ML20054M327
| ML20054M327 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/01/1982 |
| From: | IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML112410174 | List: |
| References | |
| PROC-820601-01, NUDOCS 8207120291 | |
| Download: ML20054M327 (162) | |
Text
___ _ - _ _.
Notification List No. 1 Page 1 of 2 NO REQ.
TOTAL NOTIFICATIONS PARTY CALLED HOME OFFICE IN NO IN1"lAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES NO YES NO E
EMERGENCY COORDINATOR 1
1 "S
g,
gy P) Daniel L. Mineck g l_ '
og
- 1) Bobby R. York g
fB gl1 ya
- 2) David L. Wilson B
t o"
- 3) John V. Vinquist
()
gl1
- 4) Rick L. Hannen t]1 44 Oo EMERGENCY RESPONSE & RECHERY. DIRECTOR 1
1 o o
~'
P) Dick McGaughy
- 1) Larry D. Root h5 3
- 2) liarold Rehrauer N
Ig J
Security Shift Supervisor (CAS) 1 1
^ ^ ^ ~ ~
Linn County E0C (sheriff) 15 min.
398-3911 or Point to Point Radio gp IWAS Phone Benton County E0C (Sheriff) 15 min.
11-472-4777 or 11-472-2337 or Point to Point Radio or IWAS Phone State EOC (005) 11-515-281-3231 15 min.
or 11-515-281-3561 or Point to Point Radio or IWAS Phone Communit r Name Date
Notification List No. 1 Page 2 of 2 NO REQ.
TOTAL h0TIFICAT10NS PARTY CALLED 110ME OFFICE IN N0 INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
Pil0NE EXTENSION 30 MIN.
REQ.
YES NO YES NO NRC "It0TLINE" I hour NRC Operations Center or Bethesda, Maryland l
(202) 951-0550 or (301) 427-4056 or HP Net - 22, or (301) 492-7000 Communicator Name Date 3
9 e
?.
.{
O LN LA NCS OEE I RY TA C
O I
N FL A I
TI OT NISNE I Y L
A
.Q 1
1 8
TOE ONR T
Q N
E I
RNM 1
1 5
I O
0 N
3 F1 l
i
\\
1 i
l 5 5 yK.
!i Ig5 f) 335WRE5p5RE5NRBN W 3W_
p N
2 O
I ES
.o CN N
I E FT t
FX s
OE i
L n
o i
t E
a EN c
MO 0H i
f 1 P e
1 i
t t
a D
o r
i '
,l
{34 17, N
- i ' '
?
i
$ N 3 K U pN1 o
.8 $Q ! 0 R 5 5 3t Q 5
r 1
O a
I 1
l W
t i
N n
i R
d E
r G
o A
o C,
1Rs P
I
))))))))))
n n
I i i I
Iflf L o
a e e e e e e e e e e e e e c e e e c e e i
n n n n n n n n n n i
t c
i i
i i
i i
i i
i i
i c
a a a a a a a a a a E
e n
r r r r r r r r r r M
t h
I I
I 1
I T
i T
1 T
,A o
c
((((((((((
N r
e d
/
P T
r n
E g
o o
L n
n s
r s a s
f s
c n T
o u
n o n r c
s l
i s
i a
r d e o m
i o
o s o r i
DI a e r l
s ET t
Y e s i
s e e s e u e W t
n n
etd o d l
s t
n L
a y
r v r S y
yz o
p o
LY i
h D
a r a D
h n L p
. n r
o t
o k
t n F a e a n e d e
AC d
t P
e P l
P o
o G e s e s
s r k e t h
c a A KN t
r k
i s
e L
i l
p n
i e c s
f k
g a M e
a u s m l
CN a
i b
p u b K
E R
e o d u d a o h
A d
W l
p a
v b a e a n
i b
n c y n B B
n h e
m YG K
B E
S L
P B
t n
n l
i o v a l
l e r u l
u y n e e a a c i
a m
y yG S
N N
TR e
l i
l i
a c S lI E U
E b
R G
F S
K r A i
l r e n s r n r RE t
)))
C
)))
a v u v r i
r, PE S
(((
O
((
(
le e a e e r
. e e a e o o a i
P 1
2 S
P P
1 AM K
P K
G t
L 5
J M J U A R 5
B D
l b
J W N l
M L P
B l
c in e
u m
E m
M o
I C
T 6
flotification List No. 2 Page 2 of 2 g
NO REQ.
TOTAL fiOTIFICATION PARTY CALLED 110ME OFFICE IN NO.
INITIAL RECALL i
TIME EMERGENCY TITLE /NAME PAGER NO.
Pil0NE EXTENSION 30 MIN.
REQ.
YES' f40 YES NO I
Chemistry Technicians 1
1 2
Ralph M. Lewis k
Craig healis 1
54 Anthony Funke I
F Don Rees I
l
- I Radwaste Operators 1
1 James L. Klocke Steven M. Eylers n
M. Larson i
L. Brown l ]
Robert Schlueter (New Operator) i l Marshall flickelson (Irainee) i 1 l
~
~
L. Schmidt (Trainee)
{ l J. Jacobsen (Irainee) f ]
G. 5 kala (Irainee) 1 Exposure Records Coordinator Linda itaven l'
1 Radwaste Coordinator Roger Stigers Environmental ll.P.
Administrative l
Jerald Davis f7 4
f4RC Resident Inspector 1
Larry Clardy homel Nick Chrissotimos G. E. Operations Engineer i
INFORM John Silva pA 4
i Plant Chemist Ralph Fohto k
E g
.. _. - - - ~ -
- Communic, Name Date
'F i
flotification List tio. 3 Page 1 of 4 fl0 REQ.
TOTAL fiO TIF IC ATI0ft i
PARTY CALLED liOME OFFICE-If4 fiO.
IfilTIAL RECALL TIME EMERGE!1CY TITLE /f1AME PAGER fl0.
Pl10f1E EXTENS10ft 30 MIN.
REQ.
YES fl0 YES fi0 k
1 1
TSC Supervisor 8
(P) Bobby R. York 1
(1) David L. Wilson
((
(2) John V. Vinquist 3
(3) Rick L. liannen 3
(4) Gary Van Middlesworth 3
(5) John D. Van Sickel 5
(6) Donald F. Vest E
Control Room Coordinator 1
1 (P) Donald F.
Ieply 3
(1) C. R. Mick 4
[3 Technical & Engineering (P) John Vinquist H
lq (1) Dave Wilson 5
[5 (2) Rick Hannen i
m Security & Support Supervisor (R) Dave Wilson 3
(1) Jim 5parano M
(2) Jerry Davis I
E
( 3) flike Sparks i
IN 2
8 Corrmunicators (P) Mike Chandler u
3 (P) Ken Feveler it
~
l3 (P) Linus Drouhard f i l5 (P) Jef t lielson F
lR (P) I aj Iiahamnied J
[W (1) liill Rackle T
lW (2) bill Scholberg i
15
( 3) bene Havlic p :
lR (4) Sam Ray I
~ [W (b) John Johnson T
lW (6) Bill Lilis
[4 (7) Clare Bleau lW 7*5 s
Communicator flame Date
Notification List No. 3 Page 2 of 4 NO REQ.
TOTAL NOTIF' CATION PARTY CALLED HOME OFFICE IN NO.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
r PHONE EXTENSION 30 MIN.
REQ.
YES N0 YES NO Shift Technical Advisors (STA)
' 3 e
1 2
2 Mike Teply
- I Wally Beck 1
' l John Bjorseth
~
biorgos Anagnostopoulos Paul Collingsworth Dave Mankin i
l
~l Rx. & Plant Perf. Engineers i
1 1
bary Van Middlesworth j
Donald F. Vest M
Nicholas brown N
Francis L. Brush 3
i 1
4 Mechanical Maintenance 4
James P. Goersch William E. $cely Donald L. 5thott l l James M. Meyerhoff I
Ronald D. Shields Daniel L. Coghlan James Becker David Mcbill j'
Dav id A. Pladsen Duane Long ( Apprentice) e l '
Stanley Jacobson (Apprentice)
I C. Kress (Apprentice)
(i R. Comreid (Apprentice) 7
+
i Electricians f
1
~2 Paul Abernathy James Scott 8
Harold Rodenberg Norman Thiessen D
d' l
Communicator Name Date l
Notification List No. 3 Page 3 of 4 NO REQ.'
TOTAL NOTIFICATION PARTY CALLED 110ME OFFICE IN NO.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES fH)
YES NO Instrument Technicians 1
1 g
Paul J. Maternowski l
Larry Gosnell
~
pg Michael Long W
Tony L. Olsen ll Allen R.5chmidt i
g Ernest C. Zaugg 1
R Lowell J. Russell i-
[
hob R. Stout i
l Daniel L. Thies i l
{
William A. McVicker
~~7 1-8 R. Craig Hunt (Apprentice) 4 L Electricial Design
(
1 Clare bleau tTike chandler F
Sam Ray Taj Mahammed j'
Giorgos Anagnostopoulous F
~
]
Lila brover I P Mechanical Design 1
Bill Ellis K
bill Scholberg 1
Bill Rackle
[
Jim Lochrlein i
i Ken Peveler r
Linus brouhard detf Helson bene Havlic John Johnson
! i Paul Collingsworth i
l 1
Dave Mankin Mike leply Monty Hintz i h
' Communicator Name Date l
e
Notification List rio. 3 Page 4 of 4
PARTY CALLED HOME OFFICE IN TOTAL NOTIFICATI0ii fl0 REQ.
NO.
INITIAL RECALL TIME EMERGENCY TITLE /ftAME PAGER NO.
fl PHONE EXTENSION e 30 MIN.
REQ.
YES NO YES NO
!1 1
Mechanical Superv, ors' s
(P) Fichara D. RockliiT1 i
(1) George R. Fulford
( 'e 3
s Electricial Maintenance Supervisors [
1 (P) Jerome L. Sweiger g
(1) Larry L. Voss 5
4 I f, l
Warehouse Personnel fej (P) Robert LaPointe i
(1) Russell L. Brown
/ 3 I
4 r (2) Lldon M. Marting gj Security Supervisor Q
(P) James Sparano 3
(1) Michael Sparks
! I N
E
_._E--
Communicator Name Date l
I w
4 s
O JZ ZJ O<
-U WwM
< g LAJ U.
L&.
J O
.- e4 Z b
O&
(
Z-l ZM
- L&J
>=
i I
f J
<C
- Cr e-- O uJ M
OZW W
4-O M
0' Cr a
en uJ C
M CC a
Z E e o.-e O
O Z
M N
Z ausuumu N E h umu w -
m o
o-*
O LaJ M U
UZ L
- LAJ 3
LL. >==
0 LA ><
m O LAJ GJ CE l
00
\\
C
-I O
W e
LA.J Z M
'E O e
OO t
I CL EEEE as k
O O
-u_
Z n
W LLJ E
uJ M
C3 C
M
=
CC w
CL L
L QJ CJ QJ QJ C
C e
e-Ch CD LLJ C
C W
W g
Z CD C
Ch N
C O
C
=
LAJ e-M O
@ M e-J M
CL+2 +J O
C L
W
+J L
O C
O QJ C
o-*
0 0 0
0 N
0 m
~
C N
L&J >==
b 0
1 D
L
+.3
+.a.
3 0
+J CJ G
L O +2 L
O
., J GJ
% J CL 'O QJ L
A
+J 00
_J >=
CL L
.AJ 3
3 4
4 4 I UZ M
QJ t
t M
O O V
+J QJ LaJ 3
'O V C
C
+J % E 6
A 4
E
>= LD
+J
~
~
O O
+J C R
ed
>-- Cr 4-C CB M E
=
cn C x r X
cn Z
MLJ c-I 3
C A
E C
U U
L r-9 3
L et Z r
O O
O 4
4 4
3 0
M CL uJ
<r 7 m X M
Q 3
7
% :S a O
sa n3
.U e
C 3
u)
EG E
O U
t-- l e
o b..
Additional Resources Page 2 of 5 NO REQ.
TOTAL NOTIFICATION t
- PARTY CALLED HOME OFFICE Ifl NO.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES N0 YESlNO O
2 Operators 3
John Adams
!,[
kichard L. Anderson i ll IB Kussell Becker f
1 El Wayne L. Bentley I i Ii Lonnie D. Gross l l F
Robert hovey F !
Brian Hupke 5
i E
Duane R. Johnson 1
E Kevin J. Morgan E
5 Wayne kender Keith Reule i !
E Steve keynolds l
E Stephen Rohr I
E I
E doe Ruth Frank Sauser El David M. Schussler 1
51 El Allen J. Steen leryl Subbert i
T 51 Il i
Kenneth Thomas l
El
',eorge R. Ihullen E
Frank S. VanEtten Benjamin Westcot 5
1 B
inomas A. Zimmerman E ~ _.
E I
i Paul bullivan E i E
I y
g Communicator Name Ate b
t o
5 9
- maa
t Additional Resources Page 3 of 5 NO REQ.'
TOTAL WOTIFICATION PARTY CALLED HOME OFFICE IN NO.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PH0 tie EXTENSI0ri 60 MIN.
REQ.
YES NO YES N0
' i
~
Training Group r
Robert Anderson i
Larry Morey g
Bob lhorson N
Dave Miller l
N Ed Harms 3
Alan Dalton l
3 Don Hickman
[
g i
Paul Roy
}
g l
Ea lhomas 3
3 John Connon 3
_ g F
Health Physics Support Robert Decker g
Parley Smith g'
3 Floyd Dickson
((
t E
Lhris Cummin 3,,
3 Alfred Ward Western
][33 3
_ ~
5 Communicator Name Date i
0
Additional Resource Page 4 of 5 NO REQ TOTAL NOTIFICATION PARTY CALLED 110ME OFFICE IN NO.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN RE0 YES NO YES NO Security Guard Lieutenant h f-Rollie Cantrell y
Q
)lJ Daniel Kelley iP[
g Darrell Kickels F
g
~
Richard $anders
{E g
Larry Wille f
3 5,
P Security Personnel i
lioward D. Brown lP I III Diane Engelhardt
- I f I Frederick Hadenfeldt Brian L. Hall
! 1 l
Larry Joens 5l l Ron Larsen Larry W. Mcdonald g
kobert Moriarity 1
Donald Reiner 7
lom 5tepanek i
l Melvin lheisen l
Robert Wetherall I
R. Uthoff 7
M. Meeks E
K. Moore f
R. Warren f
9 F. Stein F
i U. Roggentein i
t I'
p
~
Utility Doreen Kelly No phone
~ ~...
t x
Communicator Name Date t
e
I il j
L0 NLN OA I C TES ARE C
Y I
FL AO I
TI N OT i
I' t
NS 5
I E Y
fo 5
e g
L a
A
.Q P
T0E Of R 4
T Q
N E
I RNM I
0 0
i 3
f
',3' 4r A[l i
N l
1 l
p 1
1 i l
1 i
O p'1i l
li' l
l I
l f
e ES c
CN r
I E u
FT o
FX s
OE e
R l
~
ano E
EN i
t MO OH i
d HP d
h e
7-1 I
l
))
N gLH I l ]1
'3' l
[
[C I
i i
' t
,R p3Wy3yi i '
a D
O N
R EGA P
nos t
E r
M n
A e
r e
N k
y e
h b
yl
/
c n
e g
l e e e
l a
t n
t u
k i
E n
a c
G l
n t
L o r g
z f
o i
w g
a b
r n k
y n n e u T
r C n
t l
k n
e o o e e o a o
n r t
y r e a DI t
c i
l, c N E
e s e t
a z r M c n e s
m t w
l ET n M t
l a a t
S L
o u
F t
t n
i n
e G t
F o e H d
e c v
r e x e u s
l r
s o n
e LY C
. H e
yi n a a a K u R S
n L M L e a a a s
o l
h a F AC A
w L
a e
C W
t c V A
M a o t
5 r n a H i
CN y
E t
t A
d s
a i
c B
t l
F a H c o e a e e n m
a d n J o
a i
e y
y h
a i
H i
s F
n d f
e i
r e
YG l
i i
f c
r yl r c a p
a d r
n l
n i
r N
l e k c
a n e h
TR RE a b r
u n n m e c
v a
n e
r u e n t
e l
n t
n n u o a e a AM u o a
r o e a o
e a t
a l
a a
h a
i t
i i
a n o a h
l a h r
PE QR M b D
D J
J T
D S
L C
M P
S N
R S
L L
P A
B P
R E
R S
o tac inu m
E m
M o
I C
T l
TO:
DISTRIBUTION MANUAL Emergency Plan Implementing
/
\\
Procedures V
Date June 1, 1982 Please remove:
(1) Index and/or Revision Control Page(s) and (2) Procedure or Procedure Page(s) listed below and insert the revised material.
INSTRUCTIONS REMOVE INSERT
__ Rev.
Date Rev.
Date Revision Control Sheet 5
6 6/1/82 Index 3
3/2/82 4
6/1/82 1.1 0
5/11/81 1
3/1/82 3.1 1
10/19/81 2
3/1/82 3.2 2
10/19/81 3
3/1/82 4.1 (Revision 1 never distributed) 0 5/11/81 2
5/13/82 4.5 0
5/13/82 6.3 0
5/11/81 1
3/1/82 6.4 1
1/18/82 2
3/3/82 gsg Subsequent to making the above changes, sign and date the notice below, detach it at the bottom line and return it to the addressee.
f,/qhgQ NOTICE OF RECEIPT OF REVISION NOTIFICATION T0: DAEC SUPPORT SERVICES P.O. Box 351, Cedar Rapids, Iowa 52406 This acknowledges receipt of revision notification to the Procedure (s)
EPIP 1.1, 3.1, 3.2, 4.1, 4.5, 6.3, 6.4
,O
(,)
dated 6/1/82 and updating of Procedure (s) in accordance with the notification instructions.
Signature:
Date:
EMERGENCY PLAN IMPLEMENTING PROCEDURES REVISION CONTROL SHEET O
Revision No.
6 Revision Date__6-1-82 Page/ Proc Date Rev.
Page/ Proc Date Rev.
Page/ Proc Date Rev.
INDEX 6-1-82 4-1.1 5/11/81 0
1.2 10/12/81 1
2.1 1/15/82 2
2.2 2/1/82 3
2.3 12/2/81 0
3.1 3/1/82 2
3.2 3/1/82 3
3.3a 10/21/81 1
3.3b 5/13/81 0
v 4.1 5/13/82 2
4.2 5/11/81 0
4.3 10/19/81 1
4.4 5/11/81 0
i 4.5 5/13/82 0
1 5.1 11/24/81 1
5.2 11/24/81 1
6.1 5/11/81 0
6.2 5/11/81 0
6.3 3/1/82 1
6.4 3/3/82 2
O
., ~...
,,., _,.., _ _ _ _. - ~... _ _ _,. _ _ _. _ _ -. _ _ _ _ _,
EMERGENCY PLAN IMPLEMENTING PROCEDURES
/~
I INDEX Document No.
Title 1.1 Determination of the Emergency Action Level 1.2 Notification of the Emergency Response Organization and Offsite Agencies 2.1 Activation and Operation of the Operational Support Center 2.2 Activation and Operation of the Technical Support Center 2.3 Emergency Coordinator Duties 3.1 Onsite Radiological Monitoring.
3.2 Offsite Radiological Monitoring 3.3a Initial Dose Projections 3.3b Follow-up Dose Projections 4.1 Site Evacuation 4.2 First Aid, Decontamination and Medical Support 4.3 Rescue and Emergency Repair Work 4.4 Protective Action Guides and Exposure Limits 4.5 Administration of Potassium Iodide (KI) Organization Deactivation of the Emergency Response 5.1 5.2 Recovery and Re-entry 6.1 Maintenance of the EPIPs 6.2 Training _and Drills 6.3 Maintenance of Emergency Facilities Equipmen; and Supplies 1
6.4 Emergency Preparedness Communications Testing Rev. 4 6-1-82
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 1 of 9 DETERMINATION OF THE Revision 1 EMERGENCY ACTION LEVEL Date - 3/1/82 1.0 PURPOSE 1.1 This procedure pro.vides guidelines for determining.and revising an
~
Emergency Action Level (EAL) and provides aids to relate the required emergency response to plant conditions.
2.0 APPLICABILITY 2.1 This procedure shall be used by the Shift Supervising Engineer and the Emergency Coordinator for radiological emergencies at DAEC, as defined herein for each EAL. Other events not included in these EALs may be classified as an Unusual Event, Alert, or Site Area Emergency at the discretion of the Emergency Coordinato; or the Shift Supervising Engineer.
3.0 RESPONSIBILITIES 3.1 Shift Supervising Engineer O
3.1.1 Evaluate plant conditions to determine if an EAL has been reached.
3.1.2 Ensure that DAEC and corporate personnel and offsite support agencies are notified upon determination of an EAL.
3.1.3 Initiate actions to return the plant to a safe and stable condition.
3.2 Emergency Coordinator 3.2.1 Review the declared EAL and revise as required.
i 3.2.2 Ensure activation of the Emergency Response Organization as required.
3.2.3 Ensure that communications are established with offsite j
support agencies until relieved of this function by the E0F.
j 3.2.4 Deactivate the Emergency Response Organization when authorized by the Emergency Response and Recovery l
Director.
[
3.3 Responsibilities for other functions required at each EAL are described in more detain in other EPIPs and CPIPs.
l L
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 2 of 9 DETERMINATION OF THE Revision 1 d
EMERGENCY ACTION LEVEL Date - 3/1/82 4.0 INSTRUCTIONS 4.1 Emergency conditions are classified in an ascending order of severity as follows:
4.1.1 NOTIFICATION OF UNUSUAL EVENT (Condition Classification A)
This class of emergency conditions includes the least severe events requiring offsite notification. This emergency classification shall be declared whenever unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.
In general, no releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
4.1.2 ALERT (Condition Classification B) b The Alert emergency condition is the second class in increasing order of severity. This emergency classification shall be declared whenever' events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.
Limited releases of radioactivity may occur.
4.1.3 SITE EMERGENCY (Condition Classification C)
The Site Emergency condition is the third emergency classification in increasing order of severity. This classification shall be delared whenever events are in progress or have occurred which involve actual or likely major f ailures of those plant functions required for protection of the public. -Some significant releases of radioactivity are likely.
4.1.4 GENERAL EMERGENCY (Condition Classification 0)
The General Emergency condition is the most severe emergency classification and requires immediate notification of the public. This classification shall be declared whenever events are in progress or have occurred which involve actual or imminent, substantial, core degradation or melting with potential for loss of p
containment integrity.
Significant releases of Q
radioactivity are likely.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 -
Page 3 ~ of 9
(~
DETERMINATION OF THE Revision 1 L'}'
EMERGENCY ACTION LEVEL Date - 3/1/h2 i
t 4.2 When a suspected emergency condition occurs, the Shift Supervising.
Engineer shall make the initial analysis and determination of' the EAL referrring to Attachment 1, " Emergency Action Level" and, " Emergency Action Level Classification Guidelines".
The Emergency Coordinator, at'his' discretion, shall review the- +
determination for concurrence or revision, either.when notified of the condition, or upon arrival at the site.
NOTE i
5 The instrumentation listed under "Possible Indications" in
' may serve.as possible indicators of an EAL;
.r!,
however, the indicated list should not be considered as all a
inclusive.
4.2.1 provides a listing of[ the' Emergency Action Levels and is formatted to show increasing degrees of severity.
\\
4.2.2 Attachment 2, EAL Guidelines, are. arranged in an index' format according to type of> eve'nt; plant,condjtion, possible indications and Emergency Action Level codes.
4.2.3 To determine an EAL, the Shift Supervising Engineer shall:
Categorize the general type of event referring t,o
- a. for quick reference, as appropriate.
~
b.
Using Attachment 2, identify instrumentation or indicators to be used for. interpretation of pla'nt=
l conditions.
~
,,s c.
Identify the specific plant condition NOTE l
l Contact with the Operations Supervisor or his designee should be accomrel 7.ed if a question exists as to proper classification of the plant condition.
~ '.
i d.
Declare the EAL'.
4.3 The Emergency Response Organization shall'be activated to the,e n
extent required for the declared EAL, in accordince with EPIP 1.2.,
~
(')
" Notification of the Emergency Response Organization and Offsite N Agencies." As a minimum, the follov:ing actions shall be taken:, {i j
l t
f.
1,/f '
E
,y l'
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 4 of 9 DETERMINATION OF THE Revision 1
^ J-EMERGENCY ACTION LEVEL Date - 3/1/82 4.3.1 The Shif t Supervising Engineer shall initiate the notification process.
4.3.2 The Shift Supervising Engineer shall ensure timely notification of offsite authorities upon classification of the EAL.
In accordance with 10 CFR 50 Appendix E, paragraph 30, this notification should be conducted within 15 minutes.
4.3.3 Upon au'.horization of the Shift Supervising Engineer, the Secondary Alarm Station Operator shall notify offsite support agencies as specified in EPIP 1.2.
4.3.4 The Emergency Coordinator shall ensure that the Emergency Response Organization and emergency facilities are activated to the extent required by the EAL.
4.4 Reclassification of the EAL shall be performed by the Emergency Coordinator, with the concurrence of the Emergency Response and Recovery Director, as required.
4.4.1 The event may be reclassified to a more severe or less severe level, using the EAL Guidelines. Factors which should be included in the evaluation include actual or l
potential conditions such as the following:
a.
Chain of events b.
Plant status c.
Operability of equipment d.
Meteorological conditions c.?
e.
Man-caused or natural events
(
f.
Status of control over radiological releases.
4.4.2 The Emergency Coordinator should consult with the following personnel during such evaluations:
a.
Site Radiation Protection Coordinator I
b.
Control Room Coordinator c.
Technical Support Center (TSC) Supervisor y
d.
Emergency Response and Recovery Director l
iM
/
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1-Page 5 of 9 DETERMINATION OF THE Revision 1 C
EMERGENCY ACTION LEVEL Date - 3/1/82 4.4.3 The Emergency Coordinator shall ensure that offsite notification of reclassification to a more severe condition is conducted within 15 minutes, in accnrdance with EPIP 1.2.
NOTE i
If the EOF has been activated, this responsibility shall be assumed by the Emergency Response and Recovery Director, a.
When'the event is classified as more severe, contact shall be made with each organization or individual required by the new EAL.
b.
When the event is classified as less severe, contact shall be made with each organization or individual required by the former EAL.
c.
When the event, EAL, and Emergency Response Organization are-deactivated, contact shall be made with each organization or individual required by the former EAL.
4.4.4 Reclassification of an event shall be documented in the Shift Supervising Engineer's' log and the TSC Supervisor's log. The Emergency Operations Facility, if in' operation, l
shall also. document the reclassification, in accordance with CPIP 1.3, " Emergency Operations Facility Activation."
The following types of information should be recorded:
l
- a..Date of reclassification b.
Time of reclassification c.
New EAL designation d.
Brief summary of plant status and conditions for reclassification.
4.4.5 Notifications shall be documented as required by EPIP 1.2.
my EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 6 of 9 DETERMINATION OF THE Revision 1 EMERGENCY ACTION LEVEL Date - 3/1/8?
4.5 Natural or man-caused events shall be considered for determination or reclassification of EALs.
4.5.1 The EAL Guidelines include specific types of events which may require declaration of or revision to an EAL. Such events include:
a.
Weather conditions such as storms, tornadoes, high winds, blizzards, etc.
b.
Geological or seismic events such as earthquakes, tremors, etc.
c.
Non-radiological accidents, such as fires, airplane crashes, explosions, etc.
d.
Attacks or assaults
'O-4.5.2 Other events not included in these EAls may be classified as an Unusual Event, Alert or Site Area Emergency at the discretion of the Chief Engineer'or the Shift Supervising Engineer.
a.
The primary consideration for activation shall be to protect the health and safety of site personnel and the public.
b.
Determination of an EAL or activation of the Emergency Response Organization for such emergencies shall be noted in the Shift Supervising Engineer's log.
4. 6~
Downgrading the Emergency Action Level.
4.6.1 The EAls may be downgraded in conjunction with EPIP 5.1,
" Deactivation of the Emergency Response Organization" by the Emergency Response and Recovery Director when the s
conditions which constitute the EAls have been brought under control and no longer pose a threat to the health and safety of plant personnel or the public. The emergency condition shall be considered under control when the plant is in a stable state, necessary plant operating equipment is functioning properly and there is no potential for uncontrolled radiological releases.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 7 of 9 DETERMINATION OF THE Revision 1 O
EMERGENCY ACTION LEVEL Date - 3/1/82
5.0 REFERENCES
1.
Duane Arnold Energy Center Emergency Plan 2.
NUREG 0654, Rev. 1.
6.0 ATTACHMENTS 1.
Emergency Action Level Classification Guidelines 2.
Emergency Action Levels O
Reviewed by:
( /[ j' M Date v[u [p-L.
Operations Comittee Chairman l
l i
Approved by:
<?y h M.
Date FX/c e.
Operations Supervisor l
6 5-27-SL Approved by:
Date Chief Engineer l
em
! L/
4
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 8 of 9 DETERMINATION OF THE Revision i V
EMERGENCY ACTION LEVEL Date - 3/1/82
-ATTACHMENT 1 EMERGENCY ACTION LEVELS See Attached Sheets i
O i
1 1.
i I
O i
l
O O
O ATTAOf G T 1 DGGENCY /CTION PAE 1 of 13 LEVEL CODITION LNJSUAL SITE E?ERAL
-l QASSIFICATION EVENT (A)
ALERT (B)
DEGEPCY (C)
DGGENCY (D)
- 1. Reactor Coolant Systen
- 1. Reactor Coolant Systen - 1.LOCA greater than
- 1.LOCA, with failure of leak rate greater than lei rate greater than maketo capacity.
ECCS to perfonn, leading either the unidentified.
50 gpm but within melt in minutes or to cnre chgradation or (5 gpn) or contined Tech maketo capacity; RPV Spec limits (25 gpm),
level being maintained.
hours. Loss of but less than 50 gpm.
containnent integrity may be imninent.
2.LOCA, containmnt 4
perfonnance is msuccessful affecting longer tenn success of the ECCS. Could lead to' l
cona degradation or melt:
in several hours without-u containnent boundary.
l
Cr V
bx i-ATTAO K NT 1 EKRGEFCY ACTION I
PAGE 2 of 13 LEVEL C0f0ITION lHISUAL SITE GENERAL l
5 CLASSIFICATION EVENT (A)
ALERT (B)
ENERGENCY (C)
EKRGENCY (D) l
_?
Main Stean Line Break
- 2. Main stean line treak
- 2. Main Stean line treak l
0;tside Primary with HilV malfunction without isolation.
1 Contairment causing leakage.
i I
Environmntal Releases
- 2. Airborne effluents
' 3. Airborne effluents (Relatedto10CFR20) greater than Technical greater than 10 times Specification limits as Technical Specification reported by thalth instantaneous limits Physics.
(aninstantaneousrate i
s ich, if continued over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, would result in about 1 mr at the Site Boundary under average neteorological conditions)asreported j
by thalth Physics.
- 3. Liquid Discharge
- 4. Liquid Discharge Effluents y eater than Effluents greater than 10CFR20 Appendix B 10 times'10CFR20 limits m reported by Appendix B limits as Health Physics.
reported by Health Physics.
ATTAOfENT 1 EK RGEfCY ACTION PAGE 3 of 13 LEVEL C00lTIO4 ttU5UAL SITE GEPERAL CLASSIFICATION EVENT (A)
ALERT (B)
EKRGEPCY (C)
B{RGEPCY (D)
Environontal Releases
- 3.[bse rates re projected 3. Dose rates greater than (Related to EPA PAGs) at the site boundary 1 Rem /tr W1 ole body or 5 Rem /hr thyroid re under a1 verse meteorology greate than projectai (basai on other plant paramters),l 50 mr/hr W1 ole body or 250 nr/hr thyroid for at the site boundary 1/2 hour.
under rtual meteorological
- l. conditions.
or Containmnt Radiation or Ptnitor >
Containmnt Radiation or N nitor >
These dose rates are l
or measured in the environs.
These dose rates are measured in the or environs.
EPA PAC 6 are projected to be exceeded outside the site boundary.
I Ii
(
l I
l l
o o
o ATTACifENT 1 EK RGENCY ACTION PAGE 4 of 13 LEVEL.
C0f0ITION lNRIAL SITE U
E ERAL EVENT (A)
ALERT (B)
EERGENCY (C)
ENERGENCY (D) 0.ASSIFICATION s
1 Environrental Releases
- 4. Dose Rates re projected i
(Related to EPA PAGs) at the site boundary (Continued) under aiverse l
neteorology greater than, j
500 nr/hr sole body or l
2500 nr/tr thyroid for 2l j
minutes.
l l
E I
l l
These dose rates re neasured in the environs' l
i i
E i
EPAPAGsareprojected to be exceeded outside the site boundary.
i
.4.0ther plant conditions exist, from d atever I
source, that make release of large anounts of radioactivity in a-short tine period possible.
l
ATTAOtelT 1 EMRGENCY ACTION PAGE 5 of 13 LEVEL C00lTION LHJSt%L SITE ENERAL CLASSIFICATION EVENT (A)
ALERT (B)
EKRGENCY (C)
BERGEfCY (D)
Degraded Fuel Integrity; 4. Reactor crolant rtivity 5. Reactor coolant greater than Technical activity greater than I
l Specificatim limits of 3)0 uci/gn of cbse 1.2 uci/ gn of dose equivalent 1-131.
egJivalent 1-131 which requires shutdown.
- 5. Air Ejector monitor
. 6. Air Ejector nonitor acitivity greater tahn activity greater than '
500,000uci/secoran 5ci/seccorresponding, increase of 100,000 to 16-isotopes decayx1 uci/sec within a 30 g
30 minutes.
minute tima period.
l i
- 5. Degraded core with possible loss of coolableryometry.
Loss of 2 of 3 Fission
- 5. Loss of 2 of the Pruduct Barriers following 3 fission product barrien with potential loss of 3rd barrier:
RCS Integrity - see C-1 Clad Failure - see B-5 Containnent Integrity
- see A-12
O O
O ATTACitENT 1 EKRGEfCY ACTION PAGE 6 of'13 LEVEL C0f0ITION LHJSUAL SITE GENERAL CLASSIFICATION EVENT (A)
ALERT (B)
EERGEtCY (C)
EKRGEfCY (D) _
(t0TEC)
Systen/ Equipment
- 6. Stuck open safety or e
1 Failure or Malfunction miief valve.
7.Any ECCS actuation that results in water being discharged to the Reactor Vessel that is either unexpected or is mquired to recover and maintain RPV water level.
1
- 8. Loss of fire suppression function requiring shutdown by Technical Specifications.
7.Cmplete loss of any 6.Conplete loss of any 6.Shutcbwn occurs but function needed for functim needed for requisite decay heat plant cold shutdom.
plant hot shutdown.
rerovalsystem(e.g.,
RFR) or non-safety system heat ruroval means am mndered unavailable. Com degradation or nelt occur in dout ten hours with subsequent contalment failure.
- 9. Turbine rotating cmpon-8. Turbine failure causing' ent failure causing casing penetration.
rapid plant shutdown.
O 0;
O 1
ATTADfENT 1 DEGEfCY ACTION PAGE 7 of 13 LEVEL i
CODITIai trUStPL SITE ENERAL CLASSIFICATION EVENT (A)
ALERT (B)
EMERGENCY (C)
DERGENCY (D) l Systen/Equipmnt
- 10. Loss of FPCI and either Failure or Malfunction ADS or RCIC (LossofSafety Systen or Feature Loss of ADS logic or requiring shutdown in loss of nore than 1 ADS accordance with valve Technical Specifications)
Total loss of any of l
the following Core Spray i
I LPCI
)
Stantby Gas Treatment loss of Contairment Spray capability l
l i
Loss of both H? and 02-Analyzers 4
1 Loss of both Emergency Diesel Generators 11.Any cmbination of Safety System failures that require shutdom i
by Technical i
Specifications.
I a
ATTAOI M 1 EK RGENCY ACTION PAGE 8 of 13 LEVEL C00lTIOl l#USIAL SITE GEERAL CLASSIFICATION EVENT (A)
ALERT (B)
EKRG90Y (C)
EKRGEICY (D)
Systen/Equipmnt
- 12. Loss of primary Failure or Malfunctions contaiment integrity (Loss of Containmnt Integrity)
- 13. Loss of secondary containmnt integrity l
Systen/Equipent Failure or Malfunction.
- 14. Loss of off-site power
- 9. Tota! Loss of all AC
- 7. Total loss of AC Power; Power restoration mt possible (Loss of Power) within 15 minutes
. 15. toss of on-site power capability
- 10. Total loss of 125v DC.8. Total loss of 125 v DC Power; Power; restoration mt possible within 15 minutes Systen/ Equipment
, 11. Failure of RPS to
- 9. Transient Requiring
- 7. Transient (e.g.,lossof Failure or Malfunction initiate ani cmplete Operation of Shutdom offsitepower)plus (RPSfailure) a reactor shutdown.
Systens with Failure to failure of requisite Scran(continuedpower core shutdown systens generation, but no core (e.g., scran or stancby i danage imnediately liquid control systen).
evident).
Could lead to core nelt in several hours with contaiment failure likely. More severe consequences if ptmp trip does not function.
l 4
)
t
O O
O ATTA0t{NT 1 EERGDCY ACTION PAGE 9 of 13 LEVEL 00lOITIO1 UNUSUAL SITE E ERAL CLASSIFICATION EVENT (A)
ALERT (B)
EKRGENCY (C)
EERGENCY (D)
Natural Occurrences
. 16. Earthquake of
. 12. Earthquake creater l10. Earthquake creater than sufficient magnitude to than OBE.
DBE with plant not in
- actuate the Seismic cold shutdown.
ftnitoring Systen.
- 17. Cedar River level
- 13. Cedar River level
- 11. Cedar River level
- greater than 753'.
greater than 757'.
greater than 767' or loss of flood protcction for safety l related structures with plant not in cold l
shutdown.
- 18. Cedar River flow less
- 14. Cedar River flow less ' 12. Cedar River flow less than 200 CFS.
than 50 CFS.
than 13 CFS with plant mt in cold shutdown.
- 13. Winds greater than 100 '
nph with plant not in cold shutdown.
- 19. Tornado on site
- 15. Tornado strikes
- 14. Tornado sich danar,es facility ca; sing safety related -
danage.
structures and conpromises the func-tions of safety systems i
I I
l
i 1'
l O1 0
1
)
T D
0L
(
/E V
Y YE LC CL At RE D
EG G
NR R
EK K
E E
l
,i n
I d
d hd k
o esl cet.
f ca ni i t nn o
aeyit ht eo carc i aaw l l rt i
)
il u
Wl l o yea aetd C
r1 et n e pd tbimeamo rl c f
n oWrci er t
(
u t
h u nat ehs c
Y ht yrt i yt h ei it t
sct t sti s mirW anl C
aaesm new d ac o
aw E?
TE r pf of d
el st sl o I G cnart asl l f oa ePd l
t est
.t SR i son nseo t
an o
rc ornrsu u
K esml w isu roiaet mh f
e po set n t
cies E
al rige d
ogci ncst ctl iimtht cs l au oienasbd rs st u pnrt cxsa nomlo yih xat noal f A. m d s w s E.d s m U. t gpocpc 5
6 7
1 1
1 l
h e.
cg f
h ia o
i n c
da ye i
ri d
rl s
oW e
tb n
3 y
t yt na o
i t n e ner 11
)
htt B
sci sia nhi O Ef
(
aal nl l d at v o
rpi oip,
lel n
O T
cnr c
f oe 0
R nage l
t i
t 1 E
t f
of n orny D
L f e i
i i roit AE A
al se sstt t
- i TG rieg oeca ncsl ser oiei TA cssa l
AP rsun puf e cxsc iiaa xaf p noaa A. m c d E. cao U. t gf 6
7 8
1 1
1
+!
e c
y t
i t
i x
i s
o n
t l
e' o
s ic f
t ae t
os
)
fft n
a LA a
e e
eg i
P(
rrs n
t sae ce l
i ST rvn i
s el t N ioo a
n ib E
a r
on ma i
i l V yh e
o m
E l t s d
ri aia os ea uvr n
o tl sic rl if ut ia a p s
ncr r
ex nr U.a o T.
N. e O. o 0
1 2
3 2
2 2
2 de tc e
j 10 m
I P
1 T
0A r
I C so TI d
l F rd 0I ae S
zc 0S an CA He L
i C
rr ee O
hp t x OE i
j
{!lI, 1i j,
O O
O ATTAOMNT 1 DERGDCY ACTION PAGE 11 of 13 LEVEL C00!TIG1 tfUSlRL SITE ENERAL CLASSIFICATION
-EVENT (A)
ALERT (B)
DERGDCY (C)
EKRGENCY (D) l Release or Loss of
. 19.Any mcontrolled Control of Radioactive
( ~ increase in radiation '
Materials within the levels or airborne contanination levels {
Plant I
greater than 1000 l
tim 2s normal.
- 20. Fuel handling accident 18. Major.danage to spent that results in fuel fuel in the Reactor danage with the Building.'(Secondary release of. radio-Containnent).
activity to the.
Reactor Building.
'(Secondary Contain-i ment)
' 19. Uncontrolled decrease in Fuel Pool water.
level belar fuel level.
_J
4 ATTA0t 01T 1 EK RGEfCY ACTION PAGE 12 of 13 LEVEL i
C00lTIQ1 IJUSUAL SITE GENERAL QASSIFICATIQ1 EVENT (A)
ALERT (B)
EKRGEPCY (C)
EKRGEPCY (D)
Events Affecting
- 24. Indications or alans - 21. Loss of all safety Operational Control on process or effluent relatal alann and
, 20. Loss of all safety related alann and parameters rot.
annuncation capabil-annuncation capability functional in the ity; restoratial not coincident with plant Control Room which possible with 15 transient.
require plant shutdown minutes.
25.Significant loss of assessment or comunications l
capability.
. 26.0ther plant conditions ' 22.0ther plant conditions 21.0ther plant conditions exist that warrant exist that warrant exist that warrant increased awareness or precautionary activation of entrgency require plant shutdown activation of TSC and centers and nonitoring under Technical placing EOF and other teams or a Specifications or key mergency precautionary involve other than personnel m standby.
notification to the.
nonnal controlled public ner the site.
I shutdown.
I Control Roan
- 23. Evacuation of the
- 22. Evacuation of the liabitability Control Roon required Control Roan required for any reason.
for any mason.
Shutdom outside Shutdom outside Control Roan Control Roan rot
. initiated, inplanented within 15 minutes.
1
/'
[)]
()
% g
(
C/
ATTAOfC61 DERCBCY ACTION PAE 13 of 13 EVEL M DITION ifUStAL SITE ENERAL CLASSIFICATION EVENT (A)
ALERT (B)
DERGEfCY (C)
DERGEfCY (D) 1 Situations Requiring
- 27. Transportation of Off-Site Assistance contaninated injured individual to the lospital
- 28. Security threat 24.Confinmd on-going 23.Imninent loss of
, 8. Loss of #1ysical attetpted sabotage, or Security cotpronise.
physical control of the control of the plant unauthorized forceable plant.
entry.
- 29. Fire within the
- 25. Fire not extinguished 24.Fim caipronising the secured area that in 10 minutes in an functions of safety cannot be extinguished area that could affect system within 10 minutes by safety mlated the Fire Brigade wpipmnt j
1 1
1 i
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 9 of 9 DETERMINATION OF THE Revision 1 EMERGENCY ACTION LEVEL Date - 3/1/82 ATTACHMENT 2 EMERGENCY ACTION LEVEL CLASSIFICATION GUIDELINES See Attached Sheets O
O
O O
O EPIP 1.1 I
ATTADtENT 2 EK RGENCY ACTION LEVEL.
j
. PAGE 1 of 35 0.ASSIFICATION GJIDELIES 1
1 I
I I
- llJUSIE, i
' tbte: Tha instruaentatim listel in l
I l
this colum my serve as a possible j
SITE GENERAL indication, but they am not necessarily EVENT ALERT,BERGEfCY DERGEfCY EVENT TYPE PLANT C0f0!TIONS sufficient cause to detennine an EAL.
i LOCA Reactor Coolant Systen leak rate Stop PuTp times m IC21 resulting in one or Al l
greater than either the unidentified mm of the following alants on IQM 1
i t
(5 gun) or carbined Tech Spec limits "Drpell Floor Drain Smp hi Leak" f
(25 gpn), but less than 50 gpn.
"Drycil Equipnent Drain Stop hi Leak" and/or One or nom of the folloxing alsns on 10(M l
l f
"Drywell Floor Drain Stop hi hi level" "Drywell Equipnent Drain Smp hi hi level" I
"Drywell Equiptent Drain Stop hi Terp"
.l and l
l Flow rate calculation %n FIQ 3707 on 1C19 vs:
s tine is greater than 5 gpn or The ficw rate calculat'iiin from FIQ 3708 on I
I 1C19 vs tine added to flow rate calculation 1
fmn FIQ 3707 on IC19 is greater than 25 gpn. '
I i
Other possible indications 1
Drywell Terperatum increase as indicated on.
i TR 4383 A, B, & C on IC29 -
Drywell Cooler Tenperatum increase m 4
indicated on TR 5713 A & B on IC25 i
l i
t i
1
\\
I f
l l
l i
I
I f, m g'
(G
\\
t%)
EPIP 1.1 ATTADFB.T 2 DERGEtCY /CTION LEVEL.
PAE 2 of 35 CLASSIFICATIQi GJIDELINES l
?!ote: The instnrentatim listed in this colum may serve as a possible IRJSU4.
SITE GE' SAL indication, but they are not necessarily EVENT ALERT DERGEtCY DERGE CY EVEt3 TYPE PLA;6 CODITIO S sufficient cause to detennine al EAL.
l LOCA(cont.)
Rea-tor Coolant Systen lea'c rate Dry. ell Flone Drain Sam par (s aad/or Dry.vall f B1 greater than 50 gan but within Equipmnt Drain Smp pums ru' acessively and makeup capacity: RPV level being Flow Rate Calculations on the Drynell Ficor j
maintained Drain Sum cnd Drycell Equipmnt Drain sum j
indicates tctal flow in excess of 50 gan.
)
i and i
RPV level teing mainI3Tned as indicated on l
LI-4559,4560,4561,andLR-4559/4560on1C05.
[
Other Possible Indications Unexplained Drya311 pressure increase as l
indicated by:
a) " Primary Containmnt Hi/Lo Press" alann t
i 1Crfa b) Cacputer points B103 and B1CA i
cr Unexplained Contairrtent Air Tamarature increase as indicated by:
~
a) TR 4333%,B and C on IC29 i
b)TR5713AandBon1C25 6
4
,,.]
(-b
(,~),
x L
EPIP 1.1 i
ATTADIC K 2 EfRT1,'CY /CTION LEVEL PAGE 3 of 35 C' SSIFICATIOl GUIDELI!ES J
tbte: The instrwentation listed in this colton cuy serve as a possible t!UStFO SITE GEtERAL irdication, but they am not necessarily EVENT ALERT ETRGEtCY; EKRGDCY EVENT TWE PLANT UISITI0riS sufficient cause to datemine m EAL.
l
!LOCA LCCA greater than aceup capacity
- ECCS systens and other a/ailable nukeup Cl I
'(Continued)'
cepacity unable to maintain / recover RPV water level as inoicated on LI 4539,4540 on 1C05 and LI 4565, tR 4566 on IC03.
j e
Other indications to consider Increasing Depull Pressure as irdicated by; a) PR 43PA and 4335 on IC29 i
b) 1C05 alams
{
"Primry Ccntaiment hi/lo Pressure"
'j
Primary Contaiment hi Pressure Trip"
}
Increasing Drymil Tenperatures as indicated by:
a) TR4383 A, B, C on 1C29 b)TR5713A,8onIC25 e
I f
I.
I t
I I
.ev_
EPIP 1.1.
ATTAOiB J 2 DER ^EJCY ACTION IIVEL PAI 4 of 35 CLAS$1FICATIQi GJIDELINES tbte: Th3 instrurentation listed in this colum cuy serve s a possible lIUStKL SITE GE!3ALl indication, but they am not necessarily EVENT ALERT E!ERGEfCY DER 33CY' EVENT TYPE PL/M CIDITIGS sufficient cause to datent.ine m EAL.
LOCA LOCA, with failure cf ECCS to RPV level decreasing and less than -111.5" as
" 01 l
(Continued) perform. Loss of contain mnt indicated on LI-4559, 4560, 4561 and LR-integrityprojected.
4559/4560 on 1C05 ard RPV pressure drreasinfmd less than 450 psig as indicated on or RPV. level les than +F3. indicated.on.LI4565 and LR-4566 and Dryc. ell pressure projecEl to exceed 62 psig or Dry.eell tenperature pr5Iected to execd 281*F l
s irdicated by:
a) Dryaall pressure >10 psig for core than 30) minutes without Cnntairmnt Spray capability.
I b) TR-4333 A, B ard C on 1C29 c)TR-5713A,BandCon1C25 ECCS Conditions (See mxt page for explanation) 9
(d
(.)
~x n
f~
\\
j EPI? 1.1 ATTACHENT 2 DECENCY TCTIO! LEVEL PKE 5 of 35 CLASSIFICATIGJ GJ1DELItE.S T
i ibte: Th2 instrtraitatim listd in l SITE GEtSAL,
this coltml may serve as a possible UtOStkW indication, but tly are not necessarily[l EVENT ALERT llD1ERGEPCYlDERGE?C i
EVENT TWE PL/AT CCalTIGIS sufficient cause to datennine an EAL.
l t
j i
l
'LOCA LOCA, with failure' of ECCS to ECCS Conditions (Continued); perfonn. Loss of containcent HPCI (May not be operating dte to Rx press) integrityprojected(Continued)
FI 2309 indicating flow on ICO3 i
CV 2313 iniicates opc1 cn ICO3 RCIC(Mayrotbeo;cratingduetoRxpress) l
)
F12509 indicating fica on IC04 i
CV 2513 indicates open on IC04 i
ADS (May be necessary) i Following alarns on 1C03
)
" ADS Lo Water Level Confinred" i
" ADS Core Spray o-RFR Pup Running"
" ADS Dry.vall Press Signal Seald in"
" ADS Tiners Initiated" after 120 seconds
{
" ADS Relays energized" alann on IC03 with 4 relief valves o,x:ning to reduce Rx pressure to allon Core Spray /LPCI injection.
CoreSpray(RPVpressure<450psig)
FI 2110 and FI 2130 on 1C03 indicate floa CV 2118 and CV 2133 indicate open m IC03 LPCI (RPV pressure <450 psig) i FI 1971 A/B on 1C03 indicate flow CV 2002 or 1905 indicates opm on IC03 i
Il I
l
,a
-\\
p
(,!
EPIP 1.1 ('O ij ATTAGENT 2 EFSECY ACTID: LEVEL PAGE 6 of 35 CMSSIFICATI0fi GJIDEll?ES i
I tute: Tha instrumntatim listed in b
j SITE l GE5EPAL {
UfUSUAL this colu.n rray serve as a possible ALERT lEFSGEICYlEKRGENCY irdication,'but they are not necessarily EVENT EVEf6 TYPE PIRE C0fDITI0t;S sufficient cause to &tennine al EAL.
}
'LOCA
'LOCA, containmit rerfonnance is Drysall pressure projected to exceed 62 psig 02 l
(Continued) unsuccessful cr i
Drysell terpcrature protected to exceed 231*F as irdicated by:
a) Drysall pressure > 10psig for nere than 30 minutes without Containnent Spa y capability i
b) TR-4333 A,B and C on 1C29 c).TR-5713 A and B on 1C25 and RPV level decreasing ad less than -111.5" as i
ir.dicated on LI-4559, 4560, 4561 and LR-4559/4560onICC6 and l
lRPV pressure &creasinfand less than 450 psig as indicated cn aid Potential exists fc-f5ss of ECCS due to L
L l
a) Torus level dacreasing as indicated cn l
l or l
b) Torus' water tmp531.ure increasing and greater than 170*F as indicatai on B2 1
'hin Stean inhin stear, lim bre k with MSIV Group I isolaticn caused by Stean tunnel hi Line Break tralfunction causing leakage.
tsperature 0;tside or l
Containnant Turbine building hi teTperature
{
or Main Stean Line hi FloF ardlar (see next page) j l
l
(~.
,V V
V EPIP 1.1 ATTAOfftJ 2 BERGENCY ACTION LEVEL PAGE 7 of 35 CLASSIFICATI01 GJIDELIfES
- thte: Tie instninentatim Iistel in this cnlum may serve as a possible
.UfDSlML SITE GEtERAL indicaticn, but they am not necessarily EVENT ALERT EERGEtCY DERGErCY EVEf6 TYPE PLAr# C0f0ITIONS sufficient cause to datennine an EAL.
I I
Main Stean Main stean line treak with FSIV Radiation levels cb rot decrease back to mar Line Break halfunction causirg leakage.
nonnal followiry isolatim as indicated on:
Outside (Continued)
Turbine Bldg ARM's m 1Cll Contairmmt Main Stean raj levels on RR 4116 on 1C02 l (Continued)
Rx bldg stack rad nmitors RM 7613, 7614 l
l and 7615 on IC182 A, B and C i
W /or
' Stean tunnel temerature; or turbire bldg l
temeratures (b mt decrease after isolation.
PossibleIndicators i
Main Stean Line flow may still exist m FI 4408,4409,4410, or 4411 on ICOS after isolation.
1 Main Stean line break without
- Group I isolation caused by l
isolation.
I Stean Tunnel hi Tearratum alann 1C05 l
and/or l
Turbine Bldg hi Tameratum alann 1C05 C2 l
axi/or Main Steau Line hi Flow alann ICOS aid The 2 FSIV's m ore or~iiEre stean lines fail to close. Main Stean Line Flow will renain high as indicated on FI 4408, 44@, 4410 or 4411 m ICOS for affected stean lines.
Other Possible Indications and Infonnation The Stean Tunnel and/or lurbine Bldg Tameratures will renain hi following attemted
- isolation.
(see rext page)
O O
O EPIP 1.1 ATTAD M MT 2 EERGENCY ACTION LEVEL PAGE 8 of 35 CLASSIFICATICN GUIDELIES Note: The instrmentatim listed in this mlum nay serve as a possible lNJSLML SITE GEERAL indication, but they am not necessarily;EVENT ALERT EERGENCY EERGEEY EVENT TYPE PtANT (DOITIONS sufficient cause to &termine an EAL.
l Main Stean Main Stean line break without Rx vessel pressum will decrease rapidly m Line Break isolation (Continued) indicated by PI 4563,4564,4565,
-Outside PR 4563, 4564 and PR 4542 on 1005.
Contalment (Continued)
RX vessel level nay be hard to naintain; radiation levels and releases may requim a higher enenjency level.
Environnental Airborne effluents creater than As reported by Radiation Protection Department A2 I
Releases Technical Specification limits.
based (4xn the results of analyses conducted.
i (Relatedto 10CFR20)
Airborne Effluent Release Indicators Stack Rad 2 nitor -
Panel 1C10, RI 411fA,B Reactor Building Vent. Exh.
Panel 1C23 Annunciator Turbine Building Roof Vent Exh.
t local & nitor l
Airborne effluents greater than 10 As reported by Rajiation Protection Department B3 i
tines Technical Specification based ipan the msults of analyses enducted. '
instantaneous limits.
Airborne Effluent Release Indicators Stack Rad N nitor -
Panel IC10 R14116 A,B Reactor Building Vent. Exh.
Panel 1C23 Annunciator Turbine Building Roof Vent. Exh.
Local N nitor
- s
O O
O EPIP 1.1 ATTAOfENT 2 EMRGENCY N. TION LEVEL PAGE 9 of 35 CLASSIFICATI04 GJIDELIES Note: The instrtmentatim listal in l
l I
this colum may serve as a possible tMJSLML SITE GEERAL indicatico, but they are not necessarily EVENT ALERT EERGENCY E)ERGENCY EVENT TYPE PLANT 0]P0lTIONS sufficient cause to &tennire ai EAL.
Environnental Liquid Discharge Effluents create-As reported by Radiation Prutection Department A3
- Releases than 10TR20 Appendix B limits.
based toon the results of analyses conducted.
. (Relatedto 10TR20)
Licpid Effluent Release Indicators (Continued)
Licpid Process Rad Pbnitors -
Panel IC10** (Alarm HI)
Radiation Rate Meters
- 1997 - Rm Servi Water - (Hi Alarm) 3972 - Radwaste - (Hi Alarm) 4767 - Servim Water - (Hi Alarm)
Radiation Recorders
- 4820 - Reactor Building Closed Cooling Water Licpid Discharge Effluents cyeater As reported by Rr11ation Protection Departnent B4 than 10 times the 10TR20 Apperrlix based toon the results of analyses conducted.
B limits.
Licuid Effluent Release Indicato:s Ligiid Process R3d Monitors -
Panel 1C10** (Almn Hi)
Radiation Rate &ters*
l 1997 - Rm Service Water - (Hi Alars) 3972 - Rakaste - (Hi Alann) 4767 - Service Water - (Hi Alann)
Radiation Recorders
- 4820 - Reactor Building Closed Cooling Water I
- These meters and recorders indicate the existence of a possible problem. Actual cnrditions are determinsi by sanple analysis.
t e
o -
m.
m. m.
mm m Am n~
,n v
u ATTADIENT 2 DERGEtCY /CT10ri LEVEL.
PAE 10 of 35 CtASSIFICATIQi GJIDELItES tiote: Tre instrumntatim listed in j
this colum may serve as a possible pUSQL SITE GEtSAL i
indication, but they are not necessarily. EVENT ALERT EKRGETCY BERGEtCY EVEtli TYPE PLANT molTI0t6 sufficient cause to detennine an EAL.
Envirormental Dose rates are prVjected at the site' Projected cbse rates of 50 mr/hr whole body or C3 Releases boundary under adverse rmteorology 250 nr/hr thyroid as detenninst by l
(Related to greater than 50 nr/hr whole body or inplemntation of EPIP 3.3, " Dose Projections" EPAPAGs) 250 nr/hr thyroid for 1/2 hour.
or These cbse rates are neasured at the site or boundary follouing inplemntatim of EPIP 3.1,
~
Ch-Site Radiological Itnitoring"
-These dose rates are neasured in the or environs.
Dry. ell Radiation is >-
R/hr as indicated on Contairment Rad hitors 4379A&B or 1C29 7
EPA PAGs are proje9ted to be Airborne Effluent Release Indications exceeded outside the site boundary.
Standby Gas Flod Indicators -
Panel IC24 Fl/Amumiator Offgas Stack Rad Itnitors -
Panel IC10, itnitors 4116A,B Reactor Building Stack itnitors -
Panel 1C23, h itors 182A,B,C Turbine Building Vent i
t 6
I I
e d
4.j
EPIP ATTADtENT 2 EMRGETCY ACTION LEVEL PAE 11 of 35 QASSIFICATIQi GJIDELINES l
tbte: Th3 instrurentation listed in i
this colum my serve as a possible tMJSUAL SITE COSAL l
indication, but they am not necessarily EVENT ALERT EERGE!CY EKRGDCY EVENT TYPE PLANT @0ITIONS sufficient cause to &tennine an EAL.
! Envirmtental Dose Rates are prbjected at the site Projected &se rates of 500 w/hr hle body C4 Releases boundary under adverse reteorology or 2500 w/hr thyroid as detennined by (Related to greater than 500 w/hr hie body or inplementation of EPIP 3.3, " Dose Projections" EPAPAGs)
, 2500 w /hr thyroid for 2 minutes.
or (Continued) i These (bse rates are neasured at the site
. or boundary following inplementation of EPIP 3.1, I
"(h-Site Radiological Monitoring" These cbse rates am measured in the or environs.
Dryell Radiation is >--
R/hr as indicatal on Contaiment Rad Mmitors 437948 or IC29 EPAPAGsareprojktedtobe Airborne Effluent Release Indicators exceeded outside the site boundary.
Standby Gas Flod Indicators -
I Panel 1C24 Fl/ Annunciator Offgas St&k Rad Monitors -
Panel 1C10, M nitor 4116A,B Reactor Building Stack Fbnitors -
Panel 1C23, Mnitors 182A,B,C Turbine Building Vent -
O 1
I I
EPIP i
ATTACHEtR 2 EERGENCY ACTIOi LEVEL PA E 12 of 35 -
CLASSIFICATION GJIDELitES
~
4 tbte: Tha instruaentatim listal in I
this coltrn ray serve as a possible UtOStBL SITE GEtERAL DERGENCYllDERGEN indication, but they are not necessarily EVEPR ALERT EVEtR TYPE PLRE 010lT10NS sufficient cause to determine a1 EAL.
Ernirornental Dose rates createf than 1 Ran/hr Projected dase rates of 1 R/hr hle body cr 03 Paleases sole bcdy or 5 Ren/hr thyroid are 5 R/lr thyroid as detennined by (Relatedto projected (based m other plant inplementation of EPIP 3.3, " Dose Projections" EPAPAGs) paraneters) at the site boundary or (Contir.ued) urder actual neteorological These dose rates re neasured at the site I
corditions.
I boundary followirg inplanentation of EPIP 3.1, "On-Site Radiological tbnitoring" or or
~
1 Dryell Rajiation is >
- R/hr as These dose rates hre measured in indicated on Containnent Rad ebnitors 4379MB the environs.
l 1C29 Airborne Effluent Release Indicators
' Standby Gas Flow Indicators -
Parel 1C24 Fl/Amunciator Offgas Stack Rad >bnitors -
Panel IC10, ftnitor 411fA,B Reactor Building Stack Itnitors -
i Parel 1C23, tbnitors 182A,B,C Turbine Building Vent -
Other plar.t conditions exist, from Emygency Coordinator judgnent D4 4atever source, that nake release
-of large anounts of radioactivity in a short tine priod possible.
l 1
1 t
f l
_i
(>
O) u e
EPIP 1.1 ATTACFffNT 2 DERGENCY ACTION EVEL PAE 13 of 35 CLASSIFICATKN GJIDELIES i
Note: The instrmentaticn listed in this colmn ney serve s a possible lMJSUM.
SITE GEERAL indication, but they are not necessarily EVENT ALERT EKRGENCY EKRGENCY EVENT TYPE PLANT COPOITIONS sufficient cause to detennine an EAL.
Degraded Fuel' Rertor coolant activity cyeater Reactor Coolant denistry sarple msults as A4
- Integrity than Technical Specification reported by the Radiation Protection limit of 1.2 uci/gn of cbse Department based toon analyses conducted in egJivalent s ich requires shutdown.
accordance with applicable cps.
Other Possible Irdications
- ncreasing Reactor Coolant conductivity as indicated on Reconier 2738,2737 1004 Increasing radiation levels as indicated on:
a) MSI. Radiation N nitors b) Off Gas Pmtreatment Radiation Ptnitor 4104 1C10 MSL Hi Rad alann 1005 Air Ejector nonitor activity Indicated air ejector activity rate >
A5 greater than 500,000 uci/sec or an cpn as indicated on Offgas Pre-treatment Rad increase of 100,000 uci/sec within Pbnitor 41041C10.
a 30 minute tine period.
or Indicated air ejector Elvity rate increase of cpn within 30 minutes s indicated on 1
Offgas Pm-treatnent Rad Monitor 4104 1C10.
Other possible Indications Increasing radiaticn levels as indicated on:
a) MSL Radiation Ptnitors b) Offgas Post-treatment Rad Nnitors 4101A8B IC10 c) Stack Rad Pbnitor; RI 4116A & B 1C10 MSL Hi Rad alarm 1(D5 1
(3 (O
\\
EPI
.1 ATTACFf0 R 2 EHRGEPCY ETIOi LEVEL PAGE 14 of 35 CLASSIFICATI01 GJIDELItES tbte: The instrmentation listed in this colum may serve as a possible if0SmL SITE GEfGAL indication, but they are not necessarily EVENT ALERT EMRGEPCY EKRGEPCY' EVENT TYPE PLAM 00f0lTIONS sufficient cause to detennine an EAL.
Degraded Fuel Reactor coolant activity greater Reactor Coolant denistry sa:ple msults as B5 Integrity than 300 uci/gn of dose reported by the Radiation Pmtection (Continued) ecpivalent I-131 Departnent based mon analyses conducted in Econlance with applicctle cps.
Other Possible Infications Increasing Reactor Coolant conductivity s indicated on Paorder 2738, 2737 1C04 Increasing radiation levels as indicated on:
a)MSLRadiationFbnitors b) Off Gas Pmtreatnent Radiation etnitor 410% 1C10 MSL Hi Rad alann 1C05
' Air Ejector nonitor activity Indicated air ejector rtivity rate >
B6 greater than 5 ci/sm corresponding cpn as indicated on Offgas Pre-tmatadiE R3I to 16 isotopes deca 3ed 30 minutes.
tbnitor 41041C10.
Other possible Indications Increasing radiation levels s indicatal on:
a) MSL Radiation bbnitors b) Offgas Post-treatment Rad tbnitors l
4101A&B 1C10 c) Stack Rad ibnitors RI 4116 A881C10 MSL Hi Rad alann 1005 Degraded core with possible loss of Degraded Fuel Clad Integrity - see B-5 C5 coolable geonetry.
AfD LOCA - see C-1 or Dry ell radiation >
R/hr as indicated on e Contalment Rad Monitors 437948 1C29.
i l
1 1,
l l
O O
O EPIP 1.1 ATTACifENT 2 EMRGENCY /CTIm LEVEL PAGE 15 of 3 CLASSIFICATICN GJIDELIES Note: The instrunentatim listed in this colum nay serve m a possible LMJSlML SITE GEERAL indication, but they am not necessrily EVENT ALERT EERGENCY EKRGENCY EVENT TYPE PLANT 00f0ITIONS sufficient cause to detennine an EAL.
Loss of Any 2 of the following 3 conditions LOCA - see C-1 05
- 2 of 3 with tie potential for the third:
Fuel Integrity - see B-5 Fission
- 1) LOCA greater than makeup Contaiment Intecyity - see A-12 Product capacity Barriers 2)Degradedfuelintegrity
- 3) Loss of primary contaiment integrity Systen/
Stuck open safety or milef valve
" ADS Safety Valve Leaking" alann ICD 3 A6 Equipmnt Hic) relief valve discharge pipe tenperatum Failure or or high safey valve tail pipe tenperatums as K11 function indicated on TR 440(M,B,C and D IC21.
Wite pmss lite off 1C21 for one or nore of the respective valves.
Other Possible Indications Increasing Torus water tenperature as indicated m TR438fA/B 1C29.
Increasing Torus wata level as indicated on LR4384 and 4385 1C29.
Increasing Drywell pressure as indicated on Incmasing Drywell tmperatum as indicated on TR4383 A,8, and C 1C29 or TR 5713A and B 1C25.
" Primary Contaiment Hi/Lo Press" alarm 1005. '
" Primary Contalment Hi Press Trip alann 1C29.
Generator load decrease as indicated cn W1100.
101 and Gm Megmatts lWB.
Main Stean Line flow decrease m FI4408,4409, 4410, 4411 and FR44504 1C05.
O JD O
ATTACif1NT 2 DERGENCY TGION LEVEL.
PAGE 16 of 35 CLASSIFICATIQi GUIDEl.IES tbte: Tle instrune tation listal in this a) lum cey serve as a possible tNJSLRL SITE GEERAL indication, but they are not necessarily EVENT ALERT DERGEtCY EKRGENCY EVEr# TYPE PLANT Q1DITI0tlS sufficient cause to &tennine an EAL.
Systett/
Any ECCS actuation that results in IPCI Initiation A7 Equigent water being discharged to the 1C05 alann "lPCI Auto Initiation" on ICO3 Failure or Reactor Vessel that is either FIC 230) indicates flow.
tblfunction unexpected or is required to recover CV 2313 indicates open.
(Continued) and maintain RPV water level.
Possible response on Neutron Mxiitoring.
or RCIC Initiation
---=~"'-w=-
r :2 1035 alann "RCIC Auto Initiation" on 1004
~ ~ ~ " ~
flC 2509 TiidicatesTiow ~ ---
CV 2513 indicates open.
Possible response 01 Neutron Mx11toring.
/
or LPCI Initiation (injectial possible only if h press is less than 450 psig) on 1C03 I
" ADS Core Soray or LPCI pulp running" alann.
FI 1971 A/B indicates flow.
g CV 2002 or CV 1905 indicates open.
or Core Spray Initiation-(injection p)ssible only if h press is less than 450 psig) on 1(D3
" ADS Core Spray or LPCI ptcp ruming" alann.
FI 2110 or FI 2130 indicates flow.
CV 2118 or CV 2138 indicates 6 pen.
1 4
e 1
f
t I
EPIP 1)1 1
ATTADI S T 2 DEGENCY ACTIO1 LEVEL PAGE 17 of 35 ~
CLASSIFICATICN GJIDELINES i
i j
1.fbte: Tha instrumntaticn liste1 in this colum my serve as a possible indication, but they ane not necessarily[tJUSUAL DEGEfCYl SITE GD SAL EVENT
, ALERT DfRGENCY EVENT TYPE PLANT 00f0lTI0tS sufficient cause to chtennine an EAL.
l 4
Syste#
Loss of a fire suppdession function Loss of both the Electric aid Diesel Fire AS Equipent mquiring shutdowi tiy Technical Ptops as indicatai by Failure or Specifications.
- 0 fulfunction Inability to provide a backtp water source (Continued) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
t Orplete loss of any function needed Shift Supervising Engineer judgnent.
B7 for plant cold shutdan.
I Caplete loss of a1y function needed ShiftSupervisingEngineerjudgnent.
C6 for plant hot shutdown.
t t
Turbine rotating cmponent failure Turbine Trip Wien >30s power due to high A9 l
causing rapid plant shutcbwn.
vibration as indicated on or annunciated on Turbine failum causing casing Turbine Trip den >30% power due to high 88 l
vibration as indicated on f
or annunciated on i
ND j
Possible corriense veOnn decrease as indicated on l
i i
i i
O-O n
a v
EPIP 1.1 ATTACifENr 2 DERGENCY #LTION EVEL PAGE 18 of 35 CLASSIFICATI(N GJIDELIES Note: The instrtmentation listed in this cnitsm nay serve as a possible
- lNJSllAL, SITE GEERAL indication, but they are not necessarily, EVENT ALERT EERGENCY, EKRGDCY EVENT TYPE PLANT CONDITIONS sufficient cause to detennine m EAL.
06 Systen/
Shutdown occurs but requisite & cay Groto I isolation with total loss of RIR
,i Equiprent heat ramal systen (e.g., RlR) or sysen Failum or non-safety systers heat ramal neans md/or Malfunction am renderai unavaliable. Core Total loss of Rff & systen md/or (Continued) degradation or nelt occur in about Total loss of ESI systen ten hours with stbse@ent contairment failure.
md/or Total loss of RE systen and/or Any cmbination of the above systens that prevent decay heat ramal.
Systen/
Loss of IPCI and either ADS or RCIC Failure to satisfactorily conplete All Equipment strveillance testing in accordance with the Failum or Loss of ADS logic or loss of nore applicable STP m
Malfunction than 1 ADS valve (Lossof Visual cbservation safety Total Loss of any of the following systens or Core Spray Other Possible Indications features LPCI SBLC - Loss of Squib Valve continuity as requiring RIESW indicated by:
shutdom in ESW a) Loss of indicatirg lites 1C05.
accordance SBLC b) " Continuity loss to Smib Valve" alann
- with Techni-Standby Gas Treatnent 1(DS.
cal Specifi-cations Loss of Contairment Spray capability SBGT - Diarcoal bed temerature > 255*,310*
1C24 Loss of both IE and 02 Analyzers Diesel Generators
" Diesel Generator Trouble".
Loss of both Emergency Diesel alanns 1C08. Diesel Generator Auto-Start Generators Failure alarns 1C08. Local alarms at Diesel Generators 1C93 and IC94
l
~^
EPIPhy i
ATTIO fB R 2 EMRGEfCY ETIm LEVEL.
PAGE 19 of 35 -
QASSIFICATIm GJIDELINES Note: Tle instrumntation listed in I
this colum my serve as a possible tNJSUN.
SITE GENEPAL EERGDCYl indication, but they are not necessarily EVENT ALERT EERGDCY j
EVENT TYPE PLAW mOITimS sufficient cause to determine an EAL.
System /
Any conbination ofjsafety systen As specified on the applicable Technical All Equipmnt failures that require shutdom by Specification Limiting Conditions for Failure or TechnicalSpecification.
Operations (LCO) statemnts.
~
1l Palfunction (Lossof i
safety ered systeis or
- features
' requiring) shutdom in 1'
accordance i
with Techni-cal Specifi-cations (Continued) i s
e
)
i ea i
i
EPIP 1 ATTADfENT 2 DERGErCY ACTI0rl LEVEL.
~
PAGE 20 of 35 CLASSIFICATIDI alIDELINES tbte: Ttu instrumntation listed in this mlum may serve as a possible LNJSLRL SITE GENERAL indication, but they am not necessarily EVENT ALERT DERGEtCY EKRGEfCY EVEtK TYPE PLAT 6 00f0ITICtlS sufficient cause to detennine an EAL.
s System /
Loss of primary contaiment Both valves in one cr nore vent or purge lines A12 Equipent integrity to the drpell am open ard am required to be Failure or closed.
tbifunctions or (Lossof Any Auto isolation valve that is. failed in the Contaiment non isolated condition.
~# ~ ' -
Integrity)
- or" '-
~
'W
= 71 Both doors in the DryiiT) air lock are not scaled / clos ~edfat leastwe d50F~niist lie' ~~
closed and sealed).
i
[
Om or nom blind flaiih and/or manways not closed.
and/or IC35 Alants
?
"Drwell Torus low P" i
" Standby P Air Conpmssor Running" i
l and/or 1C05 Alanns "Containmnt hi H and 0 Content A and/or 2
2 Pover Failure"
.I "Contairrtent hi H2 and 02 ontent B and/or C
Power Failure" "d/UF t
AR 4381/4382 on 1C09 indicating increasing 02 concentration i
aidfor Torus level <
or >
or on LR 4384,4385 and IC29.
Other items to mnsider; s& next page 9
9 EPIP ATTACFfENT 2 BfRGENCY #CTION LEVEL 1
PAE 21 of 35 CLASSIFICATI01 GJIDElltES
' tbte: The instrumntatim listai in i
this colum r.ny serve as a possible lUfAJSlK SITE
- GENERAL l
indication, but they are not necessarily; EVENT ALERT' DERGENCY[NM EVENT TWE PLAT # C00lTI0tS sufficient cause to datenuine an EAL.
Systen/
Loss of priaury co'ntalment Other Item to Consider Equipmnt integrity (continued)
" Primary Containmnt Hi/Lo Press" alarm ICOS Failure or Dryell and Torus pressure as indicated on:
Malfunctions (Lossof l
Dryell tenperature as indicated on:
Contaiment Integrity)
(
a) TR 4383A,B aid C 1C29 (Continued) i b)TR5713\\andB IC25 Loss of secondary contaiment Both (bors in any airlock not closed A13 integrity
}
or Both 58GT system irgisable or Any automatic isolation valve failed in the non isolata1 position.
i or Failure to satisfactorTTy emplete f
surveillance testing in accordance with the applicable STPs.
t g
4
}
e
O O
O j
EPIP 1.1 ATTACFfB E 2 EERGENCY K, TION IfvEL PAGE 22 of 35 CLASSIFICATI(N GJIDELIES 4
t i
Note: The instrtmentation listai in this colum nay serve as a possible LHJSLML SITE GENERAL indication, but they are not necessarily EVENT ALERT EERGENCY EMRGEPCY EVENT TYPE PIR E W OITIONS sufficient cause to determine an EAL.
- Systen/
Loss of offsite power Loss of Startup Transfonmr A14 Equiprent lA3 and/or 1A4 transfer to stan&y i
Failure or transfonner Malfunction Startto transfonner OCB 5550 open as (Lossof l
indicated on 1C08
~
Powr) or Loss of Stan t y Transfonner 1C08 alann "Stanty Transfonner Lockout Trip" i
Stan6y Transfonner OC8 8490 opm as indicated on 1C08 i
or j
1Al and 1A2 power avaiTable lights are off on 1C08 and 1A1 and 1A2 voltmeters on 1C08 reading zeru volts.
and Both Diesel Generators nming md supplying i
IA3 and 1A4.
{
dix l
l Bkrs J & M (8490 and 555DT indicate open or no power availtble.
i EmergencyDieselGenerator(s) operating 1C08 Sub-station breaker position - Panel 1C08
(
f 1
i EPIP 1
[
1 ATTADtDIT 2 DERGENCY ACTION LEVEL PAGE 23 of 35 -
Q.ASSIFICATICN GJIDELitES 9
9 9
9 9
9 M
I ibte: Tlu instrumntation listed in I
this colum imy serve as a rossible l#USlRL' SITE GENERAL indication, but they are not necessarily EVENT ALERT; 9ERGENCYl; DERGEtCY EVENT TYPE PLM C0f0ITIONS sufficient cause to d2termine an EAL.
,5ystan/
Loss of onsite power capability Failure of both diesel generators to cmplete A15 lEquipx:nt surveillance testing in accordance with the Failure or applicable STP.
fialfunction
) Observation or (Lossof Poer)
I l(Continued) or Failure to start den iivired or l
Loss of one cr nore of% following Busses lA3, lA4,1B3 or IB4 as indicated by:
l
}
a) Pomr supply lites on 1C08 are not lit b) Voltaga for Bus is zem I
c) 1(D8 alanns "4KV Eus IA3 Loss of Voltage" l
"4KV Bus IA4 Loss of Voltage" "CB EL 757-6tf Trans IX314KV Bkr IA303 Trip" "CB EL 757-6LE Trans IX41 4KV Bkr 1A403 i
Trip" d) Bkr lA303 open e)Bkr1A403open 4
l
=
i 1
l 2
a
C)
EPn(.),
(D e
u ATTAOtENT 2 BERGENCY E TION LEVB.
.+
PAGE 24 of 35 QASSIFICATIQi GJIDELIES Ibte: Tin instrunentation listai in this colum may serve as a possible UtOSUAL SITE GEN 8AL indication, but they are not necessarl'ly EVENT ALERT DERGEICY EKRGENCY EVENT TYPE PLAtlT OC(OITIOlS sufficient cause to detennine al EAL.
Systen/
Total Loss of all AC Pa.er, lA3 and 1A4 Poe indicating lights on 1008 B9 Equipmnt restoration from (bntrol Roan not not on Failure or possible.
and Malfunction lA3 and 1M Volt nnters reaiing zero on 1C08 (Lossof aid P&er)
" Diesel Generator 1G3r5 tart. Failure" alann (Continued)
ICOB
~
~
~
_and.,...
" Diesel Generator 1GF5Eart Failure" alann l
1C08 aid /or The following Bkrs irdicate open on 1C08 152-301 152-401 152-301 152-311 152-411 152-402
. and/or JBkr(8490)toStandbytrans.
s MPir(5550)toStartuptrans.
lTotal Loss of AC Poyer, restoration
~
C7 not possible within 15 minutes.
Same as sove for > 15 minutes.
I Total loss of 125v DC Pc er B10l Loss of RCIC indicating lights I
and Loss of all Control Roan Annunciators and I
Loss of 611ity to open and close 4160V and i
480V breakers from Control Roan Total Loss of 125v QC Po wr; (B.
restoration not possible within Sare as above for > 15 minutes 15 minutes I
EPIP f
ATTADt D!T 2 DSG5fCY ACTI0ri LEVEL PAE 25 of 35 CLASSIFICATI01 GJIDELINES j
i m
i I
tbte: Tha instrumntatim listal in l
this cnlum reay serve as a possible i
indication, but they are not necessarily[UtOSLRL ALERT [BSGEtCY-DGGETCY SITE GEPSAL i
EVENT
[EVENTTYPE PLAT 1T 0)DITIONS sufficient cause to d2tennine an EAL.
4 J
Syster/
Failure of RPS to (nitiate aid Both of the following alanns on 1C05 Bil Equipmnt ca plete a reactor' shutdown.
" Trip Systen 'A' Rx Auto Scratf' Failure or aid i
Malfunction
" Trip Systen 'B' Rx Auto Scratf'-
(RPS l
aid Failure)
APRWIR4 is not dom scale after short period
{
of tine.
i RPV pressure on PE 4563, 4564, 4565 on 1C05 renains steady.
Other Indications
}
All rods not fully inserted as indicated on green " fill in" lites on IC05 and CRD position ind.
Transient Requiring'0peration of Both of the following alanms on ICG 09 Shutdan Systens with Failure to
" Trip Systen 'A' Rx Auto Scratt' Scran (continued power generation, and but ro core danage immdiately
" Trip Systen 'B' Rx Auto Scratf' evident).
and i
No control red notion (red fullout lites l
renain on, to nas grem lites on) on 1C05 Other indications tb decrease as indicated on:
i a) APR4s m 1005 b) Stean flav and Feed flav on ICG c)G2neratoroutputon1008 1C05 alants indicate shutdom should have occurred.
4
EPIP i
ATTADI-DJ 2 DERGE?CY ICTION LEVEL.
PAE 26 of 35 CLASSIFICATION GJIDELItES L
L tbte: The instrumntatim listed in
[ SITE this coltml may serve as a possible lJUSUAL GENERAL ALERT]EERGEfCY indication, but they am not necessarily EVENT DERGEfCYl EVENT TYPE PLANT CQDITIONS sufficient cause to datennine al EAL.
l Systen/
Transient (e.g.,lossofoffsite Sam as preceding,.plus: Inability to 07 Equipent poaar)plusfailureofrequisite initiate SBtf Failure or core shutdom systens (e.g., scran Malfunction or standby liquid control systen).
(RPS Could lead to caretrelt in several Failure) hours with contairimnt failure (Continued) likely. ftre severe consequences if ptnp trip does not: function.
~
Natural Earthquake of sufficient nugnitude Seismic Alann - Panel 1C35 A16 Occurrences to actuate the Seismic tenitoring (0.01g) Green V Light Systen.
l i
t Earthquake greater,than OBE.
Seismic Alann - Panel 1C35 B12
(.06)YellowLight 9
t I
Earthgjake greater'than DBE with Seismic Alarm - Panel 1C35 C10
(.12)RedLight plant not in cold shutdom.
9 s
l t
i l
l
i
.. ~.
(
(')
EPIP 1h i
ATTA0fftd 2 DERGEtCY ETION LEVEL.
PAGE 27 of 35 -
CLASSIFICATI04 GJIDELITES s
e t
i 9
-9 tbte: Tru instrumntation listed in I
this colum may serve m a possible
' lJU9&C SITE GEt. %t BERGEtCYlDERGDCYj indication, but they ae not necessarily EVEffT ALERT EVEtR TYPE PLAflT 00talTIONS sufficient cause to chtermine an EAL.
l
, Natural Cedar River level greater than 753'.' Intake Structure Level Recorder -
A17 l
Occurrences Parel 1C102 (Continued)
Ca:puter generated river level printout Corputer Point FD10
.I Cedar River level grater than 757'.
Intake Structure Level Recorder -
813 I
Panel 1 CIT Ccrputer generated river level printout Caiputer Point F010 t
Cedar River Idel greater than 767' Visual Observation Cll l
cr loss of flood protection for safety related structures with plant not in cold shutdcw).
\\
Cedar River floa lefs than 200 CFS.
Cedar Rapids City Water Dept. report A18
?
I i
t Cedar River flow less than 50 CFS.
Cedar Rapids City Water Dept. report B14 l
l i
EPIP.)
ATTACFIB E 2 EWRGENCYTCTIQiLEVEl.
l PAGE 28 of 35 QASSIFICATIOi GJIDELITES i
iI' ibte: Tiu instrmentation listed in this colmn rey serve as a possible INJSt%L SITE GEERAL '
4 indication, but they are not necessarily EVENT ALERT EERGEtCY EERGE?CY i
EVErli TWE PLAtli 00f0ITIONS sufficient cause to detennire an EAL.
flatural
' Cedar River flow less than 13 ES Cedar Rapids City Water Dept. report C12 i
0 currences [' with plant not in cold shutdom.
.l (Continued)
J, i
.:vm-
- z.
i c.
.. n s _
i g
t s
l Winds greater than 100 nph with
%teorological Instrmentation - Panel IC21 Cl3 plant rot in cold shutdown.
i i
s i
l l
Tornado on site. '
Visual observation.
A19
. l 8,
1 i
Torn 110 strikes fadility causing Visual observation ard associated l BIS l
damge.
I systen alanns I
(
I f
f l
EPIP ATTACKErg 2 DERGEtCY ILT101 LEVEL PAGE 29 of 35 CLASSIFICAT104 GJID-1tES 1
i tbte: Tha instrmentation listaf in j
trUSLPL SITE GE?ERAL,i this colum may serve as a possible EVENT JALERTDERGEtCYlDERGEtEY indication, but they are not necessarily EVETR TWE PLAtR 00f0ITlatS sufficient cause to chtennine al EAL.
l tiatural Tornab vhich damges safety related Visual observation and associated C14 Occurrences structures and cocpronises the systen alans (Continued) functions of safety systers Other Unusual aircraft activity over l 02munications from, Security.
.; x,,.
A2Q,
..~
_~
Hazards facility or crash on site
- Experienced l
.. w r_.
~... -
orProjected Aircraft crash or missile inpact Commnications from Security B16 thich causes facility danage.
Visual Observation and Associated Systen Alans l
I i
l i
Aircraft crash or missile inpact Comunications from Security C15 vhich danages safeyy related system Visual Observation and Associated or structures with plant rot in cold Systen Alans shutdoa1.
1 4
Train derailcent ensite Gmunicatiom from Security A21 i
i
EPIP 1 r' ATTADf04T 2 BERGENCY ILTIOi LEVEL PAGE 30 of 35 CLASSIFICATIO1 GJIDELIES Note: Th3 instranentatim listed in this colum my serve as a possible LMJStpt SITE GEfSAL irdication, but they are not necessarily EVENT ALERT ETRGEPO; DERGEtG EVEt6 TWE PIRE CDDITIGIS sufficient cause to datennine m EAL.
'Other thar or onsite explosion Comunications from Security A22
' Hazards Visual Observation Experienced or Projected (Continued)
)
... = - -
- ~-
w
=- q Explosim onsite which causes CLrrunicaticas:from Secucity...-~ - - -
817 fa:111ty danage affecting plant Visual Observation and Associated l
operation.
System Alarms j
i 3
1 I
Explosion onsite v.hich danages Comunications fmn Security C16 safety related systens or structures Visual Observation md Associated l
i with plant not in cold shutdown.
Systen Alanns i
Onsite release of toxic or Portable Detectors A23 flannable gases.
Possible Odors.
Visual Obser/ation 0
8 l
O O
O EPIP r:1 ATTACHEf6 2 DERGENCY ACTIOi LEVEL PAGE 31 of 35 CLASSIFICATI01 GJIDELI?ES i
i tbte: Tlu instrunent. ion listed in this colum my serve as a possible LIUSUAL SITE GE!ERAL indication, but they am not necessarily EVENT ALERT DERGEtCY[DERGEICY[
EVEtU TYPE PLATH 00f01TIONS sufficient cause to detennine an EAL.
' Other Uncontrolled stry of toxic or lPortileDetectors B18 Hazards flannable gases into the facility Possible Odors.
Experienced environs.
Visual Observation or Projected 1
(Continued)
-. 4 ~-
w) =..
nn Uncontrolled entry of toxic or Portile Detectors C17 flannable gases into critical plant Possible Odors.
areas where lack of. Icess to Visual Observation the area constitutes a safety problan. Plant not in cold shutdown condition.
' Release or Any uncontrolled increase in As mported by the Radiation Protection i
B19 Loss of radiation levels or; airborne Departmnt based upon tre results of surveys Control of contanination levels greater and analyses conducted in accordance with Radioactive than 1000 tines nonnal applicable PM s.
Materials Other Possible Indicators-within the l AR4 indicators l
Plant CAM mcorders 1
I l
e
O O
O
{
EPIP 171 ATTADICIT 2 DERTtCY ACTION LEVEL PA E 32 of 35 CLASSIFICATI01 GJIDELINES i
1 I
tbte: The instrunentation listed in
{ SITE i
this colmn may serve as a possible
' UttSPL GEtER2L i
indication, but they am not necessarily EVENT ]; ALERT lEtERGEtCYlDERGE L
EVENT TYPE PLA'E GOITIO15 sufficient cause to &termine al EAL.
j Release or Fuel handling accident that msults Visual observation B20 i
Loss of in fuel danage with tre release of and
' Control of radioactivity to the Rx Bldg.
As reported by the RadiHTon Protection Radiortive (Secondary Containamt)
Department bassi upon tie results of surveys Materials and aialyses conducted in a cordance with within the applicable RFPs.
l Plant i
Other Possible Indicators (Continued)
AR4 indicaton l
CN4 mcorders l
f%ior danage to spent fuel in Rx Visual cbservation C18 Bldg. (Secondary Contalment) and i
As reported by the Radiation Pmtection l
Departnent based upon the results of strveys l
and alalyses conducted in rcordance with i
i applicable RPPs.
Other Possible Indicators AP4 indicators C44 mcorders Uncontrolleddecre$seinFuelPool Water level indicator - Panel IC66 C19 water level below fuel level.
37 ft. 6 in. minicun level Fuel Pool Cooling Cleanup Filter Trouble Annunciator Panel 1C04 f
1
1 EPP ATTADIT.fE 2 OfRGErCY ICTION LEtII.
PAGE 33 of 35 -
CLASSIFICATI01 GJIDELIES j
I
- tbte
- Tlu instrumntation listed in j
t this colum nuy serve as a possible t!USLML SITE GDBAL DERGEPCYlBSG90Ylj irdication, but they am not necessarily EVEPR ALERT:
EVETE TYPE PLR E 00t01TIO15 sufficient cause to datennine an EAL.
l
- Events Indications cr Alarius cn Process or Systen Alann/ Recorder A24 Affecting Effluent Paraneters' in tre Control Operational Room which mquire blant shutdovn.
Q)ntrol
.=
t l
Loss of all safety related alarm Loss of Visual B21 and annunciation capability; restor-or ation not possible yithin loss of Visual and Bible alann systen 15 minutes.
I Loss of all safety related alarm and loss of Visual alann systen l
C20 l
annunciation capability coincident or ~
l with plant transient.
Loss of Visual and Tidible alarm systen l
l l
l Significant loss of assessnent or ShiftSupervisingEngineerjudgent.
A25 l
l comunications capability.
Other plant ccnditions exist that A26 warrant increased asareruss or require plant shutdxn under l
l l
[ Technical Specification a-involve other than nonnal controlled shutdown.
l l
l 1
I' i
I I
i i
i
.A
l EPIP i
ATTfOtGT 2 DERGEtCY ACTIO4 LEVEL.
PAE 34 of 3S -
CLASSIFICATI04 GJIDELItES
~
t tbte: The instrurentation listal in this colum may serve as a possible UtUSUAL[
SITE GEtERAL indication, but they are not necessarily EVENT ALERT DERCBCY DERGEtCY EVENT TYPE PLANT OMITIO1S sufficient cause to d3termine m EAL.
Ml Events Other plant conditions exist that Energency Coordinator judgrent 822 Effecting warrant precautionary activatial of
- 0perational TSC and placing EG and other key Cbntrol arrgency personnel on stareby.
(Continued)
Other plant conditions exist that EnErgency Coordinator judyent C21 l warrant activation of crergency l
centers zod r.onitoring tea:s or a precautionary notif,icatial to the public rear the site.
l Control Roan Evacuation of the Control Room Control Room evacuated and action initiated 823
' Habitability regaired for any reason. Shutdown in accordan with Operating Procedures outside Control Room initiated.
Evacuation of the Control Roan Failure of Systan Corponents to Function C22 required for any reason. Shutdown from Ra:ote Shutdown Panel outside Control Room rot inplcsonted within 15 minutes.
Situations Transportatico of ortaninated Comrunication from Health Physics A27
- Papiring injure 1 ir.dividual to the hcspital Off-Site i
Assistance Security threat, attepted sabatage, Comunication from Security A28 or unauthorized forceable entry f
Confirtred oi-going ' security Comunication from Security or Operations B24 cocpranise I
EPIP 1 ATTACHOff 2 DEGDCY ACT101 LEVEL PAT 35 of 35 CLASS 1FICATlat GJIDEll?ES t
t t
t e
e o
- tbte
- Tha instrumntation listed in this colum cuy serve as a possible
' UttJSLpt SITE GE' SAL indication, but they am not necessarily EVENT ALERT DECflCYlGGGBCY EVErlT TYPE Pl>NT GIDITIG4S sufficient cause to datennine m EAL.
J Situations Inminent loss of physical control Comunication from Security cr Operations C23 Requiring of the plant Off-Site Assistance i
(Continued)[Lossofphysicalcontrolofthe Commnication from Security DB m,=-"'
plant
- ~^
i i
c.
<. e __ _ _, _,... _ _ _ -......
s Fire within the secured area that Ccrmunications from Fire Brigade
.A29 l
4 cannot be extinguished within 10 minutes by the Fire Brigade 4
t B25 Fire mt extinguished in 10 minutes Comunication from Fire Brigade in an area that coul,d affect safety related equipment i
Fire corpromising the functions of Comunication from Fire Brigade C24 l
l safety systes Associated Systen and Alanns - Panel IC40 Observation i
i
. EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 1
of 8 ONSITE RADIOLOGICAL MONITORING Revision 2 Date - 3/1/82 1.0 PURPOSE This procedure provides instructions for performing onsite radiological monitoring during an emergency at DAEC including determination of habitable areas and identification of the extent of radiological effects of the emergency.
2.0 APPLICABILITY This procedure applies to specific actions to be taken by radiological monitoring personnel while conducting onsite radiation and airborne activity surveys during an emergency.
On-site surveys are expected to be performed for any event classified as an ALERT or greater, but may be performed for an event classified as a NOTIFICATION OF UNUSUAL EVENT.
3.0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinator 3.1.1 Inform the OSC Supervisor of the need to prepare and dispatch radiological monitoring / surveying teams to onsite locations (areas within the site exclusion boundary) both within plant buildings and to affected site environs.
3.1.2 Coordinate activities and evaluate the results of radiological monitoring team surveys.
3.1.3 Advise the Emergency Coordinator of onsite radiological conditions and recommend protective measures including evacuation of the plant in part or in whole, if necessary.
3.1.4 Identify the need for additional onsite monitoring personnel.
3.1.5 Authorize changes to DAEC administrative exposure limits.
3.2 Emergency Coordinator l
l 3.2.1 Initially provide protective action recommendations.
l
(
3.2.2 Obtain the services of outside agencies to assist in radiological monitoring, as necessary.
j 3.2.3 Authorize emergency exposure limits.
4.0 INSTRUCTIONS 4.1 Not'ification and Mobilization of Radiological Monitoring Personnel 4.1.1 Upon activation of the DAEC Emergency Plan, onsite personnel will be notified as outlined in EPIP'1.2, " Notification of the Emergency Response Organization and Offsite Support Agencies".
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 2
of 8 ONSITE RADIOLOGICAL MONITORING Revision 2 Date - 3/1/32 4.1.2 Radiological monitoring personnel will report to the Operations Support Center (OSC).. Refer to EPIP 2.1, " Activation and Operation of Operational Support Center".
~
4.2 Assignment of Personnel to Onsite' Radiological Monitoring
)
~
4.2.1 Personnel arriving at the OSC shall~ remove tags in sequence ar; cording to qualification, report to the OSC Supervisor and begin impJementing
~
their specific duties.
Refer to EPIP 2tl, " Activation a9d Operation of Operational Support Center".
~
4.2.2 Other emergency response personne1', not assigned OSC tag board,
duties, shall report to;their emergency response stations or to the OSC Supervisor and-inform h'im th'at they are prepared to assist as,
needed.
4.3 Initial Actions Following Activation of the DAEC Emergency Plan
['
~
,1 4.3.1 The habitability of the Control Wom and 4SC shall be initially -
determined from Area Radittion N!nitor(ng Instrumentation'\\ ARM).
Follow-up sampling /surveyir.g shculd be performed to verify '
i n
habitability. The habi'tabiiity of the OS.C and Contractor Change ~ M
()
House shall'be determed as fo:1ows:
- Q r;
~
Casite monitoring /rurveying-tag duties will accomdlish' the a.
following:
,L
/
^
5-
',,1,
'y Obtain' Health Physics monijarin,g* equipment (located in the Emergencyduponse Team lockgrsh required to perforjn sbrveys in and'around 'Ehe general assembly areas.
, en y
Designate personnel to pedorm haMtabiIGy surveys of OSC
~
/-
and contractor 'chanep house.
(
b.
The follbwing surveys shall he performed:
Arearadiation.le/
vels.
3efer to RPP 7.1, " Radiation Qurveys
e-
~g Sijrf ace contamination levels.
Refer to RPP 7.3, " Radioactive r
Contamination Surveys".
Airborne activity leypls.
Refer to RPP 7 4,N" Airborne
. Radioactivity Surveys".";.
Q
\\.
,j f
$9
{
Y
/
l
~ f h
1 A
- Fr i s r, h
b ** "
/
i s
.i.
i..
-w,
J EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 3
of 8
,a ONSITE RADIOLOGICAL MONITORING Revisior. 2
/Q Date - 3/1/82 bJ f
c.
Habitability of key assembly areas (OSC, TSC, Control Room, Change House) shall be based on the results of radiological surveys to determine exposure received from direct sources, or radiological hazards caused from surface contamination er airborne contamination in the form of particulate or gaseous releases.
Personnel stay times in these key areas may be adjusted based upon direction from the Site Radiation Protection Coordinator, in concurrence with the Emergency Coordinator.
4 General DAEC administrative guidelines are as follows:
Direct exposure - 300 mrem / day.
Airborne contamination - 2 MPC (maximum permissible concentration) hours per day.
At 10% MPC, either a time keeper should be assigned, or respirators used in affected areas. Time keeping is recommended over respirator use unless the MPC limit is being approached, to facilitate communications.
p Specific survey guidelines are as follows:
%)
12 mr/hr based on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day occupancy.
~
I-1000 dpm/100 cm2 of smearable beta-gamma contamination on floor surfaces (contamination 1000 dpm/100 cm2 requires shoe covers.)
Higher levels of smearable beta-gamma contamination that may result in the area becoming airborne may require relocation or respiratory protection.
Unidentified particulate airborne activity less than l
1 x 10-9 uci/cc can be considered safe for occupancy.
Whea sufficient personnel and time are available, another l
air sample shall be taken to determine isotopic composition of particulate filters and iodine cartridges in accordance with the limits of 10 CFR 20, Appendix B, Table I.
4.4 Onsite Radiation Surveys l
4.4.1 The Site Radiation Protection Coordinator shall direct the OSC Supervisor to prepare and dispatch monitoring teams to initiate O
surveys within plant buildings and any other onsite areas affected by V
the emergency to facilitate access to areas for rescue and emergency repair work.
This shall be determined by the type, extent, and severity of the emergency.
L
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page-4 of 8 ONSITE RADIOLOGICAL MONITORING Revision 2 Date - 3/1/82 NOTE:
The Site Radiation Protection Coordinator shall obtain authorization from the Emergency Coordinator prior to initiating surveys.
4.4.2 The Site Radiation Protection Coordinator shall determine plant-radiological status by evaluating remote radiation instrumentation as-indicated in the Control Room or TSC.
Details describing this instrumentation, the areas which they monitor, and potential hazards involved in access to the various areas are covered in detail in RPP 7.2, " Operation and Use of Area Radiation Monitors" and Post-Accident Sampling System Procedure.
If access to these areas is required, refer to EPIP 4.3, " Rescue and Emergency Repair Work" for detailed procedures to be followed.
~
4.4.3 In-Plant Radiation Surveys (areas within plant buildings) shall be conducted as follows:
a.
The Site Radiation Protection Coordinator shall consult with tea Shift Supervising Engineer and the Emergency Coordinator to determine the areas where surveys are needed and priorities for-conducting the surveys, b.
The OSC Supervisor shall ensure that survey teams are prepared for entry.
c.
The Site Radiation Protection Coordinator shall obtain authorization from the Emergency Coordinator prior to' sending survey teams into plant areas.
The TSC shall also notify the Control Room that the survey teams will be entering the affected plant areas.
l l
d.
The survey team (s) shall then proceed to the areas and initiate surveys.
Communicatic's shall be continuously maintained between the OSC, TSC, Control.om and the survey team (s) using the j
operations two-way hand-held radios.
NOTE:
i If difficulty is experienced with communications equipment, team members should use any other means available according to the following priority:
l l-Preferred method - Operations radio.
Alternate method - Plant paging system.
Second alternate method - Plant telephone system.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 5
of 8 ONSITE RADIOLOGICAL MONITORING Revision 2 Date - 3/1/82 CAUTION:
Each team member is responsible for:
Periodically checking direct reading pocket dosimeters to et,nitor total dose received.
Observing established radiation exposure limits (refer to RPP 2.1, " Personnel Exposure Limits") unless authorized by the Emergency Coordinator to exceed these limits.
Under no circumstances shall personnel exceed the emergency radiation doses as stated in RPP 13.1, " Radiation Emergencies", without approval of the Emergency Coordinator.
Insuring that respiratory equipment is fitted and functioning properly.
Refer to RPP 8.1.
.e.
Radiation survey team (s) shall obtain survey data and promptly report the results as well as~other pertinent observations to the Site Radiation Protection Coordinator and OSC Supervisor.
f.
Upon completion of the survey, team members shall return to the
,,)
OSC, observing all control point requirements, and report to the OSC Supervisor for further instructions, g.
The OSC Supervisor shall notify the site Radiation Protection Coordinator and Emergency Coordinator that survey teams have left the plant area.
The Site Radiation Protection Coordinator shall inform the Control Room.
4.4.4 Site Boundary Radiation ftnitoring (areas outside plant buildings but within restricted area) a.
The Site Radiation Protection Coordinator shall review the plant status based on plant conditions and radiation monitors to determine if a release of radioactive materials to the environment has occurred.
b.
The Site Radiation Protection Coordinator shall consult with the Emergency Coordinator to determine if a release has or is likely to occur and whether monitoring teams should be dispatched.
c.
The Site Radiation Protection Coordinator shall determine the downwind airborne activity as well as estimated dose rates the monitoring teams are likely to encounter.
Refer to EPIP 3.3,
" Dose Projections".
d.
The Site Radiation Protection Coordinator shall advise the OSC Supervisor of this information and the OSC Supervisor will then issue specific instructions to the site survey teams and dispatch the survey teams to the affected area.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 6
of 8 ONSITE RADIOLOGICAL MONITORING Revision 2
.Date - 3/1/82 e.
Team members shall proceed to the specified site area.
Care shall be exercised to avoid the activity release path enroute by utilizing the portable survey instruments. The DAEC Operations Radio System shall serve as the primary mode of
.l communications.
i f.
Radiation monitoring teams shall obtain survey data and report results as well as other. pertinent observations promptly to the Site Radiation Protection Coordinator.
Sample media from either (or both) of the Environs Monitoring Systems should be collected rd returned for analysis, if possible.
L g.
Upon completion of the survey, the team shall return to the OSC, observing all control point requirement:,. The Team Leader shall i
report results of the survey to the Site Radiation Protection Coordinator and await further instructions.
4.5 Recording of Emergency Monitoring Data O.
4.5.1 All pertinent radiological data shall be recorded in the Emergency Monitoring Log which is maintained under the direction of the Site Radiation Protection Coordinator.
4.5.2 Entries shall include the following information, as applicable:
a.
Radiation levels in mR/hr or R/hr.
Refer to RPP 7.1, " Radiation Surveys".
b.
Airborne activity concentrations in uCi/cc.
Refer to RPP 7.4,
" Airborne Radioactivity Surveys".
c.
Surf ace contaa Mtion in dpm/100 cm2 Refer to RPP 7.3,
" Radioactive Cc :. amination Surveys".
d.
Location of survey.
j I
e.
Date and time of survey.
l f.
Identification of the monitoring team members.
s g.
Illitials of the individuals recording the data.
i h.
Readings of pocket dosimeters worn during the survey by team members.
i.
Pertinent observations by monitoring team mebmers including i
physical hazards, i
4.5.3 The Emergency Monitoring Logs and any other pertinent notes shall be provided to the OSC Supervisor upon returning to the OSC. This information shall then be forwarded to the Site Radiation Protection Coordinator.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.1 Page 7
of 8 ONSITE RADIOLOGICAL MONITORING Revision 2 Date - 3/1/82 t
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan 5.2 Corporate Emergency Response Plan 5.3 Radiation Protection Procedures (RPP 2.1, 7.1, 7.2, 7.3, 7.4, 8.1, 12.1, 13.1) j 6.0 ATTACHMENTS 1
Emergency Monitoring Log APPROVED BY:
Ob REVIEWED BY:
/
b vb fpt Chief Engineer Chatrman, Operdtions Committee APPROVED BY:
v0A 4
g es., at,on e,ot.c,7,,/nen,,ne.,
l O
I
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP
- 3.1 Page 8
of 8 ONSITE RADIOLOGICAL MONITORING Revision 2 I
Date - 3/1/82 ATTACHMENT 1 EMERGENCY MONITORING LOG I
I i
MONITOR I
!RADIATICNLEVELS IAIR30RNEl SURFACE TEAM REMARKS (INCLUDE l0 PEN CLOSED
' ACTIVITY'CONTAMINATIONj POCKET MONITOR OSSERVATICNS MADE BY (uCi/ccl. (dom /100cm2)) DOSIMETER' TEAM CONC.
LEVELS i READINGS!MEM3ERS l EVACUATED OR MO OATA CATE TIME LOCATION
+ WIN 304 WINDOW I
l mR/hr mR/hr ING PERSCNNEL)
' RECORDER i
l l
l l
1 I
l t
1 I
I i,
-m I
l l
l i.
i-.
.d ~_
t j
y I
I 1
I
.I 1
1 1,
I i
i e
i
-d__.~
o i
l l
l I
~
I l
i 1
I l
i i
i i
l l
i i
i l
i i
l i
l l
l l
?
?
l l
l i
l i
i
?
?
f Survey Instruments Used Serial No.
i
EMERGENCY PLAN' IMPLEMENTING PROCEDURE EPIP - 3.2 Page 1
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 Date - 3/1/82 1.0 PURPOSE This procedure provides instructions for performing offsite radiological monitoring of the environs during an emergency.
2.0 APPLICABILITY This procedure applies to offsite radiological monitoring personnel'during a potential or actual release of radioactive materials to offsite locations.
Off-site surveys are expected to be performed for any event classified as a SITE or GENERAL Emergency but may be performed during events classified lower.
3.0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinator 3.1.1 Fulfill responsibilities of the Radiological _ Assessment Coordinator j
until the EOF is manned.
3.1.2 - Instruct and direct the_0SC Supervisor to prepare and dispatch the radiological monitoring teams to offsite locations.
i i
i
_L 3.1.3 Coordinate with the Radiological Assessment Coordinator to determine the need for followup offsite monitoring.
3.2 Emergency Coordinator 3.2.1 Authorize offsite radiological monitoring activities.
l 3.2.2 Initially provide protective action recommendations until the EOF is manned.
3.3 Radiological Assessment Coordinator 3.3.1 Direct and coordinate offsite Radiological Monitoring Teams.
l-3.3.2 Evaulate data from monitoring teams.
3.3.3 Provide recommendations to protect the population-at-risk.
l 3.3.4 Provide followup instructions for monitoring teams to continue surveillance activities, as necessary.
3.3.5 Perform dose assessment calculations.
l' 3.4 Off-site Monitoring Teams OV 3.4.1 Perform surveys at locations specified by the EOF, TSC or OSC.
Provide information to the EOF, TSC, or OSC as requested.
3.4.2 Periodically check dosimeters and evaluate exposure.
3.4.3 Document surveys and maintain a log of events.
[
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 2
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 Date
.3/1/82 4.0 INSTRUCTIONS 4.1 Notification and Mobilization of Radiological Monitoring Personnel 4.1.1 Upon activation of the DAEC Emergency Plan, radiological monitoring personnel will be notified as outlined in EPIP 1.2, " Notification of the Emergency Response Organization and Offsite Support Agencies".
4.1.2 Radiological monitoring personnel will report to the Operational Support Center (OSC).
4.2 Assignment of Personnel to Offsite Radiological Monitoring Teams 4.2.1 Personnel arriving at the OSC shall remove tags in sequence according to qualifications, report to the OSC Supervisor and'begin implementing their specific duties.
Refer to EPIP 2.1, " Activation j
and Operation of Operational Support Center".
i 4.2.2 Other emergency response personnel, not assigned OSC tagboard duties, shall report to their emergency response stations or to the OSC Supervisor and inform-him that they are prepared to assist as needed.
4.3 Initial Actions Following Activation of the DAEC Emeraency Plan 4.3.1 The Site Radiation Protection Coordinator shall report to the TSC.
He will evaluate the plant radiological conditions and determine if a release to the environment has occurred or could occur.
l 4.3.2 The Site Radiation Protection Coordinator shall estimate the downwind airborne activity and perform dose assessment calculations. Refer to EPIP 3.3, " Dose Projections".
The OSC Supervisor shall be informed of projected airborne activities and dose assessments.
4.3.3 The OSC Supervisor will prepare to dispatch monitoring teams to downwind locations. The teams should be briefed on wind speed, wind direction and the location of the projected maximum airborne activity concentrations as soon as the information is available.
4 4.3.4 Each team shall arrange for transporation and ensure that the vehicle is fueled and functioning.
Keys for vehicles and gas pumps are available at the Security Control Point. Team members shall source check portable instrumentation prior to leaving the OSC.
i 4.3.5 Each team shall establish communications with the TSC, OSC, or the E0F, as appropriate.
The Radiological Assessment Coordinator will assume control of the off-site monitoring teams when available.
The i
DAEC Security / Radiological Radio System will serve as the primary means of communications.
l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2
)
Page 3
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 Date - 3/1/82 4.3.6 Each team shall ensure that all supplies required by the tag board assignment are loaded into the. vehicle. TLD's and dosimeters shall be worn.
4.3.7 The Site Radiation Protection Coordinator or the OSC Supervisor shall notify the Security Shift Supervisor that offsite monitoring teams may be leaving the site.
4.3.8 The Site Radiation Protection Coordinator shall obtain authorization from the Emergency Coordinator prior to initiating offsite monitoring.
4.4 Offsite Surveys 4.4.1 Team members shall proceed to offsite locations as directed by the OSC, TSC, or EOF, as appropriate.
Survey instrumentation shall be used to determine if the team enters the plume. Attachment 1 or a similiar map should be used to plan the travel route to the assigned location.
Report arrival,at the location to the TSC, OSC, or EOF, as t
appropriate.
O 4.4.2 Precautions for off-site team members V
4.4.2.1 Periodically check pocket dosimeters.
Record dosisaeter readings and time on Attachment 2.
4.4.2.2 Do not exceed established radiation exposure limits (ie: 300 mrem / day) unless authorized by the Emergency Coordinator.
4.4.2.3 Perform a radition and contamination survey on the vehicle i
after exiting the plume.
4.4.2.4 Prior to entering the plume, don protective clothing and respiratory protective. devices.
4.4.2.5 When taking low volume air samples, leave the vehicle running. Take dose rates on the radiator and air cleaner.
Minimize exposure to potentially high dose rate components.
4.4.2.6 Mark data and sample locations on the map.
Project dose lines and plume path if possible.
4.4.2.7 Labels similiar to Attachment 3 shall be utilized to-identify samples and sample locations.
4.4.2.8 If the vehicle becomes heavily contaminated, it may be necessary to leave the vehicle to obtain accurate survey
(
data.
l 4
~
I EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP
- 3.2 Page 4
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3
( 'l Date - 3/1/82
\\_ /
4.4.2.9 Dose rates on the vehicle may require that the vehicle be abandoned.
Notify the EOF of the condition and receive instruction on actions to be taken.
4.4.2.10 Take actions as necessary to minimize the contamination of survey equipment.
4.4.3 Determining Presence of the Plume 4.4.3.1 Observe survey instrumentation; increasing count rates or dose rates will indicate the presence of the plume.
4.4.3.2 Take open and closed window surveys.
For the E-140, put hand over the window for closed window surveys.
4.4.3.2.1 A high open/ closed window ratio indicates that the team is in the plume.
4.4.3.2.2 A low open/ closed window ratio indicates that the plume is overhead or is approaching the team.
(~'}
4.4.3.3 Record surveys in accordance with section 4.5.
Report dose
(_ /
rate information and location of the plume to the E0F via radio.
4.4.4 Air Sampling (Low Volume Samples) 4.4.4.1 Load the air sampler with appropriate filters.
Use Silver Zeolite cartridges when obtaining low volume air samples.
4.4.4.2 Perform a radiation survey on the radiator.
4.4.4.3 Raise the hood on the vehicle.
Leave the vehicle running.
4.4.4.4 Connect the air sampler to the battery.
Ensure red lead goes to the positive terminal.
4.4.4.5 Turn the air sampler "0N".
Take precautions to prevent contamination of the sample.
The sampler should be held approximately waist high.
4.4.4.6 Obtain a 1, 5 or 10 cubic foot air sample.
If dose rates are low, obtain a 10 cubic foot sample.
If dose rates are high, obtain a 1 cubic foot sample.
4.4.4.7 Record date and time on, sample location, sampler flow rate, rs date and time off and technicians name on a label similiar to (s).
he is a
mii
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 5
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3
(]
Date - 3/1/82 v
4.4.4.8 Remove the sample from the sampler. Take precautions to prevent contamination of the sample.
Put sample in a plastic bag with the label attached.
Seal the bag.
Position the sample in the truck to minimize exposure.
4.4.4.9 Notify the TSC, OSC or E0F of completion of air sample and current radiological information.
Request further directions.
4.4.4.10 When background permits, evaluate the silver zeolite cartridge with a portable survey meter.
Determine the air activity using either an E-140 or an open window R0-2.
Compare instrument readings and volume to values on.
Report approximate airborne activity to the EOF, OSC or TSC.
4.4.4.11 Deliver samples as directed by the EOF.
4.5 Documentation of Radiological Monitoring Data 4.5.1 Radiological monitoring data gathered at the offsite areas shall be a
recorded in the Emergency Monitoring Log (Attachment 2).
t
)
4.5.2 Entries shall include the following information, as applicable:
u a.
Radiation levels in mR/hr or R/hr.
Refer to RPP 7.1, " Radiation Surveys".
b.
Airborne activity concentrations in "Ci/cc.
Refer to RPP 7.4,
" Airborne Radioactivity Surveys".
Surface contamination in dpm/100cm2 Refer to RPP 7.3, c.
" Radioactivity Contamination Surveys".
l d.
Location of survey.
l l
e.
Date and time of survey.
f.
Identification of the monitoring team members.
I g.
Initials of the individual recording the data.
l h.
Readings of pocket dosimeters worn during the survey by team members.
- i. Pertinent observations by monitoring team members including l p physical hazards.
l \\)
4.5.3 The Emergency Monitoring Logs and any other pertinent notes shall be
'~
provided to the OSC Supervisor upon returning to the plant. This information shall then be forwarded to the Site Radiation Protection Coordinator.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 I
Page 6
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 fS Date - 3/1/82 U
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan 5.2 Corporate Emergency Response Plan 5.3 Radiation Protection Procedures (RPP 2.1, 7.1, 7.2, 7.3, 7.4, 8.1, 13.1, 13.7) 6.0 ATTACHMENTS 1.
Area Map 2.
Emergency Monitoring Log 3.
Sample Label 4.
Air activity Chart for open window measurements at contact with a Silver Zeolite cartridge.
iQ 0
//,/
V i
(
APPROVED BY:
5'D'N b REVIEWED BY:\\
[ [ [ 2 vf,(b_
Chief Engineer Chhirman, Operations Committee 7L APPROVED BY:
/
M w Rad'iation PFotecty6n Engijper i
13 LJ
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 7
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 N
Date - 3/1/82
,'.._,r w
ATTACHMENT 1 AREA MAP
.. -s. ' --t - ; -.
r
- 1. W p.
w::m
... f.m4.m.. ~... ' Q:
[,.9 ).., p; q; _.,.
g
.i g.:.:,:.s..m;-:r r,
.,.... is.,Q,.we. N. G4i,:&.
d_,: <=...,f. I e
G.* n..
p a
' f
.:.5.
Q.
. _ _.. i', '. -
+
c 4
.x 3.
,.,,. ; _, m-.
.~
p-n u
- =g'--
w+_,5w_a.. a,.
t
...r,,.,
.e
.+- _s_
,e a;,
,____,y. vw qu c.
t.
.r 3-[/j.e:-i"ilW.
1
. w_.:
- L'
-[
JJ{." 3.i.g
.'.1_ q--, *ip a L j- ).Lu, x-- _h,y-
.[
4 4-
... - h..
y
= 4,-w*.--'!.. v +M.~.
1:::aV,.
., kg ag.
4 1
+
.:2. to... :- '
d'
-- /- 's. y'--~$j.
' ff:',.
.,.. h, ?. ;' D..; K t---
- w 7
am q,,.:fi,. 7,, < L.t.. -42 l..' 3 '_
T i
7e 3
.,.y,y*7
~y '
... yf j p' P, nN,,
'!i.$iI.e<ih.I-
- NJ;-d 7
.:. '[:- _(._
N N d A'U E,j g, @tn,9-E[
/ _.
i r :. i d,,N9.
1.. ?
wt 0
-~
P W v%.e, c;;.c.r... t.,,r.;..
3 m...
i w
,..7 N.
g 4
(~
5'
~
-u
~*
, ~ j; i:v..
_ /.3/ g' ' I..
J: y*,3_.
- , d,.. % p. c __ p..
- ,,,[M. %l; yq o
- W( J -s;.69T \\.,;.
_y N
v I.
P-.
~ ~.ji!N7
)p.%
1 m.q;& ~k l
4 f/
.,.._. p-X-.s. + 4 - ).
v-
, V:;s; -
3 h. <.s.-.
r
..,yl'
%.?.f.)~~Eg,p.a.-j ;) W ..,-. 'Mi%qW
?-7~"...
.e m
+J
.T
\\ '.
- {w ]T.,, 4r,, '
- E.
- ,r;.s '
\\_ _ _ =
,' e Ke n s m g % 4;' Q-L \\.;..,.,.. e s, e. j-
--gy h \\
i yp,
ip.:
...p.e>
.g>4 +.
. l;, ;.,.,, g.'t -
- . - ' -( ::1,im '
y-r---*, p. -(~
..l.
,;p -
. Q /.,y., - T.....,. sf. Y'~P
/
- l..
.y., J:-
i'..
=,
a.
f,f~ T.;t. -N e
t
-~'n y.a
- a.. ".
+.,:.,::
. ',me. %.__.a_, r...%-' w:..a..
.a -,#*
y }
. '" "Jb-_._.., -
\\*.-
1 9
a s-
.., p
- m.. f.
' v..
1 N sm,1 h, -
y.v?+
r-
. P.
.z s
- u
!. n-i f. {i (i, i '.?,. ;.2$C$r..,..
, w)' h y b H.
a.'.. a e. f ' J Etl
. I:. :. :f,.8 n
. s..~.n m.-
A
.. e w
+
. m.~.
, r.
w..
pv :..
i c
. + p,., *E. ~,n r,.
,.,,--w.
,~n.
2
~d. &
s W,~. N. ;Q. M' r.l m"r a.,W4_. m. -
b.c d'^,yt.u $v%
c - e
.,~.i. W n - 71 i
.n.
y,. ee.p
.. m,*:
- % f,:.:. -..
~
Qd:., y.%&V. { '> ' +
> l =>
.;.g'.+;
,m v.
G3.__]Q J T.QJf $; QQ AQ; gi:[. ~M.-eQ $
j.
,-- Y r
t.
~-
i p.,-f-l-4.
,b..
. v. fqs}.;.Wy}f, j'$. - %s..
.e m..
.; 4; 7 f'-+
- i. x iv --!._. m t__.t,,. '.; m'
- N,4
- r. c n o _.J
- w. '
r., w-r.:
4_.
m y
, y,n.,5 = n.mX wp mc c Q. c. m.-a u,- g==, 1 m 3v e
.x..:
m.g.
g vm-r$ EL W % :.a %.7 #z V.s-
~:
. y.
3 b ri d c'y._ # g,-Mlm._
~ ~..
"W ' n ' :. " i_1 w "f
9
' M % K J.2 L. g G p y. M',.. " 1.g s -
.R. 2-yi %.
,D
'.l' q' Qe -,
m Wt c.
a L
. i... ?
~
,/
- l M., !,
$,. ' ' 'e h: 2,,;
[,,,",,,[, 2,_[.- *.
1,
.(
). h.
" "Y f-
' ' %f ' ~h-,'-
"4
' i t
3 L.
g g
.O
\\Q
.s/,. [g_ _'h c
. !. n.!
?
F$
q a
- 4.!
ic
+,
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP
- 3.2 Page 8
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 O
Date - 3/1/82
%/
ATTACHMENT 2 EMERGENCY MONITORING LOG t
l AIRBORNE l MONITOR RA3IATION LEVELS SURFACE TEAM
~REPARKS (INCLUDE l 0 PEN CLOSED-ACTIVITY' C0'lTAMINATIOri P0CXET MONITOR OBSERVATIONS FACE BY CATE TIME LOCATION
- WINDOW WItCOW C0r.C. '
LEV;LS DOSIMETER TEAM EVACUATED OR MONITOR-DATA mR/hr '
mR/hr g(uCi/cc):. (dem/100cm2)I READINGS MEMBERS lING PERSONNEL)
IRECORDER I
i g
i l
i l
k k_
l i
l i
I f
i i
l I
l l
i l
t f
l l
l I
I l;-
i I
Survey Instruments Used Serial fio.
'O,
,U
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 9
of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3
.Q Date - 3/1/82 V
ATTACHMENT 3 AIR SAMPLE SAMPLE LOCATION DATE/ TIME ON
/
DATE/ TIME OFF
/
SAMPLE FLOW RATE CFM SAMPLE COLLECTED BY O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 3.2 Page 10 of 10 0FFSITE RADIOLOGICAL MONITORING Revision 3 r%(v)
Date - 3/1/82 ATTACHMENT 4 Air Activity Chart for 6 pen window measurements at contact with a Silver Zeelite Cartridge. (Ci/m3 or uCi/cc)
E-140 or R0-2 COUNT COUNT COUNT RATE RATE RATE (CPM)
Ift3 Sft3 luft3 (CPM)
Ift3 Sft3 10ft3 (CPM)
Ift3 Sft3 loft 3 100 3.18E-8 6.36E-9 3.18E-9 5700 1.81E-6 3.63E-7 1.81E-7 23K 7.32E-6 1.46E-6 7.32E-7 200 6.36E-8 1.27E-8 6.36E-9 5800 1.85E-6 3.69E-7 1.85E-7 24K 7.64E-6 1.53E-6 7.64E-7 300 9.54E-8 1.91E-8 9.54E-9 5900 1.88E-6 3.75E-7 1.88E-7 25K 7.95E-6 1.59E-6 7.95E-7 400 1.27E-7 2.54E-8 1.27E-8 E000 1.91E-6 3.82E-7 1.91E-7 26K 8.27E-6 1.65E-6 8.27E-7 500 1.b9E-7 3.18E-8 1.59E-8 6100 1.94E-6 3.88E-7 1.94E-7 27K 8.59E-6 1.72E-6 8.59E-7 600 1.90E-7 3.82E-8 1.90E-8 6200 1.97E-6 3.94E-7 1.97E-7 28K 8.91E-6 1.78E-6 8.91E-7 700 2.22E-7 4.45E-8 2.23;-8 6300 2.00E-6 4.00E-7 2.00E-7 29K 9.23E-6 1.85 E-6 9.23E-7 800 2.54E-7 5.09E-8 2.55E-8 6400 2.04E-6 4.07E-7 2.04E-7 30K 9.54E-6 1.91E-6 9.54E-7 900 2.8CE-7 5.72E-8 2.86E-8 6500 2.07E-6 4.14E-7 2.07E-7 31K 9.86E-6 1.97E-6 9.86E-7 1000 3.18E-7 6.36E-8 3.18E-8 6600 2.10E-6 4.20E-7 2.10E-7 32K 1.01E-5 2.04E-6 1.02E-6 1100 3.49E-7 6.99E-8 3.50E-8 6700 2.13E-6 4.26E-7 2.13E-7 33K 1.05E-5 2.10E-6 1.05E-6 1200 3.81E-7 7.64E-8 3.82E-8 6800 2.16E-6 4.33E-7 2.16E-7 34K 1.08E-5 2.16E-6 1.08E-6 1300 4.13E-7 8.27E-8 4.14E-8 6900 2.20E-6 4.39E-7 2.20E-7 35K 1.11E-5 2.23E-6 1.11E-6 1400 4.45E-7 8.91E-8 4.45E-8 7000 2.23E-6 4.45E-7 2.23E-7 36K 1.15E-5 2.29E-6 1.15E-6 1500 4.77E-7 9.54E-8 4.77E-8 7100 2.26E-6 4.52E-7 2.2SE-7 37K 1.19E-5 2.35E-6 1.18E-6 1600 5.09E-7 1.02E-7 5.09E-3 7200 2.29E-6 4.58E-7 2.29E-7 38K 1.21E-5 2.41E-6 1.21E-6 1700 5.40E-7 1.08E-7 5.41E-8 7300 2.32E-6 4.64E-7 2.32E-7 39K 1.24E-5 2.48E-6 1.24E-6 h
1800 5.73E-7 1.15E-7 5.73E-8 7400 2.35E-6 4.71E-7 2.35E-7 40K 1.27E-5 2.54E-6 1.27E-6 V
1900 6.04E-7 1.21E-7 6.04E-8 7500 2.39E-6 4.77E-7 2.39E-7 41K 1.30E-5 2.61E-6 1.30E-6 2000 6.36E-7 1.27E-7 6.36E-8 7600 2.41E-6 4.84E-7 2.42E-7 42K 1.34E-5 2.67E-6 1.34E-6 2100 6.68E-7 1.34E-7 6.68E-8 7700 2.45E-6 4.90E-7 2.45E-7 43K 1.38E-5 2.74E-6 1.37E-6 2200 6.99E-7 1.39E-7 6.99E-8 7800 2.48E-6 4.96E-7 2.48E-7 44K 1.40E-5 2.80E-6 1.40E-6 2300 7.31E-7 1.46E-7 7.32E-8 7900 2.51E-6 5.03E-7 2.51E-7 45K 1.43E-5 2.86E-6 1.43E-6 2400 7.63E-7 1.52E-7 7.64E-8 8000 2.55E-6 5.09E-7 2.55E-7 46K 1.46E-5 2.93E-6 1.46E-6 2500 7.95E-7 1.59E-7 7.95E-8 8100 2.38E-6 5.15E-7 2.58E-7 47K 1.50E-5 2.99E-6 1.50E-6 2600 8.27E-7 1.65E-7 8.27E-8 8200 2.61E-6 5.22E-7 2.61E-7 48K 1.53E-5 3.05E-6 1.53E-6 2700 8.58E-7 1.72E-7 8.59E-8 8300 2.64E-6 5.28E-7 2.64E-7 49K 1.56E-5 3.12E-6 1.56E-6 2800 8.90E-7 1.78E-7 8.91E-8 8400 2.67E-6 5.34E-7 2.67E-7 50K
' 1.59E-5 3.18E-6 1.59E-6 2900 9.22E-7 1.8 5E-7 9.23E-8 8500 2.70E-6 5.40E-7 2.70E-7 51K 1.62E-5 3.25 E-6 1.62E-6 3000 9.54E-7 1.91E-7 9.54E-8 8600 2.74E-6 5.47E-7 2.74E-7 52K 1.65E-5 3.31E-6 1.65E-6 3100 9.86E-7 1.97E-7 9.86E-8 3700 2.77E-6 5.54E-7 2.77E-7 53K 1.69E-5 3.37E-6 1.69E-6 3200 1.01E-6 2.0*E-7 1.02E-7 8800 2.80E-6 5.60E-7 2.80E-7 54K 1.72E-5 3.43E-6 1.72E-6 3300 1.04E-6 2.10E-7 1.05E-7 8900 2.83E-6 5.66E-7 2.83E-7 55K 1.75E-5 3.49E-6 1.75E-6 3400 1.08E-6 2.16E-7 1.08E-7 9000 2.86E-6 5.73E-7 2.86E-7 56K 1.78E-5 3.56E-6 1.78E-6 3500 1.11E-6 2.23E-7 1.11E-7 9100 2.89E-6 5.79E-7 2.90E-7 57K 1.81E-5 3.63E-6 1.81E-6 3600 1.14E-6 2.29E-7 1.15E-7 9200 2.92E-6 5.85E-7 2.93E-7 58K 1.85E-5 3.69E-6 1.85E-6 3700 1.17E-6 2.35E-7 1.18E-7 9300 2.9 6E-6 5.92E-7 2.96E-7 59K 1.88E-5 3.75E-6 1.SSE-6 3800 1.20E-6 2.42E-7 1.21E-7 9400 2.99E-6 5.99E-7 2.99E-7 60K 1.91E-5 3.82E-6 1.91E-6 3900 1.24E-6 2.4SE-7 1.24E-7 9500 3.02E-6 6.04E-7 3.02E-7 61K 1.94E-5 3.88E-6 1.94E-6 4000 1.27E-6 2.54E-7 1.27E-7 9600 3.05E-6 6.11E-7 3.05E-7 67.K 1.97E-5 3.94E-6 1.97E-6 4100 1.30E-6 2.61E-! 1.30E-7 9700 3.08E-6 6.17E-7 3.09E-7 63K 2.00E-5 4.01E-6 2.00E-6 4200 1.33E-6 2.67E-7 1.34E-7 9300 3.12E-6 6.24E-7 3.12E-7 64K 2.04E-5 4.07E-6 2.04E-6 4300 1.35E-6 2.74E-7 1.37E-7 9900 3.15E-6 6.3.E-7 3.15E-7 65K 2.07E-5 4.14E-6 2.07E-6 4400 1.40E-6 2.79E-7 1.40E-7 10K 3.18E-6 6.36E-7 3.18E-7 66K 2.10E-5 4.20E-6 2.10E-6 (500 1.43E-6 2.86E-7 1.4 3E-7 11K 3.50E-6 6.99E-7 3.50E-7 67K 2.13E-5 4.26E-6 2.13E-6
% 00 1.46E-6 2.93E-7 1.46E-7 12K 3.82E-6 7.64E-7 3.82E-7 68K 2.16E-5 4.33E-6 2.16E-6 4700 1.50E-6 2.93E-7 1.49E-7 13K 4.14E-6 8.27E-7 4.14E-7 69K 2.20E-5 4.39E-6 2.20E-6 4800 1.52E-6 3.05E-7 1.53E-7 14K 4.45E-6 S.91E-7 4.45E-7 70K 2.23E-5 4.45E-6 2.23E-6 4900 1.56E-6 3.12E-7 1.56E-7 15K 4.77E-6 9.54E-7 4.77E-7 eMinr U 5I 5 T IE 6 Z. m -6 5000 1.59E-6 3.18E-7 1.59E-7 16K 5.09E-6 1.02E-6 5.09E-7 10aR/hr 3.18E-5 6.36E-6 3.18E-6 O) 5100 1.62E-6 3.25E-7 1.62E-7 17K 5.41E-6 1.08E-6 5.41E-7 12mR/hr 3.82E-5 7.64E-6 3.82E-6
('-
5200 1.65E-6 3.31E-7 1.65E-7 ISK 5.73E-6 1.15E-6 5.73E-7 15M/hr 4.77E-5 9.54E-6 4.77E-3 5300 1.69E-6 3.37E-7 1.69E-7 19K 6.04E-6 1.21E-6 6.04E-7 20rR/hr 6.36E-5 1.27E-5 6.36E-6 5400 1.72E-6 3.44E-7 1.72E-7 20K 6.36E-6 1.27E-6 6.36E-7 25mR/hr 7.95E-5 1.59E-5 7.95E-6 5500 1.75E-6 3.50E-7 1.75E-7 21K 6.6SE-6 1.34E-6 6.68E-7 30tR/hr 9.54E-5 1.91E-5 9. 54 E-6 5600 1.78E-6 3.56E-7 1.78E-7 22K 6.99E-6 1.40E-6 6.99E-7 50nR/hr 1.59E-4 3.18E-5 1.59E-5 USe R0-2 readingsi
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1
[T Page 1
of 12 PLANT AND SITE EVACUATION Revision 2 l
Date 5/13/82 1.0 PURPOSE This procedure provides instructions for evacuation to a safe assembly area and for accountability of personnel at the DAEC in the event of an emergency.
2.0 APPLICABILITY This procedure applies to DAEC, IELP, Contractor, and Visitor personnel within the site boundary in the event of a site evacuation.
Requirements delineated in this procedure shall be implemented for the occurrence of an event which may result in an emergency condition classified as an Alert, Site Emergency or General Energency (Evacuation may also be used for non-emergency g
accountabi1ity).
NOTE:
A Plant Evacuation is defined as evacuation of personnel from selectea ouildings or f acilities at the DAEC, where the evacuated personnel are reassembled at locations on the site.
o A Site Evacuation is defined as evacuation of some or all personnel trom the DAEC site to an offsite location.
3.0 RESPONSIBILITIES 3.1 Shift Supervising Enaineer:
Initiate the Site Evacuation Alarm for any event classified as an ALERT or greater.
The evacuation alarm may also be sounded for other events, at the discretion of the SSE.
Ensure onsite personnel are notified by an audible evacuation signal and that appropriate announcements are made on the plant paging system.
Account for all on duty shift operating personnel.
3.2 Emergency Coordinator Ensure that non-essential personnel are evacuated from the site for a Site or General Emergency.
i
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 2
of 12 PLANT AND SITE EVACUATION Revision 2 wg I
1 Date 5/13/82 U
3.3 Security Shift Supervisor Ensure all personnel are accounted for.
Control access to and from the site during evacuation.
Coordinate Access Points at the Control Room (CR), Technical Support Center (TSC), Contractor Change House, and Security Control Point as appropriate.
3.4 Operations Support Center Supervisor Organize and control evacuated personnel at the OSC and Contractor Change House.
Assist in accounting for personnel assigned to the OSC and the Contractor Change House.
4.0 INSTRUCTIONS 4.1 Plant Evacuation n
i
\\
4.1.1 The Shift Supervising Engineer (SSE) shall sound the evacuation alarm for any event classified as an Alert or greater. At the discretion of the SSE, the evacuation alarm may also be sounded for other events, such as:
a) an unusual Event which warrants evacuation.
b) other occurrences which require the evacuation of any l
part of the plant.
(Note that, for accountability j
purposes, evacuation of any area of the plant requires l
evacuation of the entire plant).
4.1.2 The SSE, based on his knowledge of the nature and location of the problem, shall consider safe evacuation routes for l
personnel in the plant so that they may avoid hazardous areas while evacuating. The evacuation announcement (see l
l 4.1.3 below) shall provide such information as necessary.
I NOTE:
Such evaucation routes may require use of doors which are normally sealed and alarmed, and which are not normally i
l available for routine entrance or exit.
Use of such doors for emergency evacuation will, of course, sound these
' h alarms.
Security personnel should recognize that such V
alarms may be expected during an evacuation.
l L
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 3
of 12 PLANT AND SITE EVACUATION Revision 2 t
Date 5/13/82 4.1.3 Upon completion of the tone alarm, the SSE shall announce I
the evacuation and provide further instructions on the paging system.
a.
The announcement over'the paging system should be as follows:
ATTENTION ALL PERSONNEL:
An ALERT / SITE / GENERAL emergency has been declared.
All personnel onsite shall evacuate to their designated evacuation centers.
(Provide additional specific instructions, as required.)
E 4.1.4 Repeat the tone alarm and paging instructions.
4.1.5 All onsite personnel shall proceed without delay to the l
following predesignated assembly areas, (see Attachment 1). Note that it is each employee's responsibility to heed v
any instructions given over the paging system regarding safe evacuation routes, and to act accordingly, a.
Predesignated personnel shall report to the TSC as per EPIP 2.2, "Activaticii and Operation of the Technical Support Center."
4 b.
All other IELP/DAEC personnel except the on-shift l.
operating crew and security personnel shall report to the OSC as per EPIP 2.1, " Activation and Operation of the OSC."
The on-shift operating crew will report to l
the Control Room and security personnel will begin implementing their assigned duties.
See " Security Shift Supervisors Checklist", Attachment 7 of EPIP 2.1.
c.
Contractors shall report to the Contractor Change House.
d.
Visitors shall be escorted to the Security Control Point.
Upon the visitors' exit from the Protected Area, the escorts shall then proceed to their assigned area.
e.
Personnel onsite but outside of the Protected Area will report to the Security Control Point.
EMERGENCY PLAfl IMPLEMENTING PROCEDURE EPIP 4.1 Page 4
of 12 l
PLANT AND SITE EVACUAT10tl Revision 2 Date 5/13/82 4.1.6 Personnel who evacuated the reactor building by way of alarmed doors shall report immediately (prior to reporting
)
to their designated area) to the OSC to be monitored, since they will have bypassed the portal monitor at Access Control. They shall also report to the Central Alarm Station (ext. 241) the location of the alarmed door by which they evacuated.
They shall then report to their designated assembly area for accountability purposes.
4.1.7 In the event that the OSC and Contractor Change House are i
not habitable, personnel assigned to those areas shall be y
redirected to the Offsite Relocation and Assembly Area (0RAA).
r i d d 4.1.8 If the TSC is not habitable, personnel designated by the 7j f Emergency Coordinator shall report to the Control Room.
E 4.2 Monitoring 4.2.1 Initiate radiation surveys and airborne sampling as directed by the Site Radiation Protection Coordinator to-determine habitability of the OSC and Contractor Chang'e (G
House per EPIP 3.1, "Onsite Radiological Monitoring."
LJ NOTE Radiation surveys and airborne radiation sampling of the TSC and Control Room will be conducted based upon an evaluation of instrument readings monitoring the general area and atmosphere in those locations. Follow-up sampling / surveying should be performed to verify f
h abi tabil ity.
4.2.2 Radiation monitoring of evacuated personnel will be performed per RPP 5.2, " Controlled Area Methodology".
4.2.3 In the event of a radiological release, personnel to be released offsite will be surveyed for radiological contamination prior to being released from company property. -This monitoring will be accomplished at the Controlled Access Point.
{
i i
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 l
l Page 5
of 12 I
l PLANT AND SITE EVACUATION' Revision 2 l
Date 5/13/82
[]
v i
NOTE i
i l
l If designi;ed areas are not habitable, personnel i
j radiolog 91 surveying will be accomplished at the offsite assembly area.
I 4.3 Accountability 4.3.1-Personnel accountability shall be performed to identify missing personnel as soon as possible-after implementation of EPIP 4.1, " Site Evacuation". Accountability should be j
accomplished within 30 minutes af ter the ~ evacuation alarm has been sounded.
Accountability shall be reported'to the Security Shift Supervisor, as follows:
a.
The Shift Supervising Engineer shall ensure shift operating crew personnel are accounted for and report to the Security Shift Supervisor.
~
b.
The TSC Supervisor 'shall ensure personnel -in the TSC are accounted for and report to the Security Shift i
n Supervisor.
[
V l
c.
The OSC Supervisor shall assist the Security Shift f
-Supervisor in accounting for personnel in the OSC and the Contractor Change House.
Other personnel may be designated to assist in accountability, as necessary.
I d.
Accountability of personnel shall be verified and/or
~
cross checked by the Security Shift Supervisor using the Badge Board located at the Security Control Point j
and the Emergency Assignment Board located in the hall 7
near the Security Control Point.
i e.
Results of the accountability survey shall be reported by the Security Shift Supervisor to the OSC Supervisor i
and the Security & Support Supervisor.
f.
The Security & Support Supervisor shall advise the Emergency Coordinator of the results.
j 4.3.2 In the event missing personnel are identified, initiate rescue ef forts in accordance with EPIP 4.3, " Rescue and Emergency Repair Work."
i r
L 4.3.3 If the evacuation was conducted due to a local radiation emergency, once accountability has been established, the l
Emergency Coordinator may release personnel to return to s
their normal work areas with the exception of the affected local areas.
t
~- -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 6
of 12 PLANT AND SITE EVACUATION Revision 2 l
Date 5/13/82 O
4.4 Security Access Controls 4.4.1 Shift security personnel shall make a tour of the property as authorized by the Emergency Coordinator, incluaing buildings outside the Protected Area.
a.
Non-IELP personnel found on company property will be escorted to the Security Control Point, surveyed for contamination and, if not contaminated, released from the site and escorted off company property.
b.
If contaminated, decontamination shall be as described in EPIP 4.2, "First Aid, Decontamination and Medical Support."
4.4.2 The Emergency Coordinator through the Security Shift Supervisor will coordinate access to the site with local law enforcement agencies.
a.
Local law enforcement agencies will establish access control points at predetermined locations to prevent unauthorized access to the site.
']
b.
The Security Shift supervisor will coordinate with the l
local law enforcement agencies, as required, to l
authorize personnel access to the site.
4.4.3 Shift security personnel shall set up access control points at the TSC, Control Room, Contractor Change House, and the locker room in the OSC as appropriate. Access to and egress from these locations will be controlled by Security Personnel in order to maintain accountability until personnel are released to return to work or sent offsite.
NOTE Access control points may be deleted at the discretion of the Emergency Coordinator.
4.5 Evacuation Beyond the Site Boundary (Site Evacuation) l 4.5.1 Evacuation of the site property for nonessential personnel may be required based upon:
l a.
Severity of the event - Nonessential personnel shall be i
evacuated for a Site or General Emergency unless f) radiological environmental conditions prohibit.
v b.
Habitability of assembly areas.
a EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 7
of 12 PLANT AND SITE EVACUATION Revision 2 Date 5/13/82 O
4.5.2 Evacuation of personnel from the site property will be authorized by the Emergency Coordinator.
4.5.3 If evacuation is required and authorized, it shall be directed by the OSC Supervisor and coordinated with the Security Shift Supervisor.
4.5.4 Evacuation from the site property shall be to the Offsite Relocation and Assembly Area (0RAA) at the Palo School Gymnasium facility unless otherwise directed by the Emergency Coordinator.
a.
If the radiological release rate and meteorological conditions are such that evacuation to the Palo facility is inappropriate, an alternate location shall be selected by the Emergency Coordinator based upon input from the Site Radiation Protection Coordinator.
A page system announcement will be made notifying evacuees of the alternate offsite assembly area.
b.
Activities at the ORAA shall be in accordance with, " Operating Procedures for the ORAA".
, h v
c.
In the evert that decontamination of personnel, equipment or vehicles is required, such efforts will be coordinated by the Site Radiation Protection Coordinator and conducted by Health Physics personnel as directed by the OSC Supervisor.
4.5.5 Evacuation from the site property shall be by the routes
(
shown in Attachment 2, using personal transportation.
a.
The south route from the plant will normally be used l
for site evacuation unless inclement weather, high l
traffic density or radiological conditions dictate use l
Of the northern route.
I b.
Security personnel will provide traffic control onsite.
c.
Accountability of personnel during evacuation shall be maintained.
4.5.6 An accountability check should be performed once personnel have arrived at the alternate assembly location. Personnel j
may then be released, or requested to stay, as necessary.
4.5.7 The ORAA will also be used, if necessary, as a staging area L
for assembling, briefing, and equiping personnel who are assigned to reenter the site following an incident.
l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 8
Of 12 PLANT AND SITE EVACUATION Revision 2 Date 5/13/82 g
'w)
5.0 REFERENCES
1.
Duane Arnold Energy Center Emergency Plan 2.
Iowa Electric Light and Power Company Corporate Emergency Response Plan 3.
Radiation Protection Procedures 6.0 ATTACHMENTS 1.
Onsite Assembly Locations 2.
Site Evacuation Routes t
3.
Operating Procedures for the Offsite Relocation and~ Assembly Area O
3'27'8k Approved by:
Date Chief Engineer O'O Reviewed by:
/
O Date
'i Uperations Gommittee Chairman
/
l l
Approved by:
d( W M Date r/e9/f e.
Operations Supervisor l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 9
of 12 PLANT AND SITE EVACUATION Revision 2 Date 5/13/82 ATTACHMENT 1 ONSITE ASSEMBLY LUCATIONS G
CPANGE !!CUSE CNSIE CCITITGR ASSCGLY AREA Technical Support
\\
Center
\\\\ g yyyyyyyyyg g gy/
m m mm
==as N
N y// ;y f
IccIss CCtr ^~
ENERGENCY RESPONSE TEAM TAG BOARD AND LOCKER s
~
_b~
p% '
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 10 of 12 PLANT AND SITE EVACUATION Revision 2 Date 5/13/82
' ATTACHMENT 2 SITE EVACUATION ROUTES
=
NORTH EVACUATION
$s s,
ROUTE s,
. NORM AL ROADBLOCK I
PARKING LOTS i
K I
o SWITCHYARD L
I DAEC l
o V
I N -SOUTH l*
EVACUATION ROUTE Y
(SITE SOUNDARY U
a' v
u OFFSIT E RE LOC ATION t
o A S S E M B LY AREA O
F---
\\
l I
O
_l bTOWN OF FALO
.i l
i I
b---
d l
HIGHWAY 94+
1
t EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.1 Page 11 of 12 PLANT AND SITE EVACUATION Revision 2 Date 5/13/82 g
G ATTACHMENT 3 OPERATING PROCEDURES FOR THE OFFSITE RELOCATION AND ASSEMBLY AREA The Offsite Relocation and Assembly Area (0RAA) is a facility which will be used to l
relocate and reassemble people from the DAEC in case of a radiological emergency which requires evacuation.
The ORAA is located at the former gymnasium in Palo, about 21/2 miles southwest of the plant. The building and about six acres of land around it will be used as required for personnel and vehicle assembly, monitoring and accountability.
The building floor plan is shown in Figure 1.
Both the building and the land are normally used by the public for various purposes, however, during a site emergency, these uses would be temporarily superceeded by DAEC for use as the l
ORAA.
l The ORAA will be staffed by a senior management representative designated by the Emergency Coordinator. This representative will be assisted by one or more Health Physics technicians designated by the Radiation Protection l
Coordinator.
I Evacuating vehicles will
.aach the ORAA from the north. A security guard
(
or o.ther traffic control officer (s) will be stationed at the north end of the l
V] ORAA lot to direct vehicles into the ORAA, and to prevent unauthorized vehicles from outside from going north on the county road toward the plant.
A check point / monitoring station will be set up at the northwest corner of i
the CRAA ~ property. At this station, a security guard will check in and record the names of personnel from the olant. Vehicles will be monitored and directed to clean or contamined parking areas as appropriate. Contaminated vehicles will be held in the contaminated parking area until the contamination has decayed to levels acceptable for release.
People will be directed into the gymnasium through the door on the NE corner.
They will be monitored at the door (outside if weather permits, inside in case af inclement weather). Those found to be clean will be directed to the clean area on the south side of the gymnasium. Those showing contamination will be hanoled as follows:
- 1. If contamination. is on the clothing, the contaminated clothing will be removed (to the extent modesty and temperature permit) bagged and tagged with the owner's name.
If the person is then found to be clean he will be directed to the clean waiting area.
l
- 2. If remaining clothing, or the individual himself, is found to be contaminated, he will be decontaminated to the extent possible using paper towels, waterless hand cleaner, etc. and provided with clean temporary (S
clothing (e.g., coveralls). When adequately decontamined, he will be
, ()
directed to the clean waiting area.
M
/^;.
j 1
EMERGENCY PLAN IMPLEMENTING' PROCEDURE b "'
EPIP 4.1
,,i
~'
Page 12. of 'l2 PLANTANDSITEE(Ab4T'I0f Revision 2 Date 5/13/82 7,
&I l
s
' ATTACMEE '3 [ Continued) 3.
Personnel will be decontaminated only,to tt'.e, extent necessary to f acilitate their transport to the offsite decontaninition :f acility, if further decontamination is neaded.
'/
4.
Af ter decontamination, personnel will be released to go home or to return'to their assigned duties, as directed by the Emergency Coordinator or his designated representative.
Dosimeters will be collected from all evacuate.d personnel, and exchanged for those who will return to the plant.
Copies of the" Personal Stdtement Concerning Incident" form (Attachment 5, EPIP 2.1) uill be distributed to all evacuated personnel, if appropriate, and the completed copies collected before the personnel are released.
Kitchen f acilities are available at the ORAA to feed personnel who may need to remain there for extended periods.
WSI guards will maintain security at the O'RAA as requested by the senior management representative.
The Security Shift Supervisor will ensure that
(~^, the designated personnel have evacuated the plant and are accounted fcr at V the ORAA prior to being released cr reassigned to duties at the plant.-
'i The following supplies will be maintained at the ORAA for use during an emergency:
Magenta and yellow rope or ribbon i
Radiation signs Large plastic bags Masking tape Barrels / trash cans R/S stickers, tape Self reading dosimeter and chargers Public address system Ballpoint pens Felt pens Flashlites Kimwipes Tablets / clipboards Notebooks Forms
" Personnel Statement Concerning Incident" Survey Forms Rolls Visoueen O
First aid supplies
(,/
KI tablets Waterless skin cleanser Washcloths & towels Spare clean clothes (paper or cloth coveralls)
Swipe Papers
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5
~
Page 1
of 7 ADMINISTRATION OF P0TASSIUM 10DIDE (KI)
Revision 0
Date 5/13/82 O
1.0 PURPOSE 1.1 This procedure provides guidance for recommending and supervising administration of potassium iodide (KI).
2.0 APPLICABILITY 2.1 This_ procedure applies to onsite emergency workers whose estimated total absorbed dose to the thyroid, from inhaling airborne radioiodine, could exceed 10 rems.
3.0 RESPONSIBILITIES 3.1 Site Radiation Protection Coordinator 3.1.1 Verify that personnel who may require administration of KI have completed Attachment 4, " Medical Questionnaire: Iodine Sensitivity".
3.1.2 Make recommendations to the Emergency Coordinator for administration of KI.
()
3.1.3 Supervise the administration of KI.
3.2 Emergency Coordinator 3.2.1 Authorize the use of KI when deemed appropriate.
4.0 INSTRUCTIONS 4.1 Prerequisites 4.1.1 During the course of General Employee Training (GET), all onsite personnel shall complete Attachment 4, " Medical Questionnaire:
Iodine Sensitivity."
l l
a) These questionnaires shall be reviewed by the Radiation Protection Engineer and, if the response is satisfactory, approved.
b) The IELP radiologist should be consulted regarding any questionable responses indicated on the questionnaire.
Note The steps in paragraph 4.1.1 above may not always be possible prior to administration of KI.
In such cases, these steps should be taken as soon as possible afterwards.
. O
~-w--
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 Page 2
of 7 ADMINISTRATION OF POTASSIUM 10010E (KI)
Revision 0
~3 Date 5/13/82 (O
4.1.2 An adequate supply of KI shall be stored in the First Aid Facility located in the Operational Support Center.
In addition, each off-site monitoring team will be provided with a bottle of KI tablets.
a) KI has an approved shelf-life with the expiration date listed on each bottle.
b) To ensure that the KI supply is valid, these dates will be inspected during the inventory of the first aid room, the emergency cabinets and the bottles replaced as necessary.
4.2 Criteria for the administration of KI: The Site Radiation Protection Coordinator shall administer the distribution of KI in the following manner.
4.2.1 If there is reason to believe that an individual's absorbed dose to the thyroid, from the inhalation of radioiodine, might exceed 10 rems, the individual should be immediately considered for a dose regimen of KI.
Note b
Doses to the thyroid, from the inhalation of radiciodine, can be V
estimated using Attachment 2, " Occupational Dose from Inhalation of Iodine-131".
4.2.2 The Site Radiation Protection Coordinator shall review the employees " Medical Questionnaire - Iodine Sensitivity" for each pros",etive KI recepient, where possible, and obtain the approval of the Emergency Coordinator prior to administering KI.
Iodine questionnaires are maintained in the employees " Personnel Exposure Record" file folders.
4.2.3 Distribute KI to appropriate onsite personnel, a) A copy of Attachment 1, "The Food and Drug Administration Approved Package Insert," shall accompany each bottle of KI issued.
Dosage schedules and other pertinent information are outlined on the package insert and should be followed closely.
b) Prior to taking KI, plant personnel should read the Food and Drug Administration apprcved package insert (see ).
c) Personnel shall be issued only one tablet initially.
n
(#)
4.2.4 The issuing party shall complete Attachment 3, " Potassium Iodide Issue Report" for each person issued a tablet of KI. A copy of this report shall be routed to the Site Radiation Protection Coordinator.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 Page 3
of 7 ADMINISTRATION OF POTASSIUM I0DIDE (KI)
Revision 0
(^'
ate 5/ 3/82 N.
4.3 Follow up Actions: The following actions should be taken to ensure proper treatment.
4.3.1 Those plant personnel who begin therapy shall be referred to the Medical Director for continuation of the 10-day course of KI unless their thyroid dose is determined not to have exceeded 10 rem. Continuation of the KI, after the first tablet, is normally not necessary unless the persons dose exceeded 10 rem.
4.3.2 If exposure of 10 rem or greater has occurred, a licensed radiologist should be consulted as soon as possible.
5.0 REFERENCES
5.1 Duane Arnold Energy Center Emergency Plan 5.2 Iowa Electric Light and Power Company Corporate Emergency Response Plan 6.0 ATTACHMENTS 1.
The Food and Drug Administration Approved Package Insert 2.
Projected Cumulative Doses to the Thyroid 3.
Potassium Iodide (KI) Issue Report 4.
Medical Questionnaire:
Iodine Sensitivity APPROVED BY:
f DATE S' Ub2-Chief Engineer REVIEWED BY:
l
.C
' 61 DATE (
Operations pmmittee Chairman l
APPROVED BY:
- f r/ !,/y
DATE i d
?'>
ReiatlonProtec onEngneer pa
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 Page 4 -Of 7 ADMINISTRATION OF POTASSIUM IODIDE (KI)
Revision 0
g Date 5/13/82 ATTACHMENT 1 THE F000 AND DRUG ADMINISTRATION APPROVED PACKAGE INSERT
..*. f A*
1 p.s.e c..t... in..,s rer HOW POTASSIUM ICDIDE WORKS
,J Certa.m forms ofiodine help your thyroid gland work right. Most people get the iodino they need from foods, bke iodized salt or fish. The thyroid can " store
- or hold only a certain amount of i*.-
THYRO.BI'CCK *
' di^'-
f * /*-
In a radiation emergency, radioactive iodine may be released in 6
spopssiuu ico 0E) the air. This matenal may be breathed or swsunwed. It may g, enounces pot TASS e wm EVE *Mfvedl enter the thyroid gland and damace it. The damere would pro.
f.co<emies an l
baQ not show itself for years. Chddren are most hkely to have i
TAstETS ano SCLUtLOM U.S.P.
thyrosd damage.
If you takd potassium iodide. it wiu fill-up your thyroid gland.
This reduces the chance that harmful radioactsve iodine wd1 TAkE POTAS$!UM l'ODIDE ONLY WHEN PUBLIC.
}
enter the thyroid gland.
' IICALTit OFFIC!ALS TELL YOU. IN A RADIATION
! ESIERGCNCY. R A DIO ACTIVE !ODINE COULD BE WHO SHOUI.D NOT TAKE POTASSIUM IODIDE
! RELEASED INTO Tile Aln. POTASSIUM IODIDE (A
%e only people who should not take potassium iodide are peccie
.' FORhl CF IODINE) CAN HCLP PROTECT YOU.
who know they are auergic to iodide. You may tske posassium iodide evenif you are takmg medicmes for a thyroid prooiem tfor
' IF YOU ARE TOLD TO TAKC THIS MEDICINE.TAKE IT example a thyroid hormone or antithyroid drugt. Prem. ant at:d
! ONE TIME CVEltY 24 HOUltS. DO NOT TAKE IT MORE nursing women and babies and chddren may siso take inss drug.
i OFTEN. MOttC WILL NOT IICLP YOU AND MAY IN.
CREASE TILE RISK OF SIDE EFFECTS. DO NOT TAKR HOW AND WHEN TO TAKE POTASSIUM IODIDE j Tills DifuC tr YOU KNOW YOU ARC ALLERGIC 70 Potassium lodide should be taken as soon as possib'e afJer
'OulDC. (SCE SIDE EFFCCTS UCLOWJ public hestth officials ten ycu. You should teke one cose rverv ;t hours. !.h 41 nct heip you beesuse the thyroid can "ho:d" on.
ly litnited amounts of iodine. Larger doses wid increase the ri*k of side effects. You will probably be told not to take the drug for more than 10 days.
INDICATIONS SIDE EFFECTS F IIYRO!D DLCCKING IN A IIADIATION EMERGENCY UsusDr. side effects of potassium iodide happen when people
. %Ly, take higher doses for a long time. You should be careful not to DIRECTIONS FOR USE take more than the recommended dose er take it for Icoger snan de only as ilitected by State or local public health authorities in you are told. Side effects are urdseiy because of the low cosa and She event of a radiation emerCency.
the shott time you wd1 be takmg the drug.
Possible side effects include skin rashes, swelline of the salivery DOSg i rab! cts:
AD'ULTS AND CHILDREN 1 YEAR OF glands, and " iodism"(metsuic taste. burning mouth end throet, sore teeth and gums. symptoms of a head coid, and sometimes ACE OR OLDER: One (1) tablet once a stomach upset and diarrheat.
day. Crush for sn au cMdren.
BAUIES UNDER 1 YEAR OF AGE:
A ge,, people have en eUergic reaction with more serious symp-One hall (U21 tablet once a day. Crush tems. These cedd bw fever and joint psins. or sweuing ol psrts of first.
the face and body and at times severe shortness of breath requit.
Ing immediate medical attention.
Selvtlen:
ADULTS AND CHILDREN 1 YEAR OF ACE OR OLDCR: Add G drops to one-Taking lodide may rarely cause overactivity of the thyroid
,,holf glass of hauid and drmk each day.
gland, underactivity of the thyroid gland or enlargement of the" DAUIES UNDER 1 YCAR OF AGE:
thyroid gland (gester).
Add 3 drops to a small amount of liquid once s day.
WHAT TO DO IF SIDE EFFECTS OCCUR F.cdis c,f,,,mc T fic for to days unless directed otherwise If the side effects are severe or if you have an auctee resetion.
h State ur html puhhs lismisla nut!.oricks.
ago, g,ggne p g.,,ium iodido. Then. if possible, cau a,soctur or More at controtted rowm temperaturu between 15* and.10*Cl50' public health authority for instructions.
to Km. Iteep cant ner tightly c!nwd as I protnt fram heht.
IAa *vt uvo time soluuu.i nf 6.ppears brownish m tho noaalc of the HOW SUPPt.!ED Imatie.
TIIYRO-DLOCK" TA UI.ETS (Potamum fodide. U.S.P.) bot-Lles of 14 tablets (NDC 0037 047240.3 Each wrute. roand, scored WARNING tables contains 130 mg potassium iod.de.
tsesse.
.m fiJe Anot.f ou, ty
,,,f f,ppe,f,/,,ft,.cric to iodide.
TIIYRO.ULOCKm SOf.UTION (Potassium lodido Solution.
o.
'I tast ael the reesh of clui.irein. In gass of overdose or euergic U.S.PJ 00 mlil fl. os.)lin:ht resistant, measured drop dispensing bon, contact a phyncian or the pubhc hvalth authority.
units (NDC 0037 43745). Each drop contains 21 mg potassium g
E**h IlYttO ill.CCK T 13 contains 130' mg of o, fon,
8le sm'u, h d e0 of TllYRO ut.OCK" sot.UTION cantains 21 mg of CARTER W A LLACE. INC.
ne madede.
Ceanoury. Now hrser cass2 i
1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 Page 5
of 7 ADMINISTRATION OF POTASSIUM IODIDE (KI)
Revision 0
Date 5/13/82 ATTACHMENT 2 PROJECTED CUMULATIVE DOSES TO THE THYROID t o' -
s 7-N' x
-e N
N l4..i 6
...it.
~
\\
\\1 1 ! !!
t i
1 '
I 4, \\ \\\\
lllladult i l
ll l
\\ \\ \\ llll'""*
l ll l
\\
n IdJ$#
'\\
\\
\\
N l
2' l'
-3 k,.
-go N
\\ \\
l 3p-s s
s t
-r l
7-N
- . 'x
~
5 l
x x
v
....- x,. x........
\\
\\'
\\
N
\\ ' '
Il' I
4.
\\
\\
l'N l N?l\\l lNl I l lll eMild 1 l
(
\\
\\ llM \\ \\ Nlll 2-N' N
N
{ K r \\
N
'i l,,
=- to
- i s N s
. N N
i,s 2
x s
s y
3 4 lo -
=
0 1
.'s J
7-s s
g A
N.
.N. it
>! NJ
.N.
I s
...__.N.
N' s
.N N I
'N I N1
\\a. !
\\ t i
\\'
V N
4 g
I, \\ \\ I N. I l\\ Is%.1 \\ l \\ l l l'N !
N*l \\
-- 2 y
\\\\
i
\\l lll
\\
'\\ \\ x I x "'g x s
2-
- -1o-5 i s
l
\\
\\
\\\\
\\
-^
lo -
-l..
8 n
~
s
.N
...s, is
.y m_.
v.
.x
(
N oitiN-
\\
N1, Ns s N Ni
~
1 IMll \\ l\\ i \\ 1 l hj l % i\\
! lhN h k h llN.N j
8' i
\\\\
\\ \\
-,-10 l
N N ^.s I
, N
- -7 10* -
7-4 e..
y.
is y.
s, l
l { e { t j ti e
i e i N(ff4 V.
T 4 i 6 464.
e
.4 e. gg
([ y l
To USE THIS C1tAPM' Plot the point representing the espesure f ll l\\
l 2-. rate or concentration and exposure time and estimate the projected thyroid dose
\\
" 10 ;
C
\\
by tacerp.12tton.
,,.1_
y t
_,, io o.1
.2
.4
.6 1.0 2
e e
10 20 30 i
paoactta tmsuas rm oeuasi -
4.; Projected thyroid do.e as a function of either l
gamma exposure rate, or radiciodine concentration in air and the projected exposure tirne.
,.-a,
I EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 Page 6
of 7 ADMINISTRATION OF POTASSIUM IODIDE (KI)
Revision 0
Date 5/13/82
)
1 ATTACHMENT 3 POTASSIUM I0DIDE (KI) ISSUE REPORT PACKAGE l
SOCIAL SECURITY TIME OF TIME OF INSERT l
NAME NUMBER EXPOSURE ISSUE ISSUED ISSUED BY l
l
{
t I
l l
lO O
l L
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 4.5 Page 7
of 7 ADMINISTRATION OF POTASSIUM I0DIDE (KI)
Revision 0
Date 5/13/82 ATTACHMENT 4 MEDICAL QUESTIONNAIRE:
I0 DINE SENSITIVITY Name First Middle Last 1.
Have you any known allergies?
If so, please describe below the severity of the allergy and I
I I
I medications taken, if any.
Yes No 2.
Are you able to eat seafood and shellfish without synptoms of stomach or bowel upset I
I I
I Yes No or skin erruption?
If not, please explain.
3.
Has any physician told you that you have a i
sensitivity to iodine?
U Yes U No 4.
Have you ever had a gallbladder dye test, kidney x-ray requiring dye injection, thyroid q Yes j
j No isotope scan?
If so, any reactions:
j j
j j
Yes No 5.
Explanation:
1 l
l Signature Date Card / Badge Number O
Reviewed by:
Date Radiation Protection Engineer
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 1
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 1.0 PURPOSE This procedure provides instructions for maintaining those f acilities, equipment and supplies required to support activation and operation of the DAEC Emergency Plan and Implementing Procedures.
2.0 APPLICABILITY This procedure applies to DAEC supervisors involved in implementing maintenance, calibration and test schedules for facilities, equipment and supplies which may be required for a DAEC emergency condition.
3.0 RESPONSIBILITIES 3.1 Assistant Chief Engineer - Operations 3.1.1 Exercise DAEC management control for the Maintenance Program.
3.1.2 Review the adequacy of applicable maintenance, calibration and testing schedules and procedures, as appropriate.
3.1.3 Ensure that maintenance, calibration and testing procedures are O
performed and schedules are met as necessary.
3.2 Radiation Protection Engineer 3.2.1 Ensure quarterly inventories are conducted of emergency kits (refer to Attachment 1).
3.2.2 Ensure that calibration and testing of radiation monitoring equipment is conducted in accordance with the Radiation Protection Procedures (RPPs).
3.3 Security Guard Captain 3.3.1 Ensure that a monthly inventory of first-aid supplies is conducted and verify that the first-aid room is in a state of readiness.
4.0 INSTRUCTIONS 4.1 DAEC maintenance, calibration and test procedures (ACPs and RPPs) provide instructions and scheduling for inspecting and maintaining emergency facilities, equipment and supplies.
4.2 The replacement of limited life items, such as batteries, shall be (p
conducted on an as needed basis, as determined during the quarterly g
inventory of Emergency Kits and operability checks of emergency l
equipment.
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.3 Page 2
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 4.3 The inventory and operability check of emergency communications equipment will be conducted in accordance with EPIP 6.4.
4.4 The following emergency facilities shall be maintained acording to the DAEC preventive maintenance program:
4.4.1 Control Room Emergency Equipment and Supplies 4.4.2 Operational Support Center Emergency Equipment and Supplies 4.4.3 Relocation and Assembly Area (Palo School) Emergency Equipment and Supplies.
4.4.4 Mercy Hospital Emergency Equipment and Supplies 4.4.5 IE Tower (E0F) Emergency Equipment and Supplies 4.4.6 Technical Support Center Emergency Equipment 6nd Supplies 4.4.7 Central Alarm Station Emergency Equipment and Supplies
5.0 REFERENCES
Ot 1.
Duane Arnold Energy Center Emergency Plan 2.
RPPs 3.
ACPs (Section 1406, Plant Maintenance and Section 1410, Security) 4.
DAEC Fire Plan 5.
DAEC Operations Procedures 6.
Mercy Hospital Emergency Procedure 6.0 ATTACHMENTS 1.
Emergency and Decontamination Kit Inventory Approved by:
$'17 8V Reviewed by:
h vi t ftt.
l Chief Engineer Ch&irman, t
Operations Committee l
Approved by:
[t 7 /}
m v/
I Approved by:
9/
d l
RadiationProtectiongngineer Assistant / Chief Engineer -
l V
Operatiofs l
l l
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 3
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 EMERGENCY AND DECONTAMINATION KIT I!WENT0RY Performed by Date Kit Location CONTROL ROOM Type DECONTAMINATION Item Minimum As As Quantity Found Left Cotton Balls (Bag) 1 Scissors (Pair) 1 Skin Marking Pencil 1
Surgeon's Gloves (Pairl 5
Scrub Brushes 2,
Phisoderm (5 oz. Bottle) 1 5 oz. Cups 30 1 oz. Cups 30 Gauze Sponges 200 Cotton Tip Applicators 500 Potassium Permanganate (Cap) 15 Sodium Bisulfite (Cap) 15 Epoxy Remover (Bottle) 1 O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 I
Page 4
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date i
Kit Location CONTROLRQG' Type EMERGENCY Page 1 of 3 Minimum As As Item Quantity Found Left EPIPs 1
High Range Dose Rate Instrument 1
Low Range Survey Instrument 1
First-Aid Kit 1
Sets of Protective Clothing 2
Full-Face Respirator 2
Radiation Rope (Feet) 80 Caution Signs 10 Danger Signs 10 High Radiation (Insert) 4 Airborne Radioactivity (Insert) 3 Contaminated Area (Insert) 3 Radiation Area (Insert) 3 Emergency Log Book 1
Radiation Protection Procedures 1
!O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 5
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 O
EQUIPMENT AND SUPPLIES Date - 3/1/82 U
ATTACHMENT 1 (continued)
~,
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location CONTROL ROOM Type EMERGENCY Page 2 of 3 Minimum As As Item Quantity Found Left Dosimeter Charger 1
High Range Self-Reading Dosimeters 4
Tape 1
Smears and Holders 1BX (500)
Filters for Emergency Air Samples 1BX(100)
Filters for Emergency Air Samples IBX(100) l c,
O
i EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 6
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location CONTROL ROOM Type EMERPINCY Page 3 of 3 Minimum As As Item Quantity Found Left 4" Glass Fiber Air Filters 1BX (100)
Bags (Large) 10 Bags (Small) 10 Masking Tape (Roll) 2 O
Area Photos 4
Instrument Batteries For each instrument l
Speaker Batteries 1
Plastic Sheeting (Sheet) 1 Paper (Pad) 3 Pencils 12 Self-Contained Braathing Apparatus 4
Spare Bottles 8
B1anket 1
Emergency Air Sampler 1
Personnel Statement Incident Record 1 Pad Kimwipes 2 Boxes O
l i
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIF
- 6.3 Page 7
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY.",iD DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (ACCESS CONTROL POINT)
Type DECONTAMINATION Minimum As As Item Quantity Found Left Cotton Balls (Bag) 1 Scissors (Pair) 1 Skin Marking Pencil 1
Surgeon's Gloves (Pair) 5 Scrub Brushes 2
Phisoderm (5 oz. Bottle) 1 l
5 oz. Cups 30 1 oz. Cups 30 Gauze Sponges 200 l
Cotton Tip Applicators 500 Potassium Permanganate (Cap) 15 Sodium Bisulfite (Cap) 15 Epoxy Remover (Bottle) 1 l
O l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 l
Page 8
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTEP.(EMERGENCY LOCKERS)
Type EMERGENCY Page 1 of 15 Check One Comments /
Yes or No Correction Action Locker #1 Shelf # 1 Pink Tag # 1 1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
High Range Dose Rate Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good d) Source check good e) Instrument turned off 3.
High Volume Air Sampler a) Good physical condition b) Current calibration c) Operable 4.
Air Sample Filters (1 box) 5.
Air Sample Record Forms 6.
Air Sample Plastic Bags and Labels 7.
Smears (1 box) 8.
Clipboard 9.
Note pad
- 10. Pencil
- 11. Flashlight
- 12. Wristwatch
- 13. Full Protective Clothing
- 14. Self Contained Breathing Apparatus (Located in Access Control)
O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 9
of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date_
Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 2 of 15 Check One Comments /
Yes or No Correction Action Locker #1 Shelf # 2 Pink Tag # 2 1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
High Range Dose Rate Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good d) Response check good e) Instrument turned off 3.
High Volume Air Sampler a Good physical condition j
b Current calibration c) Operable 4.
Air Sample Filters (1 box) 5.
Air Sample Record Forms 6.
Air Sample Plastic Bags and Labels 7.
Smears (1 box) 8.
Clipboard 9.
Note pad
- 10. Pencil
- 11. Flashlight
- 12. Wristwatch
- 13. Full Protective Clothing
- 14. Self Contained Breathing Apparatus (Located in Access Control)
O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 10 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 l
(continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY l
Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 3 of 15 Check One Comments /
l Yes pr No Correction Action I
Locker #1 1
dnelt # 3 Pink Tag # 3 1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
Low Range Survey Instrument Serial #
a) Good physical condition b) Current calibration l
c) Battery check good s
I d) Source check good e) Instrument turned off 3.
High Volume Air Sampler a) Good physical condition b) Current calibration c) Operable 4.
Air Sample Filters (1 box) 5.
Air Sample Record Forms 6.
Air Sample Plastic Bags and Labels 7.
Smears (1 box) 8.
Clipboard l
9.
Note pad 1
- 10. Pencil l
- 11. Access Control Survey Forms
- 12. Change House Area Survey Forms
- 13. Flashlight
- 14. Wristwatch O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 11 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Paoe 4 of 15 Check One Comments /
Yes or No Correction Action Locker #1 Shelf # 4 Pink Tag # 4 1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
Low Range Survey Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good p)g d) Response check good
(
e) Instrument turned off 3.
Clipboard 4.
Note pad 5.
Pencil 6.
" Personnel Statement Concerning Incident" Forms 7.
" Personnel Contamination Survey" Forms 8.
Flashlight Orange Tag # 1 1.
High Range Pocket Dosimete's a) 1 each 5 R on zero b) 1 each 10 R on zero I
l 2.
OSC Log 3.
Pencil 4.
Noble Gas Effluent Monitar (Located in Locker # 5, Shelf # 1)
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
EPIP - 6.3 Page 12 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 4
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 5 of 15 l
Check One Comments /
Yes or No Correction Action Locker #1 l
Shelf IP 5 Pink Tag # 5 l'
High Range Poef.et Dosimeters 1.
a) 1 each 5 P on zero b) 1 each IC R on zero 1
l 2.
High Range Dose Rate Instrument Serial #
l a) Good ;nysical condition b) Current calibration i
c) Bat'tery check good l
d) Source check good m
e) Instrument turned off 3.
Teletector a) Good physical condition b) Current calibration c) Battery check good d) Source check good e) Instrument turned off 4.
Flashlight 5.
Full Protective Clothing 6.
Self Contained Breathing Apparatus (Located in Access Control) l l
O 1
l EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 13 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 l
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY l
Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 6 of 15 Check One Comments /
l Yes cr No Correction Action Locker #2 shelf f 1 Pink Tag # 6 l.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
High Range Dose Rate Instrument Serial #
a) Good phye.ical condition b) Current calibration c) Battery check good O
d) Response check good e) Instrument turned off 3.
High Volume Air Sampler a) Good physical condition l
b) Current calibration c) Operable 4.
Air Sample Filters (1 box) 5.
Air Sample Record Forms 6.
Air Sample Plastic Bags and Labels 7.
Clipboard 8.
Note pad 9.
Pencil
- 10. Site Survey "SA-1" Forms
- 11. Flashlight
- 12. Wristwatch
- 13. Full Protective Clothing
- 14. Full Face Respirator O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 14 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date l
l Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS) l Type EMERGENCY Page 7 of 15 l
Check One Coments/
Yes or No Correction Action Locker #2 l
Shelf # 2 Pink Tag # 7 l
1.
Self Reading Pocket Dosimeters a) 1 each 200 mR on zero b) I each 5 R on zeroo 2.
High Range Dose Rate Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good O
d) Response check good i
e) Instrument turned off j
3.
Low Range Survey Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good d) Response check good l
e) Instrument turned off 4.
Air Sample Record Forms 5.
Clipbcard 6.
Note pad 7.
Pencil 8.
Radiation Survey Forms 9.
Map
- 10. Flashlight
- 11. Wristwatch
- 12. Full Protective Clothing
- 13. Full Face Respirator l
- 14. Substation Key
]
l O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 15 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 8 of 15 Check One Coments/
Yes or No Correction Action Locker #2 Shelf # 3 Pink Tag # 8 1.
Self Reading Pocket Dosimeters a) 1 each 200 mR on zero b) 1 each 5 R on zero 2.
High Range Dose Rate Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good d) Response check good e) Instrument turned off 3.
Low Range Survey Instrument Serial #
a) Good physical condition b) Current calibration c) Battery check good d) Response check good e) Instrument turned off 4.
Air Sample Record Forms 5.
Clipboard l
6.
Note pad 7.
Pencil 8.
Radiation Survey Forms 9.
Map
- 10. Flashlight i
- 11. Wristwatch
- 12. Full Protective Clothing
- 13. Full Face Respirator
- 14. Substation Key i
O
i EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 I
Page 16 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continuea)
EMERGENCY AND DECONTAMINATION KIT INVENTORY l
Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS) l Type EMERGENCY Page 9 of 15 Check One Comments /
(
Yes or No Correction Action l
Locker #2 i
Shelf e 4 Green Tag # 1 l
1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
Emergency Air Sampler (Battery powered) a) Good physical condition b) Current calibration c) Operable e
3.
12 Volt Battery with Charger 4.
Air Sampler Filters (1 box each type) 5.
Flashlight 6.
Wristwatch 7.
Full Protective Clothing 8.
Full Face Respirator l
l O
l l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 17 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY l
Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 10 of 15 Check One Comments /
Yes or No Correction Action Locker #2 Shelf # 5 Green Tag # 2 1.
Self reading pocket dosimeters a) 1 each 200 mR on zero b) 1 each 5 R on zero 2.
Emergency Air Sampler (Battery powered) a) Good physical condition b) Current calibration c) Operable O
3.
Emergency Air Sanpler(Gasoline Powered)
]
a) Good physical condition b) Current calibration c) Operable 4.
Air Sampler Fuel i
5.
Air Sample Filters (1 box each type) 6.
Air Sample Plastic Bags and Labels 7.
Flashlight 8.
Wristwatch 9.
Full Protective Clothing
- 10. Full Face Respirator O
i i
L
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 18 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 11 of 15 Check One Comments /
Yes or No Correction Action i
Locker #3 i
Shelf # 1 Green Tag # 3 1.
Self reading pocket dosimeters a) 1 each 200 mR on zero b) i each 5 R on zero 2.
Emergency Air Sampler (Battery powered) a) Good physical condition b) Current calibration c) Operable 3.
Emergency Air Sampler (Gasoline Powered) i a) Good physical condition b) Current calibration l
+
c) Operable l
4.
Air Sampler Fuel 5.
Air Sampler Filters (1 box each type) 6.
Air Sample Plastic Bags and Labels 7.
Fl ashlight 8.
Wristwatch 9.
Full Protective Clothing l
- 10. Full Face Respirator l
l O
i EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 19 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type _ EMERGENCY Page 12 of 15 Check One Comments /
Yes or No Correction Action Locker # 3 Shelf # 2 Blue Tag # 1 1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
Instrumentation Tool Kit a) Good Physical condition b) Inventory from attached list completed 3.
Simpson V0M (2 each) a) Good physical condition b) Replaced batteries with fresh ones (Return old batteries to Access Control) 4.
Flashlight 5.
Full Protective Clothing 6.
Self Contained Breathing Apparatus (Located at Access Control) l l
0
EMERGENCY PLAN IMPLEMENTING PROCEDORE EPIP - 6.3 I
Page 20 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performad by Date Kit Location OPERATIONAL: SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY-Page 13 of 15 Check One Comments /
Yes or No Correction Action Locker #3 --
dnelf y 3 PJrple Tag # 1 1.
High Ranga Pocket. Dosimeters a) 1 each. 5 R'on zero
-5) 1 each 10 R on'zero 2.
Electricians' Tool Kit a) Good physical conditicn t
b) Inventory,from attached list completed 3.
Simpson V0M i
3 a) Good physical condition b) Replaced batteries with fresh ones (Return old batteries to Access Control) 4.
Flashlight 5.
Full Protectiye Clothing 6.
Self Containea Breathing Apparatus (Located at Access Control) t i
J l
1 7
l l
l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 21 'of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 f
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 14 of 15 Check One Coninents/
Yes or No Correction Action Locker # 3 Shelf IP 4 Purple Tag # 2 1.
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
Electricians Tool Kit a) Good physical condition b) Inventory from attached list completed 3.
Simson V0M O
a) Good physical condition b) Replaced batteries with fresh ones (Return old batteries to Access Control) 4.
Flashlight 5.
Full Protective Clothing 6.
Self Contained Breathing Apparatus (Located at Access Control) l lO l
t
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 I
Paga 22 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONAL SUPPORT CENTER (EMERGENCY LOCKERS)
Type EMERGENCY Page 15 of 15 Check One Comments /
Yes or No Correction Action Locker # 3 Shelf # 5 Yellow Tag # 1 1
High Range Pocket Dosimeters a) 1 each 5 R on zero b) 1 each 10 R on zero 2.
Mechanical Tool Kit a) Good physical condition b) Inventory from attached list completed 3.
Flashlight 4.
Full Protective Colothing 5.
Self Contained Breathing Apparatus (Located in Access Control) l l
i O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 23 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTAt.riMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location OPERATIONS SUPPORT CENTER Type EMERGENCY Page 1 of 2 Check One Comments /
Quantity Yes or No Correction Action
- 1. Multichannel Analyzer Model 1056A 1
a)Goodphysicalcondition b) Current calibration c) Response check good
- 2. High Voltage Power Supply, Fluke 412B 1
a) Good physical condition b) Operational
- 3. Nal detector Unit a) Good physical condition l
~
b) Response check good (along with MCA) t
- 4. Ludlum Model 2000 Scaler 1
l a) Good physical condition b) Current calibration c) Response check good
- 5. Detector / Shield assembly for scaler 1
a) Good physical condition b) Clean
- 6. Battery operated air sampler 1
a) Good physical condition b) Current calibration c) Operational
- 7. 12 Volt battery (fully charged) 1
- 8. Battery charger (12 volt) 1
- 9. Compressed air bottle with regulator sample holder and tygon tubing 1
a) Good physical condition b) Bottle pressure-at least 1800 psi c) Regulator flow test good
- 10. Calculator with extra batteries 1
a) Good physical condition b) Batteries good c) Operational
- 11. Procedure - RPP 13.7 1
0 12 t"strectie" " e i-'edie zooo 1
- 13. Extension cord with 4 plug receptacle 1
- 14. Spray and Wipe 1 can
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 24 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 G
EQUIPMENT AND SUPPLIES Date - 3/1/82 V
l ATTACHMENT 1 (continued) l EMERGENCY AND DECONTAMINATION KIT INVENTORY l
l Performed by Date Kit Location OPERATIONS SUPPORT CENTER Type EMERGENCY Page 2 of 2 Check One Comments /
Quantity Yes or No Correction Action 1
- 15. Plastic lab gloves 25 pairs l
16.Gelman 50 mm particulate filters, 100/ box 1 box 17.Cesco charcoal cartridges,12/ box 2 boxes
- 18. Silver Zeolite cartridges, 12/ box 1 box 19.Kimwipes 1 box
- 20. Pencil 1
- 21. Grease Pencil 1
- 22. Felt Tip Pen 1
- 23. Pencil Sharpener 1
- 24. Clipboard 1
- 25. Gamma Photopeak Counting Forms 1 set
- 26. General Survey Records Forms 1 set 27.Ba-133 Disc Source 1
- 28. Plastic bags with labels 50 29.125 ml squeeze bottle 1
30.250 ml bottle-isopropyl alcohol 1
31.5mears 1 box j
- 32. Flashlight with extra batteries 1
- 33. Adaptor-50 mm sample head to tygon tubing 1
- 34. Adaptor-for filling small air bottle 1
- 35. Planchets 15 Upon completion of check list, have all appropriate materials including Ba-133 source been returned to the wooden box and the lock secured?
O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 25 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location RELOCATION AND ASSEMBLY AREA (PALO SCHOOL)
Type EMERGENCY KIT Minimum As As Item Quantity Found Left Paper coveralls 25 (sets)
Shoe covers 25 (sets)
Cotton liners 25 (sets) i Rubber gloves 25 (sets)
O j
Waterless hand cleaner 2 containers Kim wipes 6 boxes Large plastic bags 10 Small plastic bags 10 Blankets 2
l Dosimeters 200mR 10 l
Dosimeters 200R 2
Dosimeter charger 2
Masking tape 2 rolls Megaphone 1
Paper (pad) 6 pads Pencils 1 box EPIPs 1
Radiation protection procedures 1
Personnel statement of incident record 1 pad First aid kit 1
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 l
Page 26 of 30 i
MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location MERCY HOSPITAL Type DECONTAMINATION Minimum As As Item gcntity Found Left Cotton Balls (Bag) 1 Scissors (Pair) 1 Skin Marking Pencil 1
Surgeon's Gloves (Pair) 5 Scrub Brushes 2
Phisoderm (5 oz. Bottle) 1 5 oz. Cups 30 1 oz. Cups 30 Gauze Sponges 200 Cotton Tip Applicators 500 Potassium Permanganate (Cap) 15 Sodium Bisculfite (Cap) 15 l
Epoxy Remover (Bottle) 1 l
l l
lO
~
l
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 27 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location MERCY HOSPITAL Type HOSPITAL EMERGENCY Minimum As As Item Quantity Found Left SheetPoly(Sheet) 6 Absorbent Paper (Roll) 1 Paper Lab Coat 25 i
Large Bags 12 Small Bags 25 Cotton Gloves (Pair) 10 Plastic Shoe Covers (Pair) 25 Masking Tape (Roll) 2 Poly Gloves (Disposable) 72 Radiation Signs 10 Rubber Gloves (Pair) 4 Full-Face Respirator 2
1 Gallon Pails 2
5 Gallon Buckets 10 Radiation Tape (Rolls) 2 Liquid Soap (Bottles) 2 Scrub Brushes 2
I EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 28 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 l
L]
EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit location IE TOWER (EOF)
Type DECONTAMINATION Minimum As As Item Quantity Found Left Cotton Balls (Bag) 1 Scissors (Pair) 1 Skin Marking Pencil 1
Surgeon's Gloves (Pair) 5 Scrub Brushes 2-Phisoderm (5 oz. Bottle) 1 5 oz. Cups 30 1 oz. Cups 30 Gauze Sponges 200 Cotton Tip Applicators 500 Potassium Permanganate (Cap) 15 Sodium Bisulfite (Cap) 15 t
Epoxy Remover (Bottle) 1 0
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 Page 29 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 O
ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENT 0RY Performed by Date Kit Location IE TOWER (EOF)
Type EMERGENCY
.Page 1 of 2 Minimum As As Item Quantity Found Left EPIPs 1
High Range Dose Rate Instrument 1
Instrument Batteries For each instrument Low Range Survey Instrument i
n
'd First-sid Kit 1
(
l Sets of Protective Clothing 3
Full-Face Respirator 2
Radiation Rope (Feet) 80 Caution Signs 10 Danger Signs 10 High Radiation (Insert) 4 l
Airborne Radioactivity (Insert) 3 Contaminated Area (Insert) 3 Radiation Area (Insert) 3 Emergency Log Book 1
Radiation Protection Procedures 1
Dosimeter Charger 1
High Range Self-Reading Dosimeters 4
l t
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6.3 I
Page 30 of 30 MAINTENANCE OF EMERGENCY FACILITIES Revision 1 EQUIPMENT AND SUPPLIES Date - 3/1/82 ATTACHMENT 1 (continued)
EMERGENCY AND DECONTAMINATION KIT INVENTORY Performed by Date Kit Location IE TOWER (EOF)
Type EMERGENCY Page 2 of 2 Minimum As As Item Quantity Found Left Emergency Air Sampler 1
Smears and Holders 1BX (500)
Fiber Filters for Emergency Air Samples 1BX (100) t Fiber Filters for Emergency Air Samples 1BX(100) 4" Glass Fiber Air Filters 1BX (100)
Bags (Large) 10 Bags (Small) 10 Masking Tape (Roll)_
2 Area Photos 4
Speaker Batteries 1
Plastic Sheeting (Strip) 1 Pa9er (Pad) 3 Pencils 12 Self Contained Breathing Apparatus 1
Spare Bottles 2
Blanket 1
O l
~._.
c EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 1
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 1.0 PURPOSE This procedure defines the requirements for emergency preparedness communications system checks to be conducted on a periodic basis as defined in 10CFR50 Appendix E.
2.0 APPLICABILITY c
This procedure applies to the emergency communications systems that are installed at both the DAEC and at the IE Tower which are associated with emergency preparedness response efforts.
3.0 RESPONSIBILITIES 3.1 Emergency Planning Assistant 3.1.1 Perform communications checks as assigned in Section 4.0 3.1.2 Verify satisfaction completion of the communication checks conducted on a periodic basis as defined in Attachments 1 through 4.
3.2 Lead STA 3.2.1 Verify that emergency preparedness communications systems checks are completed as assigned.
3.2.2 Coordinate with the Emergency Planning Assistant as required to insure satisfactory completion of the communications systems checks.
3.3 Security Guard Captain 3.3.1 Verify that emergency preparedness communications system checks are completed as assigned.
4.0 INSTRUCTION l
4.1 The following communications systems shall be checked and verified operable at the specified frequency.
4.1.1 Completion of monthly communications checks shall be
~
documented on attachments 1 & 2. include The following systems or circuits are included:
a)
NRC ENS b)
NRC HPN O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 2
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 c.
iG c)
PBX & Centrix connections to:
(1)
Office of Disaster Services (2)
Linn County Sheriff (3)
Benton County Sheriff 4.1.2 Completion of the quarterly communications checks shall be documented on attachment 3.
The following systems or circuits are included:
4.1.2.1 Dedicated telephone circuits between:
(a)
Control Room and Technical Support Center Access Control Security Control Point Emergency Operations Facility (b) Technical Support Center and Control Room Access Control Security Control Point Emergency Operations Facility (c) Access Control and
' O Control Room V
Technical Support Center Security Control Point (d)
Security Control Point Control Room i
l Technical Support Center Access Control 4.1.2.2 Operations Radio between:
(a)
Control Room (base station)
(b)
Technical Support Center (console)
(c)
Site Boundary l
(d) Access Control (console) 4.1.2.3 Security / Radiological Survey Radio between:
(a) Ten (10) mile radius (b) Technical Support Center (console) c Emergency Operation Facility (console) d Security Control Point 4.1.2.4 Operationally Check and Inventory the Following Equipment:
( a)
(2)
Six Button Phones in the Control Room (b)
(1)
Headset in the Control Room (c)
(8)
Twenty Button Phones in the TSC O
N..]
l
E EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 3
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82
(
i.~./
(d)
(5)
Headsets in the TSC (e)
(4)
Operations Radios in the SCP (f)
(2)
Security / Radiological Porta-Mobiles in the SCP (g)
(2)
Magnetic Mount Antennas in the SCP (h)
(2)
Antenna Adapters in the SCP NOTE The head set in the TSC are located in the cabinet in the Connunications Room.
4.1.3 Completion of the annual communication checks shall be documented on Attachment 4.
4.1.3.1 Centrix connections to:
(a) FFMA (b) DOE (c) Office of Disaster Services (d)
Linn County Civil Defense (e)
Benton County Civil Defense r'~'
4.2 Communication checks should be conducted as follows:
' V; 4.2.1 Monthly - first full calender week 4.2.2 Quarterly - first full calender week during January, April, July and October 4.2.3 Annual - first full calender week during October.
4.3 A message similar to that shown on Attachment 5 should be used when conducting communications systems checks external to IELP.
4.4 Communications checks should be performed by:
4.4.1 DAEC - as directed by the Lead STA and Security Guard Captain.
4.4.2 IE Tower - Emergency Planning Assistant 4.5 The Security Guard Captain shall ensure that the communications checks indicated in Attachment 1 are performed, sign the form, and forward it to the Lead STA.
4.6 The Lead STA shall review Attachment 1 upon its completion and forward to the Emergency Planning Assistant.
)
~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 4
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 4.7 The Emergency Planning Assistant shall perform the communication check indicated in Attachment 2, 3, and 4.
4.8 The Emergency Planning Assistant shall review all documentation associated with the communications checks and prepare a written summary for the Chief Engineer, Emergency Planning Coordinator, and Director Nuclear Generation.
4.9 Acceptance Criteria 4.9.1 All required communications checks shall be made and satisfactorily completed.
In the event that a call cannot be completed, contact the party by another means and inform them of the problem, making sure the party understands no problem exists at the DAEC and their response is not required.
If possible determine the cause of the problem and rectify it as soon as possible.
If the problem cannot be readily resolved, attach a note clearly stating which
)
phone, who was being called, what number (if any), who was calling and any other pertinent information to the EPIP checklist in use.
Complete the remaining communcations p
checks and forward the test and coments to the Emergency l
Planning Assistant.
5.0 REFERENCE 5.1 10 CFR 50 Appendix E 5.2 EPIP 2.2 " Activation and Operation of the Technical Support Center" 6.0 ATTACHMENTS 1.
Monthly DAEC Emergency Communications Checks 2.
Monthly IE Tower Emergency Comunications Checks 3.
Qarterly DAEC Emergency Communications Checks 4.
Annual IE Tower Emergency Comunications Checks 5.
Example ommunicati n Check Message Format b
APPROVED BY:
DATE:
Chi Engineer REVIEWED BY:
OQQ DATE: v//PL Chairmin, Operations fomittee l
APPROVED BY:
DATE:
=b24-b Assistant Chief Engineer Radiation Protection and Security
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 5
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 ATTACHMENT 1 Monthly DAEC Emeroency Communications Check Communication Initiated By Received By Circuit (Name)
(Name)
Time Date i
' 1.NRC ENS a) Control Room b) Technical Support Center (TSC) l 2.NRC HPN a) Access Control l b)TSCl I
c)TSC2 I
l l
d) Security Control Pointi
- 3. COMMERCIAL TELEPHONES a)NRC-Bethesda (301)492-8111 or (301)427-4056 or (301)492-7000 b)0ffice of Disaster Services j
(515)281-3231 or (515)281-3561 Q c)Linn Co. Sheriff 398-3911 b d)Benton Co. Sheriff 11-472-4777 or 11-472'-2337 4.P0lNT TO POINT RADIOS a)Linn County Sheriff
?
b)Benton County Sheriff I
l l
c) Iowa Highway Patrol t
I I
5.IWAS PHONE 3 a)0ffice oT Disaster Services 6.NWS FIRST ORDER STATION, Cedar Rapids Flight Service 11-364-7127
, 7.NWS FORECASTING STATION ves moines (bib) a4-4492 1 Dial 22 (NRC-Bethesda) 2 Dial 23 (NRC-Region III during regular business hours only) 3This test will be initiated by the State Office of Disaster Services on the followino days:
January 4, February 1, March 1, April 5, May 3, June 7, July 6, August 2, September 7, October 4, November 1, December 6,1982.
4 Items 1 through 3a will be performed by an STA and items 3b through 7 will be performed by Security.
REVIEWED BY DATE 5ecurity Guard captain P EVIEWED BY DATE V
Lead STA REVIEWED BY DATE Emergency Planning Coordinator l
L
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 6
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 ATTACHMENT 2 Monthly IE TOWER Emergency Communication Checks
. Communication Initiated By Received By Circuit (initials)
(Name)
Time Date Centrex NRC Region III (312)932-2500 NRC Bethesda (301)492-8111 or 301 427-4056 or 301 492-7000 Office of Disaster Services (515)281-3231 or (414)281-3561 Linn County Sheriff 398-3911
'enton County Sheriff 1-472-4777 l )
or 1-472-2337 i
NRC ENS Emergency Operations Facility NRC HPN - Bethesda Dial 22 NRC HPN - Region III Dial 23 (During Regular Business Hours Only)
NWS First Order Station 364-7127 l
NWS Forecasting Station (515)284-4492 CONDUCTED BY Emergency Planning Assistant Reviewed Date Emergency Planning Coordinator O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 7
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 ATTACHMENT 3 Quarterly DAEC Emergency Communications Checks l.
Communication Initiated By Receiv'ed By (initials)
(Name)
Time Dace, Remarks Ci_rcuit l
Control Room Dedicated Circuits TSC l
Access Control Security Control Point l
EOF Back Panel Circuit to TSC Intercom i
i Operability Check and Inventory l
Headset Six Button Phones TSC Dedicated Circuits Control Room
,-s Control Room (back panel)
Access Control Security Control Pt.
TSC to E0F E0F to TSC Intercom Operability Check and Inventory (5) Headsets (8) Twenty Button Phones Access Control Dedicated Circuits l
Control Room TSC Security Control Pt.
Intercom Security Control Pt. Dedicated Circuits Control Room l
TSC i
Access Control l
Intercom l
Continued on next page O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 8
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 ATTACHMENT 3 (continued)
Quarterly DAEC Emergency Communications Checks Communication Initiated By Received By Circuit (initials)
(Name)
Time Date Remarks Operations Radio (TSC)
Secondary Alarm Station Security Control Point Site Boundary Operability Check and Inventory
]
(4) Hand Held Radios i Security / Health Physics Radio (TSC)
EOF Security Control Point 10 mile radius j
Check and Inventory f erabilitkorta Mobile Radios (2) b 2
Magnetic Mount Antennas 2
Antenna Adapters l
CONDUCTED BY Date
~
Emergency P lanning Assistant l
Reviewed Date l
Emergency Planning Coordinator l
l l
O
~~
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP 6.4 Page 9
of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 TESTING Date 3/3/82 ATTACHMENT 4 Annual IE Tower Emergency Communication Checks i
Communication Initiated By Received By Circuit (initials)
(Name)
Time Date i
Centrex i
FEMA (202)634-7800 or (202)287-0540 00E (312)972-4800 or (312)972-5731 Office of Disaster (515)281-3231 Service or (515)281-3561 Linn County CD 363-2671 i Benton County CD 472-4519 Conducted By:
Date Emergency Planning Assistant Reviewed By:
Date Emergency Planning Coordinator l O l
EMERGENCY PLA'N IMPLEMENTING PROCEDURE EPIP 6.4 Page 10 of 10 EMERGENCY PREPAREDNESS COMMUNICATIONS Revision 2 O
TESTING Date 3/3/82 O
EXAMPLE COMMUNICATION CHECK MESSAGE FORMAT This is Name Title from DAEC or IELP The purpose of this call is simply to check operability of this communication system.
An emergency situation does not - I repeat - does not exist at the DAEC.
NOTE j
Advise the individual who answered the call that this check is being done monthiy, quarterly, or yearly, as the case may be, to comply with NRC regulations. Obtain his or her name, advise it is simply for documentation purposes, thank him and end the conversation courteously.
O 9
p _. _._ ___
jN E
l 0
^
Towa Electric Light and Ibwer Company f
SPECIAL ORDER, General # 486 t
T0:
ALL DAEC Personnel 1
SUBJECT:
Emergency Response Organization Notification List ORIGINATED BY:
Randy Portz, Emergency Planning Assistant EFFECTIVE DATE:
1 June 1982 CANCELLATION DATE:
1 September 1982 DISTRIBUTION:
L. Root D. Nowotny D. Gipson R. McGaughy M. Huting J. Davis D. Mineck (2)
L. Voss K. Meyer B. York J. West R. Portz D. Wilson D. Vest Security Control Point J. Vinquist F. Brush Chem Lab (2)
R. Rockhill N. Brown Health Physics J. Sweiger G. VanMiddlesworth Radwaste Control G. Fulford D. Teply Central Alarm Station J. VanSickel C. Mick J. Sparano s
R. Anderson J. DeVries M. Sparks L. Morey R. Roberts R. Cantrell K. Young R. Zook D. Rickels R. Steigers R. Potts R. Sanders R. McCracken B. Dye L. Wille B. Klotz M. Benfield D. Kelley All EPIP Manual Holders The attached phone list is hereby promulgated, this list supersedes Special Order General # - 479. The lists are separated according to Emer-Please place this list with your Emergency Plan gency Job Classification.
Implementation Procedure (EPIP 1.2) and discard existing Special Order #457.
0
/&l Daniel L. Mineck Chief Engineer Duane Arnold Energy Center e
o DLM/sg V
Attachment cc: Ken Vanous ikwu Anushi Essenyy Cerster
- In Ikss 351
- Cedar Resphis, lowin 5240G
- 319/MI 5611
Notification List No. 1 Page 1 of 2 NO REQ.
TOTAL NOTIFICATIONS PARTY CALLED HOME OFFICE IN NO INI"IAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES NO YES 'NO EMERGENCY COORDINATOR 1
1 P) Daniel L. Mineck
- 1) isobby R. York
- 2) David L. Wilson
- 3) John V. Vinquist
- 4) Rick L. Hannen EMERGENCY RESPONSE & RECOVERY DIRECTOR' 1
1 P) Dick McGaughy
- 1) Larry D. Root,
- 2) Harold Rehrauer
'w-Security Shift Supervisor (CAS) 1 1
Linn County E0C (sheriff) 15 min.
398-3911 or Point to Point Raoio or IWAS Phone Benton County E0C (Sheriff) 15 min.
11-472-4777 or 11-472-2337 or Point to Point Radio or IWAS Phone State E0C (0DS) 11-515-281-3231 15 min.
or 11-515-281-3561 or Point to Point Radio or IWAS Phone Cdumunici
.- Name Date y
Notification List No. 1 Page 2 of 2 NO REQ.
TOTAL NOTIFICATIONS PARTY CALLED HOME OFFICE IN NO INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER N0.
PHONE EXTENSION 30 MIN.
REQ.
YES N0 YES N0 NRC Operations Center NRC " HOTLINE" I hour Bethesda, Maryland or (202) 951-0550 or (301) 427-4056 or HP Net - 22 or (301) 492-7000 Communicator Name Date O'
O O
Notification List No. 2 NO REQ.
TOTAL NOTIFICATION PARTY CALLED HOME OFFICE IN NO.
INITIAL RECALL TI'4E EMERGENCY TITLE /NAME PAGER N0.
PHONE EXTENSION 30 MIN.
REQ.
YES N0 lYES NO Site Radiation Protectior Coordinator 1
1 (P) Keith Young (1) Bob Dye (2) Ed Parsons OSC Supervisor 1
1 (P) Ed Parsons (P) Paul Serra (1) Bob Dye Health Physics Technicians 5
8 Kevin Konzem Paul A. Louis Kevin Coppes l
Geralo G. Wilford Eric Wienota L. Sills
- 5. Hopper J. Evans M. Davison J. Elbert D. black A. Reese R. Grafton
- 5. Funk B. Sligh D. Kubacka Ierry Matta (Trainee)
DeeAnn Anderson (Irainee)
Janiece Ford (Irainee)
Wesley Kadlec (Irainee)
Norman Nelson (Trainee)
Tony Bata (Trainee)
.\\
Mary burns (Irainee)
L. Ganske (Trainee) dc'midt (trainee)
P.
n B. Nielsen (Trainee)
Communi _cor Name Date x
Notification List No. 2 Page 2 of 2 NO REQ.
TOTAL NOTIFICATION PARTY CALLED HOME OFFICE IN N0.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER N0.
PHONE EXTENSION 30 MIN.
REQ.
YES N0 YES NO 1
2 Chemistry Technicians Ralph M. Lewis traig 5ealls Anthony Funke Don Rees 1
1 Radwaste Operators James L. Klocke Steven M. Eylers M. Larson C. Brcwn Robert Schlueter (New Operator)
Marshall Nickelson (Irainee)
L. Schmidt (Trainee)
J. Jacobsen (Irainee)
G. Skala (Trainee) 1 Exposure Records Coordinator Linda Haven Radwaste Coordinator Roger Stigers Environmental H.P.
Don Johnson Administrative Jerald Davis 1
1 NRC Resident inspector Larry Clardy Nick Chrissotimos homet i
INFORM G. E. Operations Engineer John Silva Plant Chemist Ralph Fohto Date Communic'ator Name
Notification List No. 3 Page 1 of 4 NO REQ.
TOTAL NOTIFICATION PARTY CALLED HOME OFFICE IN N0.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENS10t!
30 MIN.
REQ.
YES NO YES N0 I
TSC Supervisor 1
1 (P) Bobby R. York (1) David L. Wilson (2) John V. Vinquist (3) Rick L. Hannen (4) Gary Van Middlesworth (5) John D. Van Sickel (6) Donald F. Vest Control Room Coordinator 1
1 (P) Donald F. Teply (1) L. R. Mick Technical & Engineering Shpervisor (P) John Vinquist (1) Dave Wilson t
(2) Rick Hannen
's Security & Support Supervisor (P) Dave Wilson (1) Jim 5parano (2.) Jerry Davis
'e (3) Mike Sparks Communicators 2
8 (P) Mike Chandler (F) Ken Feveler (P) Linus Drouhard (P) Jett fielson (P) laj Nahammed
( 1) Bill Rackle (2) bill 5cholberg
( 3) Gene havlic (4) San Ray
( 5) John Johnson (6) bill Ellis (7) Clare Bleau
" ' ~
Communicator Name Date
--~
s
Notification List No. 3 Page 2 of 4 NO REQ.
TOTAL NOTIFLCAT10N PARTY CALLED HOME OFFICE IN N0.
INITIAL RECAlt ME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES N0 YES NO 2
2 Shif t Technical Advisors (STA)
Mike Teply Wally Leck John Bjorseth biorgos Anagnostopoulos Paul Collingsworth Uave Mankin Rx. & Plant Perf. Engineers 1
1 bary Van Middlesworth Donald F. Vest hicholas Brown Francis L. Brush Mechanical Maintenance 1
4 James P. Goersch William E. Seely Donald L. Schott James M. Meyerhoff Ronald U. 5hields Daniel L. Coghlan James Becker David McGill David A. Pladsen Duane Long (Apprentice) 5tanley Jacobson (Apprentice),
C. Kress (Apprentice)
R. Comreid (Apprentice)
Electricians 1
2 Paul Abernathy James Scott Harold Rodenberg horman leiessen
'N Communicator Name Date t
v e
^
Notification List No. 3 Page 3 of 4 NO REQ.
TOTAL NOTIFICATION PARTY CALLED HOME OFFICE IN N0.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES NO YESl NO Ir.strument Technicians 1
1 Paul J. Maternowski Larry bosnell Michael Long Tony E. Olsen Allen R.Schmiot trnest C. Zaugg Lowell J. Russell Bob R. Stout Daniel L. Thies William A. McVicker R. Craig hunt (Apprentice)
Electricial Design
~
l Clare Bleau Mike Chanoler Sam Ray Taj Manammed Giorgos Anagnostopoulous Lila Grover Mechanical Design i
1 Bill Ellis Bill Scholberg Bill Rackle Jim Loehrlein Ken Peveler Linus brouhard Jeff Nelson Gene Havlic John Johnson Paul Collingsworth Dave Mankin Mike leply 1
Monty Hintz s
Communicator Name Date 3
V e
Notification List No. 3 Page 4 of 4 INITIAL (ATION NOTIFI NO REQ.
TOTAL RECALL PARTY CALLED HOME OFFICE IN NO.
TIME EMERGENCY TITLE /NAME PAGER N0.
PHONE EXTENSION 30 MIN.
REQ.
YES NO YES NO Mechanical Supervisors I
1 (P) Richaro D. Rockhill (1) George R. Fulford Electricial Maintenance Supervisors 1
(P) Jerome C. Sweiger (1) Larry L. Voss Warehouse Personnel (P) Robert LaPointe (1) Russell L. Brown (2) Eldon M. Martir:g Security Supervisor (P) James 5parano (1) Michael Sparks Communicator Name Date 0
9 f
v
Additional Resources Page 1 of 5 NO. REQ.
TOTAL NOTIFICATION PARTY CALLED HOME OFFICE IN NO.
INITIAL RECALL TIME EMERGEf3Y TITLE /NAME PAGER NO.
PHONE EXTENSION 30 min.
REQ.
YES NO YES NO Shift Supervising Engineers (SSE)
John DeVries Douglas R. Gipson Ronalo L. Potts Raymond Roberts Raymond L. Zook Shift Supervising Engineers "B"
f Dwight Barton i
t Uean Robertson Jack Mohr Richard Fowler Gary 5tatton Dwight Hartz m. ~_.
l Communicato'r Name Date Og e
0 e
4
v Additional Resources Page 2 of 5 NO REQ.
TOTAL NOTIFICAT10N PARTY CALLED HOME OFFICE IN N0.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER NO.
PHONE EXTENSION 30 MIN.
REQ.
YES NO YES NO Operators 2
John Adams Richard L. Anderson Russell becker Wayne L. Bentley Lonnie D. Gross Robert Hovey Brian Hupke Duane R. Johnson Kevin J. Morgan Wayne Render Keith Reule Steve Reynolds.
Stephen Rohr Joe Ruth Frank Sauser David M. Schussler Allen J.
Steen leryl Subbert Kenneth Tnomas George R. Thullen Frank 5. VanEtten Benjamin Westcot Tnomas A. Zimmerman g
Paul bullivan I
I l
Communicator Name Date e
Q
,lf)li ll (lfl 1lll ll ll ll i
,O ILN NA OCS IEE TRY A
C I
FL IA)
K TI t
L..
A
.Q TOE ONR 5
T fo 3
e g Q N
a E
I P
RNM I
O 0
N 3
~
N O
s I
e ES c
CN r
I E u
FT
+
o FX s
OE e
R l
o E
- g an i
EN t
MO OH i
d HP dA e
ta D
0 N
R E
GA P
t r
E o
M p
n A
p r
N i
e i
/
S t
E n
s L
p o
s e
T u
s c r n
W DI o
r i
e h o n ET r e y n r n n n
s k t
s i
d L
G d
e o e o a o
y c
i k
m r LY n r s l
t m
s n h
e m c m a
/. C g
A o r l
s l
k y a n P
D S
i u W m a c o m o D
C e
CN n
M o i
R o C h
t y
a m
E i
t h
M r D i
YG n
r yT a
H n
t r e o s e a
TR i
e r e H n
l I
n l
e l
yi r
N RE a
b r b v
a n u h
a b
r o r f r
AM r
o a o a a l
o a a o e o a h
l l
PE T
R L
B D
L A
D P
L J
H R
P F
C A o
ta c
i n
~
u E
m M
m I
o T
C e
i l
l l
l
Additional Resource Page 4 of 5 NO REQ TOTAL NOTIFICATION PARTY CALLED HOME OFFICE IN NO.
INITIAL RECALL TIME EMERGENCY TITLE /NAME PAGER N0.
PHONE EXTENSION 30 MIN REQ.
YES N0 YES N0 Security Guard Lieutenant
~
Rollie Cantrell Daniel Kelley Darrell Rickels Richard Sanders Larry Wille Security Personnel Howard D. Brown Diane Engelhardt Freoerick Hadenfeldt Brian C. hall Larry Joens kon Larsen Larry W. hcDonald kobert Moriarity Donald Reiner lom Stepar.ek Melvin Theisen Robert Wetherall R. Othoff M. Meeks K. Moore R. Warren F. Stein U. Koggentein Utility Doreen Kelly No phone.
9
'S e
Communicator Name Date
ilJj l
,lll j
Y FL IAO TI N OT NI NS 5
IE Y
fo 5
eg L
a A
.Q P
TOE ONR T
Q N
E I
RNM I
O 0
N 3
i
~
NO I
e ES c
CN r
I E u
FT o
FX s
OE e
R l
a no E
i EN t
MO OH i
d HP dA e
ta t
D O
N R
E GA P
nos t
E r
M n
A e
r e
N k
y e
h b
y l
/
c n
e g
l e e a
t n
t u
k i
e E
l L o r
g z
t o
i n
a c
G l
n f
w g
a b
r n k
y n n e u T
r C n
t l
DI t c
i o a o n r t
y r e a
. k n
e o o e e E
e s
e t
a z r M c n e s
m t
w T i
ET n M
t l
c L
o u K t
t n
i n
e L t
F o e H d
l a a t
S t
LY C
. H e
. s l
r s o n
e e c v
r e x e u t
n a a a K u R S
n L y
M L
e a a a s o l
h a F AC A
w L
a e
C W t c V A
M a o t 5
r n a H i
CN y E t t A d
s a
i c B t
l F
a H
c o e a e e n m
i a d n J o
a l
i s
F n d f
e i
e y
y n
a i
H r
e YG i
e k c a n e h
i f
c r
yl r c a p
a d r
n l
n i
r N
TR l
RE a b
r u n n m e c v a n e
r u e n t
e l
n t
n n u o a e a AM u o a r o e a o e a t
a l
a a n a i
t i
i a n o a h
l a n r
PE Q R M B U
D J
J T
D S
L C
M P
S l
R 5
L L
P A
b P
R E
k 5
o i
tac l
i n
J" E
m M
o I
C T
t 1{
lllIlllf(lllilII ll l
l 1