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1
CAUSES
  • traditionally component failure and operator
    error
  • frequently these turn out to be effects rather
    than causes
  • better regarded as initiating events
  • Three Mile Island a classic example

2
CAUSES
  • human action or inaction (management decisions)?
  • usually remote in location, time and corporate
    hierarchy from the human-machine interface
  • may not be recognised or acknowledged as
    safety-related

3
  • THE ORGANISATION (TOP LEVEL MANAGEMENT) HAS
    MATERIAL RESPONSIBILITIES FOR SAFETY
  • Responsibilities first formally defined by HM
    Railways Inspectorate (UK) in 1858
  • Investigation of 1870 collision (Brockley Whins)
    found management wholly responsible

4
  • we spend enormous amounts of time and effort on
    ensuring materials and components will perform
    properly
  • we spend similar amounts writing procedures,
    training operators and monitoring their
    performance
  • we spend similar amounts on ensuring engineering
    design is adequate
  • how much attention is paid to management
    performance?

5
Human error in the Boardroom
  • Management cock-ups in five flavours
  • 1. dont understand hazard
  • 2. production considerations dominate
  • 3. dont define/assign safety responsibility
  • 4 ignore, or dont learn from, experience
  • 5 dont maintain corporate memory

6
1 Misperception of hazard
  • specific vulnerabilities of technology not
    appreciated or wilfully ignored
  • technical safety envelope not understood
  • Can occur anywhere in management chain, but most
    frequently at senior levels

7
2 Dominant Production Imperative
  • production considerations override safety
  • potential economic loss of accidents discounted
    or ignored
  • resources not applied to maintain or improve
    safety

8
3 Safety responsibility undefined
  • responsibility/authority for safety inadequately
    defined, assigned or discharged
  • safety responsibility/authority does not run in
    unbroken chain to most senior level
  • senior management must be in control of all
    safety design and operating decisions throughout
    the life of the plant (Brown Meneley, 1983)?

9
4 Failure to learn from experience
  • failure to recognise, acknowledge or respond
    effectively to an unsatisfactory or deteriorating
    safety situation
  • failure to analyse, interpret or apply operating
    experience
  • wilful disregard of operating experience

10
5 Corporate amnesia
  • failure to maintain required levels of
    technical/intellectual resources
  • failure to formalise compilation, analysis and
    recording of operating experience (discounting
    historical experience)?
  • closely related to 4 most likely results from
    1 and 2

11
  • SL-1 reactivity insertion accident (1961)?
  • Herald of Free Enterprise capsize (1987)?
  • Challenger explosion (1986)?
  • Pickering pressure tube failure (1983)?
  • Pickering SLOCA (1994)?
  • Fuel string relocation issue (1962-present)?

12
SL-1
  • National Reactor Testing Station, Idaho Falls

13
SL-1
  • stationary low-power reactor for remote military
    installations (air transportable)?
  • 3 MWth direct cycle BWR designed by Argonne
    National Laboratory
  • started up August 1958 at National Reactor
    Testing Station, Idaho Falls
  • concept demonstration and training, managed by
    Combustion Engineering
  • operated by military personnel under training

14
SL-1
15
SL-1 design features
  • fuel 91 percent U-235 metal
  • core structural materials aluminium-nickel alloy
    (first use in reactor)?
  • burnable poison strips tack welded to fuel
    assemblies
  • withdrawal of central control rod sufficient to
    bring reactor critical (rod provided with 19 in
    follower to preclude its dropping out of core)?
  • only core access via CR nozzles, which required
    dismantling of CR drives and removal of shield
    plugs

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21
  • duration of nuclear portion of accident
  • 2 ms
  • total duration of accident
  • 2-4 s
  • Period of interest
  • August 1959-December 1960
  • (17 months or 90.6336 Ms)?

22
SL-1 History
  • August 1959 Significant design deficiencies
    identified
  • August 1960 Significant (hazardous) core
    deterioration reported
  • September 1960 SL-1 returned to service at
    higher power level
  • September-December 1960 severe deterioration in
    CR performance

23
SL-1 August 1959
  • distortion of poison strips noted in August 1959
    CE recommends
  • stainless steel should be used as core material
    (including fuel cladding)?
  • reactor should have adequate shutdown margin with
    any one control rod removed
  • control rod drive mechanisms should be redesigned
  • recommendations accepted by AEC-- new core to be
    available by spring 1961
  • SL-1 operations continue

24
SL-1 August 1960
  • Severe core deterioration reported
  • pieces of boron strip missing
  • core inspection curtailed because of safety
    concerns
  • 14.3 in central CR withdrawal sufficient to
    achieve criticality
  • inspection report concluded rate of loss of
    boron has been constant shutdown margin will
    continue to decrease, thus requiring remedial
    action
  • inspection results reported in Nucleonics

25
SL-1 September-December 1960
  • cadmium strips added to increase shutdown margin
  • reactor returned to power at 4.7 MWth
  • significant deterioration in CR performance (33
    cases of sticking rods in November-December)?
  • rod performance not reported-- not regarded as
    malfunction
  • SL-1 shutdown 23 December
  • flux measuring wires installed 3 January 1961

26
3 January 1961
  • 1600-midnight shift to re-assemble CR drives and
    prepare reactor for start up
  • three operators on duty
  • re-assembly of CR drives included movement of CR

27
CR drives and core access
  • access to core via CR drive nozzles required
  • disconnection of rod drives
  • manual raising of control rod for disconnection
    of stop washer, then lowering rod again
  • disassembly and removal of drive gear
  • removal of shield plug

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29
CR drive disassembly procedure
  • secure special tool CRT No 1 on top of rack and
    raise rod not more than 4 inches. Secure C-clamp
    to rack at top of spring housing
  • Remove special tool CRT No 1 from rack and remove
    slotted nut and washer
  • Secure special tool CRT No 1 to top of rack and
    remove C-clamp, then lower control rod until the
    gripper knob located at the upper end of element
    makes contact with the core shroud
  • Assembly of the rod drive mechanism are the
    reverse of disassembly

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31
SL-1 sequence 2100
  • central CR raised to 20 in reactivity insertion
    24 mk
  • power peak 20,000 MWth
  • 2 ms nuclear energy release ends
  • 34 ms water strikes vessel head loose shield
    plugs ejected vessel begins to rise
  • 160 ms operator impaled to ceiling
  • 800 ms vessel hits ceiling
  • 2000-4000 ms vessel back in place

32
Underlying failures
  • safety responsibility undefined/unassigned
  • hazard not clearly defined/understood
  • no effective response to early indications of
    design deficiency or core deterioration
  • dominating production imperative

33
Safety responsibility/authority undefined
  • Multiplicity of responsible organisations
  • Argonne National Laboratories
  • Combustion Engineering
  • AEC Chicago Operations
  • AEC Idaho Operations
  • AEC Military Reactors Division
  • AEC Army Reactors Office (Washington)?
  • No single continuously assigned safety authority

34
Misperception of hazard
  • C/R drive maintenance procedures ignored
    criticality implications of control rod movement
  • control rod sticking not considered a
    malfunction and not reported

35
Failure to respond
  • core design/materials established (and
    acknowledged) to be unsatisfactory but no
    revision of operating regime
  • serious core deterioration (with criticality
    implications) prompted no operational changes or
    procedural revisions

36
Dominating production imperative
  • It is clear, and many people have later said so,
    that the reactor should have been shut down
    pending resolution of the boron difficulties and
    the general deterioration of control rod
    operation. In fact no one did so or even brought
    the malfunctions to the attention of any
    responsible safety group. In the climate that
    existed before the accident, it is likely that if
    one man had decided that the reactor should be
    shut down for safety reasons he would have been
    ridiculed and would almost certainly have had an
    unfriendly response since he would have had to
    say some rather harsh things to accomplish his
    purpose. T J Thompson

37
  • Cross-channel ferry
  • Herald of Free Enterprise
  • Zeebrugge, 1987

38
Herald of Free Enterprise
  • Ro-Ro ferry capsized in about three minutes on 87
    03 06 after leaving Zeebrugge with bow loading
    doors open
  • 188 deaths
  • greatest British peacetime maritime loss since
    RMS Titanic

39
Standing Orders
  • required OOW to be on the bridge 15 min before
    sailing time
  • required loading officer (who was also the OOW)
    to supervise door closing
  • 1982 memo from senior Captain identifying
    inconsistency It is impractical for the O.O.W.
    (either the Chief or Second Officer) to be on the
    Bridge 15 minutes before sailing time. Both are
    fully committed to loading the ship.
  • no action taken

40
Schedule pressure
  • Intense pressure on officers for early departure
    every effort has to be made to sail the ship 15
    minutes earlier... put pressure on the first
    officer if you dont think he is moving fast
    enough August 1986 memo from Operations Manager

41
Precursors
  • instances of vessels sailing with open doors
    reported in 1983 and 1984
  • Captains suggest installation of indicator lights
  • suggestion rejected by Board of Directors

42
  • by the autumn of 1986 the shore staff of the
    Company were well aware of the possibility that
    one of their ships would sail with her stern or
    bow doors open. They were also aware of a very
    sensible and simple device in the form of
    indicator lights which had been suggested by
    responsible Masters

43
Legal requirements not met
  • excessive passenger numbers carried (masters not
    informed of passenger complement and discouraged
    from checking)?
  • masters not informed of load
  • draught marks could not be read-- fictitious
    numbers recorded (requests for draught indicators
    refused)?
  • vessels frequently sailed in unknown stability
    conditions, significantly trimmed by the head

44
  • vessels are required to have on board sufficient
    life-saving equipment for all passengers and crew
  • 1971 Merchant Shipping Act requires that master
    be aware of passenger complement and cargo load,
    and that the draught marks (ship's trim) be
    recorded in the log

45
Excessive passengers carried
  • two instances reported in 1982
  • instances reported in 1983 and 1984
  • five instances reported in 1986
  • more passengers carried than permitted (loading
    limit)?
  • more passengers carried than life-saving
    appliances

46
Excessive passengers carried
  • 1982-86 repeated written complaints from seven
    masters to shore management about excessive
    passenger complement
  • passenger manifests falsified-- at first the
    director's answers were very evasive but
    eventually he agreed that the figure given in the
    manifest was a false figure
  • no remedial action-- ... was unwilling to accept
    the figures given to him by no less than seven
    masters... the Court reluctantly concluded that
    he made no proper or sincere effort to solve
    the problem

47
  • dominating production imperative
  • misperception of hazard (wilful or otherwise)?
  • refusal to respond to clear indication os unsafe
    conditions
  • no defined safety responsibility

48
Dominating production imperative
  • just about everywhere
  • indicator light proposal rejected (1985)?
  • high speed ballast pump proposal rejected
  • continual emphasis on fast turn-round put
    pressure on the First Officer its fifteen
    minutes early for us operations manager

49
Misperception of Hazard (1)?
  • no substantive response to loading door issue
  • routine overloading and excessive passenger
    complement accepted/ignored/encouraged
  • trim issues ignored (stability very sensitive to
    trim) an operational difficulty problem
    grossly exaggerated
  • Marine Director appeared to think Herald was
    designed to proceed at sea trimmed 1 m by the
    head despite the fact he had no stability
    information for the ship in that trim
  • routine violation of Merchant Shipping Act
    accepted/ignored/encouraged

50
Misperception of Hazard (2)?
  • those charged with the management of the
    Companys Ro-Ro fleet were not qualified to deal
    with many nautical matters and were unwilling to
    listen to their Masters, who were well-qualified
  • Wreck Commissioner

51
Failure to respond (1)
  • inconsistent Standing Orders (identified to
    management in 1982)?
  • excessive passenger numbers carried (at least
    seven examples formally reported 1982-1986)?
  • sailing with loading doors open
  • no investigation of draught gauges

52
Failure to respond (2)?
  • 1982 Collision Investigation Report
  • ships draught not read before sailing
    (policy)?
  • master not informed of passenger figures
    (working practice)?
  • master not informed of tonnage of cargo (working
    practice)?
  • full speed maintained in dense fog (policy)?

53
Undefined safety responsibility
  • no director responsible for safety
  • Board did not appreciate their responsibility
    for the safe management of their ships
  • Court singularly unimpressed by Technical
    Director and Operations Director-- thoroughly
    unsatisfactory witnesses

54
  • Loss of Space Shuttle Challenger

55
STS Challenger
  • vehicle destroyed 86 01 28
  • combustion gas leak from aft field joint on
    starboard SRB (678 ms after ignition)?
  • gas jet breached external tank at 66.46 s
  • shuttle destroyed at 76.3 s, altitude 46,000 ft,
    speed M1.92

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60
SRM joint design deficiency
  • identified in 1977 (hydrostatic testing)?
  • formally reported as unsatisfactory 1979
  • the clevis joint secondary O-ring seal has been
    verified by tests to be unsatisfactory
  • redundancy of joint not verifiable, yet
    classified 1R in 1980
  • reclassified 1 (ie non-redundant) in 1982

61
Flight history
  • second flight (Nov 1981) showed primary O-ring
    erosion
  • 12 of 15 shuttle flights (Feb 84-Jan 86) showed
    blow-by/erosion
  • O-ring damage severity correlated with
    temperature

62
  • safety responsibility undefined/unassigned
  • nature of hazard either not understood or
    wilfully ignored
  • no substantive response to O-ring erosion
  • production imperative in overall programme and in
    specific launch decision

63
Safety Responsibility Undefined
  • no single group with continuous direct safety
    responsibility
  • upward reporting (Level III to Level II) of
    flight safety issues stopped in 1983

64
Misperception of Hazard
  • little NASA experience with solid fuel rockets
  • confusion over redundancy of joint
  • O-ring erosion acceptable
  • remedial action none required Possibility
    exists for some O-ring erosion on future flights
  • temperature sensitivity of O-ring ignored
  • reliability expectations 3 orders of magnitude
    above reality (R P Feynman)?

65
Failure to respond
  • inadequacy of design clearly identified by 1979
  • O-ring distress/erosion occurred in majority of
    flights (80 percent)?
  • O-ring erosion not recorded as flight anomaly and
    not considered during flight readiness reviews

66
Dominating production imperative
  • selection of SRM design based on cost MTI was
    least acceptable technically
  • ambitious flight schedule combined with staff
    reductions
  • routine use of waivers to permit flight with
    non-redundant field joint
  • concerns about low temperature launch over-ridden
    (when do you want me to launch, Thiokol? In
    July?)?
  • no SRQA representative involved in Challenger
    launch decision

67
Pickering-2 PT failure
  • failure of Zircaloy PT G-16 on 1 August 1983--
    leak rate 19 kg/s
  • unit shut down in controlled fashion
  • failure due to PT-CT contact occurring 2-5 years
    after start up
  • early contact due to out of position spacer
  • unit 1 not shut down until 14 November
  • retubing programme for all 4 Pickering units

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69
  • failure to respond to operating experience and/or
    misperception of hazard
  • dominating production imperative

70
Failure to respond...
  • inspection programme 1979-82 suggested 30 percent
    of P1 2 PT in contact with CT due to misplaced
    garter springs
  • calculation of heat loss to moderator only
    recorded response
  • OH Research strongly urged removal of Zr tube for
    examination
  • focus on Zr-Nb?
  • early indications at WNRE in 1976?
  • PT sagging more or less as predicted? Bothwell

71
Production imperative
  • operators should have tripped reactor promptly
  • OH did not shut down Unit 1 for 3 ½ months

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73
Two more quick ones
  • Pickering Unit 2 SLOCA (1994)?
  • Fuel string relocation reactivity issue
    (1962-present)?

74
  • response to an accident (or event) can be very
    revealing...
  • Pickering Unit 2 SLOC of 1994 Root Cause
    Investigation did not identify root cause (some
    information actively concealed)?
  • fuel string relocation issue consigned to
    corporate memory hole

75
Pickering-2 SLOCA
  • 10 December 1994
  • liquid relief valve fails open (diaphragm fails
    due to thermal aging)?
  • bleed condenser relief valves open RV 5
    chattered cracking inlet line 68 kg/s leak to
    boiler room

76
RCI findings
  • diaphragm replacement frequency changed from 2
    years to 10 years some time in the past
  • authority and bases for this change not recorded
  • lack of knowledge in the Canadian nuclear
    industry about sensitivity of spring-loaded
    relief valves (?!)?
  • two separate designers-- one specified valve
    size, the other designed piping layout

77
Fuel string relocation
  • en masse fuel movement identified for one LOCA
    scenario in March 1993
  • Bruce A and B derated to 60 percent
  • potential for fuel movement recognised since 1962
    (NPD start up) yet reactivity effects never
    defined as safety concern

78
RCI findings
  • lack of sufficient questioning attitude and
    environment
  • insufficiently broad knowledge in individuals
  • ineffective communication of new information and
    emerging issues
  • adequate scoping and review inhibited by time and
    budget constraints

79
RCI recommends
  • training to broaden awareness of safety issues
  • breakdowns and failures in the analysis process
    should be communicated to all nuclear safety
    staff so everyone has the opportunity to learn
    from the mistakes of the past
  • REPORT NEVER FORMALLY ISSUED

80
Some other examples
  • Brockley Whins collison (1870) I find the
    company's management wholly to blame for this
    accident
  • Shipton derailment (1874) 34 dead
  • Aberfan landslide (1966) 144 dead (116 children)?
  • Flixborough explosion (1974) 28 dead
  • Hinton (Alta) rail collision February 1986 23
    dead
  • Kings Cross fire November 1987 31 dead
  • Ocean Ranger oil rig sinking (1982) 84 dead
  • Bhopal (1984) gt3000 dead

81
  • Piper Alpha oil rig fire July 1988 167 dead
  • Clapham Junction rail collision (1988) 35 dead
  • Westray mine explosion May 1992 26 dead
  • Ladbroke Grove rail collision (1991) 31 dead
  • Columbia STS breakup on re-entry (2003) 7 dead

82
  • Crash of RAF Nimrod XV230, Afghanistan, (14
    dead) 2006
  • Sayano-Shushenskaya (Khakassia) dam turbine
    failure (75 dead), 2009
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