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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
.
. " * , gg I UNITED STATES plLE COPY T
ATOMIC ENERGY COMMISSIOkCENSE b -
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( WASHINoTON, D.C. 30848 o '
Al Docket No. 50-130 Y
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EM 1 1 136G )
Northern States Power Company \j / ' r
/
414 Nicollet Avenue l Minnesota, Minneapolis 55401 [
Attention: Mr. David F. McElroy
}N '
Change No. 9 d
Vice President, Engineering Gentleasas By application dated April 4, 1966, the Northern States Power Company (NSF) requested authorisation of a number of changes to the Technical Specifications of License No. DPR-11 pursuant to the provisions of Section 50.59 of the commission's regulations. This request would allow (1) increases in ramp reactivity addition rates under certain operating conditions, (2) a change in the shutdown margia verification
( procedures, and (3) other minor modifications to the Fathfinder reactor facility. We have designated this request Proposed Change No. 9. These changes were requested as a result of operational experience and evalua-tion of Phase I and 11 test data.
Based on our review, we have concluded that Proposed Change No. 9 does not present significant hasards considerations not described or implicit in the hasards susunsry report and that there is reasonable assurance that the health and safety of the public will not be endangered. Our related safety evaluation is attached.
Accordingly, the Technical Specifications (Appendix A) are hereby .
changed as indicated in Attachment A.
4 Sincerely yours,
! Original Signed By l,
R.LDean
- R. L. Doan, Director
! Division of Reactor Licensing
Enclosures:
- 1. AEC Safety Evaluation
- 2. Attachment A l
gig 0350214 '
! PAY 85-54 PDR ,
lb I
- EY I 1 Igg ATTACHMENT A i
NORTHERN STATES POWER COMPANY CHANGES TO TECHNICAL SPEC {FICATIONS CHANGE NO. 9 - LICENSE NO. DFR-11
- 1. Section 4.2.1.2
~
Delete the last sentences from the first and third paragraphs which read:
"(This shall correspond to a maximum reactivity addition rate of less than 5 cents /sec) ." and
" Reactivity addition by recirculation flow control shall not be continued for more than 10 seconds in any one 20 second interval."
2 section 5.6.1(b)
Change the maximum steam temperature in the table from "750'F" to "775'F."
- 3. Section 5.8.2 Delete the first sentence of the second paragraph and substitute the followings
(
"The core shutdown margin shall be verified by a demonstration that the reactor is subcritical with the superheater in its most reactive condition, the most valuable reactivity-worth rod fully withdrawn, and other rods partially withdrawn. Immediately, subsequent to the withdrawal of the most valuable reactivity-worth rod, it shall be demonstrated that the rods partially withdrawn contribute 0.003 k gg or more to the effective aniciplication."
4 Section 5.3.2 <
Add the following to the last sentence of the second paragraph:
". . . and with the range switch of channels 5 and 6 set a positions !
such that scram level shall not exceed 600 Ew for the duration of l the demonstration."
- 5. Section 5.13 Cheese the second paragraph to read:
"The maximum reactivity insertion rate when the k gg of the core is greater than 0.997 shall be 12 cents /sec except during the core shutdown margin verification of section 5.8.2, when it shall be approximately 34 cents /sec."
7
- 5. saetian 6.1.1 Delete the words "and operation of the eastgency condenser." from the second paragraph. ,
(
- 7. Section 6.1.7 Change the wording in the first table to resd:
" Condition Setooint (1) 14ss of all three Breaker Operation (msy be bypassed recirculation pumps through use of a key switch during rod latching and unistching and during verification of core shutdown margin)" i
- 8. Seetion 6.1.9.6 ,
Replace Table 2, " Nuclear system Annunciator Points" with an updated Table 2 (attached) dated 3/1/66.
9 6
4 f
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- . '.+ . .
C.
3/1/66 s
TABLE 2 r
NUCLEAR SYSTEM ANSUNCIATOR POINTS Superheater outlet temperature - High Reactor feedwater temperature - Low Superheater outlet pressure - High Reactor ' pressure - High i Turbine 1021 overspeed - Tripped ' '
Turbine trip-stop valves - Tripped Reactor Control - Runback Reactor Control - Scram Nuclear instrumentation reactor period - Short Mbin steam isolation valve by-pass flow - Low khin steam isolation valve - Tripped - Closed Nhin steam isolation valve - Loss of Power Superheater outlet temperature - Low
~ ,
Superheater outlet pressure - Low Main steam safety valves - Open
- Reactor recirculating pump motors bearing temperature - High Reactor recirculating pump motors - Overload Reactor recirculating pump motor temperatures - High Reactor recirculating discharge valves - Loss of Power 7' Reactor water level - High Reactor water level - Low Reactor feedwater temperature - High
. Reactor recirculating water temperature - Low Reactor feedwater temperature' control set point - Low Reactor building shield pool seals - Leaking Reactor building air lock doors - Open Reactor building pressure - High Reactor vent temperature - High Radiation - High, Isolation - Trip Reactor control rod drive motors - Overload Reactor' control rod drive motors - Loss of Power Reactor control rod drive motors ; Reverse Phase Reactor control rod drive seals leakage flow - High Main steam isolation valve interlock switch - Out-of-Position Nuclear instrumentation power range flux channels 7 & 8 - High Differential Nuclear instrumentation - Trouble Reactor pressure control pressure error - High - Low
- Nuclear instrumentation short period - Runback Trip Nuclear instrumentation channels, 5, 6, 7, & 8 - 2 of 4 Runback trip Reactor control loss of feedwater - Runback Trip Reactor control ejector exhaust high activity - Isolate - Scram Reactor control main steam dump valva - Low oil pressure Nuclear instrumentation channels 5, 6, 7, & 8 - Scram logic trip l
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