ML19329E034
| ML19329E034 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/31/1967 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8004090676 | |
| Download: ML19329E034 (26) | |
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CONTENTS APPENDIX 12 12A XiSWERS TO QUESTIONS nn -
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%dVUU 0112 Amendment 3 A12-1
Docket 50-312 Amendment No. 1
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February 2, 1968 QUESTION Provide an outline of the emergency plans to be followed in 12A.1 case of a major accident at the facility.
ANSWER 1.
Introduction Refer to 12.6 The Rancho Seco Nuclear Station will have a radiation emergency plan that will be employed to minimize radiation exposure to in-plant and outside personnel.
It will describe action levels and specific duties required of station personnel in the event of an accident or any unplanned incident producing high radi-ation levels.
Basis for the radiation emergency plan will be the recommendations of 10 CFR 100.
The responsibility for the coordination of duties for radiation emergency plan will be charged to the radiation protection engineer.
Periodic drills will be held to ensure that all station personnel have a working knowledge of action required of them by the radiation emergency plan.
Each individual assigned to Rancho Seco will have a written copy of his specific
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duty to be performed during the radiation emergency.
Prior to receipt of an operating license an emergency planning group consisting of selected individuals from plant management and plant operating personnel will be assigned to meet with state and local authorities to establish a clear line of action and responsibility during a radiation emergency.
Coordination will also be established with the appropriate welfare groups to assure that temporary quarters etc. can be made available for an accident evacuation period if required.
The health physics laboratory will be located in the auxiliary building and will be utilized to manage the radiation accident.
This laboratory will be equipped with all the necessary instru-mentation and equipment needed to handle a radiation emergency.
Respiratory protective equipment will be available for the protection of personnel against airborne radioactive contam-ination and will consist of full face filter masks, self-contained air-breathing units, or air-supplied masks and hoods.
Portable radiation survey instruments uill be provided and wi;l be selected to cover the entire spectrum of radiation measure-ment problems anticipated at the plant.
Sufficient quantities will be on hand to allow for use, calibration, maintenance, cnd repair.
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12A-1 I
O Training programs will be established and executed to ensure that all selected personnel assigned to emergency monitoring squads have a working knowledge of health physics procedures and of the use of radiation instruments.
II.
Action Levels for Initiatine the Radiation Emercency Plan Initiation of any of the following alarms will alert the control room operator to the possible existence of an accident in which the release of radioactive material could occur to the environ-ment.
1.
Unplanned, automatic initiation of the emergency injection safeguards system.
2.
Loss of primary coolant pressure.
3.
Reactor trip alarm.
4.
Alarm of plant vent air monitor.
5.
Alarm of reactor building air monitor.
6.
Alarm of plant boundary air monitor.
7.
Alarm of spent fuel building dose rate detector.
8.
High readings on other radiation monitoring instru-mentation.
After receiving one or more of the above alarms, the operator will evaluate the conditions producing the alarms, and if instru-mentation indicates that radiation has resulted which presents a danger to plant personnel or the surrounding population, he will sound the radiation emergency plan alarm.
This alarm will have a visual and audible indication in the control room.
The audible signal will be unique and distinguishable and will sound throughout the station and surrounding site area.
III. Station Hich Radiation Evacuation Upon the sounding of the station radiation emergency plan alarm, all station employees and visitors except designated key personnel and shift workers will immediately proceed to designated emergency areas from which they will be evacuated. All evacuees will be surveyed by an emergency radiation monitor prior to leaving the plant boundary. All personnel remaining in the plant to perforn emergency operating procedures will be surveyed for possible contamination.
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To assure that key personnel can be contacted at all times, a
" Call List" will be established, i
IV.
Evaluation of On-Site Conditions To evaluate the radiation levels on-site, the following procedure will be used:
1.
Readings will be taken from the station radiation monitoring system in the control room.
2.
A member of the emergency monitoring team will take air samples, beta-gamma swipe, and dose rate readings throughout the plant and immediate environment.
3.
These survey results will be recorded in a log book at the health physics laboratory.
l V.
Evaluation of Of f-Site Conditions To evaluate the radiation levels off-site, the following pro-cedure will be used:
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Members of the emergency monitoring team will take air
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samples, beta-gamma swipe, and dose rate readings at specific areas determined by the radiation protection engineer.
The area surveyed will depend on wind direction and wind velocity to be indicated by the Rancho Seco meteorological station.
VI.
Protective Action for Local Population If the emergency monitoring squads have reported high radiation
-levels on the off-site survey and these radiation levels are above the average projected dose Ibnit recommended in 10 CFR 100, and radiation levels are increasing, the radiation protection engineer or his alternate will call the appropriate authorities, which will be designated by state and local governments, and the local AEC operations office.
- These organizations will be informed that a major release of radioactive material occurred at Rencho Seco Nuclear station.
Evacuation of the low population zone will then be performed by pre-arranged methods by personnel notified in the preceding para-graph.
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VII. Hosnitalization of Contaminated casualties In the event a medical injury occurs that necessitates hospitali-i zation before decontamination, the following action vill be taken:
j 1.
A survey of the contaminated person vill be performed 4
by a member of the emergency monitoring squad.
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The radiation protection engineer or shift supervisor will alert the proper hospital authorities and advise them of the radiation levels of the contaminated persun.
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(Special arrangements will be made witn a designated j
local hospital on a radiation emergency plan.)
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V EE. Emercence Reserve of Personnel If additional personnel are required in the event of an energency, they will be obtained from :he following sources:
1.
Within the company and/or other operating nuclear power plants.
2.
Califernia State Public Health Department, j
3.
Outside health physics and nuclear decontamination vendors.
4 Nuclear consultants.
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Amendment 1 12A-L
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QUESTION Discuss further the relationships between SMUD, Bechtel, B6W,
-12A.2 WEC, and others. This discussion should include a list of the
. (DRL 12.1) subsystems and support functions provided by the principal l
parties.
ANSWER 12A.2.1 SMUD has entered into a contract for engineering services with Bechtel Corporation. The following defines Bechtel's relation-ship with SMUD.
3 At the request and direction of SMUD, Bechtel shall perform any or all of the following work related to Rancho ' Seco No. 1.
a.
Preliminary Reports on Design These services will include generally the following:
1.
Collecting and analyzing the engineering data and other information, preparing preliminary cost estimates, I
making supplemental field investigations, including surveys, materials testing and drilling where necessary, and carrying out such other preliminary studies as may j
be required for the formulation of the desired reports.
2.
Recommending the type and character of construction
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and of materials and equipment required.
b.
Final Desiens and Equipment Specifications 4
These services will include generally the following:
1.
Collecting and analyzing such additional engineering data and other information as may be required for the j
formulation of definitive plans and designs for the work.
2.
Recommending the detailed type and character of con-struction and of materials and equipment required.
3.
Preparing detailed specifications and schedules for 1
the purchase of all maior items of equipment and nuclear fuel for the Rancho Seco Unit 1 by SMUD.
4.
Reviewing and evaluating proposals of manufacturers
_for furnishing various items of materials and equipment and making technical recommendations to SMUD as to purchase.
5.
Preparing detailed designs, drawings and specifications i
required for the construction work.
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6.
Preparing bid invitations, bid proposals and forms of contracts for the procurement of equipment and nuclear fuel by SMUD and for the construction work.
7.
Preparing Engineer's Estimate of the quantities and cost of the work af ter definitive plans and designs for the work have been issued for bidding in each instance to permit comparative evaluation of bids received, c.
En.cineerine Supervision of Construction These services will include generally the following:
1.
Organizing, planning and managing the construction program.
2.
Assisting in soliciting, receiving and evaluating com-petitive bids and recommending actions thereon.
3.
Supervising, coordinating and inspecting the work of the contractors with the view of securing completion and fulfillment of the contracts in accordance with plans, specifications and approved schedules and per-forming such surveying services as may be required for construction.
4.
Provide soils testing and concrete laboratories at the jobsite for testing and control of materials.
5.
Checking bills submitted to SMUD by the construction contractors and checking invoices and other records submitted by such contractors in support of such bills; certifying to SMUD that the f acts set forth in such bills, invoices and records are correct and assisting SMUD in allocating contractor's charges in accordance with SMUD's cost accounting system.
6.
Preparing revised estimates of cost of Rancho Seco Unit 1 for control purposes as the Project moves along through the design, equipment procurement and construc-tion stages.
7.
Preparing cost reports, progress reports, construction schedules, estimates of monthly cash requirements, con-tractor's estimates for payments and such other reports as may be directed by SMUD.
8.
Assisting SMUD in contractual matters relating to the construction of Rancho Seco Unit 1.
9.
Assisting in coordinating engineering services with startup and testing the completed unit or portions thereof during a trial or preliminary period.
Amendment 2 12A-6
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Providing advisory assistance on labor relations and safety matters.
11.
Assisting in engineering, inspecting and expediting of equipment purchased by SMUD.
12.
Providing other construction management, supervisory and accounting services.
13.
Providing "as built" drawings of the completed work.
d.
Permits and Licenses Assist in the preparation of reports and render such other assistance as may be requested in connection with securing all permits, licenses and clearances required by the Atomic Energy Commission and other federal and state agencies.
e.
Operating Personnel Assist SMUD in the procurement and training of operating personnel for the Project.
12A.2.2 SMUD has entered into a contract with the Babcock and Wilcox Company for the supply of a Nuclear Steam Supply System. The s
l following defines B&W's relationship with SFUD.
N J a.
B&W will furnish and deliver one (1) Nuclear Steam Supply System (NSSS) complete with spare parts, tools, accessories, auxiliaries and all appurtenant equipment and controls therefor.
b.
B&W will deliver the nuclear reactor components, including the reactor vessel and steam generators, to the District's Rancho Seco Site.
In amplification of the foregoing, B&W's supply includes:
Reactor vessel and internals Control rod and drive system Neutron source Fabrication of the initial core, reactor coolant pumps, steam generators and pressurizer Nuclear steam supply system primary piping Reactor coolant make up and purification system Residual heat removal system HP and LP safety injection systems and core flooding tanks Reactor neutron monitoring system Reactor protection instrumentation Reactor control system 0.1.19 n n n 7 t_
Amendment 2 12A-7 I
Reactor process instrumentation Reactor process thermal and hydraulic monitoring system Integrated turbine control system Computer system for fuel management Reactor surveillance specimens Process monitors Reactor component and fuel handling systems (except new and spent fuel storage racks)
B&W's supply also includes assistance with operator training as outlined in Section 12.3 and provision for on-site advisors during erection, fueling and start-up operations.
12A.2.3 SMUD has entered into a contract with Westinghouse Electric Corporation for the supply of a turbine generator. The follow-ing defines Westinghouse Electric Corporation's relationship with SFUD.
Westinghouse Electric Corporation will furnish and deliver one (1) outdocr tandem compound, 1800 rpm steam-driven turbine-generator complete with reheaters; excitation equipment; voltage regulating equipment; spare parts, tools, accessories and auxiliaries and all appurtenant equipment and controls.
In amplification of the foregoing, Westinghouse supply includes:
Turbine generator Turbine stop valves, governor valves and reheater intercept valves Turbine reheaters An electro hydraulic governor system Generator nydrogen cooling system Turbine lubricating oil system Generator voltage regulator and acceleration system Generator neutral grounding connections and neutral and current transformers Westinghouse will also provide on-site advisors during erection and start-up operations.
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QUESTION Provide organization charts that show the contributions by SMUD, 12A.3 Bechtel, Babcock & Wilcox, Westinghouse Electric Corporation (DRL 12.2) during the construction phases and the operation phases.
ANSWER Figure 1B-1 (Appendix 1B) is provided to show the responsibilities and contributions of the various organizations during the con-struction and operation phases. This includes quality control and quality assurance.
(For convenience, the construction phase is defined as that period from groundbreaking until fuel loading. The operation phase is defined as that period from beginning of fuel loading until tcanination of reactor operations). The referenced figure is not intended to extend significantly beyond the period at which commercial operation has been demonstrated,
i.e.,
after the phase out of construction forces. In addition te the project construction staff and the District's operating staff, B&W will provide a field operation manager and other field engineers.
Three or more years before commercial operation, a test working group will be formed with representatives of SMUD, Bechtel, B&W, and others as required. Their responsibility is to review test specifications and to integrate the test schedule with the con-struction schedule. About one year prior to fuel-loading, the District's Rancho Seco operating staff and the B&W field engi-neering staff will move to the site, to participate in field testing. The field test working group will continue with the same basic functions, but with added responsibilities of over-
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seeing these tests as to proper methods, data tabulations, and doc umen t a t ion.
QUESTION Expand organizational charts in the PSAR to show lines of 12A.4 responsibility for quality control efforts during the construc-(DRL 12.3) tion phase.
ANSWER See answer to question 12A.3.
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3 Amendment 2 12A-9
QUESTION Submit an organizational chart for the Bechtel Corporation 12A.5 indicating responsibility channels for Quality Assurance and (DRL 12.4) Quality Control efforts for this project.
Delineate home office as well as site groups.
ANSWER The organizational chart for the Bechtel Corporation indicating i
responsibility channels for Quality Assurance and Quality Con-trol is showm in Figure 12A.5-1.
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12A-10 Amendment 2
QUESTION Submit an organizational chart for the Babcock and Wilcox 12A.6 Company indicating responsibility channels for Quality Assurance (DRL 12.5) and Quality Control efforts.
ANSWER The organizational chart. for the Babcock and Wilcox Company indicating responsibility channels for Quality Assurance and Quality Control efforts are shown in Figures 12A.6-1, 2 and 3.
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v QUESTION Submit an organizational chart for the 3abcock and Wilcox 12A.6 Company indicating responsibility channels for Quality Assurance
.(DRL 12.5) and Quality Control efforts.
ANSWER The organizational charts for the Babcock and Wilcox Company indicating responsibility channels for Quality Assurance and Quality Control efforts are shown in Figures 12A.6-1, 2 and 3.
The Babcock and Wilcox Quality Control Group Manager will have a minimum of the following qualifications:
e Graduate engineer - mechanical or industrial plus graduate work in either of these-fields.
e Minimum of 15 years within the engineering, erection, service and fabrication areas of the company or a similar organiza-tion devoted to nuclear component fabrication.
e Knowledge of welding, non-destructive testing and inspection procedures.
Ability to manage a group of 300 to 400 technically oriented people.
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In selecting a manufacturer for a given component, Babcock and
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Wilcox make a thorough evaluation of the manufacturer's capabil-ity to fabricate the component to the desired level of integrity and determined that he has the necessary experience and an adequate quality control organization.
3 B&W perform inspections and quality assurance audits on components and materials procured from such manufacturers to assure that all specification requirements are being met.
Records of these inspections and quality assurance audits become a part of the i
quality control history file. This pregram is administered by B&W's nuclear power generation department.
Before shipping any item, the preservation and packaging require-ments for each component are established consistent with the j
level of cleanliness to be maintained and to prevent damage
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during shipment. The packaged component is loaded and secured to the carrying vehicle and all shipping preparations are inspected to assure compliance with the established requirements.
In addition the carrying vehicle for large components is examined both prior to loading and af ter the load is secured to the vehicle.
With the exception of the reactor vessel, the final method of i
transporting the B&W manufactured components has not been established. The reactor vessel will be shipped from Mt. Vernon to the San Francisco area by barge and there transferred to a f\\
truck for the remainder of the trip to the site. The type of barge will be either flat deck or well type depending upon
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loading facilities available.
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Amendment - 3 12A-11
The barge will be seaworthy and certified for limited coastwise operation. The vessel will be contained in a shipping skid which is firmly mounted on the bargc. A gasketed closure will seal the larger openings and the smaller openings will be sealed by plastic caps and plastic adhesive tape.
Desicant will be held in a container mounted on the inside surface of the cover plate, and a humidity indicator will be arranged so th at it may be viewed from outside the scaled vessel. Exposed steel surfaces will be protected by a suitable rust preventative.
A waterproof covering will enclose the vessel so that it is protected from splashing water.
Components which are shipped by rail will utilize heavy duty railcars as required. Shipping bolsters and skids will be 3
used as required to insure secure mounting on the railcars.
All openings will be sealed by metal or plastic closures, either gasketed or taped with plastic adhesive tape.
Desicant will be mounted in a container inside each component and a humidity indicator will be arranged so that it may be viewed from outside the sealed vessel. Exposed steel surfaces will be protected by a suitable rust preventative.
In the case of the reactor vessel internals, shipping clearances will dictate the type of containment which will be used.
Until these clearances are established, it is not possible to give any details on preservation and packaging.
On arrival at the jobsite, equipment will be subject to careful inspection for damage or deterioration during shipment by tbc applicant's field staff.
QUESTION Submit the staffing and training plans discussed at DRL on 12A.7 February 5,1968 for the Rancho Seco No. 1 operating personnel.
(DRL 12.6)
ANSWER The answer to this question is included as a change to the PSAR Section 12.3 (Amendment 2).
Figure 12.3-1 illustrates the Dis-trict's current plans for recruiting, staffing and training of the operating staff.
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$)SMUD 0132 SACRAMENTO MUNICIPAL UTILITY DISTRICT Amende.ent 2
QUESTION Submit the staffing and training plans discussed at DRL on 12A.7 February 5,1968 for the Rancho Seco No. 1 operating personnel.
(DRL 12.6)
ANSWER The answer to this question is included as a change to the PSAR Section 12.3 (Amendment 2).
Figure 12.3-1 illustrates the Dis-trict's current plans for recruiting, staffing and training of the operating staff.
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12A-12 Amendment 2
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QUESTION Provide the following information in outline form regarding 12A.8 emergency planning for the SMUD facility; (DRL 13.4)
.a.
Plan objective, b.
- Scope, c.
Delineation of responsibility and authority for plan imple-me ntatio n, d.
Notification liaison to be established with federal, state and local authorities and emergency assistance personnel that they provide.
e.
Provisions made with local hospital and physicians for treatment of injured persons, including contaminated persons.
f.
Instrumentation to be installed with readouts in the con-trol room to be used for assessment of the extent of a radioactive release, both onsite and offsite, g.
Proposed training of onsite staff and meanc to be used to evaluate the plan's effectiveness on a periodic basis.
l ANSWER Although emergencies may never arise at a nuclear generating station, plans must be formulated and practiced so that probicas which may arise in an emergency can be handled in an orderly, efficient manner.
Emergencies may arise in two general categories, radiation and
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non-radiation. -In radiation emergencies the plan must be such 1
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that the extent of the emergency is minimized; the onsite per-sonnel and the general public are protected; and action is 4
initiated to recover from the emergency.
In non-radiation emergencies such as fire, explosion, or natural phenomena the plan should limit the consequences of such emergencies and pre-vent them from causing a radiation emergency.
a.
Plan Objective To provide a schcme of action to be carried out in the event of a plant' emergency, both a radiation emergency and non-radiation emergency, so that problems may be handled in a tbnely and effective manner.
b.
Scope The extent covered by the emergency plan will include con-sideration on non-radiation emergencies, local emergencies, site emergencies, and general emergencies, e Non-Radiation Emergency.
If the consequences of a specific non-radiation emerg'ency are unrelated to radi -
ation safety, operations may continue..If the non-radiation emergency could affect the reactor systems the 5
decision will be to shutdown the reactor or reactors.
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,(h' Natural conditions, such as extreme meteorological con-
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In such an event, the plant operating staff will curtail operations as required, e Local Emercency.
If abnormal radiation conditions in any building or area exceeds preset limits, a local emergency exists. Audible and visual radiation alarms will warn workers in the area to secure operations in a safe manner and leave the area by the most direct route.
The control room operators will alert other plant personnel and proceed according to prescribed pro-Cedures.
e Site Emercency. During a site emergency, personnel will evacuate by prescribed routes to an assembly point.
The evacuees assembled will receive permission to re-enter, instruction for further evacuation, or instructions to assist in the emergency operations.
The control room personnel will base continued operation on established criteria in the operating manual (Manual Section " Abnormal Procedures").
The control room will continue to be manned during a site cmergency to coordinate activities and to maintain communications with onsite and offsite personnel.
e General Emereency.
The operating crew will call for assistance from the plant emergency monitoring team during a general emergency to evaluate the radiation situation in the enviromment.
Basis for the emergency plan will be the recommendations of 10 CFR 100 and the National Plan for Emergency Preparedness.
c.
Responsibility and Authority for Plan Implementation e The Plant Superintendent shall have the overall respon-sibility for plant safety; therefore, he shall be responsible for the establishment of a comprehensive, workable emergency plan.
He will be assisted in this task by the Assistant Plant Superintendent and the Radiation-Chemical Supervisor, e The Radiation-Chemical Supervisor shall be responsible for the coordination of duties for the radiation emer-gency plan.
He will be a member of the Technical Sup-port Group and will have a direct line of communication to the Plant Superintendent.
The Radiation-Chemical Supervisor shall schedule and supervise training related to the emergency plan.
0.L35 12A-14
.h Amendment 2
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e The Shif t Sunervisor en watch shall have the responsi-bility and operational authority to evaluate onsite and offsite conditions and to sound the radiation emergency plan alarm, if necessary.
He will be assis ted in arriv-ing at his evaluation by other plant personnel, princi-pally the Senior Control Operator.
The immediate responsibilities of the plant personnel will be detailed in the emergency plan so that each involved individual is prepared for what is required of him in the emergency.
The Shif t Supervisor shall initiate action to have pre-designated authorities immediately apprised of the emergency. Authorities that will be included in the notification plan are as follows:
- Key SMUD Personnel
- Manager of the AEC Operations Office in San Francisco.
(Applicable if the emergency meets the criteria set forth in 10 CFR 20.)
- Transportation and law enforcement authorities.
(Appli-cable if emergency is of such a nature that travel through the area is hazardous or a relocation of popu-lation is required.)
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- Local hospital authorities
- Predesignated emergency assistance personnel e A member of the Emer2ency Monitorine Team will be respon-sible for accounting for evacuated personnel, if a site evacuation occurs during day shift hours. During other times a direct accounting will be made by the Shift Super-
- visor, d.
Notification Liaison In order to ensure timely and orderly execution of the emer-gency plan, specific lines of communication will be estab-lished among federal state and local authorities and emergency assistance personnel that they provide.
Prior to receipt of an operating license an emergency planning group consisting of selected individuals from plant management and plant operating personnel will be assigned to meet with federal, state and local representatives to delineate noti-fication liason and sequence of notification.
To assure that key personnel can be contacted at all times, a " Call List" will be established consisting of a current lis ting of names, addresses, and phone numbers.
0136 Amendment 2 12A-15
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If radiation level and release information indicate that j
people in an area should be relocated, this will be accom-plished through local civil authorities. Decisions for evacuation will be based on the guides in Report No. 5 of the Federal Radiation Counsel and the regulations set forth in Title 10, Code of Federal Regulations, e.
Provisions for Treatment of Injured Persons A medical assistance plan will be developed in cooperation with local medical facilities in preparation for the unlikely event of radiation injuries to personnel.
The plan will include local first aid, relocation to hospital facilities, and procedures for the receiving hospital. A medical radia-tion consultant will be retained by the District to provide general advice and instruction.
In the event an injury occurs that necessitates hospital-ization before decontamination, the following action will be taken:
The plan includes the specification of appropriate measures to prevent the spread of contamination in the event an injured individual must be transported to a nearby hospital and will also specify the maintenance of appropriate kits of equipment to be used in such emergencies. A trained SMUD I
employee will accompany all injured and contaminated person-nel to the hospital. They will carry appropriate equipment and protective clothing to control the spread of contamina-tion at the hospital or clinic, and will return any con-taminated material to the Station for proper disposal.
f.
Radiation Monitoring Section 11 and Appendix llA (answer to question 11A.1) of the PSAR describe the Radiation Monitoring System for Rancho Seco. Readouts will be installed in the control room to aid in the assessment of the extent of a radioactive release.
Portable radiation survey instruments will be provided and will be selected to cover the entire spectrum of anticipated radiation measurement problems, both onsite and of fsite.
Sufficient quantities will be on hand to allow for use, cali-bration, maintenance, and repair.
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12A-16 Amendment 2
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. To evaluate the radiation levels on site, the following
. procedures will be used:
e Readings will be taken from the station radiation monitoring system.
A member of the Emergency Monitoring Team will take air o
samples, beta-gamma swipe, and dose rate readings through-out the plant and immediate environment.
e These surveys will be evaluated and recorded in a record book in the site health physics laboratory.
' To evaluate-the conditions of fsite, members of the Emergency Monitoring Team will take air and water samples, beta-gamma j
swipes and dose rate readings offsite to provide information on release and possible offsite exposure.
The information will be used to direct or adjust population relocation. Area radiation monitors located at the site boundary will give immediate indication of the possibility of ra'diation hazard to offsite locations.
g.
Training and Periodic Evaluation The staff assigned to Rancho Seco will receive comprehensive indoctrination and training in all elements of the emergency
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plan.
Each individual will have a written copy of his speci-fic duty to be performed during the radiation caergency.
Training programs will be established and executed to ensure that all personnel assigned to Emergency Monitoring Teams have a working knowledge of health physics procedures and the use of radiation instruments.
In order to properly evaluate the plan's effectiveness, drills will be held on a periodic basis, both scheduled and unannouncud. Lines of communication, actual accessibility of equipment and response of personnel will be evaluated to ensure that the plan is current and realistic. During these-drills personnel will be spot-checked on their knowledge of location and use of emergency equipment, such as full face filter masks, self-contained air-breathing units, and portable radiation survey instruments.
Detailed fire prevention and control procedures will be pre-pared. A Fire Brigade will be established consisting of selected employees that will have the responsibility for fire fighting. 'Under the supervision of a designated Fire Marshall, personnel will conduct periodic inspections of the fire fight-ing equipment, will hold instructional meetings in the use of fire fighting equipment, and will conduct periodic fire drills.
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' Amendment-2 12A-17
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