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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
'
UNITED STATES
( f . ATOMIC ENERGY COMMISSION p
WASHINGTON. D.C. 20545
%)
IN JtEPLY ftEFER70s SEP 2 y ggg Docket No. 50-130 l h !
i 3
Northern States Power Company -
l" 414 Nicollet Avenue Minneapolis, Minnesot's 55401 Mr. David F. McElroy
/
['r - 9
- ' Change No. 12 Attention: [
Vice President, Engineering Gentlemen:
This refers to your requests, dated August 16, 1966, and August 18, 1966, for authorization of two changes in the Technical Specifications of ,
Provisional Operating License No. DPR-11 pursuant to the provisions of Section 50.59 of the coassission's regulations. These requests would permit (1) reactor cooling rates in excess of 2000F/hr during the power ,
escalation program up to full power, and (2) use of the reactor noise
( analysis technique in~ 1ieu of the rod oscillator technique to evaluate the stability of the Pathfinder reactor. These changes have been requested ,
to allow certain . tests which could result in rapid cooldown during.the >
startup program and to minimize disturbances to the reactor vessel and j core which occur as a result of the rod oscillator tests. We have designated these requests Proposed Change No. 12.
- We have concluded that Change No.12, as set forth below, does t present significant hazards considerations not described or implicit in the Final Hazards Summaary Report, and that there is reasonable assurance that the health and safety of the public will not be endangered. A copy of our related Safety Evaluation is enclosed.
In view of the foregoing, the Technical Specifications of License No. DPR-11 (Appendix,A) are hereby changed as follows: ,
- 1. Change Section 8.0 to read:
"During testing of the emergency condenser and during the j startup program, and with the superheater drained, the j controlled cooling rate of the reactor may exceed 2000F per hour under the following conditions:
(a) A temperature reduction not to exceed 500F may occur at higher rates during any half-hour period in which !
(
the overall temperature variation does not exceed 1000F, or ,
l 8506120415 850214 PDR FOIA PAYB5-54 PDR i4 i
~
c' .-
(
Northern States Power Company SEP 2 71966 (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 800F during this 20 minute period, and the number of such tests to be performed under this temporary authorisation shall not exceed five."
. 2. Change Section 7.5.3.6 to read:
"7.5.3.6 Stability Evaluation Transfer function measurements shall be made at sero power (less than 5 mw), and subsequently asy be made at higher power levels, to evaluate reactor stability. An oscillator rod, if used, shall be calibrated at several angular positions to assure that peak-to-peak worth does not exceed 10 cents in the configuration used for transfer function measurements. The range of investigation may extend from 0.01 to about 12 cycles per second. Evaluation of reactor stability shall be made at initial power escalation steps (as specified in 7.5.3 above),
before proceeding to the higher. power steps. Such evaluation and extrapolation of stability shall be based on analysis of I. reactor power noise (noise transfer function) or analysis of transfer function measurements made with the oscillator rod mechanism."
Sincerely yours, 9
ORH11NAL SIGNED Sy Peter A. Morris Pater A. Morris, Director .
Division of Reactor Licensing
Enclosure:
l AEC Safety Evaluation i l