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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20125D7181967-08-0909 August 1967
Safety Evaluation Supporting Change 15 to License DPR-11, Permitting Storage of New Core II Boiler & Superheater Fuel Elements in New Fuel Storage Vault
ML20125D6911967-05-26026 May 1967
Safety Evaluation Supporting Change 13 to License DPR-11, Authorizing Deletion of Separate Requirements on Max Boiler Power Fraction & Min Recirculation Flow for Given Total Reactor Power
ML20125D6181966-09-27027 September 1966
Safety Evaluation Supporting Change 12 to License DPR-11, Permitting Reactor Cooling Rates in Excess of 200 F/Hr During Power Escalation Program Up to Full Power
ML20125D5871966-05-11011 May 1966
Safety Evaluation Supporting Change 9 to License DPR-11, Allowing Increase in Ramp Reactivity Addition Rates Under Certain Operating Conditions & Changing Shutdown Margin Verification Procedures
ML20125D5671966-04-29029 April 1966
Safety Evaluation Supporting Channel 8 to License DPR-11, Allowing Reactor Startup W/Min Startup Channel Neutron Count Rate of 1/3 Counts Per Second Under Certain Conditions
ML20125D5611966-04-28028 April 1966
Safety Evaluation Supporting Change 10 to License DPR-11, Changing Min Sensitivity of Intermediate Range Channels from 10(-9) amps/75 Kw to 5 X 10(-11) amps/200 Kw
ML20125D5541965-12-20020 December 1965
Safety Evaluation Supporting Change 7 to License DPR-11, Authorizing Continued Operation of Reactor at Power Levels Up to 1 Mwt W/Containment Leak Rate Not to Exceed 0.2% Per Day at Test Pressure of 78 Psig
ML20125D5451965-09-29029 September 1965
Safety Evaluation Supporting Amend 3,Change 6 to License DPR-11,authorizing Operation at steady-state Power Levels Up to Max of 190 Mwt
ML20125D5261965-05-27027 May 1965
Safety Evaluation Supporting Change 5 to License DPR-11, Authorizing Increase of Max Reactivity Addition Rate During R&D Testing Program
ML20125D3851965-03-0404 March 1965
Hazard Analysis Supporting Change 3 to License DPR-11, Authorizing Rescheduling of Integrated Leakage Rate Testing of Reactor Bldg
ML20125D3521965-03-0404 March 1965
Hazards Analysis Supporting Amend 2,Change 4 to License DPR-11,authorizing Receipt,Possession & Use of 32,000 Ci Sb-124 as antimony-beryllium Neutron Sources
ML20125D3101964-07-24024 July 1964
Hazards Analysis Supporting Amend 1,Change 2 to License DPR-11,authorizing Receipt,Possession & Use of One Addl 6-Ci Pu/Be Neutron Source for Use in Reactor During Initial Fuel Loading & Low Pressure Testing
ML20125D2241964-03-12012 March 1964
Hazards Analysis Supporting Change 1 to License DPR-11, Authorizing Change to Range of Stack Gas Monitor from 5 Decades to 4 Decades
1967-08-09
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20125D7181967-08-0909 August 1967
Safety Evaluation Supporting Change 15 to License DPR-11, Permitting Storage of New Core II Boiler & Superheater Fuel Elements in New Fuel Storage Vault
ML20125D6911967-05-26026 May 1967
Safety Evaluation Supporting Change 13 to License DPR-11, Authorizing Deletion of Separate Requirements on Max Boiler Power Fraction & Min Recirculation Flow for Given Total Reactor Power
ML20125D6181966-09-27027 September 1966
Safety Evaluation Supporting Change 12 to License DPR-11, Permitting Reactor Cooling Rates in Excess of 200 F/Hr During Power Escalation Program Up to Full Power
ML20125D5871966-05-11011 May 1966
Safety Evaluation Supporting Change 9 to License DPR-11, Allowing Increase in Ramp Reactivity Addition Rates Under Certain Operating Conditions & Changing Shutdown Margin Verification Procedures
ML20125D5671966-04-29029 April 1966
Safety Evaluation Supporting Channel 8 to License DPR-11, Allowing Reactor Startup W/Min Startup Channel Neutron Count Rate of 1/3 Counts Per Second Under Certain Conditions
ML20125D5611966-04-28028 April 1966
Safety Evaluation Supporting Change 10 to License DPR-11, Changing Min Sensitivity of Intermediate Range Channels from 10(-9) amps/75 Kw to 5 X 10(-11) amps/200 Kw
ML20125D5541965-12-20020 December 1965
Safety Evaluation Supporting Change 7 to License DPR-11, Authorizing Continued Operation of Reactor at Power Levels Up to 1 Mwt W/Containment Leak Rate Not to Exceed 0.2% Per Day at Test Pressure of 78 Psig
ML20125D5451965-09-29029 September 1965
Safety Evaluation Supporting Amend 3,Change 6 to License DPR-11,authorizing Operation at steady-state Power Levels Up to Max of 190 Mwt
ML20125D5261965-05-27027 May 1965
Safety Evaluation Supporting Change 5 to License DPR-11, Authorizing Increase of Max Reactivity Addition Rate During R&D Testing Program
ML20125D3851965-03-0404 March 1965
Hazard Analysis Supporting Change 3 to License DPR-11, Authorizing Rescheduling of Integrated Leakage Rate Testing of Reactor Bldg
ML20125D3521965-03-0404 March 1965
Hazards Analysis Supporting Amend 2,Change 4 to License DPR-11,authorizing Receipt,Possession & Use of 32,000 Ci Sb-124 as antimony-beryllium Neutron Sources
ML20125D3101964-07-24024 July 1964
Hazards Analysis Supporting Amend 1,Change 2 to License DPR-11,authorizing Receipt,Possession & Use of One Addl 6-Ci Pu/Be Neutron Source for Use in Reactor During Initial Fuel Loading & Low Pressure Testing
ML20125D2241964-03-12012 March 1964
Hazards Analysis Supporting Change 1 to License DPR-11, Authorizing Change to Range of Stack Gas Monitor from 5 Decades to 4 Decades
1967-08-09
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.2% ,. UCENSE AUTHORITY FILE COPt' HAZARDS ' ANALYSIS BY THE RESEARCH AND POWER REACTOR SAFETY BRANCH
' DIVISION OF REACTOR LICENSING IN THE MATTER Or a
NORTHERN STATES POWER '
COM
'PATHrINDER ATOMIC POWER PLANT DOCKET NO. 50-130
' INCREASE IN NUMBER Or NEUTRON SOURCES CHANGE NO. 4 c/ A
- C WE b Introduction By application dated February 4,1965, the Northern States Power Company (NSP) has requested an amendment to the Pathfinder Atomic Power Plant, Pacility Li- ,
conse 1)PR-11 to authorize receipt, possession, and use of up to four antimony- ;
beryllium neutron sources for use in the Mactor. The Company has aquested that the total number of curies of antimony to be used in neutron sources be increased from 10,000 curies to 32,000 curies. In addition, Northern States Power has aquested that Sections 5.5.2 and 7.5.1.5 of the Technical Specifica-tions be changed to allow the use of up to four antimony-beryllium neutron ,
sources as required. These changes have been requested so that more sources ;
could be used to enhance the ability of the neutron detectors to monitor the core.
Evaluation The three additional antimony-beryllium neutron sources will be placed in the superheater region of the core along with the criginal one. Four lengths of antimony rods clad with stainless steel are senwed together to make a 6 foot long antimony rod. This assembly is placed in a beryllium cylinder to fortn one neutron source. The additional antimony rods are identical in diameter and in stairless steel clad thickness to the source originally evaluated. The operating environment and the procedures for handling and storage of the addi-tional sources will be the same as those permitted with the original source.
Therefore, no hazards considerations other than those previously evaluated are associated with these neutron sources. .
Conclusions -
Based upon our nyiew of the information submitted, we have concluded that the licensee can operate the Pathfinder reactor with up to four antimony-beryllium sources, as proposed, without undue hazard to the health and safety of the public.
Accordingly, we believe that paragraph 2.C.(1) of Provisional Operating License DPR-11 may be amended to read as follows:
0506120327 850214 PDR FOIA PAY 85-54 PDR
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"32,000 curies of antimony-124 as antimony-beryllium neutron sources."
In addition, we believe that Section 5.5.2 and the first paragraph of Section 7.5.1.5 of the Technical Specifications to License DPR-11 may be changed as indicated hereunder:
"5.5.2 Operating Source ~
t Type Antimony-beryllium Quantity Up to 4
. Location Superhgater Minimum Initial Strength 5 x 10 neutrons /sec, each A. Physical Description The beryllium annulus shall be part of inner insulating tubes of the superheater. The antimony rods shall be located in the center of the beryllium cylinder. The dimension of the assembly shall be as follows:
Total Length of Insulating Tubes Inches 194 11/32 I
Insulating Tube 0.D. , Inches one '
l g Length of Beryllium Annulus, Inches 73 3/8" "7.5.1.5 Insertion o:! Reactor Source and Refueling Test Preparatory to further testing the antimony-beryllitsn zwactor '
source (s) sna11 be loaded in the superheater and the plutonium-beryllium Jources removed. The reactor vessel shall be completely filled in<sluding the superheater steam passages during this operation. Referwnce core criticality shall be repeated to '
correlat's the regular instrumentation indication to known condi-tions." !
0 r.*:,!z1 c!:;ncd by, i
, Lugar S.13oyd ,
Roger S. Boyd, Chief Research & Power Reactor Safety Branch Division of Reactor Licensing Date: CAR 41%5 i