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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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'. i DCfNSE AUTHORITY MLE COPY 4AZARDS ANALYSIS BY THE RESEARCH
. NCH AND POWER REACTO DIVISION OF REACTOR LICENSING IN THE MATTER OF NORTHERN STATES POWER COMPANY
_ PROPOSED CHANGE NO. 3 , [
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- =ast:d authorization of a change in the 2 '1 pursuant to the provisions of 10 CTR 50.59 omp ns to Technical SP) !
Specifica ense j r_ pat:d Proposed Change No. 3, would allow NSP to re-schedulThis request, which we ha -
e the integrated
.usge
- 3 ad 10rate test of the the Technical reactor building which is required each 18 months as Specifications.
.m=::er 18,1963 The last test was performed on I JI.
NSP proposes to re-schedule the leakage er date rate testing to a la
.= $3 condition that such tests will be done after completion of the low se t: ting program and prior to continuation of reactor operation.
t:x: ion
~:*May : currently 1965 conducting low power tests which should ee be compl t d b y the x2::y la preparation for continued reactor operation.After this test phase During this interim
==., th] xeactor will not be operated.
We believe that re-scheduling the 2 a and acceptable from a safety viewpoint =.;:st:d leak rate testa to a t
==:21 'Spaci f1 cations
.2v cf the above, we believe that the first paragraph .. of 3of 7 the 2(f) e.:.:.a1
- m Specifications of License No. DPR-11 may be changed to zwad as
.7.J(f) be perfortned at least once every 18 months except t leakage rate test required to be performed by18, May 1965 ,
plant modifications for full power operation but befor reactor operations after the modifications."
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- asis of the foregoing, we have concluded that Proposed .3 Change No
- pre:ent significant hazards considerations not described c or impil it I
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in the hazards susunary mport and that them is masonable assurance that the health and safety of the public will not be endangend. '
.t Originalsigned br. 6 Rogers.Boyd Roger S. Boyd, Chief Research & Power Reactor Safety Branch g Division of Reactor Licensing ,
Date E 4E '
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