(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20214Q2701986-09-18018 September 1986 Part 21 Rept Re Defective Interlock in Control Rods During Movement to Full Up Position.Initially Reported on 860915. Corrective Action Will Be Taken by Univ of Illinois & Univ of California at Irvine 1986-09-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20216F9831999-09-20020 September 1999 Safety Evaluation Supporting Amend 11 to License R-115 ML20217B5651999-06-30030 June 1999 Univ of CA Irvine Nuclear Reactor Facility Annual Rept for 980701 to 990630. with ML20205N4461999-04-12012 April 1999 Safety Evaluation Supporting Amend 10 to License R-115 ML20202A7441999-01-22022 January 1999 Safety Evaluation Supporting Amend 4 to License R-116 ML20207C4271998-12-31031 December 1998 Annual Rept 980101-1231 Il Advanced Triga. with ML20195D6111998-10-31031 October 1998 Safstor Decommissioning Plan for Univ of Il Nuclear Reactor Lab ML20153F1361998-06-30030 June 1998 UC Irvine Nuclear Reactor Facility Annual Rept for 970701- 980630. with ML20202F4971997-12-31031 December 1997 Annual Rept 970101-1231 Il Advance Triga ML20149G2091997-07-16016 July 1997 Safety Evaluation Granting Order Terminating Facility License R-117 for Univ of Il at Urbana-Champaign Lopra ML20199L6631997-06-30030 June 1997 UC Irvine Nuclear Reactor Facility Annual Rept for 960701-970630 ML20133N7511997-01-21021 January 1997 Safety Evaluation Supporting Amend 6 to License R-117 ML20138M1511996-12-31031 December 1996 Annual Rept,1996 Il Advanced Triga ML20115J0521996-06-30030 June 1996 Annual Rept for Jul 1995-June 1996 ML20091L7731995-07-31031 July 1995 Illinois Lopra Reactor-Annual Rept for Aug 1994 - Jul 1995 ML20091L3791995-06-30030 June 1995 Univ of CA Nuclear Reactor Facility Annual Rept for Jul 1994 - June 1995 ML20080K8671995-02-28028 February 1995 Decommissioning Plan for Univ of Il Lopra ML20072C6831994-08-12012 August 1994 Ro:Damage Noted on Aluminum Clad Fuel Element in Lopra Reactor.Suspect Damage Occurred in Nov 1993 When Burr Removed from Lopra Upper Grid Plate.Fuel Element Removed from Lopra Core & Wrapped in Polyethylene ML20072L5001994-07-31031 July 1994 Illinois Lopra Reactor Annual Rept for Aug 1993 - Jul 1994 ML20059L0391993-11-0909 November 1993 Ao:On 931108,problem Discovered in Apparent Binding of Adjustable Transient Rod Externally Theaded Cylinder & Piston.Cylinder Cleaned & Honed Slightly W/Emery Cloth & Then Relubricated ML20056H3241993-08-31031 August 1993 Forwards Annual 10CFR50.59 Rept Per Section 6.7.f of TSs ML20046C3671993-06-30030 June 1993 Univ of California Irvine Nuclear Reactor Facility Annual Rept for Jul 1992-June 1993. W/930730 Ltr ML20128P8661993-02-16016 February 1993 Safety Evaluation Supporting Amend 6 to License R-115 ML20127C8971992-07-31031 July 1992 Annual Rept Aug 1991 - Jul 1992 Illinois Lopra Reactor ML20099G4661992-06-30030 June 1992 Univ of California Irvine Nuclear Reactor Facility Annual Rept for Jul 1991 to June 1992 ML20085E0011991-07-31031 July 1991 Illinois Lopra Reactor Annual Rept for Aug 1990 - Jul 1991 ML20079D5911991-07-0909 July 1991 Ro:On 910703,SRO Noticed Uncontrolled or Unanticipated Change in Reactivity During Operation to Calibr Shim Control Rod on Reactor.Caused by Overheating of Aged Resistor.On 910708,resistor Was Replaced ML20077J8981991-06-30030 June 1991 Annual Rept for Uci Nuclear Reactor Facility for Jul 1990 - June 1991 ML20059M1401990-07-31031 July 1990 Annual Rept Aug 1989 - Jul 1990,Illinois Lopra Reactor ML20058L0761990-07-26026 July 1990 Univ of Illinois Nuclear Reactor Lab Operator Requalification Program ML20055J3941990-07-11011 July 1990 Revised Univ of Illinois Nuclear Reactor Lab Operator Requalification Program ML20058L5961990-06-30030 June 1990 Univ of California Irvine Nuclear Reactor Facility Annual Rept for Jul 1989 to June 1990 ML20042D8221990-01-31031 January 1990 Site Description Nuclear Reactor Lab,Univ of Illinois. ML20011D7731989-12-18018 December 1989 Ro:Transient Control Rod Stuck Towards Upper End of Travel During Routine start-up Checks.Complete Rod Assembly Removed for Insp Showed Plastic Piston Deteriorated.New Piston Installed,Tested & Returned to Svc ML20248E1081989-09-30030 September 1989 SAR for Low Power Reactor Assembly ML20248E1331989-07-31031 July 1989 Annual Rept for 880801-890731 ML20246N3111989-06-30030 June 1989 Annual Rept for Jul 1988 - June 1989 ML20235U5011988-12-31031 December 1988 Annual Rept 1988 ML20245D6931988-07-31031 July 1988 Annual Rept Illinois Lopra Reactor Aug 1987 - Jul 1988 ML20207J0821988-06-30030 June 1988 Annual Rept for Jul 1987 - Jun 1988 ML20147A9681987-12-31031 December 1987 Annual Rept for 1987 ML20236N1511987-08-0404 August 1987 Safety Evaluation Supporting Amend 4 to License R-117 ML20236M6031987-08-0404 August 1987 Safety Evaluation Supporting Amend 5 to License R-115 ML20235K0581987-07-31031 July 1987 Annual Rept,Aug 1986-Jul 1987 ML20237G9541987-06-30030 June 1987 Univ of California,Irvine,Nuclear Reactor Facility Annual Rept for Jul 1986 - June 1987 ML20212E2641986-12-31031 December 1986 Annual Rept,Jan-Dec 1986 ML20214Q2701986-09-18018 September 1986 Part 21 Rept Re Defective Interlock in Control Rods During Movement to Full Up Position.Initially Reported on 860915. Corrective Action Will Be Taken by Univ of Illinois & Univ of California at Irvine ML20210Q5431986-07-31031 July 1986 Annual Rept,Low Power Reactor Assembly Reactor ML20215P0011986-06-30030 June 1986 Annual Rept for Jul 1985 - June 1986 ML20154C6401986-02-26026 February 1986 Annual Operating Rept 1985 ML20137F3101985-07-31031 July 1985 Annual Rept,Aug 1984 - Jul 1985 1999-09-20
[Table view] |
Text
-
. a f..
G A Technologies Inc.
PO BOX 85608 SAN DIEGO CAUFORNIA 92138 (619) 455-3000 September 18, 1986 Mr. Richard De Young, Director Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Notification Required by 10CFR21 GA Technologies Inc. TRIGA Reactors
Dear Mr. De Young:
This notification concerns a defect in equipment supplied by GA Technologies Inc. and is provided in compliance with 10CFR21. Verbal notification was made to your Walnut Creek Office on September 15, 1986. The following information is provided in the format of 10 CFR21, 21.21(b)(3).
(i) Richard A. Dean GA Technologies Inc.
P.O. Box 856C8 San Diego, CA 92138 (ii) University of Illinois 216 Nuclear Engineering Laboratory Urbana, Illinois 61801 University of California Irvine Irvine, California (iii) GA. Technologies Inc.
TRIGA Reactor Division P.O. Box 85608 San Diego, CA 92138 (iv) The control systems on these TRIGA reactors have an interlock that is supposed to insure all control rods are in the down position before you can apply air to the fast transient rod in the steady-state mode.
This interlock can be defeated when the shim or safety rods are moved to their full "up" position.
8609240243 860915 6 PDR ADOCK 0500 S
10955 JOHN JAY HOPKINS DR , SAN DIEGO. CALIFORNIA 92121
{
(v) GA obtained this information by telephone from Craig Pohlod of the University of Illinois on September 8, 1986.
(vi) There is one defective interlock in each of the above reactors.
(vii) Any corrective action will be taken by the University of Illinois and the University of California at Irvine.
(viii) GA Technologies will recommend a fix for this problem to each of the two reactor facilities.
If you wish additional information, please call Mr. Robert H. Chesworth at (619) 455-3580.
Very truly yours, i
d=2 =- ,
ichard I Dean Senior Vice President Reactor Programs cc: Mr. Robert Engelkon Regional Administrator U.S. Nuclear Regulatory Commission 1900 North California Blvd.
Walnut Creek, CA 94596