Letter Sequence Other |
|---|
|
Results
Other: 05000266/LER-1950-266-75, /75-4:on 750226,primary to Secondary Tube Failure Occurred in Steam Generator B & Went from Initial Point Leak to Max of 125 Gallons Per Minute.Extent of Incident & Radioactivity Below Point to Initiate Evacuation, 05000282/LER-1979-027-01, /01T-0:on 791002,tube Break Occurred in Steam Generator 11.Caused by Mechanical Wear.Two Defective Tubes Plugged, ML19209C950, ML19210C123, ML19259D260, ML19259D267, ML19259D273, ML19259D301, ML20031F203, ML20070J896
|
MONTHYEAR05000266/LER-1950-266-75, /75-4:on 750226,primary to Secondary Tube Failure Occurred in Steam Generator B & Went from Initial Point Leak to Max of 125 Gallons Per Minute.Extent of Incident & Radioactivity Below Point to Initiate Evacuation1975-02-27027 February 1975
/75-4:on 750226,primary to Secondary Tube Failure Occurred in Steam Generator B & Went from Initial Point Leak to Max of 125 Gallons Per Minute.Extent of Incident & Radioactivity Below Point to Initiate Evacuation
Project stage: Other
ML20070J8961976-09-29029 September 1976
RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated
Project stage: Other
ML20031F2031978-12-15015 December 1978
Forwards Summary of Recent Adverse Steam Generator Operating Experience at Facilities.Assessment of Each Event & Safety Significance Provided
Project stage: Other
ML19259D2731979-09-25025 September 1979
PNO-II-79-01:on 790925,turbine Trip & Reactor Trip Occurred Because of High Feedwater Heater Level.Caused by Failure to Realign Charging Pump Suction from Refueling Water Storage Tank to Vol Control Tank
Project stage: Other
ML19259D3011979-09-25025 September 1979
PNO-II-79-01A:after Reactor Trip & Safety Injection,Max Plant Cooldown Rate in Hot Leg Exceeded Cooldown Limit by 10 F in 30 Minutes.Evaluation Underway.Supplements PNO-II-79-01
Project stage: Other
ML19259D2601979-10-0202 October 1979
PNO-III-79-09:on 791002,steam Generator Tube Ruptured, Initiating Reactor & Turbine Trip & Safety Injection. Cause Not Stated.Release Occurred from Turbine Bldg. Steam Isolation Valves Are Closed
Project stage: Other
ML19259D2671979-10-0303 October 1979
PNO-III-79-09A:on 791002,tube Ruptured in Steam Generator A.Amount of Radioactive Matl Released to Containment Bldg Through Opened Rupture Disk Is Small.Cooldown Was Accomplished Satisfactorily.Plant Remains Shut Down
Project stage: Other
ML19209C9501979-10-0303 October 1979
PNO-III-79-09B:updates PNO-III-79-09A.On 791003,unit Reached Cold Shutdown.Caused by Tube Rupture in Steam Generator A. Plant Will Remain Shut Down Pending Completion of Generator Insp & Necessary Repairs
Project stage: Other
05000282/LER-1979-027-01, /01T-0:on 791002,tube Break Occurred in Steam Generator 11.Caused by Mechanical Wear.Two Defective Tubes Plugged1979-10-16016 October 1979
/01T-0:on 791002,tube Break Occurred in Steam Generator 11.Caused by Mechanical Wear.Two Defective Tubes Plugged
Project stage: Other
ML19209D0791979-10-16016 October 1979
Confirms Commitment Made to NRC at 791012 Meeting Re Submittal of License Amend Request within 30 Days to Adopt Primary & Secondary Coolant Activity Tech Specs.Forwards Interim Limit on Primary Coolant Iodine Activity
Project stage: Meeting
ML19254E8741979-10-22022 October 1979
Summary of 791012 Meeting W/Util Re Steam Generator Tube Rupture on 791002
Project stage: Meeting
ML19210C1231979-11-0606 November 1979
Forwards 10 Photographs Taken During Util Insp of 791002 Steam Generator Tube Rupture.Photographs Show Location of Springs & Eroded & Ruptured Tubes.Addl Photographs on File at Plant
Project stage: Other
1979-10-02
[Table View] |
Text
'
NiiiP NORTHERN STATES POWER C O F.
PANY M O N N E A PO LI S. M O N N E S OTA 55401 November 6,1979 Director of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISIAND NUCLLAR GENERATING PiANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Transmittal of No. 11 Steam Generator Tube Inspection Photographs NSP and Westinghouse representatives met with the NRC Staff on October 12, 1979 to discuss the Prairic Island No. 11 Steam Generator tube rupture of October 2, 1979.
NSP offered to transmit several sets of selected photo-graphs taken during the steam generator inspection.
The NRC meeting minutes requested three copies of pertinent pictures which show the loca-tion of springs, eroded and ruptured tubes, etc.
Enclosed are three sets of ten different photographs which show the significant observations made, and items found, during the inspection.
Additional photographs are on file at the plant for inspection.
The enclosed photographs have been numbered and a brief description of each follows:
Picture No.
Description 1-18A Views of tubes #3 and #4 on the hot leg side of the tube lace blocking device.
1-20A View of tubes #1, #2, and #3 on the hot leg side of the tube lane blocking device.
2-15 View of ruptured tube (#4).
2-24 View of spring on hot leg side of tube lane blocking device prior to tube lane blocking device removal. Also shows the first six tubes.
3-10A View of second spring and hose clamp on cold leg side of tube lane blocking device prior tu tube lane blocking device remove. l.
Note:
Color difference is because the photograph is in black and white.
7011130 306 1320 156
NORTHERN STATES POWER COMPANY November 6, 1979 Page PictureJg Description 5-8 View of both springs and hose clamp after tube lane blocking device was removed.
5-10 View of spring (cold leg side) and tube sheet wear marks from spring on hot leg side of tube lane biccking device af ter tube lane blocking device was removed.
5-12 Some as 5-10, except that the view includes more tube sheet wear marks.
1-S View of both springs and hose clamp af ter removal from steam generator.
2-S Same as 1-S cxcept somewhat different angle of view.
ha
~
Y L 0 Mayer, 1 Manager of Nuclear Support Services LOM/jh cc G Charnoff (w/o enclosure)
J G Keppler (w/o enclosure)
MPCA Attn: J W Ferman (w/o enclosure) enclosure 1320 157
