ML20217Q077
| ML20217Q077 | |
| Person / Time | |
|---|---|
| Site: | 070*****, 07003095 |
| Issue date: | 03/04/1998 |
| From: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Alkema K ENVIROCARE OF UTAH, INC. |
| Shared Package | |
| ML20217Q081 | List: |
| References | |
| TAC-L51562, NUDOCS 9803110358 | |
| Download: ML20217Q077 (25) | |
Text
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UNITED STATES e
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 2055H1001
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March 4, 1998
~/p- ?d)*S Mr. Kenneth Alkema, Director Government Affairs Envirocare of Utah, Inc.
46 West Broadway, Suite 240 Salt Lake City, UT
SUBJECT:
LICENSE APPLICATION ACCEPTANCE REVIEW (TAC L51562)
Dear Mr. Alkema:
As discussed in our letter dated December 16,1997, we have conducted an acceptance review of your license application dated December 5,1997. This acceptance review is a preliminary review of the contents of the application to determine the adequacy of the submittals as a basis for the Nuclear Regulatory Commission to commence a license review. The application was reviewec sing the requirements in 10 CFR Part 70 and the guidance in the draft Standard Review Plan (SRP) (NUREG-1520), which were provided to you at our July 30,1997, meeting.
Based on our review, we conclude that the application does not meet the requirements of Section 70.22 and accordingly, we are rejecting the application.
The application does not contain adequate information to provide a basis for NRC to review Envirocare's operations for compliance with 10 CFR Part 70. As described in the enclosed acceptance review, we identified significant deficiencies and omissions. The applicant should consider the enclosed list of deficiencies and information in the draft SRP as guidance in revising the application. Upon submission of a revised application, we will conduct an additional acceptance review.
We are also responding to yot.r letter dated November 12,1997, which requested a prompt review of your license application. As previously stated, the review of this application is an unbudgeted activity for fiscal year (FY) 98. We intend to defer the decision to reprogram resources to conduct the technical review in FY98 until we have received an acceptable application.
4 We suggest that our staffs meet to discuss the information required to provide NRC with a basis j
to assure compliance with 10 CFR Part 70 and review the enclosed list of deficiencies. I recommend that you contact us at your earliest convenience to schedule such a meeting.
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9803110358 980304 PDR ADOCK 070*****
C PDR N58 ele GEME3 80PV I.l l.lill.ll.lll 11,IlII
4 K. Alkema 2--
if you have any questions or comments, please contact me at (301) 415-7234 or Mr. Tim Harris of my staff at (301) 415-6613.
Sincerely,
[0RIGINALSIGNEDBY:]
John W. N. Hickey, Chief Low-Level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards j
Docket No.: 070-3095
Enclosure:
As stated w/ attachments i
cc: William Sinclair, State of Utah
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Ticket: N-9700520 DISTRIBUTION:
' Central File, LLDP r/f NMSS r/f DWM r/f DWM t/f PLohaus WBrach LHowell PUBLIC MLamastra RJohnson MFederline CPoland NMSS Dir, r/f ACNW DOCUMENT NAME:s:\\dwm\\lldp\\teh\\lic.cr
- See previous concurrence I
OFC LLDP LLDP LLDP OGC LLDP E
FCSS DWM F
RNelson*
WktiaY Jhhkey*
bWeber JYrbes NAME THarris/cv*
JCopeland DATE 2/19/98 2/V98 2/19/98 2/MP98 2/20/98 2 8/98 2/2/98 unamammmuammmmmmemanas --- =
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2/J /98 DATE OFFICIAL RECORD COPY i
ACNW: YES 1 NO _
Category: Proprietary _ or CF Only _
IG:
YES 1 NO _
LSS:
YES _ NO 1 Delete file after distribution: Yes 1. No _
NRC FILE CENTER COPY i
K. Alkema If you have any questions or comments, please contact me at (301) 415-7234 or Mr. Tim Harris of my staff at (30 d) 415-6613.
Sincerely,
'h John W. N. Hickey, Chief Low-Level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards Docket No.: 070-3095
Enclosure:
As stated w/ attachments cc: William Sinclair, State of Utah r
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9 ACCEPTANCE nEVIEW ENVIROCARE OF UTAH, INC.
PART 70 LICENSE APPLICATION DATED DECEMBER 5,1997 The following documents our acceptance review of the 10 CFR Part 70 license application submitted by Envirocare of Utah, Inc., dated December 5,1997. The draft Standard Review Plan (SRP) (NUREG-1520), dated March 1995, was used as guidance for this acccptance review. Comments on the deficiencies and omissions are divided into the topic areas outlined in the license application. Considering that this review was administrative, other deficiencies or omissions in addition to those listed below may be identified in future reviews. The applicant is advised to use the SRP as guidance in revising the application.
1 General Information 1.1 The exact scope of the requested license is unclear with respect to treatment of waste.
From Section 1.1, it appears that treatment is a requested activity; however, other discussions in Section 1 appear
- 2xclude treatment. The applicant should clarify this point and revise the application, as appropriate.
1.2 The basic structure of the application refers the major technical areas to appendices that contain the safety manuals, internal procedures, and State / local licensing permits. This structure does not facilitate an efficient safety review by the NRC, because it is not clear if the applicant is committing to these documents, or if the documents are provided for inform #. ion only. Safety commitments and requirements should be clearly indicated in the application.
Normally intemal procedures and licensing permits would not become part of the license commitments.
1.3 The process description (1.2.4) appears incomplete. The applicant should provide a detailed narrative of the various activities associated with low activity radioactive waste and mixed waste (MW). The applicant should discuss in specific detail the various types of processing of MW, which are currently licensed by the State of Utah, including a description of equipment used in the processing in accordance with 10 CFR 70.22(a)(7).
1.4 The applicant should orovide a more detailed description of the types 'and forms of the waste, which are to be licensed.
2 Manaaement Oroanization No deficiencies or omissions were identified.
3 C.onduct of Ooerations 3.1 Section 3.8 " Procedures" listed in the Table of Contents is omitted from the license application.
Enclosure
3.2 Records Management (SRP 3.8) is not addressed in the license application.
4 Integrated Safety Analysis 4.1 The Safety Assessment (Appendix AA) does not meet the minimum requirements for an Integrated Safety Analysis. The analysis does not address waste processing. The application lacks an adequate process description. The types of accidents identified or assessed do not include potential criticality or chemical accidents. The application also does not identify safety controls.
4.2 The application does not provide a systematic methodology for accident identification or
- analysis.
5 Radiation Safetv No deficiencies or omissions were identified.
6 Nuclear Criticality Safetv 6.1 The applicant should justify the maximum credible values of waste concentrations, masses, moderation, and other criticality parameters of the waste that are assumed in establishing that the waste will be subcritical under all credible conditions.
6.2 For the possession and use of special nuclear material under 10 CFR Part 70, the criticality analysis needs to show how all waste forms, all processing steps, and all storage configurations will be suberitical under all normal and credible abnormal conditions. In particular, storage of multiple loads, each in compliance with limits, so as to cumulatively form a critical array needs to be used to establish limits for the individual loads or units of waste.
6.3 The applicant should justify the maximum credible concentration of uranium is 1 gm/ liter as stated, considering all credible waste forms and operations at the site. The reliability of measurements, administrative procedures, and other controls used to assure that the conditions of subcriticality are maintained for all these operations needs to be assessed and described.
6.4 The processing operations do not appear to be described or limited in the application.
For criticality control, either the permissible waste forms need to be limited, with the limits stated, or bounding cases justified.
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Chemical Safetv 7.1 The application contains general statements about assurance of chemical safety, but lacks specifics about what processes are occurring.
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1 7.2 The applicant should identify the chemical processes including process descriptions, flow diagrams, process chemistry, process variables, and process limits of operation.
7.3 The applicant should identify the chemical risk including identifying potential chemical hazards.
7.4 Tho applicant should identify the chemical safety controls used to prevent or mitigate potential accidents including equipment, materials of construction, piping, and process control systems.
8 Fire Safety The fire safety acceptance review of the Envirocare license application was conducted against the Branch Technical Position, " Guidance on Fire Protection for Fuel Cycle Facilities," Federal Register (57 FR 35607-13), dated August 10,1993 (Attachment 1).
8.1 The applicant should describe the following in sufficient detail: Fire Protection Program, Administrative Controls, Facility Design, Fire Hazards Analysis, Process Fire Safety, Pre-Fire Planning, Fire Detection and Alarm, Fire Suppression, and Emergency Response.
8.2 Commitments to codes and standards were not specific. Information on the fire suppression systems conflicted between the license application and back-up material.
9 Emergency & Contingency Plan The applicant's Emergency Management Plan was reviewed against the requirements of 10 CFR 70.22(i) and the recommendations of Regulatory Guide 3.67, " Standard Format and Content for Emergency Plans for Fuel Cycle and Material Facilities" (Attachment 2).
9.1 The applicant should either provide an evaluation of the maximum dose to a member of the public offsite due to a release of radioactiv7 material would not exceed 1 rem effective dose equivalent or an intake of 2 milligrams of solubm uranium, or submit a stand-alone emergency plan with the information outlined in 10 CFR 70.22(i) and Regulatory Guide 3.67.
10 Environmental Monitoring & Surveillance No deficiencies or omissions were identified.
11 Decommissionino No deficiencies or omissions were identified.
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I Environmental Report On page 39, the right edge of Table 4.10 is omitted. Also, the Environmental Report references appendices in both the Environmental Report and License Application without distinguishing between the two. References to appendices in the License Application should be so noted to eliminate confusion.
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9 ATfACHMENT 1 i
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t 7590-01 Guidance on Fire Protection for
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Fuel Cycle Facilities AGENCY:. Nuclear Regulatory Commission (NRC).
ACTION:
Guidance to applicants and licensees for preparing license applications and conducting operations.
SUMMARY
- This notice provides guidance on fire protection for fuel cycle fact;f ties in the form of a Technical Position. The Technical Position will be admin Stered by the Fuel Cycle Safety Branch, Division of Industrial and Medical Nucler Safety, Office of Nuclear Material Safety and Safeguards.
l FOR FURTHER INFORMATION CONTACT: Amar Datta, Fuel Cycle Safety Branch, Division of Industrial and Medical.Nucisar Safety, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555, (301) 504-2536.
SUPPLEMENTARY INFORMATION:
In the Federal Reaister (54 FR 11590-98) dated March 21, 1989, the NRC published for comment four Branch Technical Positions -- Guidance on Management Controls / Quality Assurance, Requirements for Operation, Chemical Safety, and Fire Protection for Fuel Cycle Facilities.
After consideration of the comments received and the experience gained in using these Technical Positions, the NRC has decided to revise and reissue the Technical Position on Fire Protection for Fuel Cycle Facilities.
It is the NRC's intent that this revised Technical Position would serve as a source of information for applic its and licen h.:
n the features of equipment, facilities, and procedures that can be used to provide reasonable assuranca of fire safety for fuel cycle facilities.
It would provide guidance for implementing fire protection programs at these facilities that would be acceptable to the NRC staff as having the elements necessary to protect health and minimize danger to life or property.
It would thus also provide information to the staff in reviewing applications and inspecting facilities.
The information contained herein reflects the NRC staff's views concerning good industry practice. However, the provisions of this Technical Position do not constitute requirements. Other approaches to the selection of equipment, QWi ~h y pp
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design of facilities, and oporational procedures are acceptable, provided that they grant equal or higher levels of protection of health and safety.
TECHNICAL POSITION j
ON FIRE PROTECTION FOR FUEL CYCLE FACILITIES I.
INTRODbCTION To be approved by the NRC, any application for a license to possess and use licensed materials at a fuel cycle facility must provide information showing that the applicant's proposed equipment, facilities, and procedures are adequate to protect health and minimize danger to life or property.
In the area of fire protection, the staff has in the past generally accepted compliance with local building codes and proof of insurance as sufficient information for approval of license applications.
In addition, ad hoc measures have been taken in response to the staff's inspection findings relating to specific facilities. However, following an accident at a uranium hexafluoride production facility, the NRC undertook a major review of the operational safety of fuel cycle facilities.
Both the recommendations of the Materials Safety Regulation Review Study Group,' appointed by the NRC, and an independent staff action to assess operational safety at each of 12 major fuel cycle facilities licensed by the NRC, led the staff to the finding that fire protection is one of the most important safety concerns.
This finu > coupled
'th the experience of the applicants and the staff 4 their respective roles of operation and regulation of fuel cycle facilities, led to the formulation of this Technical Position (TP), which is intended to provide guidance to applicants and staff in the area of fuel cycle facility fire protection. This TP provides recommendations and guidelines for implementing acceptable fire protection programs at fuel cycle facilities and has elements that are intended to ensure protection of health and minimize danger to life and property.
The guidance should not, however, be considered l
mandatory, and nothing should preclude a licensee from adopting a program that 2
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O is prudent and employs other techniques of fire protection that meet or exceed these guidelines.
II.
DISCUSSION 4
1.
Fire Protection Concent l
The concept of fire protection presented by this TP consists of measures that will achieve a balance among the following:
Prevention of fires, Detection of fires, and
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Containment and suppression of fires.
A discussion of these three levels of fire protection follows:
a.
Fire Prevention: Fire prevention measures at a fuel cycle facility should start with the design of the buildings, structures, systems, l
components, and processes involved in the storage, handling, and processing of the radioactive materials and chemicals used in the processes.
The processes should be designed and physically laid out so I
as to minimize the possibility of overheating, over-pressurization, leakage, and the confluence of combustibles and ignition sources except where required by the process.
Even with the most well-designed facility, prevention of fires depends to a great extent on foll wing good housek:.. ping pract.ces and operating personnel scrupuloust following sdet, instructions.
i b.
Fire Detection: The best fire prevention measures may occasionally l
fail, in which case an effective fire detection system would detect the j
occurrence of fire and activate alarm systems so that measures for containment and suppression of the fire and personnel evacuation may start promptly. The type and location of the detectors would depend on the type of hazard. The installation of a fire detection and alarm 3
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system is especially important where personnel presence is infrequent and the fire hazard is moderate or high.
c.
Containment and Suppression of Fire: Containment of fire in its area of origin and prevention of its spread to new areas and new combustibles is one of the first steps to be taken upon detection of a fire.
This is achieved by activating systems such as barriers, ventilation dampers, exhaust fans, and drainage pumps to prevent migration of gases, hot combustion products, and flammable liquids to new areas.
Fire suppression activities should start at the same time as barrier systems are activated. The media employed in the suppression and the means of their delivery to the fire source and to heated areas and substances depend on the plant area and the processes and equipment protected.
The concerns for nuclear criticality safety, chemical safety, and the danger to personnel from non-life-supporting extinguishing media, such as carbon dioxide, should all be taken into account in planning a fire suppression system.
2.
Fire Hazard Analysis t
A number of fuel cycle facilities already in operation may not have all of the design and construction features considered desirable for fire protection.
For such facilities, it is prudent to perform systematic fire hazard analyses of their operations. Such analyses could be expected either to reveal fire l
protection weaknessee or to confirm the adequacy of the protection measures.
Where weaknesses are ind'catt2, they may be c:rrected by a judicious combination of facility modification and additional fire protection measures.
Also, the licensed activities, processes, or buildings of operating facilities may from time to time be modified. Whenever this happens, the fire hazard analyses should be updated. Otherwise, these should be reviewed and updated at regular intervals of time.
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I III. POSITION 1.
Fire Protection Proare 4
The licensee should establish and iaplement a Fire Protection Program.
The
.I program should reflect' a comitment to perform tasks to ensure that the j
equipment and facilities are maintained in proper condition to prevent fires from occurring, maintain awareness of fire safety procedures among the i
employees and ensure compliance with those procedures, and maintain a readiness. if a fire does occur, to implement emergency procedures to suppress it and mitigate the consequences.
The program would be expected to '.clude an appropriate set 'of the following components:
Establishment of a Fire Safety Review Comittee and a' definition of its a.
duties, frequency of meetings, frequency of plant audits, and responsibilities for reporting and recordkeeping.
(A plant safety comittee may function as the Fire Safety Review Comittee.)
b.
Initiation of a Fire Hazard Analysis of the facility and its periodic l
updating.
Maintenance of the facility and equipment in proper condition to prevent c.
fires from occurring.
d.
Review and control of modifications of the facility or processes to minimize-fire hazard.
Review and control of hazardous operations, such s welding and torch-e.
cutting, and any nonroutine use of flamable or combustible materials.
f.
Routine inspection, testing, and maintenance of all fire protection
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equipment.
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g.
Training of all employees in basic fire safety and of a selected group to respond to fire emergencies.
(The latter group may be part of the plant emergency response team.)
h.
Reporting and investigation of fire incidents.
1.
Periodic performance of fire drills.
J.
Rules for good housekeeping with a view to minimizing fire danger.
2.
Administrative Controls J
Prooram Manaaement 2.1 The licensee should ensure adequate management and supervisory attention to fire protection. The overall management of an adequate program would be expected to be under the direction and control of a senior level individual, who should be given the authority and staff assistance to l
implement measures relating to fire protection throughout the facility.
Actual implementation of the day-to-day tasks of the program should be supervised by an individual having sufficient qualifications and practical experience in fire protection.
2.2 Plant Audits plant audits of fire protection should b2 performed at two levels a follows:
a.
Monthly audits (walk-downs) to detect and correct departures from good housekeeping practices or operating procedures that may impact fire safety.
b.
Annual audits by the Fire Safety Review Committee, including plant walkdowns, to review proper functioning of the Fire Protection Program and generally the overall fire safety of the facility.
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3.
Buildina Construction 3.1 Construction Standard
' Type I construction, as classified by NFPA 220, Types of Building Construction, is considered adequately firesafe for the process
' buildings of the facility.. (The National Fire Protection Association (NFPA) documents cited in the text are listed in the reference section in the order of their NFPA numbers.) This standard specifies that the structural members of the buildings, including walls, columns, beams, floors, and roofs, are to be constructed of approved noncombustible or limited combustible materials and have specified minimum fire resistante ratings. If nonprocess areas are hmised in the same or adjoining buildings, the er. tire building complex should be the equivalent of a Type I construction.
i 3.2 Fire Areas To confine fire in its area of origin and prevent its spread, areas containing processes or materials involving fire hazards should be
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1 separated by structural barriers into fire areas.
In particular, j
solvent extraction areas, boiler rooms, incinerators, warehouses, control rooms, switchgear rooms, computer rooms, maintenance shops, fire pump areas, and office areas should be separate fire areas.
Structural brriers, including walls, floors, ceilings, and roofs, that bound fire 4.ea., should have appropriate fire resistance ratings.
Boundaries-ef such fire areas may coincide with zones the facility is divided into, based, where such zoning exists, on radiotoxicity of the materials handled therein.
Openings in the barriers that are boundaries of fire areas should have devices, such as fire doors and fire stops, installed in them. Such devices should have at least the same fire resistance ratings as the barriers in which they are installed.
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I 3.3 fy.ppsure Fire Risk When a process building is close to other buildings or installations with flamable, combustible, or reactive liquid or gas storage, the risk of exposure fires originating in those installations to the process building concerned *,hould be evaluated and appropriate protection measures should be taken. NFPA 80A, Protection of Buildings from Exterior Fire Exposures, provides guidance on protection from such exposures. NFiA 30, Flammable and Combustible Liquids Code, lists minimum separation distances from tank storages.
3.4 Personnel Earess The building design should provioe for safe means of egress for i
personnel in the event of a f,re emergency.
Egress routes should be clearly marked. NFPA 101, Safety to Life from Fire in Buildings and Structures, provides guidance on egress design and protection of egress routes.
3.5 Smoke Vents I
If the building has undivided floor areas that are not provided with j
means of automatic fire suppression and are large enough that hose j
streams directed from outside may not reach all parts of the areas, l
mitigating features, such as smoke vents and curtain boards, should be provided. NFPA 204M, Smoke and Heat Venting, may be censultec.
i 3.6 Hidden Soaces l
Concealed spaces should be devoid of combustibles as far as practicable.
Suspended ceilings and their supports, insulation for pipes and ducts, and sound-attenuating materials should be noncombustible. All cracks or openings in floors leading to inaccessible under-floor spaces should be sealed.
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3.7 Lightnino Protection Provision should be made for pr3tecting the facility from lightning damage. Guidance for the installation of such protection is provided by NFPA 78, Lightning Protection Code.
3.8 Drainaae Provisions Floor drains, sized to remove anticipated quantities of fire-fighting water, should be provided in process areas. Drainage from areas containing hazardous chemicals or radioactive materials should be co'llected in sumps for sampling and treatment before release to the environment.
3.9 Electric Installations All electrical wiring and installations should be made, used, and maintained in accordance with industry standards, such as NFPA 70, National Electrical Code, and other standards that apply to special situations, such as NFPA 70E, Electric Safety Requirements for Employee Work-places; NFPA 79, Electrical Standard for Industrial Machinery; and NFPA 75, Electrical Computer / Data Processing Equipment.
4.
Ventilation System
4.1 Ventil
ion System De:: ;-
The ventilation system should be designed to isolate affected areas during fire accidents and te provide channels for exhausting fire products, through filters if necessary, to outside the plant. NFPA Standard 90A, Air Conditioning and Ventilating Systems, may be consulted on ventilation design for f;eu protection.
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4.2 HEPA Filters When a ventilation system is required to prevent the release of radioactive material to the atmosphere, all materials of construction for the system should be noncombustible. HEPA filters should conform with industry standards, such as Underwriters Laboratories Standard VL-586 (also designated ANSI B 132.1), High Efficiency Air Filtration Units.
4.3 Barrier Penetrations Whenever the ventilation duct system penetrates a fire-rated barrier, a fire damper, having a fire resistance rating at least equal to that required of the barrier, should be installed in the duct.
Guidance will be found in UL 555, Standard for Fire Dampers and Ceiling Dampers.
4.4 Automatic Cloting All fire doors, fire dampers, and ceiling campers should close automatically, and should remain closed, upon operation of a fusible link or other heat-actuated device.
4.5 Heatina Furnatti Heating furnaces that are combined with ventilation systems should be
- , stalled in a ordance with industry standards, such as NFPA 54 (AN54
.46.), Nation 4 Fuel Gas Code, if gas fired, or NFPA 31, Oil Burning Equipment, -if oil fired. Guidance for the installation of electrical duct heaters will be found in NFPA 70, National Electrical Code.
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5.
Process Fire Safety
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5.1 Some Chemicals and Their Fire Hazards The process chemicals listed below are those that are used in bulk quantities in fuel cycle facilities and also are fire hazards.
5.1.1 Nitric Acid Nitric acid is itself noncombustible, but under certain conditions, it nitrates cellulosic and other organic :naterials, making them easily ignitible. A nitric acid spill thus constitutes a fire hazard, in addition to being a corrosion and toxicity hazard.
5.1.2 Sulfuric Acid In addition to its corrosion and toxicity hazard, this chemical has the property of absorbing water from organic materials accompanied by q
exothermic reaction, which may ignite the organic materials.
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1 5.1.3 Anhydrous Ammonia One of the uses of this chemical is as a source material for the production of hydrogen for use in reduction processes.
It is a flammable gas, which is storeo and pumped in the liquified s'.te, and undergoes d.ssociatic.. into hydrogen a..) nitrogen in a hig.. * :.p atur e dissociator at about 1650*F. Anhydrous ammonia is flammable and presents, if ignited in a confined space, an explosion hazard.
It also 1
presents a toxicity hazard.
5.1.4 Hydroaen Hydrogen has a high burning velocity and also a wide flammable range in mixtures with air. A small hydrogen flame, as at a leak from a pipe, is bluish and almost invisible. The hazards of fire and explosion are high 11
in the event of a leak from any equipment that contains or uses hydrogen. Additionally, there is the hazard of explosion in vessels and furnaces where explosive mixtures of hydrogen and an oxidizer may form inadvertently.
5.1.5 Fluorine Fluorine is one of the most reactive elements known. Apart from its being highly corrosive and toxic, it reacts violently with hydrogen and many organic materials and causes fires, even though it is itself nonflammable. Fluorine may al:;o cause explosion in contact with metallic powders and water vapor.
5.2 Processes Involvina Use of Flammable Liouids and Gases 5.2.1 Processes involving solvents or other chemical substances, that may be classified as flamable liquids according to NFPA 321, Classification of Flammable and Combustible Liquids, should be isolated from each other and from the remainder of the facility by locating them either in separate buildings or in spaces enclosed by barriers having a minimum fire resistance rating of I hour.
5.2.2 All electric motors, switchgears, lighting, and other electrical installations in these process areas should be of the explosion-proof type. NFPA 70, National Electrical Code, provides guidance.
5.2.3 No open flame should be permitted in these areas. Construction or maintenance work involving torch-cutting or welding may be permitted only when the process is shut down, the inventory of flamable and combustible materials is at a minimum, and safety measures, such as fire watches, are implemented.
NFPA 518, Fire Prevention in the Use of Cutting and Welding, provides guidance.
5.2.4 The process areas should be provided wi e automatic fire detection and automatic explosion prevention / suppression systems.
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69, Explosion Nevention Systems, provides guidance on design, selection, and installation of such systems.
5.2.5 Ovens or furnaces that use hydrogen as atmosphere and have a hydrogen burner (and usually also have a natural gas pilot burner) should have a flame-supervision system.
Such a system should activate a 4
visual and/or an audible alarm and should shut off the hydrogen supply upon loss of flame. NFPA 86C, Industrial Furnaces Using a Special Processing Atmosphere, provides guidance.
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5.2.6 Where a process involving a flammable liquid or gas must be in i
the same fire area as an ignition source, such as an open flame, one or more analyzers should be in-+.alled strategically to monitor the flammable or combustible vapor or gas concentration in the air.
The analyzers should activate both visible and audible alarms whenever the
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vapor concentration exceeds a set limit, for example 10 percent of the lower flammable limit. Simultaneously, ignition and heat sources in the area should be turned off automatically.
5.3 Fire Hazard in the Handlino of Uranium Oxides Uranium oxide powder, usually following a calcining or a blending process and sometimes when heated by process machinery, may undergo spontaneous exothermic chemical reaction. Such "unstablized" powder is known to have ignited combustible components of transfer passages and mechanical hindli.1g machinery, such as vinyl ;ipes, flexible "ecprne boots and parts of valves, and nylon parts of conveyors.
Such component Lshould be made of noncombustible materials, as far as
,.racticable, or of materials having sufficiently high ignition temperatures and resistance to heat-degradation.
5.4 Machinino Ooerations of Combustible Metals L
5.4.1 Metals, such as uranium, magnesium, titanium, and zirconium, and their alloys, are known to be combustible, especially when in a finely 13
divided form. Machining operations in the facility should, therefore, be evaluated for the potential for combustible dust cloud formation and combustible scrap and swarf accumulation from operations, such as sawing, grinding, machining, and abrasive cutting.
Fire protaction measures for all of these metals are similar. NFPA 480, NFPA 481, and NFPA 482, Standards for the Production, Processing, Handling and Storage of Magnesium, Titanium, and Zirconium, respectively, provide guidance.
5.4.2 No open flames should be permitted in the areas where machining operations of combustible metals are performed.
If maintenance operations, such as. welding, are to be performed in the vicinity, machining operations should be halted and metal scraps should be removed.
5.4.3 Machining operations producing fine particles of combustible metals should be performed in enclosures with a dust collection system in operation.
The dust-laden air should be ducted to a dust collector and, if required, a HEPA filter for removal of radioactive particles.
The collection hood and duct leading to the filter should be designed to minimize deposition of the fines and to facilitate cleaning. A liquid precipitation separator is the preferred type of dust collector.
5.4.4 Each dust-producing machine should be equipped with its own dust separator unit, as far as practicable.
5.4.3 Scrap snd swarf generated by machining operations, and accumulated in the innediate area, and dust and sludge collected in the dust separators and ducts should be removed as often as necessary, but at least once a day.
5.4.6 Extinguishing agents suitable for the particular metal fire, as well as suitable scoops or applicators for the purpose, should be readily available to the operator performing the machining.
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! o 5.5 Incinerators 5.5.1 Incinerators should be separated from the remainder of the facility by fire barriers having a minimum 1-hour fire resistance rating.
5.5.2 If.the incinerator is to burn radioactive-contaminated waste, its exhaust should be ducted to a sampling and filtration system before releasing it to the environment.
The exhaust may be ducted also to the facility off-gas system. Such ducts should be designed to minimize deposition of particulate effluent and to facilitate cleaning.
5.5.3 Depending on the temperature of the exhaust, a cooling water spray or passage through a liquid precipitation separator may be needed for both cooling and dust separation.
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5.6 Boilers and Boiler-Furnaces I
i 5.6.1 Boilers for the supply of steam for process operations and
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boi'.er-furnaces should be separated from the remainder of the facility by fire barriers that have a minimum 1-hour fire resistance rating.
1 5.6.2 The construction and operation of the boiler-furnaces should comply with industry standards, such as the relevant standards in the NFPA 65 serses, dep>nding on the type of furnace and the fuel used.
i 5.6.3 The-fuel storage tanks should be separated from the furnace area l
by fire barriers that have a minimum 1-hour fire resistance rating.
The fuel lines should be laid out to minimize the possibility of damage and should be clearly marked.
l l
15 l
[
l
5.7 Stationary Combustion Enoinet 5.7.1 Stationary combustion engines, if located in part of a structure housing fuel cycle processes, should he in enclosures that have a fire resistance rating of at least I hour.
5.7.2 Rooms housing stationary combustion engines should be of noncombustible construction or, if combustible materials are used, should be protected by automatic fire suppression systems.
5.7.3 Process-generated dust or flammable vapors should be limited in the room when the engine is operating.
5.7.4 Fuel storage tanks, except fo: Jay tanks, should be located outside the room and should be constructed in accordance with industry standards, such as NFPA 30, Flammable and Combustible Liquids Code.
Guidance on the construction and capacities of unenclosed day tanks will be found in NFPA 37, Stationary Combustion Engines and Gas Turbines.
5.7.5 The engine exhaust system should be designed to prevent ignition of any combustible material by contact with the hot metal surfaces or by leaking exhaust gases or sparks.
5.7.6 The stationary combustion engine room should be ventilated effectively to minimize accumulation of combustible vapor and the possibility of explosion.
NFPA 37 prov;Jas guidance.
5.8 Storaoe and Handlina of Flammable and Combustible Liouids and Gases 5.8.1 The construction, installation, operation, and maintenance of combustible liqui a storage and the related loading and dispensing systems should comply with industry standards, such as NFPA 30, F1ammable and Combustible Liquids Code.
16
5.8.2 Indoor storage of flammable and combustible liquids may be o
permitted in limited quantities in approved closed containers for day use and maintenance work or for diesel engine operation. Appropriate portable fire extinguishers should be on hand at such locations.
5.8.3 Steel supports of aboveground storage tanks should be protected from exposure fires, if dictated by the proximity of other flammable or combustible liquid storage tanks, location in a common diked area, or proximity of a tank-truck loading and unloading area.
5.8.4 In addition to normal operating vents, some aboveground storage tanks may require emergency relief venting.
NFPA 30 provides guidance on this matter.
5.8.5 The construction, installatior., operation, and maintenance of j
bulk gas (including liquified gas) storage and the related loading and dispensing systems should comply with good industry practice, such as NFPA 50, Bulk Oxygen Systems at Consumer Sites; NFPA 508, Liquified Hydrogen Systems I,t Consumer Sites; and NFPA 54, National Fuel Gas Code.
5.9 Hot Cells 1
5.9.1 The construction materials for hot cells should be noncombustible. The internal surface coatings should be noncombustible -
or limited combustible.
5.9.2 The liquid-filled windows should contain a noncombustible medium.
Hydrauljg Duids in the master-slave manipulators should be nonflammable.
i l
5.9.3 Where process materials and equipment present a (ire hazard, the quantities of combustible materials and the sources of ignition should be maintained at the absolute minimum.
If flammable gases or vapors may be present in explosive proportions, an inert atmosphere should be provided when operating the hot cell.
17
1 5.9.4 If combustible materials are used in a hot cell, extinguishing agents that are compatible with the materials handled should be provided within the hot cell, together with their delivery systems. Nuclear criticality concerns should be considered in selecting extinguishing media.
5.9.5 Filters for the exhaust air from a hot cell should be of noncombustible construction.
5.9.6 Further guidance for hot cell fire protection is provided in NFPA 801, Facilities Handling Radioactive Materials.
5.10 Glove Boxes 5.10.1 The construction materials for glove boxes may be of the limited combustible type if only noncombustible process materials are used within them. Otherwise, except for the gloves, the glvse box should be of noncombustible construction.
5.10.2 If combustible material; are used or if there is the possibility of an explosive mixture forming within the glove box, the relevant guidance provided for hot cells should also apply to glove boxes.
5.10.3 If a number of glove boxes see operated in series, fire dampers
- ba"id be pre 'ded at intervals to impede propagation of fire.
5.11 Labaratories The fire protection methods of labcratories handling radioactive materials are similar to those of chemical laboratories. Guidance is provided in NFPA 45, Fire Protection for Laboratories Using Chemicals.
18
6.
Fire Detection and' Alarm Systems 6.1-Automatic Fire Detectors Automatic fire detectors of appropriate types should be installed in all areas with substantial combustibles'that are infrequently visited or occupied only part of the 24-hour-day, unless such areas are covered by automatic fire suppression systems.
6.2 Vanor and Gas Detectors Automatic flammable vapor and gas detectors should be installed in areas where there is a potential for leakage of flammable liquids or gases.
6.3 Audible and Visible Alarms
~\\
Automatic fire detectors and flammable vapor or gas detectors should
{
actuate audible and visible alarms in the area of ori9n of the alarm, as well as at a central monitoring station that is constantly supervised. Actuation of any fire suppression system, such as flow through a sprinkler system, should also actuate visible and audible 4
al arms. The central monitoring stations should have continuous information on the status and functioning of the fire detection systems, combustible vapor / gas detection systems, and automatic fire suppression systems, including a zone indication of the origin of an air T.
These systems she,1d comp 1. with industry st9dards, such as NFTA "O
{
Installatica,..aintenance, and Use of Notification Appliances for ProtectivenSignaling Systems; and NFPA 72E, Automatic Fire Detectors.
i 6.4 Manual Fire Alarms Manual fire alarm actuators (pull-boxes) or telephones should be available at strategic locations, for example, near exits from the j
various facility areas.
19 l
t 7.
Fire Sunoression Eouloment 7.1 Selection of Eauioment The selection of the specific equipment for suppression of fire in an area should take into account the severity of the hazard, type of activity performed in the. area, nuclear criticality concerns, the consequences of a fire (e.g., the risk of release of radioactive material), and the consequences of spurious actuation of an automatic l
suppression system.
7.2 Automatic Sorinkler Systems Automatic water-sprinkler coverage is the preferred method of fire suppression for most areas that have significant fire hazard.
The notable exceptions are areas where accidental nuclear criticality is a concern and areas with a concentration of energized electric equipment, including computer installations and control rooms. NFPA 13, Installation of Sprinkler Systems, provides guidance on selection and design of sprinkler systems.
7.3 Gas or Foam Suporession Systems Plant areas that have a significant fire hazard, but where water is unsuitable a a suppression agent, should be protected by other systems that employ fire supp.ession agents such as inert gases, carbon dioxide, halon, and high-or low-expansion foam. Guidance on carbon dioxide and halon systems is provided in NFPA 12 and NFPA 12A, respectively.
Guidance on the selection and design of foam systems is provided in NFPA 11 and NFPA 11A.
Selection of gaseous suppression systems should take into account protection of personnel and possible pressurization of the enclosure.
20
T 4
7.4 Standnice and Hose Systems Standpipe and hose systems should have readily accessible hose outlet locations. Guidance on standpipe and hose systems is provided in NFPA 14, Installation of Standpipe and Hose Systems.
7.5 Portable Fire Extinauishers Portable fire extinguishers, suitable in capacity and type of suppression agent used, should be available throughout the facility, regardless of the availability of any other fire suppression' system.
The number and capacity of such extinguishers and their-deployment should be in accordance with industry standards, such as NFPA 10, Portable Fire Extinguishers.
8.
Fire Protection Water System 8.1 Water Sucoly An adequate supply of water for the installed fire protection systems should be ensured. Additional fire-fighting water that may be needed by an offsite fire department should be planned for in consultation with them. Compatible connections should be provided for offsite fire department use.
The fire-water distribution system should be designed and constructed for high reliability.
NFPA 24, Private Fire Se-vice Mains and Thair Appurtenances, should be used for guidance.
8.2 Fire.Pumn Installation The fire pump installation should be adequate to deliver water at full design pressure to the farthest hydrant, standpipe and hose station, or sprinkler system.
The installation should be in accordance with industry standards, such as NFPA 20, Inscallation of Centrifugal Fire Pumps.
21
I 8.3 Alternative Power for Pumos Provision should be made for alternative sources of power for fire pumps, so that failure of one source will not disable the installation.
A diesel engine-driven pump is typically used as an alternative to an electrically driven one.
8.4 Water Distribution System The water distribution system should be designed so that the failure of a single component (e.g., a pump or valve) will not hamper the ability to deliver fire-fighting water to any part of the facility.
9.
Fire Hazard Analysis 9.1 A Fire Hazard Analysis of the facility should be performed.
Such a systematic analysis should divide the facility into " fire areas." and. valuate the fire safety of each area and of the facility as a whole. The analysis should, for each fire area:
a.
account for all radioactive and combustible materials, including estimat's of their heat content; b.
describe the processes performed and their potential for fire or explosion; c.
account ror the sources o# heat and flame; d.
list the fire detection and suppression equipment; and e.
consider credible fire scenarios and evaluate the adequacy of the fire protection measures.
The analysis should then either conclude that the facility as a whole is adequately protected or list the deficiencies that should be corrected.
22
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9.2 The deficiencies identified by the Fire Hazard Analysis should be corrected expeditiously. The analysis should then be reviewed by the responsible management official and revised to indicate that it is acceptable.
9.3 The Fire Hazard Analysis should be updated at periodic intervals (for example, every 2 years) and whenever there has been a significant modification of the facility, processes, or inventories.
10.
Pre-Fire Plan 10.1 Purcose The facility should have on file, and ready to use, a Pre-Fire Plan.
j Fire emergency planning is sometimes encompassed in the general radiological emergency planning required by license condition. However, a Pre-Fire Plan is different from a Radiological Contingency Plan in 3
that it provides information needed by fire-fighting personnel responding to an emergency. Often, the sau.e team of employees is trained to respond to both fire and radiological emergencies.
This is acceptable, since a fire emergency may turn out to be a radiological emergency as well.
10.2 Contents The Pre-Fire Fl n should assign individual and alternate responsibilities for responding to a fire alarm or call; assessing the situation; suppressing incipient fires; assembling the site Fire l
Emergency Response Team and, if necessary, requesting offsite fire department assistance; personnel evacuation; orderly shutdown of l
processes; and safeguarding and control of radioactive material. The plan should clearly indicate, preferably with the help of site plans and drawings, the locations of the fire department-compatible connections and fire-fighting equipment, such as portable extinguishers, automatic 23
fire suppression systems, sectional valves, standpipes, hydrants, and hoses.
It should also indicate the areas of concentration of combustibles, storages of flammable and combustible liquids, and areas where use of water for fire suppression is restricted because of nuclear criticality or other concerns.
10.3 Coordination with the Offsite Fire Decartment The Pre-Fire Plan should be prepared in consultation and coordination with the offsite fire department (s) most likely to respond to a call for assistance. The offsite fire department personnel should be given familiarization tours of the facility at least once a year.
11.
Fire Emeraency Resocnse Team 11.1 Oraanization The organization, training, and equipment of the Fire Emergency Response Team should be adequate to respond to any credible fire emergency, with assistance from offsite fire departments where such assistance is available.
NFPA 600, Private Fire Brigades, should be used for guidance.
11.2 Trainina All members of the Fire Emergency Response leam should receiv. training adequate to perform their duties of responding to a fire emergency in the facility. NFPA 600 provides guidance on training and the frequency of refresher sessions and drills.
24
IV.
REFERENCES U.S. Nuclear Reculatory Commission Documents 1.
Federal Recister (51FR45122), Report of the Materials Safety Regulation Review Study Group, December 17, 1986.
i 2.
Results of Operational Safety Assessments at the Major Fuel Cycle Facilities: Memorandum from Hugh L. Thompson Jr., Director, Office of Nuclear Material Safety and Safeguards, to Victor Stello, Jr., Executive Director for Operations, U.S. Nuclear Regulatory Commission, July 1, 1987.
l 3.
NUREG 0800, Standard Review Plan 9.5.1, Guidelines for Fire Protection
{
for Nulcear Power Plants, Revision 2, July 1981.
4.
Federal Recister, Vol. 54, No. 53, Guidance on Management Controls /
Quality Assurance, Requirements for Operation, Chemical Safety, and Fire Protection for Fuel Cycle Facilities, March 1989.
k National Fire Protection Association Documents 5.
NFPA 10-1990, Portable Fire Extinguishers.
6.
NFPA 11-1988, 'ow Expansion F--
ind Combined Agent Systems.
7.
NFPA IIA-1988, Medium-and High-Expansion Foam Systems.
8.
NFPA 12-1989, Carbon Dioxide Extinguishing Systems.
j i
9.
NFPA 12A-1989, Halon 1301 Fire Extinguishing Agent Systems.
I l
10.
NFPA 128-1990, Halon 1211 Fire Extinguishing Systems.
L i
f 25 t
u
11.
NFPA 13-1989, Installation of Sprinkler Systems.
12.
NFPA 14-1990, Installation of Standpipe and Hose Systems.
13.
NFPA 15-1990, Water Spray Fixed Systems for Fire Protection.
14.
NFPA 16-1991, Deluge Foam-Water Sprinkler and Foam-Water Spray Systems.
15.
NFPA 20-1990, Installation of Centrifugal Fire Pumps.
16.
NFPA 24-1987, Private Fire Service Mains and Their Appurtenances.
17.
NFPA 30-1990, Flammable and Combustible Liquids Code.
18.
NFPA 31-1987, Oil Burning Equipment.
19.
NFPA 37-1990, Stationary Combustion Engines and Gas Turbines.
20.
NFPA 45-1986, Fire Protection for Laboratories Ustng Chemicals.
21.
NFPA 50-1990, 8ulk 0xygen Systems at Consumer Sites.
22.
NFPA 508-1989, Liquified Hydrogen Systems at Consurser Sites.
23.
NFPA 518-1989, Fire Prevention in Use of Cutting and Welding F*c sses.
24.
NFPA 54-1988, ANSI Z223.1-1988, National Fuel Gas Code.
25.
NFPA 69-1986, Explosion Prevention Systems.
26.
NFPA 70-1990, National Electrical Code.
27.
NFPA 70E-1988, Electrical Safety Requirements for Employee Workplaces.
26
28.
NFPA 72G-1989, The Installation, Maintenance and Use of Notification Appliances for Protective Signaling Systems.
29.
NFPA 72E-1990, Automatic Fire Detectors.
30.
NFPA 75-1989, Electronic Computer / Data Processing Equipment.
31.
NFPA 77-1988, Recommended Practice on Static Electricity.
32.
NFPA 78-1989, Lightning Protection Code.
33.
NFPA 79-1987, Industrial Machinery.
34.
NFPA 80-1990, Fire Doors and Windows.
35.
NFPA 80A-1987, Protection of Buildings from Exterior Fire Exposures.
36.
NFPA 85D-1989, Prevention of Furnace Explosions in Fuel Oil-Fired q
Multiple Burner Boilor-Furnaces.
37.
NFPA 86C-1987, Industrial Furnaces Using a Special Processing Atmosphere.
38.
NFPA 90A-1989, Air Conditioning and Ventilating Systems.
39.
-NFPA 908 '1.9, The In;tallation of War. Air Heating and A.
Conditioning Sy.tems.
40.
NFPA 101-1991, Safety to Life from Fire in Buildings and Structures.
41.
NFPA 204M-1991, Smoke and Heat Venting.
42.
NFPA 220-1985, Types of Building Construction.
43.
NFPA 251-1990, Fire Tests of Building Construction and Materials.
27
.t 44.
NFPA 321-1991, Classification of Flammable and Combustible Liquids.
45.
NFPA 600-1986, Private Fire Brigades.
46.
NFPA 801-1991, Facilities Handling Radioactive Materials.
47.
NFPA 803-1988, Recommended Fire Protection Practices for Light Water-Cooled Nuclear Reactors.
Other Documents 48.
American National Standards Institute (ANSI) N665-1985, Facilities for Fabricating Fuel for Light Water Reactors (LWR) - Fire Protection.
49.
ANSI /ASHRAE 15, Safety Cooa for Mechanical Refrigeration.
50.
American Society for Testing Materials (ASTM) E-84, Surface Burning Characteristics of Building Materials (1976).
51.
ASTM E-119, Fire Test of Building Construction and Materials (1976).
52.
Factory Mutual System Approval Guide - Equipment, Materials, Services for Conservation of Property.
53.
National Fire Protection Association, Fire Protection Handbook.
54.
Underwriters Laboratories (UL) 555, Standard for Fire Dampers and Ceiling. Dampers.
28
1*
6 55.
UL 586 (ANSI B 132.1), High Efficiency Air Filtration Units.
56.
UL Building Materials Directory.
Dated at Rockville, Maryland, this J9 of 1992.
R THE NUCLEAR REGULATORY COMMISSION
//d';/.
C4 John W. N. Hickey, Chief
)
Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS l
4 i
29
1 a
0 e
ATTACHMENT 2 I
)
1 b
1 a%
U.S. NUCLEAR REGULATORY COMMISSION January 1992 (p**gf) REGULATORY GUIDE f
OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 3.67 (Task DG-3005)
STANDARD FORMAT AND CONTENT FOR EMERGENCY PLANS FOR FUEL CYCLE AND MATERIALS FACILITIES A. INTRODUCTION maintain emergency preparedness capability. It should describe the records and reports that will be The Nuclear Regulatory Commission's (NRC's) maintamed. There should also be a section on recov-regulations in 10 CFR Part 30, " Rules of General Ap-er) after an accident, including -
s for restoring the plicability to Domestic Licensing of Byproduct Mate-facility to a safe condition.
]
rial"; Part 40, " Domestic Licensing of Source Mate-rial"; and Part 70, " Domestic Licensing of Special Detgiled, descriptive informau.on on processes.
Nuclear Material," require some fuel cycle and mate-matidin storage areas andqcontainers, ventilation, u
nals b.eensees to prepare emergency plans. The m. for-process controls, activity locations, vessels, and con-mation specified m this guide should be, cluded in finement of radioactive or other hazardous materials m
the licensee s emergency plan to comply with the may be necessary for the NRC to evaluate the re itements of 10 CFR 30.32(i)(3), 40.31(j)(3), or adequacy of the emergency plan. Detailed informa-
]
tion that would help response organizations assess
- WF This regulatory guide provides guidance accept.
accident consequences and estimate releases should be included in the plan. Other detailed information able to the NRC staff on the information to be in.
cluded in emergency plans and establishes a format that is needed primarily for the licensing review may for presenting the information. Use of a standard for-be submitted separately as a supplement to the plan or incorporated by reference to other licensing mat will help ensure uniformity and completeness in submittals.
the preparation of emergency plans.
An acceptable emergency plan should describe This regulatory guide supersedes Revision 1 of the licensed activities, the facility, and the types of NUREG-0762, " Standard Format and Content for accidents that might occur. It shouH provide informa-Emergency Plans for Fuel-Cycle and Materials Facili-tion on classifying postulated accidents and the licen-ties" (Ref.1). Licensees who prepared emergency see's procedures for notifying and coordinating with plans in accordance with NUREG-0762 should re-offsite authorities. The plan should provide informa-view their plans against this guide. Preparing plans in tion on emergency response measures that might be accordance with this guide will facilitne NRC review necessary, the equipment and facilities available to and approval of applications made pursuant to 10 respond to an emergency, and how the licensee will CFR 30.32, 40.31, or 70.22.
UsNRC REGUiATORY GUIDES The juldes are issued in the following ten troad divisions:
Regulatory Guides are issueo to describe and make availab6e to the ph inc methods acceptable to tre NRC staff of 6mplementeng specif6C parts
- 1. Power Reactors
- 6. Products of the Commission's regulations. to detensate techniques used by the
- 2. Research and Test Reactors
- 7. Transportation.
staff en evaluating specife problems or postulated accidents, or to pro.
- 3. Fuels and Materials Facilites
- 8. occupational Health vlos guidance to applacents. Regulatory Guides are not substitutes for
- 4. Environmental and Siting
- 9. Antitrust and F6nancial Review regulations, and tempilance with them is raot required. Methods and
- 5. Materials and Ptant Protection
- 10. General solutions different from those set out in the gu6 dos will be acceptat%e if they prov6de a basis for the fendings requisite to the issuance or contbrup ance of a permit or hcense by the commiss6on.
Copies of issued ou6das may be purchased from the Govemment Printing This guide was issued after consadoration of comments received from Office at tre current GPo pr6ce. Informat6cn on current GPO prices rnay the public. Comments and suggestions for improvements en these be obtained by contacting the Superintendent of occuments, U.S.
guides are encouraged at all times, and guedes will be revised. as ap.
Government Printing Offee, Post Office Box 37082. Wash 6ngton DC f2 propriate, to accommodate comments and to reflect new enformat6on or 20013-7082. telephone (202)275-2060 or (202)275-2171.
4y
.wenene..
\\
Written comments may be submitted is the Regulatory Publicatims issued guides may also be purchased from the National Technical infor-Branch, DFIPS, ADM, U.S. Nuclear Regulatory Comrnissen. Washeng-maten Service on a standing order basis. Details on this service may be tun. DC 20655.
obtained by writing NTIS, s285 Port Royal Road, Springfield, VA 22161.
e.
~
An effective response to an emergency compriscs Finally, the licensee should certify that it is in WHAT is to be done (procedures), BY WHOM (re-compliance with Title III of the Superfund Amend-sponse personnel), and WITH WHAT (equipment in ments and Reauthorization Act of 1986, Pub. L designated locations). The emergency plan reflects, in 99-499, entitled " Emergency Planning and Commu-general terms, the preplanning done in preparing to nity Right-to-Know Act of 1986," with respect to any cope with an emergency, but the details of the actual hazardous materials possessed at the plant site.
response are contained in the emergency plan's im-plementing procedures.
Any information collection activities mentoned n this regulatory guide are contained as requirements in 10 CFR Parts 30, 40, or 70, which provide the The implementing procedures are the heart of regulatory basis for this guide. The information col-the emergency response. They must be clear, precise, lection requirements in 10 CFR Parts 30,40, and 70 and easily understood. Each procedure should per-have been cleared under OMB Clearance Nos.
tain to a narrow, specific response action.
3150-0017, 3150-0020, and 3150-0009, respec-tively.
Throughout this guide, the licensee or applicant will be asked to describe procedures instead of sub-B. NRW mitting them to the NRC for approval. NRC uses this Graphical Presentations practice to eliminate the need for a license amend-ment every time the proced"res need to be changed.
Graphical presentations such as drawings, maps, Details contained in the procedures will need to be diagrams, sketches, and tables should be employed if changed from time to time. If each change in a proce-the information may be presented more accurately or dure reg red NRC approval, frequent and time-c nveniently by such means. Due concern should be consuming license amendments would be required.
taken to ensure that all information presented is leg-Therefore, the license is issued on the basis of the ible, that symbols are defined, and that scales are not descriptions of procedures in the emergency plan.
reduced to the extent that visual aids are necessary to The procedures may be changed within the scope of interpret pertinent items of information. These these descriptions. However, this practice makes it graphical presentations should be located in the sec-necessary for the licensee or applicant to give close tion where they are primarily discussed.
attention to the way the implementing procedures are R' ferences used may appear as footnotes to the e
described. In preparing the implementing procedures, page where discussed or at the end of each chapter.
the applicant should be aware that the NRC may re-view them during the licensing process and during in Physical Specifications spections to ensure that the procedures are current Paper size and workable and that they conform with the descrip-tions in the emergency plan.
(1) Text pages: 8-1/2 x 11 inches.
(2) Drawings and graphics: 8-1/2 x. inches; Any changes to the emergency plan th -
rease however, a larger size is acceptaba provided the effectiveness of the plan must ha"e NRL pproval the finished copy when folded does not ex-before implementation pursuant to 10 CFR 30.34(f),
ceed 8-1/2 x 11 inches.
40.35(f), and 70.32(i). The licensee may change the emergency plan without prior NRC approval if the Paper stock and ink. Suitable quality in sub-changes do not decrease the effectiveness of the plan.
stance, paper color, and ink density for handling and These changes should be submitted to the appropriate reproduction by microfilming or image-copying equip-NRC licensing office and to affected offsite response ment.
organizations within 'six months after the changes are Page margins. A margin of no less than 1 inch made. The submitta's should include the date the sho ild be maintained on the top, bottom, and bind-changes became effective.
ing ide of all pages submitted.
"I'"E The licensee is encouraged to have a single emer-gency plan to meet the requirements of State agencies (1) Composition: text pages should be single or the Community Right-To-Know Act as well as to spaced.
I comply with the regulations of the NRC. Additional (2) Typeface and style: should be suitable for mi-material to meet these other regulations should either crofilming or image-copying equipment.
be included in the plan or referenced in the licensee's emergercy plan submitted to the NRC. This addi-(3) Reproduction: may be mechanically or pho-tional material will be reviewed by the NRC only to tographically reproduced. All pages of text ensure that it does not diminish compliance with the should be printed on both sides and the im-NRC's requirements.
age printed head to head.
3.67-2
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Binding. Pages should be punched for standard 1.2 Description of Facility and Site 3-hole loose-leaf binders.
Provide a detailed drawing of the site for the H
Page numbering. Pages should be numbered with emergency plan. An enlarged duplicate of the draw-the digits corresponding to the chapter followed by a ing suitable for use as a wall map (24 x 30 inch mini-hyphen and a sequential number, e.g., the third page mum) should also be provided. The detailed drawing of Chapter 4 should be numbered 4-3. The chapter should be drawn to scale and show or indicate the numbers should correspond to the chapters in this following:
guide, Do not number the entire plan sequentially.
1.
Onsite and near-site structures with building
""mbers (if applicable) and descriptive List of E//ective Pages. A list of every page in the b
plan.and the effective revision number or revision date of each page should be provided as a means of 2.
A bar scale in both meters and feet.
December 1991 verifying that the plan is complete and current. The list should include the pages of any 3.
A compass indicating north, enclosures or attachments that are part of the plan.
4.
Roads and parking lots onsite and main roads Table of contents. A table of contents and an in-and highways near the site.
dex of key items should be included.
j 5.
Site boundaries, showing fencer ~d gates.
Procedures for Updating or Revising Pages 6.
Exhaust stacks, storage areas, retention Data and text should be updated or revised by Ponds, and other major site features.
replacing pages. The changed or revised portion on 7.
Rivers, lakes, streams, or other ground. water each page should be highlighted by a " change mdica-sources onsite and within approximately 1 tor mark consisting of a bold vertical line drawn m the margin opposite the binding margin. The line should be of the same length as the portion actually Provide a concise description of all site features changed.
affecting emergency response, including communica-na assusment centen, assemW and Mocadon All pages submitted to update, revise, or add ar:as, and process and storage areas. Identify any ad-pages to the plan should show the revision number or nal she kanes My to be d interet &cause revision date. Each revision should include a new list they are related to the safety of site operations. The of effective pages and an instruction sheet listing the emergency plan should include a list of all hazardous pages to be inserted and the pages to be removed.
chemicals used at the site, typical quantities pos-Readers should be instructed to check the plan sessed, locations of use and storage, and the hazard-against tha list of effective pages to venfy that the re-ous characteristics (radioactivity, pH, other) of mate-vised plan is complete.
rial in sediment and retentien ponds. The stack l
heights, typical stack flow rates, and the efficiencies C. EMERGENCY PLANS of any emission control devices should be summa-rized in the emergency plan to help response organi-1.
FACILITY DESCRIPTION zations assess releases.
The information in this section is to provide per-1.3 Description of Area Near the Site spective about the facility and the licensed activity such that the adequacy and appropriateness of the include a description of the principal characteris-licensee's emergenc/ planning, emergency organiza-tier of the area near the site at which licensed activi-tion, and emergency equipment can be evaluated, tin are conducted. Indicate the site on a general area map (approximately 10-mile radius) and on a United 1.1 Description of Licensed Activity States Geological Survey 7.5' topographical map *
(approximately 1-mile radius). Provide a map or aer-Present briefly the princip i aspects of the overall ial photograph indicating onsite structures and near-licensed activity. A general description of licensed s te structures (about 1-mile radius). On this photo-and other activities conducted at the facility, the loca-graph or map, include the following:
g tien of the facility, and the type, form, and quantities
(
of radioactive and other hazardous materials normally present should be included. Any radioactive materia!3
' Topographical rna s can be obtained from the U.S. Geologi-authorized under a State license should also be de-
[*oxT286'.$e#
[8022k She teie#Noke$u'rnbe'r nv scribed.
(303) 236-7477.
3.67-3
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Locations of population centers (towns, cit-2.2 Detection of Accidents les, office buildings, factories, schools, are-nas, stadiums, etc.):
Desch the means provided to detect and to g
alert the licensee,s operating staff of any abnormal j
2.
Locations of facilities that could present po-operating condition or of any other danger to safe op-tential protective action problems (schools, erations (e.g., a severe weather warning). For each arenas, stadiums, prisons, nursing homes, type of accident identified in the emergency plan, de-hospitals);
scribe the means of detecting the accident, the means of detecting any release of radioactive or other haz-3.
Identificat!on of primary routes for access of ardous material, the means of alerting the operating I
staff, and the anticipated response of the operating emergency equipment or for evacuation, as staff. Examples are visual observation, radiation well as potential impediments to traffic flow monitors, smoke detectors, process alarms, and criti-(rivers, drawbridges, railroad grade crossings, 4
etc.);
cality alarms. Indicate at what stage of the accident it would be detected. Also indicate if the area of the postulated accidents or remote readouts of alarms or 4.
Locations of fire stations, p9 ice stations, detectors located in such areas are under continuous hospitals, and other offsite emergency sup-visual observation.
port organizations (specify whether qualified to handle exposure to radioactive contamina-3.
CLASSIFICATION ANI# NOTIFICATION OF i
tion or toxic chemicals);
ACCIDENTS Accidents should be classified as an alert or a site 5.
The sites of potential emergency significance area emergency according to the definitions in 10 (e.g., liquefied petroleum gas (LPG) termi-CFR 30.4, 40.4, and 70.4. In its emergency plan and
{
nals, chemical plants, pipelines, electrical in coordination meetings with offsite authorities, the transformers, and underground cables);
licensee should convey the concept that fuel cycle and materials facilities do not present the same de-6.
Identification of the types of terrain and the gree of hazard (by orders of magnitude) as are pre-land use patterns around the site.
sented by nuclear power plants. Thus, the classifica-tion scheme for these facilities is different. The 2.
TYPES OF ACCIDENTS licensee should explain to offsite authorities the defi-nitions of accident severity and the expected response Emergency planning is concerned with individual actions associated with alert and site area emergency and organizational responses to a range of potential conditions. NUREG-1140, "A Regulatory Analysis accidents, including those accidents that have been on Emergency Preparedness for Fuel Cycle and Other hypothesized but that have a very low probability of Radioactive Material Licensees" (Ref. 2), contains a occurrence.
description of past incidents involving radioactive ma-terials.
2.1 Description of Postulated Accidents g
- g; g
Identify and describe each type of radioactive An alert is defined as an incident that has led or materials accident for which actions may be needed could lead to a release to the environment of radioac-to prevent or minimize exposure of persons offsite to tive or other hazardous material, but the release is not radiation or radioactive materials. Exposure levels at expected to require a response by an offsite response the site boundary should be treated as the levels po-organization to protect persons offsite. An alert re-tentially affecting persons offsite.
flects mobilization of the licensee's emergency re-Describe the act dents in terms of the process spo ise organization, either in a standby mode that and physical location where they could occur. De-wih activate some portions of the licensee s organiza-tion or full mobilization, but does not indicate an ex-scribe how the accidents could happen (equipment malfunction, instrument failure, human error, etc.)'
pectation of offsite consequences. However, an alert possible complicating factors, and possible onsite and may require offsite response organizations to respond to onsite condition such as a fire.
offsite consequences. Accident descriptions should include nonradioactive hazardous material releases A site area emergency is defined as an incident that could impact emergency response efforts. Facili-that has led or could lead to a significant release to ties that can have criticality accidents should evaluate the environment of radioactive or other hazardous the direct radiation exposure from postulated critical-material and that could require a response by an off-ity accidents in addition to the dose from released site organization to protect persons offsite. A site area radioactive materials.
emergency reflects full mobilization of the licensee's 3.67-4
tmerg:ncy response organization cnd may r:sult in essary. The licensee should describe how and by requests for offsite organizations to respond to the whom the following actions will be taken:
A
{~ '} site.
e Decision to declare an alert.
In the emergency plan, identify the classification Activation of onsite emergency response or-e (alert or site area emergency) that is expected for ganization.
f each of the accidents postulated in Section 2.1 of this guide. Relate the classification to the accident de-
- Prompt notification of offsite response
]
scription and detection means described in Section authorities that an alert has been declared 2.2. Identify the emergency action levels (EALs) at (normally within 15 minutes of declaring an i
which an alert or site area emergency will be de-alert).
I clared. EALs are specific conditions that require
- Notification to the NRC Operations Center emergency response measures to oe performed. Li-at 301-951-0550 immediately after notifi-censees should establish specific initiating conditions cation of offsite authorities, and in any case relative to particular events or citanges in instrument within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the declaration of an alert.
sensors. Appendix A provides a list of examples of (See 10 CFR Part 20 for additional notifica-initiating conditions for declaring an alert or site area tion requirements.)
emergency.
Decision to initiate any onsite protective ac-e Although it is unlikely that a site area emergency tions.
requiring offsite actions will owur at a fuel cycle or
- Decision to escalate to a site area emer-materials facility, the licensee must be able to recog nize potentia! offsite hazards and make the required gency, if appropriate.
notifications in such a manner that offsite response Decision to request support from offsite or-organizations can take appropriate actions, such as ganizations.
sheltering or evacuating persons in the affected area.
e Decision to terminate the emergency or en-The NRC intends that licensees be allowed to ter recovery mode.
have a single emergency plan that can apply to all
[
}
licensee needs and regulatory requirements. To this 3.2.2 Site Area Emergency
%./
end, it should be understood that a licensee may wish The purpose of declaring a site area emergency to include m the emergency plan some incidents that is to ensure that offsite officials are informed of po-do not fall withm the jurisdiction of the NRC. For tential or actual offsite consequences, that offsite offi-example, the hcensee may wish to include mdustrial accidents or fires unrelated to the licensee,s work c als are provided with recommended actions to pro-tect persons offsite, and that the licensee's response with nuclear materials. The licensee may include such organization is augmented by additional personnel mcidents m the emergency plan.
and equipment. The licensee should describe how The clasification of emergencies involving poten, and by whom the following actions will be taken:
tial or actual releases of nonradioactive hazardous
- Decision to declare a site area emergency.
materials should be coordinated with the local emer-
- Activation of onsite emergency response or-gency planning committee established under the pro.
visions of Section 301(c) of the Emergency Planning ganization.
and Community Right-To-Know Act of 1986 (Title e Prompt notification of offsite response III of the Superfund Amendments and Reauthoriza-authorities that a site area emergency has tion Act of 1986,. Pub. L.99-499). The licensee been declared, including the licensee's in-should clearly identify any part of the emergency plan itial recommendation for offsite protective that does not a; oly to activden licensed by the NRC.
actions (normally within 15 minutes of de-claring a site area emergency).
3.2 Notification and Coordination Notification to the NU Operations Center e
at 301-951-0550 immediately after notifi-3.1.1 Alert cation of the appropriate offsite response organizations and not later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af-The purpose of declaring an alert is to ensure ter the licensee has declared a site area that emergency personnel are alerted and at their emergency. (See 10 CFR'Part 20 for addi-
[v} emergency duty stations to mitigate the consequences tional notification requirements.)
of the accident, that the emergency is properly as-sessed, that offsite officials are notified, and that steps e Decision on what onsite protective actions can be taken to escalate the response quickly if nec-to initiate.
3.67-5
e
- Decision on what offsite protective actions 4.1 Normal Facility Organization to recommend.
Provide a brief description of the normal (day-to-a day) facility organization and identify by position I
Decision to request support from offsite or-e those rdividuals who have the responsibility W Wzation authority to declare an emergency and to initink Cra appropriate response.
a Decision to terminate the emergency or en-ter recovery mode.
4.2 Onsite Emergency Response Organization Describe the onsite emergency response organiza-3.3 Information To Be Ccmmunicated tion fu the facility, and include the organization for periods such as offshift, holidays, weekends, and exr The licensee should be prepared to provide clear' tended outages when normal operations are not being concise information to offsite response organizations.
conducted. Use organization charts and tables when The communication should avoid technical terms and appropriate. If the organization is activated in phases, jargon and should be stated to prevent an under-or describe the basic organization and each additional over-evaluation of the seriousness of the meldent.
component that may be activated to augment the or-Describe the types of informatir. i that will be commu-ganization.
nicated with respect to facilit*, stat 9s, releases of ra-dioactive or other hara-4us.matorials, and recom-4.2.1 Direction and Coordination mendations for protective actions to be implemented by offsite rrrponse organitations. The emergency Designate the position or the person and alter-plan should contain the preplanned protective action nates who have the overall responsibility for imple-recommendations the licensee will make to each ap-menting and directing the emergency response. Dis-propriate offsite organization (including the NRC) for cuss this person's duties and authority, including each postulated accident. The licensee should try to control of the situation, termination of the emergency make protec ive action recommendations directly to condition, coordination of the staff and offsite per-State or local officials responsible for implementing sonnel who augment the staff, communication with [
the specific protective actions. The recommendations parties requesting information about the event.
should specify the size of the area where the actions authority to request support from offsite agencies, and are to be taken. The licensee should obtain the input authority to delegate responsibilities. Indicate the in-of offsite organizations to ensure that they recom-dividuals who may be delegated certain emergency re-mend the most practical and efficient protective ac-sponsibilities.
tions for each postulated accident. A standard report-ing checklist should be developed to facihtate timely 4.2.2 Onsite Staff Emergency Assignments notification. Trovide assurance to the NRC that the information has been received by offsite response or-Specify the organizational group or groups as-Eanizations and that it is periodically reaffirmed and signed to the functional areas of emergency activity updated with these agencies.
listed below. Indicate the basis for personnel assign-ment for both ivorking and nonworking time periods.
The standard reporting checklist should be devel-For ead. group, describe duties, authority, and inter-oped in cooperation with offsite officials to ensure face with other groups and outside assistance.
that it meets their information needs and that their The organizational groups should provide capa-personnel are trained to receive and relay such infor-bility in the following areas:
mation. The licensee should provide initial protective e Facility system operations action recommendations at the same time it initially notifies offsite authorities of a site area emergency l
- Fire control declaration.
e Personnel evacuation and accountability 4.
RESPONSIBILITIES Search and rescue operations e
In this section, describe the emergency organiza-
- First aid tion to be activated onsite for possible events, as well a Communications as its augmentation and support offsite. Delineate the authorities and responsibilities of key itidividual and Radiological survey and assessment (onsite e
groups, and identify the communication chain for no-and offsite) 3 tifying and mobilizing the necessary personnel during normal and nonworking hours.
- Personnel decontamination 3.67-6
)
~
(
O Facility decontaminition the public and media can obtain information during an emergency.)
e Facility security and access control 3
i i
Typical agencies to be included are the local Q
Facility repair and damage control e
emerEency planning committee established under the e Post-event assessment Emergency P2nning and Community Right-To-Know Act of 1986: State department of health, environ-
- Recordkeeping mental protection, and emergency or disaster control; and local fire and police departments. Ensure that the licensee will meet at least annually with each offsite Criticality safety assessment response organization to review items of m"rual inter-o est, including relevant changes in the licenu./s emer-4.3 Local Offsite Assistance to Facility gency preparedness program. The licensee should dis-cuss the emerEency action level scheme, notification Describe provisions and arrangements fe assis-procedures, and overall response coordination proc-tance to onsite personnel during and after an emer-ess during these meetings.
gency. Indicate the location of local assistance with respect to the facility if not previously stated. Ensure 5.
EMERGENCY RESPONSE MEASURES that exposure guidelines are clearly communicated to S ecific emergen.:y response measures should be P,
offsite emergency response personnei. Identify the services to be performed, means of communication identified for each.: lass of emergency and related to and notification, and type of agreements that are in action levels or c:iteria that specify when the meas-place for the following:
ures are to be effected. Response measures include assessment a<.tions, mitigative actions, onsite and off-e Medical treatment facilities site protective actions, exposure control, authoriza-
, p g
tion of emergency exposures in excess of Part 20 lim-its, and aid to injured persons.
e Fire fighters 5.1 Activation of Emergency Response Organiza-(N e Law enforcement assistance tion
\\w]
e Ambulance service Describe the means used to activate the emer-Describe the measures that will be taken to en-gency response organization for each class of emer-sure that offsite agencies mainu.in an awareness of gency dur;ng both tegular and nonregular hours.
their respective roles in an emergency and have the Include a description of the method used to authenti-necessary pericd;c training, equipment, and supplies cate messages. Identify the activation levels for each to carry out their emergency response functions. Dis-ciasc and relate them to the responsibilities identified cuss any provatons to suspend security or safeguards in Chapter 4. In this and subsequent sections, de-measures for site access during an emergency.
scribe the specific written procedures to be used.
4.4 Coordination with Participating Government 5.2 Assessment Actions Agencies For each class of emergency, discuss the actions identify the principal State agency and other gov-to be taken to determine the extent of the problem ernment (local, county, State, and Federal) agencies and to decide what corrective actions may be re-or organizations having responsibilities for radiological quired. Describe the types and methods of onsite and or other hazardous inaterial emergencies at the facil-ffsite sampling and monitoring that will be done in ity. For each agency or organization, describe:
case of a release of radioactive or other hazardous mat arial. Describe provisions for projection of offsite its authority and responsibility in a radiologi-radiation exposures.
e
}
cal or hazardous material emergency and its interface with others, if any; 5.3 Mitigating Actions
'tt, specific response capabilities in terms of e
For the events identified in Chapter 2, briefly de-personnel and resources available; scribe the means and equipment provided for mitigat-its location with respect to the facility; ing the consequences of each type of accident. In-m o
/i clude the mitigation of consequences to workers b
The rumor control arrangements that have onsite as well as to the public offsite. In the event of a been made with the agency or organization.
warning of impending danger, describe the criteria (The emergency plan should describe where that will be used to decide whether a single process or 3.67-7
~
the cntir2 facility will be shut down, the st;ps that will o Monitoring of evacuns for contamination be taken to ensure a safe orderly shutdown of equip-and control measures if contamination is ment, and approximate times required to accomplish found p
a safe shutdown of processes. Mitigating actions could
- Criteria for command center and assembly i.nclude steps to reduce or stop any releases and steps area evacuation and reestablishment at al-to protect personnel (e.g., evacuation, shelter, decon-ternate location tamination).
a Procedures for evacuating and treating in-Means for limiting releases could include:
jured personnel, including contaminated e Sprinkler systems and other fire-suppression PCf80""'I systems
- Provisions for determining and maintaining the accountability of assembled and evacu-e Fire detection systems ated personnel.
e Firefighting capabilities 5.4.1.2 Use of Protective Equipment and e
Filtration or holdup systems Supplies. Effective use of protective equipment and supplies, including the proper onsite distribution or Use of water sprays on airborne releases of availability of special equipment, is an important radioactive material measure for minimizing the effects of exposure to or contamination by radioactive materials. Measures Automatic shutoff of process or ventilation that should be considered are:
e flows e
e Individual respiratory protection e Storage in fire-resistant containers Use of protective clothing e
Use of fire-resistant building materials Communications equipment associated with e
e Criticality controls any self-contained breathing apparatus Use of potassium iodide to block uptake of e
5.4 Protective Actions radioactive iodine (if appropriate).
The nature of onsite and offsite protective ac-For each measure that might be used, describe:
tions, the criteria for implementing those actior.s the areas involved, and the procedures for notification to e Criteria for issuance of emergency equip-affected persons should be described in the plan. Tc ment, if appropriate prevent or minimize exposure to radiation, radioac-e Locations of emergency equipment and tive materials, and other hazardous materials, the plan should provide for timely relocation of onsite supplies persons, timely recommendation of offsite actions. ef-e Inventory lists indicating the emergency fective use of protective equipment and supplies, and equipment and supplies at each specified lo-use of appropriate contamination control measures.
cation 5.4.1 Onsite Protective Actions e Means for distribution of these items.
5..i.1.1 Personnel Evacuation and A c-5.4.1.3 Contamination Control Measures.
countability. This segment of the emergency plan Describe provisions for preventing further spread of should include:
radioactive materials and for minimizing radiation ex-posures from radioactive materials that are unshield-e Criteria fr: oidering an evacuation ec ci released by abnormal conditions.
The means and time required to notify per.
Onsite protective actions should be described sons involved and should include isolation, area access control, and application of criteria for permitting return to normal Evacuation routes, transportation of person-use. Action criteria for implementing the planned l
e nel measures should be described.
Locations of onsite and offsite assembly 5.4.2 Offsite Protective Actions e
areas Describe the conditions that would require pro-
- Search and rescue tective actions of fsite and list postulated accidents 3.67-8
that could meet any of the conditions. Discuss what and permanInt r: cord devices, and mtans for ass:ss-protective action recommendations would be made to ing inhalation exposures.
offsite authorities, when each et.0mmendation would 4
be made, and what area '.lisite woald be affected.
Eescribe provisions for ensuring that dose and dose ccmmitment recorck are maintained for licensee Protective action'recorr mendations should be consis-and offsite support organization's emergency workers tent with the analysis results in NUREG-1140 (Ref.
- 2) and the guidance in the EPA Manual of Protective inv hed in any nuclear accident.
Action Guides (Ref. 3).
5.5.2 Decontamination of Personnel 5.5 Exposure Control in Radiological Specify action levels for decontaminating per-Emergencies sonnel. Describe the means for decontaminating emergency personnel, supplies, instruments, and In ttu.s section, describe the means for conuolh.ng equipment; and describe the means for collecting and radiological exposures for emergency workers.
handling radioactive wastes. Describe provisions for 5.5.1 Emergency Radiation Exposure surveying and decontaminating relocated onsite per-Control Program sonnel, including providing extra clothing and decon-taminates suitable for the type of contamination ex-5.5.1.1 Rediation Protection Program. De-pected.
scribe the onsite radiation protection program to be implemented during emergencies, including methods 5.6 Medical Transportation to comply with exposure guidelinus. Identify individu-als, by position or title, who can authorize workers to Specify how injured personnel, who may also be receive emergency doses. Procedures should be pro.
radiologically contaminated, will be transported to vided in advance for permitting onsite volunteers to medical treatment facilities. Describe how chemicals receive radiation doses in the course of carrying out or hazardous materials used in conjunction with ra-lifesaviria and other emergency acti" ties. Procedures dioactive materials may impact medical transporta-should provide for expeditious decisionmaking and a tion.
reasonable consideration of relative risks.
0 exposur.5.1.2 5
Exposure Guidelines. Specify onsite e guidelines consistent with the EPA Manual Describe arrangements made for hospital and of Protective Actions Guides (Ref. 3) to be used in medical services, both local and backup, and their actions to control fires, stop releases, or protect facili-capabilities to evaluate and treat injuries from radia-ties. Guidelines for exposure to uranium, plutonium, tion, radioactive materials, and other hazardous ma-or other toxic materials should be based on the terials used in conjunction with radioactive materials.
chemical toxicity when the toxicity hazard is greater The description should include the capabilities to than the radiation hazard. Exposure guidelines should control any contamination that may be associated be provided for:
with physical injuries. The licensee should be pre-pared to provide ambulance and hospital personnel e Removing injured person' with health physics support if needed. If needed dur-e Undertaking mitigating actions ing an emergency, the NRC can obtain physicians for consultation and other medical assistance ;hrough the Performing assessment actions Department of Energy (DOE).
e
- Providing onsite first aid 6.
EMERGENCY
RESPONSE
EQUIPMENT e Performing personnel decontamination In this chapter, describe the onsite equipment o Providing ambulance service l
arul facilities designated for use during emergencies.
- Providing offsite medical treatment.
Pn vide sufficient detail to allow the NRC staff to de-termine the adequacy of the equipment to perform its 5.5.1.3 Monitoring. Describe provisions for function during an emergency.
determining the doses and dose commitments from extemal radiation exposure and any internally depos-6.1 Command Center sted radioisotopes received by emergency personnel involved in any ace'.Jents, including volunteers and Describe *he principal and alternative locations 4
emergency workers from offsite support organizations from which control and assessment for the emergency who may receive radiation exposure while performing will be exercised. Identify the criteria used to prede-their duties at the licensee's facility. Include provi-termir.e the number and location of command centers sions for aistribunon of dosimeters, both sif-reading in order to ensure that at least one will be habitable 3.67-9
e.
during any emergency. Indicate the means for identi-MAINTAINING EMERGENCY PREPARED-e.
fying which command center will be used in a given NESS CAPABILITY emergency. Specify the criteria for evacuating a com-mand center and re-establishing control from an al-g, 7.1 Written Emergency Plan Procedures ternative location. Provide a description of the pri-mary and alternative locations from which licensee Identify the means for ensuring that written emergency workers would be dispatched for radiation emergency plan procedures will be prepared, kept up survey, damage assessment, emergency repair, or to date, and distributed to all affected parties. De-other mitigating tasks if these persons would not be scribe the review process that will ensure these pro-dispatched from the command centers.
cedures clearly state the duties, responsibilities, action levels, and actions to be taken by each group or indi-6.2 Communications Equipment vidual in response to an emergency condition. De-scribe provisions for approval of the procedures, making and distributing changes to the procedures, 6.2.1 Onsite Communications and ensuring that each person responsible for an Describe the primary and any alternative onsite emergency response function has easy access to a cur-communication systems that would be used to trans-rent copy of each procedu~ that pertains to his or her functions.
mit and receive information throughout the course of an emergency and the s*equent recovery. Discuss 7.2 Training the frequency of operational tests.
Describe the topics and general content of train-6.2.2 Offsite Communications ing programs used for training the onsite emergency response staff. Specify the training afforded to those A backup means of offsite communication, personnel who prepare, maintain, and implement the other than commercial telephone, should be provided emergency plan. Ensure that the procedures include for notification of emergencies and requests for assis-schedules and lesson plans for the training, frequency tance. Operational tests of backup communications of retraining, and the estimated number of hours of systems should be conducted periodically.
initial training and retraining that will be provided.
Include the training requirements for each position in (3
e e Een y Eannah Desch nang to M 6.3 Onsite Medical Facilities provided on the use of protective equipment such as Describe the facilities and medical supplies at the respirators. Describe the training program for onsite site designated for emergency first aid treatment and pers nnel who are not members of the emergency re-contamination control of injured individuals, sponse staff so that they are aware of what actions they may have to take following the declaration of an emergency. Discuss what special instructions and ori-6.4 Emergency Monitoring Equipment entation tours the licensee will offer periodically to-fire, police, medical, and other offsite emergency re-List and describe the dedicated emergency equip-ment that will be available for personnel and area sponse personnel. Topics to be addressed during training for offsite emergency response personnel monitoring, as well as that for assessing the release of should include exposure guidelines, personnel moni-radioactive materials to the environment. The de-toring devices, and basic contamination control prin-scription should include the purpose of the equip-ciples.
ment. The location of all monitoring equipment should be described. The emergency plan should dis-7.3 Drills and Exercises cuss how the storage locations will ensure that suih-cient emergency mot itoring equipment will be acces-Describe provisions for periodic drills and exer-sible in a nonhazardous location for each type of cises to test the adecuacy of implementing proce-postulated accident. Include similar descriptions of dures, to test emergency equipment and instrumenta-routine effluent monitors and meteorological meas-tion, and to ensure that the emergency personnel are urement systems, if present. Describe how these are familiar with their duties. Typically, drills are internal to be used to assess the magnitude and dispersion of tests of specific licensee emergency response func-releases. In addition to the radiological monitoring tions, related functions are often simulated, and off-equipment, indicate, if apphcable, the instrumenta-site organizations are not invited to participate. Exer-tion to be used for monitoring chemically toxic mate-cises are typically full-scale tests of the licensee's by}
rials. Describe available meteorological monitoring entire emergency response organization, and offsite equipment, including locations of monitors, elevations orEanizations are invited to participate. Preplanned of sensors, and location of readout.
descriptions of accidents should be used to prepare 3.67-10
scenarios appropriat3 to tl.e obj ctivs of each drill 7.5 Independent Audit and exercise. The procedures should include a re-
/
quirement for one or more nonparticipating observers Discuss the program to be used annually to re-(7) to evaluate the effectiveness of the personnel, the view and audit the licensee's emergency preparedness procedures, the readiness of equipment and instru.
program, including the emergency plan and its pro-mentation, and to recommend needed changes. For cedures; training activities; emergency facilities, those drills and exercises that involve simultaneous e9uipment, and supplies; and records associated with activities at more than one location, observers should ffsite support agency interface to ensure that the be provided at each location. Describe how criteria overall emergency preparedness program is being for acceptable performance will be prepared and pro-adequately maintained. Describe the minimum quali-vided to observers for evaluating the performance of fications of the persons who will perform the annual participants.
audit and ensure that the audits will be made by per-sons not having direct responsibilities for implement-ing the emergency response program. Changes in 7.3.1 Biennial Exercises plant layout should be included in the changes that would warrant revision of the emergency plan. De-Ensure that an exercise will be held biennially scribe the provisions for initiating corrective actions and that offsite response organizations will be invited based on audit findings and for ensuring completion to participate in the biennial exercise in order to exer-cf these actions, cise coordination with offsite assistance organizations, including test'ng procedures and equipment for noti-7.6 Maintenance and Inventory of Emergency fying and communicating with local and State agen-Equipment, Instrumentation, and Supplies cies. Ensure that the NRC will be invited to partici-pate or observe if they wish. Ensure that exercise Describe the plans for ensuring that the equip-scenarios are not known by exercise participants and ment and instrumentation are in good working condi-are plausible for the specific site. Discuss any provi-tion and that an adequate stock of supplies is main-sions to suspend security or safeguards measures for tained. A quarterly i.wentory should be made to site access during an exercise. These exercises should ensure all emergency equipment and supplies are in-be planned so that all emergency response activities tact and in good operating condition, includmg instru-(S are adequately demonstrated. The exercise objectives mentation for operation and calibration, demand i
and scenario should be provided to the NRC at least respirators, self contained breathing apparatus, fire-60 days before the exercise to obtain NRC comments fighting equipment and gear, supplemental lighting, on how well the exercise will test the licensee's emer-and communications equipment. The procedures gency response capabilities.
should include timely corrective actions to be taken when deficiencies are found during these checks.
7.3.2 Quarterly Communications Checks
- 7. 7 Letters of Agreement Ensure that checks are conducted with offsite Changes to the emergency plan should be com-response organizations each quarter to verify and up-municated to the appropriate offsite response organi-date all necessary telephone numbers.
zations; ensure that letters of agreement with offsite agencies are reviewed annually and renewsd at least every four years or more frequently if needed. Letters 7.4 Critiques f agreement may'be included in the emergency plan or maintained separately.
Ensure that a critique will be prepared for each 8.
RECORDS AND REPORTS drill and exercise by one or more of the nonpar-ticipating observers and that it will evaluate the appro-8.1 Records of Incidents priateness of the emergency plan, procedures, facili-ties, equipment, personnel training, and overall Describe the assignment of responsibility for re-effectiveness. The emergency plan and implementing pcrting and recording incidents of abnormal opera-procedures should be reviewed after each exercise, tion, equipment failure, and accidents that led to a based on the evaluation of the exercise. The emer-plant emergency, including permanent retention with gency plan should be reviewed and revised. if neces-the licensee's decommissioning records. Provide a de-sary, whenever changes occur in processeN kinds of tailed description of the records that will be kept. The O
material at risk, or plant organization. Decribe how records should include the cause of the incident, per-V deficiencies identified by the critique will be corrected sonnel and equipment involved, extent of injury and in a timely manner. (See Chapter 8 for records of damage (onsite and offste) resulting from the inci-exercises and exercise critiques.)
dent, all locations of contamination with the final 3.67-11
I*
decontamination. survey results, corrective actions Specifically, recovery plans should include taken to terminate the emergency, and the action requirements for checking and restoring to normal taken or planned to prevent a recurrence of the inci-operations all safety-related equipment involved in p
dent. The records should also include the onsite and the incident -(e.g., criticality alarms, radiation rr.oni-i offsite support assistance requested and received, as toring instruments, respiratory protection equipment, well as any program changes resulting from the les-fire-suppression and fire-fighting equipment, contain-sons learned from a critique of emergency response ments, and air filters) and assignment of responsibility 1.atles. The titles of the personnel responsible for for compiling, evaluating, and ensuring retention of mintaining the records should be specified. Those all records associated with the incident.
9 +25 unique to a radiological emergency, not cov-e uy existing NRC regulations or license condi-During any planned restoration operau.ons, per-v, uons, should be retained until the license is termi-sonnel exposures to radiation must be maintained nated.
within 10 CFR Part 20 limits and maintained as low as reasonably achievable.
8.2 Records of Preparedness Assurance
- 10. COMPLIANCE WITH COMMUNITY Provide a description of the records that will be RIGHT-TO KNOW ACT kept. These should include records of:
Show compliance with Title III of the Superfund
. Training and retraining (including lesson Amendmentr and Reauthorization Act of 1986, Pub.
e g, 99, plans and test questions) 499, entitled " Emergency Planning and Community Drills, exercises, and related critiques Right-To-Know Act of 1986," with respect to any e
hazardous materials possessed at the plant site.
Inventory and locations of emergency equip-e ment and supplies REFERENCES
- Maintenance, surveillance, calibration, and 1.
U.S. Nuclear Regulatory Commission, " Standard testing of emergency equipment and supplies Format and Content for Emergency Plans for Agreements with offsite support organizations Fuel-Cycle and Materials Facilities," NUREG-e 0762, Draft Revision 1. November 1987.*
g\\
Reviews and updates of the emergency plan e.
2.
S. A. McGuire, "A Regulatory Analysis on Notification of all personnel and offsite agen-Emergency Preparedness for Fuel Cycle and e
cies affected by an update of the plan or its Other Radioactive Material Licensees,"
implementing procedures.
NUREO-1140, U.S. Nuclear Regulatory Com-9.
RECOVERY AND PLANT RESTORATION 3.
Endronmental hotecdon Agexy, Wanual of Describe plans for restoring the facility to a safe status. Although it is not possible to detail specific Protective Action Guides and Protective Actions plans for every type of incident, the plans should in-f r Nuclear Incidents," EPA 520/1-75-001-A, clude the genen:1 requirements for (1) assessing the January 1990.
damage to and the status of the facility's capabilities to control radioactive materials, (2) determining the actions necessary to reduce any ongoing releases of
' copies may be obtained, to the extent of rupply, from the U.S. Nuclear Regulatory Commission, Washington, DC radioactive or other hazardous material and to pre-20555, Attention: Distribution and Mail Services vent further incidents (3) accomplishing the tasks to 8'*d "'
meet any required restoration action, and (4) de-
"caples may be purchased from the U.S. Government scribing in general il s key positions in the recovery l ',inting Office, P. O.
Box 37082, Washington, DC
. 013-7082: or from the National Technical lnformation organization.
Service, $285 Port Royal Road, Springfield, VA 22161.
3.67-12
c
- \\
APPENDIX A l
j EXAMPLES Ol' INITIATING CONDITIONS l
Conditions that initiate an Alert Conditions that Initiate a Site Area Emergency 1.
Fire onsite that might affect radioactive 1.
F3 onsite that involves radioactive material material or safety systems, or compromises safety systems.
1 j ' 2.
Severe natural phenomenon that might affect 2.
Severe natural phenomenon that actually radioactive material or safety systems (e.g.,
compromises safety systems or the integrity earthquake, flood, tsunami, hurricane, of radioactive material (e.g., earthquake, tidal surge, hurricane force winds, tornado i
flood, tsunami, hurricane force winds, A
striking facility).
tornado striking facility).
3.
Other severe incidents that might affect radio-3.
Other severe incidents that actually com-active material or safety systems-aircraft crash promise safety systems or the integrity of into the facility, damage to the facility from radioactive.naterial-aircraft crash into the explosives, uncontrolleo release of toxic or facility from explosives, uncontrolled release j
flammable gas in the facility, of toxic or flammable gas in the facility.
4.
Elevated radiation levels or airborne contami-4.
Elevated radiation levels or airborne con-nation levels within the facility that indicate tamination levels outside the facility that severe loss of control (factor of 100 over indicate a significant release to the environ-normal levels).
ment (factor of 100 over normal levels).
5.
Ongoing security compromise (greater than 15 5.
Imminent or actual loss of physical control minetes).
of the facility.
6.
Spent wactor fuel accident with release of 6.
Major damage to spent reactor fuel with radioacuvity to containment or fuel-handling release of radioactivity outside of
- building, containment or fuel-handling building.
7.
Discovery of a critical mass quantity of special 7.
Imminent or actual occurrence of an nuc! car material in an unsafe geometry con-uncontrolled criticality.
tainer or other condition that creates a critic'lity hazard.
8.
Other conditions that warrant precautionary 8.
Other conditions that warrant activation of activation of the licensee's emergency offsite emergency response organizations response organization, or precautionary notification of the public near the site.
l Ib i
i 3.67-13 i
s
~
t - e-l l
REGULATORY ANALYSIS A draft value/ impact statement was published with the draft of this guide when it was published for public comment (Task DG-3005, September 1990).
l No changes were necessary, so a separate value/ impact statement for the final guide has not been prepared. A copy of the draft value/ impact statement is available for inspection or copying for a fee in the Commission's Public Document Room at 2120 L Street, NW, Washington, DC, under DG-3005.
v l
3.67-14
e 4,
K. Alkama If you have any questions or comments, please contact me at (301) 415-7234 or Mr. Tim Harris
/
of my staff at (301) 415-6613.
Sincerely, (original signed by)
John W. N. Hickey, Chief LoN-Level Waste and Decomm' ioning Projects Branch Division of Waste Manag ent Office of Nuclear Mat I Safety and Safeguards Docket No.- 070-3095
Enclosure:
As stated w/ attachments cc:
William Sinclair, State of Utah DISTRIBUTION:
Central File LLDP r/f NMSS r/f D
r/f PLohaus WBrach LHowell PUBLIC MLamastra Johrsen MFederline ePdanci Ticket: N-97-520 HKSS Diri lF
/
2,_g DOCUMENT NAME:s:\\dwm\\lidp\\teh\\lic r
- See previous concurrence sp OFC LLDP LLDP,],
LM LkP b
FCSS DWM OGC JCohland Nkso'n*
WReamer JYickey NAME THarris*
MWeber JGreeves DATE 2/19/98 2Ai98
[ 2/19/98 2/ /98 2/N98 2/ /98 2/ /98 l
OFFICI RECORD COPY J
ACNW: YES.X. NO _
Categ
- Proprietary _ or CF Only _
IG : YES.X. NO _
LSS : YES _ NO.X.
Det e file after distribution: Yes.2L No,_
s
I
~
K. Alkema If you have any questions or comments, please contact me at (301) 415-7234 or Mr. Tim Harris of my staff at (301) 415-6613.
Sincerely,
[ original signed by)
John W. N. Hickey, Chief [ issioning Low-Level Waste and Decomm Projects Branch /
Division of Waste anagement Office of Nucle aterial Safety and Safegu s
Docket No.: 070-3095
Enclosure:
As stated cc:
William Sinclair, State of Utah I
DISTRIBUTION.
j Central File LLDP r/f NMSS r/f D
r/f PLohaus WBrach LHowell PUBLIC MLamastra Ticket: N-97-520 DOCUMENT NAME:s:\\dwm\\lldp\\teh\\lic.gr k
OFC LLDP LLDP OGC LLDP FCSS DWM NA~E THarr!s JCop-land hon WReamer JHickey MWeber JGreeves
/Ih98 DATE 288 2/ /98 2/ /98 2/ /98 2/ /98 2/ /98 OFFICIAL CORD COPY
'"NW: YES 1 NO _
Category:
reprietary _ or CF Only _
- YES 1 NO _
,. S : YES _ NO 1 Delete e after distribution: Yes 1. No __
i