3'"'3'Fp+!he-'*',;.+OnRP'3;:O'te'd A rotating, random sample of. 20-. 'of each type of .
2.'. sleeved inlet tube for their full length, including the sleeve from the upper end through the expanded transition of the lowex end.-
All operational tubes that had a previously identified SerOPee:;::.:candu'Oei degradation of greater than 20'; through wall to the extent of previously identified degradation. However, if after two (2) consecutive inspections these tubes have not had greater than 10-. further penetration, the inspection frequency on these tubes may be extended to 40 months.
' ADDITlONAL, PROGRAM SECTlON 11 Revision 0 Page 3 of 9 2.2 ..2 Other tubes may be added .to the program each i'aspic'Ct'xoQ~@CpC3le as necessary to meet other concerns and are classified as "owner elected". "Owner Elected" examinations are not mandatory and may be performed as determined by the owner.
2.2.3 The Ginna Steam Generator Reliability Committee may change the aforementioned plan to meet outage schedules, provided that the changes meet the requirement of Regulatory Guide 1.83 and Supplement 1
- it! f!': i.::,i': ll" W,:.- 'i:;::,:,,',ll: '::!1' 'i,:,
2.3 Examination Method:
2.3.1 Eddy Current (Volumetric) Examination techniques shall be employed to perform the required examinations on Steam Generator tubes.
2.4 Precpxency of Examinations:
2.4.1 Examinations shall be performed every -$!esp'e'Cp'ee'::,';:.,",;,O'JJ',.C3!8 to the extent required and specified within 2.2, as a minimum.
2.5 Examination Evaluation:
2.5.1 Eddy Current evaluation shall be performed in accordance with('8gpdeVe'5;,'-p'Wo'ee5~8'e.
SECTlON '1 't ADDITIONAL Revision 0 PROGRAM Page4of 9 2.6 Repair, Replacement and Testing Requirements 2.6.1 -Repair criteria for steam generato'r tubes is- based on the requirements of Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes".
2.6.1.1 Steam generator tubes that have imperfections greater than 40 percent through-wall as indicated by eddy current, shall be 'repaired by plugging or sleeving..
2.6.1.2 Steam generator sleeves that have imperfections greater than 30 percent through wall as indicated by eddy current shall be repaired by plugging.
2.6.2 Repairs by welded plugs and sleeves shall be performed in accordance with 88Cti'Op<@32:.
'I
2.7 Scheduling
2.7.1 Eddy Current examination schedules of 'Steam shall be established within Supplement Generator,'ubes 1,~/@he
%%8'8~r'Vi'C8'.":."INO'C.t'ACE ~jP~NC'gX8N>~P3,"cN 2.8 Reports and Records:
2.8.1 Applicable records shall be maintained as specified within Section 1 and Se'C'tk<ML3,,'2::.
2.8.2 .Within 15 days following the completion of the evaluation of each inservice inspection of steam generator tubes, ,the number of tubes required by Paragraph 2.6.1 above to be plugged or sleeved in each steam generator shall be reported to the NRC in a Special Report.
t e
SECTION 11 ADDITIONAL Revision 0 PROGRAM Page 5 of 9 The complete results of the steam generator tube inservice inspection shall be submitted to the BRC in RRNÃk$
a Special Report within 12 months following the completion of the inspection. This Special Report shall include:
(a) Number of tubes inspected and extent to which inspected.
(b) Location and percent of wall- thickness penetration for each indication of an imperfection, and (c) Identification of tubes plugged or sleeved.
If the number of tubes in a generator falling into categories (a) or (b). below exceeds the criteria, then results of the inspection shall be considered a Reportable Event pursuant to 10 CFR 50.73. Oral notification to the NRC Staff shall 'be accomplished'ithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, but no sooner than the next normal working day after the final review of the eddy current results. A written follow up report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to preclude recurrence. Categories (a) and (b) are:
(a) More than 10 percent of the total tubes inspected are degraded (imperfections greater than 20 percent of the nominal wall thickness). However, previously degraded tubes must exhibit at least 10 percent further wall penetration to be included in this calculation.
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SECTION 11 ADDITIONAL
<< PROGRAM Revision 0 Page 6 of 9
'b)
Nore than 1 percent of the total tubes inspected are degraded (imperfections greater than the repair limit) .
3.0
3.1 General
The augmented inservice inspection program for Reactor Coolant Pump Flywheels incorporates the requirements of the USNRC Regulatory Guide 1.14, Revision 1, dated August 1975, entitled "Reactor Coolant Pump Flywheel Integrity".
3.2 Examination Requirements:
3.2 ~ 1 "Examinations shall be performed on all active Reactor Coolant Pump Flywheels and Anti-Rotation, Pawls.
3.3 Examination Method,:
3.3.1 Reactor Coolant Pump Flywheels shall be examined using Ultrasonic and Surface examination techniques.
3.3.2 Reactor Coolant Pump Anti-Rotation Pawls shall be examined using Surface examination techniques.
3 ~ 3.3 Ultrasonic and Surface examinations shall conform to and be performed in accordance with Section 1 of this program.
'C SECT1ON 11 ADDITlONAL Revision 0 PROGRAM Page 7 of 9 3.4 Frequency of Examinations:
3.4.1 Examinations shall be performed on all operating Reactor Coolant Pump Plywheel and Anti-Rotation Pawls once each period.
1 3.5 Examination Evaluation:
3.5.1 Examination evaluations shall be perf ormed in accordance with Section 1 of this program.
3.5.2 Unacceptable examinations shall be report'ed. for evaluation,and appropriate corrective action.
3.6 Repair, Replacement and Testing Requirements 3.6.1 Repairs and Replacements shall be performed in accordance with ~88Ct'ieli~g!3', as applicable.
3.7 Scheduling
3.7.1 Examination schedules shall be established within SuPPiement Z., .themezne'etS,i'Ce@znSPeetacn<<PX'Ogtem-:.:X',1:an.
3.8 Reports and Records:
3.8.1 Applicable records shall be maintained as specified in Section i: ade:;-:,: e Sticoin '2
SECTION 11 ADDITlONAL Revision 0 PROGRAM Page 8 of 9 General:
As specified within the Federal Register, 10 CFR Part 50, Vol. 57, No. 152 dated August 6, 1992, a specific augmented examination program is required for ASNE Section XI Category B-A, Shell Welds of "Pressure Retaining Welds in Reactor Vessel".
Examination Recpxirements:
Examinations shall be performed on all ASNE Section XI Category B-A, Item B1.0, Shell Welds of "Pressure Retaining Welds in Reactor Vessel" that are not required by the Code.
Examination Method.:
Ultrasonic examinations shall conform and be performed in accordance with Section 1 of this program.
Frequency of Examinations:
Examinations shall be peri ormed once during the Inspection Interval.
ExaminationEva1uation:
Examination Evaluations shall be performed in accordance with Section 1 of this program.
' w~ AD D1TIONAL PROGRAM SECT!ON 11 Revision 0 Page 9 of 9 Unacceptable examinations shall be reported for evaluation and appropriate corrective action.
Repair, Replacement and Testing Recpxirements (4. 6. 1 Repairs and Replacements shall be performed in accordance with Sect'a'o~ti;,;:1'2:, as applicable.
Scheduling:
Examination schedules shall be established within Supplement 1,::,t58FX's'eptlXC8~sXgfSy'O'CdiCXf..":.":PX'agxlaN:;,;Plan@
Reports and Records:
4!. 8 . 1 Applicable'ecords shall, be maintained's specified within Section 1 and 8'8~C54~On's"'42:,.
