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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20148N4531978-11-0606 November 1978 Amend 37 to Provisional Oper Lic DPR-22,changing Tech Spec to Improve Simmer Margin of Safety/Relief Valves ML20058L0071977-10-14014 October 1977 Amend 31 to License DPR-22,modifying Inservice Insp Requirements for Control Housing Pressure Boundary Welds & Adding Clarifying Statement Re Specified Insp Intervals & Extent of Exam ML20125C4941976-11-0303 November 1976 Corrected Specification 4.7.11.2,as Part of STS for Fire Protection for Plant ML20127K4071975-09-15015 September 1975 Amend 12 to License DPR-22 (Change 20) Changing TS Re Hydraulic Snubbers ML20127K2301975-07-0808 July 1975 Amend 10 to License DPR-22,increasing U-235 Limitations ML20127K3191975-04-10010 April 1975 Amend 9 to License DPR-22 (Change 18) Correcting Typos ML20127J6861975-02-26026 February 1975 Amend 8 to License DPR-22,changing TS Re drywell-to-torus Vacuum Breaker requirements.Marked-up SE Encl W/Stated Changes ML20127J4951975-02-0303 February 1975 Amend 7 to License DPR-22,changing TS Re Reactor Vessel Matl Surveillance Program ML20127J6241974-08-20020 August 1974 Amend 6 to License DPR-22,authorizing Use of 250 Mci Kr-85 ML20127M7811974-06-17017 June 1974 Amend 4 to License DPR-22,increasing Stated Matls, Consolidating Cs-137 & Adding & Deleting Stated Items ML20127M8301974-05-14014 May 1974 Amend 3 to License DPR-22,including Change 14 to TS, Authorizing Partial Loading & Use of 8x8 Fuel ML20127G8021973-02-20020 February 1973 Amend 2 to License DPR-22,increasing U-235 Quantity Contained in Fission Chambers ML20127G7661971-01-19019 January 1971 Amend 1 to License DPR-22,authorizing Operation at Stated Power Levels ML20127G7411970-09-0808 September 1970 License DPR-22 1978-11-06
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C6191999-09-30030 September 1999 Application for Amend to License DPR-22,changing Tech Specs 3/4.17.B, Control Room Emergency Filtration Sys. Change Would Eliminate Unnecessary in-place Testing of HEPA & Activated Charcoal Filters Based on Sys Operating Time ML20203A3221999-01-28028 January 1999 Suppl 3 to 971125 LAR to License DPR-22 Re CST Low Level Hpci/Rcic Suction Transfer.Suppl Replaces TS Page 60d,to Include Approved Amend 103 Changes for Use by NRC in Issuing SER ML20206P1271998-12-31031 December 1998 LAR for License DPR-22,revising TS pressure-temp Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4,deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR for SLCS ML20195C8911998-11-11011 November 1998 Supplemental Application for Amend to License DPR-22, Allowing Removal of One CST from Svc for Maint ML20154L9401998-10-12012 October 1998 Suppl 2 to LAR to License DPR-22,revising Statement on Normal Shift Length & Correcting Typos ML20154L8991998-10-0909 October 1998 Suppl 1 to LAR to License DPR-22,replacing Exhibits B & C of Original Submittal to Reflect Item 2 ML20153F0161998-09-25025 September 1998 Suppl 1 to LAR for Amend to License DPR-22, Replacing Exhibit C Which Contains TS Pages Incorporating Proposed Changes Re Condensate Storage Tank Low Level Hpci/ RCIC Suction Transfer ML20249C5091998-06-19019 June 1998 Rev 2 to LAR Dtd 960726,requesting Changes to Ts,App a Sections 3.6.C & 3/4.17.B & Associated Bases.Proposed Changes Are to Establish TS Requirements That Are Consistent W/Analysis Inputs Used for Evaluation of MSLB Accident ML20216D2891998-03-25025 March 1998 Application for Amend to License DPR-22,providing Suppl 1 to 980313 Amend Request Re Plant Cycle 19 SLMCPR ML20216C9931998-03-19019 March 1998 Suppl Application for Amend to License DPR-22,requesting Consistent Wording Throughout TS & Providing Sound Basis for Frequency of Actions Required Each Shift ML20248L1951998-03-13013 March 1998 Application for Amend to License DPR-22,revising TS Re Safety Limit Minimum Critical Power Ratio ML20202H6861997-12-0404 December 1997 Rev 1 to Application for Amend to License DPR-22,increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt ML20203A9531997-11-25025 November 1997 Application for Amend to License DPR-22,revising Tech Specs for Condensate Storage Tank Low Level Suction Transfer Setpoint for HPCI & RCIC Sys ML20210Q2881997-08-21021 August 1997 Suppl to 961125 Application for Amend to License DPR-22, Revising Page 6 of TS to Add Statement Re MCPR Values Applicable to Cycle 18 Only ML20141B9111997-06-19019 June 1997 Rev 2 to Application for Amend to License DPR-22,addressing Use of Containment Pressure for Assuring Adequate Net Positive Suction Head for ECCS Pumps Under worst-case Conditions ML20138F8661997-04-29029 April 1997 Application for Amend to License DPR-22,providing Suppl to 961125 Amend Request Re Safety Limit Minimum Critical Power Ratio ML20137W2141997-04-11011 April 1997 Rev 1 to Application for Amend to License DPR-22 Re Reactor Coolant Equivalent Radioiodine Concentration & Control Room Habitability ML20136B5361997-03-0404 March 1997 Application for Amend to License DPR-22,updating Design Basis Accident Containment Temp & Pressure Response ML20149M7221997-01-23023 January 1997 Application for Amend to License DPR-22,requesting Authorization for Changes to App A,Clarifying TS 3.5/4.5.C Re Min RHR & RHRSW Pump Requirements for Post Accident & Update of Design Basis Accident Containment & Temp Response ML20132C6361996-11-25025 November 1996 Application for Amend to License DPR-22,revising Section 2.1.A,SLMCPR Value & Deleting Sentence from Section 3.11.C of OLMCPR Re Limit Penalty for Single Recirculation Loop Operation ML20117A4281996-08-15015 August 1996 Application for Amend to License DPR-22,requesting Authorization for Changes to App a of Plant License as Shown on Attachments Labeled Exhibits A,B & C ML20116D8161996-07-26026 July 1996 Application for Amend to License DPR-22,changing TS Sections 3.6.C Re Coolant Chemistry & 3/4.17.B Re CR Emergency Filtration Sys ML20116G8911996-07-26026 July 1996 Application for Amend to License DPR-22,proposing Increase Max Reactor Core Power Level by 6.3% to 1,775 Mwt from Current 1,670 Mwt.Request Also Changes TSs Based on Power Rerate Evaluations ML20100Q3761996-03-0101 March 1996 Application for Amend to License DPR-22,removing Surveillance Requirement Re Periodic Replacement of Containment Purge & Vent Valve Seat Seal ML20095J4271995-12-21021 December 1995 Application for Amend to License DPR-22,revising Main Steam Isolation & App J Leak Rate Test Requirements ML20095E7021995-12-11011 December 1995 Application for Amend to License DPR-22,removing SR 4.7.D.4 from Plant TS & Replaces Seat Seals for Drywell & Suppression Chamber Purge & Vent Valves Every Five Yrs ML20094M1941995-11-14014 November 1995 Suppl to 950815 LAR to License DPR-22,incorporating Requirements of Option B,Section Iii.A for Type a Testing (Primary Containment ILRT) Per Reg Guide 1.163 ML20091K6731995-08-18018 August 1995 Rev 2 to 940608 LAR to License DPR-22,re Section 3.7/4.7, SGTS ML20087J4211995-08-15015 August 1995 LAR to License DPR-22,revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh ML20086D7981995-07-0505 July 1995 LAR to License DPR-22,revising TS to Extend Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation ML20085N0921995-06-22022 June 1995 Application for Amend to License DPR-22,revising TS to Support Implementation of BWR Thermal Hydraulic Stability Solution ML20082N8691995-04-20020 April 1995 Rev 1 to 940608 LAR to License DPR-22,deleting 18 Month Surveillance Frequency Re Automatic Initiation of Test Specified in SR 4.7.B.2.b(3) & Modifying LCO for Spec 3.7.C.4 Re Secondary Containment ML20069J1011994-06-0808 June 1994 LAR to License DPR-22,revising TS Section 3.7/4.7, SGTS Re SR to Operate SGTS Monthly as Well as Revising Performance Requirements for SGTS Filters & Process Stream Electric Heaters ML20065B6581994-03-28028 March 1994 Revised Application for Amend to License DPR-22, Incorporating Improvement in Wording Originally Submitted for TS Section 6.7, Reporting Requirements, Re Identification of Approved Analytical Methods for COLR ML20065B6851994-03-28028 March 1994 Application for Amend to License DPR-22,changing TS Tables 3.2.4 & 4.2.1 Re SGTS Initiation Instrumentation ML20063C9821994-01-26026 January 1994 Application for Amend to License DPR-22,requesting Changes to Ts,To Require Valves Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA ML20062N8691994-01-0404 January 1994 Application for Amend to License DPR-22,revising TS Section 3.11, Reactor Fuel Assemblies by Removing Info Re Average Planar Linear Heat Generation Rate & Min Critical Power Ratio.Proposed Rev to Page 1 of 8 from COLR Encl ML20059E6011994-01-0303 January 1994 Application for Amend to License DPR-22,changing TS Surveillance Requirement 4.6.E.1.a to Require Valves to Be Tested Per Section XI Inservice Testing Requirements of ASME Boiler & Pressure Vessel Code ML20058G4311993-11-30030 November 1993 Application for Amend to License DPR-22,removing Chlorine Detection Requirements & Changing Control Room Ventilation Sys Requirments ML20056E1061993-08-10010 August 1993 LAR to Provide Clarification of Sampling & Analysis Requirements,Update Liquid Effluent Sampling & Analysis Requirements & to Correct Typographical Errors in TS Section for License DPR-22 ML20045G6061993-07-0707 July 1993 Application for Amend to License DPR-22,revising Requirements for Monitoring RCS Leakage,Per NRC Guidance Provided in GL 88-01,Suppl 1 & NUREG-1433, BWR/4 Improved Sts. ML20128M7101993-02-12012 February 1993 Application for Amend to License DPR-22,changing Ts,To Increase Minimum Core Spray Pump Flow to More Conservatively Account for ECCS Bypass Leakage Paths ML1129708521982-07-0202 July 1982 to 760907 Application for Amend to License DPR-22,changing Tech Spec to Allow Plant to Remain at Substantial Power Level W/One Recirculation Pump in Operation & Equalizer Valve Closed ML1129708171981-03-19019 March 1981 Application for Amend to License DPR-22 Revising Tech Specs App a Re Reactor Protector Sys,Submitted as Revision 1 to 810206 Amend Request ML1129708131981-02-0606 February 1981 Application for Amend to Ol.Changes to Tech Specs Requested Per Encl Exhibits A,B,C & D ML20148N4531978-11-0606 November 1978 Amend 37 to Provisional Oper Lic DPR-22,changing Tech Spec to Improve Simmer Margin of Safety/Relief Valves ML20024G4151978-08-16016 August 1978 Application for Amend to License DPR-22,revising Tech Specs by Raising Permissible Setpoint of Eight Safety/Relief Valves Installed at Plant to 1,108 Psig ML20127H2001978-08-10010 August 1978 Application for Amend to License DPR-22 to Authorize Use of Partial Drilled Model for Plant ML20024G3731978-03-21021 March 1978 Application for Amend to License DPR-22,changing Tech Specs Re Partial Drilled Model for Analyzing Retrofit Fuel Design Scheduled for Fall 1978 Refueling Outage ML20024G3931978-03-20020 March 1978 Application for Amend to License DPR-22,clarifying Sections of Interim Radioactive Effluent Tech Specs 1999-09-30
[Table view] |
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DOCKE* NC. 50-263 PROVISIONAL OPERATING LICENSE Amendment No. 1 License No. DPR-22 Provisional Operating License'No. DPR-22 is hereby superseded being-amended in its entirety as follows:
"1. This license applies to the Monticello Nuclear Generating Plant, Unit No. 1,' a aingle cycle, forced circulation, boiling water nuclear reactor and' electric' generating eculpment (the facility). The tacility is located in Wright County on tne Northern States' site in Wright and Sherburne Counties, Minnesota, and is described in the " Final Safety Analysis Report," as supplemented and amended (Amendment Nos.'9 through 28).
, ~2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Northern States:
~~
A. Pursuant. to Section 104b ' of the Atomic Energy Act
,. of 1954, as amended (the Act), and 10 CFR Part 50,
" Licensing of Production and Utilization Facilities,"
to possess, use, and operate the' facility-as a j utilization facility at the designated location at the Monticello-Nuclear Generating Plant; B. Pursuant to the Act and 10 CFR -Part 70, Special..
Nuclear Material, to receiv'e, possess, and use at t
a'ny one time up to-2300 kilograms uranium 235 as reactor fuel assemblies, one gram of uranium 235 as fission chambers and 16 grams of plutonium as contained in i ~ Pu-Be~ neutron sources in. connection with operation of the facility; i
C. - : Pursuant to the Act and'10 CFR Part 30, "Rulne of General Applicability to Licensing of Byproduct
___ - Material,'~ to receive, possess, and use in connection with operation of the facility; ten sources of-l Antimony 124, not to exceed 1,250 curies per source; i 'j .
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- one source of Americium 241, not to exceed 7 curies; !
four sources of Cobalt 60, two not to exceed 350 microcuries per source, one not to exceed 500 millicuries and one not to exceed 12.5 millicuries;
' Strontium 90, not to exceed 1.2 microcuries per
' source; Cesium 137 not to exceed 8 microcuries per source (all as sealed sources); Americium 241, Cesium 137 and Strontium 90 each not to exceed 1 millicurie per nuclide, and Cobalt 60 not to exceed 27 microcuries (all without restriction as to chemical or physical fom); and 2.702 milli-curies of Cesium 137, and 0.5405 millicurie of Cobalt 60 (in solution form); and Pursuant to the Act and 10 CFR Parts 30 and 70, to D.
possess, but not separate, such byproduct and spe-cial nuclear material as may be produced by the operation of the facility.
- 3. This license shall be deemed to contain and is subject to the
.j conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41
- of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all a applicable provisions of the Act and to the rules, regulations, j and orders of the Commission, now or hereafter in effect; and l
i is subject to the additional conditions specified below:
? A. Maximum Power Level
.I Northern States is authorized to opirate the facility at power l levels not in excess of 1670 megawatts (thermal) except that
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Northern States shall :.ot operate the f acility at power levels
'~ in excess of five (5) megawatts thermal with the reactor vessel 1 4 head in placa until acceptable performance of the f eed-i water pumps has been verified in writing by the Commission, d
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B. Technical Soecifications i
The Technical Specifications ' contained in Appendix A 7 i attached hereto are hereby incorporated in this license.
'7 Northern States shall operate the facility at power levels not in excess of those authorized under condition 3.A.
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- I abcVe in accordance with the Technical Specifications applicable to such operation and may make changes therein only when authorized by the Commission in accordance with the provisions of Section 50.59 of 10 CFR Part 50.
C. Reports Northern States shall make certain reports in accordance with the requirements of the Technical Specifications.
D. Records Northern States shall keep f acility operating records in accordance with the requirements of the Technical Specifications.
- 4. Northern States shall observe such standards and requirements for the protection of the environment as are validly imposed pursuant to authority established under Federal and State law and as determined by the Commission to be applicable to the f acility covered by this provisional operating license.
This condition does not apply to (a) radiological effects since such effects are decle with in other provisions of this operating license, or (b) matters of water quality covered by Section 21(b) of the Federal Water Pollution Control Act, as amended.
- 5. Northern States Power shall comply with all applicable require-ments of Section 21(b) of the Federal Water Pollution Control Act.
- 6. This license is effective as of the date of issuance and shall expire eighteen (18) months f rom said date, unless extended for good cause shown, or upon the earlier issuance of a superseding operating license."
FOR THE ATOMIC ENERGY COMMISSION ertstnet *fped by Few L noms Peter A. Morris, Director Division of Reactor Licensing
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Attachment:
AppendixA-TechnicalSpecificationsh[Jdj Date of Issuance: lAg yg gg) y _ . . _ . . _ ._ _ _
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