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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 PsigML20125D554 |
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Site: |
05000130 |
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Issue date: |
12/20/1965 |
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From: |
Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
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To: |
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Shared Package |
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ML20125A538 |
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References |
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FOIA-85-54 NUDOCS 8506120399 |
Download: ML20125D554 (2) |
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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
[Table view] |
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.( SAFETY EVALUATION BY THE RESEARCH AND POWER REACTOR SAFETY BRANCH DIVISION OF REACTOR LICENSING l
IN THE MATTER OF ,
NORTHERN STATES POWER COMPANY PATHFINDER ATOMIC POWER PLANT j / uv
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DOCKET No. 50-130 cfM C0ffrAINMENT LEAK RATE SPECIFICATION FCR POWERS BELOW l MW(t)
CHANGE NO. 7 l I
i Introduction and Evaluation i
By application dated December 13, 1965, the Northern States Power Company (NSP) requested a change in Technical Specifications to increase the presently specified containment leak rate limit. The increased limit would be the same cs that previously specified in the license for operation below 1 MW(t). We have been informed that this change was requested because measured leakage '
( was higher than specified. Until repairs can be affected plant testing will be restricted to power levels below 1 MW(t).
In Change No. 6, .the Technical Specifications were revised to permiti full power (190 MWt) operation of the Pathfinder reactor. _ One of the revised items was the permissible containment leak rate. This limit was changed from 0.21 per day for 1 MW(t) operation to 0.11% per day for . full power operation at the same test pressure. In Proposed Change No. 7, Northern States Power Company has requested an additional provision that will permit resumption of low power reactor testing at the previously specified containment leakage rate limit of 0.2% per day. This change does not involve significant hazards considerations different than previously considered since this mode of operation is the same cs previously approved.
Conclusions Based upon our review of the information submitted, we have concluded that the operation of the Pathfinder reactor in accordance with the proposed change
'does not present significant hazards considerations not described or implicit in the hazards summary report, and there is reasonable assurance that the health and safety of the public will not be endangered.
I 8506120399 B50214 PDR FOIA PAY 85-54 PDR I
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- Accordingly, we believe that a new sentence should be added to !
Section 3.6.2 as follows: ;
"During initial operation of the reactor at power levels up to 1 MW(t), the containment leakage rate shall not '
exceed 0.2% of the contained air within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 3
78 psig." -
Origind signed br.
!!c:tr S. Boyd Roger S. Boyd, Chief !
Research & Power Reactor Safety Branch Division of Reactor Licensing Date:
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