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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20202F9161998-01-29029 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
ML20138F5801997-04-29029 April 1997
Special Rept:On 970402,declared Reactor Bldg Wide Range Gas Monitor Inoperable.Caused by Ruptured Pump Diaphragm. Initiated Work Order,Installed Replacement Pump & Declared Pump Operable
ML20137Y2171997-04-15015 April 1997
Special Rept:On 961220,util Rail Car Was Released to Burlington Northern Railroad from Monticello Nuclear Plant. Rail Car Was Delayed in Chicago as Result of Problems W/Bill of Lading on Computer Sys.Rail Car Was Delivered on 970131
ML20101E8321996-03-15015 March 1996
Special Rept:On 960314,two of Three Fire Pumps Removed from Svc for Planned Mod Work.Returned Both Fire Pumps to Svc Same Day
ML20094E4371995-10-31031 October 1995
Special Rept:On 951010,sys Engineer & Technicians Reintiated Work on B Channel of Reactor Bldg Vent Radiation Monitor, After Providing Proper Notification to Main Control Room. Caused by Incorrect Channels Removed from Svc
ML20082R6601995-04-19019 April 1995
Special Rept:On 950404,discovered That Manual Isolation Valves for 'A' Channel in Closed Position.Cause of Failure to Correctly Position Valves Will Be Assessed.Valves Placed in Required Position & Demonstrated Operability
ML20082E5661995-04-0606 April 1995
Special Rept:On 950326,pump Discharge Relief Valve for Electric Screen Wash/Fire Pump Became Inoperable.Valve Had to Be Secured to Permit Installation of an Isolation Device. Pump Returned to Operational Status After Device Installed
ML20080G4731995-02-0101 February 1995
Special Rept:On 950119,two of Three Fire Protection Pumps Out of Svc for Period of Approx 15 H.Action Taken for Planned Preventative Maint on Two Check Valves & Drain Valve in Fire Suppression Sys.Roving Fire Watch Established
ML20067D1351994-02-23023 February 1994
Special Rept:On 940126,fire Door 105 Declared Inoperable Due to Inability to Close Properly.Caused by Higher than Normal Differential Pressure Between Plant Administration Bldg & Turbine Bldg.Cause of Failure Corrected
ML20117A5801992-11-24024 November 1992
Special Rept:On 921020,determined That RHR Sample Supply Loops a & B Excess Flow Check Valves Not Included in ASME Section XI Program.Caused by Lack of Proven Test Procedure. Valves Incorporated Into Third 10-yr ASME Program
ML20082G9261991-08-15015 August 1991
Special Rept:On 910719,potential for Inoperable Penetration Fire Barrier Identified.Caused by Use of Less Conservative, But Technically Acceptable,Design Alternatives in Plant Const.Vents Will Be Rerouted
ML20244E5941989-06-16016 June 1989
Special Rept:On 890603,two Out of Three Diesel Fire Pumps Were Inoperable for Less than 12 H.Caused by Diesel Fire Pump Day Tank Outlet Valve Being Closed Instead of Fill Valve During Performance Test 1158.Test Revised
ML20081G9561983-10-25025 October 1983
Ro:On 831024,trip Coil for Reactor Recirculation Motor Generator Set 11 Drive Breaker Failed to Trip Automatically. Investigation Ongoing.Trip Coil Replaced
ML20066E0131982-11-0101 November 1982
Ro:On 821031,thru Wall Defect Found on C 12-inch Recirculation safe-end to Pipe Weld Joint.Resolution Under Investigation
ML20064E5141982-10-21021 October 1982
Ro:On 821020,thru Wall Defect Found on E 12-inch Recirculation Sys Safe End to Pipe Weld Joint.Indications Will Be Documented as Revision to RO 82-16 Reported on 820928.Resolution Being Investigated
ML20064E4761982-10-11011 October 1982
Ro:On 821009,linear Indications Confirmed to Exist on Three Addl Welds in Recirculation Sys.Indications Will Be Documented as Revision to RO 82-16 Reported on 820928. Resolution Being Investigated
ML20071N4361982-09-28028 September 1982
Ro:On 820928,crack Indication in End Cap of a Recirculation Riser Confirmed by Radiography.Indications Initially Detected by Ultrasonic Exam During Normal Inservice Insp. Remedial Measures Under Investigation
ML20071L8261982-09-16016 September 1982
Ro:On 820915,leak Discovered on Primary Containment Suppression Chamber Nitrogen Control Sys Inboard Isolation Valve (AO-2378).Leakage Less than Tech Spec Allowable Leakage
ML20053E8071982-06-0202 June 1982
RO Iii:On 810224,failure of Discharge Valve on Instrument & Svc Air Compressor Resulted in Loss of Instrument Air Sys Pressure Causing Plant Scram.Failed Check Valve Replaced W/Similar Unit
ML20058L3431978-07-31031 July 1978
Ro:On 780728,control Rod Drive 30-47 Delayed Approx 1.4 Before Scramming.Buna N Disk in Plunger Broken in Pieces.Plungers on 242 Scram Pilot Valves & Two Backup Scram Pilot Valves Removed & Replaced
ML20090L8311978-06-0202 June 1978
Ro:On 780505,steam Leak Noted in RCIC Inlet Steam Line & Drain Line to Condenser.Caused by Pinhole Failure on Weld on 300 Lb Socket Weld.Hole Temporarily Patched
ML20091A9941978-03-10010 March 1978
Ro:On 780309,smear Survey of Chem Nuclear Sys Inc Model 4-45 Shipping Cask Disclosed Max Surface Contamination of 25,900 Disintegrations Per Min Per 100 Square Centimeters.Cask Will Be Decontaminated
ML20127G6171978-02-0202 February 1978
Advises That on 780202,during Surveillance Test,One Suppression Chamber to Drywell Vacuum Breaker Failed to Reclose Following Exercise.Plant Shutdown Initiated
ML20086D5141978-01-0606 January 1978
Telecopy Ro:On 780105,discovered That One of Two Nuclear Engineering Co Model B3-1 Shipping Casks Provided w/1-inch Diameter Lid Bolts Rather than 1-1/4 Inch Size Specified in Certificate of Compliance 6058
ML20086D5201977-12-14014 December 1977
Telecopy Ro:Heating Steam Coil Leak in Reactor Bldg Ventilation Supply Unit V-AH-4A Resulted in Freezing of Condensate at Inlet to Unit & Subsequent Inoperability of Associated Secondary Containment Isolation Dampers
ML20086D5371977-10-14014 October 1977
Telecopy Ro:Insp of Internal Torus Catwalk Support Structure Revealed That Catwalk Mitered Sections Not All Attached to Horizontal Catwalk Support Plates in Some Manner.Attachment Locations Will Be Upgraded
ML20086D5501977-10-13013 October 1977
Telecopy Ro:On 771012,local Leak Rate Testing of MSIV AO-2-80A & Nitrogen Instrument Air Sys Isolation Valve CV-7436 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation
ML20086D5541977-10-0505 October 1977
Telecopy Ro:On 771004,local Leak Rate Testing of HPCI Sys Discharge Isolation Check Valve HPCI-9 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation
ML20086D5571977-09-29029 September 1977
Telecopy Ro:On 770929,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO-14-13A Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation
ML20086D5611977-09-14014 September 1977
Telecopy Ro:On 770913,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO 14-13B Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Related Event on 770914
ML20086D5671977-09-12012 September 1977
Telecopy Ro:Main Steam Drain Isolation Valve MD 2373 & Main Steam Outboard Isolation Valve AO 2-86A Exceeded Tech Spec Acceptance Criteria for Local Leak Rate Tests
ML20086D6421977-07-11011 July 1977
Telecopy Ro:On 770709,determined That Recombiner Sys a Offgas Flow Control Valve PCV 7489A Could Be Opened W/ Controlling Solenoid Valve Deenergized.Valve Held from Svc Pending Investigation
ML20058K6111977-03-0909 March 1977
Ro:On 770223,discovered Withdrawal of in-sequence Control Rod Resulted in Period Less than 5-s & IRM Scram
ML20086D6911977-03-0202 March 1977
Telecopy Ro:On 770301,torus Water Vol Found to Be Slightly Below Min Vol Established by Tech Specs.Water Vol Restored to Normal Operating Level
ML20086D7031977-02-24024 February 1977
Telecopy Ro:On 770223,while Withdrawing in-sequence Control Rod to Bring Reactor Critical,Reactor Period of Less than 5 Obtained
ML20086D7881976-09-10010 September 1976
Telecopy Ro:On 760909,discovered That Torus Water Vol Several Hundred Cubic Ft Below 68,000 Cubic Ft Min Required by Tech Specs.Caused by Failure to Correct for Vol Vs Level Correlation
ML20056B8541976-05-21021 May 1976
Informs of 760520 Event Involving TIP Bell Valve Which Failed to Properly Close During Operation of TIP Sys.Valve Cleaned,Relubricated & Closure Spring Tension Increased
ML20086D8231976-05-0505 May 1976
Telecopy Ro:On 760504,during Routine Surveillance Test, Primary Containment Oxygen Concentration Found to Be in Excess of Tech Spec Limit.Caused by Leakage from Drywell Instrument Air Sys Into Containment Nitrogen Supply Line
ML20127L2611975-09-22022 September 1975
Informs of 750921 Incident Re Countrate Decreasing Below 3 Counts Per While Performing Refueling Core Alterations. Countrate Increased & Refueling Operations Recommenced. Further Investigation Continuing
ML20127L2751975-09-22022 September 1975
Informs of 750920 Incident Re Drywell Equipment Drain Sump Isolation Valves AO 2561A & B Exceeding TS Acceptance Criteria.Further Investigation Continuing
ML20127L2551975-09-19019 September 1975
Informs That on 750919,during Local Leak Rate Testing of MSIVs 2-86A & 2-88A,combined Leakage of Valves Exceeded Acceptance Criteria.Further Investigation Continuing
ML20127L2391975-09-15015 September 1975
Informs of 750914 Incident Re Discovery That Hydraulic Shock Suppressor Located Inside Primary Containment on Loop B HPCI Line Inoperable Due to Loss of Oil.Reactor in Cold Shutdown for Refueling.Further Investigation Underway
ML20127L1741975-08-21021 August 1975
Discusses 750818 Incident Re Broken Seal Cooling Line at Threaded Connection on Reactor Water Cleanup Pump 12.Pump Immediately Isolated & Line Repaired.Investigation Into Cause of Failure Continuing
ML20127L2651975-07-28028 July 1975
Ro:On 750727,operator Motor Failed & Stalled Due to Stalled Rotor Current Overheating Windows.Investigation Pending
ML20127L2521975-07-14014 July 1975
Ro:On 750713,small Leak Developed on Local Pressure Gauge Monitoring Reactor Pressure.Root Valve for Pressure Gauge Closed,Allowing Ref Leg to Refill & Water Level Indication to Return to Normal
ML20058L1761975-07-11011 July 1975
Ro:On 750624 & 25,10 Initial Core Fuel Assemblies Which Had Been Identified as Leakers & Removed from Core at End of Cycles 2 & 3 Inspected Using Underwater Television
ML20058K6751975-07-0303 July 1975
Notifies That on 750703,during Routine Surveillance Testing, Reactor High Pressure Scram Switches Found Inoperable
ML20127B7371975-05-27027 May 1975
Ro:On 750525 Core Spray Sys Motor Operated Valve Failed to Reopen by Means of Motorized Operator.Valve Was Returned to Normal Open Position by Local Handwheel
ML20058K6951975-05-0505 May 1975
Ro:On 750505,discovered That Control Circuit for Valve Steam Supply to RCIC Turbine Was Deenergized by Motor Control Unit Undervoltage Relay Coil Opening.Coil Replaced & Remote Operability of Valve Demonstrated
ML20127L1471975-05-0101 May 1975
RO 75-12:on 750429,surveillance Test for Exercising Unit 2 Containment Vacuum Breaker Isolation Valve CV-31628 Showed Valve to Be Inoperable
1998-01-29
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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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. D Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 June 16, 1989 Tech Spec 3.13'.B.3.b Director of Nuclear Reactor Regulation US Nuclear Regulatory Commission .
Attn: Document Control Desk i Washington D.C. 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 l
l k
Special Report j 2 of 3 Fire Purns Inoperable l This special report is being submitted per Technical Specification l 3.13.B.3.b. Technical Specification 3.13.B.3.b requires that, "With the l
fire system otherwise inoperable provide a special report to the Commission i within 14 days outlining the actions taken and the plans and schedule for I restoring the system to operable status".
On Saturday, June 3, 1989 at approximately 0500 the diesel fire pump operability test #1158 was completed in preparation for isolating the screenwash/ fire pump for repacking. During the performance of test #1158 the diesel fire pump day tank outlet valve was closed instead of the diesel fire pump day tank fill valve as the procedure states. This isolated the fuel supply to the diesel fire pump, making it inoperable. At 0525, the isolation for the screenwash/ fire pump was complete making it inoperable.
A t- 1358 it was discovered that the wrong valve had been closed. The diesel
, ump day tank outlet valve was opened and the fill valve verified c 1. The diesel fire pump was declared operable at 1500 when the ops bility test of the diesel fire pump was completed. Therefore, the two fire pumps were inoperable for less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
A backup fire suppression water system was not established since the time between discovery of the diesel fire pump inoperablity and restoration to an operable condition was less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
m h
s y
, : o Northem States Power Company Director of NRR June 16, 1989 Page 2 To prevent this from reoccurring the following actions have been taken:
- 1. The diesel fire pump day tank outlet velve is now seal wired open.
- 2. The Diesel Fire Fump Operability Test #1158 has been reviewed and revised to include valve numbers and valve tag names to any step which requires manipulation of a valve.
Please contact me if you require additional information.
M Thomas M Parker Manager Nuclear Support Services cc: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G Charnoff
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