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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
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ACCELERATED DOCUMENT DISTMBUTION SYSTEVl REGULATORINFORMATION DISTRIBUTION ITEM (RIDE)
ACCESSIOR NBR:9212100008 DOC.DATE: 92/11/23 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION YUNG,Y.Y. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION JONES,R.C. , Office of Nuclear Reactor Regulation, Director (Post 870411
SUBJECT:
Forwards supplement to 920916 response to NRC request for .
addi info on VIPRE-Ol MOD-02 Documentation EPRI NP-2511-CCM, VIPRE-Ol, "Thermal-Hydraulic Analysis Code for Reactor Cores."
DISTRIBUTION CODE: YGOZD TITLE: Generic Material with no COPIES RECEIVED:LTR ( ENCL Specific Distribution T 2 SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JONES,R.C. 1 1 INTERNAL: ACRS 6 6 EG FILE 1 1 RES/DSIR/EIB 1 1 RGN1 1 1 RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 "1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 G02-92-256 November 23, 1992 Mr. Robert C. Jones, Chief Reactor Systems Branch Division of Systems Technology US Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Jones:
Subject:
SUPPLEMENT TO RESPONSE TO VIPRE-01 MOD-02 REVIEW QUESTIONS
Reference:
Letter dated September 16, 1992, from YY Yung, VMG to RC Jones, USNRC, "Responses to Request for Additional Information on VIPRE-01 MOD-02 Documentation EPRI NP-2511-CCM, VIPRE-01: A Thermal-Hydraulic Analysis Code for Reactor Cores (TAC No. M79498)"
This letter provides the supplement to Reference 1 as was discussed during the telephone conference on November 9, 1992, with Harry Balukjian of your staff and Heidi Komoriya of International Technical Services, Inc.
Please contact me at (509) 377-4366 if there are any questions.
Sincerely, tt / ggtl$ ,
Y. Y. Yung, Chairman (PE16)
VIPRE-01 Maintenance Group
/bw CC: H. Balukjian, NRC GS Srikantiah, EPRI J. Cuta, Battelle Pacific Northwest laboratories VIPRE Maintenance Group tDocument Control-Desk;NRC RR Assa, NRC A Jh( ~> ~
9VXaibOO08 9Zaza3 pQI PDR ADOCK 05000397.
P PDR
~
C i
Supplement to Response to VIPRE-01 MOD-02 Review Questions h
Previous responses to questions on the effects of VIPRE-01 results of the changes between MOD-01 and Mod-02 have been submitted (Refer to letter of 9/16/92 from YY Yung of WPPSS to RC Zones of the USNRC, reference no. G02-92-219). The response included a table showing the magnitude and direction of the differences in code results for the test case of a specific change.
The reviewers have asked for additional information on the effect of these changes on PWR transient applications, particularly in regard to the effect of changes 125 and 128, which correct errors in the thermal properties of the zircaloy fuel cladding. To address this concern, a calculation has been performed for a typical PWR transient application of the VIPRE-01 code. A number of utility applications of the code are documented in Section 10 of Volume 4 of the VIPRE-01 documentation. (Refer to EPRI-NP-2511-CCM; Volume 4 Applications.) The FSAR loss-of-flow transient for the Comanche Peak Unit 1 nuclear station, described in Sec. 10.5, was selected for this calculation. The infoxmation available in the document describing the VIPRE model for this calculation is faixly complete, but used. As a result, it does not include the radial power distribution it was necessary to assume a reasonable distribution, based on the 'typical'alues published in the Comanche Peak FSAR.
Values were selected that gave an initial MDNBR that was close to the initial value shown in Sec. 10.5. (For this calculation, the initial value of MDNBR was 1.576 for the MOD-01 results, and 1.577 for the MOD-02 results. This is consistent with the value plotted in Figure .10.5-6 on p. 10-90 of Volume 4.) However, because the xadial power distribution for the calculation in Sec. 10.5 is not, known, it is not reasonable to directly compaxe the documented results to the current calculation. It is sufficient to note that the results are of approximately the same magnitude, and show the same txends. The significant comparison is in reviewing the xesults obtained with MOD-02 and MOD-01 in the calculation presented here.
An input file was constructed for the txansient described in Section 10.5, and was xun on the current released version of VIPRE-01/MOD-02. The same input file was then run on the master version of VIPRE-Ol/MOD-01. (A listing of the input file is attached.)
The results are shown in the attached tables; Table 1 for the MOD-01 results, and Table 2 for the MOD-02 results. As can be readily seen, the two versions of the code show the same trend in the transient, and the magnitudes of the differences are essentially the same as those displayed in the BWR transient calculation presented in the previous response.
~ ~
t,
Table 1 -- Summary of Results with VIPRE-01/HOD-01: Loss-of-flow Transient in Comanche Peak Unit 1
- ~*** operating conditions *********** *critical location*** hot channel conditions ***rod temperatures**
- system inlet inlet average *
- axial*mass flux heat flux* peak peak *
- pressure enthalpy mass flux heat rate *
- hot hot level*(mlbm/hr- equil. (mbtu/hr-* clad centerline* time case* (psia) (btu/ibm) (mlbm/hr-ft2) (btu/sec-ft) ~mdnbr"channel rod (in.) >> ft2) quality ft2) ~ (F) (F) * (sec) *
- 0 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 1 2220.0 566.48 2.620 5.393 1.576 4 6 94.5 2.349 -0.063 0.442 657.6 3906.0 0.000 1 2220.0 566.48 2.541 5.393 1.537 4 6 94.5 2.262 -0.057 0.442 657.7 3906.0 0.500 1 2220.0 566.48 2.463 5.393 1.490 4 6 94.5 2.161 -0.049 0.442 657.9 3906.0 1.000 1 2231.1 566.48 2.384 5.393 1.452 4 . 6 94.5 2.067 -0.044 0.441 658.7 3906.0 1.500 1 2242.2 566.48 2.306 5.393 1.413 4 6 99.0 1 ~ 925 -0.020 0.419 659.4 3906.0 2.000 1 2279.2 566.48 2.247 5.393 1.402 4 6 99.0 1.875 -0.023 0.418 661.6 3906.0 2.500 1 2316.2 566.48 2.188 5.393 1.390 4 6 99.0 1.829 -0.026 0.417 663.7 3906.1 3.000 1 2353.2 566.48 2.129 5.393 1.376 4 6 99.0 1.781 -0.028 I 0.417 665.8 3906 ' 3.500 1 2382.8 566.48 2.070 5 '93 1.355 4 6 99 ' 1.726 -0.028 . 0.417 667.5 3906.5 4.000 1 2392 ' 566.48 2.011 5.393 1.478 4 6 94.5 1.714 -0.070 0.411 667.6 3831.5 4.500 1 2368.0 566.48 1.952 5.393 1.642 4 6 94.5 1.719 -0.086 0.381 665.7 3720.3 5.000 1 2334.9 566.48 1.893 5.393 1.851 4 6 90 ' 1.734 -0.117 0 '60 663.2 3564.7 5.500 1 2289.2 566.48 1.834 5.393 2.015 4 6 85.5 1.716 -0.133 '.343 660.0 3399.5 6.000
Table 2 -- Summary of Results with VIPRE01/MOD-02: Loss-of-flow Transient in Comanche Peak Unit 1
- operating conditions *********** *critical location*** hot channel conditions ***rod temperatures**
- system inlet inlet average *
- axial*mass flux heat flux* peak peak *
- pressure enthalpy mass flux heat rate *
- hot hot level*(mlbm/hr- equil. (mbtu/hr-* clad centerline* time
- case* (psia) (btu/ibm) (mlbm/hr-ft2) (btu/sec-ft) *mdnbr*channel rod (in.)
- ft2) quality ft2) * (F) (F)
- * * * * * * * * * * * * * * * * * * * * * * * * * * * *
2220.0 566 2220.0
'8 566.48 2.620 2.541 5.393 5.393 1.577 1.539 4
4 6
6 94.5 94.5 2.355 2.270
-0.063
-0.057 0.442 0.442 657.6 657.7 3959.8 3959.8 0 F 000 0.500 1 2220.0 566.48 2.463 5.393 1.493 4 6 94.5 2.171 -0 '49 0.442 657.9 3959.8 1.000 1 2231.1 566.48 2.384 5.393 1.455 4 6 94.5 2.080 -0 '44 0.441 658.7 3959.8 1.500 1 2242.2 566.48 2.306 5.393 1.416 4 6 94.5 1.987 -0.038 0.441 659.5 3959.8 2.000 1 2279.2 566.48 2.247 5.393 1.406 4 6 99.0 1.893 -0.023 0'.418 661.6 3959.8 2.500 1 '316.2 566.48 2.188 5.393 1.394 4 6 99.0 1.847 -0.026 0.417 663.7 3959.9 F 000 1 2353.2 566.48 2.129 5.393 1.380 4 6 99.0 1.798 -0.029 0.417 665.9 3959.6 3.500 1 2382.8 566.48 2.070 5.393 1.359 4 6 99.0 1.744 -0.028. 0.417 667.6 3959.8 4.000 1
1 2392.7 2368.0 566 '8 566.48 2.011 1 ~ 952 5.393 5.393 1.324 1.474 4
4 6
6 99.0 94.5 1.677 1.633
-0 '20
-0.060 0.418 0.403 668.2 666.3 3960.6 3855.5 4.500 5.000 1 2334.9 566.48 1.893 5.393 1 ~ 698 4 6 90.0 1.696 -0.100 0.380 663."7 3711.3 5.500 1 2289.2 566.48 1.834 5.393 1.874 4 6 90.0 1.687 -0.106 -
0.350 660.4 3553.7 6.000
input File for MOD-01 to MOD-02 Comparison:
Typical PWR Transient Application
<</ <<<<***<<*<<*<<<<*<<<<***<<<<<<<<<<<<<<<<<<******<<<<***<<****<<* /*
- / PHR transient test, comparing MOD2 with MOD1 /*
- / A<<<<*<<<<****<<*<<<<<<<<<<<<*<<<<<<*<<<<*<<<<A<<<<<<<<*<<*<<<<<<*<<<<*<</<<
<</
<<vipre.l 1,0,0
- vipre.2 Comanche Peak Unit 1: FSAR loss of floe test (VIPRE Vol. 4; sec. 10.5)
<<geom.l geom, 16, 16, 32 g Og Og 0
<<geom.2 144.0,0.0,0.5
<<geom 4 1, 0.0590, 0.6299, 0.4406g 2g 3,0.068, 0.496g 13g0 122g0 ~ 992 2, 0.1362, 1.1750, 1.1750, 3, 3,0.122, 0.496g 5,0.122,0.496, 13, 0.244,0.992 3, 0.1180, 1.2598, 0.8812, 2, 4,0.068, 0.496, 6,0.122,0.496 4, 0.0590, 0.6299, 0.4406, 1, 7,0.122, 0.496 5, 0.1362, 1.1750, 1.1750, 2, 6, 0.122, 0.496g 13,0.244g0.992 6, 0.1362, 1.1750, 1.1750, 2, 7, 0.122, 0.496g 9,0.122,0.496 7, 0.1362, 1.1750, 1.1750, 2, 8,0.122, 0.496g 10,0.122,0.496 Sg 0.0590, 0.6299g 0.4406, 1, 11,0.068, 0.496 9, 0.1180, 1.2598, 0.8812, 2, 10,0.068, 0.496g 13,0.244,0.992 10g 0 '180g 1 ~ 2598g 0 '812g 2g llg 0 122g 0 '96g 12,0.068,0.496 llg 0 '180g 1 2598g 0 '812g lg 13gO ~ 244g 0 '92 12, 0.1180, 1.2598, 0.8812, 1, 13, 0.312, 0.992 13, 3.4518, 30.6169, 28.3457, 1, 14, 1.054, 8.466 14, 38 '089, 348.0445g 310.1883, 1, 15, 3.162, 12.699 15,190.5445,1740.2225, 1550.9415, 1, 16,7.378,25.398 16, 685.9602, 6264.8010,5583.3894
-1
- rods' 1, 1, 1.60, 1, 1,0.125, 13,0.375 211631,2,025,13,075 3g lg 1 63g lg lg 0 ~ 25g 2g 0 ~ 25g 3g 0 ~ 25g 13g 0 ~ 25 4,1,1.59,1, 2, 0.25, 5, 0.25, 13, 0.50 5,1,1.59,1, 2, 0.25, 3g 0.25, 5, 0.25, 6, 0.25 6,1,1.63,1, 3, 0.25, 4, 0.25, 6, 0.25g 7, 0.25 7glg1 60glg 4gO ~ 125g 7g 0 ~ 25g Bg0 ~ 125 8, 1, 1.58, 1, 5, 0.25, 13, 0.75 9,1,1.58,1, 5, 0.25, 6, 0.25, 9, 0.25, 13, 0.25 10g lg 1 61g lg 6g 0 ~ 25g 7g 0 ~ 25g 9g 0 25g 10g 0 ~ 25 ll, ~
1, 1.61, 1, 7, 0.25, 8, 0.25, 10g 0 0 75
'5, ll, 0.25 12g lg 1 58g lg 9g 0 ~ 25g 13g 13g lg 1 59g lg 10g 0 ~ 25g llg 0 ~ 25g 12g 0 ~ 25g 13g 0 ~ 25 14, 1, 1.57, 15g lg 1 54g 1,
lg ll, 12g 0.25, 13, 0.75 0 25g 13g 0 75
~
16, 1, 1.53, 1, 12, 0.25, 13, 0.75 17,2g 1.53g 1, 13, 18.0 18,2,0.99, 1, 14,264.0 19, 2, 1.08, 1, 15g 1320.0 20,2,0.97,1, 16,4752.0 0
<<rods.62
, ig nuclg 0.374g 0.3225g 9,0.0,0.0225
<<rods.63 Og Og Og Og Og 900 ~ Og 0 ~ 95g 0 ~ 0
1 4'fl lg
,l I
II 1
- rods.62 2gdnmygO ~ 374 corr, 1, 1,0
- corr.2 levy, homo, homo, none
- corr.6 ditb,thsp,thsp,w-31,cond,g5.7
~corr.9 w-31 icorr.ll 0.038,0.046,0.86 mixx,0,0, 1
- beta for gap li (connecting channels 1 and 3) 0.0253,0.0, 7
- beta for gap 2g (connecting channels 1 and 13) 0.0380, 0.0, 2 ~ beta for gap 3, (connecting channels 2 and 3) 0.0380,0.0
- beta for gap 4, (connecting channels 2 and 5) 0.0253,0.0, 2
- beta for gap 5g (connecting channels 2 and 13) 0.0380,0.0, 2
- beta for gap 6g (connecting channels 3 and 4) 0.0380,0.0, 7
- beta for gap 7, (connecting channels 3 and 6) 0.0380,0.0
- beta for gap Bg (connecting channels 4 and 7) 0.0380,0.0, 7 ~ beta for gap 9i (connecting channels 5 and 6) 0.0168,0.0, 7
- beta for gap 10i (connecting channels 5 and 13) 0.0380,0.0, 7
- beta for gap lip (connecting channels 6 and 7) 0.0380,0.0
- beta for gap 12, (connecting channels 6 and 9) 0.0380,0.0, 2 ~ beta for gap 13, (connecting channels 7 and 8) 0.0380,0.0, 7
- beta for gap 14$ (connecting channels 7 and 10) 0.0380,0.0, 7
- beta for gap 15$ (connecting channels 8 and 11) 0.0380,0.0
- beta for gap 16, (conneoting channels 9 and 10) 0.0215,0.0, 7
- beta for gap 17i (connecting channels 9 and 13) 0.0380,0.0, 7
- beta for gap 18, (connecting channels 10 and ll) 0.0380,0.0, 7
- beta for gap 19, (conneoting channels 10 and 12) 0.0215,0,0
- beta for gap 20, (connecting channels 11 and 13) 0.0190,0.0, 7
- beta for gap 21f (connecting channels 12 and 13) 0.0022,0.0, 7
- beta for gap 22/ (connecting channels 13 and 14) 0.0015, 0.0, 7 ~ beta for gap 23, (connecting channels 14 and 15) 0.0007,0.0
- beta for gap 24, (connecting channels 15 and 16) drag,1,1,4
- drag.2 0.0155, 0.0, 0.0, 64 .0,-1.0,0.0
- drag.8 2 ~ 66' ~ 20' ~ Og 0 ~ Oi 0 ~ Oi 0 5 grid, 0, 2
-1,7
- grid.6 0~ 75'i 21 ~ 35 ~ lg 42 ~ 35'i 62 ~ 45 , 1, 83.05, 1 103.55, 1, 124.15, 1 0
oper, 1,2,0, 1
~oper.2 0.0,0.0,2.6,0.0
- oper.5 2220.0, 565.1,2.62, 68.28,0 0 ~
- 2220 ',565.1,2.62, 0.00,0.0
- oper.l3 "- system pressure forcing function 0 ~ Og 1 OOJ 1 0~ 1 00~ 2 ~ Og 1 01~ 3 ~ 8~ 1 07 4 ~ 4J 1 OBJ 5 ~ 3g 1 06' Og 0 ~ 99' ~ 5g 0 ~ 98 9.5,0.97, 13.0,0.96, 16.5,0.94, 30.0,0.93
~oper.l5 -- inlet flow forcing function 0 ~ 0~ 1 00 ~ 2 ~ Og 0 ~ 88~ 6 ~ Og 0 ~ 70' ~ Sg 0 ~ 58 15.5,0.43, 25.0,0.33, 30.0,0.30
- oper.16 -- power forcing function 0.0, 1.00, 4 .5, 1.00, 3.8, 0.81, 5.5, 0.18 5.5, 0 '6, 15.0, 0.07, 30.0, 0 '3 cont
- cont.2 6.0, 12, 20,50, 3,2 Og 0 ~
- cont.3 0.0 *default all convergence criteria
- cont.6 5, 13, 0, 14 ~ 13, 0, 1, 1, 0, 0, 0, 1, 1, 0
- cont.8 -- channels to be printed 1 J 2 ~ 3 ~ 4g 5g 6g 7g Bg 9g 10~ 1 1 ~ 12 ~ 13
- cont.10 -- rods to be printed lg 2 3 4g 5J 6/ 7g Bg 9~ 10 llg 12'3'4
~cont.ll -- CHF channels to be printed
~ ~ ~
l~ 2g 3~ 4~ 5g 6g 7g Bg 9g 10'lg 12~ 13 endd 0