|
---|
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
.
- ,,, ( (
ORift Fit.E CO j
UNITED STATES LI ATOMIC ENERGY COMMISSION p
( wash NGTON. D.C. 20545 Docket No. 50-130 j g g yl
~
6 07 ,
Northern States Power Company a
V
~
> 414 Nicollet Avenue M )
Minneapolis , Minnesota 55401
- Attention: Mr. David F. McElroy Change No. 8 Vice President - Engineering \
Gentlemen:
By application dated March 14, 1966, the Northern States Power Company (NSF) requested authorisation of a change in the Technical Specifica-tions of License No. DPR-11 pursuant to the provisions of Section -
50.59 of the commission's regulations. This request would permit startup of the Fathfinder reactor with a minimum startup channel neutron count rate of 1/3 counts per second (eps) under certain condi-tions. We have designated this request, as revised in discussions i with NSP, as Proposed Change No. 8.
We have been informed that this change was requested because the extended startup program associated with the conservative approach to operation of the superheater results in decay of the neutron source such that a minimum count rate of 2 eps may not be achievable during startup at times throughout the life of the plant. The low count rate is a result of the high neutron httenuation due to the water in the refalector between the core and the detector.
Based on our review, we have concluded that Proposed Change No. 8 does not present significant hasards considerations not described or implicit in the hasards summary report and that there is reasonable assurance that the health and safety of the public will not be endangered. A related Safety Evaluation is attached.
Accordingly, the Technical Specifications (Appendix A) are hereby changed as indicated .in Attachment A.
Sincerely yours.
Original SicncTc-
. 8506120403 850214 R. L. Doan F0 85,yA pgg R. L. Doan, Director Division of Reactor Licensing Enclosures As stated above 12.
i i s .
,' e
( l APR 2 91966 AmCM A
[' NORTHERN STATES POWER C(MPANY
, CHANGES TO TECHNICAL SPECIFICATIONS CHANGE NO. 8 - LICENSE NO. DPR-11 (1) Add the following to Section 6.1.8(a): * ;
"This interlock may be bypassed manually with the use of a key switch to:
- I (1) permit control rod latching and unlatching as approved by the Operations ,
comunittee , ;
(2) permit use of low count rate procedure or other supervised tests approved by the Operations Comittee and in accordance with these Technical Specifi-cations."
(2) Add the following to Section 7.6.2(d):
"In the event that the source strength is insufficient to produce a count rate of 2 eps due to neutrons on the out-of-vessel detectors in the startup channels, .
approach to criticality may be accomplished provided the count rate is greater than 1/3 eps due to neutrons and the following conditions are adhered to:
(1) Prior approval of all procedures and methods of analysis for the specific startup shall be obtained from the Operations Committee and the Safety Committee.
(2) A qualified staff engineer shall be present in the control room during startup.
(3) No changes which could significantly affect reactivity shall have been made to any of the core components or to the core configuration since core reactivity was last correlated with rod position. The specific rod withdrawal sequence used in the correlation shall be used for this type of startup.
(4) If changes which affect reactivity have been made to the core or any of its components, or the rod withdrawal sequence is changed, or more than 4 months have elapsed since shutdown, new correlating data shall be obtained. If in-vessel detectors are used, they shall provide a minimum count rate of 2 cys.
(5) The noise level of the detectors and associated electronics shall be less than 1 cys.
(6) No reactivity increment shall exceed 1/3 the extra.polated snount to critical. There shall be at least a 2 minute wait before addition of the next increment is initiated. Plots of multiplication versus rod position shall be made; and enough counts shall be taken after each increment on a -
t scaler to provide 10 percent statistics until the core reactivity is 0.98,
8, . s .
( <
('
" and to provide 3 percent statistics thereaf ter. The count rate shall exceed 2 cps when the core reactivity is 0.995. Af ter the count rate exceeds 2 cps normal startup procedures may be used.
(7) Single coincidence in the startup channel short period scram circuit shall be provided.
(8) Any significant deviation from the correlated data during startup shall require an immediate reactor shutdown until the cause of the discrepancy i is determined."
\