ML20041A318
| ML20041A318 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/26/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20041A310 | List: |
| References | |
| EPIP-300-1-01, EPIP-300-1-1, NUDOCS 8202190425 | |
| Download: ML20041A318 (16) | |
Text
-
f EPIP
.t O
300 EMERGENCY MEASURES
- l
^!
300-1 Initial Notifications and GSEP Responses l
(Primary Responsibility - Station Director)
Rev. 3.
1/82'
-l 300-C1 NE61ead looiiianhReporting System Fom (Primary Responsibility - Station Director)
Rev. 2 -
5/81-300-2 On-Going Emergency Connunications l
(Primary Responsibility - station Director)
Rev.1 3 /81 300-3 Assembly and Evacuation of Personnel (Primary Responsibility - Operations Director)
Rev.1 2/81 300-4 Emergency Dose Limits and Radiological Controls for Rescue and Recovery Operations (Primary Responsibility - Rad / Chem Director)
Rev. 0 7/80 300-5 Emergency Treatment of Injured Personnel (Primary Responsibility - Operations Director) 34v.1 10/85 300-6 Survey of Injured Personnel (Primary Responsibility - Rad /Chera Director)
Rev. 0 7/80 Q
- 300-7 Personnel Decontamination (Medical -
Decontamination Area) (Primary Responsibility
- Rad / Chem Director)
Rev. 0 7/80 300-8 Post-Accident Sampling of Primary Containment Atmosp.here (Primary Responsibility - Rad / Chem Director)
Rev. 1 10/80 300-9 Pos::-Accident Sampling of Reactor Coolant (Primary Responsibility - Rad / Chem Director)
Rev. 2 1 0/81 300-10 Post-Accident Sampling and Release Rate Detemination of Radioiodines and Particulates (Primary Responsibility - Rad / Chem Director)
Rev. 1 10/80 300-11 Post-Accident Noble Gas Release Rate Detemination (Primary Responsibility - Rad / Chem Director)
Rev. 1 ' 10/80 300-12 Initiation of Environmental Monitoring Activities by the Rad./ Chem. Director (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 300-13 Rad./ Chem. Technicians Actions at Hospital (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 l
?'v JAN261982 PDR ADOCK 05000010
[,
8202190425 820211 s
PDR F
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300 ENERGEllCY MEASURES (Cont'd)
.i 300-14 Estimation of Off-site Dose from an Unplanned Release of Radioactive Effluents (Primary Responsibility - Rad./ Chem. Director)
Rev. 0 7/80 300-15 Deployment of the Eberline SAM-2 Stabilized Assay Meter (Primary Responsibility - Rad./ Chem.
Director) h.1 3/81 i
C l
l JAN261982
_._._.7__
EPIP 300-1 INITIAL NOTIFICATIONS AND GSEP RESPONSES Revision 3 (Primary Responsibility - Station Director)
January 1982 A.
SCOPE This procedure delineates responses from various Generating Station Emerpency Plan (GSEP) categories, notifications for reporting Hazardous materials, notifications for Oil Spill and other notifications required by the Nuclear Regulatory Camrtission (NRC).
B.
POLICY AND METHODS NOTE When making initial notifications j
to any agency or control center for purposes of classifying, up-grading or downgrading an event, the Nuclear Accident Reporting System (NARS) fom (EPIP 300-C1) should be used to ensure that re-quired information is reported.
The following infomation as a minimtzn should be transmitted.
1.
Name and title of the reporting person; 2.
Location and type of incident (i.e., the emergency classifi-cation);
3.
Date and time of incident; l
4.
Whether a release of radioactive material is taking place; 5.
Potentially affected population and areas; 6.
Whether protective measures may l
be necessary.
If verification of the authenticity of a notification is requested by outside agencies, suggest a callback I,
using outside phone lines but do not provide outside phone number infomation.
APPROVED JAN 26'82 1 of 14 D.O.S.R.
i EPIP 300-1 Revision 3
]
NOTE Once the NRC is notified of a GSEP condition, a continuous communications channel with the NRC Operations Center shall be maintained open and shall close only when notified by the NRC.
1.
GSEP responses, a.
Transportation Accident.
(1) Declare Transportation Accident condition.
(2) Use the Emergency Plan Implementing Procedures (EPIP) Notifications Phone List and perfom the following:
(a) Notify the System Power Dispatchsr if the Corporate Command Center (CCC) is not manned.
Otherwise, notify the CCC. Use pre-NARS form or NARS fom (EPIP 300-C1) printed Refer to the attached Table I (Recommended Protect-ive Actions for Gaseous Release).
ym (b) Notify the GSEP Station Group in accordance d
with the Unusual Event category of the attach-ed Table II (Guidance for Augmentation of the On-Site Emergency Organization within 60 Minutes).
(c) Notify the NRC Operations Center.
If the call is made on the Emergency Notifications System (ENS) phone, NRC Region III may also answer.
If NRC Region III does not answer, the NRC Operations Center will contact NRC Region III.
(3) Dispatch personnel for evaluation if deemed necessary.
(4) Notify appropriate local agencies as needed (i.e., fire departments, hospitals, etc.).
b.
Unusual Event.
(1) Declare Unusual Event condition.
(2) Use the EPIP Notifications Phone List and per-fom the following:
l 1
APPROVED M
2 of 14 D.O.S.R.
-+
i EPIP 300-1 t
Revision 3 0
(a) Notify the System Power DisPetener if the CCC is not manned. Otherwise, notify the CCC. Use pre-printed NARS fom or NARS fom (EPIP 300-C1). Refer to Table I.
~
(b) Notify the GSEP Station Group in accordance with the Unusual Event category of Table II.
t (c) Notify the NRC Operations Center.
If the call is made on the ENS phone, NRC Region III may also answer. If NRC Region III does j
not answer, the NRC Operations Center will 1
contact NRC Region III.
}
(3) Notify appropriate local agencies as needed j
(i.e., fire departments, hospitals, etc.).
c.
Alert.
(1) Declare Alert condition.
(2) Use the EPIP Notifications Phone List and perfom the following:
(a) Notify the System Power Dispatcher if the CCC is not manned. Otherwise, notify the s
CCC. Use pre-printed NARS fom or NARS fom (EPIP300-C1). Refer to Table I.
(b) Notify the NRC Operations Center.
If i
the call is made on the ENS phone, NRC Region III may also answer.
If NRC Region III does not answer, the NRC Operations Center will contact NRC Region III.
(c) Activate the GSEP Station Group and augmentation personnel in accordance with the Alert category of Table II.
During other than nomal working hours, this activation is accomplished by noti-fying the Operations Outy Supervisor.
(3) Activate the On-Site Technical Support Center (TSC) and the Operational Support Center (OSC).
(4) Notify appropriate local agencies as needed l
(i.e., fire departments, hospitals, etc.).
l d.
Site Emergency.
(1) Declare Site Emergency.
C APPROVED l
JAN 26'82 3 of 4 D.O.S.R.
I u
~
EPIP 300-1 j
Revision 3 h
(2) Use the EPIP Notifications Phone List and perfom the following:
(a) Notify the System Power Dispatcher if the CCC is not manned. Otherwise, notify the CCC. Use pre-printed NARS form or NARS fom (EPIP 300-C1). Refer to Table I.
(b) Notify the NRC Operations Center. If the call is made on the ENS phone, NRC Region i
III may also answer. If NRC Region III does not answer, the NRC Operations Center will contact NRC Region III.
(c) Activate the GSEP Station Group and augmentation personnel in accordance j
with the Site Emergency category of Table II. During other than nomal working hours, this activation is accomplished by notifying the Oper-ations Duty Supervisor.
(3) Activate the On-Site TSC and the OSC.
(4) Dispatch personnel for environs monitoring, if required.
O (5) Notify appropriate local agencies as needed i
(i.e., fire departments, hospitals, etc.).
e.
General Emergency.
(1) Declare General Emergency.
(2) Use the EPIP Notifications Phone List and perfom the following:
(a) Notify the System Power Dispatcher if the CCC is not manned. Otherwise, notify the CCC. Use pre-printed NARS fom or NARS l
fom (EPIP 300-C1). Refer a Table I.
i If initial notification is over the NARS, i
the System Power Dispatcher or the CCC should answer.
It may be desirable to confim the message to the System Power l
Dispatcher or the CCC by alternative means l
f f time pemits.
(
.~
U APPROVED 4 of 14 M
D.O.S.R.
i
.~
~
}
EPIP 300-1 Revision 3 O
(b) Notify the Illinois Emergency Services and Disaster Agency (ESDA) if the CCC is not manned. Use pre-printed NARS i
fann or NARS fann (EPIP 300-C1). Make i
recommendations in accordance with Table I and Figure I (attached).
If the call is made on the NARS phone, the Will County Emergency Operations Center, Grundy County Sheriff's Office and Illinois Department of Nuclear Safety may also answer.
If these agencies do not answer, they will be contacted by ESDA.
If NARS fails, contact all agencies by commercial phone system j
within 15 minutes of declaration.
f (c) Notify the NRC Operations Center.
If the call is made on the ENS phone, NRC Region III may also answer. If NRC Region III does not answer, the NRC Operations Center will contact NRC Region III.
(d) Activate the GSEP Station Group and augmentation personnel in accordance with the General Emergency category of Table II. During other than nonnal working hours, this activation is
(',;
accomplished by notifying the Operations j
Duty Supervisor.
(3) Activate the On-Site TSC and the OSC.
l (4) Dispatch per.,nnel for environs monitoring, i
if required.
i (5) Notify appropriate local agencies as needed (i.e., fire departments, hospitals, etc.).
(6) Provide plant status updates to the State and Local authorities until these functions can be perfonned by the CCC Director or Recovery Man-l ager.
1 l
2.
10 CFR Part 20.403 Notifications (NRC Operations Center, NRC Region III and Illinois Department of Nuclear Safety).
Refer to EPIP Notifications Phone List for notifications.
l a.
Immediate notification:
Each licensee shall immediately notify by telephone and telegraph, mailgram or facsimile, the NRC Oper-ations Center, the Director of the NRC Region III Office and the Illinois Department of Nuclear Safety APPROVED 5 of 14 JAN 26'82 1
O.O.S.R.
t
.i-
.i' EPIP 300-1
'k Revision 3
)
of any incident involving by-product, source or Special Nuclear Material (SNM) possessed by him and which may have caused or threatens to cause:
(1) A dose to the whole body of any individual of 25 rem or more of radiation; a dose to the skin of the whole body of any individual of 150 rem or more of radiation; or a dose to the feet, ankles, hands or foreams of any individual of 375 rem or more of radiation; or, (2) The release of radioactive material in con-centrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 5,000 times the limits specified for such materials in Appendix B of 10 CFR 20; or, (3) A loss of one working week or more of the operation of any facilities affected; or,
- (4) Damage to property in excess of $200,000.
b.
Twenty-four hour notification:
Each licensee shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify by telephone and telegraph, mailgram or facsimile,
-(,'
the NRC Operations Center, the Director of the NRC Region III Office and the Illinois Depart-ment of Nuclear Safety of any incident involving licensed material possessed by him and which may caused or '.hreatens to cause:
(1) A dose to the whole body of any individual of 5 rem or more of radiation; a dose to the skin of the whole body of any fncividual of 30 rem or more of radiation; or a dose to the feet, ankles, hands or foreams of any individual of 75 rem or more of radiation; or, (2) The release of radioactive material in concen-I trations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in Appendix B of 10 CFR 20; or, (3) A loss of one day or more of the operation of any facilities affected; or,
- (4) Damage to property in excess of $2,000.
l
- For the State of Illinois, the property damage reporting requirements are $100,000 and $1,000 for immediate and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification, respectively.
APPROVED 6 of 14 JAN 26*82 D.O.S.R.
i EPIP 300-1 Revision 3
{')
3.
Oil Spill.
\\
a.
Notify:
(1) Duty Officer National Response Center, U.S.
Coast Guard; or, (2)
U.S. Coast Guard District Office; or, (3)
U.S. Environmental Protection Agency.
b.
Notify the Director of Water Quality Environmental Affairs Department - G.O.
c.
Notify the Division Manager Nuclear Stations Production Department - G.O.
d.
Review Section B.4. of this procedure.
4.
10 CFR Part 50.72 Notifications (NRC Operations Center).
Refer to EPIP Notifications Phone List for notifications.
l NOTE With respect to Steps B.4.a.
through d. the Station Director, I
in addition to notification, shall establish and maintain an open, continuous communications channel with the NRC Operations Center and shall close this channel only when notified by the NRC.
The conditions listed below may or may not require GSEP activation.
However, any of these conditions require notification of the NRC Operations Center within one hour and identification that the report is being made pursuant to 10 CFR Part 50.72. The primary channel for telephone notification should be through the ENS.
In the event contact cannot be made through the ENS, the NRC Operations Center shall be contacted directly by commercial line. Any reports made over the dedicated telephone line are considered to satisfy the Technical Specifications requirements for prompt telephone noti-fication within twenty-four hours. Technical Speciff-cations requirements for confinnstion reports by l
telegraph, mailgram or facsimile transmission still l
apply.
NOTE I
The Nuclear Duty Officer and the News Infomation Duty Officer APPROVED shall be notified any time the NRC 7 # 4 U.0.S.R.
1
EPIP 300-1 Revision 3 is notified pursuant to 10 CFR Part 50.72.
I i
a.
Any event classified in GSEP as an Unusual Event, Alert, Site Energency or General Emergency.
b.
The exceeding of any Technical Specifications Safety Limit.
c.
Any event that results in a nuclear unit not being in a controlled or expected condition while oper-ating or shut down. This excludes anticipated transients which are controlled through prescribed actions. The uncontrolled condition is interpreted as a serious event that could result in an impact on public health and safety such as:
(1) A failure of the Reactor Coolant, Steam, Feedwater or Emergency Core Cooling Systems which results in an uncontrolled increase in containment radia-tion levels, pressures or temperatures, or an uncontrolled release of radioactivity off site.
(2) Reactor coolant system pressures and temperatures which cannot be brought under control due to the
{.
failure of vital equipment or vital systems.
d.
Act which threatens the safety of station personnel or the security of the nuclear units or SNti. This includes civil disturbances or acts of sabotage that threaten this safety.
e.
Any event requiring initiation of shutdown of the j
nuclear power plant in accordance with the Techni-cal Specifications Limiting Conditions for Operation (LCO).
f.
Personnel error or procedural inadequacy which, during nomal operations or accident conditions, prevents or could prevent, by itself, the fulfill-ment of the safety function of those structures, i
systems and camponents important to safety that are needed to safely shut down the Reactor, or remove decay heat, or limit the release of radio-activity to allowable levels or reduce the potential for such releases.
g.
Any event resulting in manual or automatic actuation of Engineered Safety Features (ESF), including the Reactor Protection System (RPS).
(1) Notification is required for unplanned unit APPROVED or reactor trips resulting from valid RPS actuation, gg a of 14 D.O.S.R.
I EPIP 300-1
,)
Revision 3 i
(2) Excluded from notification a: e:
(a) Partial actuation of Safeguards or RPS (i.e. - hal f scrams).
1 (b) Actuation of ESF, including the RPS, which results from and is part of the planned sequence during surveillance testing.
h.
Any accidental, unplanned or uncontrolled radio-active release. (flomal or expected releases from maintenance or other operational activities are not included.)
(1) Gaseous or liquid releases require notification if:
(a) A minor release which escapes the plant is detectable either through sampling, or observation of a (recording) monitor, or reaches a monitor alam setpoint and is associated with an unplanned or acci-dental event.
("'
(b) The release exceeds a Technical Speciff-cations LCO.
(2) Excluded from notification are increases in effluent monitor readings from sampling, in-ventory changes in vented tanks or equipment and increases attributable to operating pro-cesses wherein radioactive water moves through systems with minor leakage such that activity will be released to vented buildings (i.e. -
let down-divert or start of pumps with controlled leakage seals).
i.
Any fatality or serious injury occurring on the site and requiring transport to an off-site medical facility for treatment. Serious injury is an injury that re-l auires admission of the injured individual to a hospital for treatment or observation for greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
j.
Any serious personnel radioactive contamination requiring extensive on-site decontamination or outside assistance.
(Serious contamination re-quires medical treatment for skin tissue removal or involves internal contamination - it is more than the scrubbing of skin or shaving off of hair).
APPROVED i
JAN 26'82 9 of 14 D.O.S.R.
I
-l EPIP 300-1 Revision 3 k.
Strikes at the facility which prevent Operating or Security personnel from providing shift relief with-in four (4) hours of the nonnal relief time.
-r 1.
Any event meeting the criteria of 10 CFR Part i
il 20.403 for notification. (Review Section 8.2.
~
of this procedure.)
'l Inoperability of one or more extensions of the ENS.
m.
1 C.
REFERENCES 1.
Supplement to I.E. Infonnation Notice No. 80-06, July 29, 1980.
2.
I.E. Bulletin No. 80-15, June 18,1980.
3.
4.
10 CFR Part 20.h03.
5.
I.E. Bulletin No.79-068.
6.
I.E. Bulletin No. 79-08.
{
7.
fluclear Stations' Division Vice-President's Directive No. 014.
8.
Section D.403 of the Rules and Regulations for Protection against Radiation of the Illinois Department of Public Heal th.
l l
l l
l APPROVED JAN 26'82 D.O.S.R.
10 of y L
d EPIP 300-1 TABLE I Revision 3 RECOMMENDED PROTECTIVE ACTIONS FOR GASE0US RELEASE Accident Classification /
Actual Containment Radiation Recommended Protective NARS Fonn Release Situation Projected Doses (Rem)** Level (R/Hr) When No Actions Section 8 (HARS Fonn in Zonal Areas X,Y&Z Projected Doses are (S-Shelter, E-Evacuation, Section 6)
Whole Body Thyroid Available P-Prepare for Possible Action, I.0 - Info Only)
.y...y.
.Z'-
X ' Y-
'Z' X'Y*'l'
- *******' * **** ~~*
- 1. Unusual Event NORMAL 6.A-No Release (1) 0-0 0*
0 0
'0-CONTAINMENT RAO:** -
'I:0'****
- '(1) 8;A 6.B or E-Poten-tial or Stopped (2)<0:5 M'
M-
<2:5 M M- * ' ' *
< 2 00
- 6.C or D-Immin-I:0
- - -(2) *** 8;A*
ent or Occurring (3)<0.5 M M
(2.5 M M
<200 1.0 (3
8.A
.......................)...............
- 2. Alert NORMAL 6.A-No Release (1)- 0 0-
- 0-
- 0 0
0-
- CONTAINMENT'RAO:
- ** I:0
-(1)**** 8:A 6.8 or E-Poten-tial or Stopped (2k0.5 M M ( 2.5 M M
(200 1.0 (2) 8.A (3k1:0<0:5 M <5:0(2:5 M 200 v400 *
*-(P) 'P)* P)************(3)*****8:B****
6.C or D-Immin-ent or Occurring (4) Analysis not Complete
< 200 I.0 (4) 8.A (5) Analysis not Complete 200 - 400 (P) P) P)
(5) 8.B (6)(1.0(0.5 M
<5.0<2.5
..........................(..)..).....)............(.6)
H P
P P
8.8
- 3. Site Emergency NORMAL 6.A-No Release (1)
- 0-0 - 0 0
- 0-0 CONTAINMENT *RA0;'
(P)
P)- P)* ** ****-**(1)****'8:B'**
6.B or E-Poten- (2) All Dose All Dose
<,2000 (P) P) P)
- (2) 8.B tial or Sto;.,. a ***S1toations-S1 toa tion s ' * * * '
- 6.C or D-Immin- (3)
Analysis not Complete
<400 (P) P) P)
(3) 8.B ent or Occurring (4)
Analysis not Complete 400 - 2000 (S) P) P)
(4) 8.C&D (5)(1.0<0.5 M
<5.0<2.5 M
(P) P) P)
(5) 8.8 (6)>1.0<l.0 M
> 5. 0(5. 0 M (E*) S*) P)
(6) 8.C.H&E
( 7 )>1. 0>1. 0<1. 0 > 5. 0>5. 0 <5. 0....
....(...)E*) S)............................. H.I&F E*
(7) 8.C b
c h ~O 11 of 14 U
n
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g (n a-O h tb k n
Ji Pkx n
O o
o @ :U u)
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gyh TABLE I (Cont'd.)
Revision 3 EPIP 300-1 Acci nt Classification /
Actual Containment Radiation Recommended Protective NARS Form Release Situation Projected Doses (Rem)** Level (R/Hr) When No
-Actions Section 8 (NARS Fonn in Zonal Areas X,Y&Z Projected Doses are (S-Shel ter, E-Evacuation, Section 6)
Whole Body Thyroid Ava ilable P-Prepare for Possible Action, I.0 - Info Onl
........x....y....z.......y)
.x.
.y...y.
..y.
.y...z........
- 4. General Emergency 6.A-No Release (1)* 'NOT' APPLICABLE'T0* GENERAL'EMERGENCf'*******************'
6.8 or E-Poten-tial or Stopped (2) All Dose All Dose 0
' ' ' S 1 tua t i o n s ' *
- S i tu a t i o n s ' ' ' ' * * * * * * * * * >* * * * * * * * * * * * * ' ' ' * * (* S )
S)
P)
'*********'*(2) 8.C,0&E 6.C or D-Immin-ent or Occurring (4)(1.0<0.5 Analysis not Complete
>0 3)
((S)) S)
P)
E*
((4))
3 8.C.H&E L
M (5.0<2.5 H S)
P) 8.C D&E (f5)>1.0<1.0 M
>5.0(5.0 M (5)'
((E*1E*h E*) S)
S)
P) f 8.C H&E 6 )> 1. 0>1. 0 <1. 0
>5.0>5.0<5.0 6) 8.C.H.IAF (7)>1.0>1.0>1.0
>5.0>5.Q>5.0 (E*) E*)
E*
7
...............)........(..)....... 8.C H,1&J Foot Notes:
The symbol () ) ) represents the entire 0-2 mile area, and the 2-5 and 5-10 mile three downwind sectors.
R-Range (Miles)
SB-Site Boundary H-Minimal Evacuation, when noted, is the recommended protective action only when weather conditions permit and an evacuation time analysis confinns it as the preferred choice: otherwise, sheltering is the protective action to reconnend.
If evacuation is recommended for Zonal Areas Y and Z and if Zonal Areas Y and 2 are in Wisconsin or Iowa, then the recommendation for evacuation should extend only to the range at which the projected dose is 1 Rem WB or 5 Rem thyroid, whichever is the greater range.
out to 5 miles if the " range" is in Zone Y and out to 10 miles if it is in Zone Z. Sheltering is the protective action from this ra Projected actual doses are based on the actual or most likely release point and the existing site meteorological conditions. The Zones X, Y and Z are:
X SB
..... 4..R (2 Miles; Y-2 4.R < 5 Miles; Z-S f.R <10 Miles.
12 of 14
~
EPIP 300-1 g
Revi:fon 3 i O Taste II GUIDANCE FOR AUGMENTATION OF THE ON-SITE i
EMERGENCY ORGANIZATION WITHIN 60 MINUTES 1
Augmentation witnin 60 Minutes-Functional Area Unusual Event Alert Site & General Emergency
}
1.
Command & Control Notification Only Station Director 1
1 1
Oper. Director 1
1 1
Maint. Director
- 1 1
1 Tech. Director
- 1 1
1 Admin. Director
- 1
- 1 1
Stores Director
- 1
- 1 1
Rad./ Chem. Director
- 1 1
1 Security Director
- 1
- 1 1
Environs Director
- 1 1
1 2.
Notifications &
1 1
Communications 3.
Accident Assessment D-Off-Site
- 2 4
On-Site
- 1 1
In-Plant
- 1 1
Rad./ Chem. (Lab)
- 1 1
4.
Technical Support Nuclear (Core)
- 1 1
Electrical
- 1 1
Mechanical
- 1 1
5.
Repair & Correct lon Mechanical
- 1 1
Electrical
- 1 1
Radwaste
- 1 1
Inst. & Control
- 1 1
6.
Protective Actions Radiation Protection
- 2 4
Totals
- 2-9
- 7-24 28
- As needed depending upon the nature of the emergency.
NOTE: Additional support in the areas of Command & Control, Communications and Accident Assessment will be available from the CCC Staff.
It is reasonable to expect partial manning of the CCC within 60 minutes for Site & General Emergencies.
APPROVED 13 of 14 2 2682 D.O.S.R.
t
u-.. _,.. '
.1.
'l EPIP 300-1 Revis tori 3 SECTOR AIID f5[- 5ESIr"JATCRS
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4..
4 N-E 148' MA 11*
g 393 NNE C
e6' NW gg P
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m D
281*
ENE \\
78*
N west 1
2c8'
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sw 236*
.c/
L SSW cc-Scuth g
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G 121 K W mil _ H 2r3 f
J ue.
m'
. uuc.
APPROVED rucuRE 1 J4# 26'82
- .~ :
D.O.S.R.
14 of l'+ (FINAL.)
.. -_