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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20137G4671981-05-14014 May 1981 Forwards Dow Chemical Co 810324 & 0420 Ltrs Re Problem w/O-ring Seals of AMS-3 Continuous Air Monitor,For Review to Determine If Info Should Be Passed on to Other Users of Equipment.W/O Encls ML20137G3901978-06-15015 June 1978 Agrees That Insp Findings at Facility Raised Significant Generic Issues Concerning NRC Public Health & Safety & Security Requirements at Nonpower Reactors.Generic Anomalies Should Be Resolved as Soon as Possible ML20137H0981978-05-19019 May 1978 Advises That Imposition of Civil Penalty on Dow Chemical Co for Failure to Properly Protect Facility on 780110, Inappropriate.Noncompliance Can Be Classified No Higher than Infraction Based Upon Encl NRR Position.W/O Encl ML20137H1031978-05-15015 May 1978 Comments on Security Breakdown at Facility in Response to N Haller 780407 Memo.Security Plan Developed & Approved Based on Interim Guidance Provided by NRC in 1974 as Means of Implementing 10CFR50.34 & 73-40 Requirements ML20137G5861978-03-29029 March 1978 Forwards Description of 780110 Breach of Physical Security Sys as Possible AO for Review.Significantly Weakened Protection Against Sabotage Cited ML20137G9761978-03-0303 March 1978 Discusses Licensee Response to 780113 Immediate Action Ltr, Per NRC 780207 Enforcement Conference W/Licensee at Dow Chemical Research Reactor Facility.Tour of Facility Confirmed Appropriate Corrective Action Taken by Licensee IA-85-261, Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility1978-03-0303 March 1978 Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility ML20137H3981978-03-0303 March 1978 Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility ML20205E5361978-03-0202 March 1978 Discusses Noncompliance from Security Insp.Issuance of Civil Penalty Recommended.W/O 780113 Immediate Action Ltr & Licensee Reply.Draft Insp Rept & Notice of Violation Encl. Portions Deleted (Ref 10CFR2.790) ML20205E2451976-02-0909 February 1976 Forwards Enforcement Ltr & Initial Physical Security Insp Rept 50-264/76-01 on 760115-16.Portions Deleted ML20137G5241971-06-22022 June 1971 Advises That Licensee Conducts Carefully Administered & Limited Sample Activation Program That Presents Very Low Order of Risk.Radiation Exposure Experience in 1969 & 1970 Minimal ML20137G4871971-06-22022 June 1971 Forwards Insp Rept 50-264/71-01 on 710602.No Noncompliance Noted.Reactor Operated for Production of Short half-life Activation Samples ML20136H0111969-04-21021 April 1969 Forwards Co Insp Rept 50-264/69-01.No Noncompliance Noted. Licensee Confirmed by Test That Reactor Safety Sys fail-safe Design Upon Loss of Electrical Power Results in Reactor Scram ML20136H0261969-04-15015 April 1969 Discusses Insp of Facility.No Problems Noted.Radiation Exposure Experience for CY68 minimal.Fail-safe Design of Safety Circuit Upon Loss of Electric Power Confirmed as Satisfactory by Test ML20137G8961968-10-17017 October 1968 Advises That Dow Reactor Has Operated Essentially problem-free Since Last Insp.Mgt Attitude Cooperative ML20137G8751968-10-17017 October 1968 Forwards Insp Rept 50-264/68-01 on 680926.No Items of Noncompliance Noted ML20137G9161967-11-15015 November 1967 Forwards Insp Rept 50-264/67-03 on 671024-25.No Safety Items or Items of Noncompliance Noted.Inspector Identified Util Failure to Repair Malfunctioning Control Rod Actuating Switch as Poor Judgement ML20137G9211967-11-15015 November 1967 Advises That Licensee Did Not Challenge Position That Repair of Stuck Control Rod Switch Should Have Been Attempted Before Resuming Reactor Operation.General Attitude of Licensee Cooperative ML20137G4321967-07-19019 July 1967 Forwards Insp Rept 50-264/67-02 on 670630 & G Fiorelli 670719 Memo.No Items of Noncompliance or Safety Significance Noted.Issuance of OL Recommended on 670630.Criticality Reached on 670706 w/72 Elements Loaded ML20137G4601967-07-19019 July 1967 Forwards Insp Rept 50-264/67-02 on 670630.All Required Prestartup Items Satisfactorily Resolved.License Signed on 670703,per Inspector Recommendation ML20137G3831967-06-26026 June 1967 Forwards Insp Rept 50-264/67-01 on 670620 & 21 & Jg Condelos 670626 Memo.Upon Completion of Outstanding Items,Facility Can Be Operated W/O Undue Risk to Public Health & Safety. Fuel Loading Scheduled for 670629 ML20137G4021967-06-26026 June 1967 Forwards Insp Rept 50-264/67-01 on 670620 & 21.No Items of Safety Significance Noted.Final Insp Will Be on 670628 & 29 1981-05-14
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20137G4671981-05-14014 May 1981 Forwards Dow Chemical Co 810324 & 0420 Ltrs Re Problem w/O-ring Seals of AMS-3 Continuous Air Monitor,For Review to Determine If Info Should Be Passed on to Other Users of Equipment.W/O Encls ML20137G3901978-06-15015 June 1978 Agrees That Insp Findings at Facility Raised Significant Generic Issues Concerning NRC Public Health & Safety & Security Requirements at Nonpower Reactors.Generic Anomalies Should Be Resolved as Soon as Possible ML20137H0981978-05-19019 May 1978 Advises That Imposition of Civil Penalty on Dow Chemical Co for Failure to Properly Protect Facility on 780110, Inappropriate.Noncompliance Can Be Classified No Higher than Infraction Based Upon Encl NRR Position.W/O Encl ML20137H1031978-05-15015 May 1978 Comments on Security Breakdown at Facility in Response to N Haller 780407 Memo.Security Plan Developed & Approved Based on Interim Guidance Provided by NRC in 1974 as Means of Implementing 10CFR50.34 & 73-40 Requirements ML20137G5861978-03-29029 March 1978 Forwards Description of 780110 Breach of Physical Security Sys as Possible AO for Review.Significantly Weakened Protection Against Sabotage Cited ML20137G9761978-03-0303 March 1978 Discusses Licensee Response to 780113 Immediate Action Ltr, Per NRC 780207 Enforcement Conference W/Licensee at Dow Chemical Research Reactor Facility.Tour of Facility Confirmed Appropriate Corrective Action Taken by Licensee IA-85-261, Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility1978-03-0303 March 1978 Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility ML20137H3981978-03-0303 March 1978 Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility ML20205E5361978-03-0202 March 1978 Discusses Noncompliance from Security Insp.Issuance of Civil Penalty Recommended.W/O 780113 Immediate Action Ltr & Licensee Reply.Draft Insp Rept & Notice of Violation Encl. Portions Deleted (Ref 10CFR2.790) ML20205E2451976-02-0909 February 1976 Forwards Enforcement Ltr & Initial Physical Security Insp Rept 50-264/76-01 on 760115-16.Portions Deleted ML20137G5241971-06-22022 June 1971 Advises That Licensee Conducts Carefully Administered & Limited Sample Activation Program That Presents Very Low Order of Risk.Radiation Exposure Experience in 1969 & 1970 Minimal ML20137G4871971-06-22022 June 1971 Forwards Insp Rept 50-264/71-01 on 710602.No Noncompliance Noted.Reactor Operated for Production of Short half-life Activation Samples ML20136H0111969-04-21021 April 1969 Forwards Co Insp Rept 50-264/69-01.No Noncompliance Noted. Licensee Confirmed by Test That Reactor Safety Sys fail-safe Design Upon Loss of Electrical Power Results in Reactor Scram ML20136H0261969-04-15015 April 1969 Discusses Insp of Facility.No Problems Noted.Radiation Exposure Experience for CY68 minimal.Fail-safe Design of Safety Circuit Upon Loss of Electric Power Confirmed as Satisfactory by Test ML20137G8961968-10-17017 October 1968 Advises That Dow Reactor Has Operated Essentially problem-free Since Last Insp.Mgt Attitude Cooperative ML20137G8751968-10-17017 October 1968 Forwards Insp Rept 50-264/68-01 on 680926.No Items of Noncompliance Noted ML20137G9161967-11-15015 November 1967 Forwards Insp Rept 50-264/67-03 on 671024-25.No Safety Items or Items of Noncompliance Noted.Inspector Identified Util Failure to Repair Malfunctioning Control Rod Actuating Switch as Poor Judgement ML20137G9211967-11-15015 November 1967 Advises That Licensee Did Not Challenge Position That Repair of Stuck Control Rod Switch Should Have Been Attempted Before Resuming Reactor Operation.General Attitude of Licensee Cooperative ML20137G4321967-07-19019 July 1967 Forwards Insp Rept 50-264/67-02 on 670630 & G Fiorelli 670719 Memo.No Items of Noncompliance or Safety Significance Noted.Issuance of OL Recommended on 670630.Criticality Reached on 670706 w/72 Elements Loaded ML20137G4601967-07-19019 July 1967 Forwards Insp Rept 50-264/67-02 on 670630.All Required Prestartup Items Satisfactorily Resolved.License Signed on 670703,per Inspector Recommendation ML20137G3831967-06-26026 June 1967 Forwards Insp Rept 50-264/67-01 on 670620 & 21 & Jg Condelos 670626 Memo.Upon Completion of Outstanding Items,Facility Can Be Operated W/O Undue Risk to Public Health & Safety. Fuel Loading Scheduled for 670629 ML20137G4021967-06-26026 June 1967 Forwards Insp Rept 50-264/67-01 on 670620 & 21.No Items of Safety Significance Noted.Final Insp Will Be on 670628 & 29 1981-05-14
[Table view] |
See also: IR 05000264/1976001
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NUCLEAR REGULATORY COMMISSION
RtGION 161
799 ROOSEVELT RO AD
CLEN E LLYN BLLINoli 60937
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February 9, 1976
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G. W. Roy, Chief, Field Coordination and Enforcement Branch
Office of Inspection and Enforcement, Headquarters
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DOW CHEMICAL COMPANY
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DOCKET NO. 50-264
LICENSE NO. R-108
Attached are a copy of the enforcement letter and the inspection
report covering the initial physical security inspection conducted ;
January 15-16, 1976 at Dow Chemical's TRIGA Research Reactor facility. l
The security plan submitted by Dow Chemical Company for this facility
was reviewed by the Office of Nuclear Reactor Regulation, and on
September 3, 1974, the licensee was notified that the plan was accept-
able.
,
Section 3.3.7, paraBraph A.4, of the Dow Security Plan states that
inspection disclosed that the reactor room and main corridors '
of the first floor are equipped with an ' l
The laboratory building's main entrance
J.However, the basement, which contains the reactor water
The
purification and cooling system,
water purification and cooling system is identified in the Amendments
to the Security Plan, paragraph 1.c. as[~
.
'Ihe basement is accessible thgough
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Althoughthe{ does not ,
contain
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the door itself is located ' , !
f forcible entr'y through the
was made, an intrud,J er couldI
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S-F3-76-222 THIS DOCUMr.NT
Copy d of IS NOT TO BE
gO1 2 851004 c=L P8Ecs REPRODUCED
WITil0UT SPECIFIC
KOHN85-259 PDR
APPROVAL OF IE:1II
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-10 CFR 2l/90 mF0H.fi20N ,,
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,,_ G. W. Roy, Chief ,
-2- February 9, 1976
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Because of the wording in the Security Plan, we did not cite the
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licenseeforhaving{ but we feel the Ian
should be' modified to include [
We request that this matter be brought to the attention of the Office'
Of Nuclear Reactor Regulation.
1
J. A. Hind, Chie
Safeguards Branch
Enclosure:
1. Enforcement Itr
dtd February 10, 1976
2. Rpt No'. 050-264/76-01
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