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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] |
Text
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l C; o ' C y I
( l April 15,1969
- Boyce H. Crier, Regional Director DOW CID:ICAL CGIPMPt, DOCKET No. 50-264 No prob 1 cms were noted during the inspection of the subject facility.
The radiation c;:posure experience for calendar year 196S was mini =al.
The licensec stated ho would inform us of any civil distrubance which could affect the reactor.
The fail safe design of the cafety circuit upon loss of electric po.icr was confirmed as satisfactory by tect.
i i
G. Flore111 Senior Reactor Inspector 8508200132 850725 PDR FOIA CONDIT85-483 PDR omc > .. ..C O.:.I.I I... .. . . . . . . . . .. . . . . . . . . . . .. . . . . . . . . . . .
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