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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 ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML20012B6941990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 1999-05-05
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML19327A8691989-09-0707 September 1989 Submits Info Re Alchemie & Anderson County Bank Financing Transaction ML19332F2171989-07-10010 July 1989 FOIA Request for Documents Re Communications Between Ofcs of Edo,Deputy Edo,Ofc of Director,Regional Administrators & Commissioners Ofcs Re Plants During period,890301-0615 ML20246F1311989-06-26026 June 1989 FOIA Request for Minutes of Meeting Ref in 820210 Memo from NRR Re Design & Const Assurance for Upcoming OL Cases ML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20245C1421989-04-0303 April 1989 Forwards Endorsements 75,108,108,96 & 110 to Maelu Policies MF-56,MF-26,MF-58,MF-39 & MF-52,respectively & Endorsements 93,129,127,109 & 122 to Nelia Policies NF-186,NF-76,NF-188, NF-151 & NF-173,respectively ML20247N1551989-03-31031 March 1989 Forwards Revised Proprietary Conformance of HPCS Div to NUMARC 87-00 Alternate AC Criteria, for Review as Result of Comments from 890216 Meeting.Rept Withheld ML20246M7331989-03-15015 March 1989 Responds to NRC Info Notice 88-082, Torus Shells W/ Corrosion & Degraded Coatings in BWR Containments. Summary of Relevant Projects for Various Utils Successfully Employing Underwater Alternative to Draining Vessel Encl ML20246N1281989-02-27027 February 1989 FOIA Request for Jl Smith to NRC Re Spent Fuel Shipment from Brunswick Nuclear Power Station to Harris Plant ML17285A2351989-02-0606 February 1989 Forwards Proprietary Draft Conformance of HPCS Div to NUMARC 87-00 App B Aac Criteria, for 890214 Meeting ML17285A2341989-01-0606 January 1989 Discusses Issues Highlighted at BWR/6 Alternate Ac Task Force Meeting on 881115,including Need for Capability of Div III Sys to Maintain Plant in Safe Shutdown Condition (Hot Shutdown) for Min of 4 H ML20206H0511988-11-14014 November 1988 Urges Relicensing of Pilgrim & Expedited Operation of Seabrook.Newspaper Clipping Encl ML20150D5721988-03-0808 March 1988 Provides Summary of Utils Test Results & Calculations on Emergency Diesel Generators,Including Review of Design of Static Exciter & Voltage Regulator for Emergency Diesel Generators ML20196C1591988-02-0303 February 1988 Forwards Monthly Progress Rept P-C6177-5, Independent Analysis & Assessment, for Period Ending 880131 ML20147G0741988-01-18018 January 1988 FOIA Request for All Documents Re NRC Investigation of Wg Dick Allegations About S&W & Lilco Re Performing NRC Instructions to Bring Facility Up to Fuel Load Stds ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20237B8051987-11-25025 November 1987 FOIA Request That Encls to Listed Documents,Including NRC Forwarding Amend 1 to License NPF-73,be Placed in PDR ML20236S4291987-10-20020 October 1987 FOIA Request for Listed Documents,Including Encls from NRC Requesting Addl Info on Gpu Topical Repts TR-033 & TR-040 & Encl to NRC Meeting Summary Re SPDS ML20236U5221987-10-19019 October 1987 FOIA Request for LERs for Listed Plants,Including All Attachments & Encls from Original Documents ML20235V1321987-08-28028 August 1987 Forwards EGG-NTA-7471, Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28.... Based on Licensee Responses,Plants Reviewed Conform W/Exceptions Listed in Section 14 ML17342A7741987-07-13013 July 1987 Forwards Technical Evaluation of Rept, Retran Code: Transient Analysis Model Qualification, Dtd Jul 1985. Criteria for Use of Single & Two Loop Plant Models Listed. NRC Audit of Util QA Procedure Recommended ML20235K8731987-07-0909 July 1987 Informs That Tayloe Assoc Cannot Produce Mag or nine-track Tapes of Hearing Transcripts Until NRC Finalizes Arrangements W/Others to Provide Lexis Format,Including Library & File Numbers & Segmentation Info ML20237J2141987-07-0202 July 1987 FOIA Request for Listed Documents Ref in NUREG-1150 & Related Contractor Repts ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls 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 ML18052B1911987-06-17017 June 1987 Forwards EGG-NTA-7720, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Calvert Cliffs-1 & -2,Millstone-2 & Palisades, Final Informal Rept. Plants Conform to Generic Ltr Item ML20234B6211987-05-12012 May 1987 Requests That Listed Plants Be Added to Encl 870508 FOIA Request Re 94300 Region Input on Plant Readiness ML20234B6571987-05-0808 May 1987 FOIA Request for Placement,In Pdr,Region Input to NRC Headquarters,Nrr Re Status of Listed Plants in Terms of Plant Readiness for OL IE Manual,Chapter 94300 ML20214R4051987-05-0808 May 1987 FOIA Request for Region Input to NRR Re Status of Listed Plants Readiness for Ol,Per IE Manual Chapter 94300 ML18150A1861987-05-0101 May 1987 Forwards EGG-NTA-7612, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety- Related Components,North Anna Units 1 & 2 & Surry Units 1 & 2, Final Informal Rept ML20214Q8801987-04-17017 April 1987 Forwards EGG-NTA-7591, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept.Plants Conform to Item ML20214R0621987-04-17017 April 1987 Forwards EGG-NTA-7613, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,Arnold, Brunswick-1 & 2, Final Rept.Plants Conform to Item ML18150A1171987-04-14014 April 1987 Forwards Final rept,EGG-NTA-7625, Conformance to Item 2.1 (Part 2) Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214R8611987-03-27027 March 1987 Forwards EGG-NTA-7614, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Cook-1 & -2,Haddam Neck, Final Informal Rept.Facilities Conform to Generic Ltr ML20214R1361987-03-26026 March 1987 Forwards Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Maine Yankee, St Lucie 1 &-2 & Waterford 3, Final Rept.Plants Conform to Generic Ltr ML20214R1861987-03-26026 March 1987 Forwards Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components,Haddam Neck & Millstone 1,2 & 3, Final Rept ML20211D6631987-02-12012 February 1987 Notifies of 830204 Meeting W/Util,Idvp,Nrc & BNL in San Francisco,Ca to Discuss Status of Containment Annulus Steelwork & Status of Auxiliary Bldg ML20211D7031987-02-12012 February 1987 Notifies of 830209 Meeting in San Francisco,Ca to Discuss Shake Table Tests of Electrical Equipment ML20211D7441987-02-12012 February 1987 Notifies of 830517 Meeting in San Francisco,Ca to Discuss Development of Piping Stress Intensification Factor ML20209A8551987-01-16016 January 1987 FOIA Request for Documents to Be Placed in Pdr,Including NRC Re Calibr of Test Equipment allegation,1986 Inservice Insp Repts for McGuire 1 & Surry 1 & NRC 830307 SALP on Nine Mile Point 2 ML20207K0151986-12-19019 December 1986 FOIA Request That Encls to Insp Rept 50-247/86-26,Byron Semiannual Radioactive Effluent Rept & Millstone 1 & 2 SALP Rept Be Placed in PDR ML20211P2051986-11-24024 November 1986 FOIA Request for La Crosse & Big Rock Point Semiannual Effluent Repts & Turkey Point & St Lucie SALP Repts ML20214R8831986-11-0505 November 1986 FOIA Request for Encls to 860821 SALP Repts ML20213F8841986-10-30030 October 1986 FOIA Request for Encls to NRC 860724 & 31 Requests for Addl Info Re Vermont Yankee Spent Fuel Pool Expansion & Browns Ferry Seismic Reevaluation Program,Respectively ML20209D1691986-10-29029 October 1986 Forwards Rev 3 to EGG-EA-7035, Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Braidwood Units 1 & 2,Bryon Station Units 1 & 2,Callaway Plant Unit 1,Indian Point.... Licensees Conform to All Items W/Exception of Trojan ML20214J9761986-10-15015 October 1986 FOIA Request for Containment Event Trees for Listed Facilities,Technical Repts & Memoranda Re Interpretation & Quantification & Identification of FIN Numbers,Contractors & Investigators Involved in Creation/Analysis of Event Trees ML20214K0231986-10-15015 October 1986 FOIA Request for All Documentation Re Accident Sequence Evaluation Program Repts Re Listed Facilities in Preparation for NUREG-1150 ML20245A4451986-09-25025 September 1986 Forwards Revised Draft EGG-NTA-7188, Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20215M9941986-05-21021 May 1986 FOIA Request for Documents Re Eg Case 771201 Memo to Tj Mctiernan Concerning Chronology of Events Associated W/ Facility Fault Assessments ML20210T4441986-03-27027 March 1986 FOIA Request for Initial (Cycle 1) Startup Test Repts & Suppls for Seven Plants & Original Monthly Operating Rept for June 1983 for Virgil C Summer Plant 1989-09-07
[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 ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 1999-05-05
[Table view] |
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DAvrobURTON SLEMMONS CONetJLTING 08014088T 7 9996 OOLDEN VALLEY ROAD '
RENO. NEVADA 80806 -
. . November 25,1983 Dr. Robert E. Jackson, Chief Geosciences Branch Division of Engineering U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Dr. Jackson:
This letter responds to your request that I prepare a preliminary and independent assessment of fault capability and maximum earth-quake parameters for the Washington Public Power Supply System's Nuclear Power Project No. 3, near Gatsop, Washington. My review of the local and regional relations that affect seismic design at the site includes local and regional study of reports, responses to questions, and the relevant geological, seismological and geophysical data.
r If you require further information, please request additional comments by letter or telephone.
Sincerely yours, ode. Ln.4 D. Burton Slemmons Consulting Geologist e
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1 INTRODUCTION '
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1.1 Purpose of Study This report was' requested by Dr. Robert .E. Jackson, Chief, Geosciences Branch, Division of Engineering, U. S. Nuclear Regulatory Commission. The statements and conclusions are preliminary comments that are based on a partly incomplete data base. The appraisal of regional and site-specific geological, seismological and geophysical information are summarized and important remaining major issues are listed.
1.2 Scope of Work This report is based on a site visit and study of reports on the geological, seismological and geophysical information on the local and regional geology. My previous work in the Pacific Northwest includes study of regional seismicity, evaluation of the 1872 Pacific Northwest earthquake, evaluation of data on active or capable faults, compilation of faults and lineaments from various scales of topographic maps and several types of imagery. My investigations included the determinations of fault capability and earthquake parameters for the U.S. Corps of Engineers at six dams along parts of the Columbia and Snake Rivers and for the U.S. Nuclear Regulatory Commission in the Columbia Plateau at the U.S. Nuclear Project No. 2, the Skagit/Hanford Nuclear Project, Units 1 and 2, and the BWIP high level waste repositories.
2 GE0 LOGICAL FEATURES The following are comments regarding the geological and tectonic setting for the site and surrounding region:
- 1. None of the mapped and trenched faults at the site show any evidence for activity. This is suggested by the unfaulted older soils and terraces, and the accordant ridgelines that are about 2 million years old. I see no need for further active fault investigations at the site.
- 2. The Olympic Mountains are the nearest major structure that may be active tectonically. This is an area of slow uplift (Gable and Hatton, 1983). The eastern periphery of the Olympic Mountains has at least one short segment with Holocene offsets (Carlson, 1979; Vilson, and others, 1979). Similar appearing structures have capable faults along parts of their boundary zones or on radiating structures. The tectonic deformation of the border zone of the Olympic Mountains should be assessed in relation to the effects on faults that are near the WNP-3 site.
One zone, that may be of this type, needs further evaluation.
This zone of possible Quaternary deformation, the Humptulips-Wynocchee-Melbourne zone, is discussed in the main text of this report. This zone may extend about 12 km west of the site and 2
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..g report. This zone hay ~ extend about 12 km west of the site and needs to be investigated ^for structural continuity or noncontinu-ity, fault capability and seismogenic potential. New imagery, remote sensing data and shoreline deformation needs to be evaluated for the site region and major geologic structures.
3 The Olympic lineament is mainly identified from its gravity gradients. It is postulated to be a potential source of a magnitude (Ms) 7-1 /2 shallow-focus crustal earthquake. The closest approach of this lineament is 22 mi (35 km). There is no evidence for activity along this zone, although the Pleistocene erosion and deposition could obscure evidence fer activity for faults with recurrence intervals of over about 11,000 years. The latest worldwide data would suggest the following magnitudes for a 2/3 rupture length:
The assumed normal-slip mechanism, using the formulation of Slemmons (1982) the magnitude is:
Ms = 0.809 + 1 341 log 59,000 = 7 2 For,an assumed reverse-slip mechanism, using the formulation of Slemmons (1982) the magnitude is:
Me = 2.021 + 1.142 log 59,000 = 7 5 For an assumed normal-oblique-slip mechanism, using the formula-tion of Slemmons (1982) the magnitude is:
Ma = 0.875 + 1 348 los 59,000 = 7 3 For an assumed reverse-oblique-slip mechanism, usir.g the formula-tion of Slemmons (1982) the magnitude is:
Ms = 1.199 + 1.271 log 59,000 = 7 3 If the structure is a capable reverse-slip fault, or a normal-slip fault, the use of 2/3 rupture length may. require reevalua-tion, since the worldwide demonstration of fractional lengths for magnitude estimates is not documented, and the specific fraction has not been carefully assessed. There is no specific data on the type of fault that may control the Olympic lineament. The interrelationship of this feature with other faults of similar orientation toward the southeast requires more detailed investi-gations for possibic capability and tectonic connection to the Dalles area (U.S. Army Corps of Engineers, 1982) or to Mt. St.
Helens (Carlson, 1979; Wilson and others, 1979). In addition, this feature has not been assessed for relationship to regional stress axes or possible conjugate relationships.
Several questions remain unresolved; these include:
Is this a capable fault?
What, if any, are the interconnections to the southeast?
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What is the probable type of fault shown by direct or conjugate relationships?
The data for estimating the magnitude, taken from Slemmons (1977 and 1962), give Ms magnitudes that are somewhat 6reater than 7 3, but answers to the above qu'estions are more important issues.
3 SEISM 0 LOGICAL SETTING 3.1 General Statement The WNP-3 site appears to be in a tectonically stable region for shallow focus earthquakesas as is shown by the historical record of seismicity and the record of known active or capable faults of the region. However, the cross section of the site seismicity and the evidence cited by Heaton and Kanamori (1983) suggest that subduction in the northwestern part of United S ates is seismic that a great earthquake could occur in this regicn. Two possible maximum earthquakes should be considered for this site, shallow focus and deeper Benioff or subduction zone earthquakes.
32 Shallow Focus Earthquakes
, The number of shallow focus earthquakes is relatively low L the site area and no capable faults are defined by current seismic-ity. Seismicity patterns do not resolve the issue of whether or not the Olympic lineament or structures near the Olympic Mountains are capable. Focal mechanism studies are useful for defining the orientations of conjugate faults. The limited data that is available for the site-area suggest that most of the faults are reverse-slip faults, although strike-slip components are common. The activity at Mt. St. Helens appears to be right-slip on a north-south fault zone (Weaver and Smith, 1981). The seismologic evaluation of the site area should be reevaluated with the cross sections for narrower belts of seismicity, so that the vertical display of focal depths is more representative of -
local distributions.
33 Deeper' Shallow Focus Earthquakes The most critical single issue that needs to be resolved for the seismic design for the nuclear power generator is the question of whether or not the underlying Benioff zone or subduction plate boundary is seismogenic or aseismic. The volcanic activity of the Cascade volcanoes, and the known motions between the North American and Juan de Fuca plates clearly show that there is subduction with a relative movement between the plates of from 2 to 4 cm/yr. The seismological debate on whether or not this zone is seismic or aseismic has not been resolved and this issue, along with a maximum earthquake magnitude value, if it is seismic, must be addressed on the basis of newer analyses that were present at the time of preparation of the FSAR.
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- y. .i John Adams (oral communi6ation, J1983) has suggested that geolog-ical studies could be made of both continental lacustrine and marine sediments to determine whether or not liquefaction and landslide . events are recorded at the base of bodies..of._ water. .
Coring and dredging methods have shown the effects of paleoseis-mic activity. This method may provide a geological measure of
, whether earthquakes occur in the northwestern United States or the movement between the plates is aseismic.
4 GEOPHYSICAL SETTING The geophysical studies of the region and for the site area are mostly adequate, but they should be reexamined to determine if any of the-geophysical (e.g. intratelluric, seimic reflection profiles, etc.) methods can be expanded with new data to resolve the issue of whether or not the boundary between the North Ameri-can and Juan de Fuca plates is seismic or aseismic.
5 CONCLUSIONS
- 1. The most important single issue is the question of whether or not the Benioff zone beneath the site is capable of a large earthquake that should be considered in the design at WNP-3 This issue has not been resolved.
- 2. Two possible shallower focus earthquakes may need to be considered for seismic design at WNP-3 The seismic motion at the site may have a different spectral content and the distance to the site may be closer than for.1, above. This should include a reassessmentoof the Olympic lineament, to determine if it is a capable fault, and to examine structures around and near the Olympic Mountains to determine capability. The latter should include an evaluation of the Hamptulips-Wynocchee-Melbourne zone.
3 Site faults are older, inactive faults that show no. evidence for current activity. The old upland surfaces with their accordant ridgelines show no evidence for faults with vertical components of displacement during the past 2 or 3 million years.
Subsurface exploration at the site does not appear to be warranted.
The most important single issue is the question of whether or not the Benioff zone beneath the site is' capable of an earthquake that should be considered in the design of vital structures at the Satsop site. I believe that until this issue is resolved, no specific earthquake magnitudes should be estimated for this type of earthquake.
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