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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20058M5511990-08-0303 August 1990 Summarizes ACNW 22nd Meeting on 900730-31 to Review Plans for Decommissioning Plant,Per ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20125D1231985-02-14014 February 1985 Further Response to FOIA Request for Seven Categories of Documents Re Waste & Storage Disposal in South Dakota.Encl Documents Respond to Item 1 of Request.Search & Review of Remaining Documents Subj to Request Continuing ML20090M4981974-03-27027 March 1974 Forwards 1973 Annual Financial Rept,Including Certified Financial Statements.W/O Encl ML20058K8491973-03-21021 March 1973 Forwards 1972 Annual Financial Rept & Certified Financial Statements.W/O Encls ML20090L6181972-07-21021 July 1972 Requests That All Future Correspondence Re Util Licenses Be Directed to Manager of Power Operations ML20127H6101972-06-27027 June 1972 Forwards Endorsements 51 & 52 to Nelia Policy NF-106 for Pathfinder Power Plant,Endorsement 10 to Nelia Policy NF-197 for Prairie Island Power Plant & Endorsement 22 to Nelia Policy NF-174 for Monticello Power Plant ML20058K8521972-03-0808 March 1972 Forwards 1971 Annual Financial Rept & Certified Financial Statements.W/O Encls ML20127G8701972-01-28028 January 1972 Forwards Endorsements 50,9 & 18 to Nelia Policies NF-106, NF-197 & NF-174,respectively ML20125D7871969-05-14014 May 1969 Forwards Amend 4 to License DPR-11,amending License in Entirety ML20125D7711968-12-17017 December 1968 Informs of Change 17 to License DPR-11,cutting & Rerouting Main Steam Line & Feedwater Line,Isolating Feedwater Heater, Replacing Another Feedwater Heater W/Deaerating Heater & Installing New Feedwater Line ML20125D7601968-10-0202 October 1968 Informs of Change 17 to License DPR-11,authorizing Installation of fossil-fueled Boilers to Supply Steam to Turbine & Removal of off-gas Holdup Tanks from Plant & Storage on Present Site ML20125D7361968-08-12012 August 1968 Informs of Change 16 to License DPR-11,authorizing Removal of Fuel from Reactor & Placement in Fuel Storage Pool & Postponement of Next Class a Containment Leak Rate Test Until Just Prior to Fuel Reloading ML20125D7061967-08-0909 August 1967 Informs of Change 15 to License DPR-11,permitting Storage of New Core II Boiler & Superheater Fuel Elements in New Fuel Storage Vault ML20125D6711967-05-26026 May 1967 Informs of Change 13 to License DPR-11,authorizing Deletion of Separate Requirements on Max Boiler Power Fraction & Min Recirculation Flow for Given Total Reactor Power & Incorporating Min Allowable Burnout Ratio Requirement ML20056B6341967-01-31031 January 1967 Requests Current Estimated Schedule of Withdrawals & Returns of SNM Including Enrichment Levels for Pathfinder Reactor Under License DPR-11 to Complete Forecast of SNM Requirements for FY68 & FY69 ML20125D5951966-09-27027 September 1966 Informs of Change 12 to License DPR-11,permitting Reactor Cooling Rates in Excess of 200 F/Hr During Power Escalation Program Up to Full Power & Use of Reactor Noise Analysis Technique in Lieu of Rod Oscillator Technique ML20125D5821966-05-11011 May 1966 Informs of Change 9 to License DPR-11,allowing Increase in Ramp Reactivity Addition Rates Under Certain Operating Conditions,Changing Shutdown Margin Verification Procedures & Permitting Other Minor Mods to Reactor Facility ML20125D5711966-05-10010 May 1966 Informs of Change 11 to License DPR-11,permitting Reactor Cooling Rates in Excess of 200 F/Hr During Initial Reactor Tests When Reactor Superheater Drained ML20125D5631966-04-29029 April 1966 Informs of Change 8 to License DPR-11,allowing Reactor Startup W/Min Startup Channel Neutron Count Rate of 1/3 Counts Per Second Under Certain Conditions ML20125D5591966-04-28028 April 1966 Informs of 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,Due to Problems Achieving Required Sensitivity During Low Power Operation ML20125D5511965-12-20020 December 1965 Informs of Change 7 to License DPR-11,permitting 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 ML20125D5341965-12-0202 December 1965 Forwards Amend 3,Change 6,authorizing Operation at steady- State Power Levels Up to Max of 190 Mwt.Safety Evaluation Encl ML20125D4181965-05-27027 May 1965 Informs of Change 5 to License DPR-11,increasing Max Reactivity Addition Rate During R&D Testing Program ML20125D4041965-03-0404 March 1965 Forwards Amend 2,Change 4,authorizing Receipt,Possession & Use of 32,000 Ci Antimony to Be Used in Four antimony- Beryllium Neutron Sources.Fr Notice & Hazards Analysis Encl ML20125D3641965-03-0404 March 1965 Informs of Change 3 to License DPR-11,allowing Rescheduling of Integrated Leakage Rate Testing of Reactor Bldg ML20125D2411964-07-24024 July 1964 Forwards Amend 1,Change 2 to License DPR-11,authorizing Receipt,Possession & Use of 224 G Pu Encapsulated as Two 1-Ci & Two 6-Ci Pu/Be Neutron Sources ML20125D2081964-03-12012 March 1964 Informs of Change 1 to License DPR-11,changing Range of Stack Gas Monitor from 5 to 4 Decades & Footnoting Third Sentence of Section 4.2.1.2,Page 4-4,to Indicate That Value May Be Exceeded During Pump Startup W/Reactor at 1 Mwt 1990-08-03
[Table view] Category:NRC TO UTILITY
MONTHYEARML20125D7871969-05-14014 May 1969 Forwards Amend 4 to License DPR-11,amending License in Entirety ML20125D7711968-12-17017 December 1968 Informs of Change 17 to License DPR-11,cutting & Rerouting Main Steam Line & Feedwater Line,Isolating Feedwater Heater, Replacing Another Feedwater Heater W/Deaerating Heater & Installing New Feedwater Line ML20125D7601968-10-0202 October 1968 Informs of Change 17 to License DPR-11,authorizing Installation of fossil-fueled Boilers to Supply Steam to Turbine & Removal of off-gas Holdup Tanks from Plant & Storage on Present Site ML20125D7361968-08-12012 August 1968 Informs of Change 16 to License DPR-11,authorizing Removal of Fuel from Reactor & Placement in Fuel Storage Pool & Postponement of Next Class a Containment Leak Rate Test Until Just Prior to Fuel Reloading ML20125D7061967-08-0909 August 1967 Informs of Change 15 to License DPR-11,permitting Storage of New Core II Boiler & Superheater Fuel Elements in New Fuel Storage Vault ML20125D6711967-05-26026 May 1967 Informs of Change 13 to License DPR-11,authorizing Deletion of Separate Requirements on Max Boiler Power Fraction & Min Recirculation Flow for Given Total Reactor Power & Incorporating Min Allowable Burnout Ratio Requirement ML20125D5951966-09-27027 September 1966 Informs of Change 12 to License DPR-11,permitting Reactor Cooling Rates in Excess of 200 F/Hr During Power Escalation Program Up to Full Power & Use of Reactor Noise Analysis Technique in Lieu of Rod Oscillator Technique ML20125D5821966-05-11011 May 1966 Informs of Change 9 to License DPR-11,allowing Increase in Ramp Reactivity Addition Rates Under Certain Operating Conditions,Changing Shutdown Margin Verification Procedures & Permitting Other Minor Mods to Reactor Facility ML20125D5711966-05-10010 May 1966 Informs of Change 11 to License DPR-11,permitting Reactor Cooling Rates in Excess of 200 F/Hr During Initial Reactor Tests When Reactor Superheater Drained ML20125D5631966-04-29029 April 1966 Informs of Change 8 to License DPR-11,allowing Reactor Startup W/Min Startup Channel Neutron Count Rate of 1/3 Counts Per Second Under Certain Conditions ML20125D5591966-04-28028 April 1966 Informs of 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,Due to Problems Achieving Required Sensitivity During Low Power Operation ML20125D5511965-12-20020 December 1965 Informs of Change 7 to License DPR-11,permitting 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 ML20125D5341965-12-0202 December 1965 Forwards Amend 3,Change 6,authorizing Operation at steady- State Power Levels Up to Max of 190 Mwt.Safety Evaluation Encl ML20125D4181965-05-27027 May 1965 Informs of Change 5 to License DPR-11,increasing Max Reactivity Addition Rate During R&D Testing Program ML20125D4041965-03-0404 March 1965 Forwards Amend 2,Change 4,authorizing Receipt,Possession & Use of 32,000 Ci Antimony to Be Used in Four antimony- Beryllium Neutron Sources.Fr Notice & Hazards Analysis Encl ML20125D3641965-03-0404 March 1965 Informs of Change 3 to License DPR-11,allowing Rescheduling of Integrated Leakage Rate Testing of Reactor Bldg ML20125D2411964-07-24024 July 1964 Forwards Amend 1,Change 2 to License DPR-11,authorizing Receipt,Possession & Use of 224 G Pu Encapsulated as Two 1-Ci & Two 6-Ci Pu/Be Neutron Sources ML20125D2081964-03-12012 March 1964 Informs of Change 1 to License DPR-11,changing Range of Stack Gas Monitor from 5 to 4 Decades & Footnoting Third Sentence of Section 4.2.1.2,Page 4-4,to Indicate That Value May Be Exceeded During Pump Startup W/Reactor at 1 Mwt 1969-05-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20125D1231985-02-14014 February 1985 Further Response to FOIA Request for Seven Categories of Documents Re Waste & Storage Disposal in South Dakota.Encl Documents Respond to Item 1 of Request.Search & Review of Remaining Documents Subj to Request Continuing ML20125D7871969-05-14014 May 1969 Forwards Amend 4 to License DPR-11,amending License in Entirety ML20125D7711968-12-17017 December 1968 Informs of Change 17 to License DPR-11,cutting & Rerouting Main Steam Line & Feedwater Line,Isolating Feedwater Heater, Replacing Another Feedwater Heater W/Deaerating Heater & Installing New Feedwater Line ML20125D7601968-10-0202 October 1968 Informs of Change 17 to License DPR-11,authorizing Installation of fossil-fueled Boilers to Supply Steam to Turbine & Removal of off-gas Holdup Tanks from Plant & Storage on Present Site ML20125D7361968-08-12012 August 1968 Informs of Change 16 to License DPR-11,authorizing Removal of Fuel from Reactor & Placement in Fuel Storage Pool & Postponement of Next Class a Containment Leak Rate Test Until Just Prior to Fuel Reloading ML20125D7061967-08-0909 August 1967 Informs of Change 15 to License DPR-11,permitting Storage of New Core II Boiler & Superheater Fuel Elements in New Fuel Storage Vault ML20125D6711967-05-26026 May 1967 Informs of Change 13 to License DPR-11,authorizing Deletion of Separate Requirements on Max Boiler Power Fraction & Min Recirculation Flow for Given Total Reactor Power & Incorporating Min Allowable Burnout Ratio Requirement ML20056B6341967-01-31031 January 1967 Requests Current Estimated Schedule of Withdrawals & Returns of SNM Including Enrichment Levels for Pathfinder Reactor Under License DPR-11 to Complete Forecast of SNM Requirements for FY68 & FY69 ML20125D5951966-09-27027 September 1966 Informs of Change 12 to License DPR-11,permitting Reactor Cooling Rates in Excess of 200 F/Hr During Power Escalation Program Up to Full Power & Use of Reactor Noise Analysis Technique in Lieu of Rod Oscillator Technique ML20125D5821966-05-11011 May 1966 Informs of Change 9 to License DPR-11,allowing Increase in Ramp Reactivity Addition Rates Under Certain Operating Conditions,Changing Shutdown Margin Verification Procedures & Permitting Other Minor Mods to Reactor Facility ML20125D5711966-05-10010 May 1966 Informs of Change 11 to License DPR-11,permitting Reactor Cooling Rates in Excess of 200 F/Hr During Initial Reactor Tests When Reactor Superheater Drained ML20125D5631966-04-29029 April 1966 Informs of Change 8 to License DPR-11,allowing Reactor Startup W/Min Startup Channel Neutron Count Rate of 1/3 Counts Per Second Under Certain Conditions ML20125D5591966-04-28028 April 1966 Informs of 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,Due to Problems Achieving Required Sensitivity During Low Power Operation ML20125D5511965-12-20020 December 1965 Informs of Change 7 to License DPR-11,permitting 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 ML20125D5341965-12-0202 December 1965 Forwards Amend 3,Change 6,authorizing Operation at steady- State Power Levels Up to Max of 190 Mwt.Safety Evaluation Encl ML20125D4181965-05-27027 May 1965 Informs of Change 5 to License DPR-11,increasing Max Reactivity Addition Rate During R&D Testing Program ML20125D4041965-03-0404 March 1965 Forwards Amend 2,Change 4,authorizing Receipt,Possession & Use of 32,000 Ci Antimony to Be Used in Four antimony- Beryllium Neutron Sources.Fr Notice & Hazards Analysis Encl ML20125D3641965-03-0404 March 1965 Informs of Change 3 to License DPR-11,allowing Rescheduling of Integrated Leakage Rate Testing of Reactor Bldg ML20125D2411964-07-24024 July 1964 Forwards Amend 1,Change 2 to License DPR-11,authorizing Receipt,Possession & Use of 224 G Pu Encapsulated as Two 1-Ci & Two 6-Ci Pu/Be Neutron Sources ML20125D2081964-03-12012 March 1964 Informs of Change 1 to License DPR-11,changing Range of Stack Gas Monitor from 5 to 4 Decades & Footnoting Third Sentence of Section 4.2.1.2,Page 4-4,to Indicate That Value May Be Exceeded During Pump Startup W/Reactor at 1 Mwt 1989-06-08
[Table view] |
Text
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$ rL , p,d EN,g 8,
UNITED STATES ATOMIC ENERGY COMMISSION g Ft.E C0FT
( WASHINGTON, D.C. 20545 p /f 1
Docket No. 50-130 -
l pk EAY101E l I Northern States Power Company ' '
414 Micollet Avenue ; ',A Minneapolis, Minnesota 55401 Attention: Mr. David F. McElroy Change No. 11 Vice President, Engineering Gentlemen:
This refers to your request dated May 3,1966, for authorisation of a change in the Technical Specifications of Provisional Opera-ting License No. Upt-11 pursuant to tlee provisions of section 50.59 of the Coenission's regulations. The request would permit Pathfinder reactor cooling rates in excess of 200*F/hr during initial reactor tests when the reactor's superheater is drained.
/ This change has been requested because certain of the initial tests with the reactor will result in cooling rates in excess of the present limit.
We have concluded that Change No. 11, as set forth below, does not present significant hasards considerations not described or implicit *
. in the Final Nasards Summary Report, and' that there is reasonable I assurance that the health and safety of the public will not be I endangered. A copy of our related safety evaluation is enclosed.
In view of the foregoing, the Technical Specifications of License No. Dpt-11 (Appendix A) are hereby changed to add the following paragraph to Section 8.0.
"During testing of the emergency condenser and during l initial power escalation up to 40 percent power, and l_
with the superheater drained, the controlled cooling rate of the reactor may enceed 200'F/hr under either of the following conditions:
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Northern States Power Company -2* lpK 10 %$6 j (a) A temperature reduction not to exceed 50*F may ,
occur at higher rates during any half-hour period in which the overall temperature variation does not exceed 100*F, or (b) During performance testing of the emergency condenser, -
cooling at higher rates may occur during a single 20 minute period occurring within any given hour.
+
The cooling shall not exceed 80'F during this 20 minute period, and the number of such tests to be performed under this temporary authorisation shall not exceed five."
Sincerely yours, .
OriginalSliMd BI R.LDean I
R. L. Doan, Director Division of Reactor Licensing ,
gnclosure:
ABC gefety Evaluation ,
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planned cooldown rates (and hence induced stresses) during testing to values less than those analysed and would be done with the superheater voided. We have r; viewed the applicants analyses and believe that the higher cooldown rates under .
the proposed change are acceptable. I la view of the foregoing, we believe that the Technical Specifications should be '
changed by adding the following paragraph to Section 8.0.
"During testing of the emergency condenser and during initial power 5 escalation up to 40 percent power, and with the superheater drained. [
the controlled cooling rate of the reactor may exceed 200'F/hr under !
either of the following conditions: l (a) A temperature reduction not to exceed 50*F may occur at higher rates during any half-hour period in which the overall tempera-ture variation does not exceed 100'F, or ;
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(b) During performance testing of the emergency condenser, cooling at higher rates may occur during a single 20 minute period occurring within any given hour. The cooling shall not exceed 80'F during this 20 minute period, and the number of such teses to be performed under this temporary authorisation shall not exceed five."
t Conclusion We have concluded that Change No.11 does not present significant hasards consider-ctions not described or implicit in the Final Hasards Suassary Report, and that there is reasonable assurance that the health and safety of the public will not be cadangered.
Odg,r.a! :ip* '
C:5:tS.C','
Roger S. Boyd, Chief Research & Power Reactor Safety Branch Division of Reactor Licensing Dates y;;( , ( ;pg
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