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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
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ATOMIC ENERGY COMMISSION w ..wiue rou. o.c. .....
AMRfyy gr g August 9, 1967 i
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%s Docket No. 50-130 Qc.) vi ,g,g
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> Q Nwhn States Power Cenpany 414 Nicollet Avenue Minneapolis, Minnesota 55401 Attentient Mr. David F. McElmy Change No. 15 Vice President, Engineering License No. DPR-ll Gentlement
'Ihis afers to your aquest dated July 28, 1967, for authorization to revise Technical Specifications of Provisional Operating License No.
DPR-ll pursuant to the prwvisions of Section 50.59 of the Comunission's I mgulations. This change would pemit the storage of new Coru II boiler g
and superheater fuel elements in the new fuel storuge vault. Additional Technical Specification changes to pemit rwfueling of the Pathfinder i reactor with the Coru II boiler and superheater elements will be m- l quired at a later date. '
We have ocncluded that Change No. 15, as set forth in our Safety Evalua-tion, does not prweent significant hazards considerutions not described or implicit in the Final Safety Analysis Report, and that thers is rwasonable assurance that the health and safety of the public will not be endangered. A copy of our related Safety Evaluation is are1*.
In view of the forwgoing, the Technical Specifications of License No.
DPR-ll (Appendix A) are heruby tuvised as set forth in Attachnent A.
Sincerwly yours, l
J Pe .
M is,parw w.
h Division of Reactor Licensing Enclosurws: 3
- 1. Safety Evaluation
- 2. Attachment A
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0506120445 850214 PDR F01A PAYO5-54 PDR W
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ATDONDir A i
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N0mDW STATES POWDt CCHPANY PA'!NTINDDL A'!tHIC POWDt Pl#fr OWEE NO.15 '!O TECHNICAL SPECIFICATIONS LICENSE NO. DPR-11 i DOCKET NO. 50-130 In Section 4.9.10:
- 1. M the first sentence of this section
"'!he fuel handled or stond as described in this section shall be limited to the fuel as described in these specifications." '
l Substitute the following themfort
"'!he fuel handled or stomd as described in this section shall be limited to fuel as described in these specifications or as described in ACNP 67525." .
- 2. Delete the thirti paragraph of subsection (b):
"'!he meninsa calculated flooded X,ff for the superheater stomse shall be less than 0.70."
Substitute the following therefort t
"The maxinsn calculated flooded K,ff for the superheater stcruge ;
shall be less than 0.80." l
- 3. Delete the fifth parugmph of subsection (b):
"The new fuel stomge vault shall contain a maxina of 156 boiler i elements and 550 superheater elements. There shall be apprumimately i 173 lbs. of UO2 in each boiler element and apprtacimately 0.33 lbs.
of UO2 in each superheater element." ,
l Substitute the following therefor:
"'!he new fuel storuge vault shall contain a maxin n of 156 boiler '
elements and 550 superheater elements. '!here shall be apprtmimately 173 lbs. of UO2in each Coru I boiler element and appetncimately 0.33 lbs. of UO2 in each Core I superheater element. There shall be approximately 169 lbs. of U in each Com II boiler element and l appetstimately 5.50 lbs. of 2 in each Coru II superheater element." '
7 l
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