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A list of all pages that have property "Title" with value "Forwards ASME Section XI ISI Data Rept". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20004D959  + (Forwards ASLBP Model Hearing Schedule Over 10-month Time Frame)
  • ML20237J633  + (Forwards ASME Boiler & Pressure Code Section Xi,Form NIS-1 as Encl 1 to Inservice Insp Rept.Encls 2 & 3, 1986 Inservice Exam of Selected Class 1 & 2 Components & Sys,Vols 1-5 & Steam Generator 11 & 12..., Respectively, Not Encl)
  • ML18026A308  + (Forwards ASME Boiler & Pressure Vessel Code,Section 3 Overpressure Rept Per FSAR Question 211.204)
  • ML20084J939  + (Forwards ASME Boiler & Pressure Vessel Code Section Xi,Form NIS-1,eddy Current Exam of Steam Generators 11 & 12 & Inservice Insp Rept of Class 1 & 2 Components)
  • ML20028F268  + (Forwards ASME Boiler & Pressure Vessel Code Section XI IWP-IWV Testing)
  • ML20040B449  + (Forwards ASME Class I,Ii & III Inservice Insp Rept for Millstone Unit 1,1980)
  • ML20095G792  + (Forwards ASME Code Baseline Document Re NRC Unresolved Item 83-07-02 & Draft SER Open Item 42,presented to NRC at 840726 Meeting in Bethesda,Md.Document Will Be Referenced in Sections of Future FSAR Amend)
  • ML20036A797  + (Forwards ASME Code Comparisons,For Review,Specifically as to Whether Any Planned Code Comparisons Listed in Attachment a Seem Unwarranted or If Other Citations in Attachments B or C Should Be Included in Comparison List)
  • ML20141D976  + (Forwards ASME Code Evaluation of Braidwood Unit 2 Nozzle F to Include Effects of Proposed Grindouts. ASME Code Section III Requirements Maintained W/Up to 1-inch Grindout Depth w/three-to-one Tapering & W/O Weld Repair)
  • ML20141D981  + (Forwards ASME Code Evaluation of Braidwood Unit 2 Nozzle F to Include Effects of Proposed Grindouts. ASME Code Section III Requirements Maintained W/Up to 1-inch Grindout Depth w/three-to-one Tapering & W/O Weld Repair)
  • ML20133D176  + (Forwards ASME Code Interpretation Request & Response Re C-360 parent-daughter Transfer Sys & Need for Pressure Relief on Transfer Manifold for Compliance Plan Issue 3, Action 9)
  • PLA-2549, Forwards ASME Code NIS-1 Form Re Preservice Exams & GE & Nuclear Energy Svcs Preservice Insp Repts  + (Forwards ASME Code NIS-1 Form Re Preservice Exams & GE & Nuclear Energy Svcs Preservice Insp Repts)
  • ML17139D233  + (Forwards ASME Code NIS-1 Form Re Preservice Exams & GE & Nuclear Energy Svcs Preservice Insp Repts)
  • ML20079E748  + (Forwards ASME Code Rept Re Overpressure Protection,In Response to OL Safety Review Request for Addl Info, Question 440.3)
  • ML20056C426  + (Forwards ASME Code Section XI IST Program for 3rd 10-Yr Interval for Prairie Island Nuclear Generating Plant,Units 1 & 2)
  • ML111960070  + (Forwards ASME Code Section XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements, Revision 3)
  • ML17334A452  + (Forwards ASME Code Section XI Valve Test Program for DC Cook Nuclear Units 1 & 2)
  • ML20127L237  + (Forwards ASME Code Update for Third Interval ISI Program, Per 10CFR50.55(a(g))
  • ML20127L241  + (Forwards ASME Code Update for Third Interval ISI Program, Per 10CFR50.55(a(g))
  • ML20031C964  + (Forwards ASME Committee on Nuclear QA Comments on Reg Guide Tp 020-4 QA Program in Packaging Used in Transportation of Spent Fuel,High Level Waste & Pu. Review Is Not Approval or Endorsement of Document But Aid in Future Revision)
  • ML20115G703  + (Forwards ASME Form NIS-1, Owners Data Rept for Inservice Insps, as Followup to Submitting Refueling Interval 9R once-through SG Tube Insp Rept)
  • ML20205F587  + (Forwards ASME III Code Case N-318-3 Application at Plant, Per in Response to 860429 Request for Use of Code Case)
  • 1CAN069604, Forwards ASME Relief Request Re Hold Times for Class 1 Sys Hydrostatic Exams  + (Forwards ASME Relief Request Re Hold Times for Class 1 Sys Hydrostatic Exams)
  • ML19259C477  + (Forwards ASME Response Supporting Util Contention Re Welding of Split Backing Rings in Const.Requests NRC re-examine Apparent Noncompliance & Consider Changing Infraction to Observation)
  • ML19282B345  + (Forwards ASME Response to Util Inquiry Re Identified Noncompliance on Radiographic Procedure,Which Is Being Held in Abeyance.Requests Status Change of Item from Infraction to Observation.W/Encl Pertinent Correspondence W/Asme)
  • B10987, Forwards ASME Section Iii,Class 2 & 3 & ANSI B31.1.0 Piping Analysis, Ultrasonic Indications in Steam Generator Top Head Dome Weld. Evaluation Verified Structural Integrity of Plant Steam Generators,Per NRC  + (Forwards ASME Section Iii,Class 2 & 3 & ANSI B31.1.0 Piping Analysis, Ultrasonic Indications in Steam Generator Top Head Dome Weld. Evaluation Verified Structural Integrity of Plant Steam Generators,Per NRC)
  • ML20217G120  + (Forwards ASME Section XI ISI Summary Rept for Sequoyah Nuclear Plant,Unit 1 Refueling Outage Cycle 8)
  • ML18038B895  + (Forwards ASME Section XI ISI Summary Rept for BFN Unit 3 Cycle 7 Refueling Outage 970222-0313, for Review)
  • ML18038B896  + (Forwards ASME Section XI ISI Summary Rept for BFN Unit 3 Cycle 7 Refueling Outage 970222-0313, for Review)
  • ML20199F844  + (Forwards ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8, for Period 960609- 971104.Rept Provided IAW IWA-6220 & IWA-6230 of ASME Code, Section XI)
  • ML20058C112  + (Forwards ASME Section XI Inservice Testing Program Plan Revised Relief Requests & Supplemental Info,Per)
  • 3F0895-04, Forwards ASME Section XI Pump & Valve Program Inservice Inspection, for Crystal River Unit 3  + (Forwards ASME Section XI Pump & Valve Program Inservice Inspection, for Crystal River Unit 3)
  • ML20205P440  + (Forwards ASME Section XI Pump & Valve Test Programs,Units 1 & 2,Second 10-Yr Interval. Program Will Take Effect on 870401,including All Requests for Relief.Inservice Exam & Pressure Testing Program Will Be Submitted Later.Fee Paid)
  • ML18153A408  + (Forwards ASME Section XI Relief Request 12 for Unit 1.Relief Request Approved by Station Nuclear Safety & Operating Committee)
  • ML19305D693  + (Forwards ASME Section XI Repairs & Revisions Rept,Procedure L.S.Q.P. 3.1,Revision O)
  • ML19305D694  + (Forwards ASME Section XI Repairs & Revisions Rept,Procedure L.S.Q.P. 3.1,Revision O)
  • NG-95-2142, Forwards ASME Section XI Summary Rept for DAEC Refueling Outage 13, Addressing Exams Performed from 931014-950419. Second ten-yr Interval Extended to 961101 in Accordance W/ 10CFR50.55a.Info Re Augmented ISIs Performed Also Encl  + (Forwards ASME Section XI Summary Rept for DAEC Refueling Outage 13, Addressing Exams Performed from 931014-950419. Second ten-yr Interval Extended to 961101 in Accordance W/ 10CFR50.55a.Info Re Augmented ISIs Performed Also Encl)
  • ML20065F999  + (Forwards ASME Section XI Summary Rept for Davis-Besse Nuclear Power Station Unit 1 Refueling Outage 6)
  • ML20236C583  + (Forwards ASME Section XI Summary Rept for Davis-Besse Unit 1 Refueling Outage 5, for Mar-Dec 1988 Inservice Insp)
  • ML17349A809  + (Forwards ASME Section Xi,Div 1,Code Case N-514, LTOP, in Support of 930408 Exemption Request)
  • IR 05000266/1992010  + (Forwards ASP Analysis of LER 50-266/92-010.Analysis Will Be Part of NUREG/CR-4674)
  • ML20148M410  + (Forwards ASP Rev 5 & Sper for Subj Facil in Rough Draft Form.Encl to Be Withheld from Pub Disclosure Pursuant to 10CFR2.790)
  • ML19254D556  + (Forwards ASTM Committee D-33 Comments on Proposed Reg Guide 1.58,Revision 1, Protective Coating & Lining Work for Power Generation Facilities)
  • ML19341A647  + (Forwards ATR-1320, Analysis of Halden Irradiation Fuel Assembly IFA-223 by GEGAP-3 Code, Included in NEDE-23785-P. Rept Withheld (Ref 10CFR2.790).Affidavit for Withholding Encl)
  • NRC-89-0140, Forwards ATWS Alternate Rod Insertion & Recirculation Pump Trip,Response to NRC Rule 10CFR50.62  + (Forwards ATWS Alternate Rod Insertion & Recirculation Pump Trip,Response to NRC Rule 10CFR50.62)
  • ML17272A238  + (Forwards ATWS Cost Estimaters.Views ATWS as Licensing,Not Plant Safety Issue)
  • ML20212E844  + (Forwards ATWS Mitigating Sys Actuation Circuitry Preliminary Conceptual Design Rept & Response to plant-specific Questions Contained in NRC Safety Evaluation of WCAP-10858, Per 861024 Commitment)
  • ML18150A508  + (Forwards ATWS Mitigation Sys Actuation Circuitry plant- Specific Design Features,Per 870107 Commitment.Changes Made Between Submitted & Actual Features Will Be Provided as Addl Info)
  • ML20235R194  + (Forwards ATWS-AMSAC Design Features,Per Commitment in .Engineering on Sys in Progress But Incomplete. Installation of Sys Planned for Refueling Outages at End of Cycles 6 & 7 for Units 1 & 2,respectively)
  • ML19246C545  + (Forwards AV Grosse Suggesting That Releases of Radioactivity Be Marked by Coloring of Plume.Requests Review of Suggestion)
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