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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20149G8581994-10-31031 October 1994 Provides NRC W/Error Notice Received from Former Software Supplier ML20058L9001993-05-0404 May 1993 Part 21 Rept Consisting of Gtices Program Error Notice 93.14 Re Ibm RS6000 Computers Gt Modeler Recovery File.Resized Graphics Screen Can Not Be Completely Recovered.Lists Customers Not Notified Because of Unknown Current Addresses 1994-10-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210E9411999-07-22022 July 1999 Safety Evaluation Supporting Amend 14 to License R-97 ML20207A6541999-02-26026 February 1999 1998 Annual Rept for Ga Institute of Technology Research Reactor. New TS No Longer Require Annual Operating Rept to Be Submitted to Nrc.Rept Submitted Since Facility Under Previous TS for Portion of CY98 ML20155G9901998-11-0404 November 1998 Safety Evaluation Supporting Amend 13 to License R-97 ML20236Q0781998-06-0404 June 1998 Rev 3 to 82A9083, Ga Inst of Technology Research Reactor Decommissioning Plan ML20217K7981998-04-0202 April 1998 Safety Evaluation Supporting Amend 12 to License R-97 ML20203H0571998-02-24024 February 1998 1997 Annual Rept for Ga Institute of Technology Research Reactor ML20135D2821996-12-31031 December 1996 1996 Annual Rept for Ga Institute of Technology Research Reactor ML20106G4281996-02-27027 February 1996 Annual Rept for Ga Inst of Technology Research Reactor for CY95 ML20078A0001995-01-10010 January 1995 SAR for 5 MW Ga Tech Research Reactor, Revised from First Submittal,Apr 1994 ML20149G8581994-10-31031 October 1994 Provides NRC W/Error Notice Received from Former Software Supplier ML20072D5071994-07-27027 July 1994 Ro:On 940722,drift of Temp Trip Setting of Primary Coolant Occurred.Suspect Drift Occurred Since 940522 Due to Failure of Compressor That Provides Bldg Compressed Air.New Equipment Ordered to Replace Current Unit ML20070M9701994-04-30030 April 1994 SAR for 5 MW Georgia Tech Research Reactor. W/Financial Qualifications of Georgia Institute of Technology to Operate Georgia Tech Research Reactor ML20064N3581994-03-31031 March 1994 Nucleate Boiling Characteristics & Critical Heat Flux Occurrence in Subcooled Axial-Flow Water Sys ML20063L4971994-02-25025 February 1994 Annual Rept for Ga Inst of Technology Research Reactor ML20058L9001993-05-0404 May 1993 Part 21 Rept Consisting of Gtices Program Error Notice 93.14 Re Ibm RS6000 Computers Gt Modeler Recovery File.Resized Graphics Screen Can Not Be Completely Recovered.Lists Customers Not Notified Because of Unknown Current Addresses ML20128A1481992-09-30030 September 1992 Analyses for Conversion of Ga Tech Research Reactor from HEU to LEU Fuel ML20090B3821992-02-24024 February 1992 Annual Rept for 1991 (CY91) for Ga Institute of Technology Research Reactor ML20096H5461991-12-31031 December 1991 Corrected Pages 13 & 14 to Annual Rept,Consisting of Item 7(e) Re Max Cumulative Radiation Dose Which Could Have Been Received by Individual Continuously Present in Unrestricted Area During Reactor Operation ML20079B1551991-06-0707 June 1991 Amend to 1990 Annual Rept - Georgia Tech Research Reactor. Submittal Corrects Error in Item 1.f on Page 5 Re Changes in Plant Staff & Committee Membership ML20065S7981991-01-0202 January 1991 Requalification Program for Reactor Operators/Senior Reactor Operators,Georgia Tech Research Reactor ML20235W8571989-02-21021 February 1989 Annual Rept for 1988 ML20151C0681988-07-12012 July 1988 Safety Evaluation Supporting Amend 7 to License R-97 ML20154N0061988-04-19019 April 1988 Neely Nuclear Research Ctr Response to NRC Concerns ML20151R1981988-03-29029 March 1988 Rept of Visit to Georgia Tech Research Reactor Facility to Inspect Facilities & to Interview Operational Staff ML20148E3451988-03-14014 March 1988 Incident Rept of Cadmium Spill on 870818 ML20148F3191988-02-26026 February 1988 Annual Rept for 1987.Related Info,Including Revised Procedure 3800, Liquid Waste Disposal Sys, from Chapter 15 of Auxiliary Sys Encl ML20207T4171987-02-16016 February 1987 Annual Rept for 1986,including Operations Summary,Power Generation,Shutdowns,Unscheduled Maint on safety-related Sys & Components & Changes,Test & Experiments W/O Prior NRC Approval ML20235X1721986-12-31031 December 1986 Rev 1 to 1986 Annual Rept, Correcting Several Errors in Section 7, Environ Monitoring ML20009A1861981-03-13013 March 1981 Annual Operating Rept for 1980 ML19310A3451980-05-23023 May 1980 Ro:On 800410,heavy-water Temp Recorder TRA-D1 Was Not Recalibr After Replacement of Worn Sliding Contacts on Scanner Select Switch.Cause Not Stated.Importance of Recalibr Emphasized to Personnel ML19309F1241980-04-14014 April 1980 RO 80-02:on 800305,low Flow Scram of Flow Recorder FRA-D1 Resulted in Reactor Trip & Subsequent Shutdown.Caused by Broken Teflon Gasket Pieces Restricting Flow.Gasket Repaired & Sys Refilled ML19309F0881980-04-11011 April 1980 RO 80-1:on 791009,during ECCS Tank TD-2 Monthly Flow Rate Verification,Flow Rate Observed to Be 8 Gpm.Caused by Loose Lock Nuts Which Fix handle-to-ball Operating Shaft. Surveillance Program Will Be Strengthened ML20009A1891980-02-28028 February 1980 Annual Operating Rept for 1979 ML20009A1901979-03-0707 March 1979 Annual Operating Rept for 1978 1999-07-22
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I
,. Boeing Computer services .
1 P.o. Box 24346 i scattle. WA 98124-0346 i
.I ,
.. c October 31,1994 G-1151-RSO-94-534 -
Document Control Desk United States Nuclear Regulatory Commission ,
, Washington, D.C. 20555 pap /pp
Reference:
a) Boeing Letter G-1151-RSO-92-365 dated August 31,1992; R. S. Orr to the NRC Operations Center ,
b) NRC Letter Docket No. 99901227 dated August 12,1992; L.
J. Norrholm to R. S. Orr;
Subject:
Response to 10 CFR 21 inquiry
Dear Sir or Madam:
In accordance with the reference correspondence and 10 CFR 21, Boeing is i sending the NRC the attached error notice (s) received from our former l software suppliers. Because of unknown current addresses, the following former customers were not notified:
Reactor Controls, Inc. ;
Echo Energy Consultants, Inc.
Nuclear Applications and Systems Analysis Company (Japan)
Nuclear Power Services Error notices have been sent to our other former customers. ,
l
, Very truly yours, R. S. Orr Nuclear Administrator G-1151 M/S 7A-33
, (206) 865-6248 i Attachment (s): GTICES Program Report Form No. 94.24 ;
h 9411080126 941031 if PDR ADOCK 05000160 f P PDR 1
4 9
GeorgiaTech GT STRUDL3 October 27,1994 Attention: Nuclear Administrator iS Ilocing Computer Services P.O.llox 24346, M/S 7A-33 gg 3 i N Seattle, Washington 98124-0346 CON.(,.,,.,e-RE: GT STRUDL
Dear Sir or Madam:
Enclosed please find a copy of the GTICES PROGRAM REPORT FORM No. 94.24 and a VENDOR ACKNOWLi_DGEMENT FORM. Please sign and return the VENDOR ACKNOWLEDGEMENT FORM to acknowledge receipt of the GTICES Program Report.
Thank you for reviewing the Program Report and for returning the Acknowledgement Form.
Best regards, CASE Center
- - ~
Catherine Lee Configuration Control Manager CUapw Enclosures l
l School of Civil & Environmental Engineering Computer Aided Structural Engineering Center Georgia institute of Technology Phone: (404) 894-2260 Atlanta, Georgia 30332-0355 USA Fax:(404) 894 8014 A Umi of the Umverdtv System of Georgia
7 f
GTISL Program Report Form G P R F N o.: #k 2M
/
DATE: /O!2[h C/
FROM: GTICES SYSTEMS LABORATORY GEORGIA INSTITUTE OF TECHNOLOGY ATLANTA, GEORGIA 30332-0355 SEVERITY LEVEL:
_ URGENT Problem results in incorrect answers which may not be appareta or job abons and cannot be recovered within the session or job.
_ SERIOUS Problem results in incorrect answers which are obvious or problem prevents completion of a particular user's task.
X MINOR Problem can be worked around or problem poses high fmstration factor.
_ INFORMATIVE Documentation error, program usage tip, user inconveniences.
DATE PROBLEM CONFIRMED October 26.1994 DATE NOTIFICATION SENT 8eIo/>e,- 2[ /5'/ 9 COMPUTERS All OPERATING SYSTEM All GTISL PRODUCT NAME GTSTRUDL VERSION All versions up to and including 94.01 TARGET RELEASE FOR CORRECTION 94.02 Rev 2.1 15-6 l
0; GTISL Program Report Form
,.- (Continued)
G P R P N o.: fE.3 Y !
DATE: /0/26/94 ,
b DESCRINION: :
i The STIFFNESS ANALYSIS command will abon for a model that contains nonlinear support spring elements. The NONLINEAR ANALYSIS command is the only valid analysis command when nonlinear support spring elements are used.
Applicable sections of the User's Manual: ,
Section 2.5, Volume 3 Nonlinear Static Analysis i
he A Mer. ASD ;
Signature Title Software R&D Divisien l
Michael H. Swanger October 26.1994 t Typed or Printed Name Date of Signature hdtun6 & D&YdN kenmW '
5 Signature Title / l Professional Services Division ;
bu>rtwe hln joktkJ Typed or Printed Name Date ofdignature Rev 2.1 15-7 .;
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