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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 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 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 ML20237H4791987-08-0707 August 1987 Requests Response to Re NRC Billings for OL Review & Insp Fees ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor 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
.c p LO Docket Numbers 50-508 and 50-509 December 23, 1981 G03-81-2866 U. S. Nuclear Regulatory Commission, Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 260 Walnut Creek, California 94596-5368 Attention: Mr. B. H. Faulkenberry Chief, Reactor Construction Projects Branch
Subject:
NRC INSPECTION AT WNP-3/5 DOCKET NUMBERS 50-508 AND 50-509 ITEM 0F NONCOMPLIANCE IE REPORT N0. 50-508/509/81-14/01
Reference:
- 1) NRC Letter, NRC Inspection at Washington Nuclear Project Nos. 3 and 5, Mr. B. H. Faulkenberry to Mr. R. S. Leddick, dated October 21, 1981.
Reference l reported the results of the NRC inspection conducted August 10-16, 1981, of activities authorized by NRC Construction Permit Nos. CPPR-154 and 155. One Item of Noncompliance (81-14/01),
concerning a failure to assure proper testing of penetration welds, was identified. The Supply System was directed to provide a re-sponse to the Notice of Violation and include a discussion of the reasons for failure to adequately investigate and effect corrective actions to preclude the subject Item of Noncompliance.
Attached is a report detailing corrective / preventive actions taken '
for the subject noncompliance. In addition to providing a response to the violation, the report addresses the additional concerns raised by the NRC. The Supply System considers the violation to be satisfactorily resolved.
8203020632 820222 ~
PDR ADOCK 05000508 G PDR @ ~ l c20
i
.Mr. B. H. Faulkenberry Page 2 December 23, 1981 G03-81-2866 Should you have any questions or desire further information, please contact me directly.
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. . Leddick/1000 Program Director, WNP-3/5 DRC/tt Attachment cc: J. Adams - NESCO-WO/A D. Smithpeter - BPA-WO/A Ebasco - New York-WO/A WNP-3/5 Files - Richland-WO/A
R. S. LEDDICK, Being first duly sworn, deposes and says: That he is the Program Director, WNP-3/5, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that he is authorized to submit the fore-going on behalf of said applicant; that he has read the foregoing and knows the contents thereof; and believes the same to be true to the best of his knowledge. -
DATED N bCCSf6 , 1981.
R. S. LEDDICK STATE OF WASHINGTON )
) ss COUNTY OF GRAYS HARBOR )
On this day personally appeared before me R. S. LEDDICK to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the t4me as his free act and deed for the uses and pur-poses therein mentioned.
GIVEN under my hand and seal this 03 day ofh e.4 m 6d,1981.
m.ab Notary Public in and for the State of Washington Residing at El. rn cu
ATTACHMENT I Page 1 Nuclear Regulatory Commission - Noncompliance (50-508, 509/81-14/01) 10CFR50, Appendix B, Criterion XI states that "A test program shall be established to assure that all testing required to demonstrate that struc-tures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applica-ble design documents."
Paragraph 17.1.11 of the Quality Assurance Program documented in approved PSAR Deviation No. 26-WP, states that: " Construction testing will be per-formed by the contractors to ensure that installed equipment meets appli-cable codes, standards, and design requirements."
Contract Specification No. 3240-251/226, Page S-8, Revision 5, states, in part, that: " Field welds on pipe sleeves and penetrations shall be tested in accordance with ASME III, Article NC-6000...."
- 1. The ASME Boiler and Pressure Vessel Code Section III, 1977 Edition including addenda through Summer, 1978, Paragraph NC-6111.1 states, in part, that: "All components and appurtenances constructed or installed under the rules of this subsection shall be hydrostatically tested...." Paragraph NC-6111.2 states: "When a hydrostatic test is not practical (NC-6112), a pneumatic test in accordance with NC-6300 may be substituted." Paragraph NC-6321(a) specifies that: "The pneu-matic test pressure for components or appurtenances except storage tanks shall not be less than 1.25 times the system design pressure..."
Paragraph NC-6315 specifies, in part, that: "Following the applica-tion of pressure... examination for leakage in accordance with NC-6215 shall be made."
Contrary to the above, a 7.5 PSIG pneumatic pressure test was performed by the contractor in accordance with procedure No. PKS-WI-306, Revision 3, as approved by Ebasco, on Unit No. 3 containment penetration No. 24 sleeve welds which resulted in Field Weld No. 4 on penetration No. 24 not being tested at 1.25 times the design pressure of 50 PSIG. Field Weld No. 4 is now embedded in concrete which prevents examination of the surface for leakage.
- 2. Paragraph NC-6112(a) states, in part, that: " Pneumatic tests may be used in lieu of the hydrostatic test required by NC-6111.1...
only when the following conditions exist: (1) When components...
are so designed or supported that they cannot be safely filled with water. (2) When components...which are not readily dried are to be used in services where traces of the testing medium cannot be tol-erated...." Paragraph NC-6215 states, in part, that: "Following application of the hydrostatic test pressure... examination for leak-age shall be made of all joints...." Paragraph NC-6221(b) states, in part, that: "All pressure retaining components...shall be sub-jected to a system hydrostatic test at a pressure not less than 1.25 times the system design pressure."
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. Attachment to Letter G03-81-2866 Page 2 Dated December 23, 1981 Contrary to the above, Contract 251 Procedure No. PKS-WI-306, Revision 3, specifies a pneumatic test of the process pipe on penetration Nos. 23, 24, and 44. The process piping in these penetrations has been designed to accommodate the testing medium (water). Closure welds have been completed on penetration Nos. 24 and 44 in Unit 3 rendering the joints inaccessible for examination for leakage. The specified test pressure for penetration No. 44 is 188 PSIG whereas the specified design pressure of the process piping is 200 PSIG which would require a test pressure of 250 PSIG.
Items 1 and 2 represent failures to properly incorporate code requirements into applicable test procedures.
This is a severity Level V violation (Supplement II) applicable to Unit 3.
General Information Penetrations 23 and 24 are Type IV penetrations serving the Containment Spray System. The lines are the suction lines from the containment sumps to the Containment Spray pumps. Penetration 44 is a Type IV A penetration.
It is provided to accommondate the passage of the drain line from the Re-actor Drain Tank through the containment to the Gas Stripper.
Corrective Actions Taken A. Background Information For Part 1 Of The Noncompliance Concurrent with installation of Penetrations 23, 24, and 44, Ebasco performed a design review and verification with regard to the design pressures and temperatures of these components. The result of this investigation was documented by the issuance of a DCN on June 15, 1981.
The purpose of the DCN was to clarify that the guard pipes for these penetrations have dual design parameters. The guard pipes inside the containment form part of the containment vessel pressure boundary, thest are line numbers 2CS40-20lSA, 2CS40-203SB and 2CH8-328SA/BR. The de-sign pressure of these lines is 50 PSIG which is in accordance with
, PSAR Paragraph 6.2.4.1.la and is greater than the design pressure of the containment (44 PSIG). The DCN only changed the design pressure for line 2CH8-328SA/BR which was lowered from 150 PSIG. The design pressure of 150 PSIG was incorrectly based on the design pressure of the process line instead of the design pressure of the containment.
The guard pipes outside containment are not part of the containment pressure boundary. They are only exposed to atmospheric pressure.
The design pressure of line numbers 2CS40-200SA, 2CS40-202SB and 2CH8-624SA/BR was thus established at 5 PSIG. This was a decrease in design pressure for all three lines. Additionally, the DCN noted that the inside containment guard pipe welds would be tested during the combir ad ILRT and Overpressure Test of the containment as they are part of the containment vessel pressure boundary.
In accordance with the direction provided by the DCN, the 251 Contrac-tor (Peter Kiewit and Sons) performed the required ASME code pressure
. Attachment to Letter G03-81-2866 Page 3
.
- Dated December 23, 1981 Corrective Actions Taken (Continued)
A. Background Information For Part 1 Of The Noncompliance (Continued) test of the guard pipes based on the design pressure of 5 PSIG for Penetration 24. It was recognized that the inside containment guard pipe would still require pressure testing in accordance with a design pressure of 50 PSIG. The pressure test performed at 7.5 PSIG was not intended to qualify the inside containment guard pipe welds. After the pressure test of 7.5 PSIG, the blockout inside the containment around Penetration 24 was poured, covering fielo weld #4, one of three circumferential guard pipe welds, thus making the weld inaccessible.
On August 20, 1981, an NCR was written by Ebasco Quality Assurance stating that the construction sequence did not provide for visual accessibility of Penetration 24 during the required pressure test in accordance with ASME Section III, NC-6000, 1977 Edition, Summer 1978 Addenda. Ebasco Engineering's disposition on October 7, 1981 was that the required pressure test and examination be performed in accordance with NC-6129, Winter 1978 Addenda. This subparagraph provides a means of examination for pressure testing of inaccessible welded joints in piping. Contractor 251 is not able to perform this test as his ASME Certificate of Authorization extends up to and includes the Summer 1978 Addenda. Therefore, Contractor 224 will be assigned the responsi-bility of performing the required pressure test and preparing the necessary procedures to perform the work. The Supply System will be requested by Ebasco to inform the proper regulatory and State author-ities of Ebasco's use of this later code addenda for this particular case.
The DCN will be superseded with another DCN by December 31, 1981.
This DCN will revise the outside containment guard pipe design pres-sures to 50 PSIG for all three penetrations. While 50 PSIG is a highly conservative design pressure for these guard pipes, the use of a single design pressure for the entire length of the guard pipes is consis-tent with the original design intent. This will also clarify the test requirements for the penetration assemblies.
Contractor 224 shall also perform the pressure tests of the guard pipes of Penetrations 23 and 44, where the circumferential welds are accessible in accordance with NC-6112. It is anticipated that the pressure tests will be completed by June 30, 1982.
B. Background Information For Part 2 Of The Noncompliance Several issues were addressed by this portion of the noncompliance.
They were:
- 1. The pressure testing of the process pipe welds should have been performed prior to their surfaces becoming inaccessible for exam-ination when the penetrations were completely welded up.
i Attachment to Letter G03-81-2866 Page 4 :
. Dated December 23, 1981 Corrective Actions Taken (Continued)
- 8. Background Information For Part 2 Of The Noncompliance (Continued)
- 2. The specified design pressure for process line number 2CH3-514 SA/BR for Penetration 44 is 200 PSIG. Therefore, Procedure PKS-WI-306 should require a test pressure of 250 PSIG, not 188 PSIG as stated.
- 3. Procedure PKS-WI-306 states that the pressure test of the process pipes shall be pneumatic. This is not in accordance with Paragraph NC-6112 and another PKS procedure.
Ebasco addressed these issues as follows:
- 1. It was acceptable for Engineering to use inaccessible process pipe welds in the design of these particular penetrations. The ASME BPV Code allows the use of inaccessible welds for piping intended for this service. Specifically, Subparagraph NC-6129, issued in the Winter 1978 Addenda to the ASME Section III Code allows con-struction with inaccessible welds and provides details for per-forming the required pressure tests. This subparagraph was issued in the Winter 1978 Addenda to incorporate ASME Code Case 1541.
The Code Case, entitled Hydrostatic Testing of Embedded Class 2 and Class 3 Piping for Section III, Division I construction, was first issued in 1972. The A5ME's issuance and the NRC's acceptance of this Code Case and its subsequent revisions as stated in Regu-latory Guide 1.84, reflects the industries' position on the use of and testing of embedded and inaccessible welds.
All penetrations have been studied for access requirements (i.e.,
ISI). Penetrations 23, 24, and 44 have no access requirements and therefore, may utilize inaccessible welds in their construction.
It is physically impossible to pressure test the process pipe por-tion of these three penetrations at any time prior to complete installation of the process pipe within the penetration assembly.
The original NCR, mentioned previously, was also written against the pressure testing of these process pipes. Again, Engineering's disposition was to perform the test in accordance with NC-6129.
- 2. The specified design pressure for line number 2CH3-514 SA/BR is 150 PSIG. It has always appeared as such in the line list and was corrected to 150 PSIG fr a 200 PSIG on the appropriate Drawing by a Field Change Request, dsted December 12, 1980. Therefore, the correct test pressure is shown in Procedure PKS-WI-306 as 150 x 1.25 = 188 PSIG.
- 3. The use of a pneumatic test for testing the process pipes of Pene-trations 23, 24, and 44 is wrong. The pressure test should, and
, Attachment to Letter G03-81-2866 Page 5
- Dated December 23, 1981 Corrective Actions Taken (Continued)
B. Background Information For Part 2 Of The Noncompliance (Continued)
- 3. (Continued) will be, a hydrostatic test. Engineering failed to detect this during the procedure review. As the process pipe circumferentias welds are inaccessible, they must be tested in accordance with NC-6129 which was added in the Winter 1978 Addenda. As in the previous case, Contractor 251 cannot perform this work because his ASME Certificate of Authorization extends up to and includes the Summer 1978 Addenda. Again, Contractor 224 will be assigned '
the responsibility and will be required to develop a testing proce-dure and perform the work. It is expected that the prestare tests will be completed by May 31, 1982. Procedure PKS-WI-306 Revision 3 will be revised to delete pressure testing of the process pipes by Januarj 31, 1982.
C. Summary By resolving the pressure testing difficulties associated with these three penetrations in the dispositioning of the original NCR, the ASME Code and regulatory requirements will be satisfied. With the exception of the oversight in the review of Procedure PXS-WI-306 and the lack of clarity of the DCN, the actions taken by Ebasco as described herein provide evidence of adherence to Code requirements.
D. Corrective 5teps Taken The following corrective actions have been taken to assure compliance with the applicable code:
- 1. The design pressure for the guard pipes in all three penetrations
(#23, 24 and 44) has been made uniform (50 PSIG) over their entire length. This eliminates the original dual pressure requirements for the inboard (containment boundary) and outboard (atmospheric plus 5.0 PSIG) portions of the guard pipes.
- 2. Blockouts have been provided for Weld No. 4 on Penetrations #23 and #44 to allay any concerns relative to the accessibility of these welds during internal pneumatic pressure testing of their guard pipes at 62.5 PSIG.
! 3. Contractor 224 has been designated responsibility for performing the 62.5 PSIG pneumatic test of the guard pipes and the hydrosta-tic pressure test of the process pipes of these penetrations.
Action Taken to Prevent Recurrence For WNP-3, blockouts have been established for the guard pipe field welds on Penetrations #23 and #44 to eliminate any questions relative to access '
,, Attachment to Letter G03-81-2866 Page 6
- Dated December 23, 1981 l .
l Action Taken to Prevent Recu rence (Continued) during pressure testing of these welds. These blockouts will be maintained until pneumatic testing at 62.5 PSIG has been successfully completed.
For WNP-5, blockouts for these field welds on Penetrations #23, 24 and 44 guard pipes will be maintained until successful completion of the 62.5 PSIG pneumatic tests.
A Discussion of the Reasons for Failure to Adequately Investigate and Effect Corrective Actions to Preclude This Item of Honcompliance The Mechanical Contractor (251) installed the penetration assembly and per-formed all required tests, including a 7.5 PSIG internal pneumatic test which included Weld No. 4. Weld No. 4 falls within the containment boun-dary and as such requires testing as part of the containment. This weld will not be accessible during containment leak rate testino (Over Pressure and Integrated Leak Rate); however, its integrity will be established as part of these tests. Engineering took no corrective action after the NRC expressed its concern in May over the completion of pressure testing of field weld number 4 prior to concrete encasement because no corrective action was required. Procedure PKS-WI-306 does not specify that the pres-sure test be performed prior to the weld surface becoming inaccessible because Contractor 251 does not control concrete placement. However, as part of this procedure, it is required that pressure testing of these penetrations be performed to complete the installation activity. As an area cannot be worked by more than one Contractor at a time, Ebasco was assured that the ASME code internal pressure test could be performed, which it was, prior to concrete placement. In consideration of the above, the Civil Contractor, without concurrence of Mechanical Engineering, was re-leased to place concrete inside the containment including encasing field weld No. 4. It was not realized by Civil Construction that this blockout was intended to remain open.
Date of Full Compliance Access to Weld No. 4 on Penetrations #23 and #44 has been accomplished.
Integrity of these welds on Penetrations #23, 24 and 44, and their confor-mance to Code requirements, will be established by pneumatic pressure testing planned for completion by July 30, 1982.