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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206S9151999-05-11011 May 1999 Forwards Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. Section 16.11-16.2 Has Been Revised to Apply Guidance of NUREG-0133 for Performing Gaseous Effluent Dose Pathway Calculations ML20206K1341999-05-0303 May 1999 Forwards 1999 Interim UFSAR for McGuire Nuclear Station. UFSAR Update Includes Items Relocated During Improved Tech Specs Implementation.Next Regular UFSAR Update as Required 10CFR50.71(e) Is Due in Oct 1999 ML20206F3321999-04-28028 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for McGuire Nuclear Station. Listed Attachments Are Contents of Rept.Revised ODCM Was Submitted to NRC on 990203 ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20206B4791999-04-20020 April 1999 Requests Exemption from GDC 57 Re Reactor Containment - Closed Sys Isolation Valves,As Described in 10CFR,App a for Containment Penetrations M393 & M261.Detailed Technical Evaluation & Justification for Exemption Request,Encl ML20205S9731999-04-19019 April 1999 Submits Info Re Quantity of SG Tubes Inspected,Tube Indications of Imperfections & Tubes Removed from Svc by Plugging,Per TS 5.6.8,part B 05000369/LER-1999-001, Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence1999-04-16016 April 1999 Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence ML20205P8891999-04-13013 April 1999 Forwards Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Feb 1999 Encl ML20206K3561999-04-13013 April 1999 Forwards Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual. Significant Changes Are Marked by Vertical Bars on Right Margin ML20205K5131999-04-0707 April 1999 Forwards Complete Response to NRC 981209 & 990105 RAIs on Question 11 Re LARs for McGuire & Catawba Nuclear Stations. Addl Info Received from W & Contained in Encl W ML20205B6011999-03-23023 March 1999 Requests That NRC Place Technical Interface Agreement 97-02 Re URI 96-11-03,raising Operability & Design Criteria Conformance Issues Re Hydraulic Snubbers Installed at Plant & NRR Response on Dockets to Provide Record of Issue ML20205C4611999-03-23023 March 1999 Submits Correction to Violation Against 10CFR50 App B, Criterion VII, Control of Purchased Matl,Equipment & Svcs, Issued to McGuire Nuclear Station on 980807 ML20205B6161999-03-23023 March 1999 Provides Addl Info & Correction to Typo in Re License Bases Record Change Re License Amend Submittals ,approved as FOL NPF-9 & NPF-17,amends 184 & 166, respectively.Marked-up TS Pages,Encl ML20204J0051999-03-19019 March 1999 Forwards Response to 990127 & 28 RAIs Re GL 96-05 for Catawba & McGuire Nuclear Stations ML20204E1791999-03-18018 March 1999 Reflects 990318 Telcon Re License Bases Record Change for License Amend Submittals ,approved as Amends 184 & 166,respectively for Licenses NPF-9 & NPF-17.TS Pages Encl ML20204C8821999-03-15015 March 1999 Forwards Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Jan 1999 Encl ML20207C2071999-02-25025 February 1999 Informs of Revised Expected Submittal Date of Proposed License Amend Presented at 990127 Meeting Re Soluble Boron & Boraflex.Util Plans to Submit Proposed License Amend in First Quarter of 1999 ML20207C7691999-02-22022 February 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998. Rept Provides Tabulation of Number of Station,Utility & Other Personnel Receiving Exposure Greater than 100mRem/yr Followed by Total Dose for Each Respective Worker ML20207C6851999-02-22022 February 1999 Forwards Revised TS Bases Pages,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20206S3341999-01-28028 January 1999 Forwards Proprietary & non-proprietary Responses to NRC 981209 & 990105 RAIs Re Util Lars,Permitting Use of W Fuel at McGuire & Catawba Stations.Proprietary Info Withheld,Per 10CFR2.790 ML20199E0081999-01-12012 January 1999 Forwards MOR for Dec 1998 & Revised MOR for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199C9861999-01-0707 January 1999 Forwards Annual Lake Norman Environ Summary Rept for 1997,as Required by NPDES Permit NC0024392,including Detailed Results & Data Comparable to That of Previous Years.With Corrected Pages 3 & 19 to 1994-95 Lake Norman Creel Rept 1999-09-09
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML19327B2491989-10-0606 October 1989 Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept. ML20247G4991989-03-30030 March 1989 Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790) ML20235M8971989-02-10010 February 1989 Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790 ML20205Q6331988-11-0202 November 1988 Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected ML20195B6091988-10-21021 October 1988 Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W ML20207L9221988-09-26026 September 1988 Requests That Proprietary Rept WCAP-10988 Re Response to NRC Questions on COBRA-NC/Model 3 Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20207L7651988-08-30030 August 1988 Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20151H9381988-07-25025 July 1988 Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants ML20151F7661988-03-29029 March 1988 Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld ML20234C2231987-12-28028 December 1987 Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld ML20234D1101987-12-14014 December 1987 Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld ML20236C0261987-10-22022 October 1987 Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790) ML20236H4971987-07-29029 July 1987 Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid ML20236B4141987-07-13013 July 1987 Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid ML20212R4711987-04-15015 April 1987 Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid ML20206E7851987-04-0202 April 1987 Confirms Intention to Use FOAM2 Computer Program as Part of ECCS Evaluation Model for Westinghouse Designed Plants. Review of Applicability of Code to Westinghouse Designed Plants Requested Prior to 880701 NRC-87-3194, Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted1987-01-0707 January 1987 Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted ML20213H0151986-11-14014 November 1986 Forwards Proprietary Draft 1 to BAW-10165P, FRAP-T6-B&W Computer Code for Transient Analysis of LWR Fuel Rods. Rept Submitted to Permit Interaction Between NRC & B&W to Support Util Schedule Needs.Rept Withheld (Ref 10CFRF2.790) NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986 Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P ML20203M6321986-08-29029 August 1986 Forwards Proprietary Draft 1 to BAW-10164P, RELAP/MOD2 - B&W.Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis, Per 860714 Licensing Plan for ECCS Methodology.Rept Withheld (Ref 10CFR2.790).Affidavit Encl ML20212B8741986-08-0101 August 1986 Requests That WCAP-11224 Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20199F3121986-06-19019 June 1986 Requests Summary of 860527 Meeting W/Util to Discuss Licensee Plans to Shot Peen Unit 1 Steam Generator Tubes & Results of Recent Unit 2 Steam Generator Tube Insps ML20198J4621986-05-23023 May 1986 Forwards Proposed Licensing Plans for Safety/Eccs Analysis Submittals for Facility Reloads.Comparison W/Original Licensing Plans Provided NRC-86-3112, Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl1986-03-18018 March 1986 Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl ML20138A1331986-03-12012 March 1986 Forwards Draft McGuire Bart Evaluation Model Analysis W/Upper Head Injection (Uhi) Removed from Svc.Results Preliminary.Discussion of Calculated ECCS Performance W/O Uhi Encl as Requested ML20137L0391985-12-0606 December 1985 Requests Withholding of Proprietary Info from Public Disclosure (Ref 10CFR2.790) ML20205H3571985-09-19019 September 1985 Requests Proprietary Resistance Temp Detector Bypass Elimination Licensing Rept for McGuire Units 1 & 2 Be Withheld (Ref 10CFR2.790) ML20211K7841985-04-25025 April 1985 Forwards Affidavit for Withholding Proprietary McGuire Units 1 & 2 Tubesheet Region Plugging Criterion (Ref 10CFR2.790).Nonproprietary Version Encl.Proprietary Version Withheld ML20135E2551984-06-27027 June 1984 Requests That WCAP-10585, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for McGuire Units 1 & 2, Be Withheld (Ref 10CFR2.790) ML20087M4131984-03-14014 March 1984 Requests Withholding of Proprietary Info Requested by Util from Public Disclosure (Ref 10CFR2.790).Affidavit AW-76-60 Encl ML20079R6891983-06-17017 June 1983 Provides Info Re DS-416 Undervoltage Trip Attachments to Be Utilized in NRC Evaluation of Facility,Per B Wright Request ML20151H7721983-04-0404 April 1983 Application for Withholding Proprietary Info Re Westinghouse Reactor Protection Sys/Esf Actuation Sys Setpoint Methodology (Ref 10CFR2.790) ML20070C7631982-12-10010 December 1982 Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested ML20067B6101982-11-17017 November 1982 Requests Withholding of Proprietary Matl Re RCS Total Flowrate Vs R1 & R2 - Four Loops in Operation (Sts),Per Encl Affidavit AW-76-60 ML20052C6361982-04-29029 April 1982 Requests Withholding of Proprietary Info Re Power Level Increase & Authorizes Use of Info by Duke Power Co. Affidavit Encl ML20038B2281981-11-25025 November 1981 Authorizes Util to Use Proprietary Info.Withholding of Info from Public Disclosure Requested (Ref 10CFR2.790) ML20038C0241981-10-29029 October 1981 Requests Withholding of Proprietary Version of Clasix Computer Program for Analysis of Reactor Plant Containment Response to Hydrogen Release & Deflagration, (Ref 10CFR2.790) ML19338E9961980-09-25025 September 1980 Authorizes Use of Encl Affidavit in Support of Duke Power Co Application for Withholding CAW-80-60 Re Qualification of safety-related Instruments.Util Nonproprietary Response to NRC Questions Re Barton Transmitters Encl ML19269H4391980-07-16016 July 1980 Forwards Final Rept Re Potential Problem in safety-related Overcurrent Relays.Problem Was Random in Nature & Not Generic ML19309G0531980-04-25025 April 1980 Forwards Update to Util 800211 Ltr Re Potential Problem in safety-related Overcurrent Relays.Failure of Silicon Controlled Rectifier within Relay Traced to Migrating Copper Into Bulk Silicon Matl.Less than 0.1% Failure Rate Observed ML20126B9341980-02-12012 February 1980 Confirms 800207 Telcon Re Failure of Valves.Forwards Part 21 Rept 1989-03-30
[Table view] |
Text
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9 1 Westinghouse PowerSystems e wem Electric Corporation S'r'*
- b 3M MrugiFemyiams 15230 03%
September 26, 1988 CAW-88-105 Dr. Thomas Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commissior Washington, D.C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION Fh0M PUBLIC DISCL0sURE
Subject:
Response to NRC Questions on COBRA-NC/Model 3 (WCAP-10988)
Dear Dr. Murley:
The proprietary material for which withholding is being requested in the reference letter by the ruke Power Company is further identified in an affidavit signed by the l owner of the proprietary infonnation, Westinghouse Electric Corporation. The affidavit, which acccrepanies this letter, sets forth the basis on which the infonnation may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10CFR Section 2.790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same 3
technical type as that proprietary material previously suttnitted with Application for Withholding AW-76-045.
Acconfingly, this letter authorizes the utilization of the accccpanying affidavit by Duke Power Company.
Correspondence with respect to the proprietary aspects of ti.e application for withholding or the Westinghouse affidavit should reference this letter, CAW-88-105, and should be addressed to the undersigned.
Very truly yours, .
'lLL , ()lli (M Robert A. esemann, ager
/tu Regulatory & Legislative Af fairs Enclosure (s)
- cc: E. C. Sheetaker, Esq. _l 1
Office of the General Counsel, NRC t i
i GS10180025 881012 PDR ADOCK 05000364 i . P FDC 1
PROPAIETART INF0WTION WOTICE TRANSK:TTD NDEWITH AAI PSDPAIETART AND/OR NON-PAOPAIETAR DCQJMENTS FURNISHG TO THE NRC IN CCNhTCTION WITH REQUE PLAhi SMCIFIC REVIDI AND APPA0VAI..
IN DEER TD CChTCP.M 70 THE REQUIRDOT5 W 10CFR2 790 W IME CCH RESULATIONS CONCD.NIC THE PADTICTION & PROPAIETART IFDMT 70 THE XR;, THE Ih7DMTION WHICH IS PMPAIETART IN THE PMPAIETARY YERSICSS CONTAIND WITHE SMCKE13 AD WHD.E THE PMPAIETART INFOMTION MAS
- EE*.ETD IN THE ME-PROPAIITARY YD5 IONS OC.T THE SMOIT3 RDR3, THE -
Ih7DP/ATION THAT VAS CDiTAIND WITh3 THE 3RA3273 IN THE PA0PAIE Kri3 SIM DC.ETC. THE JUSTIFICATION FDR CLAIM 30 THI INF0MTION S0 DESI3MTD AS PR0rAUTAP.T 23 ICICATD IX SUIN YEP 3 IONS ST MEAN LCTEPS. (a) Tl!ROUCH (g) C0hiAING WITHIN PAP.Di7HI3E5 LOCATE A5 A EPER3CRIM '
IXKT.:IATE.7 FOR.CWD7 THE BM3273 Dic.CEIm F.AQi ITDI QF INFDMTION DIXTIFIIP AS PRDPAIITART Ch IN THE MAMIN OPPQSITE WQi IATOMTION.
THESE
' LCMD CASE LETTERS ADIA 70 THE TTPI3 & INFOMTION VESTIOCUSE C HC:.05 IN COiFIDENCE IDD.7ITIID IN SECTIONS (4)(it)(a) hp (4)(11)(3) 0F THE APTIDAVIT ACCOMPAhTIM THIS TRANSK:TTAL PURSJAh71010CFR2 790 !
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. O AW-76-45 AFFIDAVIT COP 9GWEALTH OF PENNSYLVANIA:
ss W W OF Al.LEGHENY:
.Sefore me, the undersigned authority, personally appeared debert A. Wiessmann, who, being by me duly sworn according to law, de-pses and says that he is authorized to executs this Affidavit on behalf ofWestinghouseElectricCorporation("Westinghouse")andthattheaver-eents of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
ALMll tu Robert A. Wiesemann, Manager Licensing Programs ,
4 Sworn to and subscribed befor Lntthis.8 day of 'Q/M// 1976.
/ WM/f4/L.)
Notaryfublic u ..:. ,, t e :: . '
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. . . . . . 4.-w s. . L. W8
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AW-76-45 o
(1) I am Manager, Licensing programs, in the Pressurized Water Reactor
.$ystans Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the Troprietary information sought to be withheld from public dis-closure in connection with nuc*iear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding en behalf of the Westinghouse Water Reactor Divisions.
(2) I as making this Affidavit in conforwance with the provisions of 10 CFR Section 2.790 of the Comission'_s regulations and in con-junction with the Westinghouse application for withholding ac-companying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating infonnation as a trade secret, privfleged or as confidential comercial or financial information.
(4) pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Comission's regulations, the following is furnished for consideration by the Comission in determining whether the in-formation sought to be withheld from public disclosure should be withheld.
(1) The information sought to be withheld from public disclosure ,
'is owned and has been held in confidence by Westinghouse.
. l
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AW-76-45 (ii) The infonnation is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the pubite.
Westinghouse has a rational basis for detennining the types of information customarily held in confidence by it and, iri that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The ap-plication of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
l Under that system, infonnation is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (orcomponent, structure, tool, method,etc.)
4 where prevention of its use by any of Westinghouse's comp 2titors without license from Westinghouse constitutes a competitive economic advantage over other companies.
l (b) It consists of supportirg data, including test data, j relative to a process (or component, structure, tooi,
- method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved unrketability.
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AW-76-45 (c) Its use by a competitor would reduce his expenditure of resources or improve his cospetitive position in the design, ahnufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production cap-acities, budget levels, or commercial strategies of
-l Westinghouse. its customers or suppliers.
(e) It reveals aspects of past, present, or futu e West-
! inghouse or customer funded development piens and pro-grams of potential consercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-taction may be desirable. .
, (g) It is not the property of Westinghouse, but must be i
treated as proprietary by Westinghouse according to ';
l agreements with the owner.
1 There are sound policy reasons behind the Westinghouse j system which include the following:
(a) The use of such infonmation by Westinghouse gives i Westinghouse a competitive advantage over its com-
- petitors. It is, tA refere, withheld from disclosure to protect the Westinghouse competitive position.
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(b) It is information which is marketable in many ways.
The extent to which such infornation is available to competitors disintJhes the Westirghouse ability to sell products and services involving the use of the inforestion.
(c) Use by our competitor would put Westinghouse at a i competitive disadvantage by reducing his expenditure of resources at our expeM e.
( J) Each component of proprietary infomation pertinent te a particular competitive advantage is potentially I as valuable as the total competitive advantage. If competitors acquire components of proprietary infor-nation, any one component may be the key to the entire puzzle thereby depriving Westinghouse of a competitive advantage.
o (e) Unrestricted disclosure would jeopardize the position of prominence of Wdinghouse in the world market, and thereby give a market advantage to the compctition in those countries.
(f) The Westinghouse capacity to invest corporate assets l in research and development depends upon the success in obtaining and maintaining a competitive advantage, s i
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.i AW-76-45 o
(iii) The information is being transmitted to the Connission in confidence and, under the provisions of 10 CFR Section 2.790 it is to be received in confidence by the Connission.
(iv) The information is not available in public sources to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in WCAP-8821,
'Tranflo Steam Generator Code Description" (Proprietary),
being transmitted by Westinghouse Letter No. NS-CE-1219.
Eiche1dinger to Stolz, dated September 29, 1976. This report is being submitted pursuant to the NRC's Topical Report Program for generic review by the Regulatory Staff and is ex-pected to be referenced in several license applications.
This infomation enables Westinghouse to: ,
(a) Justify the design basis for emergency systems.
(b) Assist its c"st #Ar.s to obtain licenses.
(c) Optimize long-ters cooling design.
Further, this information has substantial comercial value ,
as follows:
l
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. AW-76-45 (a) Wastinghouse sells the use of the information to its customers for purposes of meeting NRC requirements for
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licensing documentation.
(b) Westinghouse uses the information to perform and justify analyses which are sold to customers.
Public disclosure of this information is likely to cause sub-stantial harm to t',e competitive position of Westinghouse because it would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of this information is the result of many years of Westinghouse effort and the expenditure of a con-siderable sum of money.
In order for com,oetitors of Westinghouse to duplicate this information, siellar engineering programs would have to be performed and a significant manpower effort having the requisite talent and experience, would have to be expended for data analyses and code development.
Fu'rther the dponent sayeth not.
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WESTINGHOUSE CLASS 3 WCAP-10989 Addendum 2 COBRA-NC, ANALYSIS FOR A MAIN STE.M INE BREAK IN THE CATAWBA UNIT 1 !CE CONDENSER CONTAINNENT (RESPONSE TO NRC QUESTIONS)
SEPTEMBER, 1988 t
WESTINGHOU$iELECTRICCORPORATION NUCLEAR ENERGY SYSTEMS P. O. B0X 355 P!TTS8URGH, PENNSYLVANIA 15230 0
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i Itur.1D/900784
TABLE OF CONTENTS SECTION TITLE PAGE 1.0 SLMURY l'1 2.0 RESPONSE TO NRC QUESTIONS 2-1 3.0 REFERENCEh 3-1 l
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i LIST OF FIGURES
- FIGURE TITLE PAGE 1 Channel L4yout for Level 1 2-8 2 Dimensions for the Pipe Tunnel 2-9 i
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LIST OF TA8LES TITLE PAGE
- TA8LE {
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1 GAP 3 (Door 8) 2-12 2 GAP 10 (Door 12) 2-16 3 GAP 17(Door 16) 2-20 4 GAP 24(Door 20) 2-24 5 GAP 31 (Door 24) 2-28 6 GAP 38(Door 28) 2-32 7 GAP 45 (Door 32a) 2-36 8 GAP 156 (Door 32b) 2-40 9 GAP 124 (Dcor 32c) 2'44 10 GAP 52(Door 36) 2-48 11 Axial Area Data 2-52 12 Lateral Area Data 2-60 13 Hydraulic Diameter for Lateral Connections 2-75 9
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1.0 $UMMARY The NRC has authorized the ANL to perform an independent confirmatnry analysis using the COMNIX code to calculate the resulting conditions of the main steam line break in ice condenser containments. ANL had reviewed the ice condenser containment model developed by Westinghouse using the COSRA-NC code for the Catawba Unit 1 ice condenser documented in WCAP-10988. Questions were raised by ANL in April 1988 concerning the COSRA-NC sodel, and answers were provided to ANL in May 1988, and were documented in Addendum 1. WCAP-10988. Additional information was requested by ANL/NRC in July 1986. This addendum addresses these requests / questions. Specifically this addendum provides detailed information on: 1) mass flow rates through the condenser doors as a function of time, 2) nominal and blocked flow areas in both axial and transverse directions, 3) the geometry of the pipe tunnel and 4) hydraulic diameters for lateral flow connections.
Ita3v:1D/0e07sa 1-1 i
2.0 RESPONSE TO ANL/NRC QUESTIONS Question 1
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The volume porosity or actual fluid volume at each basic mesh cell in C08RA-NC/Model 3 In response to question 3: " ....It is g the volume porosity defined by the equation shown in the question. The volumes listed in Table 5.2 are those occupied by fluid in each cell; they are not the total control volume for the
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- a. The above statement is incorrect, because by using the redii :nd dividing angles as given in Fig. 1 or by the inspection of the values in Table 5.2, it can be shown that the volumes listed in Table 5.2 are the total t
control volume for the basic mesh cells for COBRA-NC/Wodel 2.
~
- b. Page 77 of the WCAP-10988 report: "The nominal and actual volume and the hydraulic diameter for each cell are given in Table 5.2."
Since the actual volume is not listed in Table 5.2, does the above statement indicate that it can be calculated from the product of the nominal volume and the porosity? If so, what values of volume porosity are used for levels 9 and 10 in Model 37 If the porosity listed in Table 5.2 is not the volume porosity as defined by COMMIX, please provide the volume porosity or the actual volume occupied by fluid at each basic cell in C06RA-NC/Wodel 3.
Pesoonse to Question 1
- a. The definition for the ' volume porosity' given by the 4/18/88 transmittal from ANL/NRC to TVA was Volume porosity = Volume occupied by fluid in a control volume Total control surface 1sa3v:10/coc7ss 2-1
This ecuation is incorrect. The ' porosity" shown in Table 5.2 of l WCAP-10988 is not the "volume porosity" defined by this equation, as was ind1cated in WCAP-10988, Addendum 1. The "volume porosity" definition ,
should have been Volume porosity = Volur.e occupied by fluid in a control volume i Total control volume and this was confirmed by T. b. Chien of ANL during a telephone conversation on 7/12/88. According to this corrected definition, the i porosity given by Table 5.2 which was the ratio of the actual continuity-cell area to the nominal continuity-cell area, is equivalent to the volume porosity so defined since the cell length in the axial ;
direction is the same. ,
- b. The volumes listed in Table 5.2 of WCAP-10988 are the total control volumes for the continuity cells of COBRA-NC/Models 1 and 2. In Model 3, .
the top level (level 8) from Models 1 and 2 was divided into two equal ,i height levels (8 and 9). The flow area, the volume and the volume ;
porosity were assumed to be the same for these two levels. l l
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Ouestion 2 The surface porosity or the actual flow area at each basic mesh cell in COBRA-NC/Model 3 In response to question 3: "For the transverse directions, the flow areas are given by (gap width)*(es11 height)." By checking the information given in Fig.1, these flow areas are the nominal flow areas. Please provide the actual flow areas in the transverse directions for each basic cell.
Response to Question 2 The nominal and the blocked areas for the gaps in the lateral directions are listed in Table 12 of this Addendum. Please see Table 12 for details.
1sas a e m o7sa 2-3
Question 3 l
l l The hydraulic diameters in the transverse directions
- In response to question 2:
'In the transverse directions, the flow areas are calculated differently by (gapwidth)*(cellheight). The wetted perimeters are calculated internally in the code based on the length of the gap, the numbers of the walls, and the height of the cell. These parameters are eatered into the code by INPUT DATA LINES 354-569."
Since the flow arvas are the nominel flow areas and the wettad perinters are calculated internally, the hydraulic diameters can not be calculated from the available information in the report. Please provide the values of hydraulic diameters in the transverse directions used in COBRA-NC/Model 3 calculation.
Response to Question 3 -
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Values of hydraulic diameters in the transverse directions used in the COBRA-NC/Model 3 are listed in Table 13 of this Addendum. Please see Table 13 for details. ,
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Question 4 The tabulated mass flowrates through the ice condenser doors as a function of time at each sector l
In the Westinghouse response to question 7, the mass flowrates through doors 32a, 32b, and 32c are given in Tables 1, 2, and 3. Please explain how to use l
! these tables and also provide the mass flowrate through the rest of the ice condenser doors, i.e., doors 8, 12, 16, 20, 24, 28, and 36. Please provide f 1 more detailed information at different time steps if it is available.
r
! Response to Question 4 l
1 Mass flow rates (liquid, vapor and entrainment) for doors 8, 12, 16, 20, 24, j 28, 32s, 32b, 32c and 36 are listed. Please see Tables 1-10 for detail. (
j Please note the total liquid flow is the sum of the ' liquid" and the ,
l 'entrainment" flows shown in the tchles. The "door" is represented by cells with axial range from 860.3 in. to 982.7 in.
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Question 5 The location and dimension of the 8-foot high pipe tunnel underneath the spent '
fuel storage area In the response to question 5. Westinghouse did not provide the dimension of the pipe tunnel. Please provide the location and dimension of the tunnel and describe its functions end importance in the lower containment.
Response to Question 5 A description for the pipe tunnel model is shown on the next page. Please also see Figures 1 and 2 for its location and detail dimensions.
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FIFE TUNEL MODEL DESCRIPTION l
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LD,4 Figum 2 - Muensions for the Pfpe Tumel O
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Question 6 Explanation of the variation tables listed in the INPUT DATA LINES 872-1748 From the response to questions 3 and 4 it indicatn that the variation tables for the axial area sultipliers, the axial peris ter multipliers, the axial loss coefficients, and the lateral loss coefficients used in C00RA-NC are given in INPUT DATA LINES 872-1748. Please esplain how these tables are used in Section B of Model 3, where 9 axial levels are used to model the lower containment, hsponse to Ovestion 6 In the Input Data list given by WCAP 10988, variation table numbers are 'iste:
from Lines 19 146 for all the channels. t 3,c )
Numerical values for the multipliers at all the nodes are given in Lines l l
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Table 11 and Table 22 of this Addendus contain tufsrus,: ion for the nominal and '
the blocked flow areas at the amontus-cell centers in the axial and the The fors=less coefficient may be detersined laterei directions respctively.
by the infermation provided in these tables and by vaing published flow-restriction coefficient tables or curves.
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GAP 17 (DOOR 16)
(d i O t-f e
4 9
4 4
l l
l e i I
i
! 2-23
_ _ . . .-~ . _ . _ _ . _ _ _ _ - . . - - . _ _ _ _ _ - - - - - - - _ _ _ _ _ _ - _ _ _ . _ _ _ . _ , - _ _ . - . _ _ - - __.__a
i TABLE 4 ;
GAP 24-(DOOR 20) (AQ e
O O
e e
2-24 m
1 TABLE 4 (CONTINUED)
GAP 24 (DOOR 20) ( 3,Q i
l I
i i
e l
l l
O 2-25
TABLE 4(CONTINUED)
GAP 24(DOOR 20) (a,0 e
e t
1 e
t I i L
I I
l 2-26 l
0 TABLE 4(CONTINUED)
GAP 24 (DOOR 20) (3.0 O
m S
6 l
l l
M 2-27
l TREUE 5 GaiP 31 (MER 24) hfdj l
=
I l
e G
t i
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l 1
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2-tt
. TABLE 5 (CONTINUED)
GAP 31 (DOOR 24) h.C) 1 i
i l
t F
1 i
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l l
n l [
} 2 29
l l
TABLE 5 (CONTINUED)
GAP 31 (000R 24) (g l .
l
{
l l
l ,
t I
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I
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l l
l r
[
l l
l
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2- 30 l . _ . - - - - - - . - - - - _ - - -
TABLE 5 (CONTINUED)
GAP 31 (D00R 24) ( 3,(,)
e
.l I
f i
l l
4 f
a L i
e 4 IN 2-31 4
i
A"'* -m TABLE 6 d'
- GAP 38'(DOOR 28) ,
I h
t e r t
1 f
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1 4
)
e a
I 4 .
f t
r I
4 a
t i
s
)
e e t 2-32 ;
I
TABLE 6 (CONTINUED)
GAP 38 (DOOR 28) ( 4,C)' .
e l-i9 I
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l f'
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l l
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l 6
{
l i
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r 2-33 i
. - ..._m. _ . _ _ _ _ _ _ . . _ __, . , _ _ . _ . - - - . - - - - _ _ - , . , _ _ . , - _ _ . , _ . _ _ _ - _ . _ _ _ _ . _ . _ _ _
.s - 3. ..4 TABLE 6 (CONTINUED)
GAP 38 (DOOR 28) (0 O e
l s
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i 1
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+
h I
i i
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{
l .
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\ 2-34 1 1
I
..----..--...----.----.-.-------,-.---.--------,.-c.,--
TABLE 6 (CONTINUE 0)
GAP 38 (DOOR 28) (el i Q 0
e i
i F
e b
l l
i 1 l [
- i l
o h
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I I
l f
I
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t i
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l 2-35 ,
h t__ .
TABLE 7 GAP 45 (DOOR 32a)
IM o
4 e
0 e
2-36
TABLE 7(CONTINUED) (JjQ.
GAP 45(000R32a) 6 J
G 0
2 37
TABLE 7 (CONTINUED)
GAP 45 (DOOR 32a)
(Dk) s 8 P i
i I
i l
I t
l i
l l
l l
l
' . I 2-38
4 TA8LE 7 CONTINUED)
GAP 45 000R 32a) Us()
l n
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t b
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t i
k 4
r f
P 1
1 il
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J 6
9 1
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q l
l 2-39 i I r
. - - - . .- - - . , _ , . - - . - , , _ , , . . . . , , - , , , , _ , . . . , _ , . _ , - . - . . ~ , - - . , . _ . _ , _ , . . . , . _ , , - - , . - _ . _ . . .
--e-9 TABLE 8 GAP 156 (DOOR 32b)
(,2.C.)
S t
i l
i I
a l
b i
1 6
1 3 r 6, '
I 6
I I
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i 1
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I 2-40
i TA8l.E8(CONTINUED GAP 156 (D00R 32b 0#O
/
e 8,
i e
1 l ,
1 l
t l
i I
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[
t 1
2-41 i; i,
I l
2%_ + _ _ _ _ ___
TABLE 8(CONTINUED) (J/)
l GAP 156(D00R32L) -
l l
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1 -
l l
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r l t l k b
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\
7 i
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l l i i I
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2 42 l 1
TABLE 8(C0flTINUED) /s GAP 156 (DOOR 32b) WM 4
- 1 i
l I
1 b
I i
I 4
l l l 2-43 I
l l
l
,. - -- - -- . - - - - --. . _ .- - - --- ., . - - _ . ~ . . - - -
---r ~ - - - - _
[
r TABLE 9 GAP 124 (000R 32c) (J,L) !
e I
s (
l b
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P l
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),
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l 2-44 1
- . -. , --,.,-..-- - - - - -,,-------------,-,--n.n,----,---- - . , - - - . - , , - ,.-- -_, - . - . , . ,
, - . - .- . . - - _ _ = _ = _ - . . - .
F TABLE 9 (CONTINUED'l GAP 124(DOOR 32c) 9sg e
i e
?
i-
. i l
5 e
i i
4 l'
f
. L I
I f
k i
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2-45' f I
---,--*6 '
-a + --_ n L -
1A.A >- n - s 4 s TABLE 9(CONTINUED)
GAP 124 (DOOR 32c) (8,0) t e
6 7
I 4
4 I
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i 1
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(
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2-46 i.
J i
)
TABLE 9 (CONTINUED)
GAP 124 (DOOR 32c) ggg 1 e
t I
6 s
I F
I i
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h i
e
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I 2-47 ,
I i
s vi TABLE 10 GAP 52 (D00R 36) (40 I i
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l T 1 F I
l e
f r
A I
,i l i k
F a
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l 4
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b 4
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4 4
1 4
1 l
I 2-48 6 1, 1
i l
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t P
_. - - - - . _ . _ , _ _ , . - - - _ _ _ _ _ . _ . . , _ _ . _ _ ,. - . . . , . . . - _ _ - _ , _ . - . _ - - - . ~ _ ~ . . _ _ _ . . . _ , . _ , . _ . - , _ _ _ . _ _ _ - _ _ , , - _ - - _ _ _ _ . . _ . - - - -, .
n'y- - - - - - ~ > 1 -u. A 4 a --
TAsa lo (CONTINUED) ~
u p 52 (Doon 36) (3,0 L 1
e I i,
j i
1 i
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l e
l 6
l
)
r f
{
r l 6 1 t i
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i.
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A - m- . - .~4 .-,--.-m-~4--- , . --. .e- --haaA-4.a-,,- 4-a*.-4,- .h-- e l
J 6
. TABLE 10 (CONTINUED)
GAP 52 (000R 36) UsN l l
l l
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t 4
i
- i
) k i
l t
I 4
il 1
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1
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i 1 i
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' . . ~ _ . - _ _ . - - - - - - - - . _ _ _ _ . _ , .. _ , . ,- . - _ - . . - - - . _ . . . _.~.- .- _ - ,--- --- -,... . - .. - _ ,..- _ . _ _. . _ .._ _ _ . ..
TA8LE10(CONTINUED) (,dtj.)
C GAP 52(DOOR 36)
G 9
+
l i
I i
r r
i I
s D
1 s
I f
I l '
i L
t i
o i
I
' s l
l 2 .
- I
! 2-51 l h
- - _. _.- J _ -. . _ _ _ . - _ ~a. 4 .-___ _ w_. .. _
I.
.9 .
TABLE 11 - AXIA1, ARIA DATA L8 }
"k :
o
+;
.. g s
a ,
t
'I I
i h
L
]
e l
I e
l L
b t
1
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2-52 I
4
.. t (lb)
TABLE 11 (ColtTINUED) T l
t l '
e I e
I t
I t
t r
l I
i l
i t
P
[
i g
. i l
s i >
l 2-53 emeoe* == p e eo se = w ese e ep .e
F
= . _ . _ _ .
(.di L)
TABLE 13 (CONTINUED) 3
}
. t e
t
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t b
l l
P f
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k f
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l i
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l l
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TABLE 11 (C01871NUED) m ;.
4 )
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TABLE 11 (C0ff72NUED) ,
y 9 I
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t
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M O
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. . _ , , _ _ . . . . . , . . . _ . . . _- . . _ . - - . ~ . ,, ...---__---,,..._..m..<
,-,- .,_ ... ...__ _ -_._.._ - -. , ~ , , . -
l I s I
C.,G i l) l- TA31211 (CONTINUED)
- 1 ...
4 ,
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r e i e
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2-58 1
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TABLE 12 (ColtTINt3D) ,
e e
b i
l r
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l
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t l
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i r
l i
F
.59 ,
L
(
i l
_ . ~ . _ - _ ___ - _ _ . _ _ _ . _ _ - . _ _ _ ._. - - -__ -_ _. __ _ _ _ .
e TABLE 12 - LATERAL AREA DATA
- N 4
?
l a
I I
l I
i i i i r
P I
i l
I I l l
t I
.i
't Y I i .
I e l l l l
i l
, 2-60 ;
I i 4
t I 1
l
?
TABLE 12 (CCHTINUED)
'O e
(
k I
I I
)
i l l
I
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t I
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I {
2-61 1 I
1 i
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TABLE 12 (CONTINtED) d 40)
- 7 e
l J
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l l l . I i
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, _ - . _-_.--.__--._y 9., _ _ . . _ _. . . _ . , ,
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' A3!212 (CONTINUED) -
=
k 4
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a 1
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J 9
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li I
i 1
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4 iI l
'i 1
d i
2-63 i
1
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Ng j-e E
9 e
l 4
l l
o 2-64
JO i
TABLE 12 (CONTINUED)
O e
4 G
h 2-65
L
)
i
. (, Og L) ~
TABLE !! (Mf!NUID) . i l
b l
l' l'
t-L t
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9 f
I t
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i 2-66 i
e
e e
9 L 9,0 -
TABLE 12 (CONTINUED) 6
?
l P
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c I
k e
i F
t h
s t
i h
I I
r
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f 2-67 i i
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l
l 3
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( N) .
TABLE 12 (CONTINUED) 5 O
e 0
0 G
h 2-68 I
e
- , . . . - - - - - - , - . . . - . - - - - - - - - - - - - - - - ----,-,w m-~ ---e,-,-,.-w n-r,, --
e-- ----,---~,---,n---, --,--n.- --,,_ . , --~,-- , - - -
4 ,-
4 4
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4 MW
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2-6C i
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i 2-70 4
I . . . . . ,- . .
& - a 4 9
e h TABLE 12 (C0ltTINUED) 9 e
)
i e
r a
[
l r
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E
+
i F
t L
i 1
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1 v
e m am e off P
b t
l
, s , -,,-,-my - , - - - -- - - - ---.---------,--,-.,--.,,y-y*ww-yw, p. 3-ww---e.- ---m-.-,--- + -- - - ------,--yi y,,m,.m-. - ---+ r
6
~
I/M 12 (CQQ71M) e O
2-72
~ ^ ^ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
I i
TABLE 12 (CCNTINDED)
O e
4 4
h e
e t
t e
e -
b 2-73 e
~~ ~ -- - - - _ - _ - _ . _ _ _ _ _ _
1 5
?
D TABLE 12 (CONTINUED) ('
l l
2-74
TABLE 13 -
HYDRAULIC DIAMETER FOR LATERAL CONNECTIONS i
e I
e ?
I I
i ,
4 e
e I
e i
i i
i 1
l l
1 I
l 2-75 l
l l
l
i TABLE 13 (CONTINUED) .
B 6
I I
I l
9 9
e 2-76
1 l
l l
l TABLE 13 (CONTINUED) gyg 1
t i l l l 9
l 9
e 2-77
$ 2'[)
7ABLE 13 (CONTINUED) '
8 4
9 9
l e
2-78
3.0 REFERENCES
3.1 Letter from NRC, Ms. S. Black, to TVA, Mr. S. A. White, entitled, Request for Additional Information Regarding Main Steam Line Breaks in Ice Condenser Plants - Sequoyah Units 1 and 2 and Watts Bar Units 1 and 2, dated July 15, 1988, with attachment entitled Additional Information Needed to Prepare COMMIX Input for Modeling the Catawba Ice Condenser Containment after Reviewing the Westinghouse Report WCAP-10988, Addendum 1.
l l
i l
i l
l I
i iss3<:io/coc7ss 3-1 l
_ _ . _ _ . _ _ _ _ _ _ . . _ - _ . _ _ , _ - _ _ _ _ _ _ __ _