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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217C1051999-10-0808 October 1999 Forwards Amend 153 to License DPR-3 & Safety Evaluation. Amend Revises TS Section 6.0,Administrative Controls,By Deleting TS Sections 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20212J2231999-10-0101 October 1999 Forwards Copy of Environ Assessment & Fonsi Re 990317 Application for Amend to Revise TS Section 6.0 by Deleting TS Section 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20211J5001999-08-31031 August 1999 Forwards Proposed Rev 29 to Yankee Decomissioning QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation. Amend in Response to Application Dated 990324,deletes License Condition 2.C (10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20210S0621999-08-10010 August 1999 Forwards semi-annual fitness-for-duty Program Performance Data for six-month Period of 990101-990630,IAW 10CFR26.71(d) ML20210R1421999-08-0404 August 1999 Forwards Insp Rept 50-029/99-02 on 990411-0714.One Severity Level 4 Violation Occurred,Being Treated as NCV ML20210F3691999-07-21021 July 1999 Submits Response to NRC Request for Clarification of Certain Details of Yaec Proposed Mods to Yankee Nuclear Power Station Defueled TS ML20209D4881999-07-0909 July 1999 Forwards Rev 29 to Decommissioning QA Program, for Info & NRC Approval,Iaw 10CFR50.54(a)(3).Attachment a Provides Listing of Changes,But Does Not Discuss All Refomatting, Grammatical,Editorial or Typographical Changes ML20209C3271999-07-0101 July 1999 Forwards Rev 2 to Security Training & Qualification Plan.Rev Withheld ML20209C3151999-07-0101 July 1999 Forwards Rev 9 to Security Plan,Reflecting Plant Decommissioning Activities & Continues to Provide Protection Against Radiological Sabotage.Rev Withheld ML20209D1611999-06-28028 June 1999 Forwards UFSAR for Ynps.Updated Ynps FSAR Is Being Submitted Biennially,Iaw Commitment in Ltr Dtd 950614.Document Reflects Changes Made to Ynps as of 981231,unless Otherwise Noted ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195D6781999-06-0707 June 1999 Forwards Original & Two Copies of New England Coalition on Nuclear Pollution & Consolidated Intervenor Opposition to Yankee Atomic Electric Co Motion to Terminate,As Required by Rule for Filing ML20207E6301999-06-0101 June 1999 Informs of Relocation of Yaec Corporate Ofcs,Effective 990501.New Address Submitted.All Formal NRC Correspondence to Util Should Be Directed to Duke Engineering & Svcs, Marlborough,Ma ML20207D7991999-05-29029 May 1999 Forwards Original & Two Copies of Ltr to ASLB Chairman in Matter of Yankee Nuclear Power Station Proceeding.With Certificate of Svc ML20207D8181999-05-29029 May 1999 Requests That Board Convey to Panel That within Period of Time Authorized by NRC Regulations Author Intends to File, on Behalf of Intervenors,Responsive Pleading to Yaec Pending Motion to Withdraw in Ref Matter.With Certificate of Svc ML20207D8131999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328.Forwards Organizational Chart ML20195B3491999-05-25025 May 1999 Submits Withdrawal of Proposed License Amend to Approve Plant Termination Plan.New Application Will Be Submitted in Future ML20206Q1881999-05-17017 May 1999 Forwards for Filing,Necnp Request for Permission to File Contentions & Contentions on Inadequacy of NRC Staff 990412 Environ Assessment & Finding of No Significant Impact of Approval of Util Termination Plan.With Certificate of Svc ML20206H8701999-05-0505 May 1999 Informs That DB Katz Unable to Locate Copy of Attachments to Which Zobler Referred to in Response to Block Ltr.Requests Info on How Panel Will View Receipt of Ea.With Certificate of Svc ML20206R3221999-05-0505 May 1999 Forwards Insp Rept 50-029/99-01 on 990101-0411.No Violations Noted.Activities at Rowe Facility Generally Characterized by safety-conscious Operations to Maintain Spent Nuclear Fuel & Careful Radiological Controls to Workers ML20206D1801999-04-30030 April 1999 Forwards Citizens Awareness Network First Set of Interrogatories,Requests to Produce & Certificate of Svc. Requests Any Objections Be Submitted Withing Five Days of Filing Receipt.Without Encls.Related Correspondence BVY-99-031, Forwards Ynps Annual Radiological Environ Operating Rept for Jan-Dec 1998, IAW Plant Defueled TS 6.8.2.a1999-04-26026 April 1999 Forwards Ynps Annual Radiological Environ Operating Rept for Jan-Dec 1998, IAW Plant Defueled TS 6.8.2.a ML20206B6641999-04-24024 April 1999 Requests Board Take Action to Remedy NRC Failure to Comply with Board Request & NRC Counsel Representation to Board in Relation to That Request Re Serving EA Upon Petitioners Per Request of Board.With Certificate of Svc ML20206C0801999-04-23023 April 1999 Requests That Change Proposed in Request for Transfer of Administrative Requirements for Ynps Defueled TS to Plant Decommissioning QA Program Be Withdrawn ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205S0131999-04-17017 April 1999 Forwards Original & Two Conformed Copies of Necnp First Set of Interrogatories & Requests to Produce for Filing in Matter Re Yaec License Termination Plan.Related Correspondence ML20205L0701999-04-13013 April 1999 Grants Voluntary Extension to Allow CAN to Effectively Participate in Hearing Process (ASLBP 98-736-01-LA-R).With Certificate of Svc.Served on 990413 ML20205P9091999-04-13013 April 1999 Informs That Item Intended to Be Attached to 990412 Filing (Motion for Leave to Reply(Reconsideration of Portion of of Prehearing Conference Order)) Inadvertently Overlooked. Section 4, Final Radiation Survey Plan Encl ML20205P2191999-04-12012 April 1999 Informs That Mj Watkins Has Been Appointed to Position as Yankee Rowe Decommissioning Licensing Manager,Effective 990412.Individual Will Serve as Primary Point of Contact for All Info Flow Between NRC & Yaec ML20205K9361999-04-0808 April 1999 Informs That J Block,T Dignan & D Katz Came to Agreement to Extend Discovery in Yankee Rowe License Termination Plan Hearing Process (ASLBP 98-736-01-LA-R) by 1 Wk from 990611 Until 990618 ML20205G7791999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for Yankee Power Station,Per 10CFR50.75(f) ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee ML20205F6331999-03-29029 March 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept, for Third & Fourth Quarters of 1998.Rept Summarizes Quantities & Estimated Dose Commitments of Radioactive Liquid & Gaseous Effluents Released During 1998 ML20205N1531999-03-24024 March 1999 Submits Request to Elminate fitness-for-duty Requirement from Plant.Proposed Change Has Been Reviewed by PORC & Nuclear Safety Audit & Review Committee ML20204E5051999-03-17017 March 1999 Requests NRC Review & Approval of Listed Mods to App a of Plant Possession Only License DPR-3 ML20207F8791999-03-0505 March 1999 Forwards Amend 151 to License DPR-3 & Safety Evaluation. Amend Revises Pol by Changing Submittal Interval for Radioactive Effluent Repts from Semiannual to Annual ML20207H8981999-03-0303 March 1999 Responds to Concerns Raised in Petitions to Intervene Filed with NRC by Necnp on 980224 & Citizens Awareness Network on 980226.Petitioners Requested Hearing on NRC Staff Consideration of License Termination Plan for Yankee Plant ML20203G2391999-02-12012 February 1999 Forwards Corrected Index Page for Amend 150 Issued to License DPR-3 on 990203 ML20202H5741999-02-0303 February 1999 Forwards Amend 150 to License DPR-3 & Safety Evaluation. Amend Revises Possession Only License Through Three Changes to TS ML20202F1921999-01-28028 January 1999 Forwards Copy of EA & Fonsi Re Application for Amend to Yaec Pol for Ynps Dtd 980820.Proposed Amend Would Revise Pol Through Listed Changes to TS ML20202E9401999-01-25025 January 1999 Submits Correction to Encl Request for Leave to Make Oral Appearance Statement, .Date of Conference & Desire to Make Oral Appearance Were Inadvertently & Incorrectly Entered on 990127 Instead of 990126 ML20199L1811999-01-22022 January 1999 Requests Opportunity for Representative of EPA to Make Oral Limited Appearance Statement & Submit Written Comments During 990126 Prehearing Conference Re Licensee Termination Plan ML20199K9151999-01-21021 January 1999 Requests Leave to Make Oral Limited Appearance Statement at 990127 Prehearing Conference Re License Termination Plan,Per 981130 Order Concerning Change in Filing Schedules & Date of Prehearing Conference ML20198N1691998-12-30030 December 1998 Forwards Motion for Leave to Participate in Matter of Yankee Atomic Electric Co License Termination Plan ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) ML20154P9431998-10-16016 October 1998 Forwards Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program. Program Name Changed Due to Status of Plant.Plant in Final Stages of Decommissioning ML20154F0861998-10-0101 October 1998 Forwards Insp Rept 50-029/98-03 on 980601-0731.No Violations Noted ML20153D7271998-09-23023 September 1998 Informs of Changes Made in Personnel Staff at Yankee Nuclear Power Station 1999-08-04
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20211J5001999-08-31031 August 1999 Forwards Proposed Rev 29 to Yankee Decomissioning QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20210S0621999-08-10010 August 1999 Forwards semi-annual fitness-for-duty Program Performance Data for six-month Period of 990101-990630,IAW 10CFR26.71(d) ML20210F3691999-07-21021 July 1999 Submits Response to NRC Request for Clarification of Certain Details of Yaec Proposed Mods to Yankee Nuclear Power Station Defueled TS ML20209D4881999-07-0909 July 1999 Forwards Rev 29 to Decommissioning QA Program, for Info & NRC Approval,Iaw 10CFR50.54(a)(3).Attachment a Provides Listing of Changes,But Does Not Discuss All Refomatting, Grammatical,Editorial or Typographical Changes ML20209C3271999-07-0101 July 1999 Forwards Rev 2 to Security Training & Qualification Plan.Rev Withheld ML20209C3151999-07-0101 July 1999 Forwards Rev 9 to Security Plan,Reflecting Plant Decommissioning Activities & Continues to Provide Protection Against Radiological Sabotage.Rev Withheld ML20209D1611999-06-28028 June 1999 Forwards UFSAR for Ynps.Updated Ynps FSAR Is Being Submitted Biennially,Iaw Commitment in Ltr Dtd 950614.Document Reflects Changes Made to Ynps as of 981231,unless Otherwise Noted ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195D6781999-06-0707 June 1999 Forwards Original & Two Copies of New England Coalition on Nuclear Pollution & Consolidated Intervenor Opposition to Yankee Atomic Electric Co Motion to Terminate,As Required by Rule for Filing ML20207E6301999-06-0101 June 1999 Informs of Relocation of Yaec Corporate Ofcs,Effective 990501.New Address Submitted.All Formal NRC Correspondence to Util Should Be Directed to Duke Engineering & Svcs, Marlborough,Ma ML20207D7991999-05-29029 May 1999 Forwards Original & Two Copies of Ltr to ASLB Chairman in Matter of Yankee Nuclear Power Station Proceeding.With Certificate of Svc ML20207D8181999-05-29029 May 1999 Requests That Board Convey to Panel That within Period of Time Authorized by NRC Regulations Author Intends to File, on Behalf of Intervenors,Responsive Pleading to Yaec Pending Motion to Withdraw in Ref Matter.With Certificate of Svc ML20195B3491999-05-25025 May 1999 Submits Withdrawal of Proposed License Amend to Approve Plant Termination Plan.New Application Will Be Submitted in Future ML20206Q1881999-05-17017 May 1999 Forwards for Filing,Necnp Request for Permission to File Contentions & Contentions on Inadequacy of NRC Staff 990412 Environ Assessment & Finding of No Significant Impact of Approval of Util Termination Plan.With Certificate of Svc ML20206H8701999-05-0505 May 1999 Informs That DB Katz Unable to Locate Copy of Attachments to Which Zobler Referred to in Response to Block Ltr.Requests Info on How Panel Will View Receipt of Ea.With Certificate of Svc BVY-99-031, Forwards Ynps Annual Radiological Environ Operating Rept for Jan-Dec 1998, IAW Plant Defueled TS 6.8.2.a1999-04-26026 April 1999 Forwards Ynps Annual Radiological Environ Operating Rept for Jan-Dec 1998, IAW Plant Defueled TS 6.8.2.a ML20206B6641999-04-24024 April 1999 Requests Board Take Action to Remedy NRC Failure to Comply with Board Request & NRC Counsel Representation to Board in Relation to That Request Re Serving EA Upon Petitioners Per Request of Board.With Certificate of Svc ML20206C0801999-04-23023 April 1999 Requests That Change Proposed in Request for Transfer of Administrative Requirements for Ynps Defueled TS to Plant Decommissioning QA Program Be Withdrawn ML20205S0131999-04-17017 April 1999 Forwards Original & Two Conformed Copies of Necnp First Set of Interrogatories & Requests to Produce for Filing in Matter Re Yaec License Termination Plan.Related Correspondence ML20205P9091999-04-13013 April 1999 Informs That Item Intended to Be Attached to 990412 Filing (Motion for Leave to Reply(Reconsideration of Portion of of Prehearing Conference Order)) Inadvertently Overlooked. Section 4, Final Radiation Survey Plan Encl ML20205P2191999-04-12012 April 1999 Informs That Mj Watkins Has Been Appointed to Position as Yankee Rowe Decommissioning Licensing Manager,Effective 990412.Individual Will Serve as Primary Point of Contact for All Info Flow Between NRC & Yaec ML20205K9361999-04-0808 April 1999 Informs That J Block,T Dignan & D Katz Came to Agreement to Extend Discovery in Yankee Rowe License Termination Plan Hearing Process (ASLBP 98-736-01-LA-R) by 1 Wk from 990611 Until 990618 ML20205G7791999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for Yankee Power Station,Per 10CFR50.75(f) ML20205F6331999-03-29029 March 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept, for Third & Fourth Quarters of 1998.Rept Summarizes Quantities & Estimated Dose Commitments of Radioactive Liquid & Gaseous Effluents Released During 1998 ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee ML20205N1531999-03-24024 March 1999 Submits Request to Elminate fitness-for-duty Requirement from Plant.Proposed Change Has Been Reviewed by PORC & Nuclear Safety Audit & Review Committee ML20204E5051999-03-17017 March 1999 Requests NRC Review & Approval of Listed Mods to App a of Plant Possession Only License DPR-3 ML20202E9401999-01-25025 January 1999 Submits Correction to Encl Request for Leave to Make Oral Appearance Statement, .Date of Conference & Desire to Make Oral Appearance Were Inadvertently & Incorrectly Entered on 990127 Instead of 990126 ML20199L1811999-01-22022 January 1999 Requests Opportunity for Representative of EPA to Make Oral Limited Appearance Statement & Submit Written Comments During 990126 Prehearing Conference Re Licensee Termination Plan ML20199K9151999-01-21021 January 1999 Requests Leave to Make Oral Limited Appearance Statement at 990127 Prehearing Conference Re License Termination Plan,Per 981130 Order Concerning Change in Filing Schedules & Date of Prehearing Conference ML20198N1691998-12-30030 December 1998 Forwards Motion for Leave to Participate in Matter of Yankee Atomic Electric Co License Termination Plan ML20154P9431998-10-16016 October 1998 Forwards Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program. Program Name Changed Due to Status of Plant.Plant in Final Stages of Decommissioning ML20153D7271998-09-23023 September 1998 Informs of Changes Made in Personnel Staff at Yankee Nuclear Power Station ML20238F4861998-08-27027 August 1998 Forwards fitness-for-duty Performance Data Form for Period 980101-980630 ML20217R2421998-05-0707 May 1998 Forwards,For Filing & Service,Original & Two Copies of New England Coalition on Nuclear Pollution,Inc Opposition to Yaec Motions to Strike & for Conditional Leave to Reply. W/Certificate of Svc ML20217R2691998-05-0707 May 1998 Forwards Detailed Minutes of 980429 Meeting,Which Executive Committee Voted to Endorse & Support Application of Franklin Regional Planning Board to Participate Fully Before ASLB ML20217J1731998-04-27027 April 1998 Forwards Yankee Nuclear Power Station,Annual Radiological Environ Operating Rept,Jan-Dec 1997. Rept Summarizes Findings of Radiological Environ Monitoring Program Conducted by Yae in Vicinity ML20237F1321998-04-24024 April 1998 Partially Deleted FOIA Request for Documents of All Communications Between Attorneys for Yankee Atomic Electric Co & Listed Individuals Re Decommissioning of Listed Plants ML20216G6561998-04-14014 April 1998 Responds to 980318 Request for Info Contained in QA Program ML20217N1501998-03-31031 March 1998 Discusses Response to Yankee Atomic Electric Co Answer to Request for Hearing of Franklin Regional Planning Board. W/Certificate of Svc ML20217J6391998-03-30030 March 1998 Forwards Tables That Summarize Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released from Ynps in Rowe,Ma for Third & Fourth Quarters of 1997.ODCM,encl ML20216E8131998-03-26026 March 1998 Submits Clarification Re Alpb 95-736-01-LA Document. W/Certificate of Svc ML20217F5561998-03-25025 March 1998 Forwards Response to Yankee Atomic Electric Co Answer to Petition to Intervene & Request for Hearing of Franklin Regional Planning Board ML20216F0781998-03-13013 March 1998 Forwards Copies of Answers Filed by Yaec to Four Petitions for Leave to Intervene in Listed Matter.Util Answers Were Filed & Served on 980311,before Receiving Copy of Order of ASLB Panel Establishing Board.W/O Encl ML20216H5901998-03-12012 March 1998 Forwards Response of Yankee Atomic Electric Co to Demand for Info ML20217A0701998-03-12012 March 1998 Forwards Manager Response to Demand for Info & Lead Engineer Response to Demand for Info.All Persons on Svc List Will Receive Copies of Redacted Verifications ML20217Q4481998-03-0404 March 1998 Requests,On Behalf of Franklin Regional Planning Board (Frpb) of Franklin County,Ma,That NRC Conduct 10CFR2,Subpart G Hearing on License Termination Plan Filed by Licensee. W/Certificate of Svc ML20203L4281998-03-0404 March 1998 Advises NRC of Proposed Reorganization of Cmpc,Which Will Result in Creation of New Holding Company Structure for Cmpc.Nrc Consent to Any Indirect Transfer of Control of NRC Operating License,Requested ML20203L1551998-02-27027 February 1998 Provides Response to Demand for Info to Yankee Atomic Electric Co & to Duke Engineering & Services,Inc,Re Inadequate Engineering Analyses & Materially Incomplete & Inacurate Info to NRC License 1999-08-31
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059J6681990-09-0707 September 1990 Forwards Operator Licensing Natl Exam Schedule Through FY94, Per Generic Ltr 90-07 ML20059G0411990-09-0707 September 1990 Lists Util Organizational Changes.Ac Kadak Named President & CEO & Jk Thayer Named vice-president,effective 901001 ML20059G0351990-09-0606 September 1990 Advises That Util Intends to Modify Tech Specs Re Emergency Diesel Generator Surveillance Testing.Util Will Continue to Follow Testing Prescribed by Plant Tech Specs Until Such Time as Approval Received ML20059E1081990-08-28028 August 1990 Forwards Revised Diesel Generator Test Plan,Which Includes Addl Commitments Made During 900822 Discussions ML20059B8121990-08-24024 August 1990 Provides fitness-for-duty Program Performance Data for Period Ending 900630 ML20059B3941990-08-17017 August 1990 Advises That Util Performed Automated Ultrasonic Insp of Pressurizer Vessel Cladding Interface at Plant During 1990 Refueling Outage.Results of Insp Continue to Indicate No Evidence of Any Cladding Indication ML20058N0811990-08-0909 August 1990 Request Relief from ASME Section XI Requirements for Low Pressure Surge Tank Cooling Pumps,Per Generic Ltr 89-04 as Result of Review of Facility Inservice Testing Program ML20058L2241990-08-0303 August 1990 Forwards Peer Review of 900705 Reactor Pressure Vessel Evaluation,Prepared by Le Steele.Review Indicates Agreement W/Methodology in Chapter 5 of Evaluation ML20058L2211990-08-0202 August 1990 Forwards Results of PTS Sensitivity Study for Mean Values of Ref Temps for Four Matls in Beltline Region ML20055J2011990-07-27027 July 1990 Provides Steam Generator Insp Results & Advises of Nine Defective Tubes Discovered During Jul 1990 Insp.Complete Results Will Follow within 12 Months,Per Tech Spec 4.4.10.5.b ML20055H6701990-07-25025 July 1990 Forwards Decommissioning Funding Assurance Rept & Certification, Per 10CFR50.75.Rept Includes Certification That Reasonable Assurance Will Be Provided That Funds Will Be Available for Decommissioning ML20055G6961990-07-20020 July 1990 Forwards YAEC-1731, Yankee Nuclear Power Station Core 21 Performance Analysis. Results of Analysis Demonstrate That Plant Performance Well within Acceptable Limits ML20055G6651990-07-20020 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Model 1153 Series D Transmitters Not Currently in Use at Plant ML20055G6781990-07-19019 July 1990 Forwards, Yankee Plant Small Break LOCA Analysis ML20055G7031990-07-19019 July 1990 Forwards Rev 0 to Yankee Cycle 21 Core Operating Limits Rept. Cycle Scheduled for Startup on 900811 ML20055H8291990-07-16016 July 1990 Forwards Response to Request for Addl Info Re YAEC-1710, Yankee Nuclear Power Station Pilot Evaluation Rept for Plant License Renewal, & YAEC-1727P, Methodology for Identifying Potential Fluid Component Age-Related.. ML20055H0021990-07-16016 July 1990 Forwards Rev 24 to Security Plan.Rev Withheld ML20055E1531990-07-0505 July 1990 Forwards Reactor Pressure Vessel Evaluation Rept, in Response to NRC 900501,07 & 15 Requests for Addl Info. Specific Chapters Re Requests Listed ML20055D0371990-07-0202 July 1990 Responds to 900319 Commitment to Provide Scope & Schedule for Confirmatory Analysis for Steam Generator Overfill Protection by 900702.Scope of Analysis Will Include Identification of Potential Overfill Scenarios ML20058K3601990-06-28028 June 1990 Forwards Addl Info to Support Proposed Change 234,modifying Tech Specs to Incorporate Wording Consistent w/NUREG-0452, STS for Westinghouse PWRs Re Min Discharge Pressure ML20058K3021990-06-27027 June 1990 Provides Addl Info for Proposed Change 227 to License DPR-3. One Addl LPSI Pump Must Be Capable of Being Placed in Operable Status When Utilizing Spec 3.10.6 ML20248G7471989-10-0303 October 1989 Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Program. Flow Monitoring Will Be Performed on Emergency Feedwater Pumps & Baseline Flow Data Will Be Established Using clamp-on Flow Device ML20248G8241989-10-0202 October 1989 Forwards Rev 19 to YOQAP-I-A, Operational QA Program, Re Organizational & Programmatic Changes to Stated Plants ML20247B7761989-09-0101 September 1989 Forwards Addl Info Re Topical Rept YAEC-1659 on SIMULATE-3 Validation & Verification ML20247B6051989-08-31031 August 1989 Responds to Generic Ltr 89-12, Operator Licensing Exams. Formats for Proposed Operator Licensing Exam & Requalification Exam Schedules Encl ML20247N1521989-07-27027 July 1989 Advises That Util Has No Agreements W/Employees That Contain Restrictive Clauses Re Notifying NRC of Potential Safety Issues,Per V Stello ML20247N1611989-07-24024 July 1989 Informs That Util Intends to Utilize NRC Incident Response Ctr Data Handling Capabilities to Suppl Util Communications W/Nrc.New Communication Link Will Be Implemented During Facility Annual Emergency Exercise Scheduled for 891128 ML20247H7411989-07-21021 July 1989 Provides Addl Info Re Program to Address Concerns in Insp Rept 50-029/89-05 Re Vendor Technical Info Program.Master Inventory of Vendor Technical Manuals,Located at Plant & Engineering Ofcs,Completed ML20247K0721989-07-21021 July 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning, Per Guidelines in NUREG-1344.No Significant Pipe Wall Thinning Other than That Attributed to Normal Wear Occurred in Single Phase Piping ML20248C9291989-07-19019 July 1989 Informs That Bl Drawbridge Will Be Replaced by Nn St Laurent as Acting Manager of Operations,Effective on 890724. Tk Henderson Will Become Acting Plant Superintendent ML20246A5861989-06-30030 June 1989 Informs of Implementation of Upgraded Emergency Operating Procedures,Based on Westinghouse Owners Group Emergency Response Guidelines & Util Procedures Generation Package ML20245C8721989-06-24024 June 1989 Forwards Rev 8 to Plant Security Training & Qualification Plan.Changes Reflect Upgrading Firearms Qualification Courses to practical,performance-based,combat-oriented Programs to Survive Lethal Confrontation.Rev Withheld ML20245C8851989-06-24024 June 1989 Forwards Rev 22 to Plant Security Plan.Changes Reflect Required Retention Period for Security Records.Rev Withheld ML20245H3131989-06-23023 June 1989 Forwards RELAP5YA:Computer Program for LWR Sys Thermal- Hydraulic Analysis,Vol 1:Code Description & RELAP5YA: Computer Program...Vol 2:Users Manual & Response to 197 Questions from NRC ML20245F3161989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Determination That Westinghouse Mechanical Plugs from Heat Numbers 3279,3513, 3962 & 4523 Not Installed at Plant Noted ML20247Q7791989-06-0101 June 1989 Responds to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Util Committed to Addressing All Actions of Bulletin by 910103.Justification for Continued Operation Encl ML20247E7841989-05-24024 May 1989 Forwards Response to NRC Re Violations Noted in Insp Rept 50-029/89-04.Response Withheld (Ref 10CFR2.201) ML20246D6851989-05-0202 May 1989 Forwards Response to NRC Review Questions on Plant Revised Reflood Heat Transfer Model for LOCA Analysis.To Address Recent Change in App K,Blowdown Heat Transfer Logic Modified to Prevent Use of Dougall-Robsenow Correlation ML20245B4981989-04-18018 April 1989 Forwards Printout of Status of Implementation of TMI Action Items,Per NRC 890414 Request ML20244C7591989-04-14014 April 1989 Provides Supplemental Info to Util 890321 Proposed Change 218 to Add Snubber to Pressurizer Drain Piping to Enhance Seismic Capability of Piping ML20244C5521989-04-13013 April 1989 Responds to Station Blackout Rule 10CFR50.63.Review of Existing Battery Capacity Calculations Verifies That Batteries Have Sufficient Capacity to Meet Station Blackout Loads for 1 H ML20244B8101989-04-10010 April 1989 Forwards Inservice Insp Exam Rept for 881113-890117. Form NIS-I as Required by Provisions of ASME Section XI Also Included ML20244C5381989-04-10010 April 1989 Informs That Util Will Not Propose Change to Tech Spec 6.5.2.10,per Discussion.Nuclear Safety & Audit Review Committee Will Now Rept to President of Yankee,Instead of vice-president.Tech Spec Change Unwarranted ML20247Q6421989-03-31031 March 1989 Responds to NRC Re Violations Noted in Insp Rept 50-029/88-22.Corrective Actions:Mod to Original Engineering Design Change & Evaluation of Engineering Deficiency Performed W/Actions Specific to Prevent Recurrence ML20247Q4851989-03-31031 March 1989 Responds to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Util Maintaining Stored Spares for safety-related Applications,Per Criteria for Action Item 7 ML20247B3081989-03-22022 March 1989 Informs of Present Level of Nuclear Property Insurance Coverage for Plant as of 890401.Coverage Carried W/American Nuclear Insurers & Mutual Atomic Energy Reinsurance Pool ML20247A9011989-03-22022 March 1989 Forwards Yankee Atomic Electric Co Annual Rept 1988. Rept Covers 3-yr Period Ending 881231 ML20236D5961989-03-17017 March 1989 Responds to NRC Re Violations Noted in Insp Rept 50-029/88-09.Corrective Actions:Specific Remedial Training Included in Prestartup Training Program Attended by All Licensed Operators & Shift Technical Advisors ML20235Z0571989-03-0707 March 1989 Forwards Proposed Rev 21 to Security Plan.Rev Withheld ML20235V8491989-03-0303 March 1989 Responds to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Bulletin Action Item 1a Completed During Last Refueling Outage & No Indication of Piping or Support Degradation Observed.Plant Analysis Being Performed 1990-09-07
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Te'opho"c (6 ") 2 * 'oo YANKEE ATOMIC ELECTRIC COMPANY TWX 710 380 7619
2.C.2.1 1671 Worcester Road Framingham, Massachusetts 01701 yyg g5 g7 August 15, 1985 i /
- l[- [ Q United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing i
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) License No. DPR-28 (Docket No. 50-271)
(c) License No. DPR-36 (Docket No. 50-309)
(d) USNRC Letter to YAEC and MYAPCO, dated May 11, 1984 (e) Topical Report: "RELAPSYA - A Computer Program for Light Water Reactor System Thermal-Hydraulic Analysis,"
Yankee Atomic Electric Company, YAEC-1300P, October l 1982 l
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(f) MYAPCO Letter to USNRC, dated January 31, 1985 (g) YAEC Letter to USNRC, dated February 26, 1985 (h) YAEC Letter to USNRC, dated July 1, 1985
Subject:
Response to the NRC Questions on RELAPSYA
Dear Sir:
Reference (d) requested answers to 197 questions on YAEC's Topical Report on RELAP5YA [ Reference (e)). Our schedule called for the submittal of responses to 20 RELAP5YA questions by August 15, 1985. Responses to 12 of these questions have already been submitted to you in Reference (h). Responses to the remaining 8 questions are provided as an attachment to this letter. The attachment contains 7 extra responses belonging to the next group of questions. These are provided to you in advance to facilitate the review process.
Our schedule called for the submittal of the responses to the remaining 43 questions on September 30, 1985. However, due to the unexpectedly high volume of work in our LOCA Analysis Group, these responses will instead be submitted to you by November 1, 1985.
We trust this information is satisfactory. However, if you have any questions please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY 85002 O gDR f p @29 G p Senior Project Engineer- Licensing GP/ Jo T/
9 RESPONSE TO 15 QUESTIONS ON RELAP5YA AUGUST 15, 1985 1
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I. CONDENSATION HEAT TRANSFER AND NONCONDENSABLE GASES i
0.I.11 l ,
Clarify the assessment of the vaporization model given in Equation 2.1-20 on Page 34 of Reference 10 for cases with noncondensable gas present.
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Justification is provided in the answer to Question Q.I.3 and Appendix A.I-3 to exclude noncondensable gases in our small break LOCA 1 analyses. However, the presence of a noncondensable gas will tend to i l
reduce the vaporization rate given by the current model i~ RELAP5YA.
This is further explained below.
1 The current vaporization model in RELAP5YA is given on .' age 34 of l l
Reference I.18-1 as follows:
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{'g=C(G,+G) jfP(X-X -X)(X,-X)/fy 9 (1) l i
Where: j
~ ~ ~
C = 6.4517175 x 10 (see m Pa ), empirical co".atent I
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G = mixture' mass flux (Kg m sec )
~ ~
G = 3500.0 (Kg m sec ), empirical constant P = total pressure (Pa)
X = gas phase static quality X, = equilibrium static quality X = noncondensable gas static quality X, = 1.0 x 10~ , empirical constant jy = vapor density (Kg m~)
i Let us examine the variation of gf with an increase of X n for the I case where G , P and X are held constant. From the Gibbs-Dalton m
modelforagasmixture,thevapordensity,f,isgivenby:
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1-1 _ _ . - _ . - . - - - _ . . _ _ . . _ _ _ _ . _ _ _ _ _ , - __ _ _ _ _ _ _ _ _ . . . _
i fy=MTOT v gas " TOT
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n gas Since X, is a very small constant, then the quotient given by (X - X - X )/f in Equation (1) is nearly constant. Therefore, the variation of with an increase in X depends primarily upon the static quality difference (X, - X). The answer to Question Q.I.8 shows that this static quality difference decreases to zero as X increased toward X. Thus, the calculated vaporization rate will also decrease toward zero as X increases toward X.
0 I.12 clarify how the interphase area is included and how the effect of area is modeled in cha' sing from nonstratified to stratified flow.
A.I.12 Both the vaporization and condensation models are empirical and do not include the interphase area explicitly as a variable. The vaporization model is based on data from depressurization experiments. The condensation model is geared mainly to provide rapid equilibration of phase temperatures, llence, there is no need to include the effect of changing interphase area in these models.
O.I.13 Clarify why the rate should not increase when the liquid decreases below the temperature that would make the equilibrium quality go to zero.
A.I.13 The interphase mass transfer models in RELAPSYA are written as the l
product of a conductance term and driving force. Conceptually, the l mass transfer rate should increase as the driving force increases. In RELAP5YA, the driving force is the quality difference. X, - X, but the equilibrium quality is limited to values between 0.0 and 1.0.
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Hence, if One true equilibrium quality becomes less than 0.0 (subcooled liquid) or treater than 1.0 (superheated vapor), it is reset to 0.0 and 1.0, respectively. Consequently, the driving force for interphase mass transfer is also limited. However, the conductance term in the RELAP5YA models for mass transfer is always large. Thus, the limitation on the driving force has little impset on vaporization and condensation rates.
0.I.14 Page 32 of Reference 13 states: "The main shortcoming of the air modeling in R5 is the lack of any modifications to the heat / mass transfer and drag packages when air is present. This is not believed to be a real problem for the drag packages. But the presence of noncondensables in the gaseous phase can change the heat and mass transfer rates substantially..." Clarify how the heat-transfer correlations (and in particular the ones for condensation) are modified in RELAP5YA to include the effect of noncondensable gas for flowing and nonflowing applications.
6 I.14; Reference 13 mentioned above is listed below as Reference I.14-1. The heat transfer correlations in RELAP5YA are not modified to explicitly account for the effect of noncondensable gas. However, the local state properties will be affected by noncondensables and have some impact on the heat transfer calculation. This effect of noncondensables on heat transfer does have the correct qualitative trend. It should be noted that the effect of noncondensables on heat transfor is considered to be insignificant for PWR small break ;0CAs. This has been addressed in the response to Question Q.I.3 (see Appendix A.I-3, Section 4.0).
Reference (I.14-1) J. A. Trapp, " Descriptive Evaluation of RELAP5," EPRI-NP-2361, (April 1982).
i O.I.15 Clarify if the resistance of the noncondensable gas is included as it builds up near the condensation interface for nonflowing situations. j In particular, the use of a simple multiplier may not be appropriate if i the heat-transfer process becomes diffusion limited. ;
i A.T.15 l The resistance of the noncondensable gas as it builds up near the i t
vapor-liquid interface during condensation is not explicitly modeled in RELAP5YA because it is not considered significant for PWR small break I t
LOCAs. The justification for neglecting the added resistance to heat transfer due to a noncondensable gas layer is provided in the response i
(o Question Q.I-3 (see Appendix A.I-3, Section 4.0). l t
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Examples and experimental bases for the heat-transfer-degradation functions that might be used should be described and justified.
A.I.16 The degradation of heat transfer due to presence of noncondensable gas !
is considered insignificant for PWR small break LOCA condition and is neglected in RELAP5YA. The justification is provided in the response to Question Q.I-3 (see Appendix A.I-3, section 4.0)s
- 0.I.17 ;
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l Clarify and justify the temperature difference that multiplies the heat-transfer coefficient when the atmosphere contains a noncondensable :
gas.
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A.I.17 The temperature difference that multiplies the heat transfer coefficient is the difference between the wall temperature and the local saturation temperature. When noncondensable gas is present, the saturation temperature is based on the partial pressure of the vapor and will be lower than the saturation temperature corresponding to the total pressure. Thus, the temperature difference between the wall and the bulk fluid will be correspondingly affected (decreased for condensation, increased for vaporization) and is the appropriate temperature difference to be used in estimating heat transfer rates.
This situation is illustrated (for condensation) in Figure I.3-1 of Appendix A.I-3 in the response to Question Q.I-3. However, as also discussed in the response to Question Q.I-3, we propose to neglect the presence of noncondensable gas in pWR small break analyses.
0.I.18 Clarify how the condensation is modeled at the liquid interface in the pressurizer with and without a noncondensable gas present.
b.I.18 The pressurizer is modeled by RELAp5YA using the normal hydrodynamic components available in the code (SNGLVOL, BRANCH or PIPE components).
In these components, RELAP5YA uses the condensation model described in Equation 2.1-21 of Reference I.18-1. The effect of noncondensables on the condensation rate as calculated by this model is discussed in the response to Question Q.I 8.
Reference (I.18-1) R. T. Fernandez, et al. , "RELAp5YA - A Computer program for LWR ,
System Thermal-Hydraulic Analysis, Volume I," YAEC Report i I
YAEC-1300p, October 1982.
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0.I.19 Clarify how the condensation process is modeled for pressurizer sprays with and without a noncondensable gas present.
A.I.19 The pressurizer spray is modeled in RELAP5YA as a liquid-filled junction injecting into volumes comprising the upper regions of the pressurizer. The effect of noncondensables on the condensation rate will bn as given by the model described in Equation 2.1-21 of Reference I.19-1 and as further discussed in the response to Question Q.I-8. !
During most of the small break analyses the reactor coolant pumps are [
t expected to be tripped. The pressurizer sprays will not be operable when the reactor coolant pumps are off and the condensation process associated with the sprays will not be effective. ,
Reference !
l (I.19-1) R. T. Fernandez, et al., "RELAP5YA - A Computer Program for LWR System Thermal-Hydraulic Analysis, Volume I," YAEC Report j YAEC-1300P, October 1982.
0.I.20 Clarify how the condensation process is modeled between the levels of a stratified flow with and without a noncondensable gas present.
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RELAP5YA does not explicitly account for the geometry of the flow pattern in calculating condensation rates. The condensation model is J described in Equation 2.1-21 of Reference I.20-1. The effect of l
noncondensables on the condensation rate is discussed in the response I to Question Q.I.8.
Reference (I.20-1) R. T. Fernandes, et al., "RELAP5YA - A Computer Program for LWR System Thermal-Hydraulic Analysis, Volume I," YARC-1300P, October 1982.
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- SYSTEMS VERIFICATION AND OTHER EXPERIMENTAL VgRIFICATION V.
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Figure 5.3-5 of Reference 12 shows that the break flow was !
overpredicted from 200 to 800 seconds, and yet Figure 5.3-9 of ;
Reference 12 shows the change in calculated total mass to be less than ;
t the data from the rame period. Also, Figure 5.3-3 of Reference 12 )
shows the calculated pressure agreed almost exactly with the data j during this time period so the HPIS flow would also be expected to agree very closely with the data. Clarify why then if the break flow was overpredicted during this period, the change of the total mass was I I less than the data.
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l There appears to be an inconsistency in the reported data. Table V.8-1 I j presents system mass values at 200 and 800 seconds for both the LOFT i l L3-6 data and the RELAP5YA calculation. In addition, the average flow ,
rates in and out of the system are also listed. Using these values, a [
mass balance calculation was made to check the system mass numbers ;
l l presented in Figure 5.3-9. Comparison of the two system mass numbers ;
shows that the RELAP5YA calculation agrees with the system mass (
l obtained from a mass balance while the L3-6 data does not. The !
difference between the two system masses for the L3-6 data is about
! 1,300 lbs. Taking the worst combination of the measurement I uncertainties only accounts for about 350 lbe (Uncertainties: i i
Inventory i 110 lbm, break flow i 15%, HPSI flow i 0.044 lba/sec, RCP j injection 1 0.035 lbm/sec). Therefore, there is an unexplained j i inconsistency in the reported test data. [
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TASLE V.5-1 System Mass at 800 Sec System Mass Beactor Coolant from Systest Mass at 200 See Break Floor HPIS Floor Puse Irdection Esss Balance at 800 See L3-6 9,770 lbst 7.8 lba/see .92 lba/sec .216 lba/sec 5.772 1ha 4,465 1ha Data Total 4,680 1ha Total 5521ha Total 130 1ha l
nerd 5YA 8,623 1ha 8.8 lba/sec .92 lba/sec .216 lba/sec 4,021 lba 4,032 1ha l
Total 5,284 1ha Tctal 5521ha Total 130 1he a
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r VI. FLOW REGIMES 0.VI.8 The rates of phase separation in flowing fluid will determine if steam and noncondensable gas will separate from the liquid at the top of the candy canes for B&W plants or the top of the U-bends in CE and W plants. Clarify how the phase separation is modeled as the two-phase fluid flows around the high-point bends.
A.VI 8 No special treatment is given to the phase separation at the top of the steam generator U-bends. The standard RELAPSYA interphase drag models !
described in Section 3.1 of Reference VI.8-1 are used.
Reference (VI.8-1) R. T. Fernandez, et al. , "RELAP5YA - A Computer Program for Light Water Reactor Thermal-Hydraulic Analysis, Volume I: Code Description," YAEC-1300P, October 1982. (Proprietary) l 0.VI.40 [
, Clarify and justify the verification provided by systems and I l experimental comparisons for interruption and restart of natural i
- circulation.
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- Please see the response to Questions Q.III.1 through Q.III.4 as I
- provided in our July 1,1985 submittal. [
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VII. CORE STEAM COOLING O.VII.9 Clati. the range in conditions for the core level assessment tests compared with the expected range in SBLOCA calculations.
A.VII.9 Reference VII.9-1 presents an extensive assessment of RELAPSYA compared to many separate effects and integral test results which address relevant thermal-hydraulic phenomena including core level. The most relevant tests for core level assessment are the boil-off tests. The boil-off tests used for assessment were:
- 1. The quasi steady-state boil-off Test 3.09.10I conducted at Oak Ridge National Laboratory in the Thermal-Hydraulle Test Facility (TNTF). The objective of the boll-off test series was to study the heat transfer and mixture icvel swell under SDLOCA conditions in Pressurized Water Reactors (PWRs).
The conditions for Test 3.09.101 are shown below:
System pressure 650 psi Mass flux 2.19.10 lbm Linear power / rod 0.68 kW/lb
- 2. The system boil-off experiment. Test 6441/6, conducted at General Electric, San Jose in the Two-Loop Test Assembly (TLTA) facility.
l The boil-off tests attempted to simulate system conditions which might occur during a small break LOCA in a BWR, if none of the Rmergency Core Cooling Systems, including the ADS were available.
In these tests, the recirculation loops were blocked off and the l 11guld inventory was slowly boiled off at a constant pressure and constant bundle power. The power level was representative of decay I
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l heat in a BWR. The main objective of these tests was to evaluate heat transfer in a partially covered bundle at decay power levels and low flows.
The phenomena and the range of conditions encountered in this test will also be encountered during SBLOCAs in PWRs before the l accumulator actuation if the flow from the high power safety injection pumps bypasses the core.
The initial conditions for Test 6441/6 are:
l System pressure 395 i 10 psia l Bundle power 250 1 2 kW l
Initial two-phase level Bundle top l
One of the integral tests used in the assessment of RELAPSYA simulates a small break LOCAs with core uncovery Test L3-6/L8-1 was l a small break test performed in the Loss of Fluid Test (LOFT) l l facility at the Idaho National Laboratory. Test L3-6, which cas a l
l SDLOCA with the pumps running, was extended into a more severt transient (L8-1) which produced core uncovery and heatup.
For the perfonnance of Experiment L3-6/L8-1, the LOFT f acility was l configured to simulate a small break equivalent to a 4-inch l diameter rupture in the cold leg of a large (approximately 1,000 MWe) commercial Pressurized Water Reactor. In Experiment L3-6, the l primary coolant pumps were not tripped until the hot leg depressurized to 311.83 psia. The liigh Pressure Injection System j (!! PSI) flow was then terminated and the break left open.
Experiment L8-1 started when the primary coolant pumps were i tripped. When the maximum fuel cladding temperature reached 600.53 F, core reflood was initiated, l
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l Experiment L3-6/L8-1 was initiated from primary coolant system l
l conditions of: )
l Hot leg temperature 579.1 1 3.24 F 1
Cold leg temperature 544.5 i 3.24 F Hot les pressure 2,156.7 i 20.3
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j Intact loop flow rate 1,065.48 i 5.72 l l lb/see Power level 50 i 1 MW 1 1 i Maximrm linea:- heat generation rate 16.06 i 1.12 kW/ft l l
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1 Since this is a transient test, the conditions in the test facility varied with time. A detailed account of the integral test l 1
l conditions are presented in Reference VII.9-1. '
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l (VII.9-1) Fernandez, R. T., R. K. Sundaram, J. Ghaus, A. Husain, l
J. N. Loomis L. Schor, R. C. Harvey and R. Habert, "RELAPSYA - A l l Computer Program for Light-Water Reactor System Thermal-Hydraulic l l Analysis, Volume III: Code Assessment," Yankee Atomic Electric Company Report YAEC-1300P, Volume III (October 1982). (Proprietary) l l
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X. ADDITIONAL QUESTIONS THAT ARE CONCERNED WITH SEVERAL AREAS O.X.7 Since the release of the version of RELAPS used as the bases for your small break evaluation model, numerous corrections and updates to RELAP5 have been made to correct errors and improve the numerics of the RELAPS computer program. Provide a description of the quality assurance program used by you to incorporate required changes in your EM model (e.g., corrections of coding errors). Include in this description the program to validate your EM model when changes are made.
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Yankee Atomic Electric Company utilizes a Quality Assurance Manual to l provide guidelines to the engineers to assure that design changes and additions are consistent with safety and licensing requirements. In particular, instructions WE-103 and WE-108 are the two guidelines relevant to the issue of the quality assurance of computer codes and engineering analyses.
WE-103 provides guidelines for the performance, review, approval and control of engineering calculations and analyses.
l WE=108 provides guidelines for development, acquisition, modification, verification, testing and approval of computer codes that will be used 7
for WE-103 calculations.
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i Copies of WE-103 and WE-108 are attached.
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