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| Chemical contaminants which could cause stress corrossion in the strap material are sea water, aqueous solutions containing chloride, and hy-drogen sulfide solutions. These clamps are designed for plant ambient conditions. The environment in the containment during a LOCA will have a boric acid concentration of 4,400 ppm and sodium hydroxide with pH of 8 1/2 to 11. These concentrations will not affect the strap material. | | Chemical contaminants which could cause stress corrossion in the strap material are sea water, aqueous solutions containing chloride, and hy-drogen sulfide solutions. These clamps are designed for plant ambient conditions. The environment in the containment during a LOCA will have a boric acid concentration of 4,400 ppm and sodium hydroxide with pH of 8 1/2 to 11. These concentrations will not affect the strap material. |
| No appreciable concentrations of chlorides have been identified. In the absence of a corrosive environment stress corrosion induced cracking cannot by definition occur. | | No appreciable concentrations of chlorides have been identified. In the absence of a corrosive environment stress corrosion induced cracking cannot by definition occur. |
| : 15) The response to Question #2 in your July 30, 1982 letter needs further clarification. Provide clarification of what the correlation between a pressure stress of 15,000 psi and a temperature increase of 17*F is in-tended to indicate. | | : 15) The response to Question #2 in your {{letter dated|date=July 30, 1982|text=July 30, 1982 letter}} needs further clarification. Provide clarification of what the correlation between a pressure stress of 15,000 psi and a temperature increase of 17*F is in-tended to indicate. |
| ANSWER The 17*F indicated in the original. response to Question #2 was incor-rect The radial deflection of pipe due to an internal pressure of 15,Gv0 psi is the same deflection which would occur if the pipe temper-ature was increased by 53*F. This was intended to indicate the rela-tively insignificant effect of high internal pressure. | | ANSWER The 17*F indicated in the original. response to Question #2 was incor-rect The radial deflection of pipe due to an internal pressure of 15,Gv0 psi is the same deflection which would occur if the pipe temper-ature was increased by 53*F. This was intended to indicate the rela-tively insignificant effect of high internal pressure. |
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| : 17) The response to Question #4 in your July 30, 1982 letter is not accept-able. Bolt torque is a poor indication of belt tension and a poor indi-cation of strap tension unless the friction is controlled both in the bolt and in the strap. Provide the measurements that will be taken to assure that the strap tension required for proper clamp stiffness is adequately applied without causing undue stresses in the piping. | | : 17) The response to Question #4 in your {{letter dated|date=July 30, 1982|text=July 30, 1982 letter}} is not accept-able. Bolt torque is a poor indication of belt tension and a poor indi-cation of strap tension unless the friction is controlled both in the bolt and in the strap. Provide the measurements that will be taken to assure that the strap tension required for proper clamp stiffness is adequately applied without causing undue stresses in the piping. |
| ANSWER The load rating procedure as defined by the NF Code does not address the specific stresses that are incurred by the component under load. The load rating of the component to satisfy particular operating conditions is based on the applied load at which the component fails to perform its required function multiplied by the ratio of allowable stress at temper-ature to the specified minimum tensile strength of the support material. | | ANSWER The load rating procedure as defined by the NF Code does not address the specific stresses that are incurred by the component under load. The load rating of the component to satisfy particular operating conditions is based on the applied load at which the component fails to perform its required function multiplied by the ratio of allowable stress at temper-ature to the specified minimum tensile strength of the support material. |
| In the stiff clamp, when the applied torque and the applied load are be-low those at which the clamp was rated there is no reason to determine stress levels in the component. The proper application of torque to es-tablish pretension is an industry acceptable method. The torque values that will be specified will prevent lift-off of the clamp from the pipe at the specified emergency load rating of the component, and will resist lif t-off up to a load 10% greater than the emergency load when the pip-ing temperature is at the ambient temperature level. (Note: when the piping is at an elevated temperature, the lift-off load will increase due to the increased tension in the straps), as long as lift-off has not occurred proper clamp stiffness is assured. The torque value to arrive at the lift-off load will be obtained from tests. Pipe stresses under torque and emergency load conditions will be determined by test and will be combined with all existing stresses to assure compliance with code allowables. | | In the stiff clamp, when the applied torque and the applied load are be-low those at which the clamp was rated there is no reason to determine stress levels in the component. The proper application of torque to es-tablish pretension is an industry acceptable method. The torque values that will be specified will prevent lift-off of the clamp from the pipe at the specified emergency load rating of the component, and will resist lif t-off up to a load 10% greater than the emergency load when the pip-ing temperature is at the ambient temperature level. (Note: when the piping is at an elevated temperature, the lift-off load will increase due to the increased tension in the straps), as long as lift-off has not occurred proper clamp stiffness is assured. The torque value to arrive at the lift-off load will be obtained from tests. Pipe stresses under torque and emergency load conditions will be determined by test and will be combined with all existing stresses to assure compliance with code allowables. |
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| : 19) The response to Question #8 in your November 11, 1982 letter is not ade-quate. The strap preload relaxation was tested under thermal conditions j by placing the pipe and clamp assembly in an oven and thermally cycled j the assembly ten times. The test does not simulate the actual operating i condition where the pipe will expand thermally before the clamp due to the temperature gradient caused by the internal pipe temperature. The applicant should provide the basis for assuring that the preload relaxa-tion due to thermal and pressure cycling of the pipe will not occur. | | : 19) The response to Question #8 in your {{letter dated|date=November 11, 1982|text=November 11, 1982 letter}} is not ade-quate. The strap preload relaxation was tested under thermal conditions j by placing the pipe and clamp assembly in an oven and thermally cycled j the assembly ten times. The test does not simulate the actual operating i condition where the pipe will expand thermally before the clamp due to the temperature gradient caused by the internal pipe temperature. The applicant should provide the basis for assuring that the preload relaxa-tion due to thermal and pressure cycling of the pipe will not occur. |
| ANSWER l The testing performed in response to the original question, (see Attach-ment), was a test designed to test the effects of pressure and temper-ature cycling on the preload on the straps, not its effects on piping stresses. Piping stresses will be determined from the test program dis-cussed in the response to Questions #2 and #16. There was sufficient conservatism in the test program to indeed prove that the straps would | | ANSWER l The testing performed in response to the original question, (see Attach-ment), was a test designed to test the effects of pressure and temper-ature cycling on the preload on the straps, not its effects on piping stresses. Piping stresses will be determined from the test program dis-cussed in the response to Questions #2 and #16. There was sufficient conservatism in the test program to indeed prove that the straps would |
| . not relax. For example, the testing was done on a heavy wall stainless steel pipe and at a temperature of 650 degrees F. The Load Capacity Data Sheet for this cla.np limits the use of this clamp to 350 F for use 1 with stainless steel piping. Due to the thinness of the straps in con- | | . not relax. For example, the testing was done on a heavy wall stainless steel pipe and at a temperature of 650 degrees F. The Load Capacity Data Sheet for this cla.np limits the use of this clamp to 350 F for use 1 with stainless steel piping. Due to the thinness of the straps in con- |
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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 Docket 50-508 June 15, 1983 G03-83-476 Director of Nuclear Reactor Regulation Attn: Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
NUCLEAR PROJECT 3 RESPONSES TO NRC QUESTIONS ON PIPE CLAMPS
Reference:
a) Letter G. W. Knighton to R. L. Ferguson, dated 04/04/83.
b) Letter #G03-83-384, G. D. Bouchey to G. W. Knighton, dated 05/05/83.
Reference a) transmitted to the Supply System a set of seven requests for additional information regarding the useage of ITT Grinnell pipe clamps at WNP-3. Reference b) committed the Supply System to respond to Reference a) by June 1983.
Responses to these questions are included as attachments to this letter.
Should you have any questicns or desire further clarification, the Supply System point of contact for this matter is Mr. K. W. Cook, Licensing Project Manager (206/482-4428, ext. 5436).
Sincerely, M99du C G. D. Bouchey, Manager Nuclear Safety and Licensing AJM/ss cc: J. A. Adams - NESCO PO Ebasco - Elma D. Smithpeter - BPA J ll l WNP-3 Files - Richland i )
D. J. Chin - Ebasco '
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8307060255 830615 PDR ADOCK 05000508 A PDR i J
ATTACHMENT Responses to NRC Questions 210.14 through 20.
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- 14) Your response to Question #1 in your letter from G. D. Bouchey to F. J. Miraglia dated July 30, 1982 is not acceptable. Code Case N-249 states that the maximum measured UTS of " Component support materials should not exceed 170 ksi in view of the susceptibility of highstrength materials to brittleness and stress corrosion cracking". Under those conditions the Code Case recommends that:
(1) the impact test results for the material meet Code requirements, and (2) the material is not subject to stress corrosion cracking by virtue of the fact that (a) a corrosive environment is not present, and (b) the component that contains the material has essentially no residual or assembly stress and it does not experience fre-quent substantial loads in service.
Provide additional information to address the above two concerns if the maximum UTS of the clamp strap material exceeds 170 ksi.
ANSWER Table 1-7-1 of the code indicates that the subject strap material has a reduction in toughness at room temperature after exposure for about 5,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to temperatures at 600*F and after shorter exposure above 650 F. In 98% of the WNP-3 applications the operating temperature is less than 500*F. Therefore, in the case of these applications, the material should not be susceptable to brittle fracture. The remairiing 2% of the clamp applications will be reviewed on a case by case basis.
In those instances where this cannot be tolerated the design of the sup-port will be changed.
Code Case N-249 also includes cautionary notes on the use of materials where the UTS exceeds 170 ksi. It requires impact testing of such ma-terials as a condition. In the application of the strap material, how-ever, the impact test is not required because of its thinness. NF Code Paragraph NF-2311, Component Supports for Which Impact Testing of Mate-rial is required, specifically excludes the impact testing o' materials with a nominal section thickness of 5/8 inch or less.
Chemical contaminants which could cause stress corrossion in the strap material are sea water, aqueous solutions containing chloride, and hy-drogen sulfide solutions. These clamps are designed for plant ambient conditions. The environment in the containment during a LOCA will have a boric acid concentration of 4,400 ppm and sodium hydroxide with pH of 8 1/2 to 11. These concentrations will not affect the strap material.
No appreciable concentrations of chlorides have been identified. In the absence of a corrosive environment stress corrosion induced cracking cannot by definition occur.
- 15) The response to Question #2 in your July 30, 1982 letter needs further clarification. Provide clarification of what the correlation between a pressure stress of 15,000 psi and a temperature increase of 17*F is in-tended to indicate.
ANSWER The 17*F indicated in the original. response to Question #2 was incor-rect The radial deflection of pipe due to an internal pressure of 15,Gv0 psi is the same deflection which would occur if the pipe temper-ature was increased by 53*F. This was intended to indicate the rela-tively insignificant effect of high internal pressure.
E____________
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- 16) In your letter fron. G. D. Bouchey to G. Knighton dated February 25, 1983, a response was provided to address the test program which was intended to determine the clamp-induced stresses in the piping. Your response indi-cates that the clamp preload "resulted in too wide a load range" being en-veloped due to the degree of simplicity in the test procedures.
(a) Provide a summary of the test results to date and the impact it has on the piping and clamps already installed at the WNP-3 facility.
(b) Provide justification that the test torque preload applied to the clamps on representative pipe sizes will determine the limiting pipe conditions for clamp application.
(c) Provide a clarification of the test to be performed on the tensile test machine and assurance that the strain gauges will record the maximum stress locations due to the total combined stresses from both torquing and bending modes.
(d) Provide the test report when complete.
ANSWER a) Test results to date indicate that for at least some cases clamp induced stresses are excessive. Minor clamp design modifications are being exam-Ined to increase the pipe to yoke contact area to improve load distribution thereby reducing stresses. Some clamps have been installed. These will be retorqued when the proper torque has been established.
b) The testing of the clamps was not done for one specific value of torque but rather for a series of incremental values of torque. Lift-off loads and pipe wall stresses were obtained at each step. The relationship between torque and lift-off load was proven to be a linear one. This relationship will be used to derive the final torque values as a function of the actual loads. Based on the test results, a conservative relationship between torque and pipe induced stresses will be derived and used to show compli-ance with the pipe code equations.
c) The stresses due to the " Bending Mode" will be obtained from the regular piping stress analysis. The local effects due to the interaction between clamp and pipe wall be determined by tests by measuring the stresses due to pretorque and stresses due to pretorque & applied load.
The test procedure is as follows: 1) The clamp / pipe assembly is placed in a dynamometer, pretorqued in incremental steps and for each step the lift-off load is determined. 2) The clamp is then untorqued and pretorqued again, also in steps and at each step an external load equal to the corre-sponding lift-off load is applied in both directions (tension and compres-sion). Strain measurements are taken at each step for the cases of torque alone, torque & applied load (tension) and torque & applied load (compres-sion). The stresses due to both effects (bending mode & local effects) at each restraint point will be combined and evaluated against the appropriate code allowables.
d) Test results will be provided when complete.
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- 17) The response to Question #4 in your July 30, 1982 letter is not accept-able. Bolt torque is a poor indication of belt tension and a poor indi-cation of strap tension unless the friction is controlled both in the bolt and in the strap. Provide the measurements that will be taken to assure that the strap tension required for proper clamp stiffness is adequately applied without causing undue stresses in the piping.
ANSWER The load rating procedure as defined by the NF Code does not address the specific stresses that are incurred by the component under load. The load rating of the component to satisfy particular operating conditions is based on the applied load at which the component fails to perform its required function multiplied by the ratio of allowable stress at temper-ature to the specified minimum tensile strength of the support material.
In the stiff clamp, when the applied torque and the applied load are be-low those at which the clamp was rated there is no reason to determine stress levels in the component. The proper application of torque to es-tablish pretension is an industry acceptable method. The torque values that will be specified will prevent lift-off of the clamp from the pipe at the specified emergency load rating of the component, and will resist lif t-off up to a load 10% greater than the emergency load when the pip-ing temperature is at the ambient temperature level. (Note: when the piping is at an elevated temperature, the lift-off load will increase due to the increased tension in the straps), as long as lift-off has not occurred proper clamp stiffness is assured. The torque value to arrive at the lift-off load will be obtained from tests. Pipe stresses under torque and emergency load conditions will be determined by test and will be combined with all existing stresses to assure compliance with code allowables.
- 18) The clamp preload is required to achieve adequate clamp stiffness values to prevent the clamp from lifting off the piping during dynamic loadings.
(a) Provide the basis for assuring that the required torque preload will not relax during the lifetime of the plant.
(b) Provide preload measures that will be taken to assure that the re-
! quired preload is clearly marked or identifiable for each clamp to prevent undertorquing or overtorquing the clamp at any time after installation.
ANSWER (a) A torqued clamp was checked after a period of a month and no re-laxation was evident. In the temperature test, a check after ten i
cycles did not indicate any reduction in torque. The margin of torque to assure no lift-off is ten percent over the maximum rated load of the stiff clamp component.
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(b) Site Installation Constructor's have a program to assure that all
' field work during and after installation are controlled such that there are no physical modifications without a Contractor Engineer-ing approved work package (or traveler) which includes procedures listing the appropriate torque settings by Stiff Clamp Frame and Pipe size. The Stiff Clamp itself is provided with a metal tag
- which denotes the following
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... Frame Size
... Component to be used with the Strut or Snubber, and Component Size i ... Pipe Size
... Support Mark Number In addition, following the final torque setting the stiff clamp studs and nuts will be marked. This measure will allow a quick i visual inspection to determine if the position of the nuts and studs have been altered.
The control provided during and subsequent to installation, and the '
marking of the studs and nuts after torquing, provides the necessary measures to prevent over or under torquing.
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- 19) The response to Question #8 in your November 11, 1982 letter is not ade-quate. The strap preload relaxation was tested under thermal conditions j by placing the pipe and clamp assembly in an oven and thermally cycled j the assembly ten times. The test does not simulate the actual operating i condition where the pipe will expand thermally before the clamp due to the temperature gradient caused by the internal pipe temperature. The applicant should provide the basis for assuring that the preload relaxa-tion due to thermal and pressure cycling of the pipe will not occur.
ANSWER l The testing performed in response to the original question, (see Attach-ment), was a test designed to test the effects of pressure and temper-ature cycling on the preload on the straps, not its effects on piping stresses. Piping stresses will be determined from the test program dis-cussed in the response to Questions #2 and #16. There was sufficient conservatism in the test program to indeed prove that the straps would
. not relax. For example, the testing was done on a heavy wall stainless steel pipe and at a temperature of 650 degrees F. The Load Capacity Data Sheet for this cla.np limits the use of this clamp to 350 F for use 1 with stainless steel piping. Due to the thinness of the straps in con-
! tact with the pipe the differential temperature effects will be mini-mal. A copy of the test report is provided as an Attachment to this 9
response.
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20)_ Provide the basis for assuring that the clamp yoke will not cause exces-sive local . stresses in the piping during dynamic load application.
ANSWER Clamps are selected to assure that the applied load will not exceed the maximum rated load of the component. The induced stresses due to that load, applied in tension and compression, will be combined with the pipe bending stresses to assure that code allowables have been satisfied.
This is true regardless of whether the total applied load is dynamic, static or a combination of each.
.