Letter Sequence Other |
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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
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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
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Text
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P e-September 25, 1979 PRELUiINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-II-79-1A This preliminary notification constitutes r.AKLY notice of an event of POSSIBLE safety or public interest significance.
The information presented is as initially received without verification or evaluation and is basict.lly all that is known by IE staff as of this date EACItITY: Virginia Electric and Power Comysuy North Anna, Unit No. 1 Docket No. 50-338 Mineral, Virginia I
f
SUBJECT:
REACTOR TRIP AND SAIITY INJECTION This supplements information previously submitted in PNO-II-79-1.
Subsequent to reactor trip and safety injection the maxis:um plant cooldown rate in the hot ics exceeded the coolcown limit by 10F in 30 ninutes. An engineering 7 valuation of the cooldown rate is being performed by the licensee.
Reactor coolant subcooling was maintained during the transient with a minimun pressure of 1760 psig with a 480*F coolant tenperature.
-Grab samples taken in the A and B erhanst stacks indicated 10% and 4% of allow-able release concentrations respectively.
The plant is proceding to cold shutdown using normal cooldown methods in prepara-tion for a refueling outage.
Media interest is expected.
The Licensee has issued a news release.
The Coc=:issioners will be briefed at 5:30 p.c:. today in an c,pm meeting. The ce=onwealth of Virginia has been notified.
Regios II (Atlanta) received notification of this additional information by telephone from the resident inspector at 3:45 p.n. on Sept:e';er 2.5.
Ccatset:
T. J. McHenry, RII 242-5565; P. J. Kellogg, RII e42-5649 Distribution:
Trans=itted H. St. E'oO Chair:an Eendrie Consissioner Bradford S. J. Chilt, SECY Cc=issioner Kennedy Co:=nissioner Ahearne C. C. Eamerer, CA C:=issiocer Gilinsky ACRS (For Distribution)
Tran:nitted:
MNEB N 03-P. Bldg.8['[7 IE:%0058.TM(IE:EQ Dist.)
L. V. Gossick, EDO H. R. Denton, NRR E. L. Ornstein, IDO R. C. DeYoung, ERR J. J. Fouchard, PA R. J. Mattson, NRR Landow 8.'/// (6 uin./page)
N. M. H nler, HPA D. Vassallo, NRR J. J. Cumings, OLA R. G. Ryan, OSP H. I. Shapar. ELD D.Eisenh[ut NRR SS Bldg.
.'O C/
MAIL W. J. Dircks, NMSS R. Minogue, SD Other Regional Offices 8.'."2 o, S. Levine, RES IE:XOOS (Timel 1160 123
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7910170
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