ML20054M388
| ML20054M388 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/24/1982 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17319B417 | List: |
| References | |
| PROC-820624-01, NUDOCS 8207130062 | |
| Download: ML20054M388 (64) | |
Text
,
pMP EPP INDEX INDIANA i MICHIGAN POWER CCMPANY CCNALD C. COOK NUCLEAR PLANT PLANT MANAGER PDOCEDURE index Identification Revision No.I 79 tj, Cmnu ilumcer And Data i PMP 2080 EPP.001 Emergency Plan Activation Revision 2 TP-1,5 "7-82 Exp ?!A and Condition Classification 4-27-82 EPP.002 Unusual Event CANCELLED 10-29-81 EPP.003 Alert CANCELLED 10-29-81 EPP.004 Site Emergency CANCELLED 10-29-81 EPP.005 General Emergency CANCELLED 10-29-81 EPP.006 Initial Dose Assessment Rev. 2 (Gaseous) 4-27 EPP.007 Initial Release Assessments Revision 0 TP-1,2-23-82 Exp NA (Liquid) 4-1-81 EPP.008 Calling Off-Duty Plant Revision 1 TP-1,4-30-82 Exp N/A Personnel 4-29-82 l
EPP.009 Fire Emergency Guidelines Revision 1 6-15-82 EPP.010 Toxic Gas Release Guidelines Revision 1 6-2-82 EPP.011 Natural Eniergency Guidelines Revision 0 4-1-81 l
l l
EPP.012 Initial Off-Site Notificatior Revision 1 l
j 4-27-82 j
1 i
Page 1
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AHP 2030-DCR-001-2 initials:
No.
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DOCUMENT ISSUE RECORD INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT COLOR CODED DISTRIBUTION DOCUMENT CONTROL - Original
, MASTER FILE - Purple OPERATIONS - Green ADMINISTRATIVE - Orange Op. Super,SCE,Jnit 1-2,
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INDIANA & MICHIGAN ELECTRIC COMPANY DON ALD C. CCJK NUCLEAR PLANT Instruction or Procedure Temporary Sheet This temporary sheet applies to Cm3 Ow-Bug hr Paw-L_
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instruction or Procedure No. PMP 2080 EPP 008 i
Revision No. I 1
The followirig change (
)
new requirement (X )
shall be April 30,1982 instituted effective (Date)
Add to Exhibit A under " Persons to be Called" by the Operations
)
Superintendent.
Fifth Shift Supervisor Add a section to Exhibit A Person to Make Call Person To Be Called Fifth Shift Supervisor Fifth Shift Personnel i~;,' C
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t Reason: Provide personnel to staff the Emergency Control Center k
This change should be made a permanent revision to the Instruction or Procedure:
DYES CNO O NOT KNOWN, additional review required Expiration [hte-.
o rnros,u o cou4e4en Standard Dist. List No.:
Onginator:
/dd 7b Distribution:
Managerrent Staff: [MM Senior Reactor Operatcr: 'D Set PNSRC Dite
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(
Rant Manager NNd Chte J"* 7/W P.t-(
Form No. 4330 REVISED 7na WHITE
- OR!GINAL CANARY - ORIGINATOR COPY PINK
- WORKING COPY FORM NC. PMI 201t>4 REY.2
p INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Precedure No. PMP 2080 EPP.006 Revision No. 2 N INITIAL DOSE ASSESSMENTS (GASE0US).
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SCOPE OF PEVISION Revision 1: Complete revision to si@lify dose calculation technique.
Revision 2: Revised curves, corrected errors in procedures, and added Waste Gas Decay Release curve. Incorporated Temporary Changes 1 & 2.
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SIGNATURES ORIGINAL R*V 3 REV.2 Rev.3 i
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PREPARED BY QUALITY ASSURANCE-U REVIEW U
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DATE OF ISSUE 3-31-81 (0-2.7-91 M M 7-M Fann Na PMI 20104 asv. 2 yw-r vr w-e-
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.s PMP 2080 EPP.006 LIST OF EFFECTIVE PAGES Page Number Revision Number And Date Page 1 of 17 Revision 2, 4-27-82 Page 2 of 17 Revision 2, 4-27-82 Page 3 of 17 Revision 2, 4-27-82 Page 4 of 17 Revision 2, 4-27-82 Page 5 of 17 Revision 2, 4-27-82 Page 6 of 17 Revision 2, 4-27-82 Page 7 of 17 Revision 2, 4-27-82 Page 8'of 17 Revision 2, 4-27-82 Page 9 of 17 Revision 2, 4-27-82 Page 10 of 17 Revision 2, 4-27-82 Page 11 of 17 Revision 2, 4-27-82 Page 12 of 17 Revision 2, 4-27-82 Page 13 of 17 Revision 2, 4-27-82 Page 14 of 17 Revision 2, 4-27-82 Page 15 of 17 Revision 2, 4-27-82 Page 16 of 17 Revision 2, 4-27-82 i
Page 17 of 17 Revision 2, 4-27-82 i
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PMP 2080 EPP.006 INDIANA & MICHIGAN ELECTRIC COMPANY
" i DONALD C. COOK NUCLEAR PLANT INITIAL DOSE ASSESSMENTS (GASEOUS) 1.0 OBJECTIVES This procedure provides the Shift. Supervisor /On-Site Emergency Coordinator (SS/0SEC) with a method to initially assess potential off-site dose effects of unplanned radioactive gaseous releases.
2.0 RESPONSIBILITIES 2.1 Upon a projected or actual unplanned radioactive gaseous release, and prior to activation of the Technical Support Center, it is the SS/OSEC's responsibility to make off-site dose projections.
The SS/0SEC shall also verify the projected values by organizing a Radiation Monitoring Team and sending them to appropriate off-site areas.
2.2 Technical Support Center (TSC) personnel shall assume the respon-sibilities of 2.1 upon TSC activation.
This procedure is applicable prior to activation of the Technical Sup-port Center whenever there is a significant projected cr unplanned release of gaseous radioactivity.
3.0 APPLICABILITY This procedure is applicable prior to activation of the Technical Support Center whenever there is a significant projected or un-planned release of gaseous radioactivity.
4.0 INSTRUCTIONS 4.1 Obtain data necessary to make off-site dose projections.
4.1.1 R-15, R,26, and/or R-33 radiation monitor readings.
4.1.1.1 If R-26 is off-scale high, obtain a radia-tion reading at 6" from the unit vent sample line.
4.1.1.2 If R-15 or R-33 is off-scale high, obtain a radiation reading at 6" from the GSLO or SJAE exhaust line.
4.1.2 Appropriate vent flow rate (Unit Vent, GSLO, or SJAE).
4.1.3 Wind direction and velocity.
Page 1 of 17 Rey. 2, 4-27-82
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PMP 2080 EPP.006 4.1.4 Determine PASCALL Category as per the table below:
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AT=(T@l80ft. - T@30ft.)*C PASCALL CATEGORY
.9-A
.9 to
.8 B
.8 to
.7 C
.7 to
.2 D
.2 to +.7 E
+.7 to
+1.8 F
+1.8 G
4.2 If meteorological instrumentation is inoperable use Exhibit G to estimate wind speed and PASCALL Category. Obtain wind di-rection from the Visitors Center or State Police.
4.3 Select appropriate graph (s) to use and fill in data blanks 4.3.1 R-26 On-Scale; Exhibit A 4.3.2 R-26 Off-Scale; Exhibit B 4.3.3 R-33 On-Scale; Exhibit C 4.3.4 R-15 On-Scale; Exhibit D 4.3.5 R-15, R-33 Off-Scale; Exhibit E 4.3.6 Wasta Gas Decay Tank Release; Exhibit F NOTE:
R-15 On-Scale will always result in less than 1 mR/hr off-site. With steam generator tube ruptures, readings would be expected also on R-33.
The dose associated with the release from a steam generator tube rupture will be the sum of the doses calculated from R-15 and R-33.
NOTE:
The ability to predict dose rate in the event of a steam generator tube rupture is dependent upon the release be-ing via R-33 and R-15.
If releases are being made via the safeties or steam generator PORV's because of the loss of condenser vacuum or equipment failure, there is no quick method to calculate dose rate. Dose rate should then be measured at the site boundary as soon as possible by dispatching a monitoring team to monitor downwind at the site boundary.
4.4 Complete the appropriate graph (s) to estimate off-site dose rate as follows:
4.4.1 Draw a straight line connecting the data points on scales (1) and (2).
4.4.2 Draw a straight line connecting the intersection of scale (3), from step 4.4.1, with the data point on scale (4).
4.4.3 Connect the intersection of scale (5), from step 4.4.2, with the data point on scale (6).
4.4.4 Read the 610 meter dose rate from the intersection of scale (7), caused by Step 4.4.3.
Page 2 of 17 Rev. 2, 4-27-82
/
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4.4.5 Determine the site boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 180 - 250' 0 - 70*
610 Meter Dose Rate 250* - 305*
70* - 125' 610 Meter Dose Rate 3
45*
125* - 225' 610 Meter Dose Rate 305 NOTE:
The dose will occur where the wind is blowing toward. To convert Wind Direction (from) to towards, Exhibit H of this procedure may be used.
4.5 Classify the condition as follows:
Site Boundary Dose Rate Classification 2 2 mR/hr Alert 2 50 mR/hr Site Emergency 3 250 mR/hr General Emergency
~
'l NOTE:
For wind directions over (toward) the lake consider the site boun '
dary dose rate to be the same as the 610 meter dose rate.
4.6 When the projected dose rate is 2 250 mR/hr, the SS should recom-mend to local authorities immediate sheltering within a 2 mile ra-dius of the plant and for 5 miles downwiad in the affected sector (s).
For wind directions over the lake, evacuation is appropriate.
4.7 Return to PMP 2080 EPP.001 as applicable.
.A Page 3 of 17 Rev. 2, 4-27-82
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R-26-ON SCALE PMP 2080 EPP.006 EXHIBIT A 610 METER WINO DOSE RATE A
ORY COUNT RATE CI/SEC (RAD /HR)
N VE SPEED
-G gygg3 cpm OUT VENT
- 10 (cfm)
-l
~~
('
pA 8
-- 10
-- 10 200,000 :-
-- 8
--E
- - 10 i
-.- 10-2
-O 8
710 7.
.,_go-3
- 100, 5
--10*
80,000--
-C 2 10" 7o, coo..
110
}
/
--10
/h 50,000--
3 v
8
--16 40,000--
-B 3
g
[_
__ ;g7 30,000--
--50
'}
-- I O'*
-- O~ ' '
10 0
=
-- 10'
--A 20,000--
Wind From 610 M 00se Rate Date/ Time Wind Toweres
$tte Soundary Dose Rate gy NOTE If the wind direction was towards 70*-125*, the site boundary q) dose would be the 610 meter dose rate divided by 3.
(.2R/hr + 3 =.067 R/hr).
- 4.4.1 Draw a straight line connecting the data points on scales (1) and (2).
- 4.4.2 Draw a straight line connecting the intersection of scale (3),
from step 4.4.1, with the data point on scale (4).
- 4.4.3 Connect the intersection of scale (5), from step 4.4.2, with l
the data point on scale (6).
- 4.4.4 Read the 610 meter dose rate from the intersection of scale (7),
l caused by step 4.4.3.
4.4.5 Determine the site boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 250' O - 70*
610 Meter Dose Rate 180 250* - 305*
70* - 125' 610 Meter Dose Rate 3
305* - 45*
125' - 225' 610 Meter Dose j
- Corresponds with Procedure Instructions Page 5 of 17 Rev. 2, J.-27 82 l
l
6.
R-26 -dFF SCALE
)
PASQUILL CATEGORY Cl/SEC UNIT G
T O' R/hr @ 6" VENT U' I M UNIT VENT VENT 610 METER WIND
- -F F
R
]
SAMPLE LINE 7
DOSE RATE SPEED 2
- - 10 (CFM)
(RAD /HR)
(MPH) 4 j
---10 200,000
- i g
--E j
8
-10 l
--10s 5
-D
--10'
-10 5
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- -10
-10 100,000 g
3
- -5
-C
-- -10
- -10 4
- -10 E
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_- 10
--10
_go 50,000-l j
.._ g o
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- -10 g
h
-B
- 2
$-10-'
2
" o-2 4
- -10
- - 50
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.._10-2
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m m
_ _ g o-3 10.
--10-3
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i 20,000 10 0 A
Date/Ti@e @
Wind from 6: 0 M Dose Rate m
Wind TowaYds S'.te Boundary Dose By n
PFJ 2080 EPP.006 R-26 -OFF SCALE E.uIBIT B PASOUILL CATEGCRY Cl/SEC 0
UNIT
--G R/hr @ 6" VENT
'O y
!OM UNIT VENT VENT 610 METER WIND
--F O
FLOW SAMPLE LINE R
- 10 DOSE RATE SPEED 7
2 (RAD /HR)
(CFM) clO 200,00C7
_g
-*- E f
I y lOs s
--lo
-O
- - 10 '
s go pO'
- 10" l00,000 --
-- 10a 3
--5
--C
--10 2
glo*
((
- lO
-p-
--1O
-10 MA t
pige g
[
2
--10
-- 10
__ $o
..io 2
- - 10' 3
- -lO'
..go-3 20,000--
-100
--A O
O pate/Ti@me G Wind Free O M Dese Rate Wind Towern to Soundary m sy
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NOTE If the wind direction was towards 70*-125*, the site boundary dose would be the 610 meter dose rate divided by 3.
(.2R/hr + 3 =.067 R/hr).
- 4.4.1 Draw a straight line connecting the data points on scales (1) and (2).
- 4.4.2 Draw a straight line connecting the intersection of scale (3),
from step 4.4.1, with the data point on scale (4).
54.4.3 Connect the intersection of scale (5), from step 4.4.2, with the data point on scale (6).
- 4.4.4 Read the 610 meter dose rate from the intersection of scale (7),
caused by step 4.4.3.
4.4.5 Determine the site boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 250*
O - 70*
610 Meter Dose Rate 180 250* - 305*
70* - 125' 610 Meter Dose Rate _
3 25 J
45*
125* - 225' 610 Meter Dose Rate 305*
- Corresponds with Procedure Instructions Page 7 of 17 Rev. 2, 4-27-82
)
R33-ON SCALE l
610 METER GSLO I
DOSE RATE FLOW RATE WIND fSLO V (RAD /HR)
-lo
- - 10-i
--10 10,000 MPH CATEGORY 6
-8
_-l
- -10 G
-2
-F
- 10-2
_ _lo
--10-3 3
-E
-4 i
. 3 Q10
~
-, j o-5
- -1000
~
-o 4
-10
- -10_4 l
_. g o-6
- 10-5
--10-7
- - l0
--C 3
~
j o-a
-- -10
-8
- 10
'-10-9
-100
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mu
$3
.m 2
- 7 m
.~ =
_ _lo
-7 lo-10
--B 25 po g
Ln
- : 10-a
-; 10-"
4 L
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10
-12 10'
-- 10-9
- - 10 joo
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--A O
Wind From 610 M Dose Rate Date/ Time
!1i n d Towa rds__ _ __ _
Site Boundary Dose Rate
.By..
1133 - ON ' S C A LE PMP 2080 EPP.006 EXHIBIT C I
610 METER,
GSLO OOSE RATE FLOW RATE wing w
(RAO/HR)
.cFM J
hI#SE SPEEO PASOUILL CPM SLO 8
- 10"
+10,000 MPH CAT EGORY
- 10 i-lO.:
p
--I
_q
'10-2 1.F
+
- - 10, 4
-[,o.s
~~
y t o'*
.,.10 3
-[ 10"*
--E
-10
- glO,
-0
-h lO
-1000 4
/
O~
10
--C T 16' N
--10 4
s
-10 0
.. g o-*
[
klO"
.ileo i
-e
_,o:
g
.;10..
ae" J
4,f
- 10'
".'10-8
)
1,-10 0
- - 10
--A Q60MCoseRate@
QwndFran s
i Oate/ Time Mind foueros Site Boundary Dose Rate By O
NOTE If the wind direction was towards 70*-125*, the site boundary dose would be the 610 meter' dose rate divided by 3.
(.2R/hr + 3 =.067 R/hr).
- 4. 4. I' Draw a straight line connecting the data points or, scales (1) and (2).
- 4.4.2 Draw.a straight line connecting the intersection of scale (3),
from step 4.4.1, with the data point on scale (4).
- 4.4.3 Connect the intersection of scale (5), from step 4.4.2, with the data point on scale (6).
- 4.4.4 Read the 610 meter dose rate from the intersection of sdale (7),
caused by step 4.4.3.
4.4.5 Determine the site boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 250*
O - 70*
610 Meter Dose Rate 180 250* - 305*
70* - 125' 610 Meter Dose F '
'~
3 45*
125' - 225*
610 Meter Dose Rate 305*
- Correspec.is with Procedure Instructions Page 9 of 17 Rev. 2, 4-27-82
RIS-ON SCALE (FLOW R ANGES BETWEEN ICFM-1,000 CFM).
i GIO METER
- FLOW RATE WIND i
Cl/SEC DOSE RATE THRU STAE l
CPM RELEASE (RAD /HR)
(cfm) g PASQUILL 6
RATE 7--10
__10-2 WIND 3000 l
CATEGORIES z
--10,z
.- 2
--G
_go-3
- -4
..g
~
-3
- 4
~
~
- :10 3
-- -- 10
- -6
- -E 10-5
_.go-4
- 8
- -10 0
- -0 8
4
-- 10
- -10
-,lo-7
-8
~
10-8
- :10
- - 10
--C
-6 77
-- -- 10
--10-8
~
~
- 20 3
~
.. 40
~
10-7
-10
- - 60 2
10-' '
~
~
ka
'g
-- 10
- 710-8 7
2.Es
-lO-'E a,
.. go m.
..go-9 o
PG
- '3 T
~
- - 10'
--I
- - 10 0
--A g
--10-14 D
Wind from 610 ft Dose Rate Date/ Time l
B.y Wind Towards Site Boundary Dose Rate
R15-ON SCALE I PMP 2080 EPT.0'.
(FLOW RANGES BETWEEN ICFM-1,000 CFM) EXHIBIT D Q=,.
610 METER FLOW RATE WIND Cl/SEC DOSE RATE THRU STAE CPM RELEASE (RAD /HR)
(cfm)
PA' UUlt.l.
RATE 10 2 WINO
}~' s
--1000
--l CATEGORIES 2
2
.;io-3
..o
-4
..p
- 10
rlO'*
s
--10
-LIO'S
~~
6
-E I
- -10 0 0
s
-8
.2
.W gn.1 hlO*'
_. go
--C 3
-- 20
-80 010
l
-rlO'I
- IO-*
-80 1
-10
. e ilO*
4 8
g hlO"3
- 80
- 10
~~
10 " 3
- - 8 0'
..lo-*
'go 4
--I
- - 10 0
-A
. n
@m o.s@e a.c. @
m.,.
- o.. m Wind Tom.res
$1te Soundary Dose Rate II
=.....
NOTE If the wind direction was towards 70*-125', the site boundary dose would be the 610 meter dose rate divided by 3.
(.2R/hr + 3 =.067 R/hr).
- 4.4.1 Draw a straight line connecting the data points on scales (1) and (2).
- 4.4.2 Draw a straight line connecting the intersection of scale (3),
from step 4.4.1, with the data point on scale (4).
- 4.4.3 Connect the intersection of scale (5), from step 4.4.2, with the data point on scale (6).
- 4.4.4 Read the 610 meter dose rate from the intersection of scale (7),
caused by step 4.4.3.
4.4.5 Determine the si*.e boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 180 250' O - 70' 610 Meter Dose Rate 25 0* - 305' 70* - 125' 61d Meter Dose R-
- )
3 305*
45*
125' - 225' 610 Meter Dose Rate
- Corresponds with Procedure Instructions Page 11 of 17 Rev. 2, 4 27 82
__7._.
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STEAM ' JET AIR EJECTOR GLAND SEAL EXHAUST -0FF SCALE GSLO or SJAE
~'
EXHAUST PASQUILL 610 METER CATEGORY FLOW RATE WIND DOSE RATE
--G R/itr @ 6" FROM (RAD /HR)
Mm)
-10,000 (MPH) 3 SJAE/GS
_ _10
--I
-F 2
- - 10 3
77lo 2
4
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- -10,
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- - 10 0 nd Froni 10 M Do SiteBounkary Wind Towards se Rate By
-m.
STEAM JET AIR EJECTOR PMP 2080 EPP.006 GLAND SEAL EXHAUST-OFF SCALE
' EXHIBIT E GSLO or SJAE EXHAUST PASCUILL 610 METER CATEGCRY FLOW RATE WIND DOSE RATE
~~0 R/Hr 6.FROM (RAD /HR)
(cfm)
SPEED 0' O8 j'* N 1 3 SJAE/
10
,*10
--I
--- F r10g 3
7
-LIO2
-g
. 2
--10
.'- 10 '
- - 10, 7.
610
--O 0
glO'
-- 10.,
--1000
-.,- 10
-[10 8 0
-10 0
-C
-hlO-3
- 10 i
-10 0
-8
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- 10-7 c.-io.4
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I
- - iO
= l00
--A
_-iO-3 Q=i Qs L
nd From 10 M Dose Rate Cate/ Time l
Wind fewarcs 5tte 8ouncary Cose state By h
NOTE If the wind direction was towards 70*-125*, the site boundary dose would be the 610 meter dose rate divided by 3.
(.2R/hr + 3 =.067 R/hr).
- 4.4.1 Draw a straight line connecting the data points on scales (1) and (2).
- 4.4.2 Draw a straight line connecting the intersection of scale (3),
from step 4.4.1, with the~ data point on scale (4).
- 4.4.3 Connect the intersection of scale (5), from step 4.4.2, with the data point on scale (6).
- 4.4.4 Read the 610 meter dose rate from the intersection of scale (7),
caused by step 4.4.3.
4.4.5 Determine the site boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 250' 0 - 70' 610 Meter Dose Rate 180 250' - 305*
70* - 125' 610 Meter Dose Rate 3
)
45' 125' - 225' 610 Meter Dose a..e 305'
- Corresponds with Procedure Instructions l
Page 13'of 17 Rev. 2, 4-27-82
R-26-WASTE GAS DECAY TANK RELEASE PASQUILL r
i !
Cl/SEC OUT WIND CATEGORY UNIT VENT UNIT VENT SPEED
~
COUNT 610 METER FLOW RATE (MPH)
RATE DOSE RATE (cfm)
CPM (RAD /HR)
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_ _p
-10
-- -lO 6
- 10 200,000---
I :
H
- -E
-10 '
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- -5
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_-10 20,000--
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-8 610RseRate@
Date/ Tim @e
~
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Wind from Wind Towards Site Boundary Dose Rate By
PMP 2080 EPP.006 R-26-WASTE GAS DECAY TANK REl. EASE EXHIBIT F PASCUILL
=
Cl/SEC OUT WIND CATEGORY UNIT VENT UNIT VENT SPEED a
]
COUNT 610 METER FLOW RATE (MPH)
'l
' '1 RATE DOSE RATE gC9N CPM (RAD /HR)
--I
-F
_;_ lo
$O
., io 200,0007 s
o
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5 T
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g
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((
--10 0
- 8 20,000-t-
- lO'
~~
__4 610QsseRate@
Cate/ Tim @e wind From Wind towards
$1te Boundary Dose Rate By I
I
)
NOTE If the wind direction was towards 70*-125*, the site boundary dose would be '.he 610 meter dose rate divided by 3.
(.2R/hr + 3 =.067 R/hr).
- 4.4.1 Draw a straight line connecting the data points on scales (1) and (2).
- 4.4.2 Draw a straight line connecting the intersection of scale (3),
from step 4.4.1, with the data point on scale (4).
l
- 4.4.3 Connect the intersection of scale (5), from step 4.4.2, with the data point on scale (6).
- 4.4.4 Read the 610 meter dose rate from the intersection of scale (7),
caused by step 4.4.3.
l t
4.4.5 Determine the site boundary dose rate as follows:
Wind Direction Wind Direction Site Boundary (from)
(toward)
Dose Rate 250*
O - 70*
610 Meter Dose Rate 180 250* - 305*
70* - 125' 610 Meter Dose Rate 3
45*
125* - 225' 610 Meter Dose n.
a 305*
- Corresponds with Procedure Instructions Page 15'of 17 Rev. 2,
.t_27 82
If the meteorological tower instrumentation is inoperable, atmospheric conditions may be estimated using the tables below:
WIND SPEED HPH Wind Speed (mph)
Observed Effects on Land 51 Calm, smoke rises vertically 1-3 Direction of wind shown by smoke drift 4-7 Wind felt on face, leaves rustle 8 - 12 Leaves and small twigs in constant motion 13 - 18 Raises dust, loose paper; small branches are moved 19 - 24 Small trees with leaves begin to sway 25 - 31 Large branches in motion 32 - 38 Whole trees in motion; inconvenience felt walking against wind 39 - 46 Breaks twigs off trees; generally impedes walking 47 - 54 Slight damage begins to occur 55 - 63 Trees uprocted 2 64 Widespread damage l
PASCALL Category Sunny Cloudy Cloudy Clear Day Day Night Night l
l Wind 5 10 mph B
C E
F Wind 2 10 mph C
D D
D m
+e Page 16'of 17 Rey. 2, 4 27-82
.e WlHD FROM/TO CONVERSTCN CHART PMP 2080 EPP.006 EXHIBIT H v
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l00
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's
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l INSTRUCTIONS 1.
Obtain wind direction from Unit 1 Control Room Indicator (QR-24 or QR-25).
This is the direction the wind is blowing " FRO't'.
2.
Find this direction on the chart above.
3.
From this point, follow a straight line through the center of the circle to the opposite side. This is the direction the wind is blowing "T0" and the l
direction the plume will be over.
Pa'ge 17 of 17 Rev. 2,4-27-82 i
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INDIANA & MICHIGAN POWER COMPAtlY CCNALD C. CC0K NUCLIAR PL2NT PLANT MANAGER PROCEDURE Index Identification Revision No.l 79 g),
C0mments Number And Cate PMP 2080 EPP.013 Duties of the Individual Who Rey, 1 Discovers an Emergency 6-24-82 Condition EPP.014 Personnel Injury Revision 1 6-15.
EPP.015 Responsibility of the On-Site Revision 1 TP-1,5-27-82 Exp NA Emergency Coordinator 4-29-82 EPP Appendix A Telephone Numbers for Key Revision 2 Plant Personnel 6-1-82
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EPP Appendix B Hospital Assistance Plan Revision 2 3-31-81 EPP Appendix C Radiological Supplement Revision 0 4-1-81 I
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INDIANA & MICHIGAN POWER COMPANY DONALD C. CC0K NUCLEAR PLANT PLANT MANAGER PROCEDURE Index Identification Revision No.I Title Cc=r.ents Numt:er And Date l PMP 2081 EPP.001 Emergency Telephone Rev. 1 Communica tions 6-24-82 EPP.002 Barring of the PABX Revision 0 4-1-81 EPP.003 Follow-Up Off-Site Revision 0 TP-1,4-30-82 Exp NA Communications 4-/.-81 EPP.004 Protective Action Guides Revision 0 (PAGs) and Protective Actions 4-1-01 EPP.005 Personnel Evacuation Revision 1
'N 5-25-82
.)
EPP.006 Activation of the Reentry Revision 0 and Rescue Team 4-1-81 EPP.007 Security Actions During Revision 1 Emergency Conditions 5-5-82 EPP.008 Emergency Medical Plan Revision 0 Guidelines 4-1-81 EPP.009 Health Physics Procedures Revision 0 l
4-1-81 l
EPP.010 Activation of Radiation Revision 0 Monitoring Teams 4-1-81 i,
EPP.011 On-Site Radiological Revision 0 Monitoring 4-1-81 EPP.012 Off-Site Radiological Revision 0 TP-1,2-25-82 Exp N/A Monitoring 4-1-81 EPP.013 Environmental Monitoring Revision 0 TP-1,2-25-82 Exp N/A and Analysis 4-1-81 i
?aca 2
l Rev. Cata 6-d-G
IllDIANA & MICHIGA!! FO'AER COMPANY
~
DONALD C. COOK t;UCLEAR PLANT PLANT MANAGER PROCEDURE Index Identification 8V 5 " N
Ti tle Ccmments Number And Date l l
PMP 2081 EPP.014 Off-Site Dose Assessments Revision 0 TP-1,2-25-82 Exp N/A 4-1-81 EPP.015 Sampling and Analysis of Revision 0 Waterborne Releases 4-1-81 EPP.016 Collection and Analysis of Revision 0 Liquid and Gaseous Samples 4-1-81 EPP.017 Interpretation of Liquid Revision 0 and Gaseous Samples 4-1-81 EPP.018 Transportation Accidents Revision 1
>i Involving Radioactive 6-24-82 Material EPP.019 AEP Emergency Response Revision 0 Organization Activation and 4-1-83 Management EPP.020 Activation and Operation of Revision 0 TP-1,11-16.81 Exp N/A the Technical Support Center 4-1-81 TP-2,3-12-82 Exp N/A (TSC)
TP-3,3-12-82 Exp N/A EPP.021 Activation and Operation of Revision 1 the Operations Staging Area 5-25-82 (05A) and Personnel Accountabili ty EPP.022 Activation and Operation of Revision 1 the Emergency Operations 6-4-82 Facility EPP.023 Activation and Operation of CANCELLED the Emergency Control Center 6-4-82 (ECC) (An Emergency i
Operations Facility) 1 I
EPP.024 Activation and Operation of Revision 1 the Joint Public Information 6-24-82 1
1
~,
Center (JPIC) (An Emergency 3
Operations Facility) p3;3 Rev. data b-)fi-9'i
INDIANA & MICHIGAN POWER CCMPANY CGNALD C. COOK NUCLEAR FLANT PLANT MANAGER PROCEDURE Index Identification Revision No.I Title Comnd Numcer And Date l PMP 2081 EPP.025 Activation and Operation of Revision I the Emergency News Source 6-7.-82 (ENS) (An Emergency Operations Facility)
EPP.026 Use of Stable Iodine for Revision 0 Thyroid Blocking Ouring a 12-31-81 Radiation Emergency
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1 1
i 1
l l
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4 Paga Rev. Cata 6-8Il
-mJ INDIANA & MICHIGAN ?OWER CCMPANY CCNALD C. CC0K NUCLE.;R PLANT PLANT MANAGER PROCEDURE Index Identificacicn Revisien No.1
' i tie C=ents Number And Date i PMP 2082 EPP.001 Emergency Exposure Guidelines Revision 0 4-1-81 EPP.002 Public Information Dissemin-Revision 0 ation 4-1-81 EPP.003 Maintenance of Emergency Revision 0 Records 4-1-81 EPP.004 Personnel Assignments to Revision 0 Emergency Centers 4-1-81 EPP.005 Tests and Exercises Revision 1 6-24-82 EPP.006 Training Revision 0
~4-1-81 EPP.007 Emergency Equipment and Revision 0 Supplies 4-1-81 EPP.008 Maps and Overlays Revision 1 6-24-82 EPP.009 Maintenance of the Emergency Revision 1 Plan Procedures 6-24-82 I
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INDIANA & MICHIGAN ELECTRIC CC'1PANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET P ecedure No. PMP 20E0 EPP.013 Revuien No.
1 j
N l
OUTIES OF THE INDIVIOUAL WHO DISCOVERS AN l
EMERGENCY CONDITION SCCPE CF RE'ASICN Rev.1 - Changed Sinift Operating Engineer to Shift Super /isor.
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?.M? 2080 E??.013
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LIST OF EFFECTI'vT PAGES Page Numbers Revision Number and Date Page 1 of 2 Revision 1, 5-24-22 Page 2 of 2 Revision 1, 6-24-82 l
~.
'4 Page 1 cf 1 Revision 1, 5 21.,:2
?MP 2081 I??.013 3
D* DIANA & MICHIGAN II.EC'"RIC CCM2ANY CONALD C. CCCK NUCLEAR PLANT Ct. IES OF THE D*DIVIDUAL WO DISCOVERS AN EMERGE' ICY CONDITION T
1.0 C BJE--'IVES This procedure specifies the minimum duties of the individual who discovers an incident which could lead to personnel injury and/or damage to plant components.
2.0 RESPCNSI3CITIIS All personnel are responsible for being alert to any unsafe situation which could result in personnel injury and/or damage to plant components.
Upon detection of these emergency conditions, personnel are responsible for innediately notifying the control room of the affected unit and implementing the actions described below.
3.0 INSTRUCTIONS 3.1 Notify the control room of the affected unit by PA or telephone of the following:
3.1.1 Your name.
3.1.2 Type of condition and extent of damage (fire, chlorine release, etc.).
3.1.3 Location of conditions.
3.1.4 Injured personnel.
l 3.2 Take any innediate actions you are qualified to take, such as; l
l 3.2.1 Warn all personnel in the area of the emergency condition l
and location.
3.2.2 Extinguish small fires.
3.2.3 Check injured personnel in an effort to decernine extent of 1.njuries; administer first-aid to the extent qualified.
3.2.4 Close upstream valve in the event of a rupture.
NCE:
ANT VALVI RIARRANGIMENT SECUC 3E I. E IAIELY FI?CR"~i.D TO I"iI AFTEC.r.J UNITS CO m CL RCCM.
(
v Page 1 of 2,,
2evision 1 o-4,-Oc
P.*J 2081 EPP.013
(]
3.2.5 Locate protectire ges: (face masks, etc.) that may be required to respond to the condition.
v 3.2.6 Organize search and rescue teams if the condition prohibits safe entry by a single person.
3.2.7 Cordon off the area.
3.3 Follow instructions issued by the Shift Supervisor.
3.4 If no instructions are given, withdraw to a safe area.
I, 1
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2
+3 1
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(
Retision 1, 5-2*-32
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V INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET pagu, go, PMP 2081 EPP.001 Revision No.
I TITLE EMERGENCY TELEPHONE COMMUNICATIONS i
SCOPE OF REVISION Rev.1 - Revised procedure to include instructions for reaching off-site numbers in the event of local telephone company problems after normal working hours.
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I ju:13 3 '92
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SIGNATURES ORIGINAL R*V I REV.2 Rev.3 LL MhMh PREPARED BY i
QUALITY ASSURANCE V
/
REVIEW INTERFACING DEPARTMENT [ /
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i HEAD CONCURRENCE V
N.A.
[Jd/w v
l DEPARTMENT HEAD U
l APPROVAL N.A.
X/. #
PLANT NUCLEAR SAITIY COMMilTEE
__, _ sp PLANT MANAGER APPROVAL h.I -
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DATE OF ISSUE 3-31-81 6 -A y -84 t
Tona No. PW 2010 msy. 2 l
l
. - -. -. _ - _.. - -. ~..-.... _
PMP 2081 EPP.001 LIST OF EFFECTIVE PAGES
)
Page Numbers Revision Number and Date Page 1 of 3 Revision 1 24-82 Page 2 of 3 Revision 1 24-82 Page 3 of 3 Revision 1 24-82
?.,
J 7
e N
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l Page f of 1 Revision 1, 6-24-82 a-e 1.
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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLA.TT EMERGENCY TELEPHONE COMMUNICATIONS 1.0 OBJECTIVES This procedure provides a description, and guidance in the use of the emergency communications system. This system is provided for use within and outside of the AEP system in the event of an emergency at D.C. Cook.
2.0 RESPONSIBILITIES The Technical Superintendent is responsible for ensuring the operability of this system.
The On-Site Emergency Coordinator (OSEC) is responsible for ensuring timely implementation of this system during an emergency.
3.0 DESCRIPTION
3.1 The DCCNP telephone system presently has the following capabilities for off-site dialing:
3.1.1 Twenty simultaneous circuits to the Bridgman office.
3.1.2 Two microwave circuits to South Bend.
3.1.3 Ten microwave circuits to Ft. Wayne.
3.1.4 Six microwave circuits to Canton.
3.1.5 Two microwave circuits to Benton Harbor.
3.1.6 Five outgoing only extensions off the Bridgman exchange.
These extensions are at the following locations:
3.1.6.1 Chief Security Supervisor's Office.
3.1.6.2 Central Alarm Station.
3.1.6.3 Secondary Alarm Station.
3.1.6.4 Plant Manager's Office.
3.1.6.5 Assistant Plant Manager's (Operations) Office.
3.1.7 One direct extension off the New York Office PABX. This extension is located in the Plant Manager's Office.
Page 1 of 3 Revition 1,6-24-82
- +
m
. ~
')
3.2 Additionally, ten DCCNP extensions may be switched, as described in section 4.5 below, to provide five extensions off each the Canton and South Bend PABX.
3.2.1 The Canton and South Bend Extensions are located in the Emergency Operations Facility (EOF), located at the training building.
3.2.2 The Canton and South Bend extensions can be identified by the markings at the telephone jack.
3.3 In the event of an emergency the class of service on all telephone extensions may be modified, see section 4.1 below, to require DCCNP operator assistance to dial off-site. This action may be desired to restrict outgoing calls in order to control PABX use and information given the public and press.
4.0 INSTRUCTIONS 4.1 If it is desired to restrict all outgoing calls to operator assisted calls, the OSEC should request implementation of PMP 2080 EPP.002.
4.1.1 Outside lines and microwave circuits to other company locations may then be obtained only with operator x) assistance, With the exception of:
4.1.2 The five outgoing Bridgman exchange lines (Chief Security Supervisor's Office, CAS, SAS, Plant Manager's Office, and Assistant Plant Manager's Office) and the five lines each off the Canton and South Bend PABX (if activated, see 4.5 below) will not require operator assistance.
4.2 If outside lines are lost or tied up because of the emergency, the OSEC should request the I&M Executive Assistant to ensure switchboard operators are available for Canton, Benton Harbor, South Bend, and/or Fort Wayne.
4.2.1 Outside lines may then be reached on these exchanges by dialing the operator and requesting an outside.line. These operators may be reached by dialing:
4.2.1.1 Benton Harbor - 72 4.2.1.2 South Bend - 74 4.2.1.3 Fort Wayne - 71 4.2.1.4 Canton - 73 or 71 - 81 Page 2 of 3 Revision 1, 6-24-82 c
or g
. ~
. ~
-3 4.3 Until such time as company operators are available for reaching
. s/
outside lines, the Fort Wayne dispatcher will patch calls through to specific numbers. To use the Fort Wayne dispatcher:
4.3.1 Dial the dispatcher microwave number (listed in Appendix A) and provide the dispatcher with the number to be reached.
4.3.2 The Fort Wayne dispatcher will then dial the number and patch the call through.
4.4 In the event outside calls are placed through the microwave system, return calls to DCCNP are also expected to be needed through this system. The return caller must be provided with the appropriate company switchboard telephone number (listed in Appendix A) and the DCCNP extension to be connected to.
4.5 Additional circuits to outside lines of other AEP locations may be provided by activating the five South Bend and five Canton PABX extensions.
4.5.1 Telephones for these extensions may be located in the EOF Locker in the training building. Dial type telephones must be used on the Canton circuits.
4.5.2 These extensions are activated, all at one time, by positioning the "Ctn/Sbad" toggle switch in the position x
..)
away from the PABX cabinet. This switch is located in the PABX room next to the Plant Manager's conference room.
4.5.3 Once the "Cta/Sbdn" switch is repositioned, all ten circuits are switched from the DCCNP PABX to the Canton or South Bend office.
4.5.4 To dial another company office, do so as proper from the Canton or South Bend office.
l 4.5.5 To obtain an outside line, dial 9 for outside dial tone, then dial the desired number as if dialing from the Canton or South Bend area.
l NOTE: THE DIRECT CANTON EXTENSIONS WILI. NOT OPERATE WITH PUSHBUTION PHONES, DIAL TYPE TELEPHONES MUST BE USED.
l l
I~
Page 3 of 3 Rev.ipion 1,6-24-82 l
l
~. - - -
J INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT m
e PROCEDURE COVER SHEET Procedure No.PMP 2081 EPP.018 Revision No.1 TITLE TRANSPORTATION ACCIDENTS INVOLVING RADI0 ACTIVE MATERIAL SCOPE OF REVISION Rev.1 - Clarified procedure. Added Exhibit B, " Roster of the Signatories of the Transportation Agreement."
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SIGNATUPIS ORIGINAL R*V I REV.2 Rev.S 2 e p A9 PREPARED BY
/g MM QU ASSURANCE _
INTERFACING DEPARTMENT //
j/C U4 HEAD CONCURRENCE
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APPROVAL N.A.
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PLANT NUCLEAR j
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SATETY COMMITTEE PLANT MANAGER
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__, ((M APPROVAL DATE OF ISSUE 3-31-81 6-Az/ -gA Fonn No PM12C10.I. Ezv. 2
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LIST OF EFFECTIVE PAGES t
._s Page Number Revision Number And Date Page 1 of 4 Revision 1,6-24-82 Page 2 of 4 Revision 1,6-24-82 Page 3 of 4 EXHIBIT A Revision 1,6-24-82 Page 4 of 4 EXHIBIT B Revision 1,6-24-82 4
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Page 1 of 1 Rev. 1,6-24-82 3
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PMP 2081 CPP.018 7
INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT TRANSPORTATION ACCIDENTS INVOLVING RADIOACTIVE MATERIAL 1.0 OBJECTIVES This procedure provides instructions to control and minimize damage and personnel injuries resulting from transportation accidents involving radioactive materials on-site, and for initiating or receiving requests for such assistance off-site.
2.0 RESPONSIBILITIES The Shift Supervisor (S.S.) is responsible for ensuring that appro-priate assessment and protective actions are implemented.
3.0 INSTRUCTIONS 3.1 For on-site transportation accidents, the S.S. shall perform the
.N.
following functions:
3.1.1 Contact the Main Guard House and instruct the Shift Security Supervisor (or Senior Security Guard present) to take the following precautionary actions:
3.1.1.1 Stop all pedestrian and vehicular traffic entering the plant site.
3.1.1.2 Dispatch necessary security patrols to control traffic in and around the accident site, and to keep all unauthorized personnel at least 50 feet away from the scene of the incident.
3.1.1.3 Keep the Control Room advised on the situation at the scene.
3.1.2 Contact Radiation Protection and request that Radiation Monitoring Teams be dispatched to the accident scene to determine and report the extent of radiation contamination.
l 3.1.3 Based upon results of radiation surveys, take the following actions :
3.1.3.1 For any on-site transportation accident involving a radiation release:
Declare an Unsual Event and implement PMP 2080.EPP.001, Emergency Plan Acitivation and Condition Classification.
Page 1 of 4 Revision 1, 6-24-82
'3 3.1.3.2 Fof any on-site transportation Ac :ident involving no release of radioactivity:
Instruct the Shift Security Supervisor to return p hnt traffic flow to normal and to handle the accident in accordance with standard accident investigative procedures.
NOTE: ANY VEHICLE TRANSPORTING RADIOACTIVE MATERIAL INVOLVED IN AN ACCIDENT MUST BE ESCORTED INTO THE PROTECTED AREA BY SECURITY FOR INSPECTION.
3.1.3.3 Ensure that injured personnel are transported to Memorial Hospital, St. Joseph, Michigan, as necessary.
3.1.3.4 Report all significant information concerning the accident to the Plant Manager (or Alternate).
3.1.3.5 Record all significant information on the accident.-
in the Shift Supervisor's Log.
3.2 For accidents occurring off-site, perform the following functions:
3.2.1 Provide radiation protection assistance to the Berrien County Sheriff's Department and the Michigan State Police as s
requested of the Plant Manager by these organizations.
i NOTE:
D. C. COOK SUPPORT FOR ACCIDENTS OCCURRING OFF-SITE SHALL BE LIMITED TO TECHNICAL ASSISTANCE / ADVICE IN THE AREA 0F RADIATION PROTECTION. LOCAL LAW ENFORCEMENT AGENCIES ARE RESPONSIBLE FOR IMPLEMENTING OTHER NECESSARY ACTIONS.
3.2.2 If assistance from other utilities is needed for l
transportation of nuclear materials:
3.2.2.1 The Plant Manager or his assistant shall initiate the Voluntary Assistance Agreement By and Among i
l Electric Utilities Involved in Transportation of l
Nuclear Materials as listed in Exhibit B.
This I
assistance may be obtained by telephoning a participating utility, specifying the type and duration of the assistance requested, and provide general directions when the assistance is confirmed.
3.2.2.2 Initiate and assure completion of EXHIBIT A, l
ATTACHMENT A TO THE VOLUNTARY ASSISTANCE AGREEMENT.
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Revision 1, 6-24-82
PMP 2081 EPP.018 EXHIBIT A ATTACHMENT A TO THE VOLUNTARY ASSISTANCE AGREEMENT Requesting Company Letterhead Date 19__
(Name and Address of Responding Company)
This letter confirms the telephone conversation on (insert date and time) between our and your in which our company requested assistance pursuant to the terms of the Volun-tary Assistance Agreement By and Among Electric Utilities Involved in Transpor-tation of Nuclear Materials dated November 1, 1980, and your company agreed to provide assistance pursuant to that Agreement s
Please acknowledge your agreement to the foregoing by signing and returning to me the enclosed copy of this letter.
Responding Company Name and Requesting Company Name and Address Address l
Corporate Officer Signature Corporate Officer Signature and Date l
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ROSTER OF THE SIGNATORIES OF THE TRANSPORTATIOW ACREEMENT x
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Alabama Power Company' 4
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Arkansas Power & Light Company s
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Commonwealth Edison s
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Detroit Edison 5.
Duke Power Company 6.
Gulf States Utilities Company 7.
Indiana & Michigan Electric Company 8.
Long Island Lighting Company 9.
Mississippi Power & Light Company 10.
Notheast Utilities 11.
Northern States Power Co.
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Public Service Company of Colorado
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Rochester Gas & Electric Corporation 14.
South Carolina Electric & Gas Company
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Texas Utilities G,enerating Company 16.
Virginia Electric ^and Power Company WashingtonPublicPowerSupplySysted.
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18.
Wisecasin Public Service Company Page 4 of 4
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INDIANA & MICHIGAN ELECTRIC COMPANY O
DONALD C. COOK NUCLEAR PLANT 1
PROCEDURE COVER SHEET Procedure NSMP 2081 EPP.024 Revimon No.I' TITLE ACTIVATION AND OPERATION OF THE JOINT PUBLIC INFORMATION CENTER (JPIC) (AN EMERGENCY OPERATIONS FACILITY)
SCOPE OF REVISION Rev.1 - Combined Recovery Center and Emergency Control Center to Emergency Operations Facility. Included latest Public Affairs revision into this Procedure.
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PMP 2081 EPP.024 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT ACTIVATION AND OPERATION OF THE JOINT PUBLIC INFORMATION CENTER (JPIC) 1.0 OBJECTIVES Tb's procedure is a working procedure for Public Affairs personnel.
It is included in the plant procedures for information purposes only.
It specifies conditions for activating and locating the Joint Public Information Center; describes staffing, operation, and precautions; and directly addresses public dissemination of information.
2.0 RESPONSIBILITIES Responsibilities for information dissemination are specified in the attached procedure.
3.0 INSTRUCTIONS Specific instructions for Public Affairs personnel are included in the attached EXHIBIT A, PLAN FOR PUBLIC INFORMATION DISSEMINATION AND OPERATION OF JOINT PUBLIC INFORMATION CENTER (JPIL), and in applicable Indiana & Michigan Electric Company procedures and American Electric Power Company procedures.
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PMP 2081 EPP.024 EXHIBIT A JPIC-1
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PLAN FOR PUBLIC INFORMATION DISSEMINATION AND OPERATION OF THE JOINT PUB UC INFORMATION CENTER (JPIC) 12.8 PUBLIC INFORMATION 12.8.1 Public Dissemination of Information Indiana & Michigan Electric Company (I&M) will assist the Berrien County Sheriff's Department and the Michigan Department of the Public Health in the distribution of educational information to the public within the Emergency Planning Zone (EPZ). Such information will include the warning methodology to be used in notification of the public, education information on radiation, personnel or agencies to be contacted for additional information, sheltering, and evacuation routes to be used in the event of a nuclear incident.
12.8.2 Public Affairs Organization
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In the event of any significant incident at the Donald C. Cook Nuclear Plant, it is the policy of I&M to promptly notify county, state and federal officials, and the public through the news media, as determined by the appropriate corporate officers of I&M and its parent firm, American Electric Power Company (AEP).
For Crisis Communications For many non-routine events, especially those involving even minute quantities of radiation, the NRC Office of Public Affairs has shown that it is likely to make a public announcement of even j
non-reportable events. The utility industry's experience has l
consistently shown that off-site public reaction is more favorable l
when such information originates with the utility, along with
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notification of appropriate county, state and federal agencies prior to any public announcement. The purpose of notifying the appropriate agencies prior to any public announcement is to ensure that the information presented is fully understood by all parties and does not conflict with reports and information transmitted to any agencies by other sources. Press briefings will be arranged in conjunction with appropriate agency officials to permit a consistent and timely exchange of information.
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12.8.3 JPIC Activation and Location Initial steps to activate a Joint Public Information Center (JPIC) should begin at the time the utility's near-site emergency response l.
centers are activated, to include the Technical Support Center (TSC),
Operations Staging Area (OSA), and Emergency Page 2 og 4 Revision 1,6-24-82
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PMP 2081 EPP.024 EXHIBIT A (CONT.)
JPIC-2 Operations Facility (EOF). The Benton Harbor Division Administrative Assistant will handle the physical arrangements of setting up the JPIC. Prior to the activation of the JPIC, all information about the incident will come from the Energy Information Center manager, or designee.
JPIC Location If it is determined that the Plant incident requires establishment of a JPIC to handle inquiries, the preferred location would be the Lake Michigan College Community Center in Berrien County, MI about 11 miles northeast of the site boundary. This location would be adequate to accommodate both a large and small number of news media representatives. Should the LMC area be declared under evacuation, then the Holiday Inn in Niles, MI, about 20 miles south-east of the Plant, will be used.
Both facilities could be readied for use on short notice at any time and could be, utilized for an extended period of time if need be by 1
utility, county, state and other agencies dealing with an incident at the Plant. The Benton Harbor Service Building, located one mile from LMC, would serve as a processing and logistics Center for all incoming utility and industry representatives. All news media
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JPIC. Security will be provided by I&M.
Utility Public Affairs Director at JPIC The ranking public affairs representative frem AEP or I&M, or designee, at the JPIC should maintain direct contact with utility management dealing with the emergency to develop guidance on policy, supervise all communications from the utility, and relay information to other appropriate utility employees. He should also coordinate information at the JPIC with counterparts from county, state and federal agencies and others involved with the emergency.
Utility Spokesperson One knowledgeable representative froa the nuclear section of AEP, or designee, at the JPIC will be identified as the official utility spokesperson.for the emergency.
It is of utmost importance that this
" single spokesperson" concept be carried out in fact to avoid even minimal contradictions of detail or analysis. The spokesperson will be responsible for any routine interviews granted, for being the source of utility statements quoted in press statements or releases, and for representing the utility at formal press briefings to answer i
technical questions about the incident.
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1 PMP 2081 EPP.024 EXHIBIT A-(CONT.)
JPIC-3 O
Community Relations and Government Affairs Employees responsible for keeping government officials and community leaders updated must also receive prompt information. Those who are staying in touch with state and federal officials may remain at their offices or, as appropriate, serve at one of the near-site facilities.
The community relations representative should have a special briefing room at the Lake Michigan College Community Center (JPIC) and be updated by public affairs employees at the JPIC. The Communications Coordinator will be responsible for ensuring the adequate flow of information to appropriate governmental agencies. In addition, he may also arrange to have representatives from the NRC, and other appropriate agencies or companies, present during press briefings.
Inter-Agency Liaison One of the critical needs during any emergency will be for all in-volved organizations -- utility, county, state -- to have the same information and to have a central focus for quickly controlling rumors and pooling information sources. An Inter-Agency Liaison Committee, composed of representatives from the utility, county and the Governor's Office, will provide this focus and serve as a central tracking point for reaching officials, dealing with rumors, etc.
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This liaison committee will be located at the JPIC. Other organiza-tions, such as the NRC, the Institute of Nuclear Power Operations (INPO), Westinghouse, etc., also may be located at or near the JPIC and be in consultation with liaison committee.
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Page 4 of,4 Revision 1,6-24-82
INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT a
'j PROCEDURE COVER SHEET Procedure No.PMP 2081 EPP.025 I
Revision No.
TITLE ACTIVATION AND OPERATION OF THE EMERGENCY NEWS SOURCE (ENS) (AN EMERGENCY OPERATIONS FACILITY)
SCOPE OF REVISION Rev.1 - Incorporated most recent revision of the I&M Public Affairs precedure.
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DONALD C. COOK NUCLEAR PLANT ACTIVATION AND OPERATION OF THE EMERGENCY NEWS SOURCE (ENS) 1.0 OBJECTIVES This procedure is a working procedure for Public Affairs personnel and is included in plant procedures for information only.
It describes the activation and operation of the Emergency News Source, the single source for release of information to the public during the initial stages of an incident which might endanger or alarm the public.
2.0 RESPONSIBILITIES The Cook Energy Information Center Manager is responsible for setting up and operating the ENS in accordance with EXHIBIT A, PLAN FOR REPORTING NON-ROUTINE INCIDENTS AT COOK NUCLEAR PLANT.
3.0 INSTRUCTIONS Upon notification by the On-Site Emergency Coordinator or communications personnel of any incident that may endanger or alarm the public, or on
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sounding of the Nuclear Emergency Alarm, the Energy Information Center Manager shall initiate steps to activate the Emergency News Source.
Specific actions to activate and operate the ENS are included in EXHIBIT A and in Public Affairs procedures.
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PMP 2081 EPP.023 EXHIBIT A PLAN FOR REPORTING NON-ROUTINE INCIDENTS AT COOK NUCLEAR PLANT (For use prior to operation of Joint public Information Center)
This is the procedure for the internal and external steps to be followed regarding non-routine incidents at the Donald C. Cook Nuclear Plant. This procedure is intended for use until such time as the Joint Public Information Center becomes operational, which is a.cicipated to be about four hours after the incident.
SEE THE EMERGENCY CALL LIST ON FOLLOWING SHEETS (CONTAINED IN IN-PLANT PROCEDURES ONLY) 1.
Immediately following his report to the NRC, the Cook Plant Manager, or his designated alternate, will provide the Energy Information Center Manager, or his designated alternate, with all available information of any incident that may endanger or alarm the public. While such an incident may not require an official report to the NRC, at the outset it could result in a crisis situation if not responded to.
If the Energy Information Center Manager, or his designated alternate, are not available, the I&M Public Affairs Director or Information Services Manager should be contacted in Fort Wayne.
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NOTE:
Concurrent with the above actions, the Cook Plant Manager is also notifying:
1.
The AEP Executive Vice President-Construction and New York Engineering or Assistant Vice President and Chief Nuclear Engineer, who will notify the AEP Public Affairs Manager-New York, and 2.
The I&M Executive Assistant-Power Plants, or designated alternate, who will notify senior I&M management.
2.
Cook Energy Information Center Manager, or designated alternate, will l
immediately advise I&M Public Affairs Department--Fort Wayne of incident.
I&M Public Affairs-Fort Wayne will notify AEP Public Affairs-Columbus and a decision will be made, in consultation with the Energy Information Center Manager, on whether or not a statement should be issued.
l NOTE:
AEP Public Affairs-Columbus will notify Vice President of Governmental Affairs-Washington that an incident has occurred and provide updates to that office as developments warrant.
3.
Based on information provided by the plant, and upon concurrence with AEP Public Affairs-Columbus and I&M-Fort Wayne, the Energy Information Center Manager will respond briefly to any media inquiries.
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Page 2 of 3 Revision 4,6-24-82
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PMP 2081 EPP.025 EXHIBIT A (CONT.)
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anticipated that in the initial period after a major incident the Energy Information Center Manager will receive his basic information from the plant and that his responses to the media will be based on that information and approved, as feasible, by AEP Public Affairs-Columbus and I&M Public Affairs-Fort Wayne.
4.
AEP Public Affairs Manager-New York, or designated alternate, who serves as liaison to the Incident-Initial Assessment Group (IAG), will keep Energy Information Center Manager and I&M Public Affairs-Fort Wayne advised as events warrant or as information is developed.
5.
As the incident develops and/or as written statements are prepared for release or response to media queries, the statements should be sent by the originator, via telecopier or telephone, to the following:
a.
Energy Information Center Manager-Bridgman, Mich.
b.
I&M Public Affairs Department-Fort Wayne c.
Cook Plant Manager-Bridgman, Mich.
d.
AEP Public Affairs-Columbus e.
AEP Public Affairs-New York 6.
As required, the Energy Information Center Manager will distribute statements to media in Benton Harbor-St. Joseph area, South Bend, AP (Detroit) and UPI (Grand Rapids). If Energy Information Center Manager or back-up is unavailable, Benton Harbor and South Bend adminstrative assistants should distribute approved releases.
7.
I&M Public Affairs-Fort Wayne will provide copy for statements to the following:
a.
I&M President b.
Public Affiars Director, Michigan Power Company, Three Rivers c.
NRC's Region III Office, Glen Ellyn, ILL.
(Public Affairs Office)
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When the Joint Public I'nformation Center becomes operational, all media representatives should be referred to the center. Operation of the center is covered in a separate procedure.
l Page 3 of, 3 l
Revision 1, 6-24-82
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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure No. PMP 2082 EPP.005 Revision No.1 TITLE TESTS AND EXERCISES SCOPE OF REVISICN Rev.1 - Clarified procedure, r
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TESTS AND EXERCISES 1.0 OBJECTIVES This procedure addresses the requirements for: types and frequencies of tests, drills and exercises; advance planning required to conduct successful tests, drills or exercises; agreements that must be made between on-site and off-site agencies (in level of participation, date and time, and if the activity is to be pre-announced); preparation of scenarios; and critiques and corrective actions.
2.0 RESPONSIBILITIES The Plant Emergency Planning Coordinator is responsible for the successful completion of tests, drills and exercises. Each emergency organization member is independently responsible for those actions delegated to him by the Emergency Plan Procedure.
3.0 PRECAUTIONS AND LIMITATIONS, 3.1 One exercise or drill may fulfill a combination of several of the f}
requd. red elements listed in 4.1 through 4.3 below. Exercises or drills may be announced or unannounced, should periodically be held on backshifts or normal non-working days, and should simulate a variety of possible emergencies that could occur.
3.2 All actions to alter plant conditions will be simulated, unless authorized otherwise in writing by the Plant Manager. The Shift Supervisor or On-Site Emergency Coordinator may terminate H -
drill or exercise whenever he feels actual conditions warranc such action.
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4.0 INSTRUCTIONS 4.1 Tests i
4.1.1 Conduct communications tests with State and Local Emergency
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Operations Centers monthly.
4.1.2 Security shall keep records of such tests being performed.
l 4.2 Drills 4.2.1 Conduct drills for each of the following areas as specified:
l 4.2.1.1 TSC/ EOF Communications - Quarterly 4.2.1.2 Fire Emergency - Quarterly Page 1 of 5 Revision 1, 6-24-82 l
4.2.1.3 Radiological Monitoring Team Activation - Quarterly 4.2.1.4 Health Physics - Quarterly 4.2.2 Prior to conducting any Drill, prepare a scenario incleding (as a minimum):
4.2.2.1 The basic objective (s) of the Drill.
4.2.2.2 The date(s), time period, place (s), and participating organizations.
4.2.2.3 Simulated events that could occur during an actual emergency.
4.2.2.4 A time schedule of simulated events.
4.2.3 Coordinate the Drill with DCCNP management, operations personnel and corporate management.
4.2.4 Determine that adequate resources to conduct the Drill are available.
4.2.5 Conduct a critique as soon as possible after the Drill for the purpose of evaluating participant performance.
s 4.2.6 Prepare a written report indicating:
4.2.6.1 Whether or not the basic objectives of the drill were accomplished.
4.2.6.2 Specific areas for improvement and recommendations.
4.2.6.3 Areas where participants performed well.
4.2.7 Retain sufficient information to document the drill per PMP 2082 EPP.003, Maintenance of Emergency Records.
4.2.7.1 The Plant Emergency Planning Coordinator shall l
maintain EOF and TSC drill documentation.
4.2.7.2 The Fire Protection Coordinator shall maintain fire drill documentation.
4.2.7.3 The Plant Radiation Protection Supervisor shall maintain Radiological monitoring and Health Physics drill documentation.
l 4.3 Exercises 4.3.1 Conduct exercises at least annually for each of Uhe following situations:
4.3.1.1 Personnel Injuries Page 2 of'5 Revision 1, 6-24-82 i
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4.3.1.2 Activation of the Emergency Plan for at least one of the following categories:
4.3.1.2.1 Unusual Event 4.3.1.2.2 Alert 4.3.1.2.3 Site Emergency 4.3.1.2.4 General Emergency 4.3.2 Prior to conducting any exercise, prepare a scenario including (as a minimum):
4.3.2.1 The basic objective (s) of the exercise.
4.3.2.2 The date(s), time period, place (s), and participating organizations.
4.3.2.3 Simulated events that could occur during an actual emergency.
.t 4.3.2.4 A time schedule of simulated events.
4.3.2.5 A narrative summary describing the conduct of the exercise to include such things as simulated casualties
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offsite fire department assistance, rescue of personnel, utilization of protective clothing, deployment of radiation monitoring teams, public information activities.
4.3.2.6 Arrangements for qualified observers and identification of observers.
4.3.3 Coordinate the exercise with DCCNP management and operations personnel, offsite support agencies, and individuals from other nuclear Facilities and corporate management, as appropriate.
4.3.4 Determine that adequate resources to conduct the exercise are available.
4.3.5 Contact local news media personnel during the planning stage and inform them of exercise plans.
4.3.6 Provide the appropriate number of observers to evaluate and critique the exercise including representatives of participating offsite agencies and personnel familiar with the emergency plans.
4.3.7 Instruct the observers to perform the following functions before, during, and after the exercise.
Page 3 of 5 Revision 1,6-24-82 4
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4.3.7.1 Develop a scenario critique sheet for their specific area of observation.
4.3.7.2 During the exercise, distribute simulated information provided by the planner necessary for the participants to effect actions appropriate to the simulated accident.
4.3.7.3 Throughout the entire exercise, note pertinent individual, group, and equipment performance.
4.3.7.4 Upon completion of the exercise, meet with the appropriate participants to review and discuss the performance and complete the scenario critique sheets listing comments and recommendations.
4.3.8 Conduct the exercise by implementing the scenario.
4.3.9 During the exercise the following items should be accomplished:
4.3.9.1 Demonstration of the individual's abilities to utilize actual emergency equipment.
4.3.9.2 Familiarize personnel with planned emergency procedures and actions.
4.3.9.3 Identify training needs.
4.3.9.4 Disclose any deficiencies in planning so that appropriate changes can be made in the Emergency Plan Procedures.
4.3.9.5 Check telephone and radio communications with outside agencies.
4.3.9.6 Include notification, site access control (as applicable) and radiation protection in exercises for expected roles of hospital, fire rescue / ambulance and police personnel.
4.3.9.7 Identify those key personnel (by name and title) responsible to coordinate support activities from offsite.
4.3.10 Conduct a critique as soon as practicable after the exercise.
Comment on:
4.3.10.1 Individual, group, and equipment performance.
4.3.10.2 Specific comments and recommendations to improve operations.
4.3.10.3 Brief summation of the overall exercise.
Page 4 of 5 Revision 1,6-24-82
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4.3.11 Request participating offsite agencies to conduct a similar critique of their performance, following the exercise, where appropriate.
4.3.12 Upon completion, submit the evaluation to plant management and to those responsible for updating the emergency plan and emergency plan procedures.
4.3.13 Retain sufficient information to document the test or exercise per PMP 2082 EPP.003, Maintenance of Emergency Records.
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Page 5 of S Revision 1,6-24-82 I
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yo INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT n
PROCEDURE COVER SHEET Padre No. PMP 2082 EPP.008 Revision No.
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DONALD C. COOK NUCLEAR PLANT MAPS AND OVERLAYS 1.0 OBJECTIVES This procedure describes maps being developed to assist in emergency operations at D.C. Cook Nuclear Plant. The procedure describes the use of the map overlays as applied to existing as well as future maps.
2.0 RESPONSIBLE INDIVIDUALS The Plant Emergency Planning Coordinator is responsible for developing the maps and overlays and for ensuring that these decisional aids are kept complete and current.
3.0 DESCRIPTION
3.1 Topographical maps of the 10 and 50 mile radius have been distributed to the following locatio.ns:
3.1.1 Technical Support Center r
i 3.1.2 Emergency Operations Facility 3.1.3 Michigan State Police EOC in Lansing and New Buffalo 3.1.4 Michigan Department of Public Health 3.1.5 American Electric Power Service Corporation 3.2 These maps shall indicate:
3.2.1 Population centers out to 50 miles 3.2.2 Hospitals out to 10 miles 3.2.3 Sectors, 22\\* wide, for selective evacuation purposes.
3.3 A third map has been provided, with overlays, to enable estimation of dose rate at any given location within 10 miles. These overlays l
are developed according to stablity class. Each continuous loop originating at the plant represents a projected constant dose rate; and the dose rate represented by each continuous loop is one-half l
the dose rate of the adjacent interior loop and twice the dose l
rate of the adjacent exterior loop.
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Page 1 of 2 Revision 1,6-24-82
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3.4.1 Select the overlay for the appropriate stability class, and using the map of the 10 mile radius, (black and white road map, not topographical, approximately 30" x 30") place the centerline of the plume in line with the existing wind direction. All loops on the overlay should originate at the plant.
3.4.2 Determine the dose rate at a point close to one of the constant dose rate lin2s by:
3.4.2.1 Calculating the dose rate at the site boundary.
(The imminent loop represents 1/2 the site boundary dose in the direction 0 to 70' and 125' to 225';
and represents the site boundary dose from 70' to 125*) or; 3.4.2.2 Measuring the dose rate at a point in the field.
3.4.3 The dose at any other point in the 10 mile radius is approximated by multiplying the known dose rate by one-half for each loop crossed moving away from the plant; or multiplying the dose rate by two for each loop crossed moving towards the plant.
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PROCEDURE COVER SHEET Procedure No. PMP 2082 EPP.009 Revision No. 1 TITLE MAINTENANCE OF THE EMERGENCY PLAN PROCEDURES SCOPE OF REVISION Rev. 1 - Minor changes.
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LIST OF EFFECTIVE PAGES Page Numbers Revision Nr.cher and Date Page 1 of 5 Revision 1 24-82 Page 2 of 5 EXHIBIT A Revision 1 24-82 Page 3 of 5 EXHIBIT A Revision 1 24-82 Page 4 of 5 EXHIBIT B Revision 1 24-82 Page 5 of 5 EXMIBIT C Revision 1 24-82 i
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Page 1 of 1 Revision 1,6-24-82
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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT MAINTENANCE OF THE EMERGENCY PLAN PROCEDURES
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1.0 OBJECTIVE This procedure defines periodic checks to insure the Emergency Plan Procedures are maintained up to date.
2.0 RESPONSIBILITIES The Plant Manager is responsible for ensuring the checklists included in this procedure are completed at the proper intervals.
The Plant Emergency Planning Coordinator is responsible for accomplishing Emergency Plan Procedure changes and updstes on a continuing basis and coordinating the annual PNSRC Emergency Plan Procedure review and approval.
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4.0 INSTRUCTIONS
[) The Plant Manager shall ensure that: 4.1 The checklists cited below are completed as per the specified inte rval. 4.1.1 EXHIBIT A, EMERGENCY PREPAREDNESS ANNUAL CHECKLIST 4.1.2 EXHIBIT B, EMERGENCY PREPAREDNESS SEMI-ANNUAL CEECKLIST. 4.1.3 EXHIBIT C, EMERGENCY PREPAREDNESS QUARTERLY l CHECKLIST. 4.2 Arrangements are made for an independent audit, every 24 months, of emergency preparedness. This audit shall include but not be limited to: l 4.2.1 The Emergency Plan 4.2.2 The Emergency Plan Procedures 4.2.3 Training 4.2.4 Drills and Exercises 4.2.5 Facilities and Equipment 4.3 The Emergency Plan Procedures are reviewed at least annually by the PNSRC to ensure their applicability. l Page 1 of 5 Revision A, 6-24-82 r
PMP 2082 EPP.009 EXHIBIT A bt EMERGi.NCY PREPAREDNESS ANNUAL CHECKLIST Date Initiated Date Completed Review Items: Source documents have been reviewed for changes and EPP updated as necessary; (e.g., Reg. Guides, 10 CFR 20) Remarks: Plant Emergency Planning Date Coordinator Referenced Health Physics Procedures have been reviewed, and all recent changes are reflected in the Emergency Plan Procedures. Plant Radiation Protection Date Supervisor Reviewed and approved documentation indicating personnel in Emergency Organization have received required training in past year. Remarks: Plant Emergency Planning Date Coordinator Reviewed and approved documentation indicating personnel not in the Emergency Organization (including non-badged personnel) have received required training in past year. Remarks: Training Supervisor Date Page 2 of 5 Revision 1,6-24-82 e s -we-
... - -.... - ~ - ~.. o. PMP 2082 EPP.009 EXHIBIT A (CONT.) O Veritied letters.of' agreement with outside agencies are current. Plant Emergency Planning Date Coordinator EPP submitted to PNSRC and Plant Manager for annual review. Remarks: Plant Emergency Planning Date Coordinator
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t D PMP 2082 EPP.009 EXHIBIT B n EMERGENCY PREPAREDNESS SEMI-ANNUAL CHECKLIST Date Initiated Date Completed Review Items: Conduct randon review of copies of the EPP for content of latest revisions (minimum of 3 manuals, if errors are found review an additional 3, if errors still found, review all manuals). Plant Emergency Planning Date Coordinator Reviewed and resolved discrepancies noted in previous EPP drills. Remarks: Plant Emergency Planning Date Coordinator ? Reviewed EPP for technical content and
- accuracy, i.e., sampling methods, protective measures, significant levels.
Plant Radiation Protection Date Supervisor Verified phone listings fo'r key j personnel and support agencies listed in Appendix A. 1 Plant Emergency Planning Date Coordinator l l l J l 4 Page 4 of 5 Revision 2, 6-24-82 ~. A y ...,. ~ - - -, m ,___.___z.
7 _ y PMP 2'082 EPP.009 EXHIBIT C O EMERGENCY PREPAREDNESS QUARTERLY CHECKLIST Date Initiated Date Completed Review Items: Inventories of all equipment listed in Equipment Checklists of PMP 2082 EPP.007 completed. Plant Radiation Protection Date Supervisor Radiation detection equipment is within required calibration per Health Physics Procedures, and located per inventories. Plant Radiation Protection Date Supervisor Emergency personnel assignments in PMP 2082 EPP.004 are up to date. Plant Emergency Planning Date Coordinator Remarks: O Page 5 of 5 Revision 4, 6-24-82 i -}}