ML20031B294
| ML20031B294 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/28/1981 |
| From: | Bryan J UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-520, NUDOCS 8110010180 | |
| Download: ML20031B294 (20) | |
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e UNION ELECTRIC COMPANY 1901 GRATIOT STREET ST. Louis. Missount JOHN M.SRYAN P
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September 28, 1981 D
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/bh Mr. Harold R.
Denton Director of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555 ULNRC-520 l
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Dear Mr. Denton:
DOCKET NUMBERS 50-483 AND 50-486 CALLAWAY PLANT, UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT Per the September 25, 1981 telephone conversation between members of the Union Electric Company staff and Mr. W.
L.
Axelson, of the NRC, Region III, transmitted herewith are the responses to Mr. Axelson's comments concerning the Callaway Plant emergency response plan.
This information will be included in the next revision of the emergency response plan, and as such, will be formally incorporated into the Callaway Plant FSAR in the next revision.
This information is hereby incorporated into the Callaway Application.
r truly vours, hlh av Joh I ~ryan l
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STATE OF MISSOURI )
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Robert J.
Schukai, of lawful age, being first (.uly sworn upon oath says that he is General Manager-Engineering (Nuclear) for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and.
that the facts therein stated are true and correct to the best of his knowledge, information and belief.
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By E
l Robert J.
c?fukai Genh al Ma ager-Engineering Nuclear SUBSCRIBED and swota to before: me this 29th day of September 1981
/A F Et,RBARA J. PFAFF NOTARY PUBLIC, STATE OF MISSOURI MY COMMtS$10N EXPIRES APRIL 22,1985 ST. LOUIS COUNTY y
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cc:
Glenn L.
Koester Vice President Operations Kansas Ga? & Electric P.O.
Box 208 Wichita, Kansas 67201 John E. Arthur Chief Engineer Rochester Gas & Electric Company 89 East Avenue Rochester, New York 14649 A. V.
Dienhart Vice Pressident Plant Engineering and Construction Northern States Power 414 Nicollet Mall Minneapolis, Minnesota 55401 Donald T.
McPhee Vice President Vansas City Power and Light Company 1330 Baltimore Avenue Kansas City, Missouri 64141 Gerald Charnoff, Esq.
Shaw, Pittmt.n, Potts & Trowbridge 1800 M.
- Street, N.W.
Washington, D.C.
20036 Nicholas A.
Petrick Executive Director SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 W. Hansen Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077
Y CALLAWAY PLANT UNITS 1 AND 2
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DOCKET NUMBERS 50-483 AND 50-486
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Item:
Letters of agreement have not been completed with the State of Missouri Disaster Planning and Operations Office and Callaway, Osage, Gasconade, and Montgomery Counties.
Response
Union Electric Co. will finalize these letters of agreement prior to fuel load.
2.
Item:
Table 5.1 is unacceptable Change:
(30-60) minutes to (30-45) minutes and expand cection 7.2.2.12 (the duty officer system) to include corporate personnel and other site management and supervisory personnel as necessary to ensure design objectives of Table 5.1 can be met.
Fur her, indicate in the plan that periodic off-hours drills will be conducted of the shift augmentation system.
Response
Please refer to Table 5.1 and section 7.2.2.1.2 of the Callaway Plant Emergency Response Plan, which have been revised to reflect the above comments.
3.
Item:
Indicate that a Letter of Agreement or a Memorandum of Understanding with the Wolf Creek Plant, providing mutual assistance and aid, will be reached prior to the issuance of an operating license.
Response
Union Electric Co. intends to finalize a Letter of Agreement with the Wolf Creek Plant prior to issuance of an operating license.
4,.
Item:
The following EAL's still need improvement:
1 (a)
Table 4.1 (Unusunl Event) i No. 3 - give letdown monitor reading (b)
Table 4.2 (Alert)
No. 1 - give letdown monitor reading (c)
Table 4.3 (Site Emergency)
No.
2 - give letdown monitor reading No.
2 - give incore thermocouple readings No. 11 - give effluent monitor readings
No. 13 - give specific. wind speed and specific earthquake level.
No. 15 - give specific containment pressure and temperature le/els.
(d)
Table 4.4 (General' Emergency)
No.
1 - Is there a common release point (one vent) for the plant
- Is the radwaste building vent the only release
- give the wide range radiation monitor readings.
Response
All specific monitor and other instrument readings will be included in the next revision of the emergency plan.
Item No. 15 in Table 4.3 will be incorporated into Table 4.4 and deleted from Table 4.3.
There are two (2) gaseous release points for each unit at the Callaway Plant, i.e.,
the unit vent and the radwaste building vent.
5.
Item:
Provide in the plan a description of the Class A i
meteorological dose assessment model (Radiation Release Information System).
Response
Please refer to the attached Sections Nos.
7.3.1.1, 7.3.1.1.1, 7.3.1.1.3, 7.3.1.5 of the Callaway Plant Emergency Responsa Plan that have been rev Ased in response to the above Item No. 5.
15.
Item:
Develop procedures (only) to assess radiological impact to ingestive pathway EPZ.
Commit to this in the plan.
Procedures to determine when to place cows on stored feed, restrict water intake, restrict crop usage, etc.
Licensee must be capable of making these recommendations.-
The state will conduct the monitoring.
Resporse:
Please refer to the attached Sheen No. F-2 of Appendix F of the Ca laway Plant Emergency Response Plan that 1as been revised to include the above requested procedure.
7 Item:
On page 6-15 the time estimate is missing.
Response
This time estimate is 25 minutes. -Please reft.-
to the attached page No. 6-15 of the'Callaway A
- Plant Emergency Response Plan that has been revised to include the above comment.
8.
Item:
Evacuation routes (primary and alternate) for site personnel are not provided in the plan.
How are you going to move licensee personnel from the site to the EOF.
Response: 'Please refer to Figures 6.1 and 6.2 which will be included in the next revisions of the Callaway Plant Emergency Response Plan.
These figures show the primary and alternat( routes from the plant site to the EOF.
9.
Item:
Include in Section 8.1.1.1.3 a statement to the
.effect that the radiological monitoring teams will be trained in the use of the post accident sampling system for primary coolant and station effluent.
Response
Please refer to the attached Section 8.1.1.1.3 of the Callaway Plant Radiological Emergency Response Plan which has been revised to reflect the above comment.
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Notification i.e workers on site may be made through any of several methods.
All' personnel, including visitor and
, contractor personnel inside the plant, will be notified through methods given in Chapter 7.
Such notification should
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take no longer.than one to two minutes.
During the construction of Unit 2, these methods may not be adequate outside the plant due to high noise levels.
In this case, it will be necessary to dispatch plant personnel to the construction site for notification by word of mouth, portable radio or loudspeaker. -It is estimated that this notification could be accomplished within 10 minutes.
e.
Following notification, plant personnel will evacuate the affected area.
In the worst situation, all plant perconnel without specific emergency assignments will evacuate work areas and assemble in the maintenance shop.
From this point,-
plant personnel will be instructed to evacuate to the Eniergency Control Center parking lot area.
Working and non-working visitors, contractor and construction personnel will evacuate immediately to the Emergency Control Center parking lot area.
Further instructions will be issued at the Emergency Control Center.
It is anticipated that the time required for assembly in the maintenance shop i'ill not exceed 10 minutes, and evacuation to the Emergency Control Center, by foot or automobile, approximately 15 minutes.
Evacuation outside the plant will be directly to the Emepjency Control-Center, by foot or automobile, within 15 minutes.
For the worst case situation, the emergency response times, from initiating event to evacuation of personnel to the Emergency Control f
Center, are estimated to be:
EVENT TIME a.
Detection Immediate b.
Verification 10 Minutes c.
Asses ment 30 Minutes d.
Notification 10 Minutes l
c.
Assembly & Evac 9ttion 25 Minutes Total Elapsed Time Approximately 75 Minutes 6.4.1.2 Offsite Areas Off-site protective actions are the responsibility of the principal state agency (DPOO).
Appendix D summarizes the actions which may be considered by state and local agencies in the event of an accident.
Uniori Electric assumes responsibility for promptly alerting (within 15 minutes after declaration of an emergency classification) the public out to a distance of ten miles from the plant sit".
6-15 Rev. e 9/81 a
_, s.
42 7.2.2.9 On-Site Operations Support Center Communications are provided from this area to the Control Roor' And the Technical Suppor' :: e n t e r.
7.2.2.10 Recovary Center This center maintains dedicated commuaications links to the On-Site Technical Support Center, Emergency Control Cente:, Emergency News Center, NRC, NSSS Supplier, Architect / Engineer, Corporate headquarters, anA a number of outside lines.
In addition, this center maintains data transmission capabilities and a telephone system for communicatic;is within the recovery organizatic..
Access to the plaat UHF and UE VHF radio systems is available on the EOF radio console.
j
' 2.2.11 Emergency Control Center This center maintains communic: tions links with the remaining en.ar. ency organization centers and with off-site emergency agencies.
i This anter also maintains radio comr.iunications with monitoring and assistance teams dispatched from the center.
7.2.2.12 Communication Provisions For Activating Shift Augmentative Personnel i The Shift Supervisor will contact the Emergency Duty Officer (EDO)
I from the plant.
The EDO if he deems necessary will alert and I activate the shift augmentative t'ersonnel, by means of a multiple l personnel immediate notification system.
This system is described in I the Implementing Procedures.
The system adequacy will be verified by
- l. quarterly test-activiation during normal and off-hours.
7.2.2.13 Emergency Communications With The NRC The NRC Emergency Notification System Telephone line (Red Phone) and the NRC Health Physics Network telephone lines provide direct telephone communication links with the NRC.
These telephone lines will be installed o~ uninterruptible power sources.
7-8 Rev. 5 9/81
7.3 ASSESSMENT
FACILIT'.ES 7.3.1 ON-SITE SYSTEMS AND EQUIPMENT 7.3.1.1 Natural Phenomena Monitors A monitoring system is provided for the recordine of meteorological parameters in the vicinity of the plant site.
Meteorological measurements include wind speed, wind direction,-
standard temperature at 10 meters, temperature difference between 10 meters and 90 meters and 10 meters and 60 meters, and precipitation.
Back-up meteorological measurements are wind speed, wind direction and estimation,of atmospherie stability at 10 meters.
A readout of these parameters is available in the control room, the Technical l Suppcit. Center and the Emergency Control Center located in the EOF.
Meteorological parameters, along w. th radiological monit ors and ventilation system flows are input to the Radioactive Release l In form:2 tion System iRRIS)to determine off-site dose rates. (See l 7.3.1.5).
7.3.2.1.1 Locations and Elevations of Instruments l The primary meteorological tower is located in an open field approximately 1.4 miles east-northeast of the plant (latitude, 38 45' 55" N, longitude, 91 45' 27.5" W).
The tower is on a plateau l surrounded by flat undulating terrain.
The back-up meteorological l tower is located approximately 1 mile west of the plant.
I Meteorological instruments are mounted on the priaary meteorological tower at heights of 10, 60, and 90 meters.
Wind speed and wind
. direction are measured at all three levels.
Temperature is measured at the 10-meter level as well as the temperature difference between the 60-meter and 10-meter levels and between the 90-meter and 10-meter.' levels.
Dew point is measured at the 10-meter level.
Precipitation is measured at ground level.
Wind and. temperature sensors are mounted on retractable booms l' extending 10 feet outward from the triangular primary tower mainframe and are oriented approximately south-southwest and southeast, respectively.
This sensor configuration and orientation assures maximum exposure to prevailing air flow and minimal interference from the tower structure.
Recorder equipment is housed in an instrument shed located near the tower.
7.3.1.1.2 Description of Instruments Accuracy of the instruments measuring wind direction, wind speed, and temperature conforms with NRC Regulatory Guide 1.23.
The Climet wind speed transmitter has a threshold of 0.6 mph and a calibrated range of up to 100 mph and performs over a' temperature range of -50 F to 155 F.
Temperature measurements at the 10-meter level are made with an accuracy of +0.15 C.
All temperature difference measurements are 7-9 Rev. 5 9/81
made with an accuracy of +0.15 C per 100 meters.
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In case of a power failure at the tower, there is an emergency electric generator that starts automatically and supplies-power to the meteorological instruments within 40 seconds.
7.3.1.1.3 Calibration Calibrations are performed on each of the sensors and their associated recorders at 3-month intervals.
During calibration, the instrume,ts are checked and cleaned, and parts are replaced as necessary.
The instruments are then recalibrated using NBS-traceable l standards.
Inspections for evaluation of the meteorological l measurements system are performed weekly.
7.3.1.1.4 Offsite Meteorological Data In the event that information from the meteorc.iogical towers are not available, procedures will be available whereby meteorological information can be obtained from T~te National Weather Service in Columbia, Missouri, located 30 miles west north west of the Callaway Plant site.
7.3.1.1.5 Seismic Instrumentation Seismic Instrumentation is also provided to supply information necessary for the evaluation of the effects of earthquakes on the plant Seismic Category I structures, systems, and components.
Readout is available in the control room.
7.3.1.2 Radiological Monitors F readout of the radiation monitoring systems for air, liquid, and gas radioactivity is available in the control room and may be used in emergency situations.
The radiation monitoring systems are described in Chapters 11 and 12 of FSAR.
Portable monitors and sampling equipment used during normal plant operations are available and can be used during emergency conditions.
Additional portable monitors and sampling equipment is located in the Emergency Control Center.
7.3.1.3 Process Monitors Information necessary to monitor the nuclear steam nupply system, the containment system, and the balance of plant is displayed on the operator's censole and the various vertical boards located within the control room; hot shutdown information is also displayed on the auxiliary shutdown control panel outside tha control room.
The. e indications include the information to control and operate the : nit through all operating conditions, including anticipated operacing occurrences, and accident and post-accident conditions.
This display instrumentation to discussed in Section 7.5 of the FSAR.
7.3.1.4 Laboratory Facilities Laboratory facilities include the hot chemistry laboratory and 7-10 Rev. 5 9/81
-: ~
counting room adjacent to the. Health Physics offico, a counting room in the Radwaste Building, and a, cold chemistry laboratory in the turbine building.
These facilities are designed to handle all chemical and radiolegical sampling and analysis during all normal modes of operation.
During an emergency, additional laboratory facilities may be necessary to evaluate samples which are extremely radioactive, such as high contaminated reactor coolant, and-to evaluate samples with very low level of activity, such as very lightly contaminated and/or uncontaminated environmental samples.
Back-up laboratory facilities will be available in the. Emergency Operations Facility during an emergency should the in-plant laboratory facilities be unavailable.
The EOF backup laboratory facility is a permanent fully equipped analytical laboratory wi,h the capabilities to support radiochemistry analysis and evaluation of radiological 53amples.
EOF laboratory equipment and analytical capabilities include:
a.
Gamma spectorscopy equipment consisting of a 16K channel, microprocessor based multichannel analyzer and a'HPGE de.tector with graded shield.
This equipment will provide the capability for manual or machine assisted radioisotopic identification and quantification or radiological samples significant to the assessment of plant and environmental conditions during an accident.
b.
Gas flow proportional counter for alpha and beta counting applications.
c.
GM detector and scaler for gross retivity evaluation of samples.
l 7.
.l.5 Radioactive Release InJormation System (RRIS) l The RRIS will provide real-time predictions of atmospheric transport I and diffusion estimates of radioactive releases.
It will provide l this real-time information to consoles in the control room, Technical l Support Center, and Emergency Operations Facility.
The RRIS, in l' generating the required reports, displays and interfaces, will-I utilize real-time meteorological data, radioactive release ^ rate data l from the Radiation Monitoring System, isotopic concentrations l determined from the laboratory MCA, and flow rate: from the l Ventilation System.
l Meteorological data-from both the primary and back-up towers will be I transmitted to the RRIS computer.
Normally, the RRIS will utilize l the primary tower data.
Upon detection of an 9rror, it will-l automatically switch to the back-up parameter and provide an alarm to l record the event.
l The RRIS will utilize a Class A model which will provide calculations l-of relative concentrations (X/0)'and transit times withing the plume l exposure EPZ.
Atmospheric diffusion rates will be based on l atmospheric stability as a function of site-specific terrain I conditions.
Site-specific local climatological effects on the 7-11 Rev. 5 9/81
~
l trajectories, such as seasonal, diurnal, and terrain-induced flows, l will be included'.
l Source characteristics (release mode and building complex influence)
I will be factored into the model.
The gross radiation, flow rate, and i isotopic spectrum will be input to the RRIS automatically and will be l utilized to calculate the release rate.
l The output from the RRIS will include the plume dimensions and I position and the location, magnitude, and arrival time of (1) the' l peak relative concentration and (2) the relative concentrations at l appropriate locations.
7.3.2 FACILITIES AND EQUIPMENT FOR OFF-SITE MONITORING Assessmen't of off-site dose information will be accomplished with portable-type equipment for measuring radiation and airborne radioactivity levels.
This equipment will be maintained at the site.
During operation of the Callaway Plant, extensive radiological monitoring of the facility and its environs will be undertaken.
The purpose of that monitoring will be to quantitatively docu.nent any radioactivity released from the facility and to monitor the distribution of these radioactive substances in the ecosystem.
To provide complet'e surveillance during the operation of Callaway Plant, 15 continuously operating air particulate sampJ ers are located in one rough circle and one rough half circle around the Callaway Plant (see Figure 7.5).
The inner circle was generally 1 to 3 miles from the facility, while the outer half circle was from 6 to 12 miles.
Seven o.' the particulate samplers were equipped with a charcoal iodir impregnated cartridge filter.
The cartridge was mounted behind the filter paper attachment.
To monitor gross gamma fidiation, thermoluminescent dosimeters were inctalled at 40 locations.
The TLD's were placed to provide an inter-and outer-ring surveillance network around the site.
The locations of the TLD's are 7-Ila' Rev. 5 9/81
8.1.1.1.2 Accident Assessment Personnel I
1 Accident' assessment as to emergency classification is the l
responsibility of the Emergency Plant Operations Manager.
Training of these individuals is described in Section 8.1.1.1.1.
All plant personnel will be given appropriate training on the emergency procedures corresponding to the emergency clas,iff rations.
8.1.1.1.3 Radiological Monitoring Teams All Radiation & Chemical Technicians and all plant personnel that may be required to perform surveys will be given training in emergency monitoring.
This will include instruction in the selection and une of survey instruments and air sampling equipment and in re-entry I criteria.
Also, the radiological monitoring teams will be trained in l the use of the post accident sampling system for primary' coolant and I station effluents.
8.1.1.1.4 Repair and Damage Control Teams Repair and control of Mamage to equipment will be under the direct supervision of the Emergency Plant Operations Man'ager, or his designee.
Repair and damage contre-1 teams will primarily be composed of maintenance personnel who will receive training in accordance with FSAR Section 13.2.1.6.
8.1.1.1.5 Firct Aid and Rescue Teams j
Plant personnel will be trained in basic safety, first aid, and emergency rescue operations and will include courses equivalent to Red Cross Multi-Media.
8. ~.. l.' 2 Local Services and Medical Support Personnel
' Off-site groups such as reccue and ambulance services, and medical
. doctors that may participata in on-site emergency activity will be given instructions as appropriate to ensure that they are familiar with emergency plans, procedures for notification, basic radiation protection, plant layout, and their expected response actions in the event of an accident.
Retraining of off-9ite groups will be' performed on an annual basis.
For those local services support organizations who may enter the cite, training will also include site access procedures and the identity.(by position and title) of the individual in the on-site emergency organization who will control the organizations' support activities.
8.1.1.3 Off Site Emergency Organization The initial training and plant familiarization for personnel assigned to the off-site emergency organization will include the following:
8 Rev. 5 9/81
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a.
The organization and chain of co' mand.
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' APPENDIX F LIST OF EMERGENCY PLANNING IMPLEMENTING PROCEDUP.ES-I,'
(Continued)
<4 23.
Distribution of Emergency Plhn, Implementing Procedures, and Revisicns thereto (8.2.1) l' 24.
Assessment of radiological impact to the ingestive pathway EPZ, l
and determina-tion of the corresponding necessary protective l'
actions.
0
.p_2 Rev. 5 9/81'
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E' i
TABLE 5.1 f
MINIMUM STAFFING i
FOR CARLAWAY PLANT Ll!ERGEN;I*S l
NUREG-Od34 STAFFING REQUIREh5NTS CORRELATION WITI! TABLE B-1 i
i ADDITICNAL CAPABILITY g
FOLLOWING NOTIFICATION tl -l OF SITE OR GENERAL EMERGENCY
- }
i l MAJOR FUNCTIONAL AREA MAJOR TAfMS POSITION TITLE OR EXPERTISE ON SHIFT 30-45 MIN.*
60-75 MIN.*
l l
Plant Operatione Shift Supervicor 1
l l
and Assessments of Cperating Supervisor 1
(
Operational Aspects Unit Reactor Operators 2
r Equipment Operators 2
l Assistant Equipment Operators 2
Instrument-Control Tech 1
Radiation-Chemistry Tech
- 1 I
= - -.--
=_
. 8 i
l' Emergency Direction Chift Supervisor or designated 1**
l and Control Emer9%ncy Plant Operations Manager 1
___ __---= _____--
i 1
l Notification /
Notify State, local Qualified Personnel ***
1**
1 2
l
,1 Communication and Federal personnel j
t l
& maintain communications 1
1
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_==__
-_____..._=____
=_._
.__==--..--__-______-_...__-.__-___
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Radiol 0gical Accident Offsite Dose Assessment Emergency Control Center 1
i
{
Assessment and Support Supervisor and 1
of Operational Accident Health Thysics Coordinator Assessment Offsite Serveys 2
2 1
1 Onsite (out-of-plant)
In-plant surveys Qualified Personnel ***
1**
1 1
1 Chemistry / Radiochemistry Rad / Chem Personnel 1**
=_-- --__--...--__-
- - - _ _ _ _ =
_..==_ _--
==--.
Plant System Technical Support Shif t Technical Advisor 1
1****
t Engin +ering, Repair Core / Thermal F Jraulics i
and Currective Actions Electrical 1
i 1
Mechanical 1
Repaie as* Corrective Mechanir..4aintenance/
1**
1 Ac* ions Rad W-Operator Ele'
.1 Mairtenance/
1**
1 1
t In
- .ent and Control 1**
l i
'46.s Personnel i
g l
_=_=---- -----====
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_=
=.
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M--
..s TABLE 5.1 ADDITIONAL CAPABILITY I
FOLLCWING. NOTIFICATION l
OF SITE OR GENERAL EMERGENCY l MAJOR FUNCTIONAL AREA MAJOR TASKS POSITION TITLE OR EXPERTISE-+
ON'ShCFT 30-45 MIN.*
60-75 MIN.*
l Protective Actions Radiation Protection Rad / Chem Personnel 2**
2 2
1 (In-Plant)
I
- a. Access Control
'b. HP Coverage for repair, corrective actions, search and rescue first-aid & firefighting
- c. Personnel monitoring
- d. Dosimetry
=--=---
a--------------------
--=------------------===
=---_==_.
_=- - = -----------------------------------------=_
Fire Brigade Firefighting per Technical Specifications
==--------
_=------------=___
=-
Local 2**
Rescue Operations and Support First-Aid
= =__
- =------
=== -------------------------=_- -
=-
= _--------
Site Access 'ontrol
- Security, Security Personnel All per C
and Personnel communications, Security Plan
- 1 Accountability personnel accountability g
Y
__=__
--== _ _ _ - - = = =.
=-----------------
l
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TOTAL 11 10 15 f
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I l NOTES:
- Subject to weather and road conditions. The majority of the plant personne) Aive within the 30-45 minute capa-l bility, however may take 45-60 minutes for arrival due to their commuting distancu to the plant.
- May be provided by personnel normally assigned to other tasks.
- Any plant personnel who has completed training in the assigned tasks.
- A person who has a Bachelor of Science dsgree in Engineering er related area who has completed Phase I and II l
8 l
of operations training.
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