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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20083M1611983-10-24024 October 1983 Part 21 Rept Re Noncompliance to ASME Code Test Requirement Involving Nuclear Part Not Receiving Pressure Test Prior to Acceptance.Change Control Procedure Revised to Be More Explicit on Types of Documents Utilized ML20009D4511981-07-15015 July 1981 Part 21 Rept Re Defects in Lamco Industries Guide Tube Assemblies.Mark 27-30 to Mark 27-32 Weld on Guide Tube S/N 1683 Rejected for Incomplete Fusion.Repair Will Be Completed by 811001 ML19351E5281980-11-14014 November 1980 Part 21 Rept Re Inoperable Prototype Valve,Reported on 801015.Procurement Controls Are in Place to Prevent Fabrication of Plant Valves Prior to Design Verification. Evaluation Determined Malfunction Nonreportable 1983-10-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20080S6761984-02-29029 February 1984 Draft Site Redress Plan ML20083C8921983-12-27027 December 1983 Final Rept of Crbr Piping & Valve Technical Support Team ML20083M1611983-10-24024 October 1983 Part 21 Rept Re Noncompliance to ASME Code Test Requirement Involving Nuclear Part Not Receiving Pressure Test Prior to Acceptance.Change Control Procedure Revised to Be More Explicit on Types of Documents Utilized ML20085A7361983-07-0606 July 1983 Rev 2 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20023D4071983-05-31031 May 1983 Amend 77 to PSAR ML20076D3201983-05-31031 May 1983 Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins ML20072B3561983-05-27027 May 1983 Crbr Erosion & Sediment Control Plan Rept ML20084L9931983-03-31031 March 1983 Rev 5 to Hypothetical Core Disruptive Accident Considerations in Crbrp, Vol 2, Assessment of Thermal Margin Beyond Design Base ML20071F1971983-03-10010 March 1983 Adequacy of Crbr Program Reactor Vessel NDE Insps ML20072B6401983-03-0404 March 1983 Crbr Program Heat Transport Sys Incontainment Piping Reserve Seismic Margins ML20079N3691983-03-0202 March 1983 Amend 76 to PSAR ML20028G4251983-02-28028 February 1983 Amend 75 to PSAR ML20070W2001983-02-28028 February 1983 Corrected Pages to Page Replacement Guide of Amend 75 to PSAR ML20079L5131983-02-10010 February 1983 Sodium Slug Energy Absorption Capability of Modified Crbr Closure Head, Westinghouse Crbr Engineering Study Rept ML20028C2911983-01-31031 January 1983 Crbr PSAR Chapter 17.0-QA,App D Description of NSSS QA Program, Submitted for Inclusion in Amend 75 to PSAR ML20064J9381983-01-0707 January 1983 Crbr Reliability Assurance Activities ML20070H8321982-12-31031 December 1982 Assessment of Unprotected Loss of Flow Accident at End of Cycle-4 in Crbr Heterogeneous Core Design ML20070K6661982-12-31031 December 1982 Amend 74 to PSAR ML20070H8521982-12-23023 December 1982 Freezing of Driver Fuel Upon Entry to Inner Blanket ML20070M0801982-12-21021 December 1982 Reactor Vessel Core Support Cone Structural Integrity ML20057B5651982-12-0909 December 1982 Partially Withheld Commission Paper Re NRDC Vs NRC 82-1962 Re Facility ML20057B5631982-12-0707 December 1982 Partially Withheld Commission Paper Informing Commission of DC Circuit Court Decision Re Facility ML20028E9371982-11-30030 November 1982 Crbr Plant Verification of FORE-2M Computer Code,Part II-Comparison w/EBR-11 Natural Circulation Experiments. ML20028B4681982-11-30030 November 1982 Amend 73 to PSAR ML20028B4811982-11-23023 November 1982 Thermal Margin Beyond Design Basis (Tmbdb) Melting Scenario. ML20065S2491982-10-31031 October 1982 Amend 72 to PSAR ML20070C8921982-10-31031 October 1982 Aerosol Release from Sodium-Concrete Reactions. Prototype Hydrogen Filter Preliminary Test Results Encl ML20070C9171982-10-31031 October 1982 Hydrogen Distribution in Breeder Reactor Containments, Summary Rept.Miscellaneous Updates to CRBRP-3,Vol 2 Info on Containment Cleanup Sys & Revised Response to Question CS760.144 on Axisymmetric Distribution of Temps Encl ML20028A6141982-09-30030 September 1982 Supplementary Manual for F0RE-2M Computer Program. ML20027B9471982-09-30030 September 1982 Amend 71 to PSAR ML20083M7271982-08-31031 August 1982 Thermal Margin Beyond Design Base (Tmbdb) Sodium-Concrete Penetration Margins Assessment for Crbr Plant ML20062H0821982-08-31031 August 1982 Limited Const Activities Rept ML20062N5901982-08-31031 August 1982 Amend 70 to PSAR ML20055C1621982-08-13013 August 1982 Recommends Modifying Proposed Decision Granting in Part Exemption from 10CFR50.12 by Adding Provision Re Endangered Species Act ML20057B5371982-08-10010 August 1982 Partially Withheld Commission Paper to Provide Draft Order Concluding Commission Proceeding on DOE Request for Exemption Per 10CFR50.12 ML20062D6121982-08-0404 August 1982 Hypothetical Core Disruptive Accident Considerations in Crbrp:Assessment of Thermal Margin Beyond Design Base, Vol 2,Revision 4 ML20071K4221982-07-31031 July 1982 Amend 69 to PSAR ML20058J0261982-07-30030 July 1982 Page Replacement Guide for Amend 69 to PSAR ML20058E4561982-07-22022 July 1982 Crbr Plant Rept ML20065A3701982-07-16016 July 1982 Draft Revision 1 to Analysis of Nominal Heat Removal Capacity of Crbr in Natural Circulation Mode ML20054H8261982-06-30030 June 1982 SITE-SUITABILITY Report in the Matter of the Clinch River Breeder Reactor Plant.Docket No. 50-537 ML20024E4851982-06-30030 June 1982 Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, Rev D ML20063D4631982-06-30030 June 1982 Site Preparation Activities Rept ML20063G8551982-06-30030 June 1982 Updated Pages for Ref 106 of PSAR Section 1.6,CRBRP-3,Vol 2, Hypothetical Core Disruptive Accident Considerations in Crbr:Assessment of Thermal Margin Beyond Design Base ML20054K9341982-06-30030 June 1982 Speech Entitled Simulation of Lmfbr ML20054G4801982-05-31031 May 1982 Crbr Special Matls Considerations, Crbr Engineering Study Rept ML20054G4881982-05-31031 May 1982 Crbr Special Stress & Criteria Considerations, Crbr Engineering Study Rept ML20054F1371982-05-31031 May 1982 Verification of Natural Circulation in Crbr Plant - Update ML20071E1011982-05-31031 May 1982 LMFBR Program, Fes ML20054G4651982-05-31031 May 1982 Crbr Matls Data Base, Crbr Engineering Study Rept 1984-02-29
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4 to-2%-coi Qj Atomics intemational Division Energy Systems Group 8900 De Soto Avenue Rockwell
. Canoga Park. Califemia 91304 Intefriah.Onal Telephone; (213) 341 1000 TWX: 91o-494-1237 ESG CN PK Telex: 181017
. g ESG CNPK A November 14, 1980 In reply refer to 80ESG10866 Director, Office of Inspe-nn and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555
Reference:
Energy Technology Engineering Center Letter 80ETEC-DRF-44766, dated 0:tober 15, 1980,
Subject:
Potential 10CFR21 Defect or Deviation Gentlemen:
Subject:
Functional Inoperability of a Prototype 4 In. Sodium Valve for CRBRP After Seismic Design. Verification Testing The referenced letter, a copy of which was sent to your office, in-formed Atomics International of the inoperability of a prototype valve undergoing design verification testing at the Energy Technology Engineering Center of the US Department of Energy. The valve in question had been procured by Atomics International from the William Powell Company of Cincinnati, Ohio, an: subsequently transferred to ETEC for testing.
This letter is to inform you that Ator.ics International has evaluated this valve malfunction relative to 10CFR21 reporting criteria, and has determined it to be nonreportable. The basis of this decision was the prototypic nature of the valve, in which any problem encount-ered during design verification testing would be corrected in valves intended for use in the CRBRP. Procurement controls are in place to prevent fabrication of plant valves prior to verification of the acceptability of the design.
Details of this problem will be available in the final Unusual Occur-rence Report to be issued by ETEC as UOR ETEC-80-19-GENL-80-02 upon completion of failure analysis.
A
Director, Office of Inspection and Enforcement Page 2 US Nuclear Regulatory Cornission November 14, 1980 Washington, DC 80ESG10866 If you have an Nagel at (213)y341-1000, questionsExtension on this subject, 1964. please contact Mr. W. E.
Very truly yours, 07/
R. J. ftDermott Director Quality Assurance cc Mr. A. Horn US Nuclear Regulatory Commission 1990 No. California Blvd, Suite 202 Walnut Creek, California 94696 Mr. R. Fenton Energy Technology Engineering Center PO Box 1449 Canoga Park, California 91304 Mr. D. Hunter US Nuclear Regulatory Commission 611 Ryan Drive, Suite 1000 Arlington, Texas -76012 i
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