ML20244E022: Difference between revisions
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{{Adams | |||
| number = ML20244E022 | |||
| issue date = 09/26/1960 | |||
| title = Advises That W/Listed Changes Sodium Reactor Experiment Facility May Be Operated as Proposed W/O Undue Risk to Health & Safety of Public | |||
| author name = Silverman L | |||
| author affiliation = NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) | |||
| addressee name = Mccone J | |||
| addressee affiliation = US ATOMIC ENERGY COMMISSION (AEC) | |||
| docket = | |||
| license number = | |||
| contact person = | |||
| case reference number = FOIA-89-194 | |||
| document report number = NUDOCS 8906200113 | |||
| package number = ML20244E012 | |||
| document type = CORRESPONDENCE-LETTERS, INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | |||
| page count = 2 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:.I l | |||
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON 15 D.C. | |||
September a$, 1960 t | |||
i 1 | |||
l Honorable John A. McCone cha*.rman U. 8. Atossic Energy Ccamission Wa= W gton 25, D. C. | |||
Subjects 80DEM REACIOR EKPERDBfT (SRE) i | |||
==Dear Mr. McCone:== | |||
q The Sodium Reactor Erperiment has been reviewed by the Advisory Committee on Reactor Safeguards previously and aported in its lettere dated April 14, 1955 and September 9,1955 Because of . | |||
a required rehabilitation of the facility, it was again con-sidered at the Committee's twenty-eighth meeting on September , | |||
22-24, 1960. Se ACRS was furnished with the reports listed l below. In addition to ABC staff, representatives of Atomics l International, the Chicago Operations Office, and the Canosa Park Ama Office participated in presentation of data. | |||
he investigation of the loss of fuel elements brought forth recoussendations for a couplete rehabilitation of the facility, a review of the safety aspects, and couplete delineation of required changes in the philosophy of organizational procedures and operational controls. Several major changes have been made; such as, changed fuel element design, substitution of alternate coolants for tetralin, 1 4 v e pump seals, increased mmber of in-core and coolant exit thermocouple, improved l | |||
reactor instnmentation and revised operational organization l | |||
and control responsibility. | |||
8906200113 890612 PDR FOIA DOWIEB9-194 PDR , ! | |||
l 1573 | |||
h , | |||
2 g | |||
Honorable John A. McCone Septerdber 26,1960 j' With the changer made and the revised op3 rational controls in effect, the Comittee believes the SRE may be operated as pro- Y posed without undue risk to the health and safety of the public. | |||
Sincerely yours, | |||
/s/LeslieSilverman Leslie Silverman ; | |||
1 | |||
==References:== | |||
SRS Standard Operating Pu>cedures (NAA-SR-MDO-5326) ata June 27,1960 Organization of the Sodium Reactor Ecperiment Group (NAA-SR-MDO-5360) dtd June.34 1960 Design Notifications to the SRE during FY 1960 (NAA-8R-53M) dtd June 20,.1960 HazaNis Gumary for the Moritan-Uranium Fuel in the Sodium Reactor Deperiment (NAA-SR-3175-Revised) dtd July 1, 1959 Hazards Summary for the horium-Uranium Fuel in V e. Sodium ' | |||
aeactor acperiment (NAA-SR-3175-Rev.- supplement) dta April 8, 1960 SREFuelElementDamage(NAA-SR-M88)dtaNov. 30, 1959 cc: A. R. Luedecke, GM W. F. Finan, AGMRS ' | |||
H. L. Price, DIAR l | |||
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Latest revision as of 03:32, 4 August 2021
ML20244E022 | |
Person / Time | |
---|---|
Issue date: | 09/26/1960 |
From: | Silverman L Advisory Committee on Reactor Safeguards |
To: | Mccone J US ATOMIC ENERGY COMMISSION (AEC) |
Shared Package | |
ML20244E012 | List: |
References | |
FOIA-89-194 NUDOCS 8906200113 | |
Download: ML20244E022 (2) | |
Text
.I l
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON 15 D.C.
September a$, 1960 t
i 1
l Honorable John A. McCone cha*.rman U. 8. Atossic Energy Ccamission Wa= W gton 25, D. C.
Subjects 80DEM REACIOR EKPERDBfT (SRE) i
Dear Mr. McCone:
q The Sodium Reactor Erperiment has been reviewed by the Advisory Committee on Reactor Safeguards previously and aported in its lettere dated April 14, 1955 and September 9,1955 Because of .
a required rehabilitation of the facility, it was again con-sidered at the Committee's twenty-eighth meeting on September ,
22-24, 1960. Se ACRS was furnished with the reports listed l below. In addition to ABC staff, representatives of Atomics l International, the Chicago Operations Office, and the Canosa Park Ama Office participated in presentation of data.
he investigation of the loss of fuel elements brought forth recoussendations for a couplete rehabilitation of the facility, a review of the safety aspects, and couplete delineation of required changes in the philosophy of organizational procedures and operational controls. Several major changes have been made; such as, changed fuel element design, substitution of alternate coolants for tetralin, 1 4 v e pump seals, increased mmber of in-core and coolant exit thermocouple, improved l
reactor instnmentation and revised operational organization l
and control responsibility.
8906200113 890612 PDR FOIA DOWIEB9-194 PDR , !
l 1573
h ,
2 g
Honorable John A. McCone Septerdber 26,1960 j' With the changer made and the revised op3 rational controls in effect, the Comittee believes the SRE may be operated as pro- Y posed without undue risk to the health and safety of the public.
Sincerely yours,
/s/LeslieSilverman Leslie Silverman ;
1
References:
SRS Standard Operating Pu>cedures (NAA-SR-MDO-5326) ata June 27,1960 Organization of the Sodium Reactor Ecperiment Group (NAA-SR-MDO-5360) dtd June.34 1960 Design Notifications to the SRE during FY 1960 (NAA-8R-53M) dtd June 20,.1960 HazaNis Gumary for the Moritan-Uranium Fuel in the Sodium Reactor Deperiment (NAA-SR-3175-Revised) dtd July 1, 1959 Hazards Summary for the horium-Uranium Fuel in V e. Sodium '
aeactor acperiment (NAA-SR-3175-Rev.- supplement) dta April 8, 1960 SREFuelElementDamage(NAA-SR-M88)dtaNov. 30, 1959 cc: A. R. Luedecke, GM W. F. Finan, AGMRS '
H. L. Price, DIAR l
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