|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5511999-02-0404 February 1999 Forwards Copies of NRC Form 396 & 398 for Listed Individuals Who Will Be Taking NRC License Exam at WNP-2 During Week of 990308.Without Encls 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17286A2801990-08-27027 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) ML17286A2671990-08-23023 August 1990 Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors ML17286A2641990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee ML17285B4341990-08-20020 August 1990 Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators. IR 05000397/19900141990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4171990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4041990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns ML17285B3981990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys ML17285B3991990-07-27027 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs ML17285B3761990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring ML17285B3711990-07-12012 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed ML17285B3781990-07-11011 July 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur ML17285B3841990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl ML17285B3661990-07-0505 July 1990 Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager ML17285B3641990-06-29029 June 1990 Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) ML17285B3571990-06-28028 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. ML17285B3501990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed ML17285B3511990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval ML17285B3441990-06-20020 June 1990 Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead ML17285B3451990-06-19019 June 1990 Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions ML17285B3431990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 ML17285B3461990-06-15015 June 1990 Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle ML17285B3301990-06-12012 June 1990 Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty Dtd 900521 ML17285B3251990-06-0707 June 1990 Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701 ML17285B2931990-05-29029 May 1990 Responds to NRC 900426 Ltr Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons ML17285B2861990-05-22022 May 1990 Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991 ML17285B2881990-05-11011 May 1990 Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util 900329 Ltr.W/O Encl ML17285B2471990-05-0101 May 1990 Advises That No Changes to Tech Specs Required as Stated in 891130 Ltr in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS ML17285B2741990-04-26026 April 1990 Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered ML17285B2321990-04-25025 April 1990 Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-17 ML17285B2121990-04-19019 April 1990 Responds to Fire Protection Issues Identified in 900201 Notice of Violation.Corrective Actions:Major Hardware Changes Implemented & Independent Consultant Will Be Employed to Review Fire Protection Program ML17285B2221990-04-16016 April 1990 Forwards Status Rept for Commitments Made in 891130 Ltr Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed ML17285B1881990-04-11011 April 1990 Responds to NRC 900312 Ltr Re Violations Noted in Insp Rept 50-397/90-01.Corrective Actions:Complete Job & Task Analysis Completed for Health Physics Technician Training Program & New Program Will Include Training on Fundamentals ML17285B1741990-04-0505 April 1990 Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21 ML17285B1821990-04-0505 April 1990 Requests Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii) & (IV) to Allow Delayed Submittal of NRC Form-474, Simulation Facility Certification & to Administer Simulation Test as Upgraded,Respectively ML20012F6141990-04-0404 April 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML17285B2041990-03-29029 March 1990 Requests Review of Encl Topical Rept WPPSS-FTS-127,Rev 0, Qualification of Core Physics Methods for BWR Design & Analysis. Upon Rept Approval,Tech Spec Changes (Per Generic Ltr 88-16) Scheduled for Jan 1992 ML17285B1421990-03-29029 March 1990 Forwards Revised Schedule for Plant Equipment Setpoint Methodology Program Plan.Methodology Revised to Incorporate Latest ISA Std Draft.Setpoint Program Design Team for FY90 Onsite,Trained & Began Work on 900312 ML17285B1381990-03-29029 March 1990 Forwards Concluding Rept of Results Requested by Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment. Air Quality Testing Performed to Date Reveals Steadily Improving Results ML17285B1131990-03-28028 March 1990 Advises of Release of Subchannel Thermal Hydraulic Computer Code & Requests Review of VIPRE-01 Mod-02 & Issuance of SER for PWR & BWR Applications.Bwr Qualification Analyses Completed & Rept on BWR Applications Encl ML17285B1331990-03-23023 March 1990 Responds to NRC 900221 Ltr Re Violations Noted in Insp Rept 50-397/89-40.Corrective Actions:Plant Procedure 10.25.63, Emergency Lighting Insp in Process of Being Expanded to Provide Instructions & Check Sheets to Ensure Uniform Insps ML17285B1311990-03-21021 March 1990 Forwards Proposed Bases Change Re 891129 Request for Amend to Tech Spec Table 4.3.6.1, Srm/Irm Detector Not-Full-In Functional Test. Bases Change Describes Special Circumstances Re Test Exception ML17285B1291990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in LWRs & Generic Ltr 89-21 Re Status of Implementation of Usis.Tech Specs Adequate to Verify Operability of Overfill Protection Sys ML17285B1171990-03-19019 March 1990 Suppls 900102 Response Re Implementation of fitness-for-duty Program at Facility.All Items Identified as Incomplete as of 900103 Completed at End of Jan 1990 ML17285B1121990-03-15015 March 1990 Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement ML17285B0741990-03-0202 March 1990 Responds to NRC 900201 Ltr Re Violations Noted in Insp Rept 50-397/89-30.Corrective Action:Plant Personnel Currently in Process of Making Improvements to Plant Operations Procedure Writers Guide ML17285B0931990-03-0202 March 1990 Forwards Supplementary Info Re 900214 Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Address Failed Safety/Relief Valve Position Indicators ML17285B0861990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML17285B0581990-02-26026 February 1990 Forwards Washington Nuclear Plant-2 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989 & Amend 7 to Odcm. 1990-08-27
[Table view] |
Text
t REGULATORY INFORMATION DISTRIBUTION SYSTEM t (RIDS)
ACCESSION NBR:8005050293 DOCODATER 80/04/25 NOTARIZEDR YES DOCKET FACIL;50 397 HPPSS Nuclear Projectg Unit 2P Hashington Public Powe 05000397 50 460 HPPSS Nuclear Projecti Unit ii Washington Public Powe 05000060 50 513 WPPSS Nuclear Projecti Unit 4P Hashington Public Powe 05000513 AUTH INANE,. AUTHOR AFFILIATION RENBERGERPD ~ LE Nashington Public PoWer Supply System RECIPRNAME RECIPIENT AFFILIATION SELLSPD,E, Environmental Projects Branch 2
SUBJECT:
Forwards responses to 800307 hydrologic engineering questions re waste treatment sysito assist NRC environ review of Unit 2.Affidavit encl.
DISTRIBUTION CODE: ROOTS COPIES RECEIVED:LTR i ENCI. i SIZE:
TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES: ~ eW~WWSOeaMM lS RECIPIENT t $ OP IES RECIPIENT COPIES ID CODE/NAMES f LTTR ENCL ID, CODE/NAME LTTR ENCL
'CTION: 05 PM%'. gEHC.ASKS 1 AD WODGE 1 0 BC EBB +g 1 0 LA 8'~B¹~ 1 0
'NTERNAL: 01 EG FILE 1 1 02 NRC PDR 1 1 06 I 3 3 08 OPERA LIC BR 1 1 09 GEOSCIEN BR 10 QAB 1 1 1 1 MECH ENG BR 1 12 STRUC ENG BR 1 1 13 NATL ENG BR . ? 2 15 REAC SYS BR 1 1 16 ANALYSIS BR 1 17 CORE PERF BR 1 1 18 AUX SYS BR 1 1 19 CONTAIN SYS 1 1 20 I 8 C SYS BR 1 1. 21 PONER SYS BR 1 1 22 AD SITE TECH 0 26 ACCDNT ANLYS 1 1 27 EFFL TRT SYS 1 1 28 RAD ASMT BR 1 '1 29 KIRKHOOD 1 1 AD FOR ENG 1 0 AD PLANT SYS 1 0 AD REAC SAFETY 1 0 AD SITE ANLYSIS 1 0 DIRECTOR NRR 1 0 HYDRO<<METEOR BR 2 2 MPA 1 0 OELD 1 0 EXTERNAL: 03 LPDR 1 1 04 NSIC 30 ACRS 10 10 aS /E.Cup C.u)4,4 g 8Q, l.&A 3 8l"-
++@// QDCLRAIII L.Ldg ~ g gg
/ gal+ ~ Scd
~g v $$
TOTAL NUMBER OF COPIES REQUIRED: LTTR ~ ENCL
CI 1
II
NIISo5o g g Washington Public Power Supply System A JOINT OPERATING AGENCY P. O. BOX 958 3000 GEO. WASHINCTON WAY RICHLAND, WASHINCTON 99352 PHONE (509) 375 5000 April 25, 1980 G01-80-123 Docket Nos. 50-397 50-460 50-513 Mr. Donald E. Sells, Acting Chief Environmental Projects, Branch 2 Division of Site Safety and Environmental Analysis United States Nuclear Regulatory Agency Washington, D.C. 20555
Dear Mr. Sells:
Subject:
WPPSS NUCLEAR PROJECTS NOS. 1, 2 AND 4 HYDROLOGIC ENGINEERING UESTIONS
Reference:
GI2-80-49, letter, D. E. Sells to D. L. Renberger, Dated March 7, 1980 Attached are the responses to your hydrologic engineering questions with respect to the proposed waste treatment system for the WPPSS 1, 2, and 4 plants. We trust that this will provide you with the required information for your environmental review of WPPSS 2.
Very truly yours, D. L. Renberger Asistant Director, Technology DLR:ACR mch Attachments cc: Nick Reynolds, Debevoise 8 Liberman
$g5001 (h
l k,c~T STATE'F'WASHINGTON)
) ss PPSS NUCLEAR PROJECTS, NOS. l, 2 AND $
HYDROLOGIC ENGINEERING QUESTIONS COUNTY OF BENTON D. L. RENBERGER, Being first duly sworn, deposes and says: That he is the Assistant Director, Technology, 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 r~ l g2, lgGG D. L. RENBERGER On this day personally appeared before me D. L. RENBERGER to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIYEN under my hand and seal this ~g nc day of , 1980 ota y Publsc in and for t State of Washington Residing at
I
+~
~ S I
C1 e
Eg a Eg), 1
'pgq yy ~
ATTACHMENT A HYDROLOGIC ENGINEERING QUESTIONS WPPSS-2 AND 1/4 SEWAGE TREATMENT FACILITY
- 1. PRIMARY LAGOON guestion:
Provide additional information regarding the liner that will be used to prevent seepage from the primary lagoon. This information should include liner permeability, liner strength, and durability construction techniques, and bases for the values reported.
Response
The liner which will be used to prevent seepage in both the primary (aerated) ponds and the secondary (stabilization) ponds will be a 20-mil polyvinyl chloride (PYC) membrane. It will be installed over a prepared subgrade, then covered with 12 inches of native material for sunlight and tear protection.
The liner itself is virtually impermeable to the passage of water.
Minor leaks along seams and through small tears and pinholes are, of course, unavoidable. The specifications call for the contractor to field test the completed ponds for leakage. The maximum allow-able leakage during this field test will be 1/4-inch per day.
The strength and durability characteristics of the liner are listed on attachment B. Construction techniques are shown on attachment C.
- 2. SECONDARY LAGOON guestion:
Provide the basis for your estimate of 1/4-inch per day of seepage from the secondary lagoon. Discuss the treatment of the lagoon sides and bottom that will be used to achieve this seepage limit.
Document that buildup of salts and other solids on the bottom of the secondary lagoon will not adversely affect the quality or quantity of the seepage from this pond.
Page Two HYDROLOGIC (UESTIONS AND RESPONSES
Response
The 1/4-inch per day rate is not an estimate of the leakage rate from the secondary (stabilization) ponds; it is the maximum allow-able by Washington State Standards. The actual leakage rate will be much lower than this. Rather than use a bentonite liner, it has been decided that a PVC liner will be used in the secondary ponds.
This liner will be identical to the type used in the primary ponds.
Our experience has shown that the leakage through this type of liner is virtually undetectable if proper construction procedures are followed. The organic sludge which will build up on the pond bottom will have a tendency to seal the bottom and reduce leakage through any small holes or tears in the liner. The chemical character-istics (salts) of any seepage through the sludge will be essentially the same as in the wastewater overlying the sludge blanket; a semipermeable membrane (similar to those used in reverse osmosis units) between the sludge and wastewater would be necessary for them to develop dissimilar chemical characteristics. The problem to which you refer with heavy metals and salts buildup in sludges is associated with mechanical treatment plants. In these plants, the sludge is separated from the main wastewater stream; digesting and dewatering increases the chemical concentrations. This problem does not occur with lagoon systems.
- 3. OVERFLOW LAGOON guestion:
Document the design bases for overflow into the third lagoon due to intense rainfall. Discuss the frequency of- rainfall that will be contained and the methods of computation of the required storage volume.
Response
Rainfall is not ordinarily considered as a design parameter for the flow patterns within lagoon systems. There are two reasons for this:
a) The normal variations in pond depth far exceed any rainfall considerations. The secondary ponds are designed to have a depth varying between three and five feet. This is accomplished with an adjustable outlet weir. The ponds and piping between them have been designed to handle a one-foot variation in depth (i.e., a drop from five-foot level to four-foot level or 1.5 million gallons) within a 24-hour span. The one percent storm will yield a 24-hour precipitation event of only about 2.4 inches, or 300,000 gallons well within the design capacity.
Page Three HYDROLOGIC QUESTIONS AND RESPONSES b} All lagoons within the plant are designed with three feet of freeboard above normal maximum water levels. The 2.4-inch increase in level caused by the one percent storm wi 11 be safely contained within the freeboard.
ALL THREE PONDS Question:
Provide responses to the following generic questions.
a) Provide descriptions of the floodplains of all water bodies, including intermittent water courses within or adjacent to the site. On a suitable scale map provide delineations of those areas that will be flooded during the one-percent chance flood in the absence of plant effects (i.e., pre-construction floodplain).
Response
The flood history of the Hanford Reach of the Columbia River is discussed in Section 2.4 of the WNP-2 FSAR. The derivation of critical flood elevation and the references utilized are reported therein. The Standard Project Flood (SPF) has been defined by the Army Corps of Engineers as 570,000 cfs, which represents a 367 ft. MSL elevation at the WNP-2 intake. The makeup water pumphouse operating floor elevation is 375 ft.
MSL. The lowest elevation of the Sanitary Waste Disposal System is 414 ft. MSL at the percolation beds. The one-percent flood represents 650,000 cfs and 370 ft. MSL elevation at the WNP-2 intake (please see Attachments D and E, which are respectively, Figure 2.4-3 of the WNP-2 ER-OL and Figure 2.4-14 of the WNP-2 FSAR). Attachment F shows the topographic detail of the site vicinity.
b) Provide details of the methods used to determine the flood-plains in response to a) above. Include your assumptions of and bases for the pertinent parameters used in the computation of the one-percent flood flow and water elevation. If studies approved by Flood Insurance Administration (FIA), Housing and Urban Development (HUD) or the Corps of Engineers and avail-able for the site or adjoining area, the details of analyses need not be supplied. You can instead provide the reports from which you obtained the floodplain information.
Response
Please see response at conclusion of generic question g).
.~
~ J k
Page Foun;,
HYDROLOGIC QUESTIONS QND RESPONSES c) Identify, locate on a map, and describe.. all structures, con-struction activities and topographic alterations in the flood-plains. Indicate the status of each such structure, con-struction activity and topographic alteration (in terms of star t and completion dates) and work presently completed.
Response
Please see response at conclusion of generic question g).
Discuss the hydrologic effects of all items identified in c) above. Discuss the potential for altered flood flows and levels, both upstream and downstream. Include the potential effect of debris accumulating on the plant structures. Addition-ally, discuss the effects of debris generated from the site on downstream facilities.
Response
Please see response at conclusion of generic question g).
e) Provide the details of your analysis used in response to d) above. The level of detail is similar to that identified in the item b) above.
Response
Please see response at conclusion of generic question g).
Identify non-floodplain alternatives for each of the items (structures, construction activities and topographic alter-natives) Identified in e) above. Alternately, justify why a specific item must be in the floodplain.
Response
Please see response at conclusion of generic question g).
g) For each item in f) above that cannot be justified as having to be in the floodplain either show that all non-floodplain alternatives are not practicable or commit to relocating the structure, construction activity or topographic alteration out of the floodplain.
Response to b), c), d), e), f), and g):
Attachment G shows the contours of the WNP 1, 2, and 4 plant vicinities. The Sanitary Waste Disposal System is located at coordinates N10,000, WOOO. As may also be seen in Attachment G, no other facilities are located within the designated one-percent or SPF floodplains.
mch
ATTACHMENT B
~Pro ert ~Re uired Test Method Thickness, mils 20 +/-1.0 ASTM D 882 Specific gravity 1.2 - 1.3 Elongation, X min. 3001e ASTM D 882, Method B Tensile strength, psi, 2, 200 ASTM D 882, Method B min.
100K modulus, psi 1,000 - 1,600 ASTM D 882, Method B Elmendorf tear resistance 160 each direction, gms/mil, min.
Graves tear, lbs/in, min. 2/0 ASTM D 1004 Water extraction, X loss 0.35 ASTM D 1239 Volatility, 5 loss 0.7 ASTM D 1203 Low temperature impact Not more than 'ASTM D 1790 0 deg. +3.6 deg. F two specimens of 10 shall fail Dimensional stability X ASTM D 1790 (100 deg. C - 15 min.)
Outdoor exposure, sun hrs. 1,500 Bonded factory seam strength 80 ASTM D 882 each direction, min. 5 tensile strength Pinholes/10 sq. yds. max.
Resistance to soil burial- USBR test for soil tensile strength loss, each burial direction X max.
Elongation loss, each 20 direction 5 max.
Alkali resistance Pass Corps of Engineers CRD 572-61
/2 d 'CRL/SHEO GRAVEL SL/Ri ACINS 9 EROSION PRO7EC77OIV
/2'SELEC7 IVAT/VE SL/RELACE
//L.L "m SO/L
~/
C I=- I-
<<II=- ill)=~'i EXS7 GEOL/h!0 ANCHOR eVC I I= l
)IIVIIII EXS7 SROL/A/O.
7'" //NER'r'/p ZO A/L;- PVC
~ ~
II= IIII=llll=-
IIII==IIII SL/REAL .
AO7 70 SU)LE 6/h/ER'IGURE 6A WPPSS LAGOON TREATMENT FAClLmES R}CHLAND WASHlNGTON CH2M S /3+6/AO am HILL
~
~
ATTACHMENT D EXCEEDENCE FREQUENCY PER HUNDRED YEARS 99.8,99.5 99 95 90 80 50 20 10 5 2 5 C 0OtdVt" 1000 mfn f MO O M 500 0 6C rt 8 M Q Q C) ted& tD C)
PERIOD: 1913-1965 1970 CONDITIONS 200 le
'0 td Cl QPC td X td R 10@
OMA Zt0
'dZO gMC H
MOW 0
H A
o bD H
UC5R MQC UCV P
L 3.'NZ EXCEEDENCE 10 '0 INTERVAL, YEARS 509 slh I HO LJ PZ PXR
l I'1 l
'/l
ct3 0- ~ ~
42o ATTACHMENT E 4IO X
00 400 S
~ 395
~ 380 z
< 870 t
~ 3&0 l 948 BLOOD lee< FLOOD p~ ppeu ATEc 5 8 10 2 4 8 l0 FLOW CFS ~ ~
WASHINGTON PUBLIC POWER SUPPLY SYSTEM FLOW RATING CURVE FOR COLUMBIA RIVER, FIGURE RIVER MILE 350 NUCLEAR PROJECT NO. 2 2. 4-1(
II I.M / A 4 -7 ~ 4.=,,i' ~
lt / ~
.); )
0 0 '-'s';i:-'=>E'gl ATI'ACHRG-
E4 PI-a C /
\ C I
l~ I
/ ~~~ 4 7 4 aa .I
~ di QP 3
,) -~
~
ss vO Gs I g c
I II / ssss u4
/
/ I /
'8 / Brass ID 0
o I I
Q e
~C -Well 1
- Z g D
,:."77 st/4',
",;:44/
WC'I O
ul
's I I
. L WNP-,I 4 PUMP OUSE 7,
i 've Waste I WNP-2 I 400~ 4/ ul f' I. 4 I, I (I ?,'oo-va rxooD I>g I O r
~g'~y 7 i;a HIGH WATER LQK 44 I
' . WNP PUMP HOUSE Vr Pi 0, o 70
/
'4 0
>>ec
=
'I.- 4 I
g'8
~ p~~SED 14ETEEATEE D --", -s.
7 4
TEE/4SSEET PLIE/p g I
- 6 O s ~
o ell I 4g// /
'Q 4 A I
'/i 0 @00 I
. '<<7" I
/
/
R /
/ d
~ os o O s <7G 47 a+
res
/
C7 q 4y"QSubstatIII::.'<4~.
/
"~':!'-.'.7 'j,-'4
~k', 4sf 7
l2 L~'3~4
/
go>, '::c( I Qr' 47,0W I s po"'c o a~
jg .
-ao I "44 ~
o 0 O,', O
/
I= n w~ j:,
-,':O.-:.:,
4 SCALE 1:24000 Ct 0 1 MILE I~P.:..: -I 1000 0 1000 2000 3000 4000 5000 6000 7000 FEET D I ss
- 0. 0 /7 1 KILOMETER
};0-'-'
o 4",
Q f s77 CONTOUR INTERVAL 10 FEET 43C7 OD NATIONAL GEODETIC.VERTICAL DATUM OF 1929 K=M'~.III
.'*t
~h .~ Welt E 4 Test 0~ w, A~mM~ ~n "J
~ ~ ~
ATTACHMENT G Amendment No. 5 August 1979 N20,000 4(0 420 430 430 N15, 000 430 440 WNP-4 460 430 WNP-2 WNP-1 N10, 000 cP 420 440 430
'440 4 30 420 420 OP 0
CD UJ WASHINGTON PUBLIC POWER SUPPLY SYSTEM FIGURE DETAILED CONTOURS NEAR THE SITE
,'NUCLEAR PROJECT NO. 2 2.4-10
g g ji-~
N
~ ~
Pg M
I i f l",'