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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML20217D6621999-05-14014 May 1999 Forwards NRC Operator Licensing Exams 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15.Nine Candidates Passed (& One Failed) Exam ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr 1999-09-08
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20195C1421988-06-13013 June 1988 Informs That Dk Gehmlich,Associate Dean for Academic Affairs,Replaced Re Stephenson as Reactor Administrator Effective on 880609.Current Membership of Reactor Safety Committee Listed ML20151A3451988-03-0303 March 1988 Informs That Listed Personnel Make Up New Reactor Operations Staff at Triga (R-126) & Agn (R-25) Reactors ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor ML20207R8261987-03-0202 March 1987 Forwards Ltr Requesting Commission to Review Director'S Decision DD-87-02,per 2.206 (c)(1),to Determine If Director Grossly Abused Discretion by Misrepresenting Petition,Not Responding to Important Points & Deceiving Petitioners ML20206G9281987-02-0606 February 1987 Discusses Scoping Analysis for Direct Heating in Plant. Analysis of Plant Containment Continuing.Aim to Develop Methodology That Can Be Used in Categorizing Other Containments ML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML20141N3711985-12-17017 December 1985 Appeals Denial of FOIA Request for Four Categories of Documents Re Fraudulent Computer Programs ML20138F5071985-10-25025 October 1985 FOIA Request for Four Categories of Documents Re Leak Rate Testing ML20141N2851985-10-21021 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched Fuel from Research Reactor.Indefinite Stay of Execution Requested for Listed Reasons,Per Item 3 of Order ML20141N2821985-10-0808 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched U to Secure Facility.No Unirradiated High Enriched U Kept on Hand ML20147E7671984-09-24024 September 1984 Forwards INPO Accreditation:Board Members Perspective, Presented at ANS 1984 Annual Meeting in New Orleans.Proposed Rule Should Contain Min Requirements to Avoid Discouraging INPO Initiatives ML20128N9521984-04-30030 April 1984 Forwards Comments Re Quest Study of Surry Tmlb Scenario. Clarification Needed Re Where Data Obtained for Solid Triangle (Sascha) Data Points in Figure A-3 ML20210E6661984-02-27027 February 1984 Forwards Newspaper Ad Re Reasons for 840211 Civil Disobedience Over Plant Emergency Plan ML20210E7141984-02-0101 February 1984 Provides General Concept of Evacuation Time Estimates Re Baseline Scenarios Such as Normal & Adverse Weather.Time Estimates Technically Sound & Based on Best Available Data ML20210E7101984-01-30030 January 1984 Forwards Repts on Fog & Rain.Copies of Questions on Plant & Responses to Date Requested.W/O Encls ML20210E6701984-01-0909 January 1984 Ack 831230 Response to Concerns Over Emergency Response Plan at Plant,Including FEMA Response from R Vickers.Fema Response Inadequate Re Evacuation Time Considerations & Evacuation Routes ML18089A4731983-12-20020 December 1983 Forwards Summary of Facility Evacuation Time Estimates Based on Review Against NUREG-0654,Rev 1.No Deficiencies Noted ML20210E7001983-12-0909 December 1983 Ack 851202 Response to Re Concerns in Emergency Response Plans.Concerns Expressed Re Rebuilding of Twin Bridges & Siren Backup ML20210E6841983-11-0404 November 1983 Forwards Examples from Newspaper Re Concerns Over Plants Emergency Response Plan ML20105B3561982-06-0101 June 1982 Submits Rept Re Security Incident in Response to 10CFR73.71(c) Detailing Loss of Security Effectiveness, Responses Made & Efforts to Revise Sys & Procedures to Reduce Chance of Recurrence.Portions Deleted ML20239A4041964-08-17017 August 1964 Forwards Bodega Bay Meteorological Hazard Implications Repts for Info.W/O Encls ML20234B7891964-08-0505 August 1964 Discusses Ongoing Studies of Sonoprobe Lines in Tomales Bay. About 150 Miles of Lines Completed & Indicate Complex Structures.Sonoprobe Survey Will Also Be Conducted by Scripps Institution of Oceanography.Related Info Encl ML20234E3421964-04-25025 April 1964 Discusses 640318 Visit to Proposed Reactor Site Re Geology of Bodega Head.Controversy Lies W/Displacement of Shaft Fault.Diagrams Encl ML20234F5981964-04-0808 April 1964 Advises That F Neumann Suffered Stroke & Remains in Critical Condition in Hosp.Ha Coombs & Author Available to Assist AEC in Connection W/F Neumann Work ML20235C6131964-03-27027 March 1964 Ack Receipt of Re Amend 6 to PG&E Application for Bodega Bay Reactor & Notes That Amend Supersedes Amend 4. Comments on Questions Raised at Preceeding Meeting in Washington,Dc Not Completed ML20234D7781963-07-16016 July 1963 Ack Receipt of & Inquires If Possibly Incomplete. Expresses Doubt as to Whether Dilution Factor Determined by Diffusion or Dye Extrapolated to Apply to Heat Loss of Large Water Flow ML20234D2791963-07-15015 July 1963 Advises That Matl Sent Earlier Will Probably Be Revised Following Receipt of Written Matl from Pg&E.Suggestions from Legal Staff to Answer Encl Ltrs Opposing Proposed Plant at Bodega Bay Requested ML20234F4431963-07-10010 July 1963 Informs That by End of Wk,All Modified Illustrations to Be Completed.Forwards Results on El Centro Analysis,Per Discussion of Resultant Accelerations & Velocities at Last Meeting.Illustrations to Be Included in Final Rept ML20234D9771963-06-24024 June 1963 Ack Receipt of Forwarding Matl Re Engineering Plans for Proposed Bodega Head Power Plant.Some Questions Still Unanswered & Commented on in Replies to Recent Inquiries ML20234D9131963-06-21021 June 1963 Informs of Expected Arrival on 630624 & Reservation on Jet Leaving 630626 ML20235A8491963-06-19019 June 1963 Forwards Rept on Seismological Aspects of Proposed Nuclear Power Plant on Bodega Head,Ca,Per 630613 Conference ML20235A5611963-06-0808 June 1963 Urges AEC to Consider Listed Facts in Deciding Util Application for Nuclear Power Generating Plant at Bodega Head,Ca,Including Fact That Proposed Site Located Near San Andreas Fault.Tj Edmonds Ltr to President Kennedy Encl ML20235A3161963-06-0505 June 1963 Comments on ACRS 630418 Rept Re Proposed Reactor at Bodega Head.Committee May Have Been Misled Re Potential Impact of Condensor Coolant Discharge on Local Marine Life.L Watters to President Kennedy Encl ML20234F5011963-05-29029 May 1963 Forwards Critical Review of Gw Housner Paper Entitled Behavior of Structures During Earthquakes, Ref in Hazards Rept Submitted to AEC in Connection W/Bodega Head Power Plant.Citizen Ltrs to President Kennedy & Udall Encl ML20239A5571963-05-22022 May 1963 Forwards Answers to Three Questions Raised at Urbana Conference Re Estimate of Magnitude of Max Credible Earthquake,Credible Ground Acceleration (Peak & Average) & Amount of Permanent (Faulting) Displacement of Head ML20234B2281959-12-18018 December 1959 Requests Statement of Limits Now in Force or Being Proposed for Some Larger Power Reactors in Us.Requests Specific Info on First Seven Reactors Listed on Page 6 of Info Bulletin TID-8200 1988-06-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr ML18153A3421999-03-26026 March 1999 Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML18153A3411999-03-15015 March 1999 Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls 1999-09-08
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UNIVERSITY OF VIRGINIA P mAm DEPARTMENT OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NUCLEAR REACTOR FACILITY l k ) SCHOOL OF ENGINEERING AND APPLIED SCIENCE
, P u 2 CHARLOTTESVILLE. VA 22901 April 30, 1984 Telephone: 841 924 7136 Michael W. Jankowski Accident Source Term Program Office Office of Nuclear Regulatory Research U. S. Nuclear Regulatory Comission Washington, D. C. 20555
Dear Mike:
I am enclosing a copy of my coments en the QUEST study of the Surry TMLB' scanario. I am sorry that I have not had time to do justice to this review. It is very difficult to assess the QUEST study due to its complexity. -
Sincerely, ,
A. B. Reyno s. Professor Dept. of Nuclear Engineering and Engineering Physics ABR:ph Encl.
8507130176 850425 PDR FOIA l ALVARE285-110 PDR
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Pr'eliminary Comments on the QUEST Study A. B. Reynolds I as still unprepared to make significant comments on the QUEST study. I think a meeting of the revis.v committee would be needed to perfo m an adequate review of the material. There is so much material in the DILB' report that was sent to us that I as having trouble focussing on the really significant uncertainties. The combined.
insights of the peer and observer groups might shed the necessary light and provide thA perspective required to assess the QUEST results.
A proper assessment of the QUEgT' study is important. The vide variations in possible results suggested by the Q0EST study cast greater doubt on the value of the BMI 2104 results than I think is warranted, but I cannot argue this working alone.. On the other hand, if the review committee comes to a consensus that the results are as uncertain as QUr.ST indicates, then little definition can be said about the source term unless the containment failure working group demonstrates that early failure is not credible.
Despite my lack of time to assimilate auch of the extensive work reported by SANDIA, I would offer a few specific comments, as noted below.-
l Specific Co u nts Tellurium Release The first point to note is that I as perplexed as to where the data was obtained for the solid triangle (SASCHA) data points in Figure A-3.
I have plotted the tellurium data points from the SASCHA tests, as noted 1
f .
in red (open A,D , and o's) on,the next page, and they are totally
- different from the data in Fig. A-3. Also I believe there was a factor 4
of 10 error in the plotting of the.HI-2 datus. My understanding of the correct placement of this point is also shown on the next page. The Ku w 772 curve for Te appears to be close to the upper limit of the
) release rates for the data as I have plotted them.
j In Appendix A, and elsewhere, tellurium is included with iodine and cesium as a volatile fission product, and it is argued that the volatile 1 .
fission products likely are released from the fuel early. Yet I see a factor of three variation in Te releases in Fig. 6-27, from - 30%
l release in most cases to 901 in the late high case. This is nearly as
{
I wide variation as Barium (except for the late low case), Technetium, and total mass aerosolized (Figures 6-28, 6-28, and 6-29).
Moreover, the effect of the presence of oxidized versus unoxidized
! zirconium on tellurium release was ignored, even though this effect has i been reasonably well established experimentally.
The suspended To for the late high case for code-input uncertainty (6 ) reaches 7 or 8 kg for about an hour period, while only - 1 kg is c
suspended for the base case. (These numbers compare to the total Te ,
inventory of 25 kg.) One notes that 11% of the Te is released to the I
environment in the Surry, Volume V calculation for the TMLB'-6, accident
, (Table 7.16. Vol. V). This is a high release so that Te may be important for the TMLB' accident. Hence, treatment of uncertainties in Te release data may have important consequences. Does ais-plotting the data on Figure A-3 of the QUEST study have auch significance? I find it disturbing if either mis-plotting the data or ignoring the effect of i
- zirconium on Te release has little effect on the final release to the a environment.
1 2
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Next, I note the effect of 6 uncertainties on Te release. The p
uncertainties in temperature histories in the 6 uncertainty section p
lead to Te release uncertainties similar to antimony, barium, and molybdenum releases (compare Figures 7-3, 7-4, 7-6, and 7-7). Hence Te acts like a low volatility element, not like the high volatility iodine i and cesium. These results later propagate to potentially large Te releases relative to the base case (Figure 7-30). Again I question the effect of errors in the basic Te release data (either the mis-plotting or the ignoring of the effect of Zr) on these QUEST results.
Overall Results . .
I note that the end result of QUEST is not the ,same as in the BMI study. The BMI analysis concludes with fraction of fission products released from the containment. QUEST does not present this. Based on the QUEST results of fission products suspended versus time, perhaps that ratio can be related to the fission priwiucts released.
I note that most of the QUEST results fall below the BMI base case, which is encouraging. However, some of the early failure cases fall auch above the EMI case, and some of the high late cases fall somewhat above the EMI case.
i Bence, it is difficult to assess the proper source term, especially l l if early containment failure is possible, without more understanding of l l
the complex QUEST analysis than I now have. l Effect of Natural Convection velocities The presence of large natural convection velocities relative to
, forced-flow steam velocities identified in the QUEST study may be i
important. This appears to create significant differences from the BNI 3
i y w- 4 -p . - - . - - --* - - - - - + , . -- p--+ - - --,--.-------m -.- - - . --
r
- 5 <
analysis.
n{e problem is so complex, however, as discussed in Appendix B, affecting condensation. of fission products on urosols and solaero~
settling in the' core versus the upper plenue in aadition to temperatur e distributions, that I catsot tell yet how important all of this is It .
appears to be quite important-somewhat like the whole problem of resuspension and remayoration that was also neglected in the BMI base - '
i case analysis. '
In the time availt.ble to me so far, without a meeting of the entire peer review couaittee. I have difficulty assessing a probina of this kind. /
Uncertainty in Steel and Zirconium Melt $'ractions in the Melt Uncertainties awa=faed in CORCON-VANESSA in both ste and zirconium melt fraction in ths, melt are large (4000 to 70 000 kg for steel; O to 80% for Zr-Table 4-2). ,
I, realize that' examining such large "
uncertainties in one code does not necessarily imply that the MA2 e 3 cod actually leads to such large uncertainties in these parameters
, though I ,
am concerned that some may look at Table 4-2 and wonder that , if our uncertainty range has to be this large, then diive have any cohfidence at all in what MARG is telling us? \
I Therefore I looked at the MARG uncertainty analysis to see if I J l
could gain any information on the segel and zirconium salt fraction in \
the melt. +
results.
So far I have not/ been able to determine this from the N ACH 1 I do note that there is not a large variation in'hydrogeIn
\
generation from the MARG results.
~
This wo dd indicate that there is a
not a l'rge variation in the amount of zirconium that reacts with steam .
i Hence there should not be the tremendous variation in zirconium available in the melt. ,
/
s
, 4 -
1