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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QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation.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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~~~.' April 23, 1985 VYM #101/85 W.O. #4100 DCC-VY-85-62 Mr.A.Vare1[a /
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b?b!LAYi?[4 Region I U.S. Nuclear Regulatory Commission llU /
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.2-631 Park Avenue King of Prussia, PA 19406
Dear Mr. Varella:
Pursuant to a telephone conversation with Mike Nitzel of EG&G, who requested further information regarding factors of safety for custom designed base plates, please find enclosed
~ a'~ revised' status list. ~T his revised status of deadweight supports includes _the actual ~ factors _of ~safeEyl for Hilti'
" kwik; bolts" for all non-standard base plates. These factors._
of safety' vary from'4 0 to 160.0.
If you have any further questions, please do not hesi-tate to call.
Yours sincerely, Y &
R.P. Oliver Vermont Yankee Project es Lead Mechanical Engineer Enclosure cc: A.C. Kadak W.D. Hinkle M.E. Nitzel (EG&G) '
S.R. Miller R.L. Smith R.W. Capstick D.M. Thomson 8506180366 850423 PDR ADOCK 05000029 p PDR
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e 24 HC -hD 4 ~f- (F.S.3 6.11) R ep l a c e with custe- des:;n baseclaten 6 25 HPCI-479 Replace m th st andz:rd b asepl e te 6
26 H.CO -H22 (F.5.= G.22) Ree!::ce with cu s t ce- des gn basemistec
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14 21 CS-Hr:7F ( F.5.2 5.55) Replace w:th custer des:;n baseplat:c 14 '32 CS-Hu?D To be rercved
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15 35 RHr-uS12:E(F.5. 54.cs) Repl ace wi th custos design baser ate-15 26 RHR-HD12:C (F.5.3 54.oS1 Repl ace wi th custer dest;n t a u cc : s t e _.
15 37 RHR-uD10 A To be re cved 15 39 RM.;-HDiS! 4 A t t -a ched to structur al steel 15 39 C";-HDISTAC R ep l a c e .41 t h standard baseplates
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STATUS OF DEADWElGHT PIPE SUFPORTS Pipe Stress Pipe Support Problea No. Identification No. Status 16 44 RHR-HD233 To be removed 18 45 CS-HD77 Ta be removed 18 46 CS-HD78A Replace with standard baseplates 18 47 CS-HD78B To be removed 18 48 CS-HDB2 Replace with standard baseplates 32 49 CST-H17 Replace with standard baseplates 32 50 CST-H2O Replace with standard baseplates 32 51 CST-H46 Replace with standard baseplates 32 52 CST-H17A Replace with standard baseplates 32 53 CST-H19A Replace with standard baseplates 32 54 CST-19B Replace with custom design baseplates 33 55 CST-H17 Replace with standard baseplates 33 56 CST-H19 Replace with standard baseplates 33 57 CST-H2O Replace with standard baseplates 33 58 CST-H46 Replace with standard baseplates 33 59 CST-H47 To be removed 33 60 CST-HD17A Replace with standard base' plates 33 61 CST-H19A Replace with standard baseplatou 33 62 CST-H47A Replace with utandard baseplates 33 63 CST-H47C To be removed 36 64 CST-H17 Replace with standard baseplates 36 65 CST-H19 Replace with standard baseplates 36 66 CST-H46 Replace with standard baseplates 36 67 CST-H47 Replace with standard baseplates 36 68 CST-HD17A Replace with standard baseplates 36 69 CST-H19A Replace with standard baseplates 36 70 CST-HD47A Replace with standard baseplates 36 71 CST-HD47B Replace with standard baseplates 36 72 CST-HD47C Replace with standard baseplates 36 73 CST-HD47D To be removed 41 74 CUW-HD71 Replace with standard base plate 50 75 SA-H18 To be removed 50 76 SA-H19 To be removed 50 77 SA-H31 To be removed 51 78 SA-H2O To be removed 51 79 SA-H21 ( E 5.* 4.0) Replace with custom design base plate 51 80 SA-H32 ( F.S. 3 4.0) Replace with custom design base plate 60 81 MS-H3 Replace with standard base plate 60 82 MS-HD3 Replace with standard base plate 60 83 MS-HD6 Replace with standard base plate 60 84 MS-HDBA (F.5.5 4. 59) Replace with custom design base plate 60 85 MS-HDBC Replace with standard base plate l 61 86 HPCI-H102 (F.5.* l60.0) Replace with custom design base plate '
STATUS OF DEADWEIGHT PIPE SUPPORTS Pipe Streus Pipe Support Problem No. Identification No. Status I
61 87 HPCI-H102A Replace with standard base plate 61 l 88 HPCI-H102B Replace with standard base plate l 61 89 HPCI-H102C Replace with standard base plate '
61 90 HPCI-H102D Tc be removed !
61 91 HPCI-H103A Replace with utandard base plate l 61 92 HPCI-H103C Replace with standard base plate l 61 93 MS-H13 Replace with standard base plate !
61 94 MS-HD13A Attached to structural steel l 61 95 MS-HD13B Replace with utandard base plate l 61 96 MS-HD13C To be removed i 61 97 MS-HD13D ( F.5.5 4.17) Replace with custom design base plate 61A 98 HPCI-HD61E (F.5.5 4.59) Replace with custom design base plate l 62 99 CUW-H18 Replace with standard base plate 62 100 RCIC-H52 Replace with standard base plate 62 101 RCIC-H53 To be removed 62 102 RCIC-H54 Replace with standard base plate 62 103 RCIC-H55 To be removed 62 104 RCIC-H57 To be removed 62 105 HPCI-HD24 Replace with standard base plate 62 106 HPCI-HD26A Replace with standard base plate 62 107 HPCI-HD26B Replace with standard base plate 62 108 MS-HD22A Attached to structural steel 62 109 MS-HD22B Replace with standard base plate 62 110 MS-HD22D Replace with standard base plate 62 111 RCIC-HD7B Attached to structural steel 62 112 RCW-H128 (P.S.= 6.25) Replace with custom design base plate 63 113 HPCI-H30 To be removed 63 114 HPCI-H31 l Replace with standard base plate j 63 115 HPCI-HD35A lF.S.* 5.97) Replace wi th custom design base plate 63 116 HPCI-HD35B Replace with standard base plate !
63 117 HPCI-HD35C Attached to structural steel l 63 118 HPCI-HD35D Attached to structural steel 65 119 HPCI-HD201 EBolts not loaded in tension -
65 120 HPCI-HD202 E::inting plate and bol ts remain]
67 121 HPCI-HD63B To be removed i 67 122 HPCI-HD81A To be removed 67 123 HPCI-HD81B To be removed 101 124 CST-H66 To be removed 101 125 CST-H67 Attached to & evaluated w/seis spt MS-H 101 126 RCIC-HD958 To be removed 101 127 RCIC-HD95C ( F.5. 28.o) Replace with custom design base plate 101 128 RCIC-HD95D (F.S.112.43) Repl ace wi th custom design base plate 101 129 RCIC-HD96 Attached to structural steel
dTAT05 & DJADW: 03:! r P(PE O!!PPORTS P1pe Stioss Pipe Support Problem No. Iden ti f i cat i on No. Status
.------------------------~~
102 130 MS-HD70A (ES-12.12) Replace with custom design base plate 102 131 MS-HD70B (ES. 26.61) Poplace with custom design base plate 102 132 RCaC-HD85 Replace with standard base plate 102 133 RCit-HO9TA Attached to structural steel 102 134 RCIC-H0 91B (F.5.5 M.6 0 Replace uth custom design base plate 105 135 P.CIC-H80B Attachad to structural steel 105 136 RCIC-HD100A Attached to structural steel 105 137 RCIC-HD100B To be removed 105 138 RCIC-HD80A To be removed 105 139 RCIC-HD80C Attached to structural steel 105 140 RCIC-HD81B Replace with standard base plate 105 141 RCIC-HD81C Attached to structural steel 105 142 RCIC-HDB2 To be removed 105 143 RCIC-HD83A Replace with standard base plate 105 144 RCIC-HD84A(F.$.: 6.15) Replace with custom design base plate 105 145 RCIC-H24 (F.5.s 615) Replace with custom design base plate 106 146 MS-H48 Repl ac e with standard base plate 106 147 MS-H30 Attached to structural steel 106 148 MS-H51 To be removed 106 149 MS-HD101 Attached to structural steel 106 150 MS-HD49B Attached to embed Plate 106 151 MS-HD6 Replace with standard base plate 106 152 RCIC-HD89 To be removed 112B 153 RCW-HD170 Attached to structural steel 116 154 RCW-HD77A To be removed 116 155 RCW-HD77B Attached to structural steel 117 156 RCW-HD74A Repl ace with standard base plate 117 157 RCW-HD74B (F.5.= 4.S4) Replo.ce with custom design base plate 118 158 RCW-125 Replace with standard base plate 118 159 RCW-HD1011 Replace with standard base plate 118 160 RCW-HD119A To be removed 118 161 RCW-HD119B Attached to structural steel 118 162 RCW-HD119C To be removed 118 163 RCW-HD123 (F.5.* l3.19) Repl ace wi th custom design base plate 121 164 RSW-H105 (F.S.s to.0) Replace with custom design base plate 121 165 RSW-H264 Attached to utructural steel 121 166 RSW-H98 To be removed 121 167 RSW-HD141A Attached to embed Plate 121 168 RSW-HD224 Attached to structural steel 121 169 RSW-HD225A Replace with standard base plate 121 170 RSW-HD228 To be r emoved 121 171 RSW-HD229A Attached to structural steel 121 172 RSW-HD229C Replace with standard base plate
STATUS OF DEADWElGH T PIPE SUFFOP TS Pipo Stress Pipe Support Problem No. Identification No. Statuu 121 173 RSW-HD229D To be removed 119 174 RSW-HD235E (P.5.= 5.73) Replace with custom design base plate 119 175 RSW-HD236A To be removed 119 176 RSW-HD236B (F.5.*5.o4) Replace wi th custom design base plate 119 177 RSW-HD236C Attached to structur al steel 119 178 RSW-HD264 Attached to structural steel 119 179 RSW-HD88B Attached to structural steel 119 180 RSW-HD88C No bolts 119 181 RSW-HD88D To be removed 119 182 RSW-HD126 Attached to embed Plate 119 183 RSW-HD215A To be removed 119 184 RSW-HD215B Attached to structural steel 119 185 RSW-HD230A To be removed 119 186'RSW-HD230D Replace with standard base plate-119 187 RSW-HD230E To be removed 119 188 RSW-HD231 A (F.S.* 4.79) Replace wi th custom design base plate 119 189 RSW-HD233B Replace with standard base plate 119 190 RSW-HD233C Replace with standard base plate a 119 191 RSW-HD235A Attached to structural steel 119 192 RSW-HD235B To be removed i 119 193 RSW-HD235C Attached to structural steel 119 194 RSW-HD235D To be removed 118 195 RSW-HD167 To be removed 118 196 RSW-H155 To be removed i 119 197 RSW-H100 (F.5. 5 4.49) Replace with custom design base plate 119 198 RSW-H105 To be removed 119 199 RSW-H126 Attached to embed Plate 119 200 RSW-H141 (F.5.7 4 0) Replace with custom design base plate 121 201 RSW-H229F Replace with standard base plate 121 202 RSW-H229G (F.5.* 6 55) Replace with custom design base plate 121 203 RSW-H235E (F.S.'s 5.191 Replace with custom design base plate l
! 121 204 RSW-H236A To be removed l 121 205 RSW-H236B (F.5.5 5.041 Repl ace wi th custom design base plate 121 206 RSW-H249A Replace with standard base plate 121 207 RSW-H249B Attached to structural steel 134 208 RSW-HD191 Replace with standard base plate 134 209 RSW-HD133 To be removed 134 210 RHR-HD130A (F.5.517.3%) Replace wi th custom design base plate 134 211 RHR-HD130B ( F.5.5 7 54) Replace wi th custom design base plate 134 212 RHR-HD130C Replace with standard base plate 134 213 RHR-HD156 A (F.5.5 4.44) Repl ace wi th custom design base plate 134 214 RHR-HD156B To be removed -
134 215 RHR-HD157 Replace with standard base plate
ClAIUS OF D E A D H E [ G H'i PIl'E SUPT'URTS Pipe Streus Pipe Support Problem No. Identificalito No. Status 134 216 RHR-HD187B Rep 1 ace with utandard base p1 ate 134 217 RHR-HD189A Attached to structural steel 134 218 RHR-HD189B To be removed 134 219 RHR-192 Replace with standard base plate 134 220 RHR-HD194A Replace with standard base plate 134 221 RHR--HD 194C Replace with utandar d base plate 134 222 RHR-HD195A Replace with standard base plate 134 223 RHR-HDi(76 To be removed 134 224 RHR-HD197A (F.5.:H.H) Replace with custom design base p1 ate 134 225 RHR-HD1978 Replace with standard base plate 134 226 RHR-HD197C No bolts 134 227 RHR-HD2OOA To be removed 134 228 RHR-HD2OOD To be removed 134 229 RHR-HD2OOF (F.5.5 4.ot) Replace with custom design base plate 134 230 RHR -HD2OOG Replace with standard base plate 134 231 RHR--HD2OOJ To be removed 134 232 RHR-HD201A Replace with standard base p1 ate 134 233 RHR-HD21 ( F.5.5 4.15) Rep 1 ace wi th custom design base plate 134 234 RHR-HD22 Replace with standard base plate 134 235 RHR-HD23 (F.5.= 8.69) Replace with custom design base plate 134 236 RHR-HD230 (F.5.3 5.47) Replace wi th custom design base plate 134 237 RHR-HD245 To be removed 134 238 RHR-HD246 Replace with standard base plate 134 239 RHR-HD87 Replace with standard base plate 134 240 RHR-HD91A Replace with standard base plate 134 241 RHR-HD92B To be removed 134 242 RSW-H133 Attached to embed Plate 134 243 RSW-HD216A Replace with standard base plate 134 244 RSW-HD216D To be removed 134 245 RSW-HD217B Replace with standard base plate 134 246 RSW-HD217C Attached to structural steel 134 247 RSW-HD217D Attached to structural steel 134 248 RSW-HD218A Attached to structural steel 134 249 RSW-HD2198 To be removed 134 250 RSW-HD218C ( F.5.2 5.63) Repl ace with custom design base pl ate 134 251 RSW-HD218D ( F.S.* 8.0) Replace with custom design base plate 134 252 RSW-HD220A Replace with standard base plate 134 253 RSW-HD221 Replace with standard base plate 134 254 RHR-HD187C To be removed 135 255 RHR-HD161A Attached to structural steel 135 256 RHR-HD1618 Replace with standard base plate 135 257 RHR-MD162A To be removed 135 258 RHR-HD162D To be removed
~
STATUS OF DEADWEIGHT FIN D JPf}*DP TS Pipe Stress Pipe Support Problem No. Identification No. Status
~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - -
135 259 RHR-HD162C (F.5.5 2 0.0) Repl ace wi th custom design base plate 135 260 RHR-HD163A To be removed 135 261 RHR-HD163B Replace wi th standard base plate 135 262 RHR-HD163D To be removed 135 263 RHR-HD163E Attached to embed Plate 135 264 RHR-HD163F (F.5.= 9.75) Repl ace wi th custom design base plate 135 265 RHR-HD163G To be r emoved 135 266 RHR-HD168B To be removed 136 267 RHR-HD168A To be removed 136 268 RHR-HD168C To be' removed 136 269 RHR-HD169A To be removed 136 270 RHR-HD169B (F.5. 8 25.0) Repl ace with custom design base plate 136 271 RHR-HD169C To be removed 137 272 RHR-HD202 To be removed 137 273 RHR-HD203 Attached to embed Plate 137 274 RHR-HD204 To be removed 138 275 RdR-HD172A Attached to structural steel 138 276 RHR-HD172B Attached to structural steel 138 277 RHR-HD173A To bc removed 138 278 RHR-HD173B (F.S.*50.C0 Replace wi th custom design base plate 138 279 RHR-HD173C (F.5.5 50.0) Repl ace with custom design base plate 138 280 RHR-HD173D No bolts 138 281 RHR-HD174A To be r emoved 138 282 RHR-HD174B Replace with standard base plate 138 283 RHR-HD174C Replace with standard base plate 139 284 RHR-HD246E (F.S.510.0) Replace wi th custom design base plate 139 285 RSW-H164 Replace with standard base plate 139 286 RSW-H141 (F.$.2 4.01 Replace with custom design base plate 139 287 RHR-HD246J Replace with Strndard base plate '
139 288 RSW-HD164B To be removed 139 289 RHR-HD246F Replace with standard base plate 139 290 RSW-H264 To be removed 139 291 RSW-HD141C To be removed 139 292 RHR-246G Replace with standard base plate 139 293 RHR-246H Attached to structural steel 139 294 RHR-246A To be removed 139 295 RHR-246I To be removed 151 296 RMISP-HD18A Replace with standard base plate 151 297 RMISP-HD18B To be removed 151 298 RMISP-HD20A Replace with standard base plate 151 299 RMISP-HD20B To be removed 151 300 RMISP-HD21A To be removed 151 301 RMISP-HD219 Replace with standard base plate
l STATUS OF DEADWEIGHT PIPE SUPPORTS Pipe Stress Pipe Support Problem No. Identification No. Status
.151- 302 RMISP-HD21C Replace with standard base plate 1511 303 RMISP-HD21D Replace with standard base plate 151' 304 RMISP-HD24B To be removed 151 305 RMISP-HD24D (ES,i fe.15) Replace with custom design base plate 151- 306 RMISP-HD24E (ES.5 6.15) Replace with custom design base plate 151 307 Valve Spt3A To be removed i 151- 308 Valve Spt3B To be. removed l 161 309 SLC-H4 ( ES.3 6.9)' Replace with custom design base plate l ,
161 310 SLC-HD22 To be removed 161 311 SLC-HD23 No bolts 170 -312 RSW-H88 To be removed 170 313 RSW-HD163 Replace with standard base plate 170 ~314 RSW-HD164D To be removed 170 315 RSW-HD164E To be removed-170 316 RSW-HD166A Replace with standard base plate 170 317 RSW-HD166B To be removed 170 318 RSW-HD167 To be removed 170 319 RSW-HD241A To be removed 170 320 RSW-HD241C To be removed 172 321 RSW-HD227A To be removed 172 322 RSW-HD227B To be removed 172 323 RSW-HD244A To be removed ;
172 324 RSW-HD244B To be removed 172' 325 RSW-HD244C To be removed 172 326 RSW-HD246A To be removed 172 327 RSW-HD2469 Replace with standard base plate 172 328 RSW-HD246C To be removed 172 329 RSW-HD246D To be removed 172 .330 RSW-HD246E To be removed 172 331 RSW-HD243A To be removed 172- 332 RSW-HD245B Replace with standard base _ plate 1 172 333 RSW-HD245C To be removed l 172 334 RSW-HD245D To be removed 173- 335 RSW-HD245E To be removed 173 336'RSW-HD245G- To be removed 173 337 RSW-HD245H To be removed 173 338 RSW-HD245J Attached to structural steel l i 173 339 RSW-HD247A To be' removed 173 340 RSW-HD247B .To be removed 173 341 RSW-HD247D To be removed 173' 342 RSW-H2O Replace with standard base plate 173_ 343 RSW-HD181 Replace with standard base plate 173 344'RSW-HD184 To be removed
[F STATUS OF' DEADWEIGHT PIPE SUPPORTS l l
1 I
I Pipe Stress Pipe Support Problem No. Identification No. Status l
173 345 RSW-HD252 Replace with standard base plate l
173 346 RSW-HD255 Replace with standard base plate 173 347 RSW-HD256 To be removed !
173 348 RSW-HD257A Replace with standard base plate !
173 349 RSW-HD257B To be removed i
-173 350 RSW-HD301 To be removed 173 351 RSW-HD301A To be removed 173 352 RSW-HD302 To be removed 173 -353 RSW-HD303 To be removed 173 354 RSW-HD304 To be removed 175 355-RSW-H164 To be removed 175 356 RSW-H208 ( P.5.3 6.15) - Replace wi th custom design base plate 175 357 RSW-H39 Replace with standard base plate 175 358 RSW-HD172A To be removed 175 .359 RSW-HD172B To be removed 175 -360 RSW-HD177 To be removed 175 361 RSW-HD177A To be removed 175 362 RSW-HD206 To be removed 178 363 RSW-H85 To be removed 178 364 RSW-HD807A Attached to structural steel 178 365 RSW-HDBO7B To be removed 178 366 RSW-HD85 (F.S.'4.5) Replace with custom design base plate 178 367.RSW-HD178A Replace with standard base plate 178 368 RSW-HD178B Replace with standard base plate 178 369 RSW-HD179 ( P.S.2 4.58) Replace wi th custom design base plate 178 370 RSW-HD210 To be~ removed 178 371 RSW-HD260 To be removed 178 372 RSW-HD261A To be removed 178 373 RSW-HD261C To be removed 178 374 RSW-HD262 To be removed 178 375 RSW-HD263 Attached to structural steel 180 376 RSW-HD159 Replace with standard base plate 180 377 RSW-HD160 Replace with standard base plate 181 378 RSW-HD187 (F.5.54.65) Replace with custom design' base plate 181 -379 RSW-HD197A (F.$.* 6.15).Repl ace wi th custom desi gn base pl ate -
181 380 RSW-HD197B (P.S.s S.88) Replace with custom design base plate 181 381 RSW-HD2OOA (P.$.5 4.51) Replace with custom design base plate 181 382 RSW-HD2OOD To be removed 181 383 SW-H23 To be' removed 181 384 SW-H55 Attached to structural steel 181 385.SW-H56 Attached to structural steel
-181 386'SW-H57 Attached to structural steel 181 387 SW-H58 Attached to structural steel
STATUS OF DEADWEIGHT PIPE SUPPORTS l
l l-l Pipe Stress Pipe Support l Problem No. Identification No. Status l
181 388 SW-H59 To be removed l '181 389 SW-H7 (F. S. 5 6.17) Rep 1 ace with custom derign base p1 ate 181 390 SW-HD23 Attached to structural steel
[
181 391 SW-HD76A To be removed 181 392 SW-HD76B Attached to structural steel 182 393 RSW-HD197B To be removed 182 394 RSW-HD2OOB (F.5.3 8.16) Replace with custom design base plate 182 395 SW-H11 Attached to structural steel 182 396 SW-H13 Attached to structural steel 182 397 SW-HD7A .(F.5.= 5.lt) Replace with custom design base plate 182 398 SW-HD192 To be removed 182 399 SW-HD60 To be removed 182 400 SW-HD75 To be removed 182 401 SW-HD79C To be removed 182 402 SW-HD80C Attached to structural steel i 182 403 SW-HD80D Attached to structural steel 183 404 RSW-HD197B To be removed 183 405 RSW-HD2OOB To be removed 183 406 SW-HD266 (F.5.Sl8 lt) Replace with custom design base plate 183 407 SW-H3 Attached to structural steel 183 408 SW-H55 To be removed l
183 409 SW-H57 To be removed 183 410 SW-HD78 Attached to structural steel 183 411 SW-HD79A Attached to structural steel 183 412 SW-HD79B Attached to structural steel 183 413 SW-HD80A Attached to structural steel 183 414 SW-HD80B To be removed 190 415 HPCI-HD104A To be removed 190 416 HPCI-HD104B To be removed 190 417 HPCI-HD104C To be removed 190 418 HPCI-HD104D To be removed 190 419 HPCI-HD105A To be removed 190 420 HPCI-HD105B To be removed 190 421 MSD-HD2 ( F.5.3 4.54) Replace with custom design base plate 190 422 MSD-HD3 (F.5. 2 8 99) Replace with custom design base plate 201 423 FO-HD10 To be removed 1 201 424 FO-HD16 To be removed 201 425 FO-HD17 To be removed 201 426 FO-HD18 (F.5.*11.7$) Replace with custom design base plate 201 427 FO-HD19A Attached to structural steel t 201 428 FO-HD19B Attached tu structural steel l 201 429 FO-HDiC To be removed l 201 430 FO-HD1D To be removed 1
i
.+ ***
STATU3xOF DEADWEICilT PIPE SUPP, ORTS j l
Pipe Streus Pipe Support Problem No. Identification No. Status
-201 431 FO-HD20 Attached to structural steel.
201 432 FO-HD3A To be removed 201 433 FO-HD3B To be removed 201 434 FO-HD4B To be removed 4 201- 435 FO-HDB To be removed ,
211 436 RW-HD6 Attached to structural steel-211 437 RW-HD6A Attached to structural steel 211 438 RW-HD6B Attached to structural steel 211 439 RW-HDB To be removed
-211 440 RW-HD9 To be removed
.211- 441 CS-HD116 To be removed 211 442 CS-HD117 To be removed 211 443 CS-HD118 To be removed 211 444 CS-HD119 To be removed 211 445 CS-HD120 To be' removed 211 446 CS-HD121 To be removed
'211 447 CS-HD122 To be removed 220 448 SA-HD5A Attached laa structural uteel 220 449 SA-HD6A Attached to structural steel 220 450 SA-HD7A Attached to structural steel 220 451 SA-HDBA Attached to structural steel 221 452 SA-HD5B To be removed 221 453 SA-HD6B Attached to structural steel 221 454 SA-HD7B. To be removed 221 455 SA-HD8B Attached to structural steel 221 456 SA-HD9B . Attached to structural steel 305 457 SW-H42 (F.S.= 4.01 Replace with custom design base plate 305 458 SW-H43 ( F. $ . 5 5. l1L) Replace with custom design base plate 305 459 SW-H44- Attached to structural steel 305 460 SW-H45 Attached to structural steel 305 461 SW-H46 To be removed.
305- 462.SW-H47 Replace with~ standard base plate 305 463 SW-H48 To be removed.
305 464 SW-HD41A To be removed 305 465 SW-HD41B Replace with standard base plate 305 466 SW-HD41C To be removed 305 467 SW-HD41F To be removed
.306 468 RSW-HD306B Attached to embed Plate 306 469 RSW-HD306C (F.5.5 51.l4)Repl ace wi th custom ' design- base pl ate 307 470 RHR-HD2 Tu be removed 307 471 RHR-HD20 To be removed 307- 472 RHR-HD21' To be removed 307 473 RHR-HD24 (F.5. 5 40.0) Replace with custom design base plate
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STA'IUS OF DEADUEIGilT PIPE SUPPORTS l
Pipe Stress Pipe Support
. Problem No. Identification No. Status 307 474 RHR-HD3 (f.S.: 13.35) Rep 1 ace with custom design base p1 ate 307 475 RHR-HD31 (F.5.= 6.55) Replace wi th custom design base plate 307 476 RHR-HD32 To be removed 307 477 RHR-HD33 Attached to structural steel 307 478 RHR-HD34- To be removed 307 479 RHR-HD3G (P.S.5 6.47) Replace with custom deuign base plate 307' 480 RHR-HD37 Replace with standard base plate 307 481 RHR-HD38A To be removed 307 482 RHR-HD38E ( F.5.* S.52.) Replace with custom design base pl ate 307 483 RHR-HD38F To be removed 307 484 RHR-HD38H (F.5,s 80.0) Replace with custom design base plate 307 . 485 RHR-HD38I (F.5. 5 40.0) Replace with custom design base plate 307 486 RHR-HD3BJ To be removed 307 487 RHR-HD38K (F.5.* 16.0) Replace wi th custom design base plate -
307 488 RHR-HD4 ( F. 5.sl4. 81) Re.pla.c.e with c.ostom design ba.Se Plate.
307 489 RHR-HD5 To be removed 307 490 RHR-HD6 (F.5.
- 7.01) Replace with cuctom design base p1 ate GLC/4 491 SLC-HDG7 ( F. 5. 7 4.0) Replace with custom design base plate SLC/4 492 SLC-HD43 (F.5.7 4.0) Replace with custom design base plate GLC/4 493 SLC-HD20 Replace with standard base plate ,
RC/10 494 RCIC-HD93 To be removed 493 RCIC-HD943 To"be removed k RC/10 AC /3844 496 ACSP-HD33a Function change (redesign) l AC/3t<4 497 ACSP-HD33G To be removed i AC/3844 498 ACSP-HD33L To be removed AC/3t<4 499 ACSP-HD233N Attached to structural steel AC/3&4 500 ACSP-HD2OOA Attached to structural steel AC/3&4 501 ACSP-HD2 OOC Attached to structural steel AC/3&4 502 ACSP-HD2OOD To be removed AC/3&4 503 ACSP-HD2OOE To be removed HPCI/10 504 HPCI-HD66H To be removed
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