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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program ML20206E3721999-04-29029 April 1999 Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML20206B7381999-04-26026 April 1999 Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept ML20205E3471999-03-29029 March 1999 Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to ML20204F4611999-03-19019 March 1999 Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML20203F8041999-02-11011 February 1999 Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c) ML20203C8971999-02-0808 February 1999 Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP ML20202H4891999-01-26026 January 1999 Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr ML20199H2431999-01-15015 January 1999 Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper ML20199E1841999-01-13013 January 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication ML20199E0781999-01-13013 January 1999 Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5 ML20199D9711999-01-13013 January 1999 Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl ML20199E9051999-01-12012 January 1999 Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls ML20199E7671999-01-12012 January 1999 Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24 ML20199A4151999-01-0404 January 1999 Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility ML20198K6551998-12-24024 December 1998 Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant ML20198J4001998-12-21021 December 1998 Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request ML20196H3171998-12-0303 December 1998 Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety ML20196G7541998-11-25025 November 1998 Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request ML20195G9851998-11-17017 November 1998 Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips ML20195H5321998-11-13013 November 1998 Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed ML20195F2271998-11-12012 November 1998 Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21 ML20154M5381998-10-14014 October 1998 Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items ML20154M2211998-10-14014 October 1998 Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML20203F8041999-02-11011 February 1999 Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c) ML20202H4891999-01-26026 January 1999 Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr ML20199E7671999-01-12012 January 1999 Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24 ML20199E9051999-01-12012 January 1999 Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls ML20199A4151999-01-0404 January 1999 Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility ML20198J4001998-12-21021 December 1998 Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request ML20196G7541998-11-25025 November 1998 Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request ML20195G9851998-11-17017 November 1998 Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips ML20195H5321998-11-13013 November 1998 Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed ML20195F2271998-11-12012 November 1998 Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21 ML20154M5381998-10-14014 October 1998 Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items ML20154A7511998-10-0101 October 1998 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments, Since Oct 1997.Summary of Changes to Facility, Brief Description of Each Change & Summary of SE ML20153F6061998-09-17017 September 1998 Commits to Revise Defueled Emergency Plan Currently Under Review by Staff,Per Discussion with NRC on 980917.Section 10.2, Assessment Methods Will Be Revised as Listed ML20151Y2621998-09-11011 September 1998 Provides Description of Three Listed Requirements Re Plant Defueled Emergency Plan Implementation Commitments,In Response to 980911 Telcon with NRC ML20238E8081998-08-28028 August 1998 Forwards Revised Big Rock Point Defueled Emergency Plan. Rev to Plan Resulted from NRC Questions Raised During 980813 Meeting ML20237B4351998-08-11011 August 1998 Provides twenty-ninth Update of Big Rock Point Integrated Plan.Plan Has Had No Changes Since Last Update Dtd 980213. Proposed Defueled Facility OL & Tss,Currently Under Review by Nrc,No Longer Require Submission of Plan 05000155/LER-1998-001, Forwards LER 98-001-00 Re Discovery During Facility Decommissioning of Severed Liquid Poison Tank Discharge Pipe.Rept Being Submitted IAW 10CFR50.72(b)(2)(iii) & 10CFR50.73(a)(2)(i)(B)1998-08-0606 August 1998 Forwards LER 98-001-00 Re Discovery During Facility Decommissioning of Severed Liquid Poison Tank Discharge Pipe.Rept Being Submitted IAW 10CFR50.72(b)(2)(iii) & 10CFR50.73(a)(2)(i)(B) ML20236Y4171998-08-0606 August 1998 Forwards semi-annual Fitness for Duty Program Performance Rept for Period Jan-June 1998 ML20236V7741998-07-30030 July 1998 Forwards Revs to Defueled Emergency Plan & Related Exemption Request,As Result of 980625 Meeting W/Nrc Re Plant Restoration Project Defueled Emergency Plan & Related Exemption Request from 10CFR50 Requirements ML20236W3341998-07-27027 July 1998 Submits Draft Rev 19b of Quality Program Description for Operational Nuclear Power Plants (CPC-2A).Changes in Draft Rev 19b Respond to NRC Questions Re Program Scope as Applied to Big Rock Point & Restore TSs Re on Site Review Committee ML20236T6651998-07-21021 July 1998 Provides Remaining Responses to NRC 980416 RAI Re Big Rock Plant'S Proposed Defueled Tech Specs.Proposed Defueled Tech Specs & Bases,Encl ML20236R2771998-07-14014 July 1998 Submits Response to Violations Noted in Insp Rept 50-155/98-03.Corrective Actions:Staff Reviewed Decommissioning Surveillance Testing on safety-related Sys, Structures & Components ML20236J3461998-06-30030 June 1998 Forwards Rev 135 to Vol 9 of Site Emergency Plan & Rev 184 to Vol 9A to Site Emergency Plan Implementing Procedures ML20236H0701998-06-30030 June 1998 Responds to Violations Noted in Insp Rept 50-155/98-04. Corrective Actions:Rcw Sys Function Plant Performance Criteria Was Revised to One MPFF for Sys Function in Expert Panel Meeting 98-02,980506 ML20248L8131998-06-0505 June 1998 Requests Withdrawal of Application for Amend to License DPR-6 Dtd 980325.Facility Security Mods Described in Amend Will Not Be Performed as Originally Scheduled ML20248L5461998-06-0505 June 1998 Forwards Draft Proposed TS & Bases Rev,Incorporating Changes Responsive to 980416 RAI ML20247G1481998-05-12012 May 1998 Forwards Rev 14 to Plant Suitability,Training & Qualification Plan,Per Provisions of 10CFR50.54(p).Changes Are Editorial to Reflect Change from Consumers Power Co to Consumers Energy Co.Encl Withheld ML20216A9351998-04-30030 April 1998 Forwards Big Rock Point Radioactive Effluent Release Rept & Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program ML20217N2011998-04-29029 April 1998 Forwards Brpnp Zircaloy Oxidation Analysis, Which Presents Site Specific Analysis That Derives Time When Zircaloy Oxidation Analysis Phenomenon Is No Longer Applicable to Plant Fuel Pool ML20217G4941998-04-23023 April 1998 Informs That Previous Commitments Will Not Be Retained Due to Permanent Cessation of Big Rock Point Plant Operation. Commitments Associated W/Nrc Insp Repts,Encl ML20217E9101998-04-21021 April 1998 Forwards 1997 Consumers Energy Co Annual Rept, Including Certified Financial Statements ML20217P2401998-03-31031 March 1998 Forwards site-specific Dimensions & Construction Info Re Big Rock Point Wet Spent Fuel Storage Sys as Requested in 989223 RAI on Exemption from Offsite Emergency Planning Requirements ML20217H4521998-03-26026 March 1998 Forwards Rev 2 to Post Shutdown Decommissioning Activities Rept (Psdar). Rev Incorporating Revised,Detailed Schedule & Revised Cost Estimate,Will Be Submitted to Util ML20217F5061998-03-25025 March 1998 Forwards Application for Amend to License DPR-6,per 10CFR50.90.Security Plan Revised to Reduce Scope of Plan to Correspond to Condition of Facility,Since Reactor Has Been Permanently Defueled.Encl Withheld,Per 10CFR73.21 1999-09-30
[Table view] Category:TELEGRAMS-CORRESPONDENCE
MONTHYEARML20126E3601971-02-0909 February 1971 Submits Addl Info Re Proposed Change 27.Discusses Safety of Auxiliary Neutron Sources ML20126E3661971-01-19019 January 1971 Responds to Request for Addl Info Re Tech Specs Changes 21, 22 & 24.Discusses Reactivity of gadolina-bearing Fuel & Potential Use of New Fuel Storage Racks ML20126E2181968-06-13013 June 1968 Advises That New Peak Clad Temp Calculation Results in 2,200 F.Addl Info to Be Submitted ML20126E3421966-09-26026 September 1966 Submits Addl Info Re Proposed Change 10 to Tech Specs Per 660729 Request,Including Time Constant Vs Fuel Energy Content Relationship Used in Previous Calculations ML20126E3461966-08-16016 August 1966 Submits Addl Info in Support of Proposed Change 10 to Tech Specs of License DPR-6,per 660729 Telcon ML20126E2851966-05-0202 May 1966 Submits Addl Info in Response to Questions Re Details of Accident Analysis Which Supports Request for Change 8 to Tech Specs.Substitution of zircaloy-clad Fuel for Stainless steel-clad Fuel Does Not Present Hazard ML20126E3271965-03-0202 March 1965 Submits Addl Info in Support of Request for Change to Tech Specs Per ML20126E3301964-09-28028 September 1964 Submits Info Re Operating Difficulties at Facility Concerning Failure in Main Steam Bypass Valve Control Sys. Intends to Reload Facility to Normal Core Size During Outage & Resume Normal Operation ML20126E2161964-07-15015 July 1964 Submits Info in Response to 640326 Request Re Changes to Tech Specs Change Requests 47 & 49 & Supplements Info Submitted on 640521.Provides Outline of Physics Tests to Be Run on 44-bundle Core ML20126E2321964-07-13013 July 1964 Submits Supplemental Info to 640326 Proposed Changes 3,25, 14,15,20 & 32 Re Calibr of Incore Monitoring Sys ML20126E2061964-05-28028 May 1964 Requests That Oak Ridge Operations Ofc Be Authorized to Provide GE 173.90 Kg of U-235 by 640612 to Meet Schedule for Delivery of 35 Fuel Bundles to Facility ML20126E2011964-02-24024 February 1964 Submits Info Re Proposed Sections C & E of Containment Testing Procedure 1971-02-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0161990-09-18018 September 1990 Forwards Corrected Monthly Operating Rept for Aug 1990 for Big Rock Point Plant,Consisting of Corrections to Grey Book ML20059K2381990-09-0707 September 1990 Forwards Info in Response to Request for fitness-for-duty Policy & Procedures,Per NRC ML20059F5031990-09-0505 September 1990 Forwards Description of Scope & Objectives for 1990 Emergency Exercise Scheduled for 901204.Region III Will Participate ML20059E0001990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 ML20059B6371990-08-22022 August 1990 Forwards Correction to 900628 Response to Generic Ltr 90-04 Re Status of Generic Safety Issues (Gsis).Response Contained Some Errors in That Some Palisades Plant Related Info Inadvertently Substituted Into GSI Table for Big Rock Point ML20059B6221990-08-22022 August 1990 Forwards Missing Pages 25 & 26 Omitted from Facility Decommissioning Funding Rept,Consisting of Attachment a to Exhibit E ML20059B6321990-08-22022 August 1990 Forwards Revised Engineering Analysis of Generic Ltr 88-01 on Plant Temp Pressure Limits in Support of Licensee 900110 Tech Spec Change Request,Per NRC Request ML20058L9891990-08-0606 August 1990 Provides Util Comments Re SALP 9 Board Rept.Declining Trend in Radiological Controls Noted in Cover Ltr Needs to Be Reevaluated ML20056A3491990-08-0303 August 1990 Updates Response to NRC Bulletin 90-002, Loss of Thermal Margin Due to Channel Bow 05000155/LER-1990-002, Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage1990-08-0101 August 1990 Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage ML20055J3841990-07-26026 July 1990 Forwards Certification of Financial Assurances for Decommissioning ML20055E0211990-06-29029 June 1990 Requests NRC Approval of Encl Simulation Facility Application for Plant,Per 10CFR55.45(b) ML18054B0951989-11-0606 November 1989 Forwards Executed Amends 10 & 18 to Indemnity Agreements B-40 & B-22,respectively ML18054B0431989-10-19019 October 1989 Forwards Revs 9 & 10 to CPC-2A, QA Program Description for Operational Nuclear Power Plants. Lists of Affected Pages in Revs 9 & 10 & Change Matrices Encl ML20248B4091989-09-29029 September 1989 Confirms Util Commitment to Conform W/Generic Ltr 89-04 Positions Re Guidance on Developing Acceptable Inservice Testing Program ML20247B1871989-09-0505 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-155/89-14.Corrective Actions:Appropriate Surveys & Labeling W/Contamination Levels,Contents & Date Completed & Procedures Re Guidelines for Contaminated Matls Revised ML20246N1211989-08-31031 August 1989 Forwards Integrated Plan Semiannual Update 11,consisting of Index of All Issues Identified by Category,Rank,Description & Status & List of All Open Issues Containing Detailed Scope Statements,Status & Applicable Scheduled Completion Dates ML20246N6901989-08-30030 August 1989 Forwards Response to Generic Ltrs 89-12 & 89-03.Operator Licensing & Requalification Exam Schedules for Plants Encl ML20246L9111989-08-30030 August 1989 Responds to NRC Re Violations Noted in Insp Rept 50-155/89-13.Corrective Actions:Plant Procedures Being Rewritten to Address Human Factors Concerns & Complete Insp & Clean Up of Reactor Bldg Area Conducted ML20246J1721989-08-30030 August 1989 Forwards Semiannual Radioactive Effluent Release & Waste Disposal Rept,Jan-June 1989 & Rev 4 to Offsite Dose Calcuation Manual ML20248A4431989-07-27027 July 1989 Advises That Integrated Leak Rate Test Will Commence on 890724-28,in Response to Open Items Noted in Insp Rept 50-155/85-20.Test Will Be Performed Per Method Described in Bechtel Rept BN-TOP-1 ML20247N8281989-07-25025 July 1989 Responds to NRC Concern Re Ability of Employees & Contractors to Raise Safety Issues to Licensee Mgt & NRC W/O Restrictions.Licensee Understands & Endorses Importance of Maintaining Communication Pathway Unrestricted ML20247A6161989-07-18018 July 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Review of NUMARC Guidelines Contained in App a of NUREG-1344,performed.Plant Intends to Implement Erosion/Corrosion Monitoring Program ML20245K6791989-06-30030 June 1989 Forwards Corrected Tech Spec Paragraph 3.7(f) Re Containment Sphere Leakage Testing,Per 890627 Telcon.Original 890525 Tech Spec Change Request Contained Inadvertent Textual Error ML20245K0631989-06-29029 June 1989 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Evaluation & Addl Listed Considerations Dictate That Future Component Insp Should Be Performed & Evidence of Pump Degradation Be Continued ML20245E9671989-06-23023 June 1989 Responds to 890418 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping ML20245A9771989-06-15015 June 1989 Forwards Scenario for 1989 Emergency Plan Exercise,Per Util 890322 Commitment ML20244A6311989-06-0606 June 1989 Submits Update to Util 880725 Response to Violations Noted in Insp Rept 50-155/88-12.Corrective Actions:Util Staffed Procedure Writers Group to Upgrade Maint Procedures & Procedure MGP-14 Revised ML20247D5631989-05-19019 May 1989 Responds to Re Util 881021 Rev 8 to QA Topical Rept CPC-2A.List of Recommended Changes Concerning Training Qualification & Certification Encl ML20247C3671989-05-17017 May 1989 Discusses Status of Corrective Actions Re Violations Noted in Insp Repts 50-155/87-22 & 50-155/88-11.Instructions Provided to Shift Supervisors Re Trending Requirements of Valve Timing After Maint ML20246G8961989-05-12012 May 1989 Forwards Temporary Addendum to Security Plan Re Replacement of Plant Heater Boiler.Encl Withheld (Ref 10CFR73.21(c)) ML20246C6851989-05-0101 May 1989 Forwards Annual Radiological Environ Operating Rept Jan-Dec 1988 ML20245J2871989-04-27027 April 1989 Comments on SALP 8 Board Rept for Sept 1987 - Dec 1988. Correction of Reactor Depressurization Sys Valve Problems, Neutron Monitoring Sys Upgrades & Resolution of Steam Drum Relief Valve Concerns Completed in 1988 ML20245B3601989-04-18018 April 1989 Forwards Details of Document Search Including Closure Dates in Response to 890414 Request for Status of TMI Action Plan Items ML20244D8891989-04-17017 April 1989 Submits Info Re Station Blackout Rule 10CFR50.63,including Justification for Selection of Proposed Blackout Duration, Description of Procedures Implemented for Events & Discussion of Plant Unique Design Re Survival Capability ML20245A3701989-04-14014 April 1989 Forwards Endorsement 121 to Nelia Policy NF-117 ML20244D5561989-04-13013 April 1989 Forwards Corrected 1988 Personnel Exposure Range Summary Rept,Correcting Typo ML20244D6111989-04-12012 April 1989 Responds to Request for Addl Info Re Tech Spec Change Requests Dtd 870723,880908 & 0922.Specs Cover Inservice Insp & Testing,Fire Spray &/Or Sprinkler Sys & Plant Staff Qualifications ML20244A5411989-04-0707 April 1989 Submits Supplemental Response to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers (Mcb). Justification for Continued Operation Will Not Be Prepared Since Traceability of in-stock & Installed Mcbs Established ML20247P3431989-03-31031 March 1989 Forwards Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Confirms That Requested Actions 1,2,3,4,6 & 7 Completed & Testing & Reporting Re Action 5,will Be Completed within 30 Days After Startup ML20246P3891989-03-22022 March 1989 Forwards Emergency Plan Exercise Scenario for 890523 Exercise.Comments on Scenario Should Be Submitted No Later than 890424 to Allow Mod of Package & Controller Preparation.W/O Encl ML20235S8991989-02-28028 February 1989 Forwards Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jul-Dec 1988 & Revised Semiannual Radioactive Effluent Release Rept for Jan-June 1988 W/Actual Data Replacing Estimated Values for Apr-June 1988 ML20235R7701989-02-27027 February 1989 Forwards Integrated Plan,Semiannual Update 10.Issues Added to Plan Include,Rewiring CRD Accumulator Pressure Switch & Leak Detector Schemes & Evaluate Instrument Air Sys Per Generic Ltr 88-14 ML20235R7761989-02-27027 February 1989 Responds to NRC Re Violations Noted in Insp Rept 50-155/88-26.Concurs That Potential Weakness Did Exist W/ Respect to Identifying Critical Performance Parameters for Improvement of Equipment Replacement Program ML20235T5211989-02-24024 February 1989 Advises That Payment of Civil Penalty Imposed by 880922 Order Will Be Submitted on 890301,per NRC 890131 Denial of Util 881201 Request for Mitigation of Subj Penalty ML20235R9151989-02-22022 February 1989 Forwards Description of Emergency Exercise Scope & Objectives Scheduled for 890523 ML20235Q0931989-02-20020 February 1989 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. During 1989 Refueling Outage,Instrument Air Sys Will Be Removed from Svc for Maint & Air Dryer Replacement ML20235N8411989-01-17017 January 1989 Forwards Endorsements 119 & 120 to Nelia Policy NF-117. Endorsement 119 Reflects 1989 Advanced Premium & Endorsement 120 Amends Condition 4 of Policy ML20235N8211989-01-17017 January 1989 Forwards Endorsement 4 to Nelia Certificate NW-53 & Maelu Certificate MW-137 ML20196A1631988-12-0101 December 1988 Requests Commission Reconsider Amount of Proposed Fine for Imposed Civil Penalty for Violation Re Environ Qualification of Electrical Equipment Deficiencies.Proposed Fine Unreasonable for Plant Size & Age 1990-09-07
[Table view] |
Text
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-l CONSUMERS PO'tER COMPANY j PARNALL ROAD OFFICE TVX 517 787-1955 -
. JACKSON MICHIGAN e
5-2-66 5-00 PM G}.f,.Q [iQ CD -/CE* -- .-~
""*= V J :
TO - DR. R. L. DOAN' DIRECTCR l
DIVISION OF.-- REACIOR LICENSING i l
UNITED STATES ATOMIC ENERGY COMMISSION .-
WASHINGTON' D.D.
ATTENTION - MR. ROGER S. BOYD
. t FROM -
MR. ROBERI L. HAUETER ED CONSUMERS POWER COMPANY
]y MAY3 aneuw, 1966 > 11 i
i
' DOCKET 155 e ..
4 h M # i i N < ,
I -
I THE FOLLOWING INFOPMATION IS SUBMITTED TO YOU IN REPLY To QUESTIONS f
ASKED BY DRL STAFF VIA TELEPHONE CONCERNING THE DETAILS OF THE ACCIDENT ANALYSES WHICH SUPPORTED OUR RECENT REQUEST FOR CHANGE -
)- '
$ NO. 8 - TO THE TECHNICAL SPECIFICATIONS OF LICENSE NO. DPR-6. AS
!' N"*
I O . STATED IN OUR ORIGINAL CHANGE REQUEST'WE HAVE CONCLUDED THAT THE I
t SCSTITUTION OF ZIRCALOY-CLAD FUEL FOR STAINLESS STEEL-CLAD FUEL DOES
! D :.;! PRESENT SIGNIFICANT HAZARDS CONSIDERATIONS NOT DESCRIBED OR IMPLICIT THE FHSR. AS WILL BE NOTED BELOW' THE NUMERICAL RESULTS OF THE !
'%1 g,y ACC 3ENT ANALYSES DO CHANGE SLIGHTLY FROM FHSR VALUES BUT BECAUSE OF Q
"UI VERY NATURE OF THE CkLCULATIONS AND THE NECESSARY CONCOMITANT r ASS L__ _U.MPTIONS'. THESE CHANGES CANNOT
. _ - . . . . . =..--BE - -REGARDED
. - - . - - , AS - - SIGNIFICA.NT.
- l. ,CCNTRCL ROD DROP 4CCIDENT - HOT STANDEY CON" TION -
ONLY THE RCD DROP ACCIDENT VAS ANALYZED. THE ROD EJECTICN CASE- ,
IS NCT CCNSIDERED CEEDIELE SINCE THE E.1ITTLE FRACTURE CF A CCNTROL F 0D HOUSIN3 CR SIMULT ANECUS FRACTURE OF' ALL FLANCE EOLTS MUST OCCUR ,
SIGULTANEOUSLY WITH EITHER THE MAXIMUM POSSIELE OR THE MAXIMUM PRO-CEDURAL EDD VCRTH. -
A. RESULTS - >
TAELE I LISTS THE RESULTS OF THE VARIOUS ACCIDENTS ;
ANALYZED. NOTE THAT' BASED ON OUR OPERATING EXPERIENCE-TO DATE' VE DO NOT CONSIDER THE 'MAXIMUN RCD WORTH CASES . ,
TO BE CREDIELE. TO ACHIEVE THE MAXIMUM ROD WORTH CON- {
FIGURATION
- SEVERAL PROCEDURAL CCNTROLS MUST BE VIOLATED DELIBERATELY. IT IS EXTREMELY DCUSTFUL IF ANY OPERATOR COULD DEVELOP A RCD PATTERN' STARTING FROM HOT STANDBY' .
THAT WOULD APPROACH THE NECESSARY CONTROL ROD CONFIGURA-TION FOR MAXIMUM RCD WORTH. THIS CONFIGURATION IS DIFFERENT EN00CHFROMTHETWOAPPROVEDRODWITHDRAVALSEQUENCESIh!'
USE AT BIG ROCK POINT THAT ITS OCCURRENCE AS A NONDELIE,ERATE EVENT MUST BE CONSIDERED INCREDIELE.
THE ANALYSIS OF DOPPLER LIMITED REACTIVITY INSERTION ACCIDENTS -
EXCURSIONS - WERE PERF,CRMED WITH A SYNTHESIS OF SPATI AL EFFECTS AND THE STANDARD SPACE-INDEPENDENT NEUTRON KINETICS EQUATIONS. THE METHOD CF ANALYSIS' IMPORTANT ASSUM?IIONS' AND RESULTS FOLLOV.
IT WILL EE NOTED FROM TAELE I THAT THE MAXIMUM CALCULATED ROD IN THE STAIHLESS-CLAD CORE WAS .042 DELTA X WHILE IT IS .046 DELTA K IN THE I
. ZIRCALOY-CLAD CORE. THE REACTOR LICENSE PROHIBITS OPERATING PATTERNS VITH RCD WORTHS EXCEEDING .025 DELTA K. THE FLEXIBILITY IN ACHIEVING OPERATINC PATTERNS'VITH RCD WORTHS LESS THAN .025 DELTA K IS SIMILAR l FCR THE TWO CORES. IN THE ZIRCALOY CORE' THE LARGER CORE VOLUME -
i HUR'.'ITI-ROE CONTROL AREA RULE - AND THE SLIGHTLY REDUCED INFINITE i.
! tLTIPLICATION CONSTANT - K INFINITY - 0F UNCONTROLLED FUEL MORE THAN COP.PINSATE FOR THE REDUCED K ILFINITY OF CONTPOLLED FUEL. 7 I
TAELE I -
SUMMARY
OF ROD DROP ACCIDENTS - HOT STANDBY CONDITION
.b w** 64* .*** ha- e ' *
.....+.-m4-' _ == w w ---e.,-n> **e.m~ =C mem*+ 4 w ' - =*
- CALCULATION EASED C;* CLDER GE METhCDS AND FP.SR PARAF.ETERS MAXIMUM R0D--
SS CORE ~ ZR CORE E0.
- t. 0 .
- 1. DELTA K/K INSERTED .042 .04G
- 2. MINIMUM PERIOD
- 3. PEAK NEUTRON FLUX' TIMES RATED 6'250 3'10D
- 4. PEAK FUEL TEMPERA-TURE' F 13'900 12*S00
- 5. REACTOR PEAK POVER*
MYT 1.0 X 10 TO SIXTH .7 X 10 TO SIXTH
- 6. INTEGRATED ENERGY' .
M '.'- S E C 3'320 2.'S20
- 7. UO2 EXCEEDING 5000 F
-INCIPIENT MELTING -
LB 2'200 2'200
- - E. UD2 EXCEEDING 360 6 CAL /GM- CLAD RUPTURE' LB 529 370
?
g 9. U02 IN RUPTURED FUEL RODS
- LB l*550 l*240 NOT NOT 1 10. CHEMICAL ENERGY FROM
! METAL-VATER REACTION t
MV-SEC ,,
C ALCL'L ATED , _ CALCULATED
- 11. GAS TROM METAL-VATER REACTION' SCF H2 110T CALCULATED NOT CALCULATED 1-l ..
t
(')-
CALCUL AT20N BASED O!' 'RI.SENT GE 11ETHODS ,
)
MAXIMUM ROD-- PECCEDUT.AL CONTROL SS CCRE ZR COEE SS CORE ZR CORE m
h0W NC. .
1
' !. DELTA K/K It;SERTED .042 .046 .025 .025
- 2. MINIMUM PEPIOD*MS 2.7 2.6 3.7 3.7 ,
- 3. PIAK NEUTRON FLUX' ,
TIMES RATED 900 740 700 SEO
- 4. PEAK FUEL TEMPERA-TUEE' F 15'500 15'700 9'000 E*E00
- 5. RE ACTOR PEAK P0i'ER' MWT .14 X 10 TO .lE X 10 TO . IX 10 TO .14 X 10 0 SIXTH SIXTH SIXTH SIXTH
- 6. It:TECEATED Et;ERGY' M'.'- S E C KZCKK 3*770 2'200 2*700 2'S00
- 7. UD2 EXCEEDING 5000 F - INCIPIENT 2'4GO 450 510 MILTING - LB l'420 i '
?
i i
j E. UO2 EXCEEDING 360 I CAL /GM- CLAD 450 500 NEGLIGIBLr NEGLIGIE RUPTURE' LB ,
i 1 S. UO2 IN RUPTURED ,
l'500 3'160 NEGLIGIELE NEGLIGIEE FUEL ROD 5' LB i
}
- 10. CHEMICAL ENERGY FROM METAL-VATER 600 10 150 REACTIOS' MV-SEC 27
=== e -'
.,-,,,a,% ,,se e,- aw
- = Nee *=ema*-am . e e. se i. memesp . _ . _ _. ._
= *- %
C'/ 11. CkS FFOM MITAL
. .. s, W ATE' REACTIO..
6SD I'SEO . 160 390 SCF H2'
~
-CORRESPOS;S 70 E00C F AS PRESENTED IN FHSR.
k l 1
--MAXICUM ROD WORTH CASE'NOT CONSIDERED CREDIELE.
THE PRESSURE IN THE PRIMARY SYSTEM DURING A REACTIVITY EXCURSION. 07-
$, THE MAGGITUDES LISTED IN TAELE 1 IS A CCT. PLEX DYNAMIC CUANTITY.
C ALCULATIONS INDI,CATE THAT FOR CASES WhERE THE FUEL DOES NOT EXCEID
~
E000 F - 3C0 CAL /CM - CONTINUED INTEGRITY OF THE PRIMARY SYSTEM VILL EE MAINTAINED.
i ,
THEEE APPEARS TC EE CONSIDERAELE.CONTECVERSY SURRCUNCING TME ASSUMP-TIONS CONCERNING.THE TRANSFER OF EXCURSICS ENERGY TO PRIMARY SYSTEM' VATER DURING MORE SEVERE EXCURSIONS VMERE A SIGNIFICANT AMOUNT CF: FUEL EXCEEDS 360 CAL /GM. SINCE NO CALCULATIONAL MODELS HAVE BEEN ACCEPIED FOR THIS TRANSIENT' VI CANNOT MAKE ANY MEASINCFUL STATEAENT RECAFDI:43 PRIMARY SYSTEM INTECRITY FOR THE ROD DROP CASES INVOLVING THE 4.2 OR 4.0 PERCENT RODS.
- . ANALYSIS CETHOD t
t i THE L ATEJT ANALYTICAL TOOLS ' AND METHODS VER~ EMPLCYED THROUGHCUT- THE Pr.ESENT ANALYSES. THE CHANGES AND THEIR EFFECTS WILL BE DISCUSSED.
?
- 1. TO INCOTsPCR ATE REACTOR SPATI AL EFFECTS I';TO THE DOPPLER FEEDS ACK l
TO THE KINETICS CALCULATION' A SPACE-TIME KINETICS ANALYSIS IS SYNTr.ESIZED BY A MARCHING CALCULATION. . INITIAL NEUTRON FLUX DISTRIEU-TIONS ASSOCIATED WITH ACCIDENT _AL REACTIVITY ADDITION ARE FIRST l
j- DETERMINED UTILIZING A THREE-CROUP' STEADY-STATE DIFFUSION CALCULA-f TION. A CORE AVERAGED DOPPLER SPATIAL WEIGHTING. FACTOR IS ESTIMATED FROM THE FLUX DISTRIBUTIONS AND ' UTILIZED IN THE POINT' KINETICS EQUATIO l TO GENERATE A SMALL INCREMENT OF POVER. IN THIS CASE' THE KIKETICS CALCULATION REPRESENTS THE AVERAGE REACTOR CONDITION.
f 4
THIS' INCREMENT OF POWER' EXPRESSED AS A FUEL TEMPERATURE CHANCE' IS THEN SPATIALLY DISTRIBUTED ACROSS THE CCRE ACCORDING TO INITI AL FLUX
{
DISTRIBUTIONS. NEW SPATIALLY DISTRIBUTED CFOSS-SECTIONS ARE_ COMPUTE 0' T,ETLECTING THE D0' ER EFFECT DUE TO THE ADDED TEMPERATUREAND ANOTHER j
f
,+ .r . , - , . .- , , . . m, - . , %,,'br.
, ..w-v,- m,e.,,-rv, ,v. r v - w ,.e c-w--- .+ & . e- =v~w.-v ,- v'+*,-e .,
. - - . . m ._ ._ -. , . m , -_ _ _ . . --.
d DIFFU:'IONICALCULATIO:',JS MADE. C07.PARISON 0F, THE EIGEt4VALUE CHAN3E IN -
(
TMIS CALCULATION TO T ElGENVALUE CHANGE RESULh11 G Th05 L A Ui IFORMLY.
DISTRIBUTED TEr.PERATURE It1CREMENT'PF0VIDES AN ACCURATE ESTIP. ATE OF.THE DCFPLER EEICHTIN:; FACTOR APPF10PRIATE FCR THE NEXT KIHETICS CALCULAT10::AL
~
STP. UTILIIINC THIS PRCCEDURE' THE CALCULATIOh IS MARCHED THROUGH TO ItE TETJ,1NATICN CF.THE EXCUP.SION.: ,. j o
e THE PF,EVIOUS CALCULATIONS DID NOT INCLU;E THIS. SPACE-TIr.E MARCHINC-ECLUTION' BUT ASSURED A FIXED POVER SHAPE VITH FIXED : DOPPLER VEIGHT . ;
i IN3 FACTOR THROU3HOUT THE' EXCURSION. THE SPACE-TIME DEPENDENT' CALCULATICf: INCLUDES THE INHERENT PCVER FLATTENIkG AS FUEL IS< HEATED t
IN THE ZONE CF THE DROPPED CONTROL BLADE. , ,
'e t +
[
t .
- 2. THE EXCURSIDIJ CALCULATION IE CT TERR,1NATED UNTIL TH" P0JER HAS
~
EEA0MED A SMALL FRACTION OF-RATED. PREVIOUS CALCULATIONS WERE TERF.I< j t
NATED AT 100 MS AFTER PEAK POWER' THUS ELIMINATING THE ADDITIONAL 20 TO 30 PERCENT OF ENERGY COSTAINED IN THE EXCURSION TAIL. THE TOTAL a
~,
INTECRATED ENERGY IS
- THEREFORE' L ARGER' 'THOUGH IT IS GENERATED CVER -
- r
. EXTENDED TIME. PERIOD.
i
- 5. THE EXCURSIONS ARE ASSUT.ED TO EE ADIAEATIC W'ITH ONLY THE D0??iER. $}
EFFICT SUPPLYING PRCMPT REACTIVITY FEED 5A0K TO TER.':INATE THE. POVER -
BUF.?T. II: PAETICULAR' NO NEGATIVE FESD5 ACK FF.CM PROMP* f00]ERATOR q E ATING IS ASSUMED. THE MAG:JITUDE OF THE REACTIVITY EFFECT DUE 70 DOFFLER BP.0ADENING IS CCSEERVATIVELY TAKEN TO BE ABOUT 5 PERCENT LESC i THAN THAT RESULTING TECX USE OF PETTUS DATE - I'- AND 13 PERCENT LESS THAN THAT US'IN3 HELLSTRAND DATA - 2 . THE TEMPERATURE DEPENDENCE OF
-)
, THE DOPPLER COEFFICIENT USED IN ALL THE ANALYSES IS BASED ON THE SQUARE- .s .
1 ,
1 ROCT OF TEF.PER ATURE FORM. EXPERIMENTAL DATA FOR OXIDE FUEL ARE FIT M !
PRECISELY BY THIS FORM IN BOTH DIFFERENTIAL MEASUREMENTE - 1*2'3 - AND i GROSS CORE DYNAMIC MEASUREMENTS - 4.
[
i -
i DOPPLER COEFFICIENTS ARE AFFECTED PRIMARILY BY WATER-TO-FUEL RATIO AND 70 A LESSER EXTENT BY FUEL' DENSITY AND GEOMETRY. BIG ROCX PDIN j FUEL TYPES ARE ALL SIMILAR IN THESE PARAMETERS AND' DUE TO C07.P 5
IFTECTS' ARE SIMILAR IN DOPPLER COEFFICIENT. THE 13 PERCENT DIFF l' IN DOPPLER COEFFICIENTS USED IN THE CALCULATICNS IN REFERENC i
I RELOAD AND STANDARD FUEL VAS CALCULATIONAL AND NOT A PHYSIC t
I . .. . t . s w. r. . .'s. . u . - . . %,- .
i
+
m*** v we ew t -seep p eau.e, . _
ep. S 9---, *,- ..e % w w E ,,, u .,-.we.,. , . - - - _ . - .,[.,~.m 3 ,,m'.-
r , , - , ,- , v~-e u %,. p o,- -.
. . -. . . . - . . - . . . _ . . . . . ^ ^" '
W TlE' STANDARD FUEL COEFFICIENT"HAS BEEN' CORRECTED BY OSE'0FTA"MCRC ~^:
n.
. I.CCUht.TE EFFECTIVE ' SUEraCE-TC-MASS AND RES0"ANCE ..TEGR AL? TREATICEt:T.
IU - ADDITION' THE ZR CORE CALCULATIONS HAVE BEEN RE-EVALUATED.> THE-T l RESULTA"7 VALUE FOR BOTH FUEL TYPES IS .t:EG ATIVE l'.1 TIMES 10' TOI HE 8..
MIKUS 5 DELTA K OVER.K PER DEGREE ~F AND{IS.QUCTED11N.CHAN2E NO.
THE INITI AL POWER .IS ASSUMEC TO BE 10 TO THE MINUS 6 0FJ RATED IN
. . . . . .. < . }
- 4. .
t THE HOT STAT:DBY CONDITION. ' THE PREVIOUS : AN ALYSISl ASSUMED. '10' TO. THE'
\
HII;US 10. HOVEVER' RECENT CALCULATIONS REVEAL'THAT 10 TO THE MINUS:
{
6 IS THE MINIMUM SOURCE LEVEL AT,' HOT. ST ANDBY CONDITIONS. THIS IS THE 4
RESULTAN,T LEVEL D'UE TO SOURCE NEUTRON AND SPONTANECUS FISSION NEUTRON:
INTRODUCTION FOR THE LOWE'T. S CORE' REACTIVITY AT WHICH A PROMPT CRITICAL ,
i- A*CIDENT COULD. 0CCUR WITH A 0.046 DELT A X ACCIDENT.' THIS REACTIVITY
-INCREAS-IS APPROXIMATELY 0.961' AT WHICH CORE MULTIPLICATICH IS 25.'6. ,
. IU" It;ITI AL POWEP KESULTS 'IN A SLIGHT REDUCTICN IN ACCIDENT EEVERITY. ' !
- 5. REACTIVITY IS ADDED ON THE' ACTUAL l WORTH-DISTANCE RELATIONSHIP "E" CURVE' ASSUP.ING THE ROD IS FULL IN VHEN IT COMMENCES TO FALL.'- TH
~
PT.LVIOUS ANALYSIS USED A. MO.RE CONSERVATIVE APPROACH EY. INSERT ELACTIVITY AT THE MAXIMUM RATE AVAILAELE.
C. THE LOCAL PEAKING HAS.BEEN INCREASED TO REFLECT THE SPECIFIC P OF THE SMALL CORNER FUEL RODS. . THESE RODS. HAVE THE' HOTTEST c LO PEAXINC FROM AND EXCURSION STANDPOINT.
,REFEREt.CES . .
i 1. PETTUS' W. G.* " RESONANCE ABSORPTION IN U-CIE METAL AND OXIDE RODS'"-
g EAV-1244*.19C2.
- 2. HELLSTRAND' E.'. ET AL' "THE TEMPERATURE COEFFICIENT ,0F THE RESONANCE INTEGRAL FOR URANIUM METAL AND OX1DE'" NS AND EB' 497* 1960.
I
- 3. SPAND*-A. H.' " ANALYSIS OF DOPPLER-LIMITED EXCURSIONS IN A WATER-
{'
MODERATED OXIDE CORE'" NS AND El9'.172' 1964.
- 4. " MULTI-RECION REACTOR LATTICE STUDIES MICROSCOPIC LATTICE P f
IN SIN 3LE AND MULT1-REGION CORES'" WCAP-454' JUNE 1961.
?
II. CORE SPRAY INFORMATION ,
. l ,
T): FCLLCWING INFORMATION SHOULD ANSVER QUESTIONS RAISED REGARD
~
' . _SPCLY. AH1_ElllLDit? EDU AY - ~~...u.~. __.._.
.aa _ a _, .. _.,u._.a _ _ _ . , . _ _ . - , _ . , . . . . _. _ , . , . . _ _ . . , _ . .a _ _ ~ , _
~
THE E:. CLOSURE PRESSURE PEAX.GIVEN IN FIGuRT 3 0F THE SCnMITTAL -
", . *. .,1... .
. [ T-CHANCE !!O. 8 - TS DETERMII ED BY_THE TOTAL' ENERGY RELEASED It! THE 15-SECOND ELCVDOWN PERIOD.AND IS.NOT LIMITED EECAUSE OF CCRE SPT.AY.-
1
- 2. NEED FOR THE CORE SPTAY'TO COUNTERACT THE'HYPOTHETICAb METAL-VATER '
l l
P.EACTION DCEE NOT EEGIN'UNTIL 50 TO 100 SECONDS.AFTER THE ELOUDOW::' .
AC ILLI STRATED IN FIGURE 1 0F THE SUBMITTAL. ,
- 3. CORE SPPAY VALVE ACTUATION TAKES PLACE AT 200 PSI REACT 0Tt PRESSURE -
- VMEN WATER LEVEL IS SIMULT ANEOUSLY LOV.' . CORE SPT.AY FLOW 'CT' AOUALLY INCREASES OVER THE NEXT 3 TO. 4 SECONDS AS THE BLOWD0VN QUICXLY REDUCEC
, . VESSEL PRESESRE AND PERMITS FULLL CORE SPRAY FLOW CORRESPONDI::G TO
. 'THE ENCLOSURE PRESSURE. THESE FEV SECONDS '0F PARTI AL FLOV ARE . y i
> INCONSEQUENTIAL. ,SEE TABLE.11.
t
., . 4. .AFTEP. SEVERAL MINUTES - REDUCED TO 5 MINUTES - THE CONTAINMENT-SPRAY COMES ON-IN PARALLEL ViTH THE CORE SPRAY. CORE SPRAY DRCPS TO APPROXIMATELY 91.5 PERCENT'0F ITS SINGLE FLCV VALUE. SEE TAELE 11.
- 5. AS Et:CLCSURE PRESSLRE. I DROPS TO ATMOSPHERIC LEVEL CVER THE ENSUING II MINUTES AND HOURS' THE CORE SPRAY IN PARALLEL FLOV INCREACES TO THE- ,;
INITIAL CORE SPRAY RATE.
TAELE 11 - BIG ROCK PCINT - CORE AND ENCLOSUhE SPRAY PERFORMANCE.
SPRAY N0ZZLE FLOV - GPM CONTAINMENT SPRAY SPRAY N0ZZLE FLOW - GPM k DISCHARGE PRESSURE CORE SPRAY CORE SPRAY- . CONTAINMENT SPRAY i -
VHIN PARALLEL VHEN PARALLEL.
PSIA ALONE
'. 15 400 363 352
- s j 7
, 30 373 345. 323' 50 338 316 280 )
100 235 220' .170 a ,
i 150' 80 .70 48 I
l
. 165 0 0. O L . _ _ u _ . . _ . -
di . . -. . ';
'7 ". ~ II M Fl.*M: 20C: PSI C?c-~) SPEAY" f.CTUATICM - SEC-e 3.5 .
'3.2 -
2.8 1.9
.0.9 t
0.7 . .
FHSR A!;D TECHNICAL SPECIFICATICS D ATA - AFE CORRECT A!!D CONSISTENT. - FLO' S CITED CCERESPOND TO 00!:DITIONS WHEN SPRAY N0ZZLE DIFCHARGE PRESEU?.ES ARE e
r THE CONTAINMENT PRESSURE TP.A:SIENT FOLLOUII:0 THE MCA HAS SEEN RE-EVALUATED FOR THE CASE WHERE BOTH THE. CORE AND BUILDINC' SPRAYS' ARE INCPERATIVE. THE CALCULATIONS SHOV NO CHAT:3E II: THE, PRESSURE TU.:SIE::T -[
- URVE CUT TO ABOUT 20 SEC. THE!: THERE IS A SLOV RISE IN PRESSURE TO A ,
.,0' SECONDARY PEAK OF AEOUT 43. PSI A AT APOUT: 20'000 SEC. - THIS CA' CULA- [
TIC: TOCK'INTO ACCOUNT THE FACTORS NOTED I'if THE FHSR AND'.IN 035 RECEt:T F CHA!GE REQUEST SUBMITTAL PLUS A NEW SET OF CONTAINMENT VESSEL HEAT DISSIPATION COEFFICIENTS. THE NEk' SET OF. HEAT DISSIPATION COEFTICIENTS i
4 WERE DERIVED FROM EXPERIENCE GAINED HEATING BIG ROCK POINT CCNTAlt:"i i
) VESSEL WHERE A HEATING BOILER THREE TIMES THE CALCULATED IZE WAS- l NECESSARY' 70 PROVIDE PROPER HEATING.
/
R. L. HAUETER' ,
l'
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i, .
d 4 ,
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