Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20196L2501999-05-13013 May 1999
Rev 0 to PINGP Unit 1 COLR Cycle 20
ML20198J6441998-12-17017 December 1998
Rev 0 to PINGP COLR Unit 2-Cycle 19
ML20202A9411997-09-25025 September 1997
Rev 0 to PINGP Colr,Unit 1,Cycle 19
ML20135F6611997-03-0303 March 1997
Rev 0 to COLR Unit 2 - Cycle 18
ML20115G8501996-07-12012 July 1996
Non-proprietary Prairie Island Unit 1 Cycle 18 Thimble Deletion Study
ML20100G7161996-02-0707 February 1996
Rev 0 to PINGP COLR Unit 1 - Cycle 18
ML20085G5321995-06-13013 June 1995
Rev 0 to Prairie Island Nuclear Generating Plant COLR Unit 2-Cycle 17
ML20078H3321994-11-10010 November 1994
Rev 1 to Prairie Nuclear Nuclear Generating Plant,Core Operating Limits Rept,Unit 2-Cycle 16
ML20073D5861994-09-15015 September 1994
Startup Physics Testing Rept Unit 1 Cycle 17
ML20072L3041994-08-22022 August 1994
Rev 6 to Pages 184,188,189 & 261 of Prairie Island (PI) Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20058K5151993-12-0808 December 1993
Rev 0 to Praire Island Nuclear Generating Plant Core Operating Limits Rept Unit 2 - Cycle 16
ML20126G5961992-12-30030 December 1992
Rev 0 to Prairie Island Nuclear Generating Plant COLR Unit 1 - Cycle 16
ML20094K0151992-03-10010 March 1992
Rev 0 to Core Operating Limits Rept,Unit 2 - Cycle 15
ML20081L5791991-06-25025 June 1991
Praire Island Nuclear Generating Plant Core Operating Limits Rept Unit 1 - Cycle 15 Rev 0
ML20067E5591991-02-11011 February 1991
Rev 3 to Core Operating Limits Rept Unit 1 - Cycle 14
ML20067E5601991-02-11011 February 1991
Rev 2 to Core Operating Limits Rept Unit 2 - Cycle 14
ML20028G9921990-09-27027 September 1990
Rev 2 to Core Operating Limits Rept Unit 1 Cycle 14
ML20028G9931990-09-27027 September 1990
Rev 1 to Core Operating Limits Rept Unit 2 Cycle 14
ML20058L1081990-07-27027 July 1990
Core Operating Limits Rept,Unit 1,Cycle 14,Rev 1
ML20012D9151990-03-22022 March 1990
Rev 0 to Core Operating Limits Rept Unit 1 - Cycle 14
ML20012D9171990-03-22022 March 1990
Rev 0 to Core Operating Limits Rept Unit 2 - Cycle 13
ML20206U7781986-06-13013 June 1986
Rev 4 to Reload Safety Evaluation Methods for Application to Prairie Island Units
ML20116K1971985-03-31031 March 1985
Nonproprietary Rev 3 to NSPNAD-8102, Reload Safety Evaluation Methods for Application to Prairie Island Units
ML20063E1551982-06-29029 June 1982
LOCA ECCS Limiting Break & Exposure Sensitivity Analysis for ENC XN-1 & XN-2 Reloads at Prairie Island Unit 1 w/5% Steam Generator Tubes Plugged Using ENC Wrem Iia PWR Model
1999-05-13
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pingp.With
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML20217A1691999-09-22022 September 1999
Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20216E7151999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with
ML20211J2851999-08-26026 August 1999
Safety Evaluation Supporting Amends 146 & 137 to Licenses DPR-42 & DPR-60,respectively
ML20211D3981999-08-24024 August 1999
Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively
ML20211C2531999-08-0404 August 1999
Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526
ML20211B5971999-07-31031 July 1999
Cycle 20 Voltage-Based Repair Criteria 90-Day Rept
ML20210Q4891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with
05000282/LER-1999-007-01, :on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted1999-07-23023 July 1999
- on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted
ML20209J1131999-07-15015 July 1999
Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions
ML20209F9811999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20196F4081999-06-23023 June 1999
Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20195D6151999-06-0202 June 1999
Safety Evaluation Supporting Amends 145 & 136 to Licenses DPR-42 & DPR-60,respectively
ML20195G5181999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included
ML20207B5931999-05-26026 May 1999
SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs
ML20196L2501999-05-13013 May 1999
Rev 0 to PINGP Unit 1 COLR Cycle 20
05000282/LER-1999-005-01, :on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event1999-05-0808 May 1999
- on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event
ML20206L6191999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with
ML20205N1081999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with
ML20205B3351999-03-17017 March 1999
Safety Evaluation Supporting Amends 143 & 134 to Licenses DPR-42 & DPR-60,respectively
ML20205Q5101999-03-15015 March 1999
Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229
05000306/LER-1999-001-01, :on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With1999-03-0808 March 1999
- on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With
ML20207J6951999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant
ML20202J7711999-02-0404 February 1999
Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept
ML20202G3761999-01-31031 January 1999
Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units
ML20207L2811999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2
ML20202J1731999-01-22022 January 1999
Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety
05000306/LER-1998-006-01, :on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted1999-01-18018 January 1999
- on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted
ML20206P7861998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With
ML20205H0561998-12-31031 December 1998
Northern States Power Co 1998 Annual Rept. with
ML20198J6441998-12-17017 December 1998
Rev 0 to PINGP COLR Unit 2-Cycle 19
05000306/LER-1998-005-02, :on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With1998-12-0909 December 1998
- on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With
ML20198L2211998-12-0707 December 1998
Safety Evaluation Supporting Amends 141 & 132 to Licenses DPR-42 & DPR-60,respectively
ML20206N2731998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
05000282/LER-1998-016, :on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With1998-11-24024 November 1998
- on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With
ML20196D7341998-11-20020 November 1998
Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi
ML20195D3821998-11-0404 November 1998
Safety Evaluation Supporting Amends 140 & 131 to Licenses DPR-42 & DPR-60,respectively
ML20155K6301998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20195D3761998-10-30030 October 1998
Safety Evaluation Supporting Amends 139 & 130 to Licenses DPR-42 & DPR-60
05000306/LER-1998-004-01, :on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With1998-10-0505 October 1998
- on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With
ML20202J7991998-09-30030 September 1998
Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept
ML20198R8061998-09-30030 September 1998
Rev 1 to NSPLMI-96001, Prairie Island Nuclear Generating Plant Ipeee
ML20154H4061998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With
ML20154B9241998-09-22022 September 1998
Safety Evaluation Supporting Amends 138 & 129 to Licenses DPR-42 & DPR-60,respectively
ML20198P0571998-09-0303 September 1998
Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator
ML20153B0761998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With
05000282/LER-1998-009-01, :on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures1998-08-27027 August 1998
- on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures
ML20237D6491998-08-13013 August 1998
Safety Evaluation Supporting Amends 137 & 128 to Licenses DPR-42 & DPR-60,respectively
1999-09-30
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