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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20206S2911999-05-0505 May 1999 Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site ML20202C7671999-01-22022 January 1999 Forwards Order Terminating Construction Permit CPPR-154 for WNP-3/5 Site.Safety Evaluation Associated with Action Also Encl ML20198Q7131999-01-0404 January 1999 Forwards EA & Fonsi Re 960808 Application.Assessment Being Forwarded to Ofc of Fr for Publication ML20155J9731998-11-0505 November 1998 Forwards Addl Detailed Info Re Restoration & Renovation of Site Bldgs Re Util Plans to Renovate Site for Reuse as Industrial Park by Local Government Entity ML20155G7791998-11-0202 November 1998 Forwards Insp Rept 50-508/98-201 on 981027-28.No Violations Noted.Insp Included Review of Activities to Terminate Construction Permit CPPR-154 ML20116M7191996-08-0808 August 1996 Requests Termination of Construction Permit (CPPR-154) of Nuclear Project 3 & Withdrawal of Pending OL WNP-3 ML20082A7771995-03-28028 March 1995 Forwards WPPSS Nuclear Projects 1,3,4 & 5 Restoration Plan ML20078M4961995-02-0303 February 1995 Advises of Termination of Util Projects 1 & 3 ML20059B7681993-10-20020 October 1993 Requests Code Case N-520 Approval for Nuclear Projects 1 & 3 ML20057A6031993-09-0303 September 1993 Forwards Rev 6 to Procedure WMC-051, Preservation of Assets Program, Reflecting Installation of Two Desiccant Type Dehumidifiers for Controlling Relative Humidity within Reactor Auxiliary/Reactor Bldg Superstructure ML17286B2741991-10-0808 October 1991 Forwards Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies, in Response to Open Items in Draft Safety Evaluation Re Soil/Structure Interaction/Deconvolution Issue ML17286B2661991-06-0707 June 1991 Requests Approval to Revise Tornado Design Criteria,Per Reg Guide 1.76,Section C.1.2 for Rotational & Translational Velocities. Justification for Revised Tornado Design Criteria Encl ML20073P9471991-05-13013 May 1991 Forwards Rev 5 to WMC-051, WNP-3 Preventive Maint Requirements by Equipment Type ML17286A5361991-01-0202 January 1991 Discusses Interpretation of 10CFR73,App B,Paragraph Ii.B Re Security Records Retention Period ML17286A3571990-10-12012 October 1990 Requests That Name Be Kept on Mailing List & That Firm Name Be Changed to Winston & Strawn in Response to 900927 Ltr ML20062A8981990-10-0101 October 1990 Responds to NRC Re Wish to Remain on Mailing List ML20059M0921990-09-27027 September 1990 Advises That Name Will Be Removed from Mailing List Unless Notification of Wish to Remain on List to Continue to Receive Info Re Facility Received within 30 Days ML20059M0901990-09-27027 September 1990 Informs That Name Will Be Removed from Mailing List Unless Notification of Wish to Remain on List to Continue to Receive Info Re Facility Received within 30 Days ML20059A5411990-08-16016 August 1990 Provides Notice of Changes in Key Personnel ML20056A7171990-07-27027 July 1990 Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls ML20044A4931990-06-0808 June 1990 Requests That NRC Review of Facility Seismic Rept Completed & SER Issued as Soon as Possible.Facility Seismic Issue Resolution to Minimize Uncertainties Surrounding Economic Evaluations of Deferred Plants Important ML20042G3971990-05-11011 May 1990 Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs ML20012B6941990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML19325D1831989-10-12012 October 1989 Confirms That Seismic Design Data Submitted Under Separate Cover to R Pichumani,Per 891003 Request ML20246N3191989-08-30030 August 1989 Forwards Addl Info Re Plant Soil Structure Interaction Analysis/Deconvolution Issue,Per 890213 Request.Results Presented in Encl Supplemental Rept Demonstrate Overall Significant Level of Conservatism in Seismic Design Basis ML20247R6131989-05-25025 May 1989 Documents Understanding of Agreements Re Geosciences Review & Preparation of Draft SER & Requests That Staff Schedule Geoscience Review to Be Completed by Sept 1989 in Order That Work Accomplished Currently Not Lost ML20247L3141989-05-11011 May 1989 Forwards Insp Rept 50-508/89-01 on 890413-14 & 0508.No Violations Noted ML17285A2071989-01-23023 January 1989 Forwards Wppss 1988 Annual Financial Rept.W/O Encl ML20206L7671988-11-21021 November 1988 Submits Addl Info in Response to Questions on Geosciences Program Clarifying Rates of Erosion Along State of or & State of Wa Coastlines Re Formation of Modern Wavecut Platforms.Questions Arose from NRC Sept 1988 Visit ML20153F4041988-08-29029 August 1988 Forwards Sassi Analysis & Further Clarification of Elastic Half Space Analysis Providing Confirmation That Finite Element Methodology Used for Plant Design Basis Sufficiently Conservative ML20153E2801988-08-26026 August 1988 Forwards Corrected Page 1 of NRC Forwarding Insp Rept 50-508/88-02 Re Readiness Review Module C3-02 Concrete. Ltr Issued W/O Date Annotated on First Page ML20153G4231988-08-22022 August 1988 Forwards Readiness Review Module C3-02 Concrete Insp Rept 50-508/88-02.Concrete Const Completed at Time of Work Stoppage Deemed Acceptable Assuming Open Items Resolved. Listed Items Will Be Pursued During Future Reviews & Insps ML20207G5251988-08-10010 August 1988 Forwards Plots Showing Computed Distributions of Frequency of Exceedance Displayed in Terms of Fractile Hazard Curves in Seismic Hazard Rept ML20150G0441988-06-30030 June 1988 Forwards Response to Questions 230.1 & 230.2 Re Resolution of Key Licensing Issues Concerning Questions on Cascadia Subduction Zone ML20196C3091988-06-17017 June 1988 Defers Responses to NRC Bulletins & Generic Ltrs Unless NRC Specifically Requests That Util Respond for Facility.Util Will Reply to Outstanding Bulletins & Generic Ltrs That Require Response Following Resumption of Const ML20154D2661988-05-16016 May 1988 Forwards Order Extending Const Completion Date to 990701 for Plant,Per Util 841102 & 860310 Requests.Safety Evaluation & Environ Assessment & Finding of No Significant Impact Also Encl ML20154R9251988-05-13013 May 1988 Responds to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Action on Bulletin Will Be Added to Plant Tracking Sys as Work to Be Accomplished Following Restart of Const ML20154F3191988-05-13013 May 1988 Advises That Due to long-term Const Delay Status of Plant, Action Re Suppl 1 to NRC Bulletin 87-002, Fastner Testing to Determine Conformance W/Applicable Matl Specs, Will Be Deferred Until After Restart of Const ML20154F5901988-05-13013 May 1988 Informs That Assurance That Program Implemented to Address Corrosive Effects of RCS Leakage at Less than Tech Spec Limits Per Generic Ltr 88-05 Will Not Be Provided Until After Restart of Const ML20151S4161988-04-21021 April 1988 Responds to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps. Commitment to Developing Procedures & Training for Recognizing Gas Binding Conditions & Restoring Operable Status of Safety Sys Still Valid ML20153G5781988-04-0505 April 1988 Advises That 880226 Changes & Corrections to Amend 7 of FSAR Section 17.3 Consistent W/Provisions of 10CFR50,App B & Acceptable ML20150D1301988-03-18018 March 1988 Forwards Responses to NRC 830503 & 11 Requests for Addl Info Re Application for Ol.W/Eight Oversize Drawings ML20148B5101988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville,Md ML20148G1241988-03-11011 March 1988 Forwards Insp Rept 50-508/88-01 on 880222-26.No Violations Noted ML20147J0341988-03-0707 March 1988 Responds to Sorensen Providing Proposed Schedule for Completion of Review of Geosciences Issues.Proposed Schedule Acceptable.Eforts Will Be Made to Accommodate Geosciences Issues for Facility ML20147H2741988-03-0404 March 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Delayed Until After Restart of Const ML20147D3841988-02-29029 February 1988 Forwards Seismic Hazards Assessment, Final Rept Per NRC 830503 Request for Addl Info Re Question 230.6 ML20147E1181988-02-26026 February 1988 Forwards Changes to FSAR Section 17.3, QA During Long-Term Preservation. Revised Section 17.3 Incorporated Into FSAR Amend 7 ML20149L9961988-02-23023 February 1988 Ack Receipt of 880205 Request for Info & Documents Re Certain Costs Billed to Util for June 1984 - Dec 1986 Review Period.Response Forthcoming ML20149M0031988-02-0505 February 1988 Requests Review of Details of Billings for Listed Periods & Transmittal of Copies of Billings for Periods of June 1984 - Dec 1984 & Dec 1984 - June 1985.Questions Delineated in Encl 1999-05-05
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20206S2911999-05-0505 May 1999 Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site ML20155J9731998-11-0505 November 1998 Forwards Addl Detailed Info Re Restoration & Renovation of Site Bldgs Re Util Plans to Renovate Site for Reuse as Industrial Park by Local Government Entity ML20116M7191996-08-0808 August 1996 Requests Termination of Construction Permit (CPPR-154) of Nuclear Project 3 & Withdrawal of Pending OL WNP-3 ML20082A7771995-03-28028 March 1995 Forwards WPPSS Nuclear Projects 1,3,4 & 5 Restoration Plan ML20078M4961995-02-0303 February 1995 Advises of Termination of Util Projects 1 & 3 ML20059B7681993-10-20020 October 1993 Requests Code Case N-520 Approval for Nuclear Projects 1 & 3 ML20057A6031993-09-0303 September 1993 Forwards Rev 6 to Procedure WMC-051, Preservation of Assets Program, Reflecting Installation of Two Desiccant Type Dehumidifiers for Controlling Relative Humidity within Reactor Auxiliary/Reactor Bldg Superstructure ML17286B2741991-10-0808 October 1991 Forwards Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies, in Response to Open Items in Draft Safety Evaluation Re Soil/Structure Interaction/Deconvolution Issue ML17286B2661991-06-0707 June 1991 Requests Approval to Revise Tornado Design Criteria,Per Reg Guide 1.76,Section C.1.2 for Rotational & Translational Velocities. Justification for Revised Tornado Design Criteria Encl ML20073P9471991-05-13013 May 1991 Forwards Rev 5 to WMC-051, WNP-3 Preventive Maint Requirements by Equipment Type ML17286A5361991-01-0202 January 1991 Discusses Interpretation of 10CFR73,App B,Paragraph Ii.B Re Security Records Retention Period ML17286A3571990-10-12012 October 1990 Requests That Name Be Kept on Mailing List & That Firm Name Be Changed to Winston & Strawn in Response to 900927 Ltr ML20062A8981990-10-0101 October 1990 Responds to NRC Re Wish to Remain on Mailing List ML20059A5411990-08-16016 August 1990 Provides Notice of Changes in Key Personnel ML20056A7171990-07-27027 July 1990 Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls ML20044A4931990-06-0808 June 1990 Requests That NRC Review of Facility Seismic Rept Completed & SER Issued as Soon as Possible.Facility Seismic Issue Resolution to Minimize Uncertainties Surrounding Economic Evaluations of Deferred Plants Important ML20042G3971990-05-11011 May 1990 Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs ML20012B6941990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML19325D1831989-10-12012 October 1989 Confirms That Seismic Design Data Submitted Under Separate Cover to R Pichumani,Per 891003 Request ML20246N3191989-08-30030 August 1989 Forwards Addl Info Re Plant Soil Structure Interaction Analysis/Deconvolution Issue,Per 890213 Request.Results Presented in Encl Supplemental Rept Demonstrate Overall Significant Level of Conservatism in Seismic Design Basis ML20247R6131989-05-25025 May 1989 Documents Understanding of Agreements Re Geosciences Review & Preparation of Draft SER & Requests That Staff Schedule Geoscience Review to Be Completed by Sept 1989 in Order That Work Accomplished Currently Not Lost ML17285A2071989-01-23023 January 1989 Forwards Wppss 1988 Annual Financial Rept.W/O Encl ML20206L7671988-11-21021 November 1988 Submits Addl Info in Response to Questions on Geosciences Program Clarifying Rates of Erosion Along State of or & State of Wa Coastlines Re Formation of Modern Wavecut Platforms.Questions Arose from NRC Sept 1988 Visit ML20153F4041988-08-29029 August 1988 Forwards Sassi Analysis & Further Clarification of Elastic Half Space Analysis Providing Confirmation That Finite Element Methodology Used for Plant Design Basis Sufficiently Conservative ML20207G5251988-08-10010 August 1988 Forwards Plots Showing Computed Distributions of Frequency of Exceedance Displayed in Terms of Fractile Hazard Curves in Seismic Hazard Rept ML20150G0441988-06-30030 June 1988 Forwards Response to Questions 230.1 & 230.2 Re Resolution of Key Licensing Issues Concerning Questions on Cascadia Subduction Zone ML20196C3091988-06-17017 June 1988 Defers Responses to NRC Bulletins & Generic Ltrs Unless NRC Specifically Requests That Util Respond for Facility.Util Will Reply to Outstanding Bulletins & Generic Ltrs That Require Response Following Resumption of Const ML20154F3191988-05-13013 May 1988 Advises That Due to long-term Const Delay Status of Plant, Action Re Suppl 1 to NRC Bulletin 87-002, Fastner Testing to Determine Conformance W/Applicable Matl Specs, Will Be Deferred Until After Restart of Const ML20154R9251988-05-13013 May 1988 Responds to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Action on Bulletin Will Be Added to Plant Tracking Sys as Work to Be Accomplished Following Restart of Const ML20154F5901988-05-13013 May 1988 Informs That Assurance That Program Implemented to Address Corrosive Effects of RCS Leakage at Less than Tech Spec Limits Per Generic Ltr 88-05 Will Not Be Provided Until After Restart of Const ML20151S4161988-04-21021 April 1988 Responds to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps. Commitment to Developing Procedures & Training for Recognizing Gas Binding Conditions & Restoring Operable Status of Safety Sys Still Valid ML20150D1301988-03-18018 March 1988 Forwards Responses to NRC 830503 & 11 Requests for Addl Info Re Application for Ol.W/Eight Oversize Drawings ML20147H2741988-03-0404 March 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Delayed Until After Restart of Const ML20147D3841988-02-29029 February 1988 Forwards Seismic Hazards Assessment, Final Rept Per NRC 830503 Request for Addl Info Re Question 230.6 ML20147E1181988-02-26026 February 1988 Forwards Changes to FSAR Section 17.3, QA During Long-Term Preservation. Revised Section 17.3 Incorporated Into FSAR Amend 7 ML20149M0031988-02-0505 February 1988 Requests Review of Details of Billings for Listed Periods & Transmittal of Copies of Billings for Periods of June 1984 - Dec 1984 & Dec 1984 - June 1985.Questions Delineated in Encl ML20150C4591988-01-13013 January 1988 Describes Basic Aspects of 871221 Meeting W/Util in Bethesda,Md Re Ssi/Deconvolution Issues Re Audit Finding 1 & Provides Recommendations for Resolving Associated Issues ML20234D7321987-12-21021 December 1987 Proposes Deferral of Response to Compliance Bulletin 87-002 Until After Restart of Const ML20236S9331987-11-23023 November 1987 Discusses Violation Noted During Insp Rept 50-508/82-04 Re Questionable Welds.Items Identified on Nonconformance Rept (Ncr 15313) & Implementation of Corrective Action Will Be Entered Into Site Tracking Sys & Accomplished at Restart ML20236X2531987-11-20020 November 1987 Forwards Addl Info Re Geosciences Program for Resolution of Key Licensing Issues on Seismicity of Western Area of State of Wa,Per NRC 870708 Request.Responses to Seismic & Ground Motion Questions Will Be Submitted Soon ML20236Q4451987-10-28028 October 1987 Requests Supporting Documentation Providing Basis for OL Application Review Costs for Period of 860622-1220. Documentation & Verification Requirements for Public Fund Expenditures Exist Since WPPSS Is State Municipal Corp ML20236A8001987-10-0808 October 1987 Forwards Description of Status of Plant Seismic Review,Per Request.Meeting Will Be Requested W/Util to Resolve Audit Finding 1 Issue ML20235J8801987-09-30030 September 1987 Forwards Revised FSAR QA Program Description (Section 17.3) Re Organizational Realignments,Effective on 870701,per Util .Qa Program During Plant Asset Preservation Stage Discussed ML20237H6771987-08-19019 August 1987 Proposes to Defer Response to Generic Ltr 87-12 Re Loss of RHR While RCS Partially Filled Until After Const Restart, When Resources Will Be Available.Deferral Will Allow Util to Consider in Response Info Gained by NRC ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor ML20237H4791987-08-0707 August 1987 Requests Response to Re NRC Billings for OL Review & Insp Fees ML20236N3711987-07-31031 July 1987 Forwards Addl Info Re Soil Structure Interaction Deconvolution Issue,Per NRC 870417 Request ML20236F6121987-07-29029 July 1987 Responds to Request for Info Re NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants. Util Not Able to Submit Info at Present Time Due to Const Delay.Const Activities Will Not Resume Before 1994 ML20237G3911987-07-20020 July 1987 Requests Supporting Documentation Providing Basis for NRC Billing & Operating License Reviews & Insp Fees for 850623 Through 860621 ML20235M4401987-06-25025 June 1987 Forwards EGG-NTA-7673, Conformance to Generic Ltr 83-28, Item 2.2.2--Vendor Interface Programs for All Other Safety- Related Components:WNP-1/-3, Final Informal Rept 1999-05-05
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059A5411990-08-16016 August 1990 Provides Notice of Changes in Key Personnel ML20056A7171990-07-27027 July 1990 Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls ML20042G3971990-05-11011 May 1990 Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs ML20012B6941990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML19325D1831989-10-12012 October 1989 Confirms That Seismic Design Data Submitted Under Separate Cover to R Pichumani,Per 891003 Request ML20246N3191989-08-30030 August 1989 Forwards Addl Info Re Plant Soil Structure Interaction Analysis/Deconvolution Issue,Per 890213 Request.Results Presented in Encl Supplemental Rept Demonstrate Overall Significant Level of Conservatism in Seismic Design Basis ML20247R6131989-05-25025 May 1989 Documents Understanding of Agreements Re Geosciences Review & Preparation of Draft SER & Requests That Staff Schedule Geoscience Review to Be Completed by Sept 1989 in Order That Work Accomplished Currently Not Lost ML17285A2071989-01-23023 January 1989 Forwards Wppss 1988 Annual Financial Rept.W/O Encl ML20206L7671988-11-21021 November 1988 Submits Addl Info in Response to Questions on Geosciences Program Clarifying Rates of Erosion Along State of or & State of Wa Coastlines Re Formation of Modern Wavecut Platforms.Questions Arose from NRC Sept 1988 Visit ML20153F4041988-08-29029 August 1988 Forwards Sassi Analysis & Further Clarification of Elastic Half Space Analysis Providing Confirmation That Finite Element Methodology Used for Plant Design Basis Sufficiently Conservative ML20207G5251988-08-10010 August 1988 Forwards Plots Showing Computed Distributions of Frequency of Exceedance Displayed in Terms of Fractile Hazard Curves in Seismic Hazard Rept ML20150G0441988-06-30030 June 1988 Forwards Response to Questions 230.1 & 230.2 Re Resolution of Key Licensing Issues Concerning Questions on Cascadia Subduction Zone ML20196C3091988-06-17017 June 1988 Defers Responses to NRC Bulletins & Generic Ltrs Unless NRC Specifically Requests That Util Respond for Facility.Util Will Reply to Outstanding Bulletins & Generic Ltrs That Require Response Following Resumption of Const ML20154R9251988-05-13013 May 1988 Responds to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Action on Bulletin Will Be Added to Plant Tracking Sys as Work to Be Accomplished Following Restart of Const ML20154F5901988-05-13013 May 1988 Informs That Assurance That Program Implemented to Address Corrosive Effects of RCS Leakage at Less than Tech Spec Limits Per Generic Ltr 88-05 Will Not Be Provided Until After Restart of Const ML20154F3191988-05-13013 May 1988 Advises That Due to long-term Const Delay Status of Plant, Action Re Suppl 1 to NRC Bulletin 87-002, Fastner Testing to Determine Conformance W/Applicable Matl Specs, Will Be Deferred Until After Restart of Const ML20151S4161988-04-21021 April 1988 Responds to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps. Commitment to Developing Procedures & Training for Recognizing Gas Binding Conditions & Restoring Operable Status of Safety Sys Still Valid ML20150D1301988-03-18018 March 1988 Forwards Responses to NRC 830503 & 11 Requests for Addl Info Re Application for Ol.W/Eight Oversize Drawings ML20147H2741988-03-0404 March 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Delayed Until After Restart of Const ML20147D3841988-02-29029 February 1988 Forwards Seismic Hazards Assessment, Final Rept Per NRC 830503 Request for Addl Info Re Question 230.6 ML20147E1181988-02-26026 February 1988 Forwards Changes to FSAR Section 17.3, QA During Long-Term Preservation. Revised Section 17.3 Incorporated Into FSAR Amend 7 ML20149M0031988-02-0505 February 1988 Requests Review of Details of Billings for Listed Periods & Transmittal of Copies of Billings for Periods of June 1984 - Dec 1984 & Dec 1984 - June 1985.Questions Delineated in Encl ML20234D7321987-12-21021 December 1987 Proposes Deferral of Response to Compliance Bulletin 87-002 Until After Restart of Const ML20236S9331987-11-23023 November 1987 Discusses Violation Noted During Insp Rept 50-508/82-04 Re Questionable Welds.Items Identified on Nonconformance Rept (Ncr 15313) & Implementation of Corrective Action Will Be Entered Into Site Tracking Sys & Accomplished at Restart ML20236X2531987-11-20020 November 1987 Forwards Addl Info Re Geosciences Program for Resolution of Key Licensing Issues on Seismicity of Western Area of State of Wa,Per NRC 870708 Request.Responses to Seismic & Ground Motion Questions Will Be Submitted Soon ML20236Q4451987-10-28028 October 1987 Requests Supporting Documentation Providing Basis for OL Application Review Costs for Period of 860622-1220. Documentation & Verification Requirements for Public Fund Expenditures Exist Since WPPSS Is State Municipal Corp ML20235J8801987-09-30030 September 1987 Forwards Revised FSAR QA Program Description (Section 17.3) Re Organizational Realignments,Effective on 870701,per Util .Qa Program During Plant Asset Preservation Stage Discussed ML20237H6771987-08-19019 August 1987 Proposes to Defer Response to Generic Ltr 87-12 Re Loss of RHR While RCS Partially Filled Until After Const Restart, When Resources Will Be Available.Deferral Will Allow Util to Consider in Response Info Gained by NRC ML20237H4791987-08-0707 August 1987 Requests Response to Re NRC Billings for OL Review & Insp Fees ML20236N3711987-07-31031 July 1987 Forwards Addl Info Re Soil Structure Interaction Deconvolution Issue,Per NRC 870417 Request ML20236F6121987-07-29029 July 1987 Responds to Request for Info Re NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants. Util Not Able to Submit Info at Present Time Due to Const Delay.Const Activities Will Not Resume Before 1994 ML20237G3911987-07-20020 July 1987 Requests Supporting Documentation Providing Basis for NRC Billing & Operating License Reviews & Insp Fees for 850623 Through 860621 ML20215G9421987-06-18018 June 1987 Advises That on 870317,util Realigned Corporate QA Functional Responsibilities to Consist of Consolidation of Corporate QA Audit & Const QA Activities.Also Advises That Effective 870701,mgt of Util Will Be Integrated W/Ebasco ML20215F8841987-06-15015 June 1987 Amends Util 870331 Response to Violation Item 86-13-18 Noted in Insp Rept 50-508/86-13.Spec Combined W/Design Drawings Meet Rebar Spacing Requirements of ACI Code ML20215C4411987-06-0101 June 1987 Submits Rept for Concrete Module C3-02 of Const Assurance Program,Per Readiness Review Program Agreements.Certifies That Completed Concrete Structures,W/Noted Exceptions,Meet Design & Const Requirements ML20205R5061987-03-31031 March 1987 Responds to NRC Re Violations Noted in Insp Rept 50-508/86-13.Licensee Disagrees W/Violations Re Reinforcing Steel Clearance Acceptance Criteria of ACI-318-71 & Identifying Nonconforming Concrete Grout for Future Rework ML20210D8601987-01-23023 January 1987 Requests Response to Re Possible Billing Errors for OL Reviews & Insp Fees ML17278B1711987-01-19019 January 1987 Forwards Wppss Annual Rept 1986. Financial Statements Not Certified by Auditor,Ernst & Whinney,In View of Facts Discussed in Rept ML20214P4391986-11-19019 November 1986 Responds to IE Bulletin 86-002, Static O-Ring Differential Pressure Switches. No Present or Future Use of Static O- Ring Series 102 & 103 Differential Switches Planned at Facility ML20213E0831986-11-0606 November 1986 Forwards Revised Schedule for Geosciences Program Plan,For Review.Util Continuing W/Program for Resolving Geological/ Seismological Questions ML20213G7251986-11-0606 November 1986 Advises That Response to IE Bulletin 86-003, Potential Failure of Multiple ECCS Pumps Due to Single Failure of Air-Operated Valve in Min Flow Recirculation Line, Will Be Submitted After Const Restart in 1994 ML20213G6791986-11-0303 November 1986 Advises That Readiness Review Civil/Structural Review Team Will Be at Ebasco Ofcs in New York,Ny on 861211-12 to Perform Review of Ebasco Civil/Structural Design ML20215H4071986-10-17017 October 1986 Requests Approval to Use ASME Code Case N-430,incorporating Modified Visual Weld Acceptance Criteria for Nf Structures, at Earliest Opportunity ML20197B5361986-10-17017 October 1986 Responds to IE Bulletin 85-001, Steam Binding of Auxiliary Feedwater Pumps. Bulletin Procedure Controls Unnecessary for Facility Operation ML20215M3081986-10-16016 October 1986 Forwards Pages to FSAR QA Program Description Reflecting Addl Changes Incorporated Into Amend 6 FSAR Change Notices Scn 740,SCN 778,SCN 784 & Scn 788.Changes Pose No Reduction in Commitments ML20211G6121986-10-15015 October 1986 Forwards WMC-057, Mgt Plan for Extended Const Delay of WNP-1,Executive Summary (Levels I-III) & Rev 4 to WMC-050A, Mgt Plan for Extended Const Delay of WNP-3,Executive Summary (Levels I-III) ML20214Q2301986-09-17017 September 1986 Forwards Corrected Figure 231.1-12,per Response to NRC 860630 Question 231.1 Re Geology/Seismology.Figure Revised to Correct Drafting Error & Incorporate New Info Released in June 1986 ML20211A8171986-09-10010 September 1986 Forwards Final Rept of Earthwork Module C3-01 of Facility Const Assurance Program of Facility Readiness Review Program. Earthwork Acceptable & Meets Fsar,Engineering & Const Requirements ML20205F0021986-08-13013 August 1986 Forwards Final Response to Structural Engineering Branch Audit Finding 4 Re Containment Buckling,Including Status List of Audit Findings & 220 Series Questions ML20206N5711986-08-0707 August 1986 Forwards Current 6-month Rolling Schedules for Const Assurance & Engineering Assurance Portions of Readiness Review Program.Adoption of Reduced Budget Necessitated Extension of Engineering Assurance Portion of Review 1990-08-16
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Washington Public Power Supply System Box 1223 Elma, Washington 98541 (206)482-4428 March 31, 1987 G03-87-82 Docket No. 50-508 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
NUCLEAR PROJECT 3 NRC INSPECTION AT WNP-3 IE REPORT NO. 50-508/86-13 VIOLATION ITEMS 86-13-18 AND 85-13-19
Reference:
NRC letter, Robert J. Pate to D.W. Mazur, subject, "NRC Inspection - WNP-3", dated February 26, 1987 The referenced letter reported the results of the NRC inspection conducted by Mr. A.D. Toth and C.G. Bruch on December 8-19, 1986. Two violations were identified as follows:
Violation 1 (86-13-18)
The WNP-3 construction specification for concrete installed for the reactor building did not incorporate the appropriate reinforcing steel clearance acceptance criteria of ACI-318-71.
Violation 2-(86-13-19)
Nonconforming concrete grout had not been corrected nor otherwise identified for future rework.
8704060366 870331 8 DR ADOCK 0500
/\
1
U.S. Nuclear Regulatory Commission G03-87-82 Page Two March 31, 1987 Attached is the Supply System approved repcrt detailing our disagreement with both violations. Should you have any questions or desire further information, ple contact me directly.
aul . son Program Director, WNP-3 DRC/st cc: Mr. J. A. Adams, NESCO Mr. R. M. Boucher, Pacific Power & Light Co.
Mr. W. L. Bryan, Washington Water Power Co.
Mr. R. E. Dyer, Portland General Electric Co.
Mr. W. J. Finnegan, Puget Sound Power & Light Co.
Mr. J. R. Lewis, BPA Mr. J._ B. Martin, U.S. NRC Region V Office, Regional Administrator Mr. R. J. Pate, U.S. NRC Region V Office Mr. N. S. Reynolds, Bishop, Liberman, Cook, Purcell & Reynolds Mr. D. Smithpeter, BPA Ms. R. M. Taylor, Ebasco - Elma Ebasco - New York l
9 VIOLATION 1 (86-13-18) 10CFR50 Appendix B Criterion V requires, in part, that " Instructions, procedures or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished."
The WNP-3 Final Safety Analysis Report identifies ACI-318-71 as the applicable industry standard for construction of WNP-3 concrete and reinforcing steel structures.
Contrary to the above, at the time of the inspection the WNP-3 construction specification for concrete installed for the reactor building, WPPSS-3240-412, did not incorporate the appropriate reinforcing steel clearance acceptance criteria of ACI-318-71 Part 7.4.1 and 7.4.5, which require a minimum of one nominal bar diameter clear distance between parallel bars (i.e.,1.4 inches for size #11 bar). The WPPSS specifications ' allowed as little as 1.0 inch clearance, based upon 3/4 inch and less aggregate size allowed by the specifications.
RESPONSE
The Supply System does not agree that Violation 1 is an item of noncompliance.
It is the Supply System's position that the WNP-3 construction specification for concrete installed for the reactor building (WPPSS-3240-412) does incorporate the appropriate reinforcing steel clearance acceptance criteria of ACI-318-71.
The Supply System's position is based on the following:
- 1. The WNP-3 Final Safety Analysis Report (Sections 3.8.3.2 and 3.8.3.6) identifies several codes, standards and Ebasco Specifications for design and construction of the Category I structures.
For design of concrete structures, reference to ACI-318-71 Code is made in Section 3.8.3.2.lb of the FSAR which states, "All concrete internal structures are designed in accordance with applicable portions of ACI-318-71....".
For construction of concrete structures, the detailed requirements for materials, design criteria, fabricatien, erection, inspection and quality compliance are described in Section 3.8.3.6.1 of the FSAR. A listing of-applicable purchase specification topics, which includes Formed Concrete Construction, is provided in Section 3.8.3.2.3d of the FSAR. The WNP-3 construction specification for " Formed Concrete Construction" is WPPSS 3240-412.
FSAR Section 3.8.3.6.1.1 states, "The requirements for concrete construction materials are -established by purchase specification compiled for the project. which clearly enumerate applicable ASTM, ACI and ANSI Standards or portions thereof".
Therefore, it is evident that design and construction of concrete structures was based on ACI-318-71 and other applicable documents.
Construction of concrete structures was governed by the applicable purchase.
specifications, which included references to ACI-318-71 on a selective basis.
VIOLATION 1 (86-13-18) CONTINUED
- 2. Nuclear plant structures are considered special structures and involve unique considerations in design and construction which are not fully covered by ACI-318-71 Code. Both the ACI building code and its associated commentary recognize this fact. Section 1.1 of the commentary states, in part, "Some special structures involve unique problems which are not covered by the Code...".
- 3. Ebasco Specification WPPSS-3240-412 covers the requirements of conveying, placing, curing, and finishing of the concrete. It also includes formwork and placing of reinforcing steel requirements. The specification is based on ir.dustry standards including ACI-301, ACI-304, ACI-305, ACI-306, ACI-309 and ACI-318. References to the above standards are made in various paragraphs of the specification relative to which specific provisions of the standards are to be adhered to. In Paragraph 5.0 (Placing Reinforcement) of the subject specification, the Engineer made no reference to ACI-318 in placing of reinforcing steel, including spacing or tolercace requirements.
- 4. The Commentary to ACI-318-71 Code states, "The minimum limits (spacing requirements) were established to permit concrete to flow readily into spaces between bars and between bars and forms without honeycomb and to ensure against concentration of bars on a line that might result in shear or shrinkage cracking."
- 5. The ACI Code allows and in special instances requires that the Engineer take exception with the provisions of the code, providing that in all cases a rationale for such exceptions is justified.
- 6. Considering all the above, the specification requirements for minimum spacing for reinforcing steel, together with maximum aggregate size, must meet the intent of the ACI-318-71 Code, Paragraphs 7.4.1 and 3.3.2.
Accordingly, Paragraph 5.02 of the specification WPPSS-3240-412 states, in part, " Clear distance between bars shall not be less than 1 inch, nor less than 1-1/3 times the maximum size of the coarse aggregate unless otherwise approved by the Engineer." In all instances, the Engineer approved the actual size of coarse aggregate used which in combination with the rebar spacing detailed on the design drawings meet the requirements of the ACI Code.
VIOLATION 2 (86-13-19) 10CFR50 Appendix B Criterion XV requires, in part " Nonconforming items shall be -
reviewed and accepted, rejected, repaired or reworked in accordance with documented procedures."
Contrary to the above, in 1983, concrete grout on the pedestal of the "A" Containment Spray Pump base was identified as nonconforming to approved specifications. The responsible organization prepared a Quick Fix Project Change Proposal, which was subsequently marked void after incorporation into approved design drawings. At the time of the inspection, the nonconforming condition had not been corrected nor otherwise identified for future rework.
RESPONSE
The Supply System does not agree that Violation 2 is an item of noncompliance.
It is the Supply SysteW s position that the " nonconforming condition" of the concrete grout was properly identified and tracked for future rework. The following chronological history of Containment Spray Pumps "A" and "B" base grouting is provided for clarification:
o Both Containment Spray Pumps were released for grouting by Peter Kiewit Sons, Inc. (Contract 3240-251), the mechanical contractor responsible for the pump and connecting piping installation, in August of 1982. Morrison-Knudsen (Contract 3240-263), the RAB civil / structural contractor, performed proprietary grouting of Spray Pump "A" on August 25, 1982 and Spray Pump "B" on August 26, 1982. Both grout installations were adequately documented with no resulting discrepancies or nonconformances.
o The grout configuration, as placed, conformed to the requirements of the design drawing in effect at the time of placement.
o In June of 1983, an Ebasco Civil Engineer noted that the grout configuration as placed and shown on the design drawing yielded a condition not recommended by Master Builders, the manufacturer of the non-shrink grout product used for this installation. In accordance with the site design change procedure, the Ebasco Engineer, under the authority of the Resident Engineer-Civil prepared a Project Change Proposal (PCP) which was submitted to the design engineer, requesting a drawing configuration change relative to the Spray Pump grouting details. This change was subsequently approved and posted as an outstanding (unincorporated) modification to the design drawing.
o In early 1983 the project was entering the present construction suspension period and most field construction activities were halted, with the exception of activities required for maintenance and preservation. As a result, the work required by the PCP was not and has not yet been performed. Contract 3240-263 (Morrison-Knudsen) is identified on the PCP as the contractor responsible for performing the required grout work.
Contract 263 is presently in a long-term suspension mode with contractual provisions to complete their original scope of work in accordance with 10CFR50, Appendix B requirements upon notification of construction restart by the Supply System.
kfl0LATION 2 (86-13-19) CONTINUED o Morrison-Knudsen's Document Control System, as described by an approved MK Procedure tracks design changes issued by Ebasco. Through this system, MK's engineering department identifies those items requiring additional work based on the design change. This program is currently in suspension but will be in effect at restart.
During the suspension period, as during construction, Ebasco's Site Document Control System tracks design changes (e.g., PCP's and drawing revisions) and their status of issuance to the contractors in accordance with the Ebasco Site Procedure for Document Control. At the time of the NRC inspection, the Document Control System computer printout indicated that the PCP had been incorporated into the latest revision of the design drawing and the revised drawing had not been issued to the contractor.
Design changes not issued to the contractor due to the delay will be issued to the installation contractor at project restart at which time the contractor document control system, as described above, will initiate the field work necessary to implement the design.
o During the suspension period, Design Engineering has incorporated outstanding modifications to design drawings and specifications to streamline issuance of contract documents upon construction restart. As a result, the requirements of the PCP were incorporated into the drawing and will be issued to the contractor in accordance with the Ebasco Document Control Program.
The referenced PCP copy marked void, was located in the Civil Document Control Station, Copyholder No. R40. The station is maintained in accordance with the Ebasco Site Procedure for Document Control. The PCP was stamped " VOID", indicating its inactive status which is per the requirements of Ebasco's QA ASME Manual (Section I-1, paragraph 4.1.2).
o During a routine inspection in December of 1986, the NRC Region V inspector observed cracks in the exposed non-shrink grout on the Spray Pump pedestals and a 6" x 6" triangular outside corner section on the pump "A" pedestal that had been broken off at an undetermined time.
Based on the above, the Supply System position is as follows:
There is no evidence to indicate that the damage to the grout placement, as noted by the NRC inspector, was present at the time that the PCP was generated. The PCP description of problem indicates that the originator, an experienced Civil / Structural Field Engineer, recogized a potential problem with the as-built and designed configuration of the grout and proposed the change as shown on the PCP. A Quick Fix Project Change Proposal is the proper document for effecting a change and/or correcting an error on a design document. Block 16 on the subject PCP form states that the change was made for " engineering correction, omission or error".
Although the condition of the exposed grout on the Containment Spray Pump pedestals may have appeared to be a nonconforming condition to the NRC inspector, existence of the aforementioned PCP and resulting outstanding work identified against the pump foundation drawing requiring additional work on the pedestal grout (including removal of the damaged areas) simply identifies an incomplete work-to go item. Therefore, a Nonconformance
! Report (NCR) is not warranted in this case.
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. NIOLATION 2 (85-13-19) CONTINUED The incorporation of the PCP into the drawing does not indicate that the required work has been performed or will not be performed in the future.
The responsible contractor is, under the terms of the suspension agreement, required to implement all programs and procedures upon construction restart to assure that their scope of work is complete prior to turnover to the Supply System.
Analogous to this situation would be the incomplete status of a given bay of structural steel as of the date of work suspension. The fact that particular members shown on the design drawing are not yet installed is not a discrepant condition. The contractor is responsible for turnover of a complete system.
Additionally, the project PRIDE Program (Project Review of Installation, Documentation and Engineering) has been established for WNP-3 in part to assure that installation has been accomplished in accordance with the latest design revisions. PRIDE utilizes physical plant walkdowns, documentation review, design installation verification and work package controls to establish an overall program capable of verifying installation to the latest design at the time of installation, completeness of records, and ensuring that design changes are incorporated into final installation.
The design installation verification portion of this program is performed prior to system / area turnover to the Owner in accordance with the Ebasco Site Procedure for System Completion and Provisional Acceptance.
In addition to providing a response to Violation 2, the referenced NRC letter also requested that the Supply System " discuss the method the Readiness Review Program will implement to assure that construction changes have been accomplished in accordance with such design revisions". Accordingly, the following discussion is provided:
The Construction Assurance portion of the Readiness Review Program also samples completed installation work. If an installation, such as the Spray Pump pedestal with an outstanding design modification, surfaced in the CAP sample for field inspections, the Review Team is required to obtain the latest design information (including the drawing) to identify construction and inspection requirements. As the repeat visual inspection of " completed work" is performed, the uncompleted design change would be identified.
Follow-up investigation to determine the cause of difference between the as-built condition and the final design would reveal the item as work to go. Such follow-up work is required by CAP Procedure CAP 6.5, Revision 3, paragraph 3.10. Further, the CAP Office informs the project in writing of work-to-go and construction-related damage items identified in its field inspections.
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