ML20244D986
| ML20244D986 | |
| Person / Time | |
|---|---|
| Issue date: | 06/16/1986 |
| From: | Heltemes C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Jennifer Davis, Harold Denton, Minogue R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20236H487 | List: |
| References | |
| FOIA-87-377, RTR-NUREG-0090, RTR-NUREG-90 NUDOCS 8606230525 | |
| Download: ML20244D986 (3) | |
Text
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o NUCLEAR REGULATORY COMMISSION 6f7 "
, t l wAssiNGTON. @. C. 20655 p June 16, 1986 I'
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MEMORANDUM FOR: H. R. Denton, Director, NRR l J. G. Davis, Director, HMSS R. B. Minogue, Director, RES j J. M. Taylor, Director, IE j i
G. H. Cunningham, Executive Legal Director J. J. Fouchard, Director, PA 3 G. W. Kerr, Director, SP ]
Regional Administrators j l l FROM: C. J. HeTtemes, Jr., Director f Office for. Analysis and Evaluation L of Operational Data
SUBJECT:
ABNORMAL OCCURRENCE REPORT TO CONGRESS FOR f FIRST QUARTER CY 1986 Based on the responses to the AE00 April 7,1986 memorandtim to the Office Directors and Regional Administrators on this subject, we have prepared the enclosed draft Commission Paper (Enclosure 1), the letters of transmittal to Congress (Enclosure 2), and the First Quarter CY 1986 Abnormal Occurrence (AO) l Report to Congress (Enclosure 3).
The draft quarterly report contains the following items:
A0s at NRC Licensees 86-1 LossofPowe[andWaterHammerEvent(SanOnofreUnit1).
86-2 Loss of Integrated Control System Power and Overcooling Transient (Rancho I
Seco).
86-3 Inoperable Standby Liquid Control System (Vermont Yankee).
l 86-4 Rupture of Uranium Hexafluoride Cylinder and Release of Gases (Sequoyah Fuels Facility; near Gore, Oklahoma).
86-5 Therapeutic Medical Misadministration (Washington Hospital Center; Washington, D.C.).
36-6 Overexposure to a Member of the Public from an Industrial Gauge (C-E Glass; St. Louis, Missouri).
86-7 Breakdown of Management Controls at an Irradiator Facility (Radiation Technology, Inc.; Rockaway, New Jersey).
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Multiple Addressocs 2
. 0 86-8 Tritium Overexposure and Laboratory Contamination (Ferris State College; Big Rapids, Michigan).
A0s at Agreement State Licensees ;
AS86-1 Radiation Injury of an Industrial Radiographer (BF Inspection Services; )
Midland, Texas). l AS86-2 Contamination of a Scrap Steel Facility (Tamco Steel Company; Ontario, California). j l
AS86-3 Radiation Injury of an Industrial Radiographer (Boothe-Twining, Inc. ; {
Bakersfield, California). y AS86-4 Radiation Injury of an Industrial Assistant Radiographer (Basin Industrial X-Ray; Odessa, Texas).
Appendix B (Updates of Previously Reported A0s) 79-3 Nuclear Accident at Three Mile Island - Further information is provided /
and the item remains open.
85-7 Loss of Main and Auxiliary Feedwater Systems - Further information is provided and the item remains open.
85-10 Breakdown in Management Controls - Further information is provided and i l
the item is closed out.
85-12 Management Control Deficiencies - Further information is provided and i the item remains open.
85-13 Inoperable Steam Generator Low Pressure Trip
- This previously closed ;
item is reopened to report new information. The item is then reclosed. !
85-14 Management Deficiencies at Tennessee Valley Authority - Further i information is provided and the item remains open.
85-20 Management Deficiencies at Fermi Nuclear Power Station - Further information is provided and the item remains open.
Appendix C ("Other Events of Interest")
- 1. Failure of Lifting Rig Attachment While Lifting an Upper Guide Structure (St. Lucie Unit 1).
- 2. Degraded Reactor Coolant Pump Shafts (Crystal River Unit 3 and possibly Davis-Besse Unit 1).
- 3. Earthquake in Vicinity a Nuclear Power Plant (Perry Facility).
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$, , Multiple Address = s 3 In regard to A0 86-7, in our April 7, 1986 memorandum, we suggested the event.
could be handled as an update to A0 77-10, provided the name of the original A0 was changed to reflect management deficiencies. In Region I's May 13, 1986 response to our memorandum, the Region recommended the latest incident should be considered as a new AO. We concur. ;
1 In Region V's April 25, 198S response to our April 7, 1986 memorandum, a write-up of a loss of decay heat removal event at San Onofre Unit 2 on March 27, 1986 is suggested as a possible Enclosure 3 ("Other Events Considered for A0 Reporting") item to the Commission paper. Based on our preliminary review of j the event, we believe it may be more significant than any of the other loss of I decay heat removal events,.which have occurred in recent years at U.S. PWR plants. )'
The issue of loss of decay heat removal during modes 4, 5 and 6 is being con-sidered by NRR as a high priority generic issue (#99). The issue of decay heat removal problems is addressed in AEOD case study report (AEOD/C503) which was issued for staff action during December 1985. !
l It is noted that one of the A0 examples states that series of events, recurring l incidents, and (or) incidents with implications for similar facilities, which create major safety concern can be considered an AO. We -believe that the large number of such events which have occurred satisfies this A0 example. Therefore, 1 we will prepare an A0' write-up, based on the AE00 case study report and the in- >
formation provided by Region V regarding the March 27, 1986 event at San Onofre Unit 2, for inclusion in the second quarter CY 1986 A0 report. l We request your review, comments and concurrence on this memorandum and its ,
enclosures no later than June 25, 1986. Please provide updating information, ;
if necessary, for all of the items in Enclosures 1 through 3 to reflect any l changes in status. We plan to submit the report to the Commission by mid-July 1986. If you have any questions, please contact Paul Bobe at 492-4426.
I C 4 Heltemes, r., Director O i be for Analy is and Evaluation of Operational Data
Enclosures:
- 1. Draft Commission Paper
- 2. Draft transmittal letters to Congress
- 3. Draft First Quarter CY 1986 A0 Report cc w/ enclosures:
J. Sniezek, DEDROGR J. Murphy, RES K. Murphy, Region I R. Whipp, SEC/ADM L. Cobb, IE L. Bettenhausen, Region I T. Dorian, ELD E. Weiss, IE K. Landis, Region II G. Holahan, NRR J. Callan, IE J. Rausch, Region II M. Caruso, NRR (3) R. Cunningham, NMSS J. Strasma, Region III J. Lubenau, SP R. O'Connell, NMSS D. Powers, Region IV S. Schwartz, IE R. Gramann, NMSS J. Crews, Region V E. Jordan, IE R. Hall, TMI-2 CPD J. Partlow, IE F. Ingram, PA
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