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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
[Table view] 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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, 4 Northem States Powe' Company 414 Nicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330-5500 March.3, 1994 Technical Specification Section 3.14 U S Nuclear Regulatory Commission Attn: Document Control Desk Wanhington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT.
Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Report of Fire Protection Equipment j Removed from Service for areaLer Than Foujtteen Days This letter in to document the inoperability of deluge systems and a fire
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detection panel in the DS/D6 Diesel Generator Building.
In accordance with Section 3.14.A.1 of the Prairie Island Technical Specifications, the minimum fire detection instrumentation for each fire detection zone shown in Table 3.14-1 shall be OPERABLE whenever equipment in that fire detection zone is required to be operable.
TS 3.14.A.2 requires that:
If TS 3.14.A.1 cannot be met: ,
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a) Within one hour, establish a fire watch patrol to inspect zone with the inoperable instruments at least once per hour.
b) Restore the inoperable instruments to operable status within.14 days or submit a special report to the Commission within 30 days ~
outlining the cause of the malfunction and the plans for restoring the instruments to OPERABLE status.
In accordance with Section 3.14.C.1 the listed spray.and sprinkler systems are' required to be OPERABLE whenever equipment protected by this spray and oprinkler system is required to be OPERABLE.
TS 3.14.C.2 requires thatt j If TS 3.14.C.1 cannot be met, a continuous fire watch with backup fire suppression equipment shall be established within one hour. Restore inoperable spray and sprinkler systems to' OPERABLE status within 14 days i O-1 Y
9403100367 940303 PDR ADOCK 05000202 g PDR
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US NRC' NORTHERN STATES POtWER COMPANY H&rch 3, 1994 Page 2 i
I or submit a special report to the Commission within 30 days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.
On January 17, 1994 the locil Fire Panel for the D5/D6 building was taken out !
of service to rewire the dr.tector circuits for the detectors that provide I input to the preaction valves from class B to class A. During this time the l deluge system for the D5 and D6 diesels were also out of service but were available for use if needed by manual actuation. The panel and the deluge systems were returned to service on February 1, 1994. During the time the panel and deluge systems were out of service a fire watch was established for the affected areas.
The D5/D6 fire panel and deluge valves have not been added to the Prairie Island Technical specifications but the above actions were taken as compensatory measures since the diesels they are protecting are safety related.
No new NRC commitments are being made in this letter.
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you require additional information.
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Ro er O Anderson Director Licensing and Management Issues i
c Regional Administrator - Region III, NRC Senior Resident Inspector, NRC l NRR Project Manager, NRC J E Silberg l
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