Testimony of Wf Wegst Re UCLA Reactor Safety.Bldg Fire Could Not Damage Core.Sufficient Energy or Oxygen Could Not Reach Graphite to Cause Rapid Oxidation to Ignite Large Quantity of Energy.Prof Qualifications EnclML20077J107 |
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08/12/1983 |
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Wegst W CALIFORNIA, UNIV. OF, LOS ANGELES, CA |
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ML20077J103 |
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NUDOCS 8308150221 |
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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20247Q7371989-07-28028 July 1989 Order Authorizing Dismantling of Facility & Disposition of Component Parts ML20211Q3021986-07-14014 July 1986 Order Authorizing Dismantling of Facility & Disposition of Components in Accordance W/Phase I of Dismantling Plan & NRC Rules & Regulations,Per 851029 Application ML20205G6071985-11-0808 November 1985 Order Terminating Proceeding Since Committee to Bridge the Gap Withdrew Petition for Leave to Intervene.No Other Petitions Remain.Served on 851112 ML20205G6551985-11-0808 November 1985 Memorandum & Order Approving Parties 851010 Stipulation to Dismantle & Dispose of All Reactor Components & Equipment Except for Biological Shield & Components Described in Stipulation.Served on 851112 ML20133Q2781985-10-30030 October 1985 Response to ASLB 851016 Memorandum & Order Re Settlement Agreement & Proposed Order on Matters in Dispute Concerning Proposed License Renewal & Dismantlement Proceedings. Paragraph 6 of Proposed Order Should Be Revised ML20133Q2941985-10-30030 October 1985 Affidavit of Dj Kasun Re Question 3 in ASLB 851016 Memorandum & Order Concerning Effect of Release of UCLA Security Plan to Public on Security of Other Nonpower Reactors W/Similar Plans.Certificate of Svc Encl ML20133J0691985-10-16016 October 1985 Memorandum & Order Requesting Parties to Respond by 851030 to Listed Questions Re 851010 Settlement Agreement & Proposed Order Terminating Proceeding.Served on 851017 ML20108A9601984-11-13013 November 1984 Answer Opposing Committee to Bridge the Gap 841024 Petition for Hearing & Leave to Intervene.Petition Fails to Satisfy Requirements & No Good Cause Exists for Deferment of Ruling on Petition.Certificate of Svc Encl ML20094A4741984-10-24024 October 1984 Petition of Committee to Bridge the Gap for Leave to Intervene & Request for Hearing Re Proposed Issuance of Orders Authorizing Disposition of Component Parts & Termination of License R-71.Certificate of Svc Encl ML20097A1271984-09-0707 September 1984 Response to ASLB 840806 Order Part B.Prompt Shipment of SNM, Removal of Metallic Core Components & Prompt Dissolution of Protective Order Required by Order,Regulations & Public Policy.Declaration of Svc Encl ML20097A0181984-09-0707 September 1984 Reply to Committee to Bridge the Gap 840801 Response Re Request to Withdraw Application.Aslb Should Approve Withdrawal of Application & Terminate Adjudicatory Proceedings.Certificate of Svc Encl ML20096G8791984-09-0707 September 1984 Response to ASLB 840806 Order Re Other Parties Responses to UCLA Motion for Withdrawal of Renewal Application. Clarification of Ambiguities in Proposals Progressing.W/Svc List ML20094C1371984-08-0101 August 1984 Response Opposing Staff Proposed Conditions for UCLA Withdrawal of License Renewal Application.Aslb Should Follow Required Practice Consistent W/Nrc Case Law.Certificate of Svc Encl ML20093H9281984-07-20020 July 1984 Reply Opposing Committee to Bridge the Gap (Cbg) 840703 Response to Univ Request to Withdraw Application.Cbg Not Established as Participant in License Termination Proceeding.Certificate of Svc Encl ML20093G1541984-07-20020 July 1984 Withdrawal of 840622 Emergency Petition for off-shipment of Reactor Fuel Prior to Arrival of Olympic Athletes.Petition Moot.Declaration of Svc Encl ML20090C7851984-07-11011 July 1984 Response Opposing Committee to Bridge the Gap 840622 Petition for Commission Order to Remove SNM Prior to Olympics.Motion Lacks Factual Basis & Does Not Conform to Procedure.Certificate of Svc Encl ML20092P2431984-07-0303 July 1984 Response Supporting Univ 840614 Request to Withdraw Application for License Renewal.Proposed ASLB Order Accepting Withdrawal Request Encl.W/Certificate of Svc ML20151J9891984-06-25025 June 1984 Memorandum Explaining Reason Underlying 840622 Telegraphic Memorandum & Order Suspending All Further Proceeding. Licensee Has Shown No Desire to Retain Fuel Longer than Necessary.Served on 840626 ML20092G2821984-06-22022 June 1984 Emergency Petition for off-shipment of SNM from Site Before Olympics,Due to Withdrawal of Renewal Application & Security Risk Associated W/Olympics.Declaration of Svc Encl ML20140C6651984-06-18018 June 1984 Order Canceling Contention Xx Evidentiary Hearings Due to Licensee 840614 Request to Withdraw License Renewal Application & to Decommission Reactor.Served on 840619 ML20197H3831984-06-14014 June 1984 Request to Withdraw License Renewal Application on Condition That Application Be Made to Decommission ML20197H4051984-06-14014 June 1984 Motion to Suspend Proceedings Pending ASLB Action on Request to Withdraw Application.Hearing on Security Contention Should Be Canceled Immediately to Avoid Unnecessary Expense.Certificate of Svc Encl ML20197G7651984-06-11011 June 1984 Motion to Compel Further Written Response of B Ramberg or for Alternative Relief & Costs.Committee to Bridge the Gap Has Not Revealed Documents Per Interrogatory Requests. W/Certificate of Svc.Related Correspondence ML20091Q6071984-06-11011 June 1984 Objection to ASLB 840606 Notice of Evidentiary Hearing Specifying That Portions of Contention Xx Evidentiary Hearing Will Be Closed to Public.Only Portions Dealing W/Protected Info Should Be Closed.Certificate of Svc Encl ML20091M8351984-06-0707 June 1984 Motion to Compel Committee to Bridge the Gap to Provide Further Written Answers to Questions 6 & 7 of Univ 840525 Interrogatories Re Security Contentions.Certificate of Svc Encl.Related Correspondence ML20091G8411984-05-30030 May 1984 Notice of T Taylor & D Hafemeister Depositions on 840604 & 05,respectively.Certificate of Svc Encl.Related Correspondence ML20091B3371984-05-25025 May 1984 Interrogatories Re Security Contention.Certificate of Svc Encl.Related Correspondence ML20090J6721984-05-0909 May 1984 Response to Applicant Request for Reversal of ASLB 840413 Finding of Matl False Statements.Requests Hearing in Which Questions Unanswered by Two UCLA Responses Can Be Thoroughly Explored.Declaration of Svc Encl ML20084H1991984-05-0404 May 1984 Notice of Disposition of Plotkin & Gt Cornwall on 840510 Re Physical Security & Request for Production of Documents. Certificate of Svc Encl.Related Correspondence ML20084F7061984-05-0101 May 1984 Estimate of Level of Threat Facing UCLA Reactor in Response to ASLB 840420 pre-hearing Conference Order.Facility Attractive Theft & Sabotage Target.Certificate of Svc Encl ML20084F1971984-05-0101 May 1984 Declaration of Wh Cormier in Response to ASLB 840413 Memorandum & Order Re Questions About Apparent Misrepresentations Made by Univ & NRC ML20084F1641984-05-0101 May 1984 Response to ASLB 840413 Order Directing Univ to Indicate Whether Any Representatives Had Reviewed Cormier 830825 Statements.No Representative of Regents Reviewed Statements Before or After Submittal ML20084F1881984-04-27027 April 1984 Declaration of Nc Ostrander Re Review of Cormier 830825 Statements.No Member of Staff Requested to Review Documents Before or After Submittal ML20084E7271984-04-27027 April 1984 Notice of Appearance in Proceeding.Certificate of Svc Encl ML20084D0711984-04-25025 April 1984 Motion for Reconsideration & Clarification of Portions of ASLB 840420 Prehearing Conference Order Re Contention Xx. Certificate of Svc Encl ML20084C4001984-04-24024 April 1984 Reply Opposing Applicant Motion for Reconsideration of ASLB 840322 Order & Further Suppl to Rebuttal.Source Term Issue Under Investigation Should Not Be Litigated in Individual License Proceeding ML20084C4151984-04-23023 April 1984 Response to Committee to Bridge the Gap (Cbg) 840406 Motions for Reconsideration of ASLB 840322 Memorandum & Order Ruling on Cbg Objections to Rebuttal Testimony.Motions Should Be Denied.Certificate of Svc Encl ML20088A0551984-04-0606 April 1984 Motion to Reconsider Portions of ASLB 840322 Memorandum & Order,Overruling Objections to Untimely Filed Rebuttal Testimony.Aslb Has Placed Interest in Complete Record Above Statutory Interests of Proceedings.W/Certificate of Svc ML20088A1611984-04-0606 April 1984 Motion for Reconsideration of Certain Portions of ASLB 840322 Order.Only Penalty for Violation of ASLB Orders Is Further Delay & Continued License Possession,Precisely What Licensee Desires.Declaration of Svc Encl ML20088A2011984-04-0606 April 1984 Response to Applicant 840330 Rept Re Reactor Shutdown, Repair & Testing Schedule.Certificate of Svc Encl ML20088A6911984-04-0606 April 1984 Petition Per Reconsideration of ASLB Order Ruling on Committee to Bridge the Gap Objections to Rebuttal Testimony.Certificate of Svc Encl ML20087D7111984-03-0909 March 1984 Response to ASLB 840224 Order Indicating Concerns on Security Plan & Security Insp Repts Re Sabotage Matters Raised by Contention Xx & Directing Univ & Staff to Respond by 840309.Certificate of Svc Encl ML20235Z3661984-03-0606 March 1984 Affidavit of MD Schuster in Response to Question Raised by Aslp in UCLA Proceeding in Aslp 840224 Order Re Physical Security Insp Repts to UCLA & Every Licensee Inspected ML20080N2431984-02-16016 February 1984 Motion Denying Committee to Bridge the Gap 740109 Motion for Reactor Curtailment.No Factual or Legal Basis Exists to Support Extreme Remedy Sought.W/Certificate of Svc ML20080B7491984-02-0101 February 1984 Response Objecting to Applicant/Nrc Proposed Witnesses & Proposed Mod to Protected Order.Witnesses Do Not Qualify as Experts.Declaration of Svc Encl ML20080B6871984-01-31031 January 1984 Response Objecting to Release of Certain Protected Info. Proposed Sanitized Portions of Security Plan Should Be Released Only to Qualified Witnesses.Certificate of Svc Encl ML20079H8501984-01-20020 January 1984 Reply Opposing Applicant 840117 Request for 24-day Extension to Respond to Committee to Bridge the Gap 840109 Motion for Curtailment.Reasonable Extension Not Opposed.Certificate of Svc Encl ML20079H4011984-01-17017 January 1984 Application for Extension of Time Until 840216 to Respond to Committee to Bridge the Gap 840109 Motion for Curtailment III (Irreparable Injury Associated W/Any Further Delay). Extension Will Not Delay Matters.W/Certificate of Svc ML20079H3751984-01-17017 January 1984 Response to Committee to Bridge the Gap Memorandum Clarifying Contention Xx,Paragraphs 1,2 & 3.Committee Should Be Made to Respond to NRC Motion Re 10CFR73.67. Certificate of Svc Encl ML20079J1881984-01-16016 January 1984 Review of UCLA Analysis of Facility Shutdown Mechanism. Postulated Power Excursion Will Not self-terminate as Assumed by Expulsion of Water Out Top of Fuel Box Region Through Surrounding Brick Walls 1989-07-28
[Table view] Category:TRANSCRIPTS
MONTHYEARML20082B4891983-11-17017 November 1983 Corrected 831107 Rebuttal Testimony Re Shutdown Mechanism ML20081M3181983-11-0707 November 1983 Rebuttal Testimony Re Reactor Shutdown Mechanism & of Credibility of Graphite Fire & of Committee to Bridge the Gap (Cbg) Fission Product Release Model & Rebuttal to Cbg Panel I Rebuttal & to Cbg Energy & Dispersion Testimony ML20077J1101983-08-12012 August 1983 Testimony of Ha Morewitz Re UCLA Reactor Safety.Analysis of Hypothetical Fuel Handling Accident in UCLA SAR Postulating Release from One Fuel Plate Represents Conservative Estimate of Possible Releases.Prof Qualifications Encl ML20077J1071983-08-12012 August 1983 Testimony of Wf Wegst Re UCLA Reactor Safety.Bldg Fire Could Not Damage Core.Sufficient Energy or Oxygen Could Not Reach Graphite to Cause Rapid Oxidation to Ignite Large Quantity of Energy.Prof Qualifications Encl ML20077J0841983-08-0909 August 1983 Limited Appearance Statement of Eg Fontheim.Urges Renewal of License R-71.Danger of Unanticipated Surge of Power Impossible ML20024A5461983-06-14014 June 1983 Testimony of L Wayne,R Finston,S Aftergood,L Foster,M Kaku, B Norton,R Kohn,S Plotkin,M Pulido,D Dupont & D Hirsch,As Panel IV Re Radiation Doses from Accidental Release of Fission Products.Declaration of Svc Encl ML20024A5371983-06-14014 June 1983 Testimony of B Norton,M Kaku,R Kohn,M Pulido,S Plotkin, D Hirsch,S Aftergood & D Dupont,As Panel III Re Core Disruption & Related Accidents.Reactor Not Inherently Protected Against Mechanical Damage ML20024A5231983-06-14014 June 1983 Testimony of L Wayne,D Dupont,B Norton,M Kaku,M Pulido, R Kohn,D Hirsch,S Plotkin,S Aftergood,As Panel II Re Chemical Reactions.Reactor Not Inherently Protected Against Severe Core Damage from Fire ML20024A5101983-06-14014 June 1983 Testimony of B Norton,M Kaku,R Kohn,D Hirsch,S Aftergood, M Pulido & D Dupont,As Panel I Re Concepts of Inherent Safety Applied to Reactor ML20024A4991983-06-14014 June 1983 Testimony of B Norton,L Wayne,M Kaku,R Finston,R Kohn, M Pulido,D Dupont,S Aftergood,L Foster,D Hirsch & s Plotkin, Questioning Inherent Reactor Safety ML20097B7851982-10-17017 October 1982 Transcript of H Scoville 821017 Declaration Re Proposed Renewal of Facility License ML20054L3081982-06-30030 June 1982 Transcript of 820630 Prehearing Conference in Los Angeles, Ca.Pp 713-793 ML20054L3061982-06-30030 June 1982 Transcript of 820630 Prehearing Conference in Los Angeles, Ca.Pp 654-671 ML20054L0271982-06-29029 June 1982 Transcript of 820629 Hearing in Los Angeles,Ca.Pp 492-653 1983-08-09
[Table view] Category:DEPOSITIONS
MONTHYEARML20082B4891983-11-17017 November 1983 Corrected 831107 Rebuttal Testimony Re Shutdown Mechanism ML20081M3181983-11-0707 November 1983 Rebuttal Testimony Re Reactor Shutdown Mechanism & of Credibility of Graphite Fire & of Committee to Bridge the Gap (Cbg) Fission Product Release Model & Rebuttal to Cbg Panel I Rebuttal & to Cbg Energy & Dispersion Testimony ML20077J1101983-08-12012 August 1983 Testimony of Ha Morewitz Re UCLA Reactor Safety.Analysis of Hypothetical Fuel Handling Accident in UCLA SAR Postulating Release from One Fuel Plate Represents Conservative Estimate of Possible Releases.Prof Qualifications Encl ML20077J1071983-08-12012 August 1983 Testimony of Wf Wegst Re UCLA Reactor Safety.Bldg Fire Could Not Damage Core.Sufficient Energy or Oxygen Could Not Reach Graphite to Cause Rapid Oxidation to Ignite Large Quantity of Energy.Prof Qualifications Encl ML20077J0841983-08-0909 August 1983 Limited Appearance Statement of Eg Fontheim.Urges Renewal of License R-71.Danger of Unanticipated Surge of Power Impossible ML20024A5461983-06-14014 June 1983 Testimony of L Wayne,R Finston,S Aftergood,L Foster,M Kaku, B Norton,R Kohn,S Plotkin,M Pulido,D Dupont & D Hirsch,As Panel IV Re Radiation Doses from Accidental Release of Fission Products.Declaration of Svc Encl ML20024A5371983-06-14014 June 1983 Testimony of B Norton,M Kaku,R Kohn,M Pulido,S Plotkin, D Hirsch,S Aftergood & D Dupont,As Panel III Re Core Disruption & Related Accidents.Reactor Not Inherently Protected Against Mechanical Damage ML20024A5231983-06-14014 June 1983 Testimony of L Wayne,D Dupont,B Norton,M Kaku,M Pulido, R Kohn,D Hirsch,S Plotkin,S Aftergood,As Panel II Re Chemical Reactions.Reactor Not Inherently Protected Against Severe Core Damage from Fire ML20024A5101983-06-14014 June 1983 Testimony of B Norton,M Kaku,R Kohn,D Hirsch,S Aftergood, M Pulido & D Dupont,As Panel I Re Concepts of Inherent Safety Applied to Reactor ML20024A4991983-06-14014 June 1983 Testimony of B Norton,L Wayne,M Kaku,R Finston,R Kohn, M Pulido,D Dupont,S Aftergood,L Foster,D Hirsch & s Plotkin, Questioning Inherent Reactor Safety ML20097B7851982-10-17017 October 1982 Transcript of H Scoville 821017 Declaration Re Proposed Renewal of Facility License ML20054L3081982-06-30030 June 1982 Transcript of 820630 Prehearing Conference in Los Angeles, Ca.Pp 713-793 ML20054L3061982-06-30030 June 1982 Transcript of 820630 Prehearing Conference in Los Angeles, Ca.Pp 654-671 ML20054L0271982-06-29029 June 1982 Transcript of 820629 Hearing in Los Angeles,Ca.Pp 492-653 1983-08-09
[Table view] Category:NARRATIVE TESTIMONY
MONTHYEARML20082B4891983-11-17017 November 1983 Corrected 831107 Rebuttal Testimony Re Shutdown Mechanism ML20081M3181983-11-0707 November 1983 Rebuttal Testimony Re Reactor Shutdown Mechanism & of Credibility of Graphite Fire & of Committee to Bridge the Gap (Cbg) Fission Product Release Model & Rebuttal to Cbg Panel I Rebuttal & to Cbg Energy & Dispersion Testimony ML20077J1101983-08-12012 August 1983 Testimony of Ha Morewitz Re UCLA Reactor Safety.Analysis of Hypothetical Fuel Handling Accident in UCLA SAR Postulating Release from One Fuel Plate Represents Conservative Estimate of Possible Releases.Prof Qualifications Encl ML20077J1071983-08-12012 August 1983 Testimony of Wf Wegst Re UCLA Reactor Safety.Bldg Fire Could Not Damage Core.Sufficient Energy or Oxygen Could Not Reach Graphite to Cause Rapid Oxidation to Ignite Large Quantity of Energy.Prof Qualifications Encl ML20077J0841983-08-0909 August 1983 Limited Appearance Statement of Eg Fontheim.Urges Renewal of License R-71.Danger of Unanticipated Surge of Power Impossible ML20024A5461983-06-14014 June 1983 Testimony of L Wayne,R Finston,S Aftergood,L Foster,M Kaku, B Norton,R Kohn,S Plotkin,M Pulido,D Dupont & D Hirsch,As Panel IV Re Radiation Doses from Accidental Release of Fission Products.Declaration of Svc Encl ML20024A5371983-06-14014 June 1983 Testimony of B Norton,M Kaku,R Kohn,M Pulido,S Plotkin, D Hirsch,S Aftergood & D Dupont,As Panel III Re Core Disruption & Related Accidents.Reactor Not Inherently Protected Against Mechanical Damage ML20024A5231983-06-14014 June 1983 Testimony of L Wayne,D Dupont,B Norton,M Kaku,M Pulido, R Kohn,D Hirsch,S Plotkin,S Aftergood,As Panel II Re Chemical Reactions.Reactor Not Inherently Protected Against Severe Core Damage from Fire ML20024A5101983-06-14014 June 1983 Testimony of B Norton,M Kaku,R Kohn,D Hirsch,S Aftergood, M Pulido & D Dupont,As Panel I Re Concepts of Inherent Safety Applied to Reactor ML20024A4991983-06-14014 June 1983 Testimony of B Norton,L Wayne,M Kaku,R Finston,R Kohn, M Pulido,D Dupont,S Aftergood,L Foster,D Hirsch & s Plotkin, Questioning Inherent Reactor Safety ML20097B7851982-10-17017 October 1982 Transcript of H Scoville 821017 Declaration Re Proposed Renewal of Facility License ML20054L3081982-06-30030 June 1982 Transcript of 820630 Prehearing Conference in Los Angeles, Ca.Pp 713-793 ML20054L3061982-06-30030 June 1982 Transcript of 820630 Prehearing Conference in Los Angeles, Ca.Pp 654-671 ML20054L0271982-06-29029 June 1982 Transcript of 820629 Hearing in Los Angeles,Ca.Pp 492-653 1983-08-09
[Table view] |
Text
4 j
UNITED STATES OF AMERICA '
NUCLEAR REGULATORY COMMISSION -
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )
) Docket No. 50-142 THE REGENTS OF THE UNIVERSITY ) (Proposed Renewal of Facility OF CALIFORNIA ) License Number R-71)
)
(UCLA Research Reactor) )
)
TESTIMONY OF DR. WALTER F. WEGST CONCERNING THE SAFETY OF THE UCLA RESEARCH REACTOR Q.l. Please state your name and occupation.
A.l. My name is Walter F. Wegst. I am employed by the University of California as Director of the Office of Research and Occupational Safety for the Los Angelns campus (UCLA).
Q.2. Please describe your current responsibilities and experience relevant to the testimony you are providing. ,
A.2. I am responsible for providing for the safety of the campus from all health and safety hazards, including the possibility of fire. The Campus Fire Marshall, who is a Deputy State Fire Marshall, and the Campus Radiation Safe'ty l Officer are both under my supervision. My office is responsible for coordinating with the Los Angeles Fire Department (LAFD) to the extent that the assistance of the LAFD is needed on the UCLA campus. My educational background is in engineering and physics. I have twenty-three years of 1 l
l 1
8308150221 830812 PDR ADOCK 05000142 O PDR
^ .
i
- l. ,
l ,, experience in the safety field and regularly consult on safety questions. I have had numerous consultations with experts in the field of fire control. My experience also includes three years on the staff of the University of Michigan's water-moderated, graphite-reflected research reactor. I am a member of the UCLA Reactor Use Committee which oversees the activitier; of the UCLA reactor. A statement of my professional qualifications is attached.
Q.3. What in your opinion is the likelihood that a building fire could damage the core of the UCLA reactor? i
- A.3. In my opinion, thereh.snocrediblewayafireeither within Boelter, Hall, the Nuclear Energy Laboratory (NEL),
or the reactor room (the high bay) could damage the core of the reactor. There is simply no way that aufficient 1
energy (ignition source) or . oxygen could reach the graphite to cause it to oxidize rapidly enough to liberate a'large quantity of energy. .
Q.4 What is the basis of your opinion?
A.4. Fundamentally, three elements are required before a fire can occur. These three elements, ignition source, fuel and oxygen make up the so called " fire triangle" and all must be continuously present for a fire to be self-sustaining. For example, a fire can be extinguished C'
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~. .
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.. by: water which cools the fuel and hence removes the ignition source (heat); carbon dioxide which removes l l
the oxygen; a " firebreak" which removes the fuel. This concept is very basic, but is is very important to answering the question as to whether any external fire can adversely affect the reactor core. In considering the question whether a fire external to the reactor could reach the core and damage the fuel, three possible scenarios can be distinguished. First, there could be a' major fire in the buildings (Boelter Hall and the Mathematical Sciences Addition) which surround the NEL. Second, there could be a fire in the NEL but outside of the reactor high bay room.
Third, there could be a fire inside the reactor high bay, but outside of the biological shielding for the reactor. '
Q.5. Would you explain the factors you considered for each of these scenarios?
A.5. A major building fire can be described as one that spreads beyond the room or place of origin. Concerning the suggested scenario that a majob building fire in Boelter Hall or the Mathematical Sciences Addition (MSA) could result in damage to the reactor core, the following 6
~
1 1
I facts need to be considered:
(1) There has never been a' major building fire at UCLA.
(2) The LAFD respense time is 2-5 minutes to any l place on the campus. l (3) The Reactor Building is a separate structure-from Boelter Hall and MSA, which surround it i
on the top and three sides. All three buildings are constructed of non-combustible poured reinforced concrete.
(4) The entire NEL outside of the reactor high bay room an'd excluding the west exterior exposure is equipped with a fire sprinkler system.
(5) The roof of the Reactor Building is 6 inches of concrete and is separated from the building above by 26 feet of open space (hence no fuel immediately in contact with the . roof') . Six inches of concrete will hold back any fire for many hours.
Because of these considerations a major building fire in Boelter Hall or MSA is extremely unlikely to occur.
If a' fire did occur, the LAFD would be on the scene very quickly. In any event, the structure of the Reactor Building will provide more than adequate
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_y protection against the intrusion of any fire into the NEL. Any fire that did penetrate into the outer perimeter spaces of the NEL would be extinguished by the water sprinkler system.
Q.6. What about a fire starting within the NEL itself?
A.6. The NEL consists of the 2-story Reactor Building and adjacent portions of Boelter Hall and MSA. A fire starting within the NEL but outside of the reactor room would immediately trigger the sprinkler system and hence would be quickly suppressed. Further, whenever any campus sprinkler. system is activated, a signal is ,
automatically sent to the 24-hour campus central dispatch center which relays the alarm by direct line to the IAFD. In addition,the following factors must be considered:
(1) The high bay itself has 14 inch concrete walls, equipped with double fire doors (three hour rating each door) on all openings except the west, exterior side.
l (2) The fuel loading ~in the NEL is relatively light.
There are paper supplies and wood furniture in the various laboratories, but there are no large quantities of combustible or flammable liquids.
The amount of available conbustible materiai is .
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insufficient to generate a fire that could breach the reactor room walls. Although there are small holes for pipes and conduits that do penetrate i
the reactor room walls, there is no force that l
would drive a potential fire through these holes.
Q.7. What about a fire within the reactor high bay room.
A.7. In addition to the factors already mentioned the following must be considered:
(1) The amount of combustible material in the high bay area is so small (no combustible or fla==ahle liquids) that this area offactively acts as a fire-l break between any external fire and the reactor itself.
(2) The reactor is surrounded by 5-6 feet of concrete.J{t; i
with a few penetrations for experimental equipment. !
\
The north and south walls of this shield are ,,
monolithic pours of concrete (no cracks). The ~I ~
east and west walls are slabs of concrete stacked so that there are no cracks that pass entirely t
through the shield (for radiation shielding) .
Concerning all three of the fire scenarios, because of the factors I mentioned there is no credible way that any_ fire could ever reach the biological shield of the reactor or get into the reactor core. There are other l points that can be made which greatly suppo;;t this general conclusion.
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Q.8. What other points do you wish to make? -
A. 8. One important point is that the few small cracks in 4-t the shield, or even an open beam port in the shield !
I would not provide a path for an external fire to reach the core. The convection currents set up by a fire outside the shield would, if anything, tend to draw air out of the shield toward the fire.
Also, any flame front that impinged on the shield would be rapidly cooled (hence removing the ignition part of the fire triangle) by passage through 5 or 6 foot long cracks or small holes in the concrete.
Q.9. What about the combustibility of graphite? ,
i A.9. Graphite is considered a non-combustible material; it !
\
does not support combustion under any ordinary conditions. !
For example, consider the graphite electrodes used in
\. -
the common (all movie theaters) electric are light.
{
i When the electric current is flowing, the tips of the 1 I
- graphite electrodes are at 5000-6000 degrees [. When the current is turned off, the electrodes do not continue to burn. Graphite crucibles are used in high temperature (several thousand degrees Farenheit) metallurgical work and they do not burn. Graphite electrodes are used for certain types of electric welding and electric arc l
9
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., . - 8-9 cutting, and they do not burn. In fact, powered graphite a
is recommended as the appropriate extinguishing agent for metal fires, inciuding uranium metal fires (see National Fire Codes, Vol. 803, 1981). Fire, as commonly pictured, is the rapid oxidation of gaseous material usually derived from the vaporization of solid or liquid materials. Note that solids and liquids do not burn. The energy from the exothermic oxidation of the gas must be sufficient to continuously vaporize the fuel source. It is essentially impossible to vaporize graphite (boiling point is approximately 8700 degrees F.) and the so called " burning" of graphite is actually a surface reaction more analogous to the rusting of iron than to burning in the sense of a self-sustaining, propagating fire. If a mass of graphite is heated to a sufficiently high temperature (appro::imately 1200 degrees F., or bright red heat) and air is forcefully directed on to the surface, the energy liberated is sufficient to cause the temperature of the graphite to l rise (R.E. Nightingale, Nuclear Graphite, 1962). If the forced draft of air is removed, or if the entire mass is not preheated, the reaction rate is too slow to cause the temperature to rise. I emphasize that a forced draft is required, not convection currents generated by
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a fire, and that high temperature preheating is necessary. A flame front directed onto a block of graphite will not ignite the graphite. This experiment has in fact been tried at the NEL with an oxy-acetylene torch and a small 0.5 inch diameter rod of dense graphite. The graphite could not be made to burn.
Q.10. Could you summar'ize your conclusions regarding fire scenarios that could damage the reactor core?
A.10. There is no credible fire scenario that could result in damage of the reactor core. For each of the three postulated fire scenarios one of the essential elements of a fire (fuel, oxygen and ignition) will be missing or the magnitude of the fire will be far too small to restilt in any damage to the reactor core.
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4 .
Se CURRICUL1JM VITAE -
1 Name: Walter F. Vegst, Jr. .
i 510 Fairview i Sierra Madre, CA 91024 i
Born: Philadelphia, PA, December 26, 1934
Title:
Director, Research and Occupational Safety University of California, Los Angeles I i
405 Hilgard Ave. 1 Los Angeles, CA 90024 Education:- B.S.E., Electrical Engineering, University of Michigan 1956
)' M.S.E..' Nuclear Engineering, University of Michigan 1957 Ph.D., Environmental Health, University of Michigan 1963 i .
Professional Experience: -
1979 to present: Director, Research and Occupational Safety, UCLA 1968 to 1979: Manager of Safety California Institute of Technology l 1971 to 1973: Manager of Safety and Security, California Institute of Technology '
1963 to 1968: Institute Health Physicist, California Institute of Technology'and Radiation Safety Officer, Jet Propulsion
. Laboratory 1959 to 1960: Supervisor, Phoenix Memorial Laboratory, University of Michigan -
l 1957 to 1959: Reactor and Laboratory Health Physicist, Phoenix Memorlal Laboratory, University of Michigan
- Consulting Experience
' Atomics International Division of Rockwell International City, of Hope National Medical Center i
Nuclear Products Inc.
Teledyne-Waterpik l
Casady Engineering Kirschner Associates Inc.
Technical Advisory Service for Attorneys Bio-Science Laboratories Genentech, Inc.
Scathern California Edison Inc.
l lrthe areas of interest include management of comprehensive safety programs such
! a, required at a large reseacch institution (academic, medical, or industrial),
.i-.v m.1 cr.sul:i y it. various areas of operational Health Physics.
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o Professional Certifications: '
American Board of Health Physics, 1966 -
Board of Safety Professionals, 1971 ~
California State, Professional Safety Engineer,1975 Registered Professional Engineer #212 -
I Professional Society Memberships:
American Industrial Hygiene Association .
Society of the Sigma Xi American Association Advancement of Science Campus Safety Association
, Health Physics Society I Professional Society Activities:
1974 - president, Southern California Chapter, Health Physics Society 1969 - Treasurer, National Health Physics Society, Midyear 4
Symposium 1979 - Registration Chairman, National Health Physics Society, Midyear Symposium .
1977 - to present, Member Program Committee, National Health Physics Society 1974-77 Member Education and Training Committee, National Health Physics Society 1973-78 Hember Panel of Examiners, American Board of Health Physics .
1975 - to present, Coordinator, National Association of Campus Radiation Safety Officers 1970-72 Member Program Committee, Western Industrial Health Conference Publientions and Papers:
" Initial Calibration of the Ford Nuclear Reactor", }2fPP 110-1, June, 1958
" Atmospheric Concentrations of Gaseous Effluents from the Ford I;uclear Reactor", }c!PP 110-4, May,1962
" Safety Analysis Report for Alpha Sources Used on Surveyor Spacccraft". Health Physics Vol. 21, pp. 301-308, 1971 -
" Computer Program for Maintaining Radioactive Source Inventories",
} !!nith Physics Vol. g, pp.44-448, 1970.
"Public Relation Constraints on Health Physics Communications",
presented at the 1969 Midyear Symposiugt of the Health Physics Society "th" .a ent of P.adtation Emergencies", presented at 1977 Southern CH r-M C& ater, t Health Phystes Society Sy pesium on E_ergency M c . 8 2.
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