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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:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20058A1421990-09-20020 September 1990 Forwards Application for Withholding Proprietary Info from Public Disclosure,Per 10CFR2.790(b)(4) ML17262A2061990-09-0505 September 1990 Forwards Proprietary Presentation Overheads for Facility Feedwater Control Sys.Encl Withheld ML17309A4001987-12-0303 December 1987 Requests Proprietary Status for LOFTTR2 Analysis of Potential Radiological Consequences Following Steam Generator Tube Rupture at Re Ginna Nuclear Power Plant, Per 10CFR2.790.Affidavit Encl ML20137J4101985-07-12012 July 1985 Sanitized Version of EP Rahe Confirming 850711 Telcon Re Former Employee Allegations.Westinghouse Intends to Cooperate Fully.Internal Review in Progress.Preliminary Review Revealed No Actual Safety Deficiencies ML17254A8811984-07-20020 July 1984 Requests Withholding of Proprietary Revised DNBR Licensing Basis for Steam Break Analysis at Reduced Pressure.Encl Withheld (Ref 10CFR2.790) ML17255A7741984-04-10010 April 1984 Submits Application to Withhold Proprietary Info in Cook Apr 1984 Ltr to Denton (Ref 10CFR 2.790).Affidavit Encl ML17255A7091984-03-16016 March 1984 Application for Withholding Proprietary Responses to Questions Re Applications for Amend to Tech Specs Dtd Dec 1983 ML19320C9681980-07-0909 July 1980 Responds to 800703 Inquiry Re Process Whereby Draft Evaluation Performed by Franklin Inst & Containing Possibly Proprietary Info Could Be Released to Rochester Gas & Electric.Westinghouse Has Proprietary Agreement W/Util ML17249A7171980-02-0505 February 1980 Advises of Authorization to Use Previously Furnished Affidavits for Current Reload Review Re Cycle 10. Same Proprietary Matl Being Used ML17244A6941979-03-13013 March 1979 Forwards Response to IE Bulletins 78-12 & 78-12A, Records Investigation Rept Re Off-Chemistry Welds in Matl Surveillance Specimens & Responses to Bulletin 78-12&78-12A Suppl. Concludes Crystal River 3 Isolated Event 1990-09-05
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Ntestinghouse Electric Corporation YYater Reactor Divisions iix&r Technology Oivision Box 355 PitlsburghPennsylvania 15230 February 5, 1980 NS-RAW-005 Mr.Dennis Ziemann, Chief Operating Reactor Branch S2 Division of Operating Reactors Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, 0.C.20555
SUBJECT:
Docket No.50-244, R.E.Ginna Nuclear Power Plant REF: Rochester Gas and Electric Company Application for Withholding, White to Ziemann, February 1980
Dear Hr.Ziemann:
The proprietary material for which withholding is being requested by Rochester Gas and Electric Company (RGE)is of the same technical type as that proprietary material previously submitted in connection with an NRC.Staff reload review.The previous application for withholding, AH-76-31, was accompanied by a non-proprietary affidavit signed by the owner of the proprietary information, Westinghouse
'Electric Corporation.
The subject.proprietary material is being submitted in support of the reload review msociated with RGE's R.E.Ginna Nuclear Power Plant, Cycle 10.On March 2, 1977, Westinghouse submitted a proprietary affidavit to supple-ment the non-proprietary affidavit accompanying application for withholding AW-76-31.Because the reload review material associated with Cycle 10 is of the same technical type as that associated with WCAP-9272, the proprietary affidavit submitted to supplement the previous justification is equally applicable to this material.Accordingly, this letter authorizes the utilization of the previously fur-nished affidavits in support of the reload review associated with RGE'.s R.E.Ginna Nuclear Power Plant, Cycle 10.
~P;Mr.D.Ziemann 0 Pw February 5, 1980 NS-RAW-005 Correspondence with respect to the proprietary aspects of the app1ica-tion for withho1ding or the Westinghouse affidavits shou1d reference CAW-80-08, and should be addressed to the under signed.Very'tru1y yours,~>&6M.a.KJ Robert A.Hiesemann, Manager Regulatory E Legislative Affairs/bek.cc: J.A.Cooke, Esq.(NRC)L.D.White (RGE)
Attachment B Response to Question 6 on Mixed Oxide Fuel (Proprietary)
~.
~g4 1 WESTINGHOUSE PROPRIETARY CLASS 2 6.The staff SER on Mixed Oxide Fuel states that use of U02 densification models for HOX should be verified.(l)
Since it appears that this assumption was used for the VOX fuel for Ginna, please verify this assumption.
Does the predicted amount of densification satisfy Reg.Guide 1.126.The current Westinghouse U02 fuel densification model was used to predict the densification performance of the tIOx fuels fabricated for Ginna.This empirical model, which was derived using only U02 performance data, uses fuel sintering temperature and sintered density to predict the extent of densification.-
The application of the model to lIO fuel is justified on X two bases;the similarity in procedure used in fabrication of NO fuel to X UO>procedures and the ability to conservatively predict the performance of previously irradiated t~i0 fuels.X While, studying the densification of pure U02, the relative dimensional ,stability of fuel was found to be strongly dependent on the pelletizing.process employed and the values of key processing parameters.
The processes used in pellet fabrication for Ginna are essentially identical v(ith those used.in preparing MO fuel previously irradiated by Westinghouse whose X performance is conservatively predicted by the U02 model.Further, the pelletizing processes used for preparing the Ginna Il0 fuel is very similar X to that used by Westinghouse to produce U02 fuel.The limiting processing
parameters, sintering temperature and final pellet density, were controlled to a range which produces U02 fuel with predicted performance within design requirements.
The Westinghouse experience with IIO densification performance during irradiation has been reported and compared wi th model predictions in WCAP-8349-P.
Theoretically, MO densification would be expected to X proceed at a lower rate than in UO since pore removal is directly related to local fission events.Densification or pore removal is a bu1k process and in U02 fuel the fission events are fairly uniformly distributed in the material and the product densifies uniformly.
.However, in MOthe fission events are concentrated in or very near to Pu02 particles which are free to densify independently of the U02 matrix.The low enrichment U02 matrix experiences a lower frequency oT fission events than normal enriched U02 fuel at similar burnup and should show a lower amount of densification.
The Westinghouse urSTINGHOUSE PROPRIETARY CLASS 2'2 experience with densification of MO fuel operated in a corrmercial power X reactor is compared with predicted values in Figure 1 which is taken'from MCAP-8349-P.
The Figure also contains data for the performance of a VO2 fuel with similar fabrication characteristics for direct comparison.
Figure 1 contains data for both mechanically mixed and"mastermixed" fuel.Mastermixed fuel is prepared by co-precipitating V02 and'Pu02 then mixing the Co-precipitated material with U02.The U02 model is a best estimate model and hence there should be'as many points with densification under predicted as overpredicted.
This is obviously not the case for either the U02 or MO fuel with the densification' being generally overpredicted.
Significantly, the prediction of the model was noticeably more conservative for the MO fuel than for the U02 with X similar processing history.As shown in Figure 1, the prediction for master mixed MO was less conservative than for'm chanically mixed MO.This is as X X~expected and further illustrates the lower densification expected from fuel'with inhomogenously distributed fission events.The performance of an MO fuel of higher Pu02 content which was operated in X the Saxton test reactor was also reported in MCAP-8349-P
.'his fuel, which.operated at higher temperatures than commercial power reactors,'as also found to densify less than predicted by the model.The predictive capability of the U02 model was further tested by evaluating the performance of the MO fuel in the EPRI MO.densification program.'hese X X fuels were prepared by a wide variation in processing variables and hence represent a range of conditions greater than was present in data on which the model was based.The performance of the EPRI fuels as reported in EPRI HP-637 are compared with model predictions in Figure 2.The data in Figure 2 indicate the model is essentially conservative for all fuels shown, even those unstable fuels prepared by procedures dissimilar to those for fuel on whose performance the model is based.For the stable fuels, those which densified<2 volume percent, the model is highly conservative in that it greatly overpredicts the densification.
The Ginna MO fuel is projected to behave stably;all currently manufactured Westinghouse U02 fuels are also projected to show'stable behavior.
)YESTlNG'HOUSE PRPPRIU~QY gQSS P sReg.Guide 1.126 does not indicate a maximum amount of densification allowable but, rather defines the amount of densification that must be assumed based on a'thermal resintering test.Design must account for the amount of densification assumed from the resinter test.Thermal resinter data is not available for the Ginna t10 fuel so an alternate X method must be chosen to predict the densification performance; the'ethod used was the Westinghouse U02 model.The accuracy of this model can be compared to the predictions from the thermal resinter model in Reg.Guide 1.126.The basis for establishing the relative abilities of the two models to predict performance was established by use of the EPRI data.The.predicted performance using the thermal resintering model is compared with actual performance in Figure 3.Examination of data in Figure 3 indicates the resinter model significantly overpredicts the amount of densification, especially in the.region of stable fuels (<2-v6lume percent densification) where the overprediction is as much as 2.5 percent.Comparison of Figures 2'C and 3 indicates the relative predictive abilities'of the two models.The comparison shows the two models are very similar, both models being generally conservative.
The degree of conservatism is found to be greater in the region of stable fuels.Similar numbers of data points are slightly under-predicted by the two models, however, the Westinghouse model is both more consistent and more conservative in the less than 2 percent densification
'ange which is representative of the Ginna HO fuel.X The data presented demonstrate that the Westinghouse U02 fuel, densification model yields predictions similar to'nd more reliably conservative for NO X fuel than the resinter model in Reg.Guide 1.126.'
STIIIGHOUSE PROPRIETARY CLASS I I 8198-I9).b,c)~E'1.0 O I C3 LEG EHO'HIXEO U02-3j, PuO~HASTERAIXEO UO2<<3$Pu02 Q UO>.0.0 0.0 , 0.5'.0 MEASURED STACK LEHGTH DECREASE, nL/L OR 1/3 Ap/p (PRESENT)Figure 1.Comparison oF Densification Data for UO-3%PuO with UO Both Fabricated under Similar Conditions to a Density of Approximately 91%T.D.
)VESTIWGHOUSE PROPRIETARY CI.aSS 2 Figure 2.Westinghouse U02 Model Prediction of Densification of EPRI MO Fuels X Qzz 0>>Qi>Q lg Q.Q>>Qp, QQ<<o EU 1 0 Qiz@<a O~'g Q I I pg rsQ<<~i;Q3<<7 (Dll Qa Q<<Qv Q MO Mechanically Mixed S MOMaster Mixed Q U02 Data Numbers indicate EPRI'fuel types.0 2 3 Actual Change in Density, 5
WESTINGHOUSE PROPRIETARY CUSS 2 Figure 3.Reg.Guide Prediction of EPRI MO Data X l9)9 Q I Qf w GQ cJ 3 2.CL Ol~l3 O f8~gg gg 0>~OI~gy Ol 8'bs\l7 (7 (p tg IX lk Q 0 Ik O MO Mechanically Mixed X I MOx Master t1ixed e U02 Data Numbers indicate EPRI fuel types.~1"0 2'Actual Change in Density