ML19274D353
| ML19274D353 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 01/19/1979 |
| From: | Shriver B VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901230229 | |
| Download: ML19274D353 (98) | |
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/ UNIVERSITY OF VIRGINIA SCHOOL OF ENGINEERING AND APPLIED SCIENCE L CH ARLOTTESVILLE, 22901 V
D EPARTM ENT OF NUCLEAR ENGIN EERIN G AND ENGIN EERING PHYSICS TELEPHON E: 804-924-7136 REACTOR FACILITY January 19, 1979 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn: tr. Robert W. Reid, Chief Operating Reactor Branch #4 Division of Operating Reactors Re: License No. R-66, Docket 50-62 License No. R-123, Docket 50-396
Dear Sir:
This letter supplies additional information in support of our March 9, 1977 request for approval of an amendment to extend the expiration date of license R-66. This letter supplements our letter of December 18, 1978 and completes our response to the license renewal items identified in the enclosure to your letter of Ocotber 16, 1978.
The major items included in this letter are the Emergency Plan for the University of Virginia Reactor Facility (Attachment A), the revision to the University of Virginia Reactor (UVAR) Technical Specifications (Attachment B), and a list of changes to the UVAR Safety Analysis Report (Attachment C). These items have been approved by the Reactor Safety Committee.
In addition, Attachment D requests approval of three specific changes to the Technical Specifications for the CAVALIER which is operated under License No. R-123, Docket No. 50-396. These changes are considered neces-sary to make the CAVALIER Technical Specifications consistent with the revised UVAR Technical Specifications and have been approved by the Reactor Safety Committee.
The following additional information is provided as requested by License Renewal Items 3. (a)(1) and 3. (a)(2) of the October 16, 1978 letter.
Item 3. (a) (1) . Changes to the UVAR Safety Analysis Report to make it consistent with the present facility and revised Technical Specifications are included in Attachment C. We consider that the previous safety analyses, which were completed in 1971 to support operation of the UVAR at two megawatts, are still valid and adequate. The required maintenance of the reactor systems and planned replacement of system components are considered adequate to ensure continued safe operation of the UVAR.
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Mr. Robert W. Reid January 19, 1979 Item 3. (a)(2) . No major changes .to the UVAR are presently planned. It is anticipated that the next reactor core will use either uranium aluminide or uranium oxide fuel. In addition, the use of fuel with a lower uranium-235 enrichment than presently used may be required during the license renewal period. Since the design and safety analyses of fuel elements using the new fuel types are not complete, we are not requesting approval of their use in the UVAR at this time.
In summary, this _1 tter requests U. S. Nuclear Regulatory Commission approval of the revisec. Technical Specifications for the UVAR enclosed as Attachment B and of the changes to the Technical Specifications for the CAVALIER enclosed as attachment D. The other items included in this letter are for information. This letter completes our response to your letter of October 16, 1978.
Sincerely, B. L. Shriver, Director Reactor Facility BLS/lt Attch, cc: Dr. T. G. Williamson Mr. J. P. Farrar Reactor Safety Committee Sworn to and subscrihd Lafore mc thit lV dayof- ymg _ gg Witness mfland cad cuid u;,l,
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N'W tiotary Public fr$ced Hereon is My Albemarfe Cour5 yt. PMtary Public Seal My Commi:sion l,xpires January 21,1979 LLNA R. THORNE
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- " ; Attachment A UNIVERSITY OF VIRGINIA REACTOR FACILITY EMERGENCY PLAN January 16, 1979 TABLE OF CONTENT _S Section -Title Page I PURPOSE OF EMERGENCY PLAN 1 2 DEFINITIONS I 3 EMERGENCY ORGANIZATION 3 4 EMERGENCY RESPONSE ACTIONS 6 S ADMINISTRATIVE CONTROLS 10
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- 1. PURPOSE OF EMERGENCY PLAN This document outlines the plan for responding to potential emergencies at the University of Virginia Reactor Facility to minimize their effect on personnel, the Reactor Facility, and the environment.
To accomplish this goal, the emergency plan defines the emergency organization and general actions to be taken in response to hypothesized emergencies of varying levels of severity. Specific actions to be taken to implement this plan in the case of actual emergencies are defined in UVAR-Standard Operating Drocedures, the Safeguards Contingency Plan, and Security Plan for the University of Virginia Reactor Facility.
- 2. DEFINITIONS
- a. Reactor Rooms. The rooms containing the 2 W UVAR reactor (Room 131) and the 100 watt CAVALIER reactor (Roon G-007).
- b. Reactor Facility. The building containing tha reactor rooms, work areas, laboratorc. and offices as described in UVAR-18, Part I
" Revised Safety Analysis Report in Support of Amendment to License R-66 for two megawatt operation of the University of Virginia Reactor",
section 2.
- c. Reactor Facility Exclusion Area. The Reactor Facility and adjoining area bounded by the exclusion fence as defined in UVAR-18, Part I, section 2.
- d. Affected Area. The area beyond the Reactor Facility exclusion area in which the -limits for radioactive materials or radiation exposure to individuals are likely to exceed thosespecified for unrestricted -
areas by 10 CFR Part 20.
- e. Emergency Action Classes. The emergency action classes are methods used to define the re19tive severity of the emergency condition. The actions necessary to assess, correct and recover from emergencies are based on its severity as defined by these classes.
The Em: gency Action Classes are:
Class I. Personnel Emergency - A personnel emergency is.an accident occurring within the Reactor Facility Exclusion Area which requires the emergency treatment of one or more individuals. These occurrences may be complicated by radioactiv,e contamination of radiation exposure.
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t This class of emergency does not necessarily have an effect on the reactor and immediate operator action to alter the reactor status is not required unless it is likely that theClass I emergency will escalate to a more severe (Class III or Class IV) emergency.
Class II. Emergency Alert - An emergency alert results from situations which can be recognizeo as creating a hazard to the reactor or personnel that is not normally present. Enmples of this class of occurrence are:
- Threats to or actual breaches of security, civil disturbances or bomb threats affecting the Reactor Facility.
- Instrument readings or alarms indicating an atypical reactor operating condition which do not require immediate shut down of the reactor as defined by the UVAR Technical Specifications (UVAR-18, Part II), such as, alarm of the radiation monitor in the demineralizer room.
- Measurement of radioactivity levels of any isotope in the holding pond which exceed the limits for water in unrestricted areas specified in 10 CFR Part 20.
- Severe natural phenomena, such as a tornado alert.
- While time is available in these situations to prevent or minimize the effect of these occurrences, emergency alert conditions imply a rapid transition to the state of readiness by reactor personnel and the possible changes in normal reactor or facility operation.
Class III. Reactor Emergency - Situations which directly affect reactor safety and require immediate corrective action, but are predicted to have negligible radiological consequences outside of the Reactor Facility. Examples of these situations include:
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- Fires or minor explosions in or near the reactor rooms.
- Malfunction of a reactor safety system component while the reactor is operating.
- Activation of a local radiation monitor requiring immediate shutdown of the reactor, but which does not indicate that radioactivity in excess of the limits defined in 10 CFR Part 20 will be released outside the reactor room.
- Sudden or unexpected changes in reactivity,such as a large increase in reactor power with no control rod movement.
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Class IV - Reactor Facility Emergency - Situations which directly affect reactor safety and indicate that levels of radioactivity which exceed the limits specified in 10 CFR Part 20 for unrestricted areas may be released outside of the Reactor Facility exclusion area. Examples of these situations include:
- Measurement of radioactivity dose rates greater than two millirem per hour at the Reactor Facility Exclusion Area boundary downwind of che Reactor Facility using a portable gamma radiation monitor.
- Ralease of water from tha holding pond which contains radioactive isotopes which exceed the concentrations allowed for water in unre-stricted areas by 10 CFR 20.
- 3. EMERGENCY ORGANIZATION AND EQUIPMENT
- a. On-Site Emergency Organization. The on-site emergency organization shall consist of the following persons, listed in order of their position in the chain of command in the event cf an emergency.
- 1) Director of the Reactor Facility '
- 2) Reactor Supervisor
- 3) Health Physicist or the senior member of the Radiation Safety Office.
- 4) Senior Reactor Operators
- 5) Licensed Reactor Operators at the Facility.
The Director of the Reactor Facility shall take charge of all operations and coordinate efforts to assess the severity of an emergency and determine corrective and protective actions to minimize the effects of the emergency. The reactor supervisor shall assume the duties of the Director if the Director is not present.
The Health Physicst shall ensure that the emergency equipment is available for use during an emergency, determine whether any radio-activity has been released during the emergency, and recommend to the Director actions to minimize the effect of the emergency.
Other members of the on-site emergency organizatien shall assist in minimizing the effect of the emergency as requested by the Director or defined in specific procedures. All reactor operators are qualified in the use of radiation detection equipment.
- b. Off-site Emergency Organizations - The following organizations will respond to an emergency at the Reactor Facility if needed:
- 1) The University of Virginia Medical Center has agreed to accept and treat personnel injured at the Reactor Facility. Actions to be taken are ide.. tified in a Radiation Emergency Plan which was prepared by the hbdical Center. The bbdical Center can be contacted by telephone and two way radio through the University Police Department.
- 2) The University of Virginia Police Department has agreed to respond to emergencies at the Reactor Facility. Actions to be taken are identified in the Response Procedures for the U. Va.
Reactor Facility which were. prepared by the University Police Departmen t. The University Police can be contacted by telephone or two-way radio.
- 3) The Charlottesville-Albemarle Rescue Squad has agreed to provide on-site medical aid and transport injured personnel to the University Medical Center. The Rescue Squad can be contacted by telephone and two way radio through the Unisersity Police Department.
- 4) The Charlottesville Fire Department will respond to emergencies
. .. at the Reactor-Facility. -The Fire Department can be contacted by telephone.
- 5) The Charlottesville City Police Department will respond to emer-gencies at the Reactor Facility. The Police Department can be contacted by telephone. -
- 6) The Albemarle County Police and Virginia State Police can also be contacted if additional police assistance is needed.
- 7) The Virginia Office of Emergency Services and Oak Ridge Region Coordinating Office for Radiological Emergency Assistance can also assist in the event of a Reactor Facility Emergency. These offices can be contacted by' telephone.
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- c. Emergency Equipment. Equipment which can be used in the event of an emergency is available at the Reactor Facility and other sites as follows:
- 1) Reactor Facility
- fixed radiation monitors as required by the UVAR Technical Specifications.
- portable radiation monitors for detecting neutron, gamma and charged particle radiation.
- multichannel analyzers for determining specific radioactive isotopes present and the absolute level of radioactivity.
- emergency first aid equipment.
- portable fire extinguishers.
- telephones.
- two-way radio for contacting dhe University Police.
- 2) Rescue Squad Ambulance
- emergency first aid equipment.
- basic and advanced life support systems.
- 3) Physics Particle Accelerator Building (located about 400 feet southeast of the Reactor Facility)
- portable radiation monitors.
- telephones.
- 4) University of Virginia Medical Center (located about two miles from the Reactor Facility)
- complete medical facilities.
- portable radiation monitors.
- 5) Radiation Waste Management Facility (about two miles from , Reactor Facility)
- portable radiation monitors and dosimeters
- multi-channel analyzer
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- 4. EMERGENCY RESPONSE ACTIONS
- a. Class I - Personnel Emergency - Immediate action will be taken to determine the number of people injured,. the nature and severity of the injury, provide medical aid, and determine whether the accident has any potential for affecting operation or safety of the reactor.
The person 'first aware of a personnel injury should immediately contact the Reactor Supervisor or Facility Director using the Facility public address system or other method. The Reactor Supervisor or Facility Director will notify the Health Physicist and Rescue Squad.
If necessary, emergency first aid will be administered pending arrival of the Rescue Squad. The level, if any of radioactive contamination will be measured by the Health Physicist or other person qualified in radiation detection.
Actions to be taken in the event of a personnel emergency are de-fined in UVAR procedure 12 " Emergency Procedures."
- b. Class II - Emergency Alert - Immediate action will be taken to deter-mine the nature and possible consequences of the potential emergency.
Based on this information corrective action necessary to minimize the adverse effects of the situation will be defined.
To accomplish this objective, anyone aware of a situation which may affect the reactor safety or safety of personnel at the Reactor Facility will notify the Facility Director and Reactor Supervisor. The Reactor Director will determine response actions, such as securing the reactor and monitoring for radioactive effluents, based on the available inform-ation and cons.ultation with . members.of the emergency team as considered necessary.
While the broad spectrum of emergency alerts precludes definition of specific actions in all cases, procedures for several possible situations which may affect reactor.or personal safety are contain'gd in UVAR and CAVALIER Procedures 11 " Procedures for Abnonnal Conditions" and 12 " Emergency Procedures." The Reactor Facility Security Plan and Contingency Plan also include procedures for possible alert conditions, such as bomb threats.
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- c. CLASS III - Reactor Emergency - Immediate action will be taken to. shut down the reactor and;if high radiation levels are present to evacuate the reactor facility and secure all openings to the outside.
After the reactor shut down the zaactor operator will notif'y the 1
Reactor Supervisor or Facility Director who will notify other ,
members of the on-site emergency organization. The Health Physicist, or other qualified person, will make radiation measurements inside the Facility to determine what areas, if any, have high radiation levels.
As soon as possible the Health Physicist, or other qualified person, will make radiation measurements outside of the building to determine
- whether a Reactor Facility Emergency exists.
The criteria for re-entering the Reactor Facility are defined in Section e, below. Specific procedures to follow in the event of a Reactor Emergency are included in UVAR and CAVALIER Procedures 11
" Abnormal Conditions" and 12 " Emergency Procedures."
- d. CLASS IV - Reactor Facility Emergency - Action will be taken to determine the source, magnitude and affected area by the release of radioactive material. Personnel within the affected area will be in-
. - - - - _ _ . formed that radioactive material has been released and protective ._
actions defined. Access to the affected area will be controlled by the Police. If the source of the radioactive release is the reactor, it will be shut down and the building evacuated.
. - The on-site emergency organization, the University Radiation Safety Office,and the University Police will be notified in the event of a Reactor Facility Emergency. Members of the Radiation Safety Office, or other qualified personnel will make radiation measurements to determine the extent and level of airborne and other radioactive releases and to determine when the levels of radioactivity released have decreased to acceptable icvels, o >" " " " '
The University Police shall notify all personnel within the area where radioactivity levels in excess of two millirem per hour exist or areas where other limits for unrestricted areas are likely to be ,.
, - . .. . . . exceeded. .In~the event of -a-major release which precludes = timely"* "' i determination the aff'ected area, personnel within 2000 feet of the
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Reactor Facility in the downwind sector (one sector covers 22.S degrees) and the two adjacent sectors will be notified.
The most likely -protective-action to be taken will be to inform personnel to remain inside with all windows and doors closed and ventilation systens turned off. The need to evacuate specific areas will be evaluated. Access to the offected area will be controlled by the University Police.
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Criteria for re-entering the Reactor Facility are defined in sec-tion e, below. Specific procedures to follow in the event of e Re tetor Facility emergency are provided in UVAR and C.WALIER Procedure 12 " Emergency Procedures."
- e. Criteria for Re-entering the Reactor Facility - Following a reactor emergency or Reactor Facility emergency in which high radiation levels were indicated, the Reactor Facility shall only be re-entered by the Health Physicist, or other qualified person having a portable
- radiation level measuring instrument and an acceptable personal radiation monitor, such as a dosimeter. Once a determination of the actual radiation levels has been made, areas of the facility having radiation levels below the limits established for unrestricted areas by 10 CFR 20 may be entered and used.
Entry into areas having high radiation levels for the purpose of radiation surveys, clean-up or other actions not judged to be necessary to the safety of the reactor or personnel should be planned and per-formed to limit the total dose to the whole body of any person to less than one rem. Both a film badge and a pocket dosimeter should be used to record the actual exposure.
In the event that entry into a high radiation area is considered r.ccessary for reactor or personnel safety, such as to isolate a system to reduce the release of high level radioactice materials, the entry should be planned to limit the total dose to the whole body of any person to less than 25 rem. Both a film badge and a pocket dosimeter should be used to record the actual exposure.
In cases where immediate action is necessary to save a person's life, m.. m. ...,m.m,
. . . the entry -should 'be planned-to > 1imit to less than "75 ' rem.' ' 'Both' C film" " " "' '
badge and a pocket dosienter should be used to record the actual exposure.
,, f. Methods Used to Account for Personnel - Following evactuation of the facility it is important'to account for all personnel. This will'- '
be accomplished by the following methods:
- 1) Discussions with personnel who have evacuated the Facility to confirm that all personnel in the building prior to the evacuation are accounted for.
- 2) Checking film badge racks to determine that all film badges are either on the rack or on evacuated personnel. Personnel will be instracted to keep their film badges during the evacuation instead of placing them on the storage racks. Personnel in the reactor
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building will either have film badges or be escorted- (visitors only). Since the film badge storage racks are near the Reactor Facility exits the radiation levels should be low enough to allow determination of which.. film badges are stored on the rack g following facility evacuation.
- 3) During the initial re-entry by the IIealth Physicist, cr other
, personnel, to determine radiation levels a visual check of all accessible areas will..be..made to detect personnel within the facility.
, 8. - Emergency Control Center - A central location for directing the emergency actions will,be established. The Facility Director will,normally.be .at ,the_, control, center, unless it is necessary .to be in anoth6r location to provide better control of the emergency actions. The emergency control center shall be established as follows:
.1) Personne.l. emergency,,- As.near.,to the accident location as possible
- h while ensuring that acceptable radiation levels and adequate com-
.g munications are present.
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- 2) Emergency alert and reactor emergencies not resulting in high radiation levels outside the reactor room - In the Reactor Super-visor's Office.
- 3) Reactor emergency or Reactor Facility emergency - At a location within the Reactor Facility or other location having acceptable
. . , , radiati.on,, levels, as,. determined by the llealth Physicist, or other
authorized person, and having adequate communications.
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- 5. ADMINISTRATIVE CONTROLS The following administrative controls will be used to ensure that the Emergency Plan and Procedures are useable in the event of an emergency.
- 1) A summary of emergency actions will be posted in the Reactor Facility and other buildings near the Reactor Facility. The purpose of this summary is to provide an up-to-date listing and phone numbers of key personnel on the emergency organization and off-site personnel and organizations who would participate in a reactor or Reactor Facility emergency.
- 2) The Emergency Plan and Procedures for implementation of the plan will be reviewed and, if necessary, updated by the Reactor Safety Committee during even numbered years. Changes considered necessary
. . based on the. results.of. drills .or other experience will be made. as soon as practical.
- 3) Practico emergency drills will be undertaken at 1 cast once each calendar year to test the response of the on-site emergency organ-
, , .ization. The . Facility Director .will be responsible for defining - -
the objective and details of each drill. Following the drill the on-site emergency organization will meet to critique the drill and determine whether changes to the procedures or additional personnel training are warranted.
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APPENDIX TO 'lllE UNIVERSITY OF VIRGINIA REAC'IDR FACILITY EMERGENCY PLAN Jihis appendix supplies additional information in support of the Univer-sity of Virginia Reactor Facility Emergency Plan as identified in NRC proposed Regulatory Guide 2.XX.
- 1. General building layout plans and area maps.
This information is included in the UVAR Safety Analysis Report, UVAR-18, Jart I in the following figures.
Figure II-l Aerial View of Reactor Site and Immediate Vicinity (1967)
Figure II-3 Contour Map of UVAR Site with Exclusion Fence Figure II-4 Map of Charlottesville and Vicinity Figure II-6 First Floor Plan of UVAR Section of Building Figure II-7 Mezzanine Level of UVAR Section of Building Figure II-8 Ground Floor Plan of UVAR Section of Building Figure II-9 Plans of the Nuclear Reactor Facility The building plans were also included in UVAR Security Plan which was submitted to the Directorste of Licensing on August 23, 1974.
- 2. Copies of agreement letters with offsite emergency response organizations and copics of referenced interfacing emergency plans.
The requested documents are included as attachments to this appendix.
- 3. A listing by general category of emergency kits, protective equipment and supplies that are stored and maintained for emergency purposes.
This information is included in Section 3.c., Emergency Equipment, of
, the Emergency Plan.
- 4. A listing by titic of written procedures that impicment the plans.
The titles of written procedures used to implement the plan are:
- a. For use b e the Reactor Facility Staff:
UVAR Procedure 11, " Procedures for Abnormal Conditions" UVAR Procedure 12, " Emergency Procedures"
" Emergency Actions, University r,f Virginia Reactor Facility" i
" Security Plan, University of Virginia Reactor Facility" dated August 13, 1974
" Safeguards Contingency Plan, University of Virginia Reactor Facility"
- b. For use by offsite organizations:
" Radiation Emergency Plan" which was prepared by the University of Virginia Medical Center
" Nuclear Reactor Response Procedures" which was prepared by the University of Virginia Police Department
- 5. An analysis which sets forth the basis for the emergency plan.
Based on the previous evaluations and the reactor design and safety features, it is considered very unlikely that a reactor incident resulting in significant release of radioactive material will occur. However, an Emergency Plan is considered warranted to ensure that protective and corrective actions will be taken in the event of an unforeseen incident.
Documents previously submitted to the NRC have provided evaluations of possible reactor incidents. These evaluations have provided the basis for the Emergency Plan and related procedures. Specific items which have been submitted include the following:
- a.Section IX of the UVAR Safety Analysis Report, UVAR-18, Part I and Sections X and XI of Amendment I to UVAR-18, Part I provide analyses of reactor performance during accident conditions. These analyses include discussions of possible reactor incidents and conclude that it is very unlikely that fuel element damage or release of radioactive materials would occur.
- b. Sections 4.9 and 5.4 of the UVAR Safety Analysis Report, and Section IX of Amendment 1 to UVAR-18, Part I discuss the basis for and evalu-ation of airborne effluents from the Reactor Facility. Those analyses concluded that the offsite exposure due to airborne effluents were less than the 10 CFR 20 limits, even when conservative assumptions were used.
,. c. The University of Virginia Reactor Facility Security Plan and Contin-
- gency Plan. discuss possibic incidents affecting reactor security and the basis for response procedures.
Additional items relevant to the Emergency Plan are as follow:
- d. The format of the Emergency Plan, including the definitions of the various levels of emergencies were based on NRC proposed . Regulatory Guide 2.XX and proposed ANS Standard 15.16.
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- e. The use of a dose rate of 2 mrem /hr at the down wind boundary of the Reactor Facility exclusion area for determining whether a Reactor Facility emergency exists is based on the criteria contained in 10 CFR Part 20 and in the U.S. Environmental Protection Agency
" Manual of Protective Action Guides and Protective Actions for Nuclear Incidents", EPA-520/i-75-001.
Specifically 10 CFR Part 20.105 limits the whole body exposure to 500 mrem per year in unrestricted areas, 2 mrem in one hour or 100 mrem in 7 days. The limit of 2 mrem /hr meets the second-of these c rite ria. Corrective actions can be taken following an incident to ensure that the other criteria are not exceeded.
Figure 5.2 of the GPA-520/1-75-001 shows the dose to the thyroid resulting from the release of radioiodine, which is the limiting, gaseous fission product , to the measured dose rate and exposure time.
For an measured dose rate of 2 mrem /hrof r one hour the dose to the thyroid is less than 500 mrem. This is well below the limit of 15 rem identified in " Basic Radiation Protection Criteria", NCRP Report No. 39, issued by the National Council on Radiation Protection and Meas ures .
- f. The corrective actions to be taken in the event of a Reactor Facility emergency are consistent with or more conservative than those identified in Table 5.2 of EPA-520/1-75-001. These actions include additional monitoring of locations beyond the site boundary since significant dilution of radioactive effluents will occur before they reach area routinely occupied by the general public.
- g. The criteria for allowing reentry into the Reactor Facility following an incident are based on 10 CFR Part 20 and EPA-520/1-75-001. 10 CFR Part 20.101 limits the routine whole body exposure to 1-1/4 rem per calendar quarter to workers in restricted areas. The 1 rem limit for personnel providing surveys or cican up work is consistent with the 10 CFR 20 limit. The use of higher allowabic doses for emergency corrective actions necessary to reduce the severity of the incident or lifesaving is consistent with the guidelines contained in Table 5.2 of EPA-520/1-75-001, r.
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CIIARLOTTESVILLE ALBEMARLE RESCUE SQUAD, INC. u-A VOLUNTEER, Nox PRor:T ORCANIZATION '
P. O. Box 160 - CirAr.LoTTESVILLE, VIRCINIA 22902 ,,
E.TIERGENCY PIIONE 295 1191 Des NESS ParoNE 296-1825 SouAo IIoC5E PitoNE 296-1825 luol OFFICERS PREstDENT LARRY W. CLAYTOR VICE PRESIDENT ROBERT B. JASKIEWICZ SECRETARY EMitv C.rLEET January 5, 1979 TREASURER CLAUDIA BRYNER SQUAD SURGEON WHITE McK. WALLEN BORN M.D.
- 8 REGISTERED AGENT J AMES HARRY MICH AEL. JR. Reactor Facility CAPTAIN Department of Nuclear Engineering JOSHU A L. PRITCHETT and Engineering Physics ist LIEUT EN ANT University of Virginia
- * " " * ' * " ' "' charlottesville # Virginia 22901 2No LIEUTENANT L. DAYTON H AUGH 1st SERGEANT LEWIS D. POUND Dear Dr. Williamson-2ND SERGEANT WILLI AM E. NELSON
"",[,'*E3 * * "U^R ETr Your letter to Dr. Wallenborn was presented at MOTOR SERGEANT the Charlottesville-Albemarle Rescue Squad Board ROsERT s. JASkitwicz meeting on Tuesday, Janua'ry' 2, 1979.
SCUB A SERGEANT C'^" ' ^ * " * " ' " The Directors agreed that the Rescue Squad will treat
' " ,,^ ' " ' , " o p[3u o injured personnel at the Reactor Facility a'nd transport them to the University of Virginia Medical Center if DOARD OF DIRECToRG CtauDi A oRYNER n cessary.
LARRY W. CLAYTOR
- ' ' " Thank you for your interest in this o'rganization.
S CR GEORG E DANSEY. JR. If We may be of help to you in the future, please do T"ca^5 >. DuDtEv not hesitate to ask.
EMILY C. FLEET THEODORE F. HOLLID AY RODERT D. J ASKIEWICZ s.DWIN L E A KE. JR. f*
CH ARLES W. MILLER. M D. SincerO1.#
/ er JOSHU A L. PRITCHETT VHITE McK WALLENDORN. M D.
Emily Chwning eet ADVISORY DoARo 34gG EDDiE oAiN g 2.p g
Secrgtary JOSEPHINE P. FLOOD A. H. H AWKINS. JR. y WILLt AM R. HILL T g FR ANK P. HUNTER. JR. .
N gy K. K. KNICKERDOCKER CEORGC N. MILLS FHILLIP MORTON #
JOHN S. PANNELL g HE RG ER T A. PICKFORD k g ROGER R. RINEH ART. JR. g3 M. FR ANK RITTER LESLIE C. RUDOLPH. M D.
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CC hV WILLI AM W. STEVENSON DAVID V. ST RIC,ER. M D.
UNIVERSITY OF VIRGINIA DEPARTMENT OF POLICE OFFICE OF THE L'rsECTOR 412 BRANDON AVENUE CH ARLOTTESVILLE. VIRGINf A 22903 January 11, 1979
- Mr. Bryce Shriver Director of Reactor Facility University of Virginia Dear Mr. Shriver; This is to inform you that the University Police Department will continue, as it has in the past, to respe,nd to any emergency requests for assistance at the Reactor Facility, f Enclosed is a copy of our General Order 979-2 " Nuclear Reactor Response Procedures." which outlines our response for routine and emergency situations.
1 Enclosed also is a copy of the relevant portions of a reciprocal agree-ment made between the City of Charlottesville, Albemarle County, t-he University of Virginia and others for mutual assistance under Virginia code, Section 15.1-131.
This Mutual Aid Pact has been in existence for over three years. It has been invoked on 2 or 3 occasions and the response has been immediate and continuing.
Sincerely yours,
,d/.4 L Frank W. Johnstone Director FWJ:mlb Attachments s
,' IVEIGITY 0 . VIRGINIA POLICE DEPARTMENT DATE OF ISSUE EFFECTIVE DATE N3, 1/]/79' GENERAL ORDERS
.. _ 79-2_
SUIUECT AMfM . '
Il_U_CLE AILREACTOR__RESEO NSE_2RO CE Di t R E -
REFERlWCE -
RESCINDS
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1.0 PURPOSE Ol' :Tile RESPONSE PLAN _ .
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TO ESTABLISH PR0bbDURbS AND GUIDELINES fd Bb FdLLOhED bh PdLkbE-0FFICERS It. THE FOLLOWING CONTINGENCIES.
- 1. NORMAL P kOL bHbbKb bF RE bTdk F bILkTh.
- 2. BOMB THREATS 3.UNAUfHORIZbDbNTRhINT5MkTERI L.AbbEdd.hkE (tiAA)
II. CI.VIL. DISORDERS . .
- 5. ACCfDEtJTSf FIRES, OTHER EMERGENCIES REQUIRING TRAFF.I.C CONTROL'
- 6. !!0 STAGE SITUATI0tJS 1.1 SEG_URITY PROGRAM AT U VA. R'EAE'TORFEiLIT .
1.11 TiiE PRIMARY PURPOSE OF TIiE SE, CUR 1TY, PROGRAM A,T,THE,,,UVA , ,
REACTOR FACILITY .IS THE PROTECTION O.F. SPECI AL. .NUCL. EAR.MA.T.ERI.AL..(
At1D PLANT FACILITIES AND THE PREVENTION OF . SABOTAGE WHICH COULD i CAUSE RADIOLOGICAL RELEASES.
.1.12THIhISPRIMkRILY_THERESPONSIblLifh.kND,fkISSIdt bk,ibE REACTOR STAFF DURING Tile fl0RMAL WEEK. , TrieUNIVERSlTYfolICE , .
Deer. Wit'L SuePORT TnE REACTOR STAFF.,.DURING THE,fl0RMAL Vf0R,K,,
WEEK AND WILL PERF,0RM LIMITUD SECURITY FUNCTIONS AT f1IGHT, ON WEEKErlDS AND ON HOLIDAYS. g.3 1.13 Tile SEbuRIhh PROGRAM ,IS kIDED bh tj 'kbbESh-EGREsd ,bothTRdL. ,
SYSTEM TliAT OPERATES . I N CONJ. UN. CT. I ON. _ W. 1.TH P. HY.S I C AL B AR R I E..R.S AN D ALARM SYSTf.:MS CONCERNING SECURITY AREA, PROTECTED AREA AND MATERIAL ACCESS AREAS.
s
2.0 EV.ERLS_ Rep uj alludOL LC_e_8 E _Srp0gSE, 2.1 NORMAL PATROL CliECKS OF REACTOR FACILITY.
2.11 ESCAPE MANHOLE (A ON MAP) LOOK FOR SIGNS OF ENTRY OR EXIT.
2.12 MAIN ENTRANCE (B ON MAP) LOOK FOR SIGNS OF FORCED'Et1TRY, UNLOCKED. DOOR, BROKEN OR CRACKED GLASS, NO NIGHT LIGHTS, ETC
. < .. , ~ , ; -
. 2.121 CHECK'UVAR (MAlti liEACTOR) ROOM D0OR WHIcH IS VISIBLE THROUGli MAIN, ENTRANCE. THE STEEL BAR DOOR SHOULD BE LOCKED AT ALL~ TIMES. IF FOUND UNLOCKED,
, HAVE DISPATCHER CALL AN ,AUTil0RIZED PEPSON (DIRECTOR, REACTOR SUPERVISOR OR SENIOR OPERATOR) TO INVESTIGATE.
2.13 CAVALIER ROOM WIND 0ws (C ON MAF-WEST SIDE) LOOK FOR SIGNS OF FORCED ENTRY, CLOSED BLINDS, NO NIGHT LIGHTS, BARS REMOVED OR SAWED THROUGH. .
2.14 FUEL STORAGE . ROOM (D ON MAP-GROUND FLOO,R-WEST SIDE) LOOK ,
FOR SIGNS OF FORCED ENTRY', NO NIGHT. LIGHTS, CllE,CK'0UTSIDE _
DOORS.& WINDOWS FOR SIGNS,0F TAMPERIN,G,,, FORCED EN,TR,Y. _ -
~2.15 UORK SCHEDULES ARE NORMALLY_ CONTROLLED ,
T,, ,O MINIM}ZE ENTRY INTO UVAR ROOM, CAVALIER , ROOM,AND FUEL STORAGE,,RO0M , ,
AFTER NORMAL HOURS. _IF AN'(ONE IS SEEN ENTERING ,0R_ . _,
ATTEsPTING TO ENTER TilESE AREAS AFTER HOURS, DETAIN AND MAKE POSITIVE IDENTIFICATION., IFPE.RSONWILLNOT'[ .
PROVIDE IDEf1TIFI, CATION, ARREST FOR TRESPASSING AND fl0TIFY SHIFT COMMAflDER.
'2.16
~
RECORD LICEf4SE flUMBERS .0F ANY SUSPICIOUS VEllICLES PARKED IN AREA OUTSIDE OF SECURITY FENCE.
2.17 GET ao_S_ILLV_E _LDEt4LIHCAILOR OF ANY SUSPICIOUS PERSON INSIDE SECURITY FENCE AFTER tJORMAL WORKING liOURS.,, ,
2.171 .IF POSITIVE IDENTIFICATION IS NOT POSSIBLE, NOTIFY SilIFT COMMANDER AND DETAIN SUSPECT..- -.
2.172 IF PERSON IS f.10T COOPERATIVE, ARREST FOR TRESPASSIf1G.
2.18IFANOUTSIDED0bR;ISFbUh1D..bNb[.THEPbLibE.dFFibERWI L ~
STATION HIMSELF -0UTSIDE AND. NOTIFY DISPATCHER. W110-WILL.
NOTIFY AN AUTFORIZED INDIVIDUAL WHO .WILL E iTHER CALL:~TiiE' '
FACILITY -T0 IDENTIFY WHO -IS IN.THE BUILDING OR-COME TO..
Tile FACILITY Af1D SEARCH THE-BUILDING. BEFORE SECURING THE DOOR. .fHE OFFICER WILL REMAlf1 OUTSIDE THE DOOR UNTIL BUILDING IS SECURED.
7D N D 'S 0 l{h 'p fw d 1L.A A
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2.181 IF ANYONE ATTEMPTS TO LEAVE Tile BUILDING BEFORE Tile REACTOR STAFF MEMBER AUTl10RI7.ED IT, S/IlE SHOULD BE DETAINED UNTIL POSITIVELY IDENTIFIED.
2.182 IF PERSON IS NOT COOPERATIVE, ARREST FOR TRESPASSING AND NOTIFY SillFT COMMANDER. -
2.2 BonB_IvREA1S_ . ..
..,,,7 .
2.21 IF TilREAT ORIGINATES WITil REACTOR STAFF, TilEY WILL MAKE EVALUATION AND DECis10N FOR FURTilER ACTION IN ACCORDANCE WITH
~~
TilEIR PROCEDURES. .
2.22 IF TilREAT IS RECEIVED BY POLICE DEPT., IT WILL BE RELAYED AS SOON AS POSSIBLE TO A SENIOR REACTOR MEMBER Wl10 WILL EVALU_ ATE AND MAKE Tile DECISION TO TAKE FURTilER ACTION.
2.23 IN ANY EVENT, POLICE WILL ASSIST AS REQUESTED BY SENIOR REACTOR MEMBER.
2.211 IF DECISION IS MADE TO SEARCll REACTOR FACILITY, THE POLICE DISPATCHER WILL ALERT THE CllARLOTTESVILLE POLICE AND ARMY I30MB SOUADS TO GO ON STAND-BY ALERT.
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2.25'IF ANY EXPLOSIVE OR INCENDIARY DEVICE IS FOUND, T R APPROPRIATE AGEtlCY'SBOMBSQUADWdLBEREQUESTEDTOREMOVEORIMMOBILIZE.
2.26 IF A FIRE OR EXPLOSION OCCURS, SEE SEC. 2. 5,2. 6 2.3 NUAUTILORIZED ENTBLINJ_0_IlATERIN ACCESS AREA 2.31 DuRING NORMAL WORKING ll0URS (8AM-SPM) Tile POLICE WhLL RESPOND IMMEDIATELY TO AN INTRUSION ALARM OR TO A DIRECT REQUEST FOR ASSISTANCE FROM A STAFF MEMBER WilETilER BY Pil0NE OR RADIO (39.5).
2.32 DURING NON-WORKING ll0URS (SPM-3AM) Tile POLICE, DISPATCHER WILL t10N I TOR INTRUSION ALARMS, Pil0NE AND RADIO. PATROL UNITS WILL BE DISPATCllED IN ACCORDANCE WITl1 EXISfING PROCEDURES AND Tile
'.' SillFT COMMANDER WILL BE NOTIFIED IMMEDI ATELY.
2.33 IF AN INTRUSION ALARM IS ACTIVATED AT IllE DISPATCHER'S OFFIChi, S/llE SilALL DISPATCH OFFICERS TO COVER ALL BUILDING EXITS AND NOTIFY SillF T COMMA'NDER AND Tile AU fl10RIZED INDIVIDUAL WHO SilALL COME TO Tile REACTOR FACILITY. , , , , ,
2.331 ADDITIONAL OFFICERS WILL BE SENT TO ASSIST-REACTOR STAFF' IN SEARCll 0F SECURITY AREA WillCli HAS BEEN VIOLATED. IF ANY.
UNAUTl10RIZE0 INDIVIDtlAL IG FOUND IN FACILITY, S/llE SilALL BE ARRESTED. ,
w w . _a
0 2 . 11 Cl V il .DI S.OR DE RS.
- 2. Ill POLICE WILL BE fl0TIFIED BY REACTOR STAFF 0F SUSPECTED f!ATURE OF DISORD!iR. DISPATCilER hlLL fl0TIFY SilIFT COMMANDER AllD F01. LOW USUAL fl0TIFICATION PROCEDURE.
2.ll2 IF Tile DISORDER IS VIOI.EN T, .CilARLOTTESVILLE POI. ICE DEPT.,
$1.BEMARLE COUtiTY SilERIFF'S OFFICE AND STATE POLICE WILL BE NOTIFiliD AND A COMMAtlD POST ESTABLISilED (AS NECESSITY AND CIRCUMSTAllCES REQUIRE). '_~
2,l121 POLICE WILL SECURE Al.l. ACCESS PolNTS INTO REACTOR FACILITY.
2.l22 l OniER OFFICERS WILL ATTEMPT TO REMOVE GROUP TO A POINT OUTSIDE OF SECURITY FEflCE AND WILL CLOSE GATE ACCESS TO ROADWAY.
2.l 23l ARRESTS WILL BE MADE ONLY FOR SPEC _IfjC OFFENSES..
~
2.!!3 IF Tile DISORDER I S' NON-VI OLEllT, Cll'VILLE POLICE DEPT.,
ALBERMARI.E CO. SuliRIFF'S DEPT. AND STATE POLICE WILL BE ADVISED AND KEP f IflFORMED.
2.ll31 POLICE WII.L SECURE Al.l. ACCESS POINfS IilTO REACTOR FACILITY.
2 Il32 OTiiER OFFICERS WII.I. ATIEMPT TO REMOVE CROWD TO A PolNT GUTSIDE OF SECURITY FEtlCE AND WII.L CLOSE GATE ACCESS TO ROAD'.!AY.
2.'l33 ARRiis rS WILT. BE MADE ONI.Y FOR SPEC I F 1C_ OEI!.EUSliS.,
2.5 ACC l oEN rS,_ F I RES ,_0RIER30GENCJES]EOUJ R I NG [R AF F.I C1CODTROI 2.51 IF NEEDED OR REGUESTED, . POLICE WILL CONTROL TRAFI IC (VE,ilICULAR AND PEDESTRIAN) ON ROADS 1.EADillG TO REACTOR FACILITY TO FACILITATE EMERGENCY VElllCl.E FI.0W.? -
2.S2 IF ADDITIONAL ASSISTANCE IS REQUESTED, CHARLOTTESVILLE Pol. ICE DEPT. WII.l. BE NOTIFIED.
f
- 2. 6 0._I l3 BO Rfl.E _. RAD I_0ACJ_I Vli IkEl.liAsti IF IT IS DETERMillED TilAT AN AIRBORNE RADIOACTIVITY,REl.IIASE !!AS OCCURRED OR IS IMMINENT, UNIVERSITY POLICE WILL NOTIFY PERSollNiil IN Tile AFFLICTED. AREA (2000 FT. RADIUS) AND PROVIDli INSTRUCTIONS TO MINIMIZE Tile !!FFl[CT ON-Tile' PUBLIC. .
TiiE INSTRUCTIONS TO BE GIVEN WII L bE DliTERMIf1ED BY RiiACTOR' DIRiiCTOR OR lilS AGENT AS CONDITIONS WARRANT.
INSTAL.l.ATIONS WITilIN Till: 2000 FT. RADIUS AREA INCL.UDE Tile ORDNANCE l .A13, RADi0 ASTRONOMY 81.DG., IllNERAL RESOURCliS & FORESTRY BLDG.,,_
UNIV. [lAlflTEilANCli $110P AND ALDERMAN RD. DORMS Es.ENDING 10_ SCOTT STADIUM.
2.61 Al.L ROADS l_EADING INTO Tile 2000 FT RADIUS WILL BE BLOCKkiD BY Pol. ICE UNTIL Tile EMERGENCY IS OVER, 2.62 l'lllEN T!!!! EMERGENCY IS OVER Tile, RADIATION SAFETY OFFICEI OR DIRECTOR OF Tile FACil.ITY Wil'L NOTIFY Tile UNIVERSITY POLICE.
Tili UNIVERSITY Pol. ICE WIU. NOTIFY OTilER ORGANIZATIONS OR INSTAL.l.A fleMS TilAf Tile EMERGENCY IS OVER.
2./lIOSFAG.E...SI.TifATIONS.
2./l IF ADVISED 03 AWARE OF A ll0 STAGE S1I UAiION INV01.VING A REAC f 0R STAFF MEMBER OR FAMILY MEc'BER OF Tilli REACTOR. STAFF,,
l'IlE DISPATCllER WILL NOTIFY SilIFf COMMANDER AND FOLLOW USUAL NOTI.FICATION PROCEDURES. ,
2./2 REFER TO Il0 STAGE PROCEDURES.FOR DEfAILS. , .
9 e-J_QO u c . . \. E :3
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i hol @l#; $].d} o I
MUTUAL - AID AGREEMENT I l
This agreement, diade and entered into this day, 1 July 1976, by and between the political subdivisions of the State of i Virginia, who.are signatories hereto.
{
WHEREAS, these political subdivisions of the State of '
Virginia have determined that the provisions of law enforcement mutual aid acrcss jurisdictional lines in emergencies will ,
increase their ability to preserve the safety and welfare of i their citizens; and I
WHEREAS, these political subdivisions of the State of Virginia are authorized by the Code of Virginia, Section 13.1-131 to provide mutual aid; and WHEREAS, the governing body of each of th'ese political
, subdivisions of the State of Virginia who are signatories hereto l 1 have adopted resolutions authorizing the execution of this ,
[ reciprocal agreement, certified copies of said resolutions being i
' hereto attached,
- NOW, THEREFORE, the parties hereto do agree as follows:
ll 1. When a state of emergency resulting from the existence .
p of a state of war, internal disorder, or fire, flood, epidemic i
[ or o ther public disaster exists within the boundaries of any of i i the parties hereto, the party or parties shall notify the other
{ party or parties to this agreement of such emergency and its Such assistance shall be rendered according to the procedures established in the opera-
[l need for law en forcement assistance.
tional plans developed and agcced to by all of the parties to this agreement pursuant to the provisions in para $raph 2 herein.
t l 2. The mu tual assistance to be rendered under this agree-men t , hall be available upon the development and approval by l Lhe pa ctics here to of. an opera tional plan. The plan shall ou tline the exact procedure to be followed in requesting and l
' responding to a request for assistance. Upon execution of e.
this adreement, the parties hereto shall designate an appro- !
priate official in each jurisdiction to participate in the !
development of the operational plan. The parties shall meet l at least annually to review and, if necessary, to propose '
amend!.wnts to the opera ticnal plan. Ariy proposed amendments i shall not be effective until approved in writing by all the i
, parties to this agreement.
0 3 The services performed and expenditures made under this l agreement shall be deemed for public and governmental purposes.
!,1 All im... unities from liability enjoyed by the local political cubdivision within its boundaries shall extend to its part;ici-
'i pation in rendering mutual aid under this agreement outside its boundaries unless otherwise provided by law. * .
Each party to this agreement shall waive any and all
- I claims against all the ot.her parties hereto which may arise j; out of their activities outside their respective jurisdictions ,
while rendering aid under this agreement. -
h Each party shall indemnify and save harmless the other -
t parties to this agreement from all claims by third partied for .
propenty damage or personal injury which may arise out of the :
activities of the other parties of this agreement ouside their respective jurisdictions while rendering aid under this agreement.j, I '
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- 4. All the immunities from liability and exemptions frcm laws, ordinances, and regulations which law enforcement officers employed by the various parties hereto have in their own juris-dictions shall be effective in the j,urisdiction in which they are giving assistance.
All compensation and other benefits enjoyed by law enforce- .
ment officers in their own jurisdictions shall extend to the services they perform under this agreement.
- 5. Law enforcement officers rendering assi Lance under this agreement shall do so under the direction nd control of the appropriate official designated by the jurisaiction requesting the aid.
The parties shall notify each other of the name, address, and telephone number of the official authorized to direct mutual aid activities within their jurisdiction.
- 6. This agreement shall remain in effect until terminated by all the parties hereto upon written notice setting forth the data of such termination. Withdrawal from this agreement by any one party hereto shall be made by thirty days' written notice to all parties but shall not terininate this agreement among the remaining parties. -
IN WITNESS WIIEiiEOF, the parties hereto have executed this a6reement as of the date first above w> itten.
~
City f Charlottesville Cou iM by[* fr. \ ! a , $ca.u) by C hN^ J title date Meiyor June 1 1976
[iN dat'e
'h u vr.mn
,Inty_1g .1976 Cour y of Albemnr'l C n nty of Nelson lLYbtd _
~ " e titic_ chairman tle ke /g4 #b date Fay 24, 1976 date /[- # 74 County of Creete The-University of Virginia by_Y UA&D gg b ,
If. Ib \%v ( ...
titlh Chairman title President date June 5, 1976 date July 28, 1976 County of Fluvanna by E'.e.9 W -r- A D ]# IV *D'T}
D ti tle Cha_i rman o - A =
, date._Jiule 7. 1976 ll ,
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C PRELD11 NARY COPY OF PARTS I AND II RADIATION EMERGENCY PLAN UNIVERSITY OF VIRGIt:1 A MEDICAL CENTER f.
R.iili.it ion 1:nwr,a ncy Plan Commit tec L'nivers i ty of Virgin ia ?!cilical Center Ch.i r lot t esv i l l e, Virginia 1918 q ' ~T g D aa i
< m 6 e) J
RADIATION EMERGENCY PLAN, '
UNIVERSITY OF VIRGINIA Il0 SPITAL ,',
Contents P_a ge, I. Overview of the Radiation Emergency Plan . . . . . . . . . . . . . . 1 II. Prehospital Radiation Emergency Plan A. Prehospital Plan (Diagramatic Flow Chart). . . . . . . . . . . . 2 B. Cencral Information. . . . . . . . . . . . . . . . . . . . . . . 3 C. Decontamination Procedures of Patients . . . . . . . . . . . . . 5 D. Transport. . . . . .. . . . . . . . . . . . . . . . . . . . . . 6 E. Map of Entrance to Controlled. Area and Radioactive Waste !!anagement Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 F. Decontamination of Equipment and Rescue Personnel. . . . . . . . 8 III. llospital Radiation Emergency Plan. . . . . . . . . . . . . . . . . . 9 A. Notification Procedure . . . . . . . . . . . . . . . . . . . . . 9
- 1. Radiation Emergency Calling Chain. . . . . . . . . . . . . . 11
- 2. Criteria for Activation of Radiation Emergency Plan. . . . . 12 B. Controlled Area Floor Plan - University of Virginia llospital . . 13 C. Supplies for Radiation Accidents . . . . . . . . . . . . . . . . 14 D. Patient Management Procedures. . . . . . . . . . . . . . . . . . 16
- 1. Receiving. . . .. . . . . . . . . . . . . . . . . . . . . .
16
- 2. Triage and Tagging . . . . . . . . . . . . . . . . . . . . . 16
- 3. Decontamination. . . . . . . . . . . . . . . . . . . . . . . 16
- 4. Energency Team Member Responsibilities . . . . . . . . . . . 18
- a. General Information. . . . . . . . . . . . . . . . . . . 18
- b. Specific Inforr,ation . . . . . . . . . . . . . . . . . . . 20
- 1) Admissions . . . . . . . . . . . . . . . . . . . . . '20 9
,2) Clerk - E.R. . . . . . . . . . . . . . . . . . . . . 20
- 3) D! rector . . . . . . . . . . . . . . . . . . . . . . 21
- 4) llospital Administrator . . . . . . . . . . . . . . . 21
- 5) llousekeeping . . . . . . . . . . . . . . . . . . . . 21
- 6) !!a in t enance . . . . . . . . . . . . . . . . . . . . . 22 7)' Nursing. . . . . . . . . . . . . . . . . . . . . . . 23
- 8) Physicians . . . . . . . . . . . . . . . . . . . . . 29
- 9) Public Relations . . . . . . . . . . . . . . . . . . 32
- 10) Radiation Safety Officer . . . . . . . . . 32
l
. r I. Overview of the Radiation Emergencyl lan I
The following Radiation Emergency Plan outlines a cooperative plan among ,
the rescue squads in surrounding areas, the Radiation Safety,0ffice of the University of Virginia, . the University of Virgirif a llospital, and the
{ City of Charlottesville. The Radiation Safety Officer will' assist the rescue squad in measuring patient contamination at the accident' site and advise rescue squad personnel of radiation hazards. Following emergency treatment and preliminary decontamination, the patients will be trans-ported to the side entrance of the University of Virginia Emergency Room.
The Emergency Room and Radiological Physics personnel will prepare tc treat the contaminated patients, once they have received radio alert of their imminent arrival.
Acting on the information available, the Emergency Room senior physician and the Radiological Physicist will determine whether or not to initiate the Radiation Emergency Plan. The flow diagrams that follow outline the general conditions under which it might be deemed safe to handle minimal risk patients without activating the emergency plan. The Radiation Emergency Plan, if activated, will result in the isolation of a portion of the Emergency Room and several corridors that will be used for triage, decontamination, and initial, treatment. Designated individuals will be assigned areas of responsibility, and appropriate safety measures will be taken. At the completion of the emergency treatment, the Radiological Physicist and the Radiation Safety Officer will supervise the decontam-ination of the rescue squad and their equipment, hospital personnel, and the Emergency Room area. ,
D~"D D o o T t l2]k.. @n
.a
2 DUPLICATE .
1 .
I PRI?!ARY SURVEY - LIFE Tl!REATENING CONDkTk0if'[ YES PERFORFI BLS AND ALS~ >
ROTATING PERSONNEL
- l l .
NO, CONTACT IIOSPITAL BASE ST5 TION RADIATION SAFETY OFFICER (UNIVERSITY OF VIRGINIA Et!ERCENCY MEDICAI. SERVICES) - ENROUTE TO SCENE.
BY RADIO CO?!MUNICATION SURVEY ' ?IETER AVAiLABLE NO CONFER IIITl! RADIATION SAFETY OFFICER PRIOR TO RENDERING TREATMENT OTllER TIIAN BLS AND ALS Y P,S
........l...
LEVEL OF RADIOACTIVITY
< 25 REMS (TOTAL) NO -- - - - - - - - - -
YES EMERGENCY THEATlIENT ENTER AREA. DO NOT PERilIT SPECTATORS IN AREA.
REMOVE PATIENT FRO?! CONTAllINATED AREA.
?!0NITOR VITAL SICNS.
SECONDARY SURVEY - TREAT IuJURIES.
DECONTAMINATION PROCI: DURE UNDER Tile DIRECTION OF Tile RADIATION SAFETY OFFICER.
Rl; MOVE CLOTilING AND l?ASil CONTA?!INATED SKIN.
PLACE CONTA!!INATED MATERI ALS IN PLASTIC BAG.
IJRAP PATIENT IN BLANKET. e.
!!,0TIFY !!GSPITAL BASE STATION AND TRANSPORT.
/ STOP \
AT TRIAGE l l yTATION/
_ . . . . . l
]g* jD O Y [ s MONITOR RADIOACTIVITY OF PATIENTS Jo J, o
__.l._.....___.. .._ .
NO CONTAll! NATION CONTAMINATION
! . _ . .l . . _ _ ..
ROUTINE 'IRANSPORT PATIENT TliROUGil SIDE ENTRANCE
--- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
EMERGENCY R00?! ~T
^ '
l~r sil0ULDRF'URNTOTRIAGESTATIONl
n . ... n u.a a g .
(
l..... . ._.
CONTAlll!!ATION NO P.ETUlUi TO SQUAD 110USE l
YES I.._...... . .... ..
CO TO Tile RADIOACTIVE WASTE llANAGEllENT FACII.ITY FOR DECONTAtlINATION OF LQUIPllENT AND SQUAD }! Ell!!ERS_
0
_ g. . - -
--==.;._.--
n : -l. . . :. , .. .. l. .-: , .. . . . L.,m ..- ~,
- .. *L:: .
- ; .0 . ...* . .. . .. .. ..
~_.
2 PRfflOSPITAl, RADI A, TION Dti:RCINCY Pl.AN POSSIBILITY OF RADIOACTIVE CONTMl!NAT10NT 5 l
Y ES
~
PUT ON PROTECTIVE CLOT!11NG YES PRit!ARY SURVEY - LIFE TliREATENING CONDi'Tici[?] PERFORF1 BLS AND ALS l, ROTATING PERSONNEL' NO;
-.~. -- - . . --
CONTACT 110 SPITAL CASE ST5 TION RADIATION SAFETY OFFICER (UNIVERSITY OF VIRGINIA EPIERCENCY ?!EDICAL SERVICES) ENROUTE TO SCENE BY RADIO CO?DIUNICATION
[SURVEYh!ETER kVAILEBI.h NO ' CONFER WITl! RADIATION SAFETY OFFICER PRIOR TO RENDERING TREAT?!ENT OTilER TilAN Bl.S AND ALS YS LEVEL OF RADIOACTIVITY
< 25 REllS (TOTAL) NO - - . - - . . -
I YES lEffERCENC[I TREATl1ENT]
. . _ _ = _ .. . _ . .
lf;NTERARCA. D0 NOT PER?IIT SPECTATORS IN AREA.
'FJ10VE PATIENT FROtt CONTAt!INATED AREA.
I!ONITOR VITAL SICNS.
SECONDARY SURVEY - TREAT INJURIES.
DECONTMIINATION PROCEDURE UNDER Tile DIRECTION OF Tile RADI ATION SAFETY OFFICER.
RDIOVE CLOTillNC AND l'ASil CONTA?flNATED SKIN.
Pl. ACE CONTA!!!NATED flATERI ALS IN PLASTIC BAC.
I! RAP PATIENT IN BLANKET. e.
t(OTI}Y ll0 SPITAL EASE STATION AND TRANSPORT.
[ 510P h AT TRI AGE yTATION/
I
@ D fl 9 ' q
?!ONITORRADIOACTIVITYOFPATIENTSl [ D](OD ) j y
. . . . _ . . . ._ b l .l -
NOCONTA>llNATIONf ' hf3NTAhlfhATION)
I *
._..J .. .
ROUT!NE E2fERCENCY R00?! l TRANSPORT PATIENT TilROUCH SIDE ENTRANCEf --*-""*
]
Dff S!!OULD RETURN TO TRIACE STATION '
I il0NITOR RAD 10kCTiVITY bF Ettr AND 0QUll'Ilr.N .
t
/ CONTMi[hATION I NO RETURN TO SQUADl!OUS I
YES CO TO Tile RADI0 ACTIVE WASTE PIANACf.?IENT FACil.ITY FOR DECONTAtlINATION OF LQUIP!!ENT AND SQUAD FIEPIDERS
. . .*.J.?;.f' .
'-1. - .2*- * *
.'{ . .. .-
...,.,........,.*.1,.,"*: .. . ,-.,.....,b
3
- 8. General Information Rescue Squad Personnel are usually the first respondera of the medical team to care for a patient with radiat. ion exposure and/or contamination.
In accidents that involve radioactive materials, suspect and treat the' patient as potentially contaminated until it is proven otherwise.
Do not let radioactive contamination compromise the care of the victim;-
life threatening emergencies are first priority. Treatment must be rendered to assure a patent airway, breathing, and to control bleeding.
If the patient is breathless or has respiratory distress, ventilate the patient with a bag-mask ventilator; mouth-to-mouth ventilation is inadvisabic unless there is equipment failure. Once the patient's con-dition is stabilized, attention can focus on the radioactive contamina-tion. If time permits, protective apparel should be worn, which con-sists of gloves, shoc covers or boots, coveralls, long laboratory coat, head cover, and face mask.
Rescue Squad Personnel should contact the hospital base station (the m
University of Virginia Emergency Medical Services.) by radio co'munica-tion. If a radiation contamination is suspected, the 11ospital Radiation Emergency Plan will be activated, based on the information received from the alerting source (i.e., University Reactor Facility, Charlottesville-Albemarle Police, Rescue Squad, Charlottesville-Albemarle Fire Depart-ment, or University Police). This information should include the number of victims, the level of contamination, and the source of radioactive material. Upon notification, the Emergency Room Charge Nurse will con-tact the Radiation Safety Officer who will report to the scene and direct the rescue procedure.
~
',' If energency care is required before the Radiation Safcty 01ficer atiives, maaitor the patient and the *:urrounding area with a beta-gamma Ceiger survey meter and/or an ion chamber survey meter to deter-mine the level of radiation. Examples of these types of instuments are:
- 1. CD V-700, 0-50 milliroentgens (mR/llr) survey meter: a low-range lustrument that measures gamma exposure rates and detects the presence of beta particles. This. instrument is designed for low-level neasurements and has limited usefulness in areas of high contamination. When the probe shield on the CD V-700
', - 4 is closed, beta particles are stopped and only the gamma exposure rate is measured. IIhen the shield is open, both gamma-rays and beta particles are detected. One particular
. operating characteristic of the CD V-700 with which the monitor shauld be familiar is " jamming" or " saturation."
Radiation exposure rates from 50 mR/llr to 1 R/ilr (IR =
1000 mR) will produce off-scale readings. However, when exposure rates materially exceed 1 R/hr, the CD V-700 may
" jam" or " saturate" and read zero or less than full scale.
.A higher-range instrument is required for measurement of exposure rates higher than 50 mR/hr.
- 2. Ion chamber survey meter: CD V-715, 0-500 Koentgens per hour (R/hr) survey meter will measure gamma-ray ~ exposure rates only and is a high-range instrument. The CD V-715 has no beta detection capability.
- 3. Response Time: Survey meters do'not respond instantaneously to changes in dose rate or to changes in the range position.
A period of at Icast fifteen seconds should be allowed for meter response before readings are observed.
The procedures for area monitoring are:
- 1. Use a survey meter such as the CD V-715. If the exposure rates are expected to be below 50 mR/hr, also carry.the CD V-700.
- 2. Take readings at about three feet (belt high) above the ground.
- 3. Record thc exposure rate, time, and location for each reading.
The procedures for patignt monitoring are:
- 1. Use a survey miter such as the CD V-700 or CD V-715.
- 2. Place the probe about six inches from the patlent's oody, being careful not to touch him. Starting at the top of the head, move the probe downward on one side of the neck, collar, shoulder, arm, wrist, hand, underarm, exilla, side, leg, cuff, and shoe. Monitor the insides of the legs, and front and back of the body. pay particular attention to.the feet, seat, elbow,' axilla, and hairy or moist areas.
- 3. Record the exposure rate, time, and location for each readi.ng.
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evaluates the degree of contamination. The relationship between total radiation exposure, exposure rate, and time is:
Total Radiation Exposure (rems) =- Exposure (rem /hr) x time '(brs)
This is also approxima'tely equal to:
Exposure (Roentgens /hr) x time (hrs)
If tbc total radiation exposure received by rescue personnel while providing aid to the patient is less than 25 rems, the personnel should wear protective apparel which consists of gloves, shoe covers or boots, coveralls or long laboratory coat, head covers, and face masks.
The following guidelines should be employed in the care of the patient:
~
- 1. Primary Survey. Treat life threatening conditions. If f.he patient is breathless or has respiratory distress, ventilate the patient with a bag-mask ventilator; mouth-to-mouth vent-ilation is inadvisable unless there is equipment failure.
- 2. As soon as possible, move the patient upwind to an area of low contamination and begin the decontamination procedure.
- 3. Secondary survey. Identify and treat other injuries. Cover the open wounds vi i sterile dressings.
- 4. Before starting an intravenous or giving medications, scrub and clean the skin thoroughly before inserting the needle; this cicansing procedure will prevent contaminating particles from being forced under the skin.
- 5. Monitor vital signs.
C. Decontamination Procedures of Patients I Af ter the patient's condition is stabilized, the following decontamina-tion procedure will be started:
- 1. Remove the patient's clothing and place it in a plastic bag.
This bag should be scaled and properly labeled " Radioactive Con t a m ina t ion. "
- 2. Decontaminate the patient using detergent, water, and brushes.
Open wounds should be irrigated with water and covered with water-proof dressing if avaiiable. If there is widespread ,
contamination and a shower facility is available, the patient 3
6
- should wash himself with a detergent while showering. .The Radiation Safety Of ficer will survey the' patient to deter-mine the Icvel of residual contamination after each washing until all significant contamination is removed. If there is no water source, the fire department hoses can be used to wash the patient. ,
3 When washing, particular attention should be given to areas where contamination may be trapped.
- 4. Place all contaminated materials in plastic bags.
5 If the patient is not ambulatory, he should be placed on a sheet prior to the removal of his clothing. Subsequently, 4
the naked patient should be decontaminated by one of the j rescue squad personnel. After decontamination, the naked patient should be covered by clear. sheets and blankets.
I To avoid contamination of equipment and other personnel, the patient should not be moved into the ambulance before decontamination unless the patient's condition cannot be managed at the scene. In the latter case, his outer clothing should be removed and placed in plastic bags along with supplies in contact with the patient.
D. Transport
- 1. After decontamination is completed, transport the patient to the Emergency Room. Advanced. notification and estimated time of arrival s important for Emergency Room preparation.
- 2. Enter the hospital side entrance, locat'd to the right of the Emergency Room. Stop at the Triage Sta ion where the Radio-logical Physicist and Tr'iage Physician .ill monitor and label the patient's level of contamination and injury.
- 3. The Triage Physician will thei. direct the transporting of the patient into the designated controlled area.
- 4. After delivery of the patient to the controlled area, rescue squad personnel should then exit through the side entrance-with the equipment that came in contact with the patient. The Radiological Physicist will survey the personnel for contamina-tion. If contamination is detected, the rescue squad personnel will be instructed to go to the Radioactive Uaste llanagement Facility (see map: Entrance to Controlled Area and Radioactive D**)D 70 '[ = $
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F. Decontamination of Equipment and Rescue Personnel The Radiation Safety staff will supervise the decontamination of the rescue squad personnel, equipment, and vehicle at the Radioactive Waste Management Facility. Contaminated clothing should be removed and placed in plastic bags labeled " Radioactive Contamination." Decontam-ination of the personnel will consist of washing the area of contam-ination with detergent and water. All contaminated equipment and vehicle interior will be washed. Once decontamination is completed, the rescue squad personnel can return to the squadhouse.
4
. e Attachment B APPENDIX A FACILITY LICENSE NO. R-66 TEGINICAL SPECIFICATIONS FOR THE UNIVERSITY OF VIRGINIA DOCKET NO. 50-62 DATE: JANUARY 18,I979
TABLE OF CONTENTS P_ age, 1.0 DEFINITIONS ' '
i
~""'
2.0 SAFETY LIMITS AND LIMITING SAFETY SYF',EM SETTINGS 5 2.1 Safety Limits 5 2.2 Limiting Safety System Settings 8 3.0 LIMITING CONDITIONS FOR OPERATION 9 3.1 Reactivity )
3.2 Reactor Safety System ~ ^
11 3.3 Reactor Instrumentation 13 3.4 Radioactive Effluents 15 3.5 Confinement ' 16 3.6 Limitations on Experiments 17 3.7 Operation with Fueled Experiments 19 3.8 Height of Water Above the Core in Natural 21 Convection Abde of Operation 3.9 Rod Drop Times 22 3.10 Emergency Removal of Decay Heat 23 4.0 SURVEILLANCE REQUIRESENTS 24 4.1 Safety Rods 24 4.2 Reactor Safety System 25 4.3 Emergency Core Spray System 26 4.4 Radiation Abnitoring Equipment 27 4.5 Maintenance 28 4.6 Con finement -
29 4.7 Airborne Effluents 30
TABLE OF CONTENTS (Continued) fags.
5.0 DESIGN FEATURES 31 5.1 Reactor Fuel 31 5.2 Reactor Building 32 5.3 Fuel Storage 33 6.0 ADMINISTRATIVE CONTROLS 34 6.1 Organization 34 6.2 Review 37 6.3 Operating Procedures 39 6.4 Action to be Taken in the Event a Safety Limit 40 is Exceeded 6.5 Action to be Taken in the Event of an Reportable 41 Occurrence 6.6 Plant Operating Records 42 6.7 Reporting Requirements 43 6.8 Review of ..periments 46
'-- LIST OF FIGURES Figure 2.1 Safety Limits with Forced Convection Flow 6
-6.1 Organizational Structure of the University 36- -
of Virginia Relating to the Reactor Facility
1.0 DEFINITIONS The terms Safety Limit (SL), Limiting Safety System Setting (LSSS),
Limiting Condition of. Operation (LCO), surveillance requirementh and design features are as defined in 10 CFR Part 50.36.
1.1 Reactor Shutdown - The reactor is in a shutdown condition when all shim rods are fully inserted.
1.2 Reactor Secured - The reactor is secured when:
- a. All shim rods are fully inserted;
- b. The console key is in the OFF position and is removed from the lock;
- c. No work is in progress in-core involving fuel or experiments or maintenance of the core structure, control rods or control rod mechanisms.
1.3 True Value - The true value of a process variable is its actual value at any instant.
1.4 Measured Value - The measured value of the process variable is the value of the variable as it appears on the output of a measuring channel.
. 1.5 hkasuring Channel - A, measuring channel is the combination of sensor, lines, amplifiers and output devices which are connected for the purpose of measuring the value of a process variable.
1.6 Reactor Safety System - The reactor safety system is that combi-
, , nation.of measuring channels,and associated circuitry which forms the automatic protective system of the reactor, or provides information which requires manual protection action to be initiated.
1.7 Operable - A component or system is operable when it is capable of performing its intended-function in a normal manner. - >--- -
1.8 Operating - A component or system is operating when it is per-forming its intended function in a normal manner.
'1.9 Channel . Check - A channel check is a qualitative verification of '
acceptr.,le performance by observation of channel behavior. This verification should include comparison of the channel with other independent channels or methods of measuring the same variable, where this capability exists.
1.10 Channel Test - A channel test is the introduction of a signal into a channel to verify that it is operable.
1;11 Channel Cr.libration - A channel calibration is an adjustment of the channel such that its cutput responds, with acceptable range and accuracy to known values of the parameter which the channe'1" '
measures . Calibration shall encompass the entire channel, includ-ing equipment actuation, alarm, or trip.
1.12 Reportable Occurrence - An reportable occurrence is any of the following:
- a. Any safety system setting less conservative than specified in the Limiting Safety System Settings section of these Technical Specifications.
- b. Operating in violation of a Limiting Condition for Operation established in these Technical Specifications unless prompt ramedini action is taken.
- c. Safety system component malfunctions or other component or ' ~ ~ '
system malfunctions during reactor operation which could, or threaten to, render the safety system incapable of performing its. 3 . tended safety function.
- d. .ielease of fission products from a failed fuel element; -
- e. An uncontrolled or unanticipated increase in reactivity in excess of 0.005 ak/k.
- f. An observed ihadequacy in ~the implementation of either admin-istrative or procedural controls, such that the inadequacy could have caus'ed the existence or development of an unsafe condition in connection with the operation of the reactor.
- g. Abnormal and significant degradation in reactor fuel, and/or; cladding, coolant boundary,' or containment boundary (excludid( '
minor leaks) where applicable which could result in exceeding 4 prescribed radiation-exposure limits of personnel and/or environmen t.
a O 1.13 Experiment - f.n experiment is:
- a. Any apparatus, device or material placed in the reactor core region, in an experimental facility associated with the reactor,
,, . , . ,. . . . . , , , or in-line'with~a' beam"of radiation emanating from the reactor; or
- b. Any in-core operation derigned to measure reactor character-istics.
1.14 Tried Experiment - A tried experiment is:
- a. An exp'eriment previously performed in this reactor; or
- b. An experiment for which the size, shape, composition and location does not differ significantly enough frem an experiment previously performed in this reactor to affect reactor safety.
1.15 Beam Ports - The beam ports are the two 8-inch neutron beam ports ,
which penetrate the shield on the south side of the pool.
1.16 Large Access Facilities - The large access facilities are the two large openings approximately 5-feet wide by 6-feet high which penetrate the shield on the south side of the pool.
1.17 Fueled Experiment - A fueled experiment is any experiment which contains urmium 235, uranium 233 or plutonium 239. This does not include the normal reactor core fuel elements.
1.18 Secured Experiment 2 Any' experiment, expeiimerital facil/ tty l or component of an experiment is deemed to be secured, or in a secured position, if it is held in a stationary position relative to the reactor by mechanical means. The restraint shall exert sufficient force on the experiment to overcome the expected effects of hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which might arise as a result of credible malfunctions. This condition is met if the experiment fits into the grid plate and is held down by a rod fastened to the reactor bridge. The hold down rod must have a strength equivalent to or greater than Schedule 40,1.5 inch diameter aluminum pipe.
1.19 Unsecured Experiment - Any expe'riment, experimental facility, or component of an experiment is deemed to be u'nsecured when it is not secured as defined in 1.18 above.
1.20 Movable Experiment - A movable experiment is one which may be inserted, remove'd7 or manipulated while the reactor is critical.
1.21 Experimental Facility - An experimental f acility is any structure or device associated with the reactor which is intended to guide, orient, position, manipulate or otherwise facilitate a multi-plicity of experiments of similar character.
1.22 Reactor Operation - Reactor operation means that the shim rods are not fully insertedand that the console key is in the ON position.
Reactor operation is not possible when there are less than six '
fuel elements loaded on the grid plate.
i 1.23 Shim Rod - A shim rod is a control rod fabricated from borated stainless steel which is used to compensate for fuel burnup, tem-perature, and poison effects. A shim rod is magnetically coupled to its drive uait allowing it to perform the function of- a safety rod when the magnet is de-energized.
'1.24 Regulating Rod - The r.egulating rod is a control rod of low reactiv-ity worth fabricated from stainless steel and used to control reactor power. The rod may be controlled by the operator with a manual switch or by an automatic controller.
1.25 Reactivity Limits - The reactivity limits are those limits imposed on reactor core excess reactivigy. Quantities are referenced specifically to a cold core (<90 F) with the effect of xenon poisoning on core activity accounted for if greater than or equal to 0.05%
ak/k. The reactivity worth of samarium in the core will not be included in excess reactivity limits. The reference core condition will be known as the cold, xenon-free criti~ cal condition.
1.26 Explosive Material - Explosive material is any solid or liquid which is categorized as a Severe, Dangerous, or Very Dangerous Explosion Hazard in " Dangerous Properties of Industrial Materials by N. I. Sax, Third Ed.' (1968), or is given an Identification of Reactivity (Stability) index of 2, 3, or 4 by the National Fire Protection Association in' its publication 704-M,1966, "Identifi-cation System for Fire Hazards of Materials," also enumerated in the " Handbook for Laboratory Safety" 2nd Ed. (1971) published by the Chemical Rubber Co.
e
.g 4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits 2.1.1 Safety Limits in Forced Convection bode of Operation Applicability This specification applies to the interrelated variables assoc- ,
iated with core thert.1 and hydraulic performance in the forced con-vection flow mode of operation. These variables are:
P = Reactor thermal power W = Reactor coolant flow rate T7 = Reactor coolant inlet temperature L = Height of water above the core Objective To assure that the integrity of the fuel clad is maintained.
Specification In the forced convection flow mode of operation,
- a. The pool water level shall not be less than 19 feet above top of the core.
- b. The,F.
~111 reactor coolant inlet temperature shall not be greater than .
- c. The combination of true values of P and W shall be in the unshaded .
. .. .., _. , . . portion of Figure 2.1. ~i- . - "" " * "' ' ' " " '
f Bases Above 400 gpm in the region of full power operation, the criterion
.... ..m.. ,. . m.. .used to. establish the.. safety limit ewas -a burnout ratio of 1.49 ' including '"' '"-
the worst variations in the manufacturer's tolerances and specification, hot channel factors, and other appropriate uncertainties. The analysis is
- given in Section 9.4 of the SAR.
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0 200 40b 600 800 1000 1400 Reactor Coolant Flow Rate, W, 'GPM FIG. 2.1 Safety Limits with Forced Convection Flow.
~3 In the region below 400 GPM where the flow coasts down to zero, reverses, and natural convection cooling is established, the criterion for selecting a safety limit is taken as a fuel plate temperature.
The analysis of a loss of flow transient from 3.45 megawatts of power
.. ,,s.. . . . . . , ... s,
.and ,744. GPM of flow,. shows_that-the maximum -fuel plate temperature' '
reached is 303 F which is well below the temperature at which fuel clad damage could occur. The analysis is given in Section 9.7 of the SAR.
2.1.2 Safety Limits in Natural Convection Mode of Operation Applicability
' This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the natural convection flow mode of operation. These variables are P = Reactor Thermal Power- -
Ty = Reactor Coolant Inlet Temperature Objective To assure that the integrity of the fuel clad is maintained.
Specification
,, , ,, , ,,m.. . . .. .. , , ,
.In .the_ natural convection flow mode of operation, the true value ' '"
of P and Ty shall not exceed:
P 750 kWt Ty 111 F Bases '
The criterion for establishing a safety limit with natural convection flow is established as a fuel plate temperature. This is consistent with
. Figure A for forced. convection-flow during a transient. 'Thi'anhlysis ' '
far natural convecgion flow shows that at 750 kN, the maximum fuel plate temperature is 259 F which is well below the temperature at which fuel clad damage could occur. The flow rate with natural convection at this power is calculated to be 129 GPM. The analysis is given in Chapter X of Amendment I to the SAR.
2.2 Limiting Safety System Settings Applicability _
This _ specification applies .to .the set points for the safety channels monitoring reactor diermal power, P, coolant flow rate, W, reactor coolant inlet temperature, T y, and the height of water above the core, L.
Objective To assure that automatic protective action is initiated in order to prevent a safety limit from being exceeded.
Specifications
~
- 1. For operation in the forced convection mode; the limiting safety system settings shall be as follows:
P 3.0 MNt(max)
W 800 GPM (min)
Tg 108 F (max)
L 19 ft, 2 in (min)
_ . . . . . , . . . . . ... .. . 2,,EgLpperation,,in,the,oatural..conveetion mode, the limiting safety system settings shall be as follows:
P 300 KWt (max)
Ty 108 F (max)
Bases The analysis shows that there is sufficient margin between these settings and the Safety Limits under the most adverse conditions of operation. (See Section 9.S of the SAR.') With natural convection m,,,,,,..., . . . . ~ .
09W.tl 3ereJE ng minimum coolant.. flow rate, water above the core so long as there is a p;ath andfor noflow.
minimum (Seeheight of Section 3.8 of these specifications.)
3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Applicability These specifications apply to the reactivity condition of the reactor, and the reactivity worths of control rods and experiments.
Objective -
The objective is to assure that the reactor can be shut down at all times and that. the safety limit will not be exceeded.
Specifications The reactor shall not be operated at powers in excess of one kilowatt unless the following conditions exist:
. . . , , . . . . , . . .. m..A..The minimum 5 shutdown.. margin-provided by control rods, with ~ secured ~
m experiments . in place and referred to the cold xenon free condition with the highest worth control rod fully withdrawn, is greater than 0.4% A k/k.
. . . . , . . . . . , . . . . . . . b.., Any , experiment ,with a- reactivity worth greater than 0.45% A k/k >
must be a secured experiment.
- c. The total reactivity worth of the two experiments having the highest reactivity worth is less than 1.6% A k/k.
- d. The total reactivity worth of all experiments is less than 2.0%
A k/k.
Bases --
The shutdown margin required by specification 3.1.a is necessary so that the reactor can be shut down from any operating condition and remain shut down after cool down and xenon decay even if one control rod should stick in the fully withdrawn position. For definition of " secured experiment,"
'- ~' " -
,,,, see Specification 1.18.
The reactivity of 0.45% A k/k in Spec _ification 3.1.b corresponds to a three second period. An analysis that shows the peak power does not exceed the safety limit when the reactor power Icvel is increasing on a three second period as the true value of the LSSS is reached is given in '
. . . .. . . . . . . eSection-9.6-of the SAR- (UVAR-18)- and in Section XI of .bendmetit* 1"t6' UVAR-Ilf. ' ' '
The reactivity of 1.6% A k/k in Specification 3.1.c corresponds to a 6.9 millisecond period. Reactor Core DU-12/25 of the SPhRT-1 series of tests had twelve P late fuel elements containing 168 grams of U-235 substantially similar to the UVAR fuel elements (
Reference:
Thompson and.,,
Beckerly, " Technology of Nuclea'r Reactor Safety", Volume I, page 683 (1964)). A 6.9 millisecond period was non-destructive. The simultaneous failure of more than two experiments is considered unlikely.
The total reactivity of 2.0% A k/k in Specification 3.1.d plac_es a reasonable upper limit on the worth of all experiments.
Operation of the reactor at a power of less than one kilowatt is allowed to n,asure the reactivity worth of untried experiments in accordance with procedures' approved by the Reactor Safety Com:nittee and to measure the excess reactivity of new core loadings.
s 3.2 Reactor Safety System Applicability This specification applies to the reactor safety system channels.
Objective The objective is to stipulate the minimum number of reactor safety system channels that must be operable in order to assure that the safety.
limit is not exceeded during nomal operation. (
\
Specification _
The reactor shall not be operated unless the safety system channels described in the falowing table are operable:
Measuring Minimum .
Operating Mode Channel No. Operable Setpoint* Function in Which Required Pool Water Level 2 19 ft 2 in Scram Forced Convection Monitor (min) Mode Bridge Radiation 1 Scram All Modes Monitor Pool Water 1 108 F(max) Scram All Modes Temperature Power to Primary 1 Loss of Power Scram Forced ?nvection Coolant Pump Mode Application Scram Natural Convection of Power bbde Primary Coolant Flow 1 800 GPM (min) Scram Forced Convection Mode Startup Count Rate 1 2 cps (min) Prevents Reactor Startup withdrawal of two shim rods Manual Button 1 Scram All Modes Reactor Power Level 2 3 FMD'(max) Scram Forced Convection Mode 0.3 FMt (mad Naural Conwetion Mode "Re acto r- Pe rio d' ---
-1 ' ' '- 3 sec ' (min) Scram "- -All Modes " '
Air Pressure to Header 1 Scram All Modes
- Values listed are limiting set points. For operational convenience set points may be changed to more conservative values.
t G Bases The startup interlock which requires a neutron count rate of at least 2 CPS before the reactor is operated, assures that sufficient neutrons are available for proper operation of the startup channel.
The pool water temperature scram provides protection to assure that if the limiting safety system setting is exceeded an immediate shutdown will occur to keep the fuel temperature below the safety limit. Power level scrams are provided to assure that the reactor power is maintained within the licensed limits and to protect against abnormally high fuel tempe ratures . The manual scram allows the operator to shut down the reactor if an unsafe or abnormal condition arises. The period scram is provided to assure that the power level does not increase on a period less than 3 secohds. This assures that a Safety Limit will not be exceeded as described in Chapter XI of Amendment 1.
Specifications on the pool water level are included as safety measures in the event of a serious loss of primary system water. Reactor operations are terminated if a major leak occurs in the primary system. The analysis in Section 9.8 of the SAR sh'ows the consequences resulting from loss of coolant.
The bridge radiation monitor gives warning of a high radiation level in the reactor room from failure of an experiment or from a significant drop in pool water level.
A scram from loss of primary coolant flow or of power to the pump both protect the reactor from overhsating.
9 3.3 Reactor Instrumentation __ .
Applicability This application applies to the instrumentation which must be operable for safe operation of the reactor.
Objective The objective is to require that sufficient information is available to the operator to assure safe operation of the reactor.
Specification The reactor shall not be operated unless the measuring channels described in Section 3.2 " Reactor Safety Systems" and in the following table are operable.
Measuring Minimum Operating Mode in
,,, ,,,,,, Channel , . . . ,, ,- ,. . , , No. .,0pe rab l e hhich Required Linear Power 1 All M:les Log N and Period 1 All Modes
, , Core Gamma Monitor. 1 All Modes '
Reactor Room Constant Air Monitor 1 All Modes
- Bridge Radiation Monitor 1 All Modes Reactor Face Monitor 1 All Modes
- Pool Water Level Monitor 2 Forced Convection Mode Pool "ater Temperature 1 All Modec
, , , , , . Primary Coolant,. Flow . 1, - . Forced Convection' Mode-- '"'
i Start-Up Count Rate 1 ~ Reactor Start-Up Reactor Power Level 2 All Modes t
The reactor room constant air monitor, and the reactor face monitor may be out of service for a period not to exceed 7 days without requiring reactor shut down. If the reactor face monitor cannot be repaired within 7 c5vs, it may be replaced by a locally alarming monitor of similar range for a to 30 days without requiring a reactor shutdown.
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Bases The neutron detectors, and either of the core gama monitors _____. . -~=
provide assurance that measurements of the reactor power level is _.
adequately covered at both low and high , power ranges. ?
The radiation monitors provide information to operating personnel of a decrease in pool water level and of any impending or existing danger from radiation contamination or streaming, allowing ample time to take necessary precautions to initiate safety action, s
I The reactor room constant air monitor and reactor face monitor provide redundant measures of abnormal high radiation levels. Since
- - - - - - c - other methods for determining the radiation levels are required for ...
reactor operation, the reactor can be operated safely if the monitors are not functioning for short periods of time.
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l 3.4 RADIOACTIVE EFFLUENTS - -
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This specification applies to the monitoring of radioa::tive effluents t
from the Reactor Facility. Airborne and liquid effluents are discussed separately in the following sections.
- 1. Airborne Effluents Objective i
The objective is to assurc that exposure to the public resulting from the release of A-41 and other airborne effluents will be wc11 below the limits
- of 10 CFR 20 for unrestricted areas.
Specification When any of the experimental facilities in the ground floor experi-mental' area are in use, the centrifugal blower which exhausts that area shall be in operation and the airborne activity in the effluent ..
shall be monitored by an instruridrit located in the six inch exhaust duct.
Bases The basis for this specification is given by the analysis in Chapter IX of Amendmant 1 to the SAR.
- 2. Liquid Effluents ,
l Objective i
The objective is to assure that exposure to the public resulting from
. the release of- radioactive effluents will be 'well below the' limits of i
10 CFR 20 for unrestricted areas. '
Specification
-The activity of liquids rgleased from the pond used for liquid waste disposal shall not exceed 1 x 10 ~ microcuries per milliliter.
Bases The basis for this specification is given in Section 4.8 in. the SAR.
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3.5 Confinement ,
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Applicability 0 ,,, , . , This specification applies to, the capability of isolating the reactor ' ~^~
room when necessary.
Objective The objective is to prevent the exposure to the public resulting from airborne activity released into the reactor rcom from exceding the limits, of 10 CFR 20 for unrestricted areas.
i Specification The reactor shall not be operated unless the following equipment is operable:
Equipment Function Truck Door Closed Switch Scram reactor when truck door is not fully closed.
Ventilation Exhaust Close and seal when Bridge Radiation Duct Doors Monitor alarms.
Personnel Door Close and seal when Bridge Radiation -
bbnitor alarms.
Emergency Exit Manhole Water Water level is high enough to form a Level water seal at least 6 inches in depth.
Emergency Exit Manhole Hatc h Scra=r reactor when the hatch is open.
Open Switch' Bases The bases for the proper operation of thest itens of equipment--are given in Section 6.1 of the SAR.
Ensuring that the emergency exit manhole hatch open switch will increase reactor security by ensuring that the reactor room cannot he entered from the outside while the reactor is operating.
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3.6 Limitations on Experiments '
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y Applicability This specification applies' to experiments installed in the reactor and its experimental facilities.
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Objective The objective is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.
Specifications The reactor shall not be operated unless the following conditions exist:
- a. The reactivity worths of all experiments shall be in conformance with Specifications 3.1.
- b. Movable experiments must be worth less than 0.1% A k/k.
- c. Experiments worth more than 0.1% must be inserted or re=oved with the reactor shut down except as noted in item d.
- d. Previously tried experiments measured to be worth less than 0.4% A k/k may be inserted or removed with the reactor 2% or more subcritical,
- e. If any experiment worth more than 0.4% is inserted in the reactor, a procedure approved by the Reactor Safety Committee shall be followed.
- f. All materials to be irradiated in the reactor shall be either corrosion resistant-or encapsulated within corrosion resistant containers.
- g. Irradiation containers to be used in the reactor in which a static pressure will exist or in which a pressure buildup is predicted shall be _ designed and tested for a pressure exceeding the maximum expected by a factor of 2.
- h. Explosive material shall not be allowed in the reactor unless specifically approved by the Reactor Safety Committee. Exp erimen ts reviewed by the Reactor Safety Con =ittee in which the mater,ial is potentially explosive, either while contained or if it leaks frem the container, shall be designed to prevent damage to the reactor core or to the control rods or instrumentation, and to prevent any
. schanges in reactivity.
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- i. Cooling shall b'e provided to' prevent the surface temperature of an- ' ' '
experiment to be irradiated from exceeding -the boiling point of the "~
reactor pool water. -
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- j. Experimintal apparatus, material or e'quipment to'be inserted in the reactor, shall not be positioned so as to cause shadowing of the nuclear instrumentatioa, interference with the control rods or oth'er -
perturbations that may interfere with the safe operation of the reactor.
- k. The radioactive material content, including fission products, of any singly encapsulated experiment should be limited, so that the complete release of all gaseous, particulate, or volatile components from the encapsulation could not result in doses in excess of 10% of th'e equivalent annual doses stated in 10 CFR Part 20. This dose limit applies to persons occupying (1) unrestricted areas continuously for two hours starting at time of release or (2) restricted areas during the length of time required to evacuate the restricted area.
- 1. The radioactive material content, including fisrion products, of any doubly encapsulated or vented experiment should be limited so that the complete release of all gaseous, particulate or volatile com- , ,
ponents from the encapsulation or confining boundary of the experi--
ment could not result in (1) a dose to any person occupying an un-restricted area continuously for a period of two hours starting at the time of release in excess of 0.5 rem to the whole body or 1.5 rem to the thyroid or (2) a dose to any person occupying a restricted area during the length of time required to evaculate the restricted area in excess of 5 rem to the whole body or 30 rem to the thyroid.
Bases The limitations on experiments specified in items a-j are based on the irradiation program authorized by Amendment No. 3 to License No. R-66 dated August 13, 1962. The' reactivity of less than 0.1% which can be insert'ed or removed with the reactor in operation is to accommodate experiments in the hydraulic rabbit'. ,
Items k. and 1. conform to the NRC Regulatorv Guide 2.2 issued in "*
November 1973.
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Thisspecificationaphliestotheoperationo he reactor with any"..
fueled experiment within the reactor building. ,
Objective To assure that the confinement leak rate and fission product inventory in fueled experiments are within limits used in the safety analysis.
Specification The reactor shall not be operated with fueled experiments unless the~
following conditions are satisfied:
- 1. For fueled experiments in which the thermal power generated is greater than 1 watt:
a) The experiment must be in the reactor pool and under at least 15 feet of water.
b) The thermal power (or fission rate) ggerated in the experiment is not greater than 100 watts (3.2x10 fissions /second) .
c) The total exposure of the experiment is not greater than the equivalent of 6 years continuous operation at 100 watts.
d) The Icak rate from the reactor room is not greater than 50% of containment volume in 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> as measured within the previous 12 months.
- 2. For fueled experimegs in which the thermal power generated is less than I watt (3.2x10 fissions /second) :
a) The experiment may be located anywhere in the reactor building.
b) The total exposure of the experiment is not great.cr than the equivalent of 6 years of continuous operation at 100 watts.
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In the event of the failure of a fueled experiment, with the subsequent
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release of fission products (100% noble gas, 50% iodine,1% solids), the 2-hour inhalation exposures to iodine and strontium 90. isotopes at th'e '
facility exclusion distance, 70 meters, are less than the limits set by 10 CFR Part 20, using an averaging period of 1 year.
The safety analyses for which results are used here are found in the
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Safety Analysis Report, Section 5.4. The analysis supporting Specification 3.7.2 assumes 100% exfiltration of fission products from the reactor building in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The analysis supporting Specification 3.7.1 for the fueled experiments within the reactor pool assumes a fission product retention in the reactor room equivalent to 100% fission product exfiltration in 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. The specification provides suitable allowance for degradation between tests. The measurement of the exfiltration value is described in Section XII of Amendment 1.
below:
Isotope inventory data used in the analysis of Section 5.4 are given Isotope Inventory Comment 1-1 31 0.0251 Ci/ watt Infinite Operation TID-14844 Values I-132 0.0381 " "
I-133 0.0563 " "
I-134 0.0658 " "
I-135 0.0510 " "
Sr-90 0. 75 Ci 6-Year Operation at 100 watts
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3.8 Height of Water Above the Core in Natural'Chiivection Mode of Operation , 4,
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Objective To assure that there is a continuous path for circulation of water when the reactor is operated in the natural convection mode.
Specification The reactor shall not be operated in the natural convection mode unless there is at least one foot of water above the core.
Bases One foot of water above the core is sufficient to provide a continuous path for natural convection cooling. For other than zero power operation, the radiation levels may require a greater depth for shielding, in which case, the regulations in 10 CFR Part 20 will govern.
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Applicability -
This specification applies.to the_ time from the initiation of a scram - s to the time a rod starts to drop (=agnet release time), and to the time it takes for a rod to drop from the fully withdrawn 'to the fully inserted
, position (free drop time) .
Objective To assure that the reactor can be shut down within a specified interval of time.
Specification The reactor will not be operated unless:
(a) The =agnet release tire for each of the three shim rods is less than 50 =illiseconds, and (b) The free drop tice for each of the thne shim rods is less than 700 tilliseconds.
Bases Rod drop times as specified will assure that the safety licits will not be exceeded in a short period transient. The analysis is given in Section 9.6 of the SAR, and Chapter XI of Amendment 1.
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Objective - .-
l The objective is to assure that the flow rate from this system is sufficient to prevent overheating of the fuel elements subsequent to a total
. loss of primary water from the core.
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i Specification i There shall be two separate emergency core spray systems, each capable of maintaining a flow rate of at least 10 gpm over the 64 fuel element positions for the first 30 minutes, and at least 7-1/2 gpm over the 64 fuel element positions for the next 60 minutes following a total loss of coolant.
Bases Either of the two spray systems as specified will provide sufficient cooling to maintain the fuel temperature below its melting point as demonstrated by the evaluation in Section 9.9 of the SAR.
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4.1'ShimF$ds- '
Applicability This specification applies to the surveillance requirements for the shim _ rods.
Objective To assure that the shim rods are capable of performing their function and that no significant physical degradation in the rods has occurred.
Specification
- a. Shim rod drop times shall be measured at intervals not to exceed five months. Safety rod drop times shall also be measured if the control assembly is moved to a new position in the core or -if maintenance is performed on the mechanism.
- b. The shim rod reactivity worths shall be measured whenever the rods are installed in a new core configuration.
- c. The shim rods shall be visually inspected at intervals not to exceed thirteen months, and when rod drop times exceed the limiting conditions for operation, Section 3.9 of these specifications. If the shim rod is found to be deteriorated or to have a crack of more than 1/4 inches in length, it shall be renaved from service.
Bases The reactivity worth of the shim rods is measured to assure that the required shutdown margin is available and to provide means for determining the reactivity worth of experiments inserted in the ' core. The visual inspection of the shim rods and measurement of their drop times are made to determine whether the shim rods are capable of perfoming properly.
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4.2 Reactor Safety System , n. 3 , -
Applicability'; - - "
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This specification applies to the surveillance
requirements for the
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reactor safety system of the reactor.
Objective The objective is to assure that the reactor safety system is operable as required by Specification 3.2.
Specification
- a. A channel test of each of the reactor safety system measuring channels shall be performed prior to each day's operation or prior to each operation extending more than one day.
- b. A channel check of each of the reactor safety system measuring channels shall be performed daily when the reactor is in operation.
- c. A channel calibration of the reactor safety measuring channels shall he per-formed at intervals not to exceed eight months,
- d. The power range channels 1 and 2 shall be checked against a, primary system heat balance at least once each week the reactor is in operation above 100 kilowatts.
- e. The following items which are listed in section 3.2 are not con-sidered to be reactor safety measuring channels: Power to primary coolant pump, manual button, header air pressure, and pool water level monitor. Operation of these systems will be checked prior to each days operation or prior to each operation extending more than one day.
Bases The daily channel tests and channel checks will assure that the safety channels are operabic. The semi-annual calibration will permit any long-term drift of the channels to be corrected. The weekly calibration of the power measuring channels will correct for drift and assure operation within the requirements of the license.
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Applicability 'Q ] 7f-This specification applies to the emergency core spray system.
Objective The objective is to assure that the spray systems are operable, and will deliver the specified flow rate of emergency coolant.
Specification
- a. h'henever the reactor bridge is moved and replaced into position for forced convection operation, the remote coupler for each spray system shall be air pressure checked to assure that there is no leakage.
- b. At intervals not to exceed thirteen months, measurements will be made to verify that each spray system will deliver at least 10 gpm for 30 minutes.
Bases The emergency spray system is an engineered safeguard. At the initial installation, each of the two core spray systems was checked to assure that it delivered the flow as specified in Section 3.10 of these speci-fications. Since there are no moving parts and no automatic electronic or mechanical machanisms subject to failure, a verification that the remote couplers are engaged and not leaking will assure that the two care spray systers are operable. The annual measurement of the flow rate will verify that each of the two core spray systems will deliver the flow as desired. The preoperational test of the core spray system demonstrated that water delivery is at least 10 gpm for 30 minutes and 71/2 gpm for the next 60 minutes. Subsequent annual tests, which verify the 30 minute flow rate, are adequate to verify design performance. The core spray system is described in Section 4.10 and the Safety Analysis is given in Section 9.9 of the SAR. The annual measurement of the flow rate is described in Chapter IV of the Supple-ment to the SAR- .
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This specification applies to the radiation monitoring equipment required by Sections 3.2 and 3.3 of these specifications., ' ~
Objective The objective is to assure that the radiation monitoring equipment is operating and to verify appropriate alarm settings.
Specification The operation of the radiation monitoring equipment and the position of their associated alarm set points shall be verified daily during periods when the reactor is in operation. Calibration of the radiation monitoring equipment shall be performed at intervals not to exceed eight months.
Bases Surveillance of the monitoring equipment will provide assurance that sufficient warning of a potential radiation hazard is available.
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' Applicability . .. . ,. . . , . .
This specification applies to the surveillance requirements following maintenance of control or safety systems.
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Objective The objective is to assure that a system is operable before being used after maintenance has been performed.
Specification Following maintenance or modification of a control or safety system or component, it shall be verified that .the system .is operable prior to its return to service or during initial operation.
Bases The intent of the specification.is to assure that work on the system or component has been properly carried out and that the system or component has been properly reinstalled or reconnected. Correct operation of some systems, such as power range monitors, cannot be verified unless the reactor is operating. Operation of these systems will be verified during their initial operation following maintenance or modification.
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Applicability __.
This specification applies to the surveillance requirements for confinement > '
of the reactor room.
Objective The objective is to assure that the closure equipment to the reactor room is operable.
Specification
- a. Prior to each day's operation or prior to each operation extending more than one day, the water level in the emergency exit manhole shall be verified.
- b. At least once each month, a test shall be made to assure that the following equipment is operable:
Truck door closed switch Ventilation exhaust duct doors Personnel door Emergency exit manhole hatch open switch
- c. At intervals not to exceed eight months, a visual inspection of the seals and gaskets of the truck door, the personnel door, and the
> ventilation er.haust duct door shall be made to verify that they are operable.
- d. Prior to operation with fueled experiments whose power generation is greater than I watt, leak rate shall be verified when the interval since the last verification is greater than 12 months.
Bases_
Surveillance of this equipment will verify that the confinement of the reactor room is maintained.
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! 4.7 Airborne Effluents -
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i This specification applies to the surveillance of the instrument which -
! monitors the airborne effluents from the ground floor experimental area.
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1 Objective To ensure that the airborne effluent monitor is operating and properly calibrated.
Specification
- 1. Prior to each day's operation or prior to each operation extending more than one day when any of the ground floor experimental areas are in use the centrifugal blower which exhausts that area shall be in operation, a channel check shall be performed on the airborne effluent monitor.
- 2. A calibration of the airborne effluent monitor will be performed using
- a radioactive source-at-invervals not to exceed eight months.
Bases The daily channel check of the monitor will assure that it is operable.
The= semi-annual calibration with an external source will permit any long term drift to be corrected. The analysis is given in Chapter IX of Amendment I to the SAR.
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DESIGN FEATURES : . _
t 5.1 Reactor Fuel The fuel elements shall be of the MTR type consisting of plates highly . _. _
enriched uranium alloy fuel, clad with aluminum. There shall be twelve fuel plates containing 165 ( 3%) grams of uranium-235, or eighteen fuel plates containing 195 ( 3%) grams of uranium-235, in the standard fuel elements.
There shall be six fuel plates containing 82.5 ( 35.) grams of uranium-235, or nine fuel plates containing 98 ( 3%) grams of uranium-235, in the control rod fuel elements. Partially loaded fuel elements in which.some of the fuel plates do not contain uranium may be used. The mass of uranium-235 listed above refers to the initial (zero burnup) loading.
5.2 Reactor Building - ,
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- a. The reactor shall be housed in a roon designed to restrict leakage.
- b. The reactor room shall be equipped with a ventilation system designed to exhaust air or other gases from the reactor room through a stack at a minimum of 37 feet above ground IcVel.
- c. The minimum free volume of the reactor room shall be 60,000 cubic feet.
- d. The openings into the reactor room are the truck door, the personnel door, the escape manhole, and the exhaust ducts.
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- 3.- .. g 5.3 Fuel Storage
- a. All reactor fuel elements shall be stored in a geometric array where k',gg is less than 0.8 for all conditions of moderation.
- b. Irradiated fuel elements and fueled devices shall be stored in an array which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device surface, temperature will not exceed 100 C.
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PRESIDENT OF Tile UNIVERSITY OF VIRGINI A i RADIATION SAFETY DEAN, SOf00L OF ENGR.
COSMITTEE AND APPLIED SCIENCE REACTOR SAFETY CUSNITTEE ~"".... CIAIRMAN, DEPARTMENT i
1F NiiCI. EAR FNGINEERING
$ UNIVEPSITY RADIATION I
- SAFETY OFFICER b____y J
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DIRECTOR i
- REACTOR SUPERVISOR ~ ~ '
REACTOR OPERATORS AND STAFF Figure 6.1
, , DRAFT ,
6.0 ADMINISTRATIVE CONTROLS 6.1 Organization
- a. The Reactor Eacility shall be an integral part of the School of Engineering and Applied Science of the University of . Virginia. The organizational structure of the University of Virginia relating to the Reactor Facility is shown in Figure 6.1.
- b. The Reactor Facility Director shall be responsibic for the overall Facility operation. During periods when the Reactor Facility Director is absent, his responsibilitics are delegated to the Reactor Supervisor.
The Reactor Facility Director shall have a Bachelor of Science or Engineering degree and have a minimum of five years of nuclear exper'ience. A graduate degree may fulfill four years of experience on a one for one time basis.
- c. The Reactor Supervisor shall be responsible for the day-to-day operation of the UVAR reactor and for assuring that all operations - ;
are conducted in a safe manner and within the limits prescribed by the facility license and the provisions of the Reactor Safety Committee. During periods when the Reactor Supervisor is absent, his responsibilitics are delegated to a person holding a Senior Reactor Operators license.
The Reactor Supervisor shall have a Bachelor of Science or Engin-cering degree and have at 1 cast 2 years experience in Reactor Operations at this facility, or an equivalent facility, or at 1 cast 6 years experience in Reactor Operations. Equivalent education or experience may be substituted for a degree. h'ithin nine months af ter being assigned to the position, the Reactor Supervisor shall obtain and maintain, a NRC Senior Operator license.
- d. When the reactor is not secured the following conditions will be met:
(1) A licensed Senior Reactor Operator or licensed Reactor Operator shall be present at the reactor controls.
(2) A licensed Senior Reactor Operator shall be on call, but not necessarily at the Facility. The licensed senior operator shall insure that he is within a reasonable driving time (within 15 miles) from the Reactor Facility and shall keep the licensed operator inforned of where and hou he may be contacted.
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(3) At 1 sast one other perso'n, not necessarily licensed to operate the reactor, will be' present at the facility.
- c. All rearrangements of the core or other nonroutine actions shall be supervised by a licensed Senior Reactor Operator,
- f. A health physicist who is organizationally independent of the Reactor Facility Operations group, as shown in Figure 6.1, shall be responsible for radiological safety at the facility.
t e
4 35 -
i
6.2 Review and Audit l
6
- a. There shall be a Reactor Safety Committee which shall review and i audit reactor operations. to assure that the facility is operated in l a manner consistent with public safety and within the terms of the l facility license. The Reactor Safety Committee shall report to the President of the University and advise the _ Chairman, Department of Nuclear Engineering and the Reactor Facility Director on those areas of responsibility rpecified below,
- b. The Committee shall be composed of at least five nenbers, one of whom shall be the Radiation Safety Officer of the University. No more than two members will be from the organi:ation responsibic for Reactor Operations. The ner..bership of the Committee shall be such as to. maintain a degree of technical proficiency in areas relating to reactor operation and reactor safety,
- c. A quorum of the Committee shall consist of not less than a majority of the full committee and shall include the Chairman or his designee.
- d. The Committee hall meet at least once every six months and on call by the Chairmain. Minutes of all meetings shall be disseminated to the President of the University, the Chairman of the Nuc1 car Engineering Jcpartment, the Reactor Facility Director, all Reactor Safety Conmittee members and other people as requested by the Committee Chairman.
- c. The Committee shall have a written statement defining such matters as the authority of the Committee, the subjects within its purview, and other such administrative provisions as are required for e f fec t i ve functioning of the Committee.
As a minimum the responsibilities of the Reactor Safety Committee include the following:
(1) Review and approval of untried experiments and tests which are significantly different from those previously used or tested in the re.,ctor as determined by the Facility Director.
( .') Review and approval of changes to the reactor core, reactor systems or design features ubich may affect the safety of the reactor.
(3) Review and approve all proposed amendments to the Facility.
License, Technical Specifications and changes to the Standard Operating procedures as discussed in section '6,.3 of these Specifications.
(4) Review reportable occurrences and the actions taken to identify and correct the cause of the occurrences.
(S) Review significant operating abnormalities or deviations from normal performance of Facility equipment that affect reactor safety.
(6) Review reactor operation and audit the operational records for compliance with reactor procedures, Technical Specifications
- nd License provisions. These audits shall be performed at t- 1st once cach calendar year.
6.3 Operating Procedures
- a. Written procedures reviewed and approved by the Reactor Safety Committee, shall be in effect and followed for the items listed below. These procedures shall be adequate to assure the safe oper-ation of the reactor, but should not preclude the use of independent judgement and action should the situation require such.
(1) Startup, operation, and shutdewn of the reactor.
(2) Installation or removal of fuel elements, control rods, experiments',
and experimental facilities.
(3) Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary coolant system Icaks, abnormal reactiv-ity changes.
(4) Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, re-entry, recovery, and medical support.
(5) Preventive and corrective maintenance operations which could have an effect on reactor safety.
(6) Periodic surveillance (including test and calibration) of reactor instrumentation and safety systems.
- b. Radiation control procedures shall be maintained and made available to all operations personnel,
- c. Substanti;c changes to the procedures shall be made only with the approval of the Reactor Sa fety Committee. Temporary changes to the procedures which do not change their original intent may be made with the approval of the Reactor Supervisor. All cuch temporary changes to procedures shall be documented and cubsonmentiv reviewed by the Reactor Safety Comnittee.
t 6.4 Action to be Taken in the livent a Safety Limit is Exceeded In the event a safety limit is violated the following 5ctions shall be taken:
- a. The reactor shalI be shut down and reactor operat ions shalI not be resumed until authorized by the Co:: mission;
- b. The occurrence shall be reported to the Reactor Facility liirector .
and the Chai rman of the Reactor Safety Contmi ttee, or their designee, '
as soon as possible but not later than the next work day. Reports shall be made to the Com:tission in accordance with Section 6.7 of these specifications;
- c. A written, Safety Limit violation report shall be raade which shall include an analysis of the causes of the violation and extent of resulting damage to Facility components, systems or structures, corrective actions taken, and recommendations for measures to prevent the probability of reoccurrence. This report shall be submitted to the Reactor Safety Committee for review.
b
6.5 Action to be Taken in the' Event of a Reportable Occurrence In the event of a reportabic occurrence, as defined in Section 1.12 of these Technical Specifications, the following action shall'bc taken:
- a. The Director cf the Reactor Facility shall be notified as soon as possibic and corrective action taken prior to resumption of the operation involved.
- b. A written report of the occurrence shall be made which shall include an analysis of the cause of the occurrence, the corrective action taken and recommendations for measures to prevent or reduce the probability of reoccurrence. This report shall be submitted to the Director and the Reactor Safety Conunittee for review,
- c. A report shall be submitted to the Commission in accordance with Section 6.7 of these specifications.
4 I
e
- c. A report within 30 days in writing to the Director, Division of Reactor Licensing, US NRC, Washington, D.C. 20515, with a copy to the Coruaission Region II Compliance Office of:
- 1. Any substantial variance from performance specifications contained in these Specifications or in the Safety Analysis Report.
- 2. Any signific. int change in the transient or accident analyses as described in the Safety Analysis Report.
- 3. Changes in personnel serving as Chairman of the Department of Noelcar Engineering, Reactor Faci lity Director, or Reactor Supervisor.
- d. A report ..ithin nine months after initial criticality of the reactor or within 90 days of coupletion of the startup test programs, whichever is earlier, to the Director, Division of Reactor I,icensing, US NRC, Washington, D.C.
20515 opon receipt of a new facility license, an ataendment to the license authorizing an increase in reactor power IcVel or the installation of a new core of a different design than previously used. The report will include the measured values o f the operat ing conditions or charac-t erist ics of the reactor under the new conditions, including:
- 1. Total control rod reactivi ty worth.
.. Reactivity worth of the single control rod of highest reactivity harth.
- 3. Llinimo:a shutdown margin both at ambient and operating temperatures.
- e. A routine report will be made by March 31 of each year to the Director, Division of Reactor Licensing, US NRC, Washington, D.C. 20515, with a copy to the Cor mission Region II Compliance Of fice providing the following i n fo rmat ion :
- 1. A narrat ive sua . t ry o f opera t. i ng expe ri ence (including experiments pe r fo n.ed ) and o f changes in faci l i ty desi gn, performance charac-teristies and operat ing proerdure: related to the reactor sa fety occurring duriny t he report ing pe riod.
. ' . A t Milatien , cwing t he energy gt nerated by the reactor (in aegawatt hcurs) .nd t he nn".l'e r o f hou rs t he reactor was critical each quarter d ninn the year.
- 3. A repart o f t he results of the sa fety related maint enance and in-
- cections. the reasons for corrective raintenance of cafety related items tilI be included.
6.6 Plant Operating Records In addition to the requirements of applicable regulations, records and logs of the items listed below shall be kept in a manner convenient for review and shall be retained as indicated:
- a. Records to be retained for a period of at least five years:
- 1. Normal plant operation.
- 2. Principal maintenance activities.
- 3. Experiments performed with the reactor.
- 4. Reportable occurrences.
- 5. Equipment and component surveillance activity.
- 6. Facility radiation and contamination surveys.
- 7. Transfer of radioactive material.
S. Citanges to operating precedures.
- h. Records to be retained for the life of the Facility:
- 1. Gaseous and liquid radioactive effluents released to the environs.
- 2. Off-site environmental monitoring surveys.
- 3. Fuel inventories and trans fers.
- 1. Radiation exposures for all personnel.
- 5. Changes to reactor systems, coapoacnts, or equipment which may a f fect reactor sa fety.
- o. IlpJa t ed, corrected and as-built drawin s of the facility.
~ ':i n n t e:, o f Ib 'ac t o r Sa : e t :. Cr> : i t t ee c.c e t i n gs .
- L4 e
- 6. 7 Reporting Requirements In addition to the requirements of applicable regulations reports should be made to the Commission as follows:
- a. A report as soon as possible, but no later than the next working day, (by telephone and confirmed by telegraph or mailgram) to the Commission Region 11 Regional Office of:
- 1. Any accidental off-site release of radioactivity above permissible limit s, whether or not the release resulted in 1)roperty damage, personal injury or exposure;
- 2. \ny reportable occurrences as defined in Section 1.12 of these specifications; and
- 3. Any violation of a safety limit,
- b. A report wi. thin 14 days (in writing to the Director, Division of Reactor I.icensing, US NRC, h'ashington, D.C. 20545 with a copy to the Coruainsion Region II Compliance Of fice) of:
- 1. Any accidental off-site release of radioactivity above permissibic 1imits, whether or not the release resulted in property damage, personal injury or exposure.
- 2. Any reportable occurrence as defineu in Section 1.12 of these spee i fica t ions.
- 3. Any violation of a safety limit.
e e
- 4. The number of emergency shutdowns and inadvertent scrams, including their reasons and corrective actions taken.
- 5. A summary of changes to the Facility or procedures, which affect reactor safety, and performance of tests or experiments carried out under the conditions of Section 50.59 of 10 CFR Part 50.
- 6. A summary of the nature and amount of radioactive gaseous liquid and solid effluents released or discharged to the environs beyond the ef fective control of the licensee as measured or calculated at or prior to the point of such relense or discharge.
- 7. A description of any environmental surveys performed outside the facility, and
- 8. A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant ex-posures (greater than 500 mrem for adults and 50 mrem for persons under 18 years of age) and a sui: mary of the results of radiation and contamination surveys performed within the facility.
d A 6.8 Review of Experiments
- a. An " irradiation request" shall be submitted to the Reactor Super-visor for any material to be irradiated or experiment to be performed in the UVAR. This request shall contain information on the target naterial including the amount, chenical form, and packaging and an evaluation of the experiment or irradiation by the experimenter.
All proposed experiments utilizing the reactor shall also be evaluated by the Reactor Supervisor or Senior Operator to assure corpliance with the provisions of the utilization License, the Technical Specifications, and 10 CFR Part 20. When pertinent these evaluations shall include the following items:
items:
- 1. The predicted reactivity worth of the experiment.
- 2. The inte;;rity of the experiment, including the effects of changes in temperature, pressure, or chemical composition.
- 3. Any physical or chemical interaction that could occur within the reactor components.
- 1. Any radiation hazard the may result from the activation of ma t e ria l s o r f rom ex* . cna l beams.
- b. I f, based on the evaluations, the Reactor Supervisor or Senior Operator determines that an experiment or irradiation is a tried experiment which does not contain nuclear fuel or known explosive materials, and uhich does not constitute a significant threat to the integrity of the reactor, it may be approved by the Reactor Supervisor or Senior Operator,
- c. Prior to performing an untried experiment or irradiation in the reactor which could affect the reactivity of the core or result in the release of radioactive materials and is signi ficantly different f rom previous expe riment s, it shall be reviewed and approved by the Reactor Sa fety Cor.mi t tee. Its review shall consider the fo l l owi ng i n fo rna t i on :
- 1. The purpose o f t he expe r i::.cn t.
- 2. A ,r<cedurt for the performance o f the experiment.
- 3. rhe citten evaluatians t de as in paragraph a. above.
Attachment C REVISION TO THE REVISED SAFETY ANALYSIS REPORT IN SUPPORT OF AMENDMENT TO LICENSE R-66 FOR TWO FEGAWATT OPERATION, UNIVERSITY OF VIRGINIA REACTOR UVAR-18, PART I The changes listed below are being made to the Safety Analysis report for the University of Virginia Reactor, UVAR-18, Part I.
Item No. Section Page Change and Basis for Change
- 1. -
Title Delete: October 1970 Add: Revision 1, January 1979 Add the following note at the bottom of the page:
" Revision 1 to UVAR-18, Part I combines the contents of the October 1970 version of the SAR and Amendment 1 to the SAR dated March 1971. Additional minor changes are included to make the SAR consistent with Revision 1 to the UVAR Technical Specifi-cations, UVAR-18, Part II.
Basis: To indicate the date and purpose of the revision.
- 2. Table of Delete: REFERENCES FOR CHAPTER IX Contents, Add: "9.10 References to Chapter IX"
- E E* Add the following after Section 9.10
" Appendix A: Amendment I to the Revised Safety Analysis Report and Technical Specifi-cations for Two Megawatt Operation, University of Virginia Reactor."
Basis: To update Table of Contents.
- 3. List of Figures and Revise the figure titles to read as follows:
E"#
- 14 Figure II-6 First Floor Plan of UVAR Section of Building.
15 Figure II-7 Mezzanine Level of UVAR Section of Building.
16 Figure II-8 Ground Floor Plan of UVAR Section of Building.
17 Figure II-9 Plans of the Nuclear Reactor Facility.
24 Figure III-3 Standard Flat Plate Fuel Element.
25 Figure III-4 Flat Plate Control Rod Element.
Item No. Section Page Change and Basis for Change Basis: To reflect changes to the facility completed since the SAR was issued and to differentiate flat plate fuel elements from curved plate elements which are also used.
- 4. List of Add: II-l Relative Frequency of Hourly Wind Tables Speed in Percent by Season ...19 II-2 Relative Frequency of Hourly Wind Directions in Percent by Season.. 19 III-l Reactor Data .... 31 Basis: Io add title of Tables which were pre-viously included in the SAR but not listed.
- 5. 1.1 1. Change the second paragraph which now reads
"... operations staff composed of a reactor operations manager, ..."
to "... operations staff composed of a Reactor Supervisor, ...".
Basis: To make Reactor Supervisors title consistent with the Technical Specifications.
- 6. 1.2 4. Add References 30) through 35) which are pro-vided in Attachment I to this section.
Basis: To include reference to documents affecting the UVAR license which were issued since the SAR was last revised.
- 7. 2.1 6. Change the last sentence in the second para-graph to state that the addition to the reactor building was completed in 1970.
Basis: To indicate completion of the addition.
8, 2.3 12. Delete the existing paragraph and replace with the following paragraph:
" Construction of an addition to the Reactor Facility was completed in 1970. The new addition provided office space, a machine shop, an electronics shop, a low background counting room, a health physics laboratory, student laboratories and a low power (100 watts) training reactor."
Basis: To indicate completion of the new addition and related facilities.
Item No. Section Page Change and Basis for Change
- 9. 2. 17. Replace existing Figure II-9 with Figure II-9 included as Attachment 2 to this section.
Basis: To include changes to the facilit) which have occurred since the SAR was last revised.
- 10. Deleted
- 11. 3.2 26. Add the following new paragraph at the end of Section 3.2:
Also available for use in the UVAR are MTR type curved plate elements. The standard fuel element has 18 fuel plates and a loading of N195 grams of U-235. The control rod fuel elements have 9 fuel plates with a loading of 497.5 grams U-235. Partial loaded fuel elements are also available for use. The construction of these elements is the same as the flat plate elements.
Basis: To add a description of curved plate fuel elements which were approved for use in the UVAR by Reference 32) in Section 1.2 of the updated SAR.
- 12. 3.5 30. Revise the second sentence of Section 3.5 to read "Three of these designated as shim rods are designed ..."
Replace the term " safety shim rods" or " shim-safety rods" in paragraph 2 and 3 of Section 3.5 with the term " shim rods".
Basis: To be consistent with the terms used in the UVAR Technical Specifications.
- 13. Table 32-33 Replace existing pages 32 and 33 with the III-l revised pages included as Attachment 3.
Basis: To provide data on curved plate fuel elements which was approved for use in the UVAR by Reference 32) in Section 1.2 of the updated SAR.
Item No. Section Page Change'and Basis for~ Change
- 14. 3.5 35. Delete the phrase ", or each 50 megawatt days," from the first sentence in the last paragraph on page 35.
Basis: To be consistent with the change to the UVAR Technical Specifications approved by Reference 34) in Section 1.2 of the up-dated SAR.
- 15. 3.6.1 42. Delete the last paragraph in Section 3.6.1 and replace with the following sentence:
"The major circuits are described in the following sections;"
Basis: To delete reference to the change from vacuum tube to solid state components since the change has been completed.
- 16. 3.6.7 59. Delete all of Section 3.6.7.
Basis: Section 3.6.7 listed the advantages of changing from vacuum tube components to solid state components. This section is not needed since the change has been completed. .
- 17. 3.7 59. Delete Item 6. High radiation level, reactor face.
Basis: To be consistent with the revised UVAR Technical Specifications. The reactor face radiation monitor will be retained and will alarm in the reactor control room.
- 18. 3.7 60. Revise Item 12 to" Emergency eccape hatch open."
Basis: To be consistent with the revision to the UVAR Technical Specifications approved by Reference 35) in Section 1.2 of the updated SAR.
- 19. 3. 7 60. List the following values after Items 14 and 15:
- 14. High reactor inlet water temperature >108 F.
- 15. Low pool level (2) 19 ft. 2 in.
Basis: To be consistent with values contained in the UVAR Technical Specifications.
- 20. 4.1 ,
- 62. Replace 19.0 feet with 19 feet 2 inches in the third paragraph of Section 4.1.
Basis: To be consistent with the UVAR Techni-cal Specifications.
Item No. Section Page _ Change and Basis for ' Change
- 21. 4.3 66. Change the temperature listed in the last paragraph of Section 4.3 to 108 F.
Basis: To be consistent with the UVAR Technical Specifications.
- 22. 4.4 66. Revise the second paragraph in Section 4.4 to read ". . . the normal AT across the reactor at two megawatts is about 15 F." Delete the last sentence.
Basis: To provide updated AT value for two megawatt operation.
- 23. 4.6 67-69. Delete all of Section 4.6. Add the following sentence. "See Section II of Appendix A."
Basis: The information in Section 4.6 was superceded by the information in Amendment I to the SAR which is now incorporated as Appendix A.
- 24. 4.5 67. Revise the following values in the first sentence of Section 4.5:
"750 gallons per minute" should be "about 1200 gallons per minute".
"1 MW" should bi "2 MW" "75 F wet bulb" should be "73 F wet bulb".
Revise the second sentence to read "The system utilizes a conventional centrifugal pump driven by an induction motor."
Basis: To be consistent with the present system used for 2 MW operation.
- 25. 4.7 69. Revise the second sentence of Section 4.7 to read "The water is normally maintained at a pH of 4.5 to 7.5 with a conductivity of less than 5.0 micor mhos."
Basis: To allow an expanded range of pH and conductivity of the reactor coolant. Experi-ence at other facilities has shown that these ranges will adequately control corrosion of the aluminum components in the reactor coolant system and fuel elements.
- 26. Deleted -
Item No. Section Page Change'and' Basis'for Change
- 27. 4.10 77. Add the following paragraph at the end of Section 4.10:
" Additional information on the Core Spray System is provided in Sections III and IV of Appendix A.
Basis: To provide reference to additional information contained in Amendment I to the SAR which is now included as Appendix A.
- 28. 5.4.6 87. Add the following paragraph at the bottom of page 87: " Additional Analysis of airborne effluents is provided in Section IX of Appendix A."
Basis: To provide reference to additional analyses of airborne effluents contained in Amendment I to the SAR which is now included as Appendix A. '
- 29. 6.1 90. Delete the third sentence in the last para-graph on page 90 and replace with the following sentence:
"The emergency escape hatch is normally closed and secured with a slide bolt which will allow easy opening from the inside in the event of an emergency."
Basis: To be consistent with the change to the UVAR Technical Specifications approved by Reference 35) in Section 1.2 of the updated SAR.
- 30. 6.1 93. Delete the phrase " intake and" from the first sentence of the last paragraph in Section 6.1.
Basis: The intake ducts have been sealed shut to increase reactor security. The personnel door now acts as the reactor room air intake.
- 31. 6.1 93. Revise the third sentence of the last paragraph in Section 6.1 to read "...upon a high radi-ation level at the reactor bridge."
Basis: To indicate the location of the radi-ation monitor which results in closure of the exhaust ducts.
Item No. Section Page Change and ' Basis fcr Change 32 7.4 104. Revise the first sentence of the last para-graph in Section 7.4 to read "...and work areas on a regular basis established by the Health Physicists."
Basis: To delete reference to the interval for radiation surveys since they are defined in specific procedures used by the Health Physicist.
- 33. 7.5 104 Delete the phrase "will have had a physical examination and" from the last sentence of the first paragraph in Section 7.5 Basis: It is not necessary to ha/e all workers at the facility, which includes faculty and students, to have a ph rsical examination to ensure reactor safety. Reactor Operators will have physical examination as required by the NRC.
- 34. 7.4 105 Delete the last paragraph in Section 7.5 and replace it with the following paragraph:
"If any individuals receive a radiation dose in excess of the limits of 10 CFR Part 20 as determined by the ionization chambers, film badges, or other methods the Health Physicist will notify the Facility Director. The Health Physicist will provide information concerning the amount and type of exposure and recommend actions that should be taken by the overexposed individual and to avoid future, similar over
. exposures. The Director will take action in accordance with 10 CFR Part 20."
Basis: Editorial.
- 35. 7.6 105 Delete the third paragraph in Section 7.6 and add the following sentence to the end of the paragraph:
"The disposal of liquid radioactive vastes is d'.scussed in Section 4.8 of this SAR."
Basis: To provide a consistent, accurate dis-cription of liquid waste disposal.
- 36. 7.7 106 Replace "AEC" with "NRC" in the last line of the first paragraph on page 106.
Basis: Update of commission naue.
Replace "10 CFR Part 20" in two places with
, "10 CFR Part 71" on page 106 and delete
, "...and a license must be obtained by the recipient" in the last sentence on page 106.
Item No. Section 'Page Change 'and Basis for ' Change
- 37. 8.1 107-110 Delete pages 107 through 110 and replace with revised pages 107 through 110 enclosed as Attachment 4.
Basis: To make the discussion of Reactor Administration consistent with Section 6.0 of the UVAR Technical Specifications.
- 38. 8.2 111 Delete the partial sentence at the top of page 111.
Replace "AEC" with "NRC" in two places in the first paragraph and one place in the second paragraph of page 111.
Basis: To be consistent with the revised pages 107-109 and update the name of the Commission.
- 39. 8.2 112 Replace "AEC" with "NRC" in two places in the second paragraph on page 112.
Basis: To update Commission name.
- 40. 4.8 70 Replace " iodine-131" with ' iodine 129" in the last sentence of Section 4.8.
Basis: To correct a previous error.
- 41. List of Delete "VIII-2 Organization of the Reactor Figures - Facility at the University of Virginia. ..110" Basis: Figure VIII-2 has been deleted from the SAR.
ATTACHMENT 1 List of References to be Added to Section 1.2 of the UVAR Safety Analysis Report
- 30) August 4, 1971, Amendment No. 8 to License R-66 to allow storage of 70,000 curies of Cobalt-60 in reactor pool, signed by Donald J. Skovholt.
- 31) November 4, 1971, Amendment No. 9 to License R-66 to allow operation at 2 FM and incorporate Technical Specifications into the license and to receive, possess, and use up to 7.9 kilograms of contained uranium-235 for use in connection with tne operation of the reactor and receive, possess, and store up to 6.1 kilograms of contained uranium-235 not for use in connection with operation of the reactor, signed by Donald J. Skovholt.
- 32) February 6, 1975, Amendment No. 10 to License R-66 to receive, possess and use up to 14.0 kilograms of contained uranium-235 and 16 grams of plutonium in a Pu-Be source for use in connection with operation of the reac to r. -Also change No. 1 to the Technical Specification 5.1 describing the fuel elements that one used in the reactor, signed by Karl R. Coller.
- 33) May 17, 1976, Amendment No.11 to License R-66. Change in Technical Specification 3.7 to clarify the use of fueled experiments in the reactor facility, signed by George Lear.
- 34) December 19, 1978, Amendment No. 12 to License R-66 to change the requirement of visual inspection of control rods as stated in Technical Specification 4.1.C, signed by Morton B. Fairtile for Robert W. Reid.
- 35) December 22, 1978, Amendment No. 13 to License R-66 to allow the receipt, possession, and use of 1.0 grams of Neptunium-237 in connection with the operation of the reactor. Also a change in Technical Specifi-cation 3.5 regarding the exit manhole hatch cover, signed by Morton B.
Fairtile for Robert W. Reid.
Attachment 2 I
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17
Attachment 3 TABLE III-l (Continued)
Graphite Water
_ .. . Peflected Reflected Bottom Reflector
% Water 39 39
%AL 61 61 ,
Average Thermal Flux at neut 2 MW Operation 2 2x1013 .17x1013 em2nec E,U235 g cm
-I 0.0573 0.0555 Fuel Elements - type: Flat Plate, U-AL Alloy, Clad with Al Curydd Overall Dimensions Flat Plate Plate Length in. 34.38 34.38 Width in. 2.996 2.996 Depth in. 3.150 3.150 Standard Element Number of Plates 12 18 Width in. 2.886 -
Thickness (inner plates) in. 0.050 0.050 (outer plates) in. N/A 0.065 Length in. 24.63 24.63 Cladding Thickness (inner plates) in. 0.015 0.015 (outer plates) in. N/A 0.0225 Fuel Thickness (U-AL Meat) in. 0.020 0.020 Fuel Width in. .
2.50 2.375 Fuel Length in. 23.5 23.5 U 235 vol % in Alloy 3.67 Weight U 235 per element gn. 165. 195.
Water space between plates in. 0.211 0.122 Side Plates - Overall .
Length in. 28.69 28.69 Width in. 0.188 0.188 Depth in. 3.150 3.150 TABLE III-l
(' continued) 12 18 Number of Grooves .
Depth of Grooves - in. 0.138 _. -
in. 0.055 -
Width of Grooves Partial Elements - The dimensions are the same as for the fully loaded elements but only every other plate is loaded with fuel, the alternate plates.being ,
made of aluminum only. This produces a U 235 content of 82.5 gs/ element for the flat plate partial elements and 95 gm. for the cursed plate elements.
Control' Rod Elements Similar to standardaelements but with the central-fuel-plates removed to provide a gap for insertion of a control rod.
Curved Flat Plate Plate gmU 235 82.5 98 Fuel Loading in. 1.130 1.125 Central Gap 6 9 Number of plates Control Rods Shim Rods 3
Number Absorber Material Boron-Stainless Steel 1.5% Boron AL Clad Dimensions, Overall in. 1 Width (Approx.)
in. 2.38 Depth (Approx.)
' ' in. 27.5 Length (Approx.)
in. 24 Travel (Approx.)
kg. 5.5 Weight (Dropping Section)
Drive - Electric motor, 115 B 60 cycle, split phase.
3600 rpm at 60 cps. From top by lead screw.
in/ min 3.74 Drive Speed ,
Release - Magnetic - af ter release, mechanism must be driven down to re-engage absorber
' -' Typical-Reactivity, Fully inserted % AK7.,3.0 . _ .
AK/in 0.125 Typical Reactivity per inch % g 0.008 Typical rate of Reactivity Increase -3 3-in up travel %
ATTACHMENT 4 Revised Pages 107-110 for SAR VIII. ADMINISTRATION 8.1 General Organization The organization of the University of Virginia as related to ensuring the safe use of radioactive materials'is shown in Figure VIII-1. This organization consists of two major committees; the University Radiation Safety Committee and the Reactor Safety Cormittee.
The Radiation Safety Committee is appointed by the President of the University and must approve the possession and use of radioactive materials at the University with the exception of those associated with the Reactor Facility.
Production, posssssion and ssagd of'rsdiodetive materials at the reactor come under the reactor license and are reviewed by the Reactor Safety Consittee.
However, if a radioisotope is made in the reactor for use outside the Reactor Facility, its possession and use must'be approved by the Radiation Safety Committee.
8.2 Reactor Safety Committee As
~~ The reactor'is operated uhddr AEC License R-66 granted in 1960.
that required by the license, a Reactor Safety Committee was appointed at time. The organization within the University is shown in Fig. VIII-1 As a minimum, the Reactor Safety Committee is composed of five members and includes the University Radiation Safety Officer. In general the Reactor Faciiity Director and at least one professor from a department other than Nuclear Engineering will serve on the committee. Additional members are appointed to ensure that people knowledgable in the major areas affecting safe operation of the reactor are included. The major areas include reactor 107
engineering, instrumentation and control systems and radiological safety.
No more than two members of the Reactor operating staff will serve on the committee to prevent domination of the committee by the operating organization.
However, members of the operating staff or other people may attend meetings in an advisory capacity.
The responsibilities of the Reactor Safety Committee are defined in Section 6 of the UVAR Technical Specifications. These responsibilities include review and audit of reactor operations, approval of changes to the operating procedures, approval of proposed changes to the Technical Specifications, and approval of experiments.
Page 110 has been Deleted 108
PPESIDENT
- : . OF THE - - 2 UNIVERSITY r -
DEAN, SCH'00L OF
. UNIVERSITY RADIATION MEDICAL ISOTOPE P ID _ E SAFETY COMMITTEE SUBCOMMITTEE CHAIRMAN, DEPARTMENT OF REACTOR SAFETY UNIVERSI'iv NUCLEAR ENGINEERING ANE COMMITTEE RADIATION SAFETY ENGINEERING PHYSICS -
OFFICER
' I E -
I e -
i DIRECTOR
- -~- - d '
RADIATION SAFETY
- ~ ~ ' - - - - - - - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ -
REACTOR FACILITY 0FFICE STAFF REACTOR SUPERVISOR ~
4 N
e REACT 0jR STAFF.
i 1 FIGURE VIII-1. RADIATION-SAFETY ORGANIZATION AT THE UNIVERSITY OF VIRGINIA e
Attachment D PROPOSED 01ANGES TO 111E CAVALIER TECHNICAL SPECIFICATIONS (Facility License No. R-123, Docket No. 50-396)
Approval of the following changes to the Technical Specifications associated with the CAVALIER License R-123, Docket No. 50-396 is requested.
Section Change and Basis for Change 1.15 Change the first line to read: '
" Reportable Occurrence - A reportable occurrence is any .
of the following:"
Basis: To replace the term " abnormal occurrence" with the proper term " reportable occurrence."
1.15D Change the sentence to read: " Release of fission' products from a f-J ted fuel element;" '"
Basis-. To clarify the source of fission products and preclude the need for reporting the presence of very low radioactivity IcVels not associated with failed fuel elements as has occurred in the past. A procedure is being developed to determine whether low levels of activity are from a failed fuel element. This is con-sistent with the revised UVAR Technical Specifications and the approved University of Michigan reactor Techni-cal Specifications.
6 Delete all of Section 6, Administrative Controls, and
._... replace.with.a ,gew p,qction 6 which is. identical to that contained in the proposed UVAR Technical Specifications, UVAR-18, Part II, dated January 1979.
Basis: To make the Administrative Controls Section for
~~ " ' " " ' '
- ~the CAVALIER the same as for the UVAR. '
.