Letter Sequence Other |
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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
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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
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NORTHERN STATES POWER COMPANY 1
usussanous.wissueQTA 55401 January 16, 1981 Director of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License No. DPR-22 50-306 DPR-60 NUREG-0737 Item II.K.3.17, Report on Outages of Emergency Core-Cooling Systems NUREG-0737, " Clarification of TMI Action Plan Requirements," issued by the NRC Staff on October 31, 1980 contains the requirement (Item II.K.3.17) to submit a report detailing outage dates and length of outages for all emergency core-cooling (ECC) systems for the last five years of operation.
The purpose of the report is to provide the Staf f with data on unreliability due to test and maintenance outages which will be used to determine if cumulative outage requirements are needed in the Technical Specifications.
Attached is the tabulation of outage information for the Prairie Island Nuclear Generating Plant. The data represents all outages of ECC systems from January 1,1976 through December 31, 1980 except during refueling.
The Prairie Island ECC systems include the high-head safety injection system, the low head safety injection system, and the accumulators.
We believe the outage times reported on the attached table do not constitute excessive unavailability. There is no case where accumulation of short permissible outages resulted in unacceptable overall system availability.
No Technical Specification changes are warranted.
Please contact us if you have any questions concerning the information we have provided.
L 0 Mayer, PE Manager of Nuclear Support Services cc: J G Keppler G Charnoff NRC Resident Inspector I
At tachment i
I 8101200 N
e d
a Director of NRR, USNRC January 16, 1981 At tachment Prairie Island Units 1 and 2 Report of Outage of ECC Systems From January 1,1976 to December 31, 1980 Outage Re ference Date Duration Cause and System (Work Reg) 12-19-80 L hr 44 min Modify W-2 Control Switch (RH)
D6980 12-15-80 3 hrs.58 min Modify W-2 control Switch (SI)
D6946 12-12-80 4 hrs 59 min Modify W-2-Control Switch (RH)
D6981 11-5-80 19 hrs 5 min Preventative Maintenance, RHR Pump (RH)
Note 1 11-3-80 19 hrs 28 min Preventative Maintenance, RHR Pump (RH)
Note 1 9-13-80 1 hr 30 min Maintenance on Motor Valve (RH)
D5423 9-10-80 15 hrs (EST)
Preventative Maintenance, RHR Pump (RH)
Note 1 9-11-80 15 hrs (EST)
Preventative Maintenance, RHR Pump (RH)
Note 1 8-5-80 8 hrs 38 min Gasket Leak Repair (RH)
D3366 8-4-80 8 hrs Gasket Leak Repair (RH)
D1697 7-29-80 21 hrs 5 min Gasket Leak Repair (RH)
D3055 3-31-80 13 hrs 45 min Preventative Maintenance, RHR Pump (RH)
P3124-1 1-8-80 15 hrs (EST)
Preventative Maintenance, RRR Pump (RH)
Note 1 12-10-79 7 hrs 30 min Radiograph Inspection, RHR Pump (RH)
C6655 10-1-79 11 hrs 20 min Gasket Leak (RH)
C4853 9-26-79 11 hrs 55 m n Preventative Maintenance, RHR Pump (RH)
P3124-1 i
9-25-79 15 hrs 5 mir.
Preventative Maintenance, RHR Pump (RH)
P3124-1 4-18-79 18 hrs Gasket Leak (RH)
A7836 1-31-79 13 hr 56 min Preventative Maintenance, RHR Pump (RH)
P3124-1 1-30-79 6 hrs 40 min Preventative Maintenance, RHR Pump (RH)
P3124-1 8-29-78 7 hrs 15 min Preventative Maintenance, RHR Pump (RH)
P3124-1 8-28-78 14 hrs 50 min Preventative Maintenance, RHR Pump (RH)
P3124-1 2-23-77 7 hrs 46 min Gasket Leakage (RH)
A0871 1-29-77 12 hrs 35 min Gasket Leakage (RH)
A0463 7-30-79 3 hrs 22 min Modification (SI)
C4186 & A4187 11-28-77 22 min Testing to Determine Leakage (SI)
A7186 11-1-77 3 hrs Testing to Determine Leakage (SI)
A7135 10-20-77 20 hrs Testing to Determine Leakage (SI)
A6880 6-18'-77 4 hrs 57 min Replace Leaking Safety Valve (SI)
A4223 6-8-77 3 hrs 30 min Testing for Possible Pump Damage (SI)
A3790 6-8-77 8 hrs Testing for Possible Pump Damage (SI)
A3564 10-6-76 7 hrs 46 min 21 RH Loop Leakage Check (RH) 3128 9-16-76 7 hrs 19 min 22 RH Loop Leakage Check (RH) 3099 Notes:
1.
Record of Outage date and duration based upon PM schedule 2.
This tabulation does not include work done on ECCS components during refueling outages 3.
RH - RHR (Low Mead Safety Injection)
SI - Safety Injection (High Head) and accumulators I
i i
l
