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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20086G7951995-07-10010 July 1995
Special Rept:On 950610,122 Diesel Fire Pump Started 2 Psig Below Acceptable Pressure Range Allowed by Procedure
ML20085G0591995-06-12012 June 1995
Special Rept:On 950515,121 Motor Driven Fire Pump Was Taken Out of Svc Due to Failed Transformer in Pump Control Circuitry
HL-4693, Special Rept 1-94-001:on 940911,seven Days Elapsed Since Main Stack post-accident Effluent Monitoring Sys Declared Inoperable Due to Damage to Sys Electronics by Lightning. Sys Expected to Be Returned to Svc by 9409211994-09-15015 September 1994
Special Rept 1-94-001:on 940911,seven Days Elapsed Since Main Stack post-accident Effluent Monitoring Sys Declared Inoperable Due to Damage to Sys Electronics by Lightning. Sys Expected to Be Returned to Svc by 940921
ML20072C8621994-08-0909 August 1994
Special Rept:On 940711,fire Protection Pump Removed from Service for Greater than Seven Days Due to Normal Preventive Maint Work.Pump Returned to Svc on 940721
ML20063M1741994-03-0303 March 1994
Special Rept:On 940117,fire Protection Equipment Removed from Svc for Greater than 14 Days.No NRC Commitments Being Made in Ltr
ML20125C8771992-12-0707 December 1992
Special Rept:On 921030,fire Zones Bypassed to Avoid Frequent Alarms During dual-unit Outage to Replace Cooling Water Pipe.Separate Fire Watches Posted for Each Ignition Source Activity & Open Penetration Door
ML20055D4051990-06-28028 June 1990
Special Rept:On 900607,inoperable Fire Suppression Water Sys Not Restored within 7-day Time Frame Per Tech Spec 3.14.B.2. Caused by Worn Bearing/Impeller Assembly.Efforts Underway to Procure Spare Bearing Housings for All Fire Pumps
ML20155B5661988-09-29029 September 1988
Ro:On 880903,circulating Water Pump 12 Suction Bay Isolated & Drained Down,Rendering diesel-driven Fire Pump Inoperable & on 880910,circulating Water Pump 11 Suction Bay Isolated & Drained Down,Rendering motor-driven Fire Pump Inoperable
ML20058A1521978-11-0101 November 1978
Environ Event Rept 78-10;covering Operation of Circulating Water Sys in Partial Recycle Mode W/Daily Average Blowdown Flow in Excess of 150 Cfs
1995-07-10
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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
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
ML20210Q4891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with
ML20211B5971999-07-31031 July 1999
Cycle 20 Voltage-Based Repair Criteria 90-Day Rept
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
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20209F9811999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
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
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
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
ML20205Q5101999-03-15015 March 1999
Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229
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
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
ML20206N2731998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20196D7341998-11-20020 November 1998
Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi
ML20155K6301998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20154H4061998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.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
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
ML20237A3961998-08-11011 August 1998
Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View
ML20237A8171998-08-0505 August 1998
SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2
ML20236X8531998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant
ML20236R6481998-07-15015 July 1998
Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept
ML20236R0771998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant
ML20249A5751998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant
ML20247G7011998-05-31031 May 1998
Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2
ML20248M0561998-05-31031 May 1998
Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique
ML20247E2671998-05-0505 May 1998
Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy)
ML20247G2921998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant
ML20217M6901998-04-29029 April 1998
Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2
ML20216C6361998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2
ML20216H0341998-03-31031 March 1998
Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept
ML20217D2041998-03-13013 March 1998
Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn
ML20236P9801998-03-12012 March 1998
Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys
ML20248L3931998-03-10010 March 1998
ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212
ML20216D0911998-03-0606 March 1998
Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept
1999-09-30
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 August 9, 1994 Technical Specification
.Section 3.14 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Report of Fire Protection Pump Removed from Service for Creater Than Seven Days This special report is being submitted in accordance with Prairie Island Technical Specification 3.14.B.2. Technical Specification 3.14.B.2 requires that, "With one or two of the pumps required by Specification 3.14.B.1.a inoperable, restore the inoperable equipment to OPERABLE status within seven days or provide a special report to the Commission within 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in the FIRE SUPPRESSION WATER SYSTEM."
On July 11, 1994 the 122 Diesel-Driven Fire Pump was taken out of service for normal Preventive Maintenance work. During this time regular maintenance was performed on the diesel engine and the pump end was entirely rebuilt. This work took 10 days and the diesel fire pump was returned to service on July 21, 1994.
During the time the Diesel-Driven Fire Pump was out of service, both the 121 Motor-Driven Fire Pump and the 121 Screenwash Pump were available for fire duty. In addition, the plant retained the ability to crosstie the cooling water system to the fire header should it have been required.
If you have further questions, please contact us.
No new NRC commitments are being made in this letter.
9408100126 940809 h
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US NRC
- NORTHERN STATES POWER COMPANY i
August 9, 1994 Page 2 Please contact Jack Leveille (612-388 1121, Ext. 4662) if you require additional information.
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(Roge O An o/ rs Director J Licensing and Management Issues c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg l
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