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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20058K6971975-05-0101 May 1975
Notifies That Surveillance Test for Exercising Unit 2 Containment Vacuum Breaker Isolation Valve Showed to Be Inoperable & Would Not Close.Maint Work Initiated & Valve Was Returned to Operable Status
ML20058K7981975-01-29029 January 1975
AO 75-3:on 750128,both Unit 2 Safety Injection Pumps Incapable of Starting on Automatic SI Signal from Approx 0900 to 100 H
ML20127K8731973-10-0808 October 1973
Ao:On 730929,SGBT Sys B Low Heat Alarm Received & Low Differential Pressure Observed.Caused by Failure of 30 Amp 600 Volt Fuse Block Assembly in Heater Circuit.Fuse Block Assembly Replaced & Operability Test Performed
ML20127K8761973-10-0505 October 1973
Ao:On 730926,discovered That Low Pressure Cooling Svc Water Sys for Diesel Generators 11 & 12 Not Demonstrated Operable on 730924 & 25,respectively.Caused by Personnel Error.Dg Starting Sys Maint Procedure to Be Revised
ML20127K8801973-09-25025 September 1973
Ao:On 730917,sodium Pentaborate Solution Found in Standby Liquid Control Pump 12 Lubricating Oil.Caused by Closed Stuffing Box Drain,Resulting in Leakage Into Crankcase. Crankcase Drained,Flushed & Refilled W/Oil
ML20024G2971970-09-29029 September 1970
Ao:On 700920,standby Power Source Failed to Close to Energize Bus,During Test of Emergency Power Source When Power Source 4.16 Kv.Caused by Undervoltage Relay Failing to Drop Out
ML20056B7511970-09-29029 September 1970
Ao:On 700921,localized Fire in Portion of SGTS Train a Charcoal Filter Bank Rendered Unit Inoperable.Caused by Overheating One of Four Strip Heaters.Corrective Actions: Place Temp Switch on Filter
ML20056B7281970-09-18018 September 1970
Ao:On 700908,failure in Current Limiting Circuitry for Air Heater in SGTS Filter Train a Rendered Unit Inoperable.On 700910,SGTS Filter Train B Failed to Provide Flow Rate Sufficient to Maintain .25 Inch of Water Vacuum
1975-05-01
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1261999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With
ML20216E7031999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With
ML20210Q0521999-08-0404 August 1999
Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided
ML20210Q6611999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With
ML20209F7901999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With
ML20195H0351999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With
ML20206N1721999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With
ML20205N0861999-04-12012 April 1999
Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20205P5701999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With
ML20204H4951999-03-18018 March 1999
SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05
ML20205G7391999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With
ML20202F7901999-01-25025 January 1999
1999 Four Year Simulator Certification Rept for MNGP Simulation Facility
ML20199E4871999-01-0606 January 1999
SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode
ML20199F6211998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Mngp.With
ML20205H0561998-12-31031 December 1998
Northern States Power Co 1998 Annual Rept. with
ML20198P0691998-12-28028 December 1998
Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized
ML20198D0751998-12-10010 December 1998
Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding
ML20198B2531998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With
ML20195E3691998-11-12012 November 1998
Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46
ML20195D2381998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With
ML20198J4451998-10-22022 October 1998
Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv
ML20154L3471998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With
ML20153F0511998-09-21021 September 1998
Rev 2 to MNGP Colr,Cycle 19
ML20153E9361998-09-0808 September 1998
Rev 1 to MNGP Colr,Cycle 19
ML20153B0861998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With
ML20237B8461998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant
ML20236W5041998-07-21021 July 1998
ISI Exam Summary Rept - Refueling Outage 19
ML20236R1941998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant
ML20249A5861998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant
ML20247K3971998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant
ML20217D8731998-04-13013 April 1998
Rev 0 to MNGP Colr,Cycle 19
ML20217F6431998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant
ML20216D1041998-03-0505 March 1998
Rev 21 to Operational QA Plan
ML20216H6481998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant
ML20203G1431998-02-10010 February 1998
Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531
ML20203B2821998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station
ML20202F9161998-01-29029 January 1998
Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128
ML20216D2071997-12-31031 December 1997
1997 Annual Rept for Northern States Power Co
ML20197J8131997-12-31031 December 1997
Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing
ML20198P2201997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant
ML20203J7131997-11-30030 November 1997
Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant
ML20199G7051997-11-19019 November 1997
Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval
ML20199H8181997-10-31031 October 1997
Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant
ML20217K2081997-09-30030 September 1997
Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant
ML20216H7771997-08-31031 August 1997
Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant
ML20217K2741997-07-31031 July 1997
Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant
ML20196H1081997-07-0808 July 1997
Rev 20 to Operational QA Plan
ML20141B9271997-06-30030 June 1997
LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps
ML20149E2921997-06-30030 June 1997
Monthly Operating Rept for June 1997 for MNGP
ML20148S6341997-06-23023 June 1997
NPSH - Rept of Sulzer Bingham Pump
1999-09-30
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Text
1 Ri~gulal0ry D00'gl utB NSP NORTHERN STATE 5 POWER COMPANY M A N N E A Pol.l S. M IN N E S OTA SS401 s MM~ /'
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on .'3 3 SEP 281973 * :- n .
Mr. J. F. O' Leary, Director Directorate of Licensing k2 $Ng tg1 um I" '>
1 Office of Regulation 'Q. , O 8 United States Atomic Energy Commission 7y b ,i #
c3 Washington, DC 20545 T, Dear Mr. O' Leary MOSTICELLO NUCLEAR GENERATING PIANT Docket No. 50-263 License No. DPR-22 Sodium Pentaborate Solution in No. 12 SBLC Pump Lubricating 011 A condition occurred at the Monticello Nucicar Generating Plant which we are reporting to your office in accordance with Section 6.7.B.1. Abnormal occurrence Reports, of the Appendix A Technical Specifications, of Provisional Operating License DPR-22.
On September 17, 1973, sodium pentaborate solution was found in the No. 12 Stand-by Liquid Control pump lubricating oil. An investigation of the problem revealed that the stuffing box drain valve was closed, which caused the normal pump packing leakage to collect in the stuffing box until it leaked into the crankcase through the plunger stub ports. The drain valve was immediately opened. It was deter-mined that the stuffing box drain valve had been closed on or about September 17th for painting of the pump mounting base.
The No. 12 pump crankcase was drained, flushed, and refilled with new oil. The No.11 SBLC pump was inspected and also found to have the stuffing box drain valve closed; however, the amount of solution which accumulated in the stuffing box was not sufficient to result in leakage into the crankcase. The drain valves will be seal wired in the open position to prevent future inadvertent closure.
This occurrence did not affect safe operation of the plant since the redundant Standby Liquid Control pump was fully operable. Standby Liquid Control pump operability has not been compromised on any previous occasions due to inadvertent closure of the stuffing box drain valves.
Very truly yours, L 0 Mayer, PE Director of Nuclear Support Services 9211230307 730925 m r cc: J G Keppler PDR ADOCK 05000263 (M o rM G Charnoff S PDR Minnesota Pollution Control Agency--Attn. K Dzugan - _
