Letter Sequence Other |
|---|
|
Results
Other: ML113201659, ML19211A683, ML19250A799, ML19260C541, ML19270H670, ML19305D654, ML19309F147, ML19338D111, ML19339A494, ML19340C533, ML19345A918, ML19345E813, ML19347C731, ML19350C136, ML19350C628, ML20002D280, ML20004E248, ML20008F373, ML20008F375, ML20009A583, ML20009C950, ML20009E854, ML20009E864, ML20037D431, ML20037D434, ML20037D461
|
MONTHYEARML19250A7991979-10-17017 October 1979 Commits to Implement Requirements of NUREG-0578 for Followup Actions to TMI-2 Accident.Forwards Description of Actions Already Taken,Planned Actions & Expected Implementation Dates Project stage: Other ML19211A6831979-12-14014 December 1979 Notifies That Util Will Be in Compliance by 800131 W/Lessons Learned Task Force Recommendations Re Relief & Safety Valves Direct Position Indication & Inadequate Core Cooling Detection Instrumentation Project stage: Other ML19270H6701979-12-28028 December 1979 Submits Info Re Auxiliary Feedwater Sys for TMI Lessons Learned Task Force Recommendations 2.1.7a & 2.1.7b.Forwards Electrical,Flow & Logic Diagrams Available in Central Files Project stage: Other ML19260C5411979-12-31031 December 1979 Forwards Rept on Implementation of TMI Lessons Learned Task Force Recommendations Re Emergency Power Supply,Relief & Safety Valve Testing & Direct Position Indication of Relief & Safety Valves Project stage: Other ML19257A5341979-12-31031 December 1979 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Changing Auxiliary Feedwater Sys Tech Specs Project stage: Request ML19305B3431980-03-13013 March 1980 Supplements Re Lessons Learned Task Force Implementation.Includes Info Re Emergency Power Supply, Direct Position Indication of Relief & Safety Valves & Instrumentation for Inadequate Core Cooling Project stage: Supplement ML19305D6541980-04-11011 April 1980 Forwards Addl Info Re Implementation of short-term Lessons Learned Task Force Recommendations Project stage: Other ML19309F1471980-04-25025 April 1980 Requests NRC Review of Proposed Implementation of short-term Lessons Learned Task Force Recommendations Re Item 2.1.6.b, Plant Shielding Review, Item 2.1.9, Reactor Vessel Head Vent, & Item 2.2.26, Onsite Technical Support Ctr Project stage: Other ML19338D1111980-09-12012 September 1980 Notifies of Delay Until 801114 for Submittal of Proposed Tech Specs for Lessons Learned Category a Requirements, Requested by NRC Project stage: Other ML19339A4941980-10-29029 October 1980 Responds to NRC Re Interim Criteria for Shift Staffing.Requirements Outlined Have Been Implemented Re Administrative Procedures,Movement of Key Individuals About the Plant & Overtime Work Project stage: Other ML19340C5331980-11-13013 November 1980 Describes Status of Environ Qualification Deficiency Re Namco EA-180 Limit Switch Installation Discovered During IE Bulletin 79-01B Investigations.Matl Necessary to Upgrade Switch Installation Has Been Ordered Project stage: Other ML19345A9181980-11-20020 November 1980 Requests Relief from TMI Action Plan Implementation Schedule of NUREG-0737,Item II.F.2,re Final Instrumentation for Detection of Inadequate Core Cooling.Affidavit Encl Project stage: Other ML19340E0211980-12-15015 December 1980 Notification of 801112 Meeting W/Util Re Draft Emergency Plan.Trip Rept Encl Project stage: Request ML19340D3171980-12-18018 December 1980 Responds to NRC 801024 Request for Addl Auxiliary Feedwater Sys Info.Specific Responses,Related Tables & Drawings & Correction to Util Encl Project stage: Request ML19340D3311980-12-19019 December 1980 Forwards Application for Amend of Licenses DPR-42 & DPR-60, Changing Tech Specs Re TMI Lessons Learned Category a Procedural & Equipment Requirements.Fee Encl Project stage: Request ML19340D3341980-12-19019 December 1980 Proposed Changes to Tech Specs Sections 3,4 & 6 Re TMI Lessons Learned Category a Procedural & Equipment Requirements Project stage: Request ML19340D3331980-12-19019 December 1980 Application for Amend of Licenses DPR-42 & DPR-60,changing Tech Specs Re TMI Lessons Learned Category a Procedural & Equipment Requirements Project stage: Request ML19347C7311980-12-30030 December 1980 Forwards Commitments to Hardware,Procedural & Organizational Implementation Requirements of NUREG-0737.Implementation Dependent on Equipment Availability & Firm Regulatory Position Project stage: Other ML20002D2801981-01-16016 January 1981 Forwards Rept of ECCS outages,1976-80,per NUREG-0737,Item II.K.3.17.ECCS Outage Frequency Does Not Constitute Excessive Unavailability.No Tech Spec Changes Are Warranted Project stage: Other ML1132016591981-01-30030 January 1981 Forwards Info Re post-TMI Requirements.Revised Emergency Plan & Meteorological Sys Description Will Be Mailed by Wk of 810201.Shift Technical Advisor,Containment Pressure Setpoint,Eccs Sys Outages & Control Room Info Encl Project stage: Other ML19345E8131981-01-30030 January 1981 Forwards Info Re Shift Technical Advisor & Control Room Habitability for NRC Review of Implementation of TMI Action Plan Requirements Per NUREG-0737 Project stage: Other ML20037D4611981-02-28028 February 1981 Reactor Vessel Head Vent Operation, Revision 0 Project stage: Other ML20037D4341981-02-28028 February 1981 Background Info for Reactor Vessel Head Vent Operation, Revision 0 Project stage: Other ML20008F3731981-03-0202 March 1981 Amends 46 & 40 to Licenses DPR-42 & DPR-60,respectively, Incorporating New Requirements for Instruments & Equipment & Shift Manning,Resulting from NRC Assessment of TMI-2 Accident Project stage: Other ML20008F3751981-03-0202 March 1981 Notice of Issuance & Availability of Amends 46 & 40 to Licenses DPR-42 & DPR-60,respectively Project stage: Other ML19350C1361981-03-27027 March 1981 Informs That Implementation of NUREG-0737,post-TMI Item I.C.5 Requirement,Will Be Delayed Until 810701 Due to Mgt Procedures Being Written in Series Rather than in Parallel. Procedures Build on Requirements Per Higher Level Directive Project stage: Other ML19350C6281981-03-31031 March 1981 Advises of Delay in Implementation of NUREG-0737 post-TMI Requirements Due to Unavailability of Variance Computer Hardware.Projected Inservice Date Is Now 810501 Project stage: Other ML20009E8641981-05-31031 May 1981 Revised Main Control Room Habitability Study Project stage: Other ML20004E2481981-06-0808 June 1981 Forwards Addl Info Re post-TMI Requirements for Emergency Operations Facility Per 810408 Commitment.Includes Descriptions of Emergency Response Facility Implementation & Technical Support Ctr Project stage: Other ML20009A5831981-07-0606 July 1981 Informs That Util Will Provide NRC W/Description of C-E Heated Junction Thermocouple Sys by 810901 Upon Demonstration of Feasibility.Submittal Will Include Info Re NUREG-0737,Item II.F.2 Project stage: Other ML20037D4311981-07-0606 July 1981 Forwards Background Info for Reactor Vessel Head Vent Operation, Revision 0 & Reactor Vessel Head Vent Operation, Revision 0 in Response to NUREG-0737,Items II.B.1 & II.D.1 Project stage: Other ML20009D0121981-07-0808 July 1981 Discusses Review of 790430,0518 & 0622 Responses to IE Bulletin 79-06A & 79-06A,Revision 1.Encl Safety Evaluation Completes TMI Item II.K.1 & Bulletins.Responses to IE Bulletin 79-06C Will Be Reviewed as Part of Item II.K.3.5 Project stage: Approval ML20009D0151981-07-0808 July 1981 Safety Evaluation Re Applicant Responses to IE Bulletins 79-06A & 79-06A,Revision 1.Actions Taken by Licensee Demonstrate Understanding of Concerns & Implications of TMI-2 Accident Project stage: Approval ML20009C9501981-07-10010 July 1981 Order Confirming Licensee Commitments Re post-TMI Related Requirements of NUREG-0737.Requests That Applicant Satisfy Specific Requirements of Nureg,Described in Attachment, within 30 Days Project stage: Other ML20009E8541981-07-20020 July 1981 Forwards Revised Main Control Room Habitability Study, Per NUREG-0737,Item III.D.3.4.Revision Corrects Errors in Radiological Analysis Assumptions.Mods Recommended in Toxic Chemical Study Will Be Scheduled for Completion by 830101 Project stage: Other ML20090D3981984-06-20020 June 1984 Toxic Chemical Study Project stage: Other ML20090D3651984-07-0909 July 1984 Forwards Suppl 1 to 840410 Application for Amend to Licenses DPR-42 & DPR-60,changing Tech Specs to Delete Requirement for Ammonia,Hydrocloric Acid & Formaldehyde Gas Detection Sys in Main Control Room,Per NUREG-0737,Item III.D.3.4 Project stage: Request ML20090D3761984-07-0909 July 1984 Suppl 1 to 840410 Application for Amend to Licenses DPR-42 & DPR-60,changing Tech Specs to Delete Requirement for Ammonia,Hydrocloric Acid & Formaldehyde Gas Detection Sys in Main Control Room,Per NUREG-0737,Item III.D.3.4 Project stage: Request 1980-09-12
[Table View] |
Text
_ _ _
O
590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-282 AND 50-306 NORTHERN STATES POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory " omission (the Comission) has issued Amendment No. 46 to f acility Operating License No. OPR-42, and Amendment No. 40 to f acility Operating License No. DPR-60 issued to Northern States Power Company (the licensee), which revised Tech-nical Specifications for operation of Prairie Island Nuclear Generating Plant, Unit Nos. I and 2 (the facilities) located in Goodhue County, Minnesota.
The amendments are effective as of the date of issuance.
The amendments revise the Technical Specifications to incorporate additional requirements as a result of reviews and modifications accoglished to satisfy the Category "A", TMI-2 Lessons Learned recomendations.
The application for the amendments complies with the standards j
and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has i
made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments was j
not required since the' amendments do not involve a significant hazards -
consideration.
l 830818019
I i
7590-01 1
1 l i The Comaission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or l
negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dat'ed December 19,1980,(2) Amendment Nos. 46 and 40 to License Nos. DPR-42 and DPR-60, and (3) the Comission's related letter dated March 2, 1981 All of these items are available for public inspection at the Connission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the Environmental Conservation Library, 300 Nicollet Mall, Minneapolis, Minnesota 55401.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory i
- Commission, Washington, D.C.
20555, Attention:
Director, Division of Licensing.
Dated at Bethesda, Maryland, this 2nd day of March,1981.
FOR THE NUCLEAR REGULATORY COMMISSION k
hu R.'A. Clark, Chief N
Operating Reactors Branch #3 Division of Licensing a-p
.,,s
,-ec<
+
r-,
..,4.-
y w,-,
...-**g
+---r,.,,
s,w.~..
.,.g.
9...cv.,-
p--.
---w,_.
w.
e-,,
e.--i