000			01866cam a2200457 a 4500
001			4012095
003			BD-DhUL
005			20161120153534.0
007			he bmb---bbca
008			890420s1989 dcua bbt f000 0 eng d
035			_a(OCoLC)19575606
035			_a4012095
037			_a052-021-00027-8 _bGPO _fpaper copy
040			_dGPO _dGPO _dBD-DhUL _cBD-DhUL
074			_a1051-H-11 (MF)
086	0		_aY 3.N 88:25/5293
088			_aNUREG/CR-5293
088			_aPARAMETER IE-184
091			_amfm
100	1		_aFoley, W. J.
245	1	0	_aCloseout of IE bulletin 86-01 _h[microform] : _bminimun flow logic problems that could disable residual heat removal pumps / _cprepared by W.J. Foley, R.S. Dean, A. Hennick.
260			_aWashington, DC : _bDivision of Operational Events Assessment, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, _c1954.
300			_a1 v. (various pagings) : _bill. ; _c28 cm.
500			_a"PARAMETER, Inc."
500			_aDistributed to depository libraries in microfiche.
500			_aNo longer available for sale by the Supt. of Docs.
500			_a"Date published: March 1989."
504			_aIncludes bibliographical references (p. B-4, 4th group).
513			_aTechnical. _b3/24/88 - 2/6/89.
536			_bB8729.
650		0	_aBoiling water reactors _xFluid dynamics.
650		0	_aNuclear power plants _xThermodynamics _xSafety measures.
650		0	_aBoiling water reactors _xCooling _xSafety measures.
700	1		_aDean, R. S.
700	1		_aHennick, A.
710	2		_aU.S. Nuclear Regulatory Commission. _bOffice of Nuclear Reactor Regulation. _bDivision of Operational Events Assessment.
710	2		_aParameter, Inc.
740	0		_aMinimun flow logic problems that could disable residual heat removal pumps.
942			_2ddc _cBK
984			_aANL _cmc SUDOC Y 3.N 88:25/5293
999			_c126222 _d126222