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: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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Text
Westinghouse Power Systems Nuclear Technology Electric Corporation Systems Oivision Box 355 Pmsburgh Pennsyivama i 5230 0355 December 3, 1987 CAN-87-123 D.. Thomas Murley, Director ..
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
LOFTTR2 Analysis of Potential Radiological Conse uences Followin a Steam Generator Tube Rupture at the .R. E. Ginna Nuclear Power Plant
Dear Q . Murley:
The proprietary information for which withholding is being requested in the enclosed letter by Rochester Gas and Electric Corporation is further identified in an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10CFR Section 2.790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same technical type as that proprietar y material previously submitted with Affidavit AW-76-31.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by Rochester Gas and Electric Corporation.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-87-123, and should be addressed to the undersigned.
Very tz'uly yours, r
'-i '.".T."~t.~~ C'r(L(/l A. Wiesemann, Manager k:'obert Regulatory 5 Legislative Affairs Enclosure(s) cc: E. C. Shomaker, Esq.
Office of the General Council, NRC iipp.
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% I
PROPRIETARY INFORMATION NOTICE TRANSMITTED HEREWITH ARE PROPRIETARY AND/OR NON-PROPRIETARY VERSIONS OF DOCUMENTS FURNISHED TO IHE NRC IN CONNECTION WITH REQUESTS FOR GENERIC AND/OR PLANT SPECIFIC REVIEW AND APPROVAL.
l ZN ORDER TO CONFORM TO THE REQUIREMENTS OF 10CFR2.790 OF THE COMMISSION'S REGULATIONS CONCERNING THE PROTECTION OF PROPRIETARY INFORMATION SO SUBMITTED TO &E NRC, THE INFORMATION WHICH IS PROPRIETARY IN THE PROPRIETARY VERSIONS IS CONTAINED WITHIN BRACKETS AND WHERE THE PROPRIETARY INFOiMTION HAS BEEN DELETED IN THE NON-PROPRIETARY VERSIONS CNLY THE BRACKETS REMAIN, THE INFORMATION THAT WAS CONTAINED WITHIN THE BRACKETS IN %E PROPRIETARY VERSIONS HAVING BEEN DELETED. 'IBE JUSTIFICATION FOR CLAIMING THE INFORMATION SO DESIGNATED AS PROPRIETARY IS INDICATED IN BAH VERSZONS BY MEANS OF LOWER CASE LITERS (a) THROUGH (g) CONTAINED WITHIN PARENTHESES LOCATED AS A SUPERSCRIPT IMMEDIATELY FOLL(MING THE BRACKETS ENG.OSING EACH ITEM OF INFORMATION BEING IDENTIFZED AS PROPRIETARY OR IN &E MARGIN OPPOSZTE SUCH INFORMATION- THESE LOWER CASE LETTERS REFER TO THE TYPES OF INFORMATION WESTINGHOUSE CUSTOMARILY HOLDS IN CONFIDENCE IDENTIFIED IN SECTIONS (4)(ii)(a) throve (4) (ii)(g) OF THE AFFIDAVIT ACCOMPANYING THIS TRANSMITTAL PURSUANT TO 10CFR2.790(b)(l) ~
N-76-31 AFFIDAVIT CNHONMEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before ee, the undersigned authority, personally appeared Robert A. Miesemann, who, being by Ie duly sworn according to law, de-poses and says that he is authorized to execute this Affidavit on behalf of Mestinghouse Electric Corporation ("Mestinghouse") and that the aver-aents of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
Robert A. Miesemann. ihnager Licensing Programs Sworn to and subscribed befo this -w day of 1976.
Notary ic 4 nch> LllU>>fl sr aeMCsio>> amRaS era.H.'Oa
AM-76-31 (1) I am Manager, Licensing Programs, in the Pressurized Mater Reactor Systems Division, of westinghouse Electric Corporation and as such.
I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-c1osure in connection with nuclear power plant licensing or rule-aaking proceedings~ and am authorized to apply for its withholding on behalf of the.. westinghouse Water Reactor Divisions.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Caamission's regulations and in con-5unction with the westinghouse application for withholding ac-companying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems $ n designating $ nformatign as a trade secret, privileged or as confidential coarnercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Comnission's regulations, the following $ s furnished for consideration by the Commission in determining whether the in-formation sought to be withheld from public disclosure should be ertthheld.
(i) The information sought to be withheld from public disclosure
$s owned and has been held in confidence by Mestinghouse.
($ $ ) The information $s of a type customarily held $ n conf)dence by Mcstfnghouse and not customarily disclosed to the public.
Mestinghouse has a rational basis for determining the types of -4nformat<on customarily held $ n confidence by $ t and, $ n that connect)on, utf lazes a system to determine when and whether to ho% certain types of $ nfonnat$ on $ n confidence.
The applkcatkon of that system and thc substance of that system constitutes Mcst<nghouse policy and prov)des the rational basis requ)red.
Under that system, Information $ s held $ n conf)dence 1f $ t falls $ n one or aore of several types, the release of which adght result $ n the loss of an ex$ st$ ng or p'otential com-pet$ tfve advantage, as follows:
(a) The $ nformat$ on reveals the dlstkngufshfng aspects of a process (or component, structure, tool, method, etc.)
where prevent<on of its use by any of Mcst)nghouse's.
competitors Kthout 1lcense from Mcstfnghouse consti-tutes a competitive economic advantage over other companies.
(b) It consists of supporting data. )ncludfng test data, relative to a process (or component. structure. tool, aethod. etc.). the appl<catkon of which data secures a competitive economic advantage. e.g., by opt$ m3zat$ on or improved aarkctab)1)ty.
N-76-31 (c) Its use by a competitor would reduce his expenditure of resources or improve h$ s competitive pos$ t$ on 4n the design, aanufacture, shipment, fnstallatkon, assurance of qual)ty, or lkcenskng a skmflar product.
(d) It reveals cost or price Information, production cap-ac$ t$ ~. budget levels, or cewercfal strategies of Qestfnghohse, its customers or suppliers.
(e) It reveals aspects of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential corwerckal value to westinghouse.
(f) It contains patentable Ideas, for which patent pro-tect)on aay be desirable.
(g) It $s not the property of Westinghouse, but aust be treated as proprietary by Westinghouse according to agreements Rth the owner.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Mestfnghouse gfves Mestknghouse a competitive advantage over its com-petitors. It $ s. therefore, Hthheld from d)sclosure to protect the Mestknghouse compet$ t$ ve pos$ t$ on.
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k4 Ap~
(b) it $s information which $ s aarketable $n aaron ways.
The extent to which such $ nformat$ on $s available to competitors diminishes the ifest$ nghouse ability to sell products and services Involving the use of the 4nfonnat$ on.
(c) Use by os competitor would put Mestfnghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a part)cular competitive advantage $ s potentially as valuable as the total competitive advantage. if competitors acquire components of proprfetary $ nfcr-aat$ on, any one component may be the key to the entire puzzle. thereby deprfving westinghouse of a compet<tfve advantage.
(e) Unrestr)cted disclosure would Jeopardize the position of prominence of Mestfnghouse $ n the world market.
and thereby give a market advantage to the competition
$ n those countries.
(f) The Mestfnghouse capacity to invest corporate assets Cn research and development depends upon the success
$n obtaining and aainta$ n$ ng a competitive advantage.
0-76-31 (iii) The information is being transmitted to the Coamission in confidence and. under the provisions of 10 CFR Section 2.790,
$ t is to be received in confidence by the Caanission.
(iv) The information is not available in public sources to the best of our knowledge and belief.
l (v) The proprieta~ information sought to be withheld in this submittal is that which is appropriately marked in the attach-aent to westinghouse letter No. NS-CE-1142, Eicheldinger to Kisenhut dated July 27, 1976 concerning reproductions of view-graphs used in the Mestinghouse presentation to the NRC during the aaeting on July 27. 1976 on the subject of westinghouse Reload Safety Evaluation Methodology.
This information enables Mestinghouse to:
(a) Justify the design for the reload core (b) Assist its customers to obtain licenses (c) Neet contractual requirements (d) Provide greater flexibility to customers assuring them of safe and reliable operation.
Further, this information has substantial caaaercial value as follows:
(a) Mestinghouse sells the use of the information to its customers for purposes of a>>eting HRC requircaents for licens'ing. documentation.
(b) westinghouse uses the information to perform and 5ustify analyses xhich are sold to customers.
(c) westinghouse uses the information to sell nuclear fuel, and related services to its customers.
public disclosure of this information is likely to cause sub-stantial harm to the competitive position of westinghouse Sn selling nuclear fuel and related services.
westinghouse retains a marketing advantage by virtue of the knowledge. experience and competence it has gained through long involvement and considerable investment in all aspects of the nuclear power generation industry. In particular Westinghouse has developed a unique understanding of the factors and parameters xhich are variable in the process of design of nuclear fuel and xhich do affect the in service performance of the fuel and its suitability for the purpose for xhich 4t xas provided.
In all cases that purpose is to generate energy in a safe and efficient Wanner Mile enabling the operating. nuclear gener-ating station to Neet all regulatory requirements affected by the, core loading of nuclear fuel. Confidence in being able to accomplish this comes from the exercise of Judgement based on experience.
Thus ~ the essen'ce of the competitive advantage in this field
)ies in an understanding of which analyses should be performed and in the methods and aedels used to perform these analyses.
A substantial part of this competitive advantage vill be lost 4f the competitors of Mestinghouse are able to use the results of the Mestinghouse experience to normalize or verify their own process or if they are able to claim an equivalent under-standing by demonstrating that they can arrive at the same or similar conclusions. Its use by a competitor auld reduce his expenditure of resources or improve his competitive position in the design and licensing of a similar product.
This'nformation is a product. of Mestinghouse design technology.
As such. it is broadly applicable to the sale and licensing of fuel in pressurized eater reactors. The development of this information is the result of many years of Mestinghouse effort tnd the expenditure of a considerable sum of mney. In order for canpetitors of Mestinghouse to duplicate this process
aeuld require the investment of substantially the ski.'neunt of effort and expertise that Westinghouse possesses and srh$ ch was acquired over a per)od of Nore than fifteen years ind by the investment of millions of dollars.
Further the deponent sayeth not.