ML20236C595
| ML20236C595 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/13/1987 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20236C566 | List: |
| References | |
| PROC-870713, NUDOCS 8707300123 | |
| Download: ML20236C595 (131) | |
Text
_ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _
i i l..,
4 , -
l" , i l July.8, 1987'
'U.S. NRC-Washington, Document Cntl Desk h s <
L l POINT BEACH-NUCLEAR PLANT
, EMERGENCY PLAN-IMPLEMENTING PROCEDURES (EPIPs)
-i The following revised procedures are attached.and should be inserted into your '
manual. Please destroy the revisions removed'from.your manual.
- 1. EPIP 1.1,- " Plant Operations Manager Initial Response," Revision 7
- 2. EPIP 1.2, '" Event' Classification," Revision 17
~3. . EPIP 6.10 - " Personnel Assembly and Accountability," Revision 8
Revision 8 3 '5. EPIP 7.3.2, " Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant," Revision 19
- 6. EPIP-7.3.3, " Post-Accident Sampling of Containment Atmosphere," Revision 18
- 7. EPIP 10.1,- " Fire Fighting," Revision 3
- 8. EPIP Appendix A " Emergency Plan - Abbreviations & Acronyms," Revision 0.
(Insert this appendix behind EPIP-25, following the Call Lists.)
The following revised'and new forms are attached and'should be inserted into i
your EPIP manual according to instructions provided.
L 1. .EPIP-6.10a " Accountability Short Form," (Insert'behind EPIP 6.10, and remove EPIP 17).
- 2. EPIP-6.10b " Assembly Area Roster," (Insert behind EPIP-6.10a form,.and remove EPIP 18).
- 3. EPIP-6.10c " Assembly Area Designations," (Insert behind EPIP-6.10b). i
}
- l 8707300123 g70719 zy DR- ADDCK 05000266E PDR \
\
l h l
i l
4 g__,_ .
- n n
- = U
> 07-08-87 EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF_ CONTENTS.
Revision Date
~l 1.0' . CLASSIFICATION & ASSESSMENT l '.1 . Plant Operations Manager Initial Response.. . . . . . . . . . . . . 7 07-08-87 1.2 Event Classification . . . . . . . . . . . . 17 07-08-87 1.3 Offsite Agency Notification- . . . . . . . . 3 ~02-20-87/
1.4 Radiological Dose. Evaluation . . . . . . . . 13 01-05-87 1.5 Protective Action Evaluation . . . . . . . . '12 04-28-87 1 1.6 Radioiodine Blocking & Thyroid Exposure i Accounting . .. . . . . . . . . . . . . . . 3 08-15-84 H 1.7 Core Damage Estimation . . . . . . . . . . . 8 12-30-85.
1.8. Emergency Off-Site Dose Estimations . . . . 10 01-05-87 2.0 : UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.l' - Unusual Event - Immediate Actions . . . . . 7 04-28-87 ;
2.2' Unusual Event - Plant & Company Personnel i Notification . . . . . . . . . . . . . . . 3 06-27-86 1 1
3.0 ALERT IMPLEMENTING PROCEDURES 3 .1 - Alert - Immediate Actions . . . . . . . . . 9 04-28-87
-3.2 Alert - Plant & Company Personnel Notifi-cation . . . . . . . . . . . . . . . . . . 3 06-27-86 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES 4.1 Site Emergency - Immediate Actions . . . . . 12 04-28-87 4.2 . Site Emergency - Plant & Company Personnel Notification . . . . . . . . . . . . . . . 3 06-27-86 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General' Emergency - Immediate Actions . . . '12 04-28-87 5.2 General Emergency - Plant & Company Personnel Notification . . . . . . . . . . . . . . . 3 06-27-86 s
l
[
j Page 2 i
L L I l
Revision Date l
6.0 EVACUATION AND ACCOUNTABILITY 6.1 Limited Plant Evacuation . . . . . . . . . . 4 01-05-87 6.2 Plant Evacuation To Onsite Assembly Areas . . 7 01-05-87 6.3 Plant & Exclusion Area Evacuation To Offiste Assembly Areas . . .. . .. . ... . . . 6 01-05-87 6.4 Energy Information Center Evacuation . . . . . 4 04-28-87 6.5 Technical Support Center Activation . . . . . 10 04-28-87 6.6 DELETED 6.7 Emergency operations Facility Activation . . 6 04-28-87 6.8 Emergency Operations Facility Evacuation . . 1 04-28-87 6.9 Site Boundary Control Center Evacuation . . 0 07-31-86 i
6.10 Personnel Assembly & Accountability . . . . . 8 07-08-87 7.0 CHEMISTRY AND HEALTH PHYSICS RESPONSE & PREPAREDNESS 7.1 Internal Chemistry and Health Physics Personnel Notification / Initial Response 7.1.1 Chemistry and Health Physics On-Site Notification and Response . . . . 9 04-28-87 7.1.2 Chemistry and Health Physics Offsite Notification and Response . . . . 4 03-22-85 7.1.3 Health Physics Protective Actions by Operations Personnel Prior to Arrival of HP Personnel . . . . . . . . . 5 04-28-87 7.2 Health Physics Facility Activation l I
7.2.1 Activation of HP Facilities at Site l Boundary Control Center . . . . . 8 07-08-87 7.2.2 Activation of Chemistry & Health i Physics Facilities at Technical l Support Center / operations Support l Center . . . .. . . . . .. . . . . 8 02-20-87 i 7.2.4 Health Physics Communications . . . 5 04-28-87 7.3 Radiological Survey, Sampling & Analysis 7.3.1 Airborne Sampling & Direct Dose Rate l Survey Guidelines . . . .. . . . 10 04-01-86 7.3.2 Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant . . . . . . . . . . . . . 19 07-08-87 1
-_a_-- - -
+
-/-
I
> i 5
..; t , .L . .
e h ,
Page 3:
[?:
i..,jt.
i Revision 'Date I '73 3'.3 = Post-Accident Sampling of.Contain - . . .
co . ' ment. Atmosphere . . . . .. . . . . 18 -; ~07-08-87 7;3.41 .' Movement of Required. Chemistry
-Equipment & Materials to the-Technical Support Center. counting
' Room &. Mini-Laboratory... . . . . 41 06-27-86 7.3.5 Post-Accident Sampling of the Auxiliary Building'&LDrumming-
, Area Vent Stacks Using the Iso-kinetic Stack Sampling System.. . 3- .04-01-86 714 Emergency' Equipment
n' .
{
7.4.3.1 Use:of; Canberra Model 3100 Series 30 t '!
-Multichannel' Analyzer'to Determine a
" Airborne' Iodine Activities. . . . O' 02-26-82:. -l 8.0 DELETED '
i 9.0 DELETED' 1
10.0 FIREFIGHTING-
- 10.1 . Fire' Fighting . . . . . . .. . . . . . . . 3 07-08-87 11.0 FIRST AID & MEDICAL CARE!
11;1 On-Site:First Aid Assistance . . . .. .. . 6 04-28 . 11.2 ; Injured Person's Immediate Care' . . . . . . 4 04-28-87 11.3 Hospital Assistance- .. . . . . .. . .. . 6 04-28-8't
12.0 REENTRY & RECOVERY PLANNING-
- 12.1- Reentry Procedures for Emergency. Operations 7 02-20 12.2 Personnel' Exposure & Search & Rescue Teams 8 04-28-87 go 12.3. Recovery' Planning. . . . . . . . ... . . . 2 01-05-871.
g -12.4 ' Personnel' Exposure Guidelines . . . .. . . . 4 09-03-85 ot 4
I' l
_2-.-_... - . _ _ _-.
Page 4 Revision'
~
.,. Date-
-13.O PUBLIC-INFORMATION:
'1311' Crisis Communications. . . . . . . . . . . . 6~ ' 01-05-87' I14.0! COMMUNICATIONS'
- 14L2 Paging System Operation . . . . . . . . . . 8 01-05-87 15.0 DELETED
~
L16.0 WISCONSIN ELECTRIC' GENERAL OFFICE PROCEDURES
.16.1- Headquarters Support Notification & Response. . 10 04-28 EPIP APPENDIX'A-Appendix A, Emergency Plan'- Abbreviations & Acronyms 0 07-08-87
- f. ,
.(
_ __----__--_-------a
1 07-08-87 I
TABLE OF EPIP FORMS l
EPIP EPIP Fo rm - Title Procedure
-01 'E4nergency Plan' Airborne Radiation Survey Record Site l Boundary Control Center (10-86)- 7.3.1
. Emergency Plan Survey Record Site Boundary Control' Center (10-86) 7.3.1 l
-03 Dose Factor Calculations for Specific Noble Gas Analysis Results.(03-81) 7.3.1
-04 ~ Status Report on Plant Systems & Controls for Affected
. Unit (09-86)- <
. 6.5
-05 RMS Status (Release Point Monitors) (01-87) 6.5
-06 RMS Status (Area Type Monitors) (08-84) 6.5
-06a RMS Status (Process Monitors) (05-84) 6.5
--6.10a' Accountability Short Form (07-87) 6.10
-6.10b Assembly' Area Roster (07-87) 6.10
-6.10c Assembly Area Designations (07-87) 6.10
-07' For X/Q Determination (03-85) 1.4
-7.2.la Radiation control Team Equipment Inventory & Functional Test Checklist:(07-87) .
7.2.1
-7.2.lb Offsite Sampling Team Equipment Inventory & Functional i Test Checklist.(07-87) 7.2.1
-7.2.1c Shuttle Team Equipment Inventory & Functional Test Checklist (07-87) 7.2.1
-08 Estimated Whole Body & Thyroid Projected Doses-(03-85) 1.4 4
-09 Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases (03-85) 1.4
-10 Estimated Ground Deposition Calculation Worksheet for 3 Particulate Radionuclides Releases (03-85) 1.4
-10a Estimated Population Dose (03-85) 1.4
' 11 Summary of Radiological Dose Evaluation Calculations (03-85) 1.4
-12 Incident Report Form (07-87) 1.3
-13 Status Update Form (02-87) 1.3
-14 NRC Event Notification Worksheet (02-87) 1.3 Unused ,
-16 Unused
-19 Unused
-20 Technical Support Center Activation Checklist (04-87) 6.5
-21 Emergency Operations Facility Activation Checklist (01-87) 6.7
-22 ' Plant Personnel Emergency Call List (07-87)
-23 Call List Tab Offsite Agency Emergency Call List (07-87) Call List Tab
-24. Emergency Response Facility Telephone Directory (07-87)
-25 Call List Tab Wisconsin Electric Headquarters Support Personnel Emergency Call List (07-87) Call List Tab
- (.
.m_.m.__._'- . - - - -
.a.- >
? ;
[', 4 '
i;
- h. ' ,' . ,
Page 2:
[f f b ".
- EPIP- EPIP.
- 4
~
Forms: Title' Procedure
-26 Unused '-
' '-27' Unused '.
' sUnused'
- -29 Unused
-30 , Reactor Coolant Post-Accident' Sampling An'alysis, Report (06-86)
- 7.3;2
~
31 '. Containment-Atmosphere Post-Accident Sampling Analysis'
. . . ' Report.'(06-86)- . .
7.3.3:
(2)-32. Search'& Rescue and Emergency Operations Checklist (02-87)~ 12.1', - 12 ~. 2 i
-33 - Unused '-
-34 . Calculationjof XE-133 Equivalent Release. Rates (04-86) s
- 1.8
-35'- Dose calculations (09-85)- '
1.8 i ,
\^
I ji a
g h
CL_:N, a:_- _ L_ ._. . _
,. 4 f - NAMES. AND'.
- W f.. '
. .c IEEEP_ HONE NUMBERS L h pELETED,- ***
$$R Revision 7' 07-08-87 PLANT OPERATIONS MANAGER INITIAL ~ RESPONSE
.c PROCEDURE ~
SUMMARY
SHEET (PSS) '
Line No.
- 1. .WHOLE BODY DOSE RATE (Site Boundary) rem /hr
- 2. THYROID DOSE RATE-(Site Boundary) rem /hr .)
- 3. This event, at a MINIMUM, must be classified as a' SITE EMERGENCY Initials Time (2400 clock)
- 4. This event is a GENERAL EMERGENCY based on.offsite radiological f conditions-(real meteorology, RMS-CRT).
Initials Time (2400 clock)
- 5. Protective Action Recommendations:
Action Miles Sectors-HAN{CECULATION
- 6. Release rate (Circle one: Ci/sec RMS-CT/ Contact)._ _
- 7. WHOLE BODY DOSE RATE (Site Boundary) rem /hr (
(worst case meteorology, hand calculation) '
- 8. This event is a GENERAL EMERGENCY based on offsite radiological k conditions (worst case meteorology, hand calculation). l Initials i Time
- 9. THYROID DOSE RATE-(Site Boundary) rem /hr
- i. ,
.<- > k
- 10. This event, at a MINIMUM, must be classified as a SITE EMERGENCY ]
Initials Time (2400 clock) l
- 11. Integrated WHOLE BODY DOSE: rem )
i
- 12. Integrated THYROID DOSE: rem i
- 13. Most severe emergency classification: /
Time
$ . .L_
EPIP 1.1 Page 2 SECTORS REQUIRING PARS
-BASED ON WIND DIRECTION NOTE: RECOMMEND, PROTECTIVE. ACTIONS FOR ALL SECTORS (360') IF WIND SPEEDS-ARE
- LESS THAN 3~ MPH OR THE' DIFFERENCE BETWEEN ACTUAL WIND DIRECTION VALUES (NONE GREATER THAN'360')-FOR INLAND AND NEARSHORE METEOROLOGICAL
' TOWERS IS: GREATER THAN 90*.
Wind Direction * (Degrees) Sectors in 90* Downwind Quadrent O- 11. (G), H,;J, K,'L
>11 - -34 H,J,K,L,M
>34'- '56. 'J', K, L, M,'N
>56 - 79- K,L,M,N,P
>79 - 101 L, M, N, P,-Q
>101 - 124 M,N,P,Q,R
>124 - 146 N,P,Q,R,A
>146 - 169 P,Q,R,A, (3).
>169 - 191 Q, R, A,(B),(C)
>191 - 214 R, A,(B),(C)'(D)
>214 - 236 A,(B),(C),(D),(E)
.>236 --'259 (B),(C),(D),(E),(F) I
.I
>259 - 281 (C),(D),(E),(F),(G)
>283 - 304 (D),(E),(F),(G),H
>304 - 326 (E),(F),(G), H,.J L. >326 - 349 (F),(G), H, J, K l
>349 - 360 (G),H, J, K, L I
l j
- As read on control room chart recorders.
() Denotes sectors over lake Michigan
,i L _ _: __ _ - --- . _ - - _ - . _ -
?>
x t
~5 .
o I
, .J4 m
. e, , g4 n .y,3 EPIP 1.1 .j i- Page 3- '
g_ ' ,
- u. 9
((. ,L.*f .
i., . ~9 h i .
- P.ROCEDURE
}g ' %Q ND'lE : .THIS PROCEDURE IS INTENDED FOR USE DURING ALL CLASSIFICATION (EAL)?
4 CHANGES.
Qg- .,
Q .--
7
^t! l NOTE: NOTIFYTHEDUT?\TECHNICALADVISOR.(DN))DUTYANDCALLSUPERINTENDh$
- (DCS ) , ' AND,,%gUTY - 7ihiM.TH PHYSICS SUPER y- @f(t,
. ' g' 1 - /V . g G. Wk NOTE THl'.WXPONSIBILITY OF THE DUTY SHIFT SUPERINTEN-
.THIS DENT UNTIL PROCEDUREETS,AIVAL;pF THE AA THE PLANT OPERATIONS MANAGER (POM
.J- - '
,. \ . w NOTE: COMPLETE THIS PROCEDURE REGARDLESS OF CHANCING PLANT CONDITIONS.b
..tp Q + . "i a'( gsis NOTE: THEDECISIONTONOTIFlh$DTORECOMME5fDPROTECTIVEACTIONSTO'0FFSITIQ AUTHORITIES MAY NOT BE DEf.,2 GATED. '4'-
NN K,j ,
y~
?
'} .e \ l '< '
,, Affected Unit: k "i s W
'i O.
& gc
- L%+1
,3 w .,
3
,. 4 Time Prow dure,Ini iated:,
- Jb 6 (2400 Clock),; .*
- 4
- 3. ,)'
y
, W t-4 r, .
3 STEP ACTION a / EXPECTED RESPONSEf ,, R_Ef,sy4SE N0*C OBTAINED O
Check if a Radioactive gt. \ * ' l' 'y-
_ g ga 'l
'C- .
- 1. "f'
' Go to litep 22 -
~f Re2 ease ic in; Pro ges,s,*' s a -(Classification)
' y[ ,
1
.s4 . >
N3
- (-
, 'a. Release monijor(s) s
' '{TXGH
' - alarm , '
_ \ or 6 e .$)e g s s
" [' '
g\ b. Plant conditions sugge9t a release y
.s 4
4o ;
s ,i .,, i, m 1 ik
(- - f. . . *
, z ',
i ,7d __
- 2. RMS-C$T is Available Go to Step 9 i' PS* N (RMS-CT Available) t/ ,(y
- y, <' 4 x
, 1 i
.. .n %
t {+
w.
'h.
.% F g Wl?f '
. .& ',4 gr -
6 %. ,
i h .
( f 's
' .% c. ,Q 9 .
'(- T kg [
[ % p .;
i
} g hh m).m'i, 'g
,% p
.Q * ~ ,, \p 1,1 ~
% 9 ,
g
.-- :'s %
^
y s
9 ,y
/_
3 ,% . . .
- -fa
_ _s :
fl i
n '
EPIP 1.1
.Page 4 f-@ STEP' ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 'l i
-' ' 3. ; Estimate"Off-site Dose Rate
- a. Press "P" on RMS-CRT key-board to perform an offsite l dose projection based on worst case meteorology.
, NOTE: IF,IN DOUBT,-THEN CHOOSE LOCA
- b. Enter the number which
- corresponds'to.the-appropriate accident' j
' type, then press RETURN ~
'(EMIER). !
L LOCA .
E[I' 2. Gap Activity. . .
- i - (DNB Accident)
-]
[ 3. Fuel Handling -!
- 4. SG tube rupture ;
it ' 5. Addicent type unknown
- 6. No accident has- -I occurred'
- c. Record the. projected .!
WHOLE BODY DOSE RATE N. on PSS, Line 1
- d. Record the projected THYROID DOSE RATE
'on PSS, Line 2
- 4. Cheek'if the Event Should be C.lassified as a SITE EMERGENCY
- a. -Projected dose rate at Go to Step 22 theJsite boundary exceeds (Classification) the' limits' listed on the lower half of the RMS-CRT screen.
y 11 b. Log MINIMUM SITE I EMERGENCY on PSS,
.Line 3.
I k
y
J l' __
l[ ' 'a EPIP 1.1
- i. 1
-Page 5
, - STEP ' ACTION / EXPECTED RESPONSE:
v K
- f ; 5. Check for GENERAL--
EMERGENCY Classification t' ..
- a. Press " Return" g . NOTE: 'IF THE PRIMARY METEOROLOGICAL TOWER IS NOT AVAILABLE, THEN USE (IN' ORDER)':
THE BACKUP TOWER', KEWAUNEE' NUCLEAR PLANT
' INLAND TOWER.
- b. Obtain,Lrecord, and L
input to the RMS-CRT the following:
4 Wind speed . mph Wind direction'
- Time-of reactorLshutdown: (2400 Clock)
Present. time: (2400 Clock) <
u Estimated' release duration: hours' (If unknown, use 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)
Change!in' temperature over change'in height *F Sigma Theta
- i 4
Unit'Affected (1 or 2)
Which valveLis open (check)
O. No valves are_open
- 1. 1 Safety I
- 2. ~2 Safeties
- 3. 3 Safeties
- 4. 4 Safeties
- 5. Atmospheric
- c. Verify and correct input as appropriate-
- d. Press "Y," then " Return" o
. I i
j l
EPIP 1.1-Page 6 STEP' ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. Check if the Event Sho*11d be Classified as a GENERAL EMERGENCY
- a. Dose rate at site boun-
. dary exceeds the limits listed on the lower half of the RMS-CRT screen.
- b. IF GENERAL EMERGENCY, THEN loa on PSS, Line 4
- c. Press " Return" to deter-mine if Protective Action Reconnendations should be made.
NOTE: IJ_ THE RMS-CRT INDICATES THAT PROTECTIVE ACTIONS REQUIRED ARE "NONE,"
THEN RECORD "NONE" AND THE SECTORS INDICATED.
- d. Log protective. action recommendation on PSS, Line 5
- 7. IF SITE EMERGENCY, THEN Go to Step 22
-(Classification)
- 8. Go to Step 24 (Announce. GENERAL EMERGENCY).
- 9. Check if RMS-CT is Available
- a. " Mon" and " Control" lights Go to Step 12 are intermittently flashing. (Contact readings)
(Indicates both cts are operating.) l 1
.1
- b. -" Control" light is on and
" field" light flashing.
(Indicates one CT is operating).
l I ,'J )
- . g; -.'
'i s
- o. m
%. 4- '
EPIP 151 l a, <
'Page 7
- f. ,
i
' STEP '~ i
. ACTION / EXPECTED RESPONSE.
- c A T10. Estimate Release Rate Using.
i l' Data From RMS-CT-n
, 1
- a. - Obtain a list of alarming release monitors by pressing,' in orders _
f < PRINT) .<6) :< ENTER >
b.iReview C7 printout for high alarms'on release monitors,
- c. Releare' monitor lista-
! +
.RMS No. 'Monitorl- Dam . Channel RE-214- AUX BLD VWT '7 4 RE-310J SPING, RE-315. . Low Range Gas 23 5 RE-317 ,
Medium Range Gas' :23. 7 9-
~
RE*319 High Range Gas 23 RE*221 DRUM AREA VNT 5' 7 JRE-320- SPING-RE 325 Low Range Gas- 24 5 m RE-327. . Medium Range. Gas 24 7.
n.
1RE-212- U1 COM PURGE, 1 3.
SPING' 1RE-305 Low Range Gas -21 5 1RE-307- Medium Range Gas 21 7 --
1RE-309' High Range Gas ; 21 9 ,
E 2RE-212- U2 CONT PU3GE '2 3 SPING' 2RE 305. Low Range Gas 22 ' '5
. Medium Range Gas.
2RE 307 22 7 E2RE-309 . High Range Gas 22 9 RE-224 GAS STRIPPER BLD 6 6 REa225: COMB 1.' E. 7 ,1 RE-226-STEAM LINES-
, ,1RE-231~ SG 11 3 . 9 -J 1RE-232f SG 13 5 2-
- c. Display (pci/cc) data on the CT LCD for each alarming release monitor by pressing the following keys in order:
<D&TA> - < M) <-> (M) < ENTER >'
(D&M) (CHANNEL)-
d.' To print the data on the CT tape, follow the entries in Step C with:
< PRINT) < FILE) (EWER) 1 i.
p l_________E____ _ _ i
EPIP 1.1 Page 8 STEP ACTION / EXPECTED RESPONSE 10 .~ (Continued) e.' Calculate release rate:
1
- 1) Record alarming RMS channel readings on the table,below.
2)'. Perform the calculation indicated.
3): Add the values in the right hand column to arrive.at a total release rate.
NOTE: CONVERSION FACTORS ASSUME NOMINAL FLOW RATES.
. NOTE: USE HIGHEST IN-RANGE ALARMING MONITOR.
RMS NO. LOCATION- READING CONVERSION R'3 LEASE RATE (pC1/cc) (cc-Ci/sec-pci) (Ci/sec)
RE-214 AUX BLD VNT ,, x 33 = 'I RE-310
- RE-221 DRUM AREA VNT x- 20- =
RE-320 1RE-305 .U1 CONT (0 or 1 fan)' x 6. =_
1RE-307 PURGE 1RE-309 (2 fans) x 12 =
2RE-305 U2 CONT (0;or 1 fan) x- 6 =
2RE-307 PURGE 2RE-309 (2 fans) x 12 =
RE-224 GAS STRIPPER x 6 =
BLDG ;
\
RE-225 COMB A.E. x 0.012 =
RE-226 .
RE-232 STEAM LINE HEADER I ATMOSPHERIC x 1.0 = 1 RE-231 1 SAFETY- x 2.5 =
2 SAFETIES x 5.0 = j 3 SAFETIES x 7.6 = 'l 4 SAFETIES x 10.1 = i TOTAL = -
1 J
- f. Record release rate TOTAL I (Ci/sec) on PSS, Line 6. I I
4
.i
n .
EPIP 1.1 Page-9 STEP. ACTION / EXPECTED' RESPONSE-
- 11. Go to Step 13.(Estimate WHOLE. BODY' DOSE RATE) 4 12. Estimate Release Rate Using Contact Readings
- a. Calculate release rate below:
1 1)' Record contact readings' in the appropriate space below. ~
- 2) Perform-the calculation' indicated.
- 3) Add the values in the right hand column to arrive.st total release' rate.
NOTE: . CONVERSION FACTORS ASSUME NOMINAL FLOW RATES.
NOTE: : EVALUATE INPLANT-RADIOLOGICAL HAZARD PRIOR.TO ORDERING A CONTACT-PEADING SURVEY.
NOTE: FOR STEAM.LINE HEADER CONTACT READING INSTRUCTIONS,.SEE EPIP 1.8, SECTION S.2.7; LOCATION. iREADINGS. CONVERSION , RELEASE' RATE (R/ hour)~ -(Ci-hr/R-sec) (Ci/sec)
AUX BLD'VNT 'L x 300 =
. DRUM AREA VNT x 230 .=
U1 CONT
' PURGE (0 or 1 fan)'
- x '80 =
(2 fans) x- 160 =
U2 CONT'-
PURGE (0 or 1. fan) x 80 =
-(2 fans) x 160 =
GAS STRIPPER x 80 =
, ' BUILDING VNT
-COMB. A.E. x 160 =
' STEAM'LINE HEADER
' ATMOSPHERIC x 800 =
1 SAFETY x 2,000 .=
'2 SAFET1ES x 4,000 =
3 SAFETIES x 6,000 =
4 SAFETIES x 8,000 =
l TOTAL =
- b. Record release rate TOTAL (Ci/sec) on PSS, Line 6
I 1
t g 10 STEP. ACTION / EXPECTED RESPONSE' RESPONSE NOT OBTAINED- .
- 13. ' Estimate the WHOLE BODY DOSE .
RATE at the-Site Boundary l
- a. Calculate:
6.46'E-03 x Ci/sec = rem /hr (Conversion)- (From PSS, Line 6)- '(WHOLE BODY DOSE RATE)
- b. Record WHOLE BODY DOSE RATE on PSS, Line 7.
f q
a
- 14. Check if the Event'is a GENERAL i EMERGENCY- i j
'a.
WHOLE. BODY DOSE RATE'>l rem /hr _ _ Go to Step 16, (PSS, Line 7) (THYROID DOSE RATE determination) !
- b. Log GENERAL EMERGENCY
. on PSS, Line 8.
- 15. Go to Step 24.
(Announce GENERAL EMERGENCY)
- 16. Calculate THYROID DOSE RATE
- a. Calculate: ;
NOTE: IF IN DOUBT, PIEN CHOOSE LOCA
. Accident WHOLE BODY Conversion THYROID-Type' DOSE RATE DOSE RATE (rem /hr) (rem /hr)
(PSS, Line 7)
Gap Activity rem /hr x 2 =
Fuel Handling rem /hr x 77 =
SG Tube Rupture rem /hr x 62 =
- b. Record THYROID DOSE RATE on PSS, Line 9
'l
- l
)
EPIP 1.1 J Page 11 -]
-1
~
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED :
- 17. Check if the Event is a GENERAL
. EMERGENCY
- a. ' THYROID DOSE RATE >5 rom /hr' Go to Step 19 .)
(PSS, Line 9) (Check SITE EMERGENCY)
.b. Log the GENERAL EMERGENCY.
on PSS, Line 8
- 18. Go to Step 24 (Announce GENERAL EMERGENCY)
- 19. Check if the Event, at a MINIMUM, is a SITE EMERGENCY
- a. WHOLE BODY DOSE RATE Go to Step 21 (PSS, Line.7) (Check SITE EMERGENCY)
>0.05 rem /hr for hour or- -
5.5 rem /hr for 2 minutes I
- b. . Log SITE EMERGENCY on PSS, Line 10
- 20. Go to Step 22 (Classification) l
- 21. Check if the Event, at a MINIMUM, is a SITE EMERGENCY
- a. THYROID DOSE RATE Go to Step 22, l (PSS, Line 9) (Classification) l
'l
>0.25 rem /hr for. hour l 9E
>2.5 rem /hr for 2 minutes ;
- b. Log SITE EMERGENCY on PSS, Line 10 )
l
-_____________________-________-_____-_a
'EPIP 1.1 Page 12 STEP ACTION / EXPECTED REPONSE i
- 22. Determine EMERGENCY CLASSIFICATION
.i
- a. Check (J) all applicable categories relating to current plant events or conditions from the list below.
Category Table 1.2-1 Highest Possible Page Number Classification i
- 1. Abnormal Primary Leak Rate 1 General Emergency _
- 2. Abnormal Primary / Secondary Leak 2- General Emergency 3.- Core Fuel Damage 4 General Emergency
- 4. Secondary Coolant Anomaly 6 General Emergency j
- 5. Abnormal Effluent 7 General Emergency
- 6. Major Electrical Failures 8 General Emergency {
- 7. Fire 10 Site Emergency j
- 8. Hazards'to Plant Operations 10 Site Emergency l
- 9. . Natural Events 11 Site Emergency
- 10. . Plant Shutdown Function 12 Alert !
.11. Fuel Handling Accident 13 Alert -l
- 12. Other 13 Alert
- 13. Safety System Functions 14 Unusual Event I
- 14. Abnormal Coolant Temperature / Pressure 14 Unusual Event
- 15. Serious or Fatal Injury 14 Unusual Event j
- 16. Reactivity Transic.nt 14- Unusual Event.
- b. Beginning at the page indicated, review initiating conditions in Table 1.2-1 (EPIP 1.2) for all categories checked ab ve.
NOTE: UPON IDENTIFICATION OF AN EMERGENCY CLASSIFICATION, IT IS NOT NECESSARY TO EVALUATE FOR LESS SEVERE EMERGENCY ACTION' LEVELS. , ;
I
- c. Record MOST SEVERE emergency classification from Table 1.2-1 and the PSS lines 3, 4, 8'or 10 on PSS line 13.
l 1
7 =:
, g; - <
3; >
' f._
e EPIP'1.1 Page 13 y STEP' . ACTION / EXPECTED RESPONSE
~23. Proceed as Indicated Below'
'(Using Classification From'PSS, Lini 13)
~ a. . H . GENERAL EMERGENCY, 1- lTHEN go to Step 24 o -(Announce GENERAL EMERGENCY)- i L ,
L' 'b. 1 H SITE EMERGENCY, ;i H , . .. THEN go,to Step 26 l1 <
-(Announc'e SITE EMERGENCY) lc j c. .E ALERT, THEN go to Step 29:
(Announce ALERT)-
- d. .IF UNUSUAL EVENT, THEN go.to Step 31 (Announce UNUSUAL EVENT)
- e. IF None of!the Above, DE}[ .
return to'EOPs,'and/or reevaluate e need to be in' Emergency Plan Implementing Procedures--
I
.24. Announce GENERAL EMERGENCY
. ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. ~ THERE ARE CONDI-
=. TIONS AT THE PLANT THAT WARRANT A GENERAL EMERGENCY.- THESE CONDITIONS a '
ARE:
25:. Evacuate Plant / Site
- a. E the plant'has-NOT been evacuated,
-THEN go to step-27 (Plant Evacuation).
h
.b. IF the plant has been. evacuated,
, THEN to to step 35 (Evacuate Exclusion Area)
.rw
- 26. Announce SITE EMERGENCY
~ ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THERE ARE CON-DITIONS AT.THE' PLANT THAT WARRANT A SITE EMERGENCY. THESE CONDITIONS
, ARE:
- 41 ~
EPIP 1.1 Page 14
- STEP- ' ACTION / EXPECTED RESPONSE
- 27. Evacuate P'lant'
- a. ' Call CAS~ Request' activation of accountability-readers.
1
- b. Ensure-sounding of'the plant' evacuation alarm-
- f. c..'Announce'(Gai-tronics):
ATTENTION:ALL' PERSONNEL, ATTENTION ALL PERSONNEL. THERE ARE CONDITIONS AT.THE PLANT THAT WARRANT A PLANT EVACUATION. ALL PER-SONNEL f, HALL IMMEDIATELY ASSEHBLE -IN THE FOLLOWING' AREAS:
PLANT PERSONNEL WITH EHERGENCY DUTIES -' REPORT TO ASSIGNED !
EHERGENCY LOCATIONS. l
"' PLANT PERSONNEL NOT' ASSIGNED EHERGENCY DUTIES - REPORT.TO-
.EL. 18.58 0F TECHNICAL' SUPPORT CENTER.
VISITORS AND CONTRACTORS-'- REPORT TO THE' SITE' BOUNDARY CONTROL CENTER.
USE ACCOUNTABILITY CARD READERS ENROUTE TO ASSEHBLY AREAS'.
AWAIT FURTHER INSTRUCTIONS.
- d. Repeat.the alarm-and announcement
- 28. Go~to Step 35' (EIC Evacuation) m
- 29. Announce ALERT-ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THERE ARE CONDI-TIONS AT THE PLANT THAT WARRANT AN ALERT-CLASSIFICATION. THESE l CONDITIONS ARE:
i 30. Go to Step 32 d i
(Check Limited Plant Evacuation) !
- 13 ,
1 A
6
P R
EPIP 1.1 Page 15
- STEP ACTION /EXPNCTEDRESPONSE . RESPONSE NOT OBTAINED.
'31. Announce UNUSUAL EVENT
' ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THERE ARE CONDITIONS AT THE PLANT'THAT WARRANT AN UNUSUAL EVENT CLASSIFICATION. .THESE CON-DITIONS:ARE:
.32. Eheck'if' Limited Plant Evacuation is Required
- a. Evaluate: Go to Step 34
. (UNUSUAL EVENT)
Unanticipated radiation level increase at any area radiation monitor in; excess of 100 mR/hr.
A containment evacuation alarm.
Excessive radioactive surface contami- ,
nation levels due to a major' spill of~ 'l radioactive materials OtherJemergency. conditions,;that may endanger human life or. health as deemed necessary by the Duty Shift Superin-tendent or Health Physics ~ Supervisor (e.'g., fire, unanticipated airborne activity, . etc.. ) - ,
1 i
l'
,]
')
EPIP-1.1' Page 16- I STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED !
- 33. Limited Plant Evacuation
- a. Call CAS Request activation of accountability readers.
- b. Ensure sounding cf the plant evacuation alarm (and. fire alarm, if
. appropriate).
1
.c. Announce: (Gai-tronics)
ATTENTION ALL PERSONNEL. ATTENTION'ALL PERSONNFL. THERE ARE.
CONDITIONS AT.THE PLANT THAT WARRANT A_ LIMITED PLANT EVACUATION IN THE AREA (S). ALL PERSONNEL IN THE
.(Specify Area)
AP.EA(S) EVACUATE'IMMEDIATELY AND REPORT TO THE (Specify Area).
AND AWAIT FURTHER. INSTRUCTIONS. 1 1
- d. Repeat alarm and announcement. I
- 34. IF an UNUSUAL EVENT, THEN go to Step 46 (Initial Incident Report Form)
- 35. Evacuate Exclusion Area Visitors
{
- a. Notify the Energy Information Center i and tell them to-implement EPIP 6.4, " Energy Information Center h
Evacuation."
- b. Instruct'the control operator to activate the fisherman's pier
, evacuation alarm (" Fisherman Alert", Unit I) I
- 36. IF an ALERT, THEN go to Step 46 (Initial Incident Report Form)
~
- 38. IF a SITE EMERGENCY, THEN co to Step 40 (Radiological Release) l
?
4 <
l];
7 ,
j .h ~ , ' I.
[ U.. .
EPIP 1.1
.g Page 17 ]
1 STEP- ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
- 39L ~ General ~ Emergency Minimum Protective Action Recommendations
' NOTE: -IF SECTORS REQUIRING PARS WERE NOT;.0BTAINED USING THE RMS-CRT,.'THEN
'F . SELECT SECTORS'FOR PROTECTIVE ACTION RECOMMENDATIONS"USING WIND DIRECTION AND:THE TABLE ON THE. REVERSE SIDE OF THE PSS.
L '-
NOTE: RECOMMEND PROTECTIVE ACTIONS FOR ALL' SECTORS (360*) IF. WIND SPEEDS ARE -l LESS THAN 3 MPH OR THE DIFFERENCE BETWEEN ACTUAL (i'.e.'NONE GREATER.THAN L ,360') WIND DIRECTION VALUES FOR INLAND AND NEARSHORE METEOROLOGICAL
+' <
- TOWERS.IS GREATER THAN 90'.-
- a. < Recommend the following:
Action Miles' Sectors
'TAKE SHELTER 0 to 2 miles Radius (All Sectors)
, 'TAKE SHELTER. 2 to 5 miles 45* each side.of downwind
-center line.(90* total)'
~
NOTE: JIF A'IROTECTIVE ACTION RECOMMENDATION WHICH IS'MORE' SEVERE THAN THE: MINIMUM IS ALREADY' RECORDED ON LINE 5 0F THE PSS,..
DO NOT RECORD THE PAR DETERMINED.IN STEP 39a.
.b. Record protective action recommendation' determined.in Step 39a t- on PSS, Line'5.
- c. Go to' Step 46
~(Initial Incident Report Form)..
- 40. . Check if Classification is 'Go to' Step 46 ..
Based on a Radiological Release (Incident Report Form)
- a. Entry made on PSS Lines 3, or 10.
1
- 41. .IF RMS-CRT was Available, THEN l
-Go To Step 46.
(Incident Report Form)~
4 i..
f7't
( f. i s
'7 ,
EPIP'1.1 Page 18 STEP ACTION / EXPECTED RESPONSE. RESPONSE NOT OBTAINED.
- 42. Calculate Integrated Doses j
.(For PAR Determination)
NOTE: RELEASE DURATION IS UNKNOWN, THEN ASSUME 8 HOURS.
- a. Record an estimated release duration'(ERD) in the proper-blanks blow.
- b. Obtain WHOLE BODY DOSE RATES and THYROID DOSE RATES.from PSS, Lines'7 and 9, and insert the values in the proper blanks below.
.___ c. ' Calculate integrated WHOLE BODY DOSE.
.(PSS, Line 7) (ERD) (Integrated WHOLE BODY DOSE),
- d. Record the Integrated WHOLE BODY DOSE on PSS, Line 11.
. e. -Calculate the Integrated THYROID DOSE.
rem /hr. THY x ' hrs'. = rem I (PSS,-Line;9) (ERD) .(Integrated THYROID DOSE) l
- i
- f. . Record the Integrated THYROID DOSE on PSS, Line 12.
l l
u p' i 1
1 i l b l l V _ _ _ _ _
.i
t e
EPIP 1.1 Page 19
_ STEP ACTION / EXPECTED: RESPONSE
'43; Deterr.ine Protective Action Recommendations
- NOTE: SELECT SECTOR FOR PROTECTIVE ACTIONS USING WIND DIRECTION AND CONTROL ROOM EMERGENCY PLANNING ZONE MAP.
1
' NOTE: RECOMMEND PROTECTIVE ACTIONS FOR ALL SECTORS (360') IF WIND SPEEDS ARE LESS THAN.3 MPH OR THE DIFFERENCE BETWEEN 1.:.:TUAL (i.e. NONE GREATER THAN lI 360*) WIND DIRECTION' VALUES FOR INLAND AND NEARSHORE METEOROLOGICAL TOWERS 1 IS GREATER THAN 90'.
NOTE: EVACUATION RECOMMENDATION MUST CONSIDER ADVERSE WEATHER CONDITIONS, POTENTIAL EXPOSURE DURING EVACUATION AND OTHER ASSOCIATED FACTORS.
RECOMMEND SHELTER IF EVACUATION IS DEEMED IMPRACTICAL.
- a. Compare values from'PSS, Lines 11 and 12, to the values in the
" Integrated Dose" column below.
Protective i Integrated Dose Action _, Miles Sectors WHOLE BODY <1 rem None or Required THYROID <5 rem
<WHOLE BODY 1 to <5 rem Evacuate 2 miles All i or Shelter 2-5 miles 90* downwind
-THYROID _ 5 to <25 rem .
WHOLE BODY~ >5 rem Evacuate 2 miles All i or . Evacuate 2-5 miles 90' downwind '
TdYROID >25 rem Shelter 5-10 miles 90' downwind ;
I
- b. Select downwind sectors using the table on the reverse side of the PSS. !
- c. Record the appropriate protective action recommendations on PSS, Line 5. i
- 44. Go to Step 46 (Initial Incident Report Form) J
- 45. Obtain the Protective Action l Recommendations From Emergency '
Support Manager i
- a. Record the protective action recommendations on PSS, Line 5 *
. j l
< I J
L-k _
[
EPIP 1.1
.Page 20
' STEP . ACTION / EXPECTED RESPONSE
- 46. Form EPIP-12 Complete appropriate portions of
-.the incident report form below -
THIS (IS/IS NOT) A DRILL.
This is at the (Hame)- (Title)
Point Beach Nuclear Plant. .An incident has occurred at our facility and we have
[ declared / terminated) a(n) [ UNUSUAL EVTI(T, ALERT, SITE EMERGENCY, GENERAL EMERGENCY] at on .
(Time) (Date)
There [has/has not) been a radiological release to the er,vironment.
Recommended protective actions arer
- a. Not required at this time,
- b. As follows:
Take shelter in the following areas:
(Location, sector and miles radius) 1 Evacuate the following areas (Location, sector and miles radius) i other in (Recommended Action) (Location) i in (Recommended Action) (Location) l 1
Relay this.information to Emergency Government immediately.
Verify this message by return telephone call to the appropriate number listad in your procedure.
THIS (IS/IS NOT) A DRILL.
- 47. Provide THIS PAGE to the Offsite Communicator. ' Instruct him to complete EPIP 1.3.
Notification Callback Answered Received NAWAS(J) . Agency Time / Person Notified . Time / Initials Manitowoc County / /
Kewaunee County / /
Wisconsin DIG / '/
(Warning Cntt 2)
- State Patrol, Fond du Lac- / /
- SITE EMERGENCY and GENERAL EMERGENCY only.
4
< a EPIP 1.1 Page 21 STEP- ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 48. Check if the Event is a gGo to Step 71 GENERAL EMERGENCY. (EPIPs)
- a. General Emergency logged or recorded on PSS Lines 4, 8, or 13
- 49. Check'if Core Damage is in Go to Step 71 Progress or Projected (EPIPs)
- a. Core exit thermocouple are or have been'>700'F
- 50. Cheex if Large Fission Product Go to Step 53 Inventory is in Containment (Containment Atmosphere failure) l 1
- a. 2 of 3 containment high range radiation monitors 1(2) RM-126,'127, or 128
>1,000 R/hr
' 51.. Check if Containment Failure Go to Step 58 is Imminent or Underway (Incident Report 1 Form)
- a. One or more containment isolation status lights dim j
.l EI j
- b. Containment pressure >25 psig with fan coolers and spray-inoperative l or j
- c. Observed or suspected physical breach of containment SE
- d. Hydrogen concentration >3%
- 52. Go to' Step 54. i (Check normal weather)
1 L
EPIP 1.1 Page 22 ,
i
' STEP- -ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED !
l 1
- 53. Check if Containment Failure is Go to Step 70.
, Imminent or Underway -(Incident Report Form)
- a. One' or more containment
-isolation status. lights dim.
i
_o_r
'q
- b. Containment. pressure >25 psig i with fan coolers and spray i
. inoperative i i
SUE J
- c. Observed or suspected physical-breach of containment. j
)
.!ME .!
- d. Hydrogen concentration >3%
-[
- 54. Check if Normal Weather Go to Step 57 i Conditions Exist (ERD >12 hours)
- a. ' Auto travel notl impaired due to visibility, wind, fallen snow or other natural event.
NOTE: ,IF RELEASE DURATION CANNOT BE ESTIMATED, THEN ASSUME IT IS GREATER THAN 5 HOURS.
- 55. The Estimated Release Duration Go to Step 62 ]
is Greater Than 5 Hours (ERD >1 hotr) )
I i
- 56. Go To Step 58 J (EPIP-12) 1 NOTE: IF RELEASE DURATION CANNOT BE ESTIMATED, THEN ASSUME IT IS GREATER I THAN 12 HOURS.
- 57. The Estimated Release Duration Go to Step 60 j Is Greater Than 12 Hours (ERD >3 hours)
.____?_____-______-___-__----_-_Q
. 7 L-EPIP 1.1 Page 23 STEP -ACTION / EXPECTED RESPONSE l- 58. Form EPIP-12 Long duration release Adverse weather
- a. Complete Appropriate Portions >12 hour ERD of the Incident Report Form Normal weather Below. >$ hour ERD NOTE ' SECTORS REQUIRING PROTECTIVE ACTIONS CAN BE DETERMINED USING WIND DIRECTION -
,; AND THE TABLE ON THE REVERSE SIDE OF THE PSS.
NOTE: RECOMMEND PROTECTIVE ACTIONS FOR ALJ SECTORS (360') IF WIND SPEEDS ARE LESS THAN 3 MPH OR THE DIFFERENCE BETWEEN ACTUAL (i.e. NONE GREATER THAN 360') WIND DIRECTION VALUES FOR INLAND AND.
l; - NEARSHORE METEOROLOGICAL Tol'ERS IS GREATER THAN 90*.
THIS (IS/I$ NOT) A DRILL.
l This is at the Point-Beach Nuclear Plant. An (Name) (Title) incident has occurred at our facility and we have declared a General Emergency at- on (Time) (Date) ;
There (has/has not) been a radiological release to the environment.
Recommended protective actions are as follows:
l EVACUATE the following areasi 5 mile radius 5 - 10 miles 45' each side of downwind center line ,
Sectors _ , _ , _ , _ , _
(4 minimum)
]
TAKE SHELTER in the following areas: REMAINDER OF THE 10-MILE EPZ Relay this information to Emergency Government immediately.
I Verify this message by return telephone call to the appropriate number listed in your procedure. j THIS (IS/IS NOT) A DRILL.
~
- b. ' Provide THIS PAGE to the offsite communicator.
Instruct him to complete !
Notification Callback Answered -Received NAWAS(J) Agency TfJne/ Person Notified Time /Initiale I
Manitowoc County / / j Kewaunee County / /
Wisconsin DEG / /
(Warning Cntr 2)
State Patrol, Fond du Lac / /
.j m_ m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _E. _ ._ !
i . s EPIP 1'.1- .)
Page 24 i
.1 STEP. ' ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED I i
- 59.: Go to-Step 71- 4
, (EPIPs) q
~1
- 60. The Estimated Release Duration _ Go.to. Step.65 ,
is Greater Than 3 Hours' '(ERD >2 hours) 61., .
Go to Step 63-(EPIP-12)
- 62. The' Estimated Release Duration Go to. Step 68 l
-is Greater Than 1 Hour ~(PAR) i i
l l
s.
l L:
EPIP 1.1 Page 25 STEP ACTION / EXPECTED PISPONSE
- 63. Form EPIP-12 Adverse weather 3-12 hour ERD i
- a. Complete Appropriate Portions Normal weather I of the Incident Report Form 1-5 hour ERD Belev.
1 THIS (IS/IS NOT) A DRILL j This is at the Point Beach Nuclear Plant. An :
(Name) (Title) incident has occurred at our facility and we have declared a General Emergency at on (Time) (Date)
]
There (has/has not) been a radiological release to the environment.
Recommended protective actions are as follows: )
s EVACUATE the following areas: 5 mile radius l
TAKE SHELTER in following areas REMAINDER OF THE 10-MILE EPZ Relay this information to Emergency Government immediately. )
Verify this message by return telephone call to the appropriate number listed in your procedure.
THIS (IS/IS NOT) A DRILL.
~
- b. Provide DIIS PAGE to the offsite Communicator.
. Instruct him to complete EPIP 1.3.
Notification Callback Answered Received NAWAS(J) &oency Time / Person Notified Time / Initials ,
1 Manitowoc County / /
Kewaunee County / / ]
l Wisconsin DEG / / 1 (Warning entr 2) I i
State Patrol. Fond du Lac / / l 4
I l
l i
l i
I i
l l
1
i r i
G- EPIP.1.1 Page'26 c.c .
L> ACTION / EXPECTED RESPONSE STEP. RESPONSE NOT OBTAINED
'64 Go to Step'71
-(Implemcnt remaining'EPIPs)
]
.g
'65.
The Estimated Release Duration Go to Step 68 I '
is Greater Than 2 Hours (Incident Report Form)
L: .
s t-
>. -i 4
4 4
1
)
l 1
I f
~
9; EPfP 1.3 Page 27 STEP ACTION / EXPECTED RESPONSE
- 66. Form EPIP Adverse weather i
2-3 hour ERD l- _
ai Complete appropriate portions l of the incident report form 1' kolows THIS (IS/IS NOT) A DRILL.
This is _
at the Point Beach Nuclear Plant. An
-(Name) (Title) incident has occurred at our facility and we have declared a General Emergency at on (Time) (Date)
<There (has/has not) been a radiological release to the environnient.
Recommended protectiva actions are as follows:
EVACUATE the following areas 2 mile i'adius
-TAKE SHELTER in the following areast REMAINDER OF THE 10-MILE EPZ
.l j
Relay this information to Emergency Government inuwdiately.
Verify this message by return telephone call to the appropriate number listed in your procedure.
.THIS (IS/IS NOT) A DRILL.
~b. Provide THIS PAGE to the offsite Communicator..
. Instruct him to complete
'EPIP 1.3.
Notification Callback '
Answered- Received
- h'AWAS (J) 'Am Time / Person Notified Time / Initials.
. Manitowoc County '/ '/
_ Kewaunee County / /
_ Wisconsin DEO /, /
(Warning Catr 2)
State Patrol, Fond du Lac / /
I o ;
)
1 i
11 8 '-
, 1
- v-r'.
M.
ju >
-EPIP 1.1 W.
ll n. . ,
Page.28
- t. -
.i t
' STEP ACTION / EXPECTED. RESPONSE - RESPONSE NOT OBTAINED.
p:
p.
p . 67.i Go.to Step 71
- (Implement EPIPs) s !
l
[5i r .p.
h r: ' ',
. ,:h, }
,).-
h, l
4
/
./
i
-l 1
1
)
.p ,
4
. . .p l
s i
e i
. 0 l I
i
_U.___._._____ ____ _-
b
- 'l
_(.
- 'j
.I -
o- >
EP2P 1 1 Page 29' STEP '- ACTION / EXPECTED RESPONSE.
- 68. Form EPIP Short duration release Adverse wettter
- a. ' Complete Appropriate Portion , <2 hour ERD of the Incident Report Form Normal weather below: <1 hour ERD THIS (IS/IS NOT) A DRILL.
1 This is at the Point Beach Nuclear Plant.' An-(Name) .(Title). .I incident has occurred at our facility and we have declared a General Emergency at- on (Time) (Date) 5 There (has/has not) been a radiological release t<) the environment.
t.
Recommended protective actions are as follows: -f TAKE SHELTER in following areas: ENTIRE 10 MILE EPZ Relay this information to Emergency Government immediately.
Verify this messarje by return telephone call to the appropriate number listed i your procedute.
THIS (IS/IS NOT) A DRILL. ,,
-i
- s. '
~'
- b. Provide THIS PAGE to the i
~offsite Communicator. ..g Instruct him to complete EPIP 1.3. q 3 J Notification " -
Callback Answered .
. q d. Received NAWAS(J) Agency Time / Person Nocified Time / Initials 9
danitowoc County / /
Kewaunee County '/ /'
Wisconsin DEG / _ / i (Warning Cntr 2) l State Patrol, Fond du Lac / / l 1
l i
4 1
1 1
l I
l l
I 1
m_____________ '_._. I
m.(;p. ;1.4; s ,
g
.'p /.
m, , i i:
$ i 'i. . p.. ,
, jl ,f 4
. - -s
'N' -
< EPIP 1.1,.
Page 30
.a ;
4 1
STEP: ' ACTION / EXPECTED RESPONSE- RESPONSE NOT OBTAINED
. 69. Go to Step'71' ,,
.(Implement EPIPs)
-p -
j.-
.v.
I s
i 1l.'
s t
')5 t (
e 9 l.
p:
.. _..________._____________a
e zg ( F
- ~
~ 7 -~ ~ ~~ '
'~ '
]
- yr W- \-
t A
u.
. .: y , - 4 9
9Y A (sg I %
i .. ,-
.1 y EPIP 1.1
@ ,y Page 31
.(/
TA,3 '/ 4 ACTION / EXPECTED RESPON qv '
- ( ' i% : 70. Form EPIP-12~ Fission Products lh '
Complete Appropriate Portions in Containment,'
containment intact i s.
of tha Incident Report Form 9'y 4
f( if***
1 Jt '\
p TE: S!;CTORS REQUIRING PROTECTIVE ACTIONS CAN BE DETERMINED VSING WIND DIRECTION-
.,s - MD THE TABLE ON THE REVERSE SIDE OF THE PSS.
+
NOTE: RECOMMEND PROTECTIVE ACTIONS FOR N SFMRS '(3608) IF WIND SPEEDS AR[LESS THAN 3 HPH OR THE DIFFERENCE BETWEEN ACTUAL (i.e. NONE GREATER THAN 360') WIND
-e '); GRE*.TER THAN 90',
e DIUCTIONVALUESFORINLANDANDNEARSHOREMETEOROLOGICALTOWERSIg\
i- JY THIS (IS/IS NOT) 'A DRRI,. '
t y sfg i This is
% at the Point seich Nuclaer Plant. An
, { (NarJe)
(Title) % d,j
, p !j , incident has. occurred at our facility and we have declared a Central Emergency at on ,
"i ' '
.(Time) (Date)
"l) g '[ ,
~(,
~
.%- 3 j
~
[
Thi '(hae/has W t) en ratho) cm (*1b e e the environment. '
41 3 1
- j ,3 -A l}. D / ms ,s j ftly .j Rect nded prutectly actions are as followes' 4 r(
\ L}
2 mile radius iO L
y' 9
'(
~ f . EVACUkTE the following aieas Tl- 5 miles 45' cc.h side ce downstind 4
f
\' ,
- < center line Sectors ;$
-(' ,\ ~~~~,A
., I s
- 4. .t .
'h d.g ./ G> t g, Y al Em,u Tn ,,
4 4 V .
TAKESHELTERinthefollowingareal .1EMAINDER'cF THE 10-MIIE.EPZ i
[- !3 bl 77- , Relay this information to EmergurT!Governmend immediately.
'~
d #
y N
W 4' h '
- ?,',
Verify this message by return teltphone call to the appropriate number lhted in your procedure.
M
- Y THIS (IS/IS NOT) A DRILL. .;! .
A t b
.r. /- .
.,s
- ,3
<4
- b. ;
_ Provide THIS PAGE to the- I$ s
(. .
Offsite Communicator. ' q' j k "'
-i Instruct him to complete > ,
'( .EPIP 1.3. u i-Q j Notifit&ticpt callba.:k 1 Lhsweredib ,
+/ s - Received
' hg,'g!(M '
,&oenet $ w Pegaon s Notif M . Cine / Initials
. _1Ajt X
.., s ,q% ,
^ j, i, ;. - Manitowoc County /_ /
@g . _
,jg{ *A Fewaunee Covity /, /
Wisconsin DEG / A q (Warning Cntt 2) /
\r
, State Patrol, Fond du Lac /
f_
ps . # .. 4 x
-9
- 3 a .
J' #
s 3 J(, ' \ ',
T fj ,
1 1 gl s,
- l
- . y %.
( '
it te S s y; ' , J L .
C L. bui _______ 2 2
tL_____- - - -- - m' I- ,,, _ .
}[-
ll ,
Y..
EPIP 1.1 1 Page 32 i
STEP ..A_CTION/ EXPECTED RESPONSE
- 71. Implement the Following
- Procedures as Required:
li73f , , a. EPIP 11.0 "First Aid and Medical Care" b b. EPIT 7.1'.3 " Health Physics Protective Actions by Operations.
Personnel Prior to Arrival of HP Personnel" c'. -EPIP 10.1 " Fire' Fighting"
- d. EPIP 6.10 " Personnel Assembly and Accountability"
- e. EPIP 12.21 " Personnel Exposure and Search and Rescue Team"
- 72. Return to the Emergency Plan ..
Implementing Procedures (EPIPs)
.as Indicated Below:
- a. IFF GENERAL EMERGENCY, THEN go to EPIP 5.1
- b. IF SITE EMERGENCY, THEN go to EPIP 4.1 ,
- c. IF ALERT, THEN go to EPIP 3.1 q
- d. IF UNUSUAL EVENT, THEN go to EPIP 2.1 1
l i
.i l
e E
r
_ _ _ _ _ _ _ . _ ____ a
n,- ,;;
4
+ > j s
4 EPIP 1.2'
~
MINOR Revision 17 07-08-87 EVENT CLASSIFICATI0N' E1.0' GENERAL
.The! purpose of this procedure'is.to provide a means of classifying an event; or condition'at the Point' Beach Nuclear Plant into one of four emergency. !
classifications as described in the Point Beach' Nuclear, Plant Emergency.
Plan. The classifications are listed in order.of increasing severity.
,1,11 Unusual' Event
- L ,
An unusual plant condition ~which either has occurred or might occur.
, This condition could possibly lead to.a degradation in overall safety.
This condition does not represent'a significant radioactivity release,
- involves noloffsite response,Jand may require no augmentation of
. plant personnel. "In spite of the above, prompt notification'of-the<
An - counties and' state is required.
b ~ 1.2L Alert.
' s g: Plant conditions.in which events;are in progress or have occurred
'e '
which involve an actual or potential degradation of plant safety.
~
-Radiation releases.are not likely to cause;an offsite hazard. Prompt R v offsite' notification is necessary and the~ plant organization'may have
- to be augmented.
I '. 3 . Site Emergency Plant = conditions in' which events -dre in progress or'have occurred which involve actual or. probable majorffailures of plant functions.
- Potential radioactive releases may have an impact on offsite people.
Prompt notification of offsite agencies is required. The plant ,
organization'must be' augmented and the technical support center (TSC), !
operations support center 1(OSC),~ emergency operations facility l(EOF),
and joint public information center '(JPIC) will be operational.
Public protective actions'may be necessary. A plant-evacuation is required.
-7 A
's.' g f !
I M.
g I 3
EPIP 1.2 Page 2 1.4 General Emergency Plant conditions in which events are in progress or have occurred which involve actual or imminent loss of two of three fission product ;
barriers with the. potential loss of the third. There may be substan- '
tial core degradation, loss of primary coolant. and a potential for loss of containment integrity. Potential radioactive releases may have an impact on offsite public. Prompt notification of offsite agencies is required. The plant organization must be augmented and the technical support center (TSC), operations, support center (OSC),
emergency operations facility (EOF), and joint public_ information center (JPIC) will be operational. A public evacuation may be necessary.
A plant evacuation is required.
2.0 REFERENCES
2.1 Nuclear Regulatory Commission NUREG-0654, Revision 1, published c November, 1980. <
2.2 Point Beach Nuclear Plant Emergency Plan Sections 4.0 and 5.0.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged.
r .
}
3.2 Emergency Plan Implementing Procedures are not to be used to respond I to security threats. See DCS 2.1 for classification and reporting ;
of security events.
i 3.3 The " Indications Used" in Table 1.2-1 are those which one may expect if that level of emergency occurs very quickly. For more slowly developing situations, other indications may be judged appropriate.
For example, a primary system leak rate of 40 gpm is an Unusual Event. Subsequently, charging may.be lost and, in addition, the leak may worsen. One may not,see charging flow 50 gpm greater than l
letdown flow when in fact an Alert should be declared.
l 3.4 For classification purposes where offsite radiological dose is the ;
primary parameter leading to a classification, use EPIP 1.1, " Plant j operations Manager - Initial Response." ],
3.5 The Shift Superintendent has the responsibility and authority to take immediate action to mitigate the consequences of the emergency. He j will consult with the Duty & Call Superintendent and assign the appro-priate emergency classification and initiate the necessary Emergency j Plan implementing procedures.
3.6 If anf " Indication Used" in Table 1.2-1 is unavailable or unknown, then it may be assumed that the specific criterion has been met. f t
3
(
EPIP 1.2 Page 3
- 4.0. INITIAL CONDITIONS None.
NOTE: NOTIFICATION OF OFFSITE AGENCIES SHOULD BE COMPLETED WITHIN ABOUT 15 MINUTES OF EVENT CLASSIFICATION. APPENDIX 1 0F NUREG-0654 (PAGE 1-3).CONTAINS THIS SENTENCE: "THE TIME IS MEASURED FROM THE TIME AT WHICH OPERATORS RECOGNIZE [ EMPHASIS ADDED] THAT EVENTS HAVE 'q
_ OCCURRED WHICH.MAKE DECLARATION OF THE EMERGENCY CLASS APPROPRIATE." I 5.0 PROCEDURE Initiate EPIP 1.1, " Plant Operations Manager - Initial Response."
Call the Duty & Call Superintendent for consultation to establish the initial classification. If he is unavailable,.the Shift Superintendent is' responsible for. classification.
mm s..
9
t ml EC G e i S
l C. 7 s s
~
l u %tau b y
p s ,t d
- e. r6 s s e g 3 o6 a t
. a / t 9 n a s
r e
2 , i o t c
) n ,i n i a v h9 o5t e d a t 4 a m n m%l 4
n u i 9 n o i g
w n o i l F , e ,s a - d s
- m7 g4i t .i e a 0 0 r4 o r%tn nS. h t 0 0 a9 oC a gh
- 0 7 l d cD ll c nc 1 e > yI e e%
> c n s a 5, ,hH[ m
" 4 n or t o v8 e<
i d]
n8 it ni nw /
C
~glea e y9lt i l i 2 us T l : a 0 nna eS 2 4 r
-x aa p grI 5 eot gS .k1 l - e kb u npP9 min .aD n1 e1 sh i a o i S[ nt o m ~: a - vL pt es c w .i ac a y g t I e m l s o ot g8ar n' ut a m l ni4t t e .db i l L l ,
7 pa mm r lonpes9nnr ml d w or r2 e e oeoiae o ro e4 et
/ t y h f ru ,
ccmdrn l t / z- l h e sb y
t i56 n ui l nd iI bg s
U ea244 orst m o on rL ai sd e
t ht >9 t n - f cot cr f ca u l l i h ue s , i i n yt x o3I o %egrt e e1 sG ad o ra e fC/P 3 nit e h n a 4 e2 ve i ac o"2[3 > Ol Sd t t 1 r4 ar
.t mi e :
l - p-N a y O
I i c iPirnn d* d. rd on C*
n A a
- b. c. d f
o oI VL oL N[
I l e l h T .d l
" [ At I n
A . - . . l I_ . . .
~- C I 1 2 3 A 1 2 3 4 1 I
- F -
2 I S
1 S A
e L l C t b n a Y e T C m .
g N ne E i g G aa R t m I E na S M od E cl d pa d e nu ae t h af p yr h eg t o l i if bh ~-
r gl l a,)2 ea i g t i an3 nt vi in ag4 e r1 mt f a eo ohR n t p cA o s s S i ye sgF en(
t sh t i t ci r d y xdI t - o n rh euS
~ nt p o at l ene c mi ncd d eR i w i na nd g r i e ens n py e h t ei i t t y nt s t fi at w i ny .a org rio ril .i cl era pen t se k e i st a pd upA S u n on ea n I Li L ca S y l t l t e aff Cia hS
&S l yya t t n uui y DDF r a
- - - m i
r P
. y r
~
r ok
.f s
o g
na b e e e AL t t o a .
N C 1 (l I
j qb l1I
]-
. m~ y c .
- 0 n n e
.o g i
t t
n e
s e
a v yc E Em
. ci
.nf ei l
a l
a 1 gs t u a
- r s r s w
.ea e u r 2 ~ ml l n e 1 EC A U G 2
e l e bg aa TP m m S r r e S a a .
r D l l e o y a a g m h .
a b t ] ) r m i h" 3 h" 3 e p< d w , g6 g7 v e l i4 i4 a "o n m1 ,
H H l 0 i r3 ) , ,- ,
- 5 m a4 5 l 2 l2 F i > r l 2 e6 e7 h^ l e a , 9 v4 v4 '0 e ) t 0 e e 0 ll v 8) e 3 , L , L . 7 e% e 24 d I" 4 4 1 1 >
v8 l) " 1 3 S , 2 " 6 " 7 e< 8 i 1 s 9 A4 B4 - s l r2 h I - a s9 - ' " - " - e 2 e4 FI s2 1 I I l k1 z - d (F s e4 F - rL rL p n1 a-i 1 rL e
e
( e c
r - l o( ol u g u p w
ow n PI t t o n
tI L s , s l o e w[
P m a1 a1 c g- r0 r0 o i l s7 fl m o e7 e7 m w cr e2 p f m Lg n> n> r o ro r4 m e o i 0 e . e e d
e l t/ p- u nn c rs 0 G3 .G3 h l nd I p i w ep 0 / / t s o on gL l o n t 1 m2 m2 u f ca n g d w i5 > a a t i , n gt o r3 eh eh i n e e1 s6 i ne d u7 w i t t t t x o h e m4 a2 g il t s1 o r S i r_S i e i t t 1 e4 r g u ,
s< l e wo" w t
a f l -
oI r-cI h a rn aa hS sC e f h" e c o r3 d t r VL eL C hh D P/ I n i . . n oC i
d
" l Dl ". Ct n ed
" 2 Sa E a b d_
a n . .
h n.
JA I 1 2 3 4 Wr 1 2 3. 4 m
e t
s y
s y
< r e _
a h m t _
i r h p t i
n w o)1 i k t a a3 e c l i 4 f1 y .
i re ag cR eA da pS SF mma n ( cd o l e i
n a) sl i
t u i c n u /e yu d g ng rf n h a C
o 5
0 c0 e1 mr i o
> T( rf o p n n e ge l o i t nt l a i t a ia ai t a r dr mt a i
t k e
ek rn oe c i
i a ca nt f n e xe bo i I L El Ap t o
N 2 _
k 7 a 0 e / 5 L y )
y r e R ak g F r
a ma a C y m) i e p r rL 0 id P y t o r 1 g
e P 't l r s
e r
- e aa n o t
a l
aC c md f C m( rn oo d r e 1 oe nc u nt be AS n 2 i
b a t S AR n C
. 2 o D 1 C
( e
^' e S
f
- i! IL
ei E 1 gs t
- rs e r 2 ea t e
_ ml i l
. 1 EC S A 3
e l e b g
_ aa TP l ] l )
e
) e )
n a
g ] ] n: g } )
ps i
e
) )
an po i ) ) &
% e % %
p p ron 0 0 i 0 0 -
4 7 7 rt 7 7 2 oi 5 > > oa S > > ) ) 9 e tt 3 t c ? s s - r ca 7 " 3 " 3 y ci 7 " 3 " 3 p p I u ac 1 i/ i/ ad 1 i/ i/ m m Fs ei rd
( h2 ( h2
(
b en < h2 h2 . a a ye s
ri ( ( s n 3 l l d 3 l l r 0 0 b r ti / e3 e3 e t n / e3 e3 e ( ( p u 2 v v7 t uo v6 v7 t d og
- n
( eM e4 a c
oi ",(2 e4 e4 "e e 2 2 ee ti I
S1 l -
I l -
I i
- t t a I
S 1 l -
I l -
I gm mC at O t g ar srrm s4 3 aL BL d n sm rr s4 3 &L aL tl l o n n ca ih w.
ii s - r . r . i ii s - r , r , ov o o d co ff eI o2 o2 ff e I o2 o2 v nsl gon n
rP t6 go n rP r r t7 u t 6 t7 r4 iif p
nc ,
a4 r-a4 r - g nc P
a4 r -
a4 r-e0 dA t e
t e
n d
o a i o0 eI e1 i o0 eI eI n s e ipt wh ot l3 r-4 nL e
nL e
g 0
0 .
wh et L3 4
nL e
nL e
u& e m
s m
m m
gmg d li g , ,
0, ce 1i r- g , g , s3 e a 0pn i
e l w eI 1 1 1 w eI 1 1 u0 0 i s o sP m6 m7 4 n o sP m6 m7 b5 3 4 4di U f n i o r ,
a4 e-a4 e-
>a l
f n i o r ,
a4 e-a4 e- Vn 0
A 0
4
> nmaop n
o ei u9 t I tI wa ei u9 : tI tI R o w o o i
t ht t a i
s2 s4 e -
re S L E"S [L h" [ l ob fe ht t a i
s2 s4 e- re S L E S" [L h"
[
6V 1
t t o5 s l 2 e f9 r a f c rI t s f c rI t 0 4 4 - r c on u
PP i . . I e onu " PP( i . . 4 0 0 I I o i " [ Ea b S m Ea b " & 3 3 SF c d l n n n l n . . .
yAan 1 . . . . . .
I A a 1 2 3 2 3 4 5 6 f
o s
s o
~
l -
)
n &
u g )
e 0
g i
0 0
4 0
( 0 4
s >
e (
b )
u e4 t
G e2 t
S 4 G1 n 0 S o 1 R i > 1A t S i f fF d o o(
n o e er C r re g l u uw l o n i i p i a a t f f e a t i d si t i ss
. i p of n a rf
-- I R Go
=
L.
/
y r
ak y
r ie ma o rL g P e y t l r) a aad C
m nd 't r
- oon
~ nco b eC y AS(
2
ei a a 1 gs r r
- rs e e 2 ea n n ml e e 1 EC G G 4 2 e / ,
l e 28 b g 4 % s aa s s9 3 u TF r , u > ,t y o r l , ) a r b t h p6 s7t h s f o
- g F
4 r s se du i
n ,
or
/
R m
39
/ - t o%s n a
/
R m n ml r p e et t a e 0 e 0l mh 2I i , o t i i m g at n 1
/ 0 F n6i n 0 f a n/ cs o >d aR 2 h( o6t e 0 : 6 s ns oi i l e 1 t m9 a m 6 g0l o i C dt t eo i r3 > i ,
n ,l n > n1 e ce sp nn s sc a0 E 9 w)9 e5 s o i a
i -
9 wE e v
tt h s i 0 i e a e
a ed m
e 0 m4 g6i t . 0 oR l n f0 sn l rn g0 n
1 r9 a
o9 r
nS oC 1l) en s>
3 ai a
ca e
,tn l 2 n mi t a6 E l , d cD E o( o u w tt a ds r> R a7 y4 e m sr Rf1 i t
rs on h o sn oo r e
h8 g2
)
2
( : "y 4
9 h%n t - i t o
)
2 er a (h o i t l se nv si t
l c o et ru .
unF5 i1 1 a ,
nI a eS 1 tti ad ,i le sa yr y ti*
h gr5 eHt gS i r t o t am33 r r np4 m[ n aD rf n rmy st i i r 82 t o o is9 n o m ay ooo oen yn rn r g
e02>
n t w - inc t m hovo l e go p6<
e , i otI ao .db i e grri ac ei e s m7 n l nF ti e nnm i ut nn t t t et er n2 o l e( nt rmld ooo hesal ao na n: t sru i 1 m om oaoiae m o i c i v i g aus d a , f ng crnd t i rn t r s pd d l r nglt s e t l ii ui l s mml a at t e , Si e a e eae ,4 eotnrst eae r a er cc ns m cr m s n6 C wl err U o2 u ht p uel i sh ,i u ebi R o hep mod n
o c1 3M f
d t n fc25
]f c o50 onegrt onit e h ue fl pf m
dt a ohaioh nen@oeo c
r mmd n
i l s fll ldt p oooneC s
i t 3 e o">93 cOlSd eaS ctMhrC p aat fCitR t f) l t u s a
c o2$
( !
l i $
a '!
y n .
id an . . .
$ ns@$
oii!
se i
d 21 E F A a b c d. F aa b c E Cvl E eh t t a.
n . . . . .
. I 1 2 3 1 2 3
, l a S i tC t nR n e e ef m
t r o o i p as t s e no h . ol t y c t r hi f o t r of i g wet sl s a nn oi oi lt i n t t de an nt i e aop n dn o o ar e i ri ge t a ah i ht gn mt d a n io dh t o hc C li tf ew g no e
u f yy n
i ms t t t ns eii a io vrr igg i al t t see i nr st t n oo a nn I cf Mii e
g a
y m a
r D o
g l e e t u a F C
e r
o
- i. C 3
ei gs E a 1 t u
- rs e r s 2 ea t e u ml i l n 1 EC S A U 5
e l e ,
bg mh m, e aa s og t so l t TP '
r moi r rh c
u h r mo rr p c u m
s h i ,d / i a d r / f esmo R f ess o o R nl opr morop m nl m r t m opr e p i cmir 0 cmih n . 0 ef n 2 aft n or 0 6 sneo 1 6sn o mH 6 0 oli 1 0 on i
/ > 1 ecps 1 eci s aR h ms - h s e 9 : Ett ai . 9 : E tt s i .
r3 0 gR nsf n g 0 gR nl f n a0 1 n) ne 1 n) nee g E - i2i mes/ - i2 i mv s/
e E w( uh wi E w( ue wi g0 R o1 srt oC R o1 srl oc n ) l l t hp ) l l t h p a6 2 l resns 2 l resn s r1 ( oovni ft ei s0 0 ( o ovno ft eii 0
1 1 s6 h8 il si3 i l t i >
g2 r en yl s1 r e n ya s i1 o honeey o h onei ys n r t t movvl n t t movd l n i i r eao i i ra ao t o n f mt ul ni n f mt ur ni n o ooas at o o oas at e7 m oi n a m oi d a d m2 erddol r e rdde l r e n1 l n ali at l i al s at U
s i a ,
e u
oeret cn e u
r erea o cn t6 f t l
ph&imc aie f t l
p h & re m, mc s mgncoe n ie n n2 smgnden o o1 d aaiaaho d a aianoho i c- e eShHrC c e eS hHirC c t H l l l l a 3R i$ ig c a" t . . .
an t . .
i d
f) F
- Aa b c F e A a. b c o2 n ( . '. . .
_ I 21 1 2 1 2 n
o i
t a
i n d o a e i r g t a e i hg m g d a a n i d m o h a C l d t e ..
g n u l n n e f e o i m u i t n e f t a i v a i a i s c t t s s i i n s o f n o a r i I C M C t o
N 2
7 0
5 e R g F a C y m a 0 r D 1 o
g l r e e) o t ud f a
C F 't 1 en ro 2
oC
, C( S C
D 3
e e
S
) ;1 jl l!I IlIj l{
o c
- n n e g
o t i r n t e e yc a m v E E ci nf l l ei gs a a 1 r t u
- rs e r s ea n e u
- 2. ~ ml e l n 1 EC G A U 6
e l e bg ] ]
aa )
g
)
g TF p
i e
i e e "t
rr
]
) "t rr
]
) %
S C
F i p p t eh eh 0 F r r a l/ l/ l9 e t 0 0 r ab ab l2 n t r
3 3 l I a o a 5 5 k l l m w oe "s < "s < a e* ee no 4 ed t n s s e n0 n0 orf 8 re
]} co e3 e3 l n1 ax n1 e3 ue 33 ai r/ r/
y ax ) r4 tf M4 7 et p2 p2 h9 h9 %n u- a
- ra (
o
( r a
c c 5 o t0 r5 II w] t rm 4 1 2 L3 d l >
3 l>
3 >i (t
a7 r
e9 p
LL o4 ui 8 8 n o o a e& mf l1 f0 of
- n o4 L - m4 o I - c s
i2 s
i2 et sn p& t eo m
t o e ae r-4 e8 22 I I / / t 67 sc &P BF s &1( 81 em t1 le r - r lII 44 s- -
eI tF a
ih ft p , p , o o9 o9 t .
p o5 . g5
(
cn nt r-4 e0 al ct ou o
- ELL w ,] i o6 o7 - e o7 : ie t7 lo g
n v
e , ,
d77 gw n
l4 l4 yu rg lM l4 g n
n s r y yn i 11 1 e03 e00 i n wo eI eI a eI eI i
ri e
wr eb be p oar . e ed dr w f44 nP nF m0 i1 nF nF w GM7 i -
o 4 - - oi i i i i o r
-- de s
l l
o 5 - -
gLL II yII rFF a
lt l a oi l ,
m 8
l , r m7 8 pt s
l .
m6 4 .
l ,
m7 4
l l
o dco peol fe gat eo.
mt rar t
r U f n(( i , .
l26 fc n
aM e-a4 e-da ee a4 e-a4 e-f eup nc i ce o -
e ct rn i ii fit t n e s i03 eu : tI tI ml tI tI sd nda c -
o h nGJ x09 hn r S r r S F r_s F h oeo an one a i
t t eSS e
r*
u44 a- -
t n a
e h
s P E * [F
- [ it fa n
e *[
h o*[ t goc eca rt eI r
c Cib e r
a c
f o eAS oFF II f ol i e
t E a b
of Co Ea t
i . .
f o nne e .dn . o i
d D" N((
l n b Uer Daab N n yA . l a . . . . .
31 I 1 2 Ap 1 2 3 1 2 3 k~
a e -
d l e y wr ou l o r
a t lh d n o
f1 n) o5 d e
> c i
, e2 c rr s n eo 4 i tf o1 s t y p
r r ee yak l et rS a' ea aF h
<* i m( t n
p rm p e f g r
'e h e n sy t0 t o or i1 a _
i l a w f w _
t i d i al ko e d
n i a es f e -
hx) o t u1 rs )
C g
n i a1 w
t o f1 be ex ne c
n6 i
n.
1 n.-
o -
i n 4 i o4 i -
t es1 l n i1 t a i s i t a i soR m cA c t nlA ae a A i i
n a
ryF S et t a
&5 eF f
i I Tb( Sr R( t .
o N
2 7
0 t 5 n
a R l F o C _
y o
C 0 r 1 o y _
g r r e ay o t dl f a na C om co 1
en 2 SA
, S C
. D 4
e e
S
,~
' , lj?)!l1
's
~
y c
o n -
^
n e y - _ ~
o g c.
- ~
, t.
~
i a t.
t e s
e - .
s e-se'
~
a m g .
v _ v
- yc - E r E E
~~
ci e nf l m l 'l -
ei a E' a~ a 4 ' gs r t u u
- r s e e r s s 2 ea n t e u u ml e i l n n 1 EC G S A U U 7
e l e b g aa TP
~
~
t f M 0 O P P y y l l r r n y n o o o l o' S S n
s o s S S t t d
.D D n s' n e o o e u
t e s n u U
t t l e l d d f -
f u' f l f n e e e f e o t t f i r r e e e t o o n n a p p r d r c e e' o i o~
i r r' b u b
- d. r q r -
r s s i i i I A A A L A l
a )
c .
.i n - es l -
g o
o sy eg . e n t n a n d h a ,i o c l
o e d t o ul t . t ssi n i i s sr t o n s
s r s i no n r nuei i h o
l d a l osir i ee li ohd t c e e e b e: remo ht a a e
.v e
t e
r u d vg en yt h u2t e d' e
t e m
cn ht n o c T e e iA2t c i l m s a
li rt n r t a ar n( >a l f s t wu i rm u h i e
.. t
.l e c t ooemo s a c rRa c m c a m e cl hh f e a dp e .omci e i) e u j el t2 s e e Tsf p t 3 -
t t s o t o% dr m t t t I g S -
e c e r ef rrie cn sid o 02 d a t p d rooov s ea emetl l 1 r
a eoff rd ya e jl miuuo a $4 s r s shf t op il nor c) 1 r e e rt r yh a r t ibo i 2 t o: d e t o yudt r r pn st ae n uR t r n s a' tfdoo o o 0 un t h2 bA i e y u o rs i oohbef e s 1 oof e c S nh d d r n b h s ed >ecom e4 l F ot o y ee oy 5et y o t e n
- mie bdr i a e'
v st oe : mne al rooa l r d as ra saf ee t ti sg T1 >(
t' n t R . -
o gt eod o dm gt oohtd e b nn oa nA ns a v run e ea nnol rn b nnohf w ,dr eS et i i et oyu a er i et w o s , uth e uF ui t wu hh o va op wu rrho b oy l scav l( l m i ol gwtb e ol grhh/b a~ dr f ni a f fi d
n lf n l fi rre h b lf nh//R e
a fih n fd fl -
o oedhht s t at n
lfi/RR me ed e wir ee e oedR mm t h hn n e d n eonm C f n//i n f f a f 0i t s t u l oetd l e l o g enp eoRR s o osn ol p e n p0 5 0 5 000 s n o ait l n ae ai , -
n h rs15 e i
t r o r h rs5252 e f o ori fb o
ct auu iars cc ia ct n - -
i t oe .h i e r e r t oe>>>>h e gc ey ge i a gc o -
t a
br' f rr))
t d n
h i v
h e br t v nne Agn si t oisrr a
o oi i
t -
i oio1 2t o i t
n i t h t
f rr))))
oio1 234t Aj l f u oiodd l s ot l f oi a
c t Ac(( ac E e Eo Ac(((( a icel n ii ic a i y denuu dm de f n n apeoo ap M e.
ai i I b c A a. b. c Rst wb Rl RS t o =-
- N -
2
.70 t .5 -
n k e t u C l
y f 0 r f 1 o E g -r e l o t
a a
m f _ _
C r 5 o
n 2 _
b .
A S C
5 D _
e e ._
l, - S i
( l1 l! ! IIli
ei gs a E E 1 r
- rs e e e 2 ea n t t ml e i i 1 EC G S S 8
e l e b g aa TF s l
e
)
s t
e i i
)
H D
)]
f I O ) ) ) 33 lh ) )
M ( s a s net s e O 2 p p p 87 4 os o p p l
( O m
a m
a m
a w
o eb m a
s l C
I I Vi e n a 2 0 0 0 l
f LL 0
Dr o
o O 'n ( (
0 0 r C o
(
r
, . gf ( ( o 2 2 2 e 22 67 "e r
e" 2 "e f n 2 r 4 0 O O t 44 gmd O D u s o 0 C C C a l - - aE e C C l r 2
2 n n n w) e1I d7 vLL t
l" l n
i 4 e r b n a0 t 0 o o o e3 e o&a o o fC e 2 e r r r e0l . , v s r g m
g r t f4 1 1 : r6i r rd t e e e e - o67 g e0d e e n en l n e m t t t yI s44 n dA t t i wa o i t e m
e e rF - - i n m e e w o v
_ w e t i
m m m a g1 I w u ,e s m o p ,
o m M m m m i , nLL o 5t su m l 3 e d l a a a l6i(( l s0 s a a l r0 h e l t i x i3 s l uA y o eC t s o M u 3 4 1 s0 aGG o b ,s 3 4 f t U f a 0 0 0 u4 eSS f 0 0 ,
ns n e x
u n A A A a- r I c" " e V4 g K0n A A h
e h2 cO oei o h a o o o o oF eAB h Ai o ot t nC Vr i t i t t t N[D" "
t t h t 6 ,t t u e
- 1. 3 ra t f n . 0t a f i a 4 4 2 t f 4 4 o nl 0t c o n t 0 0 O o . ~. o 40t 0 0 Ao 1 a i U S M 1 X B e b " A s 2 2 h " C
u Co f r Ah o e w
e1 s o t > s p i
s r o no l C of D d
n e l r l e a t i
at r s s n a e e n o d w w t o i nd o u t ae p n l i e i a d ef e m t n t t i o i y i 5 v c s r f a s 1 g fi f > l f l n ol o r a i i o t f x f f f i
a oua o o s
r i
t sl s e s s w s n ol o o o I L a L p L l )
a e c g i
r a y t p r c t
_ o g
e x l s e E e e t r n a ru d C ol e ji aa u MF n i
.e t n
- 6. o C
(
hrl l ,!1
1 gs t u u u
- r s r s s s u
. 2 ea e u u n n n ml l
- 1 Ec A U U U 9
e l e b g a a TP s l
e s
e i %
D 0 5 .
l h ) ) > ) ) m net s s s s e os o p p t p p t Vi eb m a
m a
a p .
m ma a s s
y Dr g i s & r S O o O 0 n r r 0 0 e gf ( ( i t e ( ( t gs "e
r w t e nl "e e" 2 2 o e p "e e 2 2 gm i e gmd O 0 l n i gm O O at t s aE e C C l i r a t C C t l r e t
- l o b t t l l o ai l b n n f r l o n n ov t D o& a o o u e o v o o : vr S
- vr6i s e t n v 6 h r r h - i : r 4 r r g e0 l t g e0d e e t t b g e 0 e e n dA eo n dA t t u r n d A t t i n sb i
.n m e e f o u i n e e w ud e w ta e m m o k t w u & m m o n i r o 5. t m m c o m m l s a D o d l s0 s a a h o t l s 3 a a l u f e uA y u u 0 o y s
l o b s 3 4 t
on l o
l o b A 3 4 f b5 0 c V4 . g U f 0 0 B er k f 0 0 VA n d" A A wo c V n A A e K e e n e K0 n rot o e K o h n gl o h Ai o o opa l h o o t 6 o rb i t 6 ,tr t t r t 6 V t t 1 e a t
a f 1
3 a 4 4 s r e ron i t
f 1
0 4 4 f
o 4 V ms Ei c o 40t O O et e n o 4 O O " O " D i " A s X X h cG U * & X X h d l l t n l . . .
it e a . . l . . .
o ; .
I A 1 2 3 -
E r1 2 A 1 2 3 B 1 2 C
A e y t s t i
s e i t l n u i o n b i a l ) m p l 9 a a 5 c 1 1 f > r o 4 e 1 r w s e o s R w p o A o l S p C F A d ( e n t e a d i t a s i rs o f s n ee l f n o wt o o i ou l t pn a f f i i c o o d
n t em i r s s o i5 t s s) c sl c o os g
f <
f e l l e .
n or l
e d t n o d u o i
ff e en i t
a f n ni t o o i im a i r a a c t se s t t 5 i
n sw s s sl i
f I
oo L p o u u> i L S S( t o
N 2
7
) 0 5
l d a
c 't R F
i n C y ro t C 0 r c( 1 o e g l s r e E e o t r f a ru C ol 1 ji aa 2 MF S
C
- 6.
D e
e f S
y p _
e _
3, _
n y y y y
-~
o c t c c c t t i n n n n n n n t e e e e e e e a g v g g g v v yc r E r r r E E _
i e e e
_ c.if e 1 h m n l l
,. ss m E a E a a 1 t e
t t t u u
- e r e e r r r s s e
2 10 e
1 ea ml EC t
i S
l A h i t
S i
t s
t i
S l
A e
l A
e l
A e
n U
u h
B u
l e bg aa r TP o r r r r r r g
n --
o o s o o o o i
=
s s s s s k i
v r
i v
r i
v r
i v
r i
v r
i v
r n
a e e e e e e l _
p g g g g p u
e u
s i
s a
s e e n _
f f f S n e s o e e s s s s s s i i i n n n n n n r h h h o o o o o o e C C C i i i i i i p t t t t t t o e e a a a a a a t d d d r r r r r r n g
a a g
a g e e e e e e a p p p p p p l i
r i
r i
r o O o o O O p
- B B B y y y y 'y y y b b b b b b b e e e r r r n n s n n n n S n i i i o o a o o o o S o F F F i i D i i i i Di
. d t t t t t t t e y y y a a y a a a ae oa s b b b vr vr b v vr v vc t vr u r r rr _
d d d e e d e e e eo de n e e e s s e s e s sf es i
o t r
t r
t r b o
b o i r b e
b e
b a
boy tb re t o o o a t o a p p p l l g l l l li p1
- c e e e a a e e a a ar em i r r r u u r s u u uu rus d
s s s e s s sc n s s i i s i i i i e si
, I A A A v v A v v v vs Av l )
sg o e t s an ei t r c n
nay a
g
- f rd n e lt of f aul o f pi c
-f e o o c l i l c e gi n
. de s as o e h nc o s i s n t e n c t ias t s m su i a
i r tfe m e v) & u n c s r e
t t
s dl ea t r
oc s
o s
i h
ena fi g t y o s
y y
s li lt o tt ne t e y t
i f
ass i
l l e'
s oi w i u n w es i y rn t ,
n a ( yse c f
y t
e a
t f
e a
s ti n
or cet .
t o
e gg nn ii rd el i
5 m
1' f m_
o r
a e
r a
l t ac igo iep cl r
f a
r e
e l
f s eft g ti > abl v f han a nu . y d fae o r f o t e m eb mn t e o o
n nepsm d a
sy oo i t omum mr y s i oti er oi l c e
t ao t n a us g ea rt a
i l n i o n rnay c t ef v i i r n ni lt a o g g s n
o a
r t oie i s
gl s le os r
f r p arn i
t o' i t e a m g u eas t n n moi a d c
a l
g t
2 n
o e0n r1i a
c l ua bag nw oo o n dcu i
d a>h e cd s i il t e n m, sc f _
n g g s t s m,s t t h ot a e _
~c o
i n
i n l gi anu cm ae sms eoe f u oh c
e s
a iTe s
r c
t i
t t ti g pt l oc s p r o .t r s .
g n
c e
c e
it n ms fro r
n oe s c l pne n i n n vsi i y i a o o i
t f
f f
f at nl x e s rl p oort it t o e t
f xom ein l re i
t a a a i e l y am ue l a nart o a osa a i
e t
ene it se ct s cr i r c
u c
.t i r e
r rar sf ine sor a s
s r wri oev s
u re al i
f n i i ili ia oco vt i i npn n ee i I F F F pf Ms T( n Ea M a Koe U Nr t o
m 2
7 0
5 t R n F a C l
y P 0 r 1 o on g t o r e i o -
t st f a da C
- rr 1
.
- ae zp 2 aO H S
- C D
8 e e
S
i' i!
n y y o c c t t t i n n n n n t e e e e e yc a g g v v v r r E E E ci e e nf m m l l l
_ ei E E a a a
_ 1 gs t t t t u u u
- rs e e r r r r s s s 2 ea t t e e e e u u u n
ml i i l l l l n n 1 1 EC S S A A A A U U U 1
_ e l e bg aa f . y TF o r b v d- 9' e
g y t
en i oen 3e
.d a s f cei m m.
o m
a s i
ryud k sr ii
. o d n eban f w -
m o
r l i o v wu rl o l no eol o p a t doif vceb -
r r a n r e m
u u r ag eM o l&
t r p t e hp n ,r s '
n . a c p sina i rl9 -
e s e g
d e
u rt O m hki pass v
r ee -
m m t v0 -
n o h e ti r l 0 ahnr e ae1 i o c f sp o l a
0 rsoe g p wl -
a r t 1 cb t t) t i y tl S h > odsm s ,ral n G w r ne S rniu ge e ~
o c
D E
s i
a au df D e n
s a
euWn l o s
n nblee v im
- l l n y i erfe cgon o navl -
_ o g h a i et b b d i nhe -
t n t t x t n r e c o t ucl*
i o i u t e n u t al yh a r ey( 7 e w b v a ap o t a atP r g o s i c 2 ci( e sga d
e a l l
n n n i i i h
t r t
a i n i d
2is srr O p prbr m ueo m
U s
d a
f o
r r r i o w
v r r i n f yee ohvt y usro p ol e e e t e e pi n b nff n
a l
a e t a
t a
t a
en k e b s t a
d e
n olUC ne d We C ' ge -
j r ht w w w am o w e ia ) e ns --
t a t u f
- un qi l f p
s t ugc3 at ni2 d g oOiu n ro c c o 3' 2 2' h a a u
o vcim- u wuh -
i u > > ? tt d iat sP j hosp d r rn s n t ciI tl as a n t . . . ao i 6" i cyaeP s i eei
. I S Adn1 2 3 Ec V > W AbtSE A Wbmp e -
k -
a -
d u q
e s h -
u t a r -
c a -
e
. s g i
. s -
e a --
( b s g y a n t s e i i l r t l e -
a a i v e l r c e t e t . e a l i v n) p o
f s e es ml e l p m l
pe n h e i o r iv a t v s r e -
ue h g e e f t a
n ql t l d e
o e n w i
t l p r e
i k p f o
l b n i e ai t i i i a d g t s a r s s s g n a ie e t e s e i i o m vd r s d e k v h C a g c a c d n> o r x u q
o i ,
g i e d a e d M n n h e k a e h a o i t gh = n n n t n e i -
t a
i nc ii ~
r o e i r a
r o
k a
t a
w i de t h s e t L c t d os n c d y y i
i n o r y i n w f n n e n n i l y a i o i _
I W Fb E A S W a A L t o
N 2 _
7 _
0 5
R m
t s
F C _ _
y n 0 _
r e 1 o
g v r E
e o t l f a a C r 1 u
t 2 a
' N S C
D 9 e e
S ll ,lIhl1 ,
n o t t i n n t e e yc a v v E E ci _
nf l l _
ei a e 1 gs t t t u u _
- rs r r r s e
- 2. ~
ea e e e u u ml l l l n n 12 Ec A A A U U 1
e l e bg aa r TP o n t & o a i c 2 . t .
g 4i t O S a 3 0d o C 5 r 0 n Cn n D b C i i , i s
". vg n t 1 4 y f u od u 0 0 b y o o e p n 0 C h rt t w d r n k .
oa ti u
o a
r n
o n
o en o i s r c ec a ns ac d rr i i a b ii io r h "e
ee m v e bd s
o t dd t e g "e r r b n r _
r aa r e e o ur
- a. as
.m e c
t t
i w
y l
u ee hh m
f i
n l
u i d t
e s
p u o f
m r
t o eor d e l l
i f
a rtt ess o o l
o f a
s e 9
1 l a
f e od a
tf u t ee s c : a n 0 a nl g
- u ono n g e f r e g aww n i t g
n r
e n
- i g b 6
- n i ob i
n ti a s
e w4 o0 n
i e w&& a r
n e
i w w o i o n i u r R T i o t a a
i w st r t pC w chh t n o p t w T t my o ra o o ca o " n a ) itt l a rb d l im e c r2 l vur h p l r l o r i e l fr t i o( l roo t m o o i l r b f n s o i a d t1 o esn o o f t d o ot n o i no
. U f df en dg i i n a i .
f s b c e i i a n f a i.
v oi _
= ct n
o h e no nc en mi c3 n0 h e f=
o12 f
o o f h c e i c
t s g n
a _
i t
t a lh ry ea I
P R
uC n) t stt s s t
f n ede l h
t n u im al ci i r
l r at ue a f f s o n d sn o oLs a pt t c n2 sii n i f -
c o ni Uw ne Id 1
A( o onn LUU A
a o n A
n7 e ie i " 1 L h F I > B Vp d
I n
1 1_
A 1 2
3 1
I n
A_ 1 2
3 t
t o
1 2
jlA 1 2
3 4
i l
4 ot l e > rn a l t a c i r nl _
i h o op .
t w f c g s i e r s n a en c n
c e a hi b t ks t r e _
ou u i u t s i
n t u
nu i q q
e
_ mr eo m h s sr e s n
t t 5 m o sc ya 1
d l
r s ar c
se o l e h r t c at t n s e i os on rn ow rm w i g l w o
oa t n f o r e ci )d d sa r er st dt np u tb ru eu o l o oh dh i m i rh t s es t e a n pc a e at f o i id nd cs i rh cl l iy l t
i t ow no uc so nc ds n
a c
d cp n o i y i
_ n o
ai er nn ai it t a l a r n a
C rt (
t c
ne am ni h
ce o
f a so ul or n n o e mn fi ip . m o enw n i r h t i t et as f w e t
. i a re ul li a
o s mood t
n i
a c
t l p t sr f mt b i i i m li su nou r f _
n ao l n oo ooh u i I Fc au Lh Nrs T t o
N
_ 2 7
0 _
5 _
R _
n F _
w C o
y d 0 r t 1 o u g hn r e S o o t i f a tt c nc an 1 l u 2 PF S
C _
D 0
1 e e
S l!li _
ei a a 1 gs t t t t u u
- r s r r r r s s 2 ea e e e e u u ol J
l l l l n n 13 FC A A A A U U 1
e .
l e_
b g a a e g
TP e l d r b f i i o o r a n e b
t n n t g r
t i yeree g e e m
a p h n m h rt i n n c l o i, d i i e a n a a n u .
nll o e t t i f) oa L e n n 1 i r o o r t2 t m e o C C v n2 ao C
r o
t i
c 1 o2 r" S g
i e-ps sI t cr if d
y V 1 t1
- 2i2 y n
( nn i o b r o
g- n- b ot i nE os nen dt eas.
- S t i R ml ) t g S e e e g S a w) n S ev c c c ecr n D l r i D e n n n pi e i u o 2 "e (2 o l( w ra e e e sdw w ot p l1 t1 t o a o o . oe r r
r r
r no o i i l t g t r r dit d l n f nl nn l n ca u u u n e l d a ouoo o di i c c c i nl s o er m e c m f el V g n n n woa U f t o td n o o o ic n e rs oi n
o t rt h .marai m "s h e rn oa ni o
c c c l ti l cg o h pv fl al e t ph S S S aeo er m . oApAg e S S S i
t a
t f
rep r a$ 2 y f
o rl e
mr ad D D D fi o rl odr c o su l 8 n . . su l & & & o i AS A8 Aa b h Af A& sde d t S S S snt n . . o . C C C eie 31
. I 1 2 3 B 1 2 D D D l wm l
y l a t a i i c c v i .
ny s i t i m f s n t ht a f t m e m
n c
a o
ci el ti t
e l
o n e
my i i c g a uc a d f a n c rn t a of i o t e n r r l sg o t s o nr c f nn t r i e o) eo i o m n 1 mi n / l e i e ht o d a l
s2 a ir s a m n a
cm i r e e4 l e f -
go u l 1 b p o e of f e ao t l r rA t sy e a oe d A s t r p e hS ec u S o t
a tF i( se n
s a eo t t i w g t g t t e d nr n n my n a t n ae a a t i
o r r
ni ed rm re r
r r
r fi ol t i dl a a a i i ii w& w w sb d o cu sa n t cb t r t t o o a y ae a a l s c e g er ht h h r ga t n t t ti .
g a e nat n m a
ai nc o
n o
ns apn i
d ml ai it os cne t i ie ii m a dx t r t t n f s u
ip i r i ie ihs t o l a d d dr nce i j e uo n n na gi s n a o o ow ih s I M Ft Cs C Ca S wa
~
g n
y i r l o d g nt e an t He a d r C li e ec ht
. uc FA O 1 2 1 1
' Jl . ,I!ll l l 1 . l j)'
i! iI jj lj 1 Q. _
n i
o t n
t e
i s
t n
t a
s e
t s
r
. t.s 4 t s
i t.
t e e e e e s.-
a v v v v v v _
v v yc E E E E E E E F ci sa f l l l l l l
_ l l ei a a a a a a a a 1 gs u u u u u u u u r s s s s s s s s s 2 ea u u u u u u u us ml n n n n n n n s 1 4 EC u U U U U ;
t U. U 1
e l e bg aa TP ] S S S p ) ) ) S S S i ) ) g D D D r - ) g g i t r ) i i s y' y y n i g s s p b b b o rf .i p p i on . p s 5 d d d n t t o 0 0 3 e e e o a cc a 5 3 3 7 n n n i z 5 5 ! ~i i i er rot
> "s s
s "s s
( < g m m m t
a i
l i r r r l a 3 e3 e3 3 s e e e u t t a / r/ r/ / p t t t c i uc 2 p2 p2 2 e e e l p ci ( ( ( ( 0 d d d a s d 0 o I" 0 c o t n 9 1 2 l3 S1 5 s s s h si r
" 4 - 8 8 3 l a a a l ih ft i9 h -
I 04 1 -
I o4 l -
I s4 s -
eI e
s e
s e
s' e' :
a u
n t
c .
e) gw i sP s
AP BP rP p
r u
c c c g a ps e e p , n n n n m xr c c n e , p . s e e e eu n n i n wo r7 o9 o9 o0. s e
m m m i
w y ( o e e p4 o6 o7 l3 m m m o b h r t oi 9 l 4 l 4 4 r o o o l .
S r r d
e l t t - - - r- p c c c l S n S8 u u -
s l a nI eI eI nP eI e n o A o D4 c c -
oi: eP nP n n U fcd ne m
n ,
i l
i i zP r , n g w o
w o
w o
f e
S n
i t yt n
o on .-
.n eut i5 8.
l ,
8 u9 a d d d h o a
m bs a
c c .
i o h no t nn a4 t9 m6 a4 m7 a4 s2 s4 r t u
t u
t u
t e if r de el S
S S
S
. t a
a n- e- e- e- e hS hS hS f r g D D f n oI t I t I rI d sC sC sC o a n dt c ol o CP SP SP PP i D D D l o ua & & -
i ei " [ " ( " { W n n n 'h A C j d
n ynt naa .
".[ ed ed ed t r S. S h n h n h n o so C C Wa I Apn 1 2 3 4 5 Wa Wa B 1 2 Af D D r
) .
2 l
g ra 1 n oti i 4 l g yp 1 l s o n ) so &
o i e uh c g r l n o 1 e
i nib i io r
n' u q of a g rt 1 om i
rs ii rm r e ce es t cee a se 4 i n rn ce p t. m t 1 ys t uo qi o npo g di -
cy et ei f
uS ny n
ns R ns rt is a A ra ua l i m S e
gy yi c t c ai masn ecpo l
o do er F
(
)
rr 4 ea t f ef ti mi o t f mm ii rc fi c
snus c a l 1 _
ge ye yh ps b nl a ei r ep sc e u i a w 4 f p t S t p eS nTrp eer s mu ad a
r 1 _
o n f o i p n t i d R e il al i yf u i nv h A n nh a sa tb s oi t S o ot t c c c h e cd i F i i ni di ent e s n w ( _
t t o en en t wor a fi i at mh rh oobi e o d a s
nc d i ec rd r d o o n t n i e ee pt ,f c ne r a o io aT nT u .p e or t C ni t i u d i u d c _
g it c
ny gy eh rs e. k tj e s i
n de ob c
nb e
i i c f g( a d
e an ti l
l l u
i ej n n n b r t nn f w t o l s f w fi s c oy r a ni a ood oo orno e pl t i
t l h d
sm i on p sl n M_
st st sytdi x na o S
C ._
i n pt su su e at c s i o. h eh n ra I Uw 1 s t s 'etrca an U Tf U n V _
C e t _
r n _
u e s l i .
a t s s _
ne ar t n _
m a a _
. y e l P F r _
r o/ T o
t s oe r _
g ys Cr o y e S n u t o l t s i t
a aa uy v C
yi t t mr r e or i u i
t ec op rj c f n au nm b e en a SF Si e AT R _
3 4 5. 6.
- 1 1 1 1
?
f.
- ~
, [Iil l
POINT BEACH NUCLEAR PLANT INCIDENT REPORT FORM j i
l l
Notification- Call Back l Answered .
Received !
NAWAS- Agency Time / Person Notified Time / Initials Manitowoc County / /
Kewaunee County / -/ -]
Wisconsin'DEG / / I (Warning Center 2)
- - State Patrol / /
(Fond du Lac) ]q
- SITE EMERGENCY'& GENERAL EMERGENCY only, j THIS [IS/IS NOT] A DRILL. l l
This is at the- )
-(Name) (Title) l Point Beach Nuclear Plant. An incident has occurred at our facility anc we have-(declared / terminated] a(n) [ UNUSUAL EVENT, ALERT, SITE EMERGENCY, GENERAL EMERGENCY) at on .
l j
(Time) (Date) i There (has/has not] been a radiological release to the environment, j Recommended protective actions are:
- a. Not required at this time.
- b. As follows:
Take shelter in following areas:
(Location, sector and miles radius) q Evacuate the following areas:
(Location, sector and miles radius)
Other in (Recommended Action) (Location)
'~
in -
(Recommended Action) (Location)
Relay this'information to Emergency Government immediately.
Verify this message by return telephone call to the appropriate number listed in your procedure.
-THIS [IS /IS NOT) A DRILL.
.EPIP-12
'(07-87)
= - = _ _ __ - _-
N 3 f <Alljj ? '
i s
..,)
?.
n' -
1 p
r G
f i I
a" , , -
EPIP 6.10-
/, t MINOR- ,
- g. , Revision 8 l 07-08-87 !
, PERSONNEL ASSEMBLY AND ACCOUNTABILITY ,
b J1.0 PURPOSE:-
The purpose'of this procedure is to detail a method for-(1) the assembly of-Li : personnel <on.the. plant site in the event of an emergency. situation and (2)'
the subsequent accounting of personnel. The goal of this procedure is to
~
E.k . account for-all personnel within 30 minutes of the evacuation alarm.
~
w- 2.0 ' REFERENCES 2.1 :EPIP.'6.1, " Limited Plant Evacuation"-
2.2 EPIP.6~.'2, " Plant Evacuation to Onsite Assembly Areas" y
~
- 2. 3 EPIP 6.3, " Plant'and Exclusion Area Evacuation to Offsite Assembly' 1 Areas", (
3.0 INITIAL CONDITIONS 3.1' A limited plant (EPIP 6.1), plant (EPIP 6.2), or an exclusion area
'(EPIP 6.3) evacuation has been ordered.
3.2~ The shift superintendent has determined.that personnel assembly and.
accountability is necessary.
4.0 ' PROCEDURE NOTE: 'IFlALL' PERSONS ARE NOT ACCOUNTED FOR WITHIN ABOUT 30 MINUTES OF AN
- : EVACUATION ALARM, IMPLEMENT' EPIP 12.2, " SEARCH AND RESCUE." a 4 .' 1' Shift Superintendent or Plant Operations Manager l
Coordinate personnel accountability..with the security ' shift commander
'and plant supervisors as required. Fonn EPIP 6.10a, " Accountability Short Form" may,be used to, summarize accountability results.
4.2 Security Shift Commander.
Perforin PBSP-1.9, " Plant Emergency Response" to complete accountability.
-. 1 I
t v .
I
~
EPIP 6.10 g
i
?r'c '
Page 2' 4.31 Designated Suoervisor at the Assembly Area (Including my Centers for Emergency' Operations)
- - 4. 3 .1 Upon arrival at.the assembly. area,'use form EPIP-6.10b-or an area roster (EPIP-6.10a),'to. compile a list-of.all
' personnel who are present.and accounted for. Personnel'
. rosters are availalle in the TSC/OSC, control room, health-
- physics station,
- El. 18.5' assembly 1 area.and the' EOF /SBCC.
4.3.2 Provide completed rosters to the security supervisor-(or.
designee) as' appropriate. ,
1 4.3.3- Update the respective' group roster as personnel-arriveLat or l
' depart from the assembly area.
4.3.4, Assign the task of ongoing-personnel' accountability'in the-
- emergency. response. facility to security' personnel,-as-appropriate.
p
! 4.4 Security Officer / Designee ,
. Perform'PBSP 1.9, " Plant Emergency Response."
(
. s; i
,~
l 1
1 i
1
\, .
l l
tr l
7----------
, ;q
- 1 c
, y i U. 4 p
-N ,
~
' ACCOUNTABILITY SHORT FORM J]
Q. ~
, J , , All ;- ,
i
.. Accounted Name s
For- '
of 'Lastf ..
- GROUP "(Yes/No). Missing Badge #- Location i Control Room
W , Duty Shift.-
- (including) DTA)
LHial'th Physics'-
l- S tation : ' '
, Chemistry &'HP ..
i
[. : ..
,t
. El..1815'!A'ssembly.
'Arsal
- Maintenance & Const
. Operations:
{ReliefCrew).
i
! Acknininstrative r (Technical' Services (RE, I&C,.TRN)
.EQRS- ._
TSC-l JSBCC.
"Sscuriy . j imC. -~
j A. 1 EPIPi 6.10a .
l l
/.(07-87)
M
ASSEMBLT AREA ROSTER
~
g- (Location)
Dept. or Name ' Organization- Arrived . Departed Destination 1
r.
(
l
{
, v.
a _
Routing: Route a copy to the security Lieutenant as soon as possible.
Completed By: Date:
r \,
l EPIP-6.10b Page of l
.(07-87)
. .. i
WJ '
. NAMES ' AND
- o- TELEPHONE NUMBERS jf<.
AssrMst.7 AarA orstonATrens
' DELETED ADM:NISTRATIVE
. ASSEMBLY LOCATION: El. 18.5' TSC Status- Name l'
- y 1
f 1
I
._ l L
.( -
. a, .
[
i I
I i
'l q
i i
I.
- EPIP-6.10c PAog 1 0F 7
~ (. (07-87) i
- ' s y, .
4 ASSEMBLY AREA CESIGNAT:ctis.
.E;RS ASSEMBLY LOCATION: El. 18.5' TSC .
l Status- 'Name l
1 l
1
-- q d
'l i
r E
1 i _
w:
l l
1 EPIP 6.10c PAGE 2 0F 7
-( .. (07-87) i.
3
- 3.
1 I i
l$ ,'
[ }' 't.' c, .
- . v. : cg.
p -
ASSEMBL7 AREA DESIGNATIC'fj3-p;
~HE:4:5:?? & HEA'.:H ?:.rt5: 5 ;f L . .
ASSEMBLY LOCATION: HP Station n 1 ' ';
i-
. Status. Name lI ','.
(k if j
r ,'q .
] -
4 s'
0
/ '
( ' .,
4 g.
I tr s
/
3c ll
's f
{ 1 l
< \ <
f
' \
-l j
l
. (. EPIP-6.10c PAGE 3 0F 7 .
- N (07-87) ! ,
l 4
s
's
- - _ - _ _ _ . _ _ _ _ _ _ . _ b
, , . r: A55EMBL7 Agga ogg;gyg77cyg "A:NTEN;JJcE ASSEMBLY LOCATION: El. 28,5' TSC Status Name M '
,\ ),',
t-
.i a
f L
i f
f
)
f
/
4 6' EPIP-6.10c PAGE 4 0F 7
'w. (07-87).
=-_____-_:_ __
y.
4 g;.;
g - ~ ~ .
f.
- x:'
..j.
j '
,y gs f. ax k N.{
,~ 7 c !; ^ t1,n h; ,s . s a gm-4 o -
. 3.
f.% ';N; ,_ Yz..Q. ASSEMBLY AREA ' des!Gr.,l:TIONS X; N.w3 :FIF;,- :n3 u .dtJ;, rgy' mn .,
+r
..M[
" 7 g
t.ocinox, n.18.s' rseg,g)l,-- 4,s'
,, Ass g p % . . . , ... .
~
' YO I
' l, 13 $ a '# W
~
y 7 # o- . L ' %" '
l '
I ~ .**I N , gd?p M r%
.s d .c a ,h.~' <
i
%. 3 i p ps 9. e % gql N-21 y n y ,
u a 8. n; ,L :.
{- .V j.
& ,r~p 't . '%p , ,
v- .4 , 1, I
- .A' ( . 3 . . . y g,
>i g 3- y
'S 'f. 5 y
.\ .
k Y' ,
.d ' k h'l -l
'%. m:n . ,\ ,
.fw.
+ Y 3_\sy, -
4
' > y?x 'ja&J i
Ag ,
- b
,6 .g( .
- 1 s
c > 4.c:,{ > c . g.. , ; -
g s L
'Duuuuum
'~
l,l 9; . . ,
2 A 4 I 8 h
7 ..
1 -Ni '
, r ,7 s x
'l;h tj Jf ) ". N , ,
is- .s. .
[.+.A, -
4 Q&
yh'
\
_f
.l
.g.
Ly
'1; % s ? - 'N '
/ -
.rj l 1;', 96, 3
( ^
.t -u. Ip -
. e. . -
sv
., g - .
T) f '/[ g y 3.% g
'.1
' a,*b._ l-t 1
- ), , 4(. fga
,k-
' g.
k, p +
y_. .
i'4 . 'g r .g
[ t +
,Y.
V-y ri .
- s 5p --
4
) 4 s u
]
, ')\
\ 4A g'\ .f.,
\
l
/4p (v. 4 * ,
7 by y 'f %
- .
- j')e ~-
3 iq. '/ ), t )
. c. .,
, t a s
.]4 a a . ,
a A p+g-4, s
g %y .PpGE50F7 ,..
J
( -(0HS76 EPIP-6.L){% Qt i ;. I s t
1 l u 1
'g. 7 a .cg +
t 'y; 1 g%
--[(q L i i g- s .V j ,
e xd e %> -t 9 i
[spg x (.3 4 j a- J p (
, j j L8.f YbOf _CA ?? 4 I
,,p- yr iv,
- 4, r' z'( / 6 f$F M?tw Sk* <
ASSEMBLY AREA DESIGNATIONS
.-,;..a,.......
-u. .,
. :Ur..r. . :. . l . .. :. a f-lr h ASSEMBLY-LOCATION: '. TSC Status'- Name, i:
- iv s b 'j,'
l _'8%
.~. .
1
~
.-: 9,kN,, ,
k \; 4l.2 ;
1 l}-
a, -
.+ s l
4 1
-Y j
i i
- 1 d
i i
i i
I 4
I
( EPIP-6.10e PAGE 6 0F 7
- k. (07-87)
m..
Q(
' i4 ASSEMZLY AREA' DESIGNATIONS TE :-21!:A; 5ER'/::E5 ASSEMBLY LOCATION: El. 18.S' TSC Status Name a',
(.
.EPIP-6.10e pagg 7 or 7
~
(07-87) l
gN .
Wy EPIP*/.2'1' .
-MIHOR Revision 8 07-08-87L
.c, .
ACTIVATION OF HEALTH PHYSICS' FACILITIES AT
, SITE BOUNDARY CONTROL CENTER
. 1.0 PURPOSE ,
s
- The primary purpose
- of. this procedure is' to prov'i de guidelines' for:
= activating the site' boundary control center (SBCC).during an alert, site or general; emergency. Modifications to these guidelines may.be imple-1
- .mented by the health physics director (Health Physicist).to meet the existing plant and site radiological' conditions.so as to ensure the con-tinued safety of plant personnel and the general public.
2.0 ACTIVATION OF HEALTH PHYSI'S C FACILITIES AT SBCC 2.1~ 'Offsite Health Physics Director The offsite health physics director or designated alternate is
~
y ,
responsible for directing health physics activities at the SBCC.
and for.providing radiation protection assistance as requested by the chemistry director. 1When the radcon/ waste manager'is' avail
..< .able,;the offsite health-physics l director'should report to him.
?(' Appendix "A," Offsite Health Physics Director Duties,'provides the specific guidelines for' accomplishment of.these duties. ;
242 L. Assistant to the Offsite Health Physics Director When manpowerLallows, another individual in health physics super-vision'will be assigned the. duties of assistant'offsite health physics:
director. This' individual.is' responsible for directing Health Physics personnel from the SBCC and for the coordination of all health physics . j related activities with the offsite HP director. -Appendix "B" provides j the guidelines for accomplishment of these duties.
2.3 The following teams will be manned by personnel as assigned by the offsite health physics director. Team duties are outlined in the respective. appendix.
Team Appendix Site Boundary Control Center / Radiation Control Team' B Survey Teams C Kewaunee/ Environmental Shuttle Team C
?
tj
/
f EPIP 7.2.1 ;
Page 2 l 4
s 2.4 Appendix "D," " Guidelines for Off-Site Survey Team Management," should be used as a guide for managing the activities of off-site survey teams.
I t
s
i EPIP 7.2.1 Page 3 l
APPENDIX "A" SITE BOUNDARY CONTROL CENTER OFFSITE HEALTH PHYFICS. DIRECTOR RESPONSIBILITIES & DUTIES 11 Obtain environmental data (wind speed, direction and stability !
class) from the chemistry director in the technical support center or the radcon/ waste manager as appropriate. ,j
- 2. Use results from EFIP 1.4, " Radiological Dose Evaluation," and .
EPIP 1.5, " Protective Action Evaluation," and determine the extent and location for the initial and follevup environmental surveys as j required.
q
- 3. When manpower availability allpws. designate another individual in Health Physics supervision to perform the dutiss of. assistant offsite '
i health physics director at the SBCC (EPIP 7.2.1,' Appendix "B"). . 'If j manpower is not sufficient, oerform the duties listed in Appendix "B." "
- 4. Coordinate with the radcon/ waste manager, when available, the control
-of dose and personnel exposure documentation within the exclusion area and off site, h 5. . Coordinate with the radcon/ waste manager, when available, on the evaluation of environmental radiological survey results, and make d recommendations consistent with the Emergency Plan with respect to j the general population (EPIP-1.4 and EPIP.1.5). 1
- 6. Coordinate off-site surveys with radcon/ waste manager when available. .
- 7. Assist'in' evaluating radiological aspects'of medical emergencies and I cocedinate response with the health physics director in.the TSC.
- 8. With Security, astablish access controls to coordinate access to the TSC/OSC i and the protected area. Ensure that all personnel entering or exiting ]
the site are properly accounted for and are equipped with the neces- i, sary' dose evaluation devices. Issue TLDs and SRDs as necessary. !
1 i
l
. 1
t I h C
, m.
[.i EPIP 7.2.1'
,, -Page.4' PPPENDIX "B" SITE BOUNDARY CONTROL CENTER ASSISTANT TO THE OFFSITE HEALTH PHYSICS DIRECTOR RESPONSIBILITIES &. DUTIES k 1,
. Direct the available Health Physics personnel in setting up and. making available for use' all SECC. health physics equipment. Verify theLavaila-
~
gs bility,and' operational status'of equipment using forms EPIP-7.2.la, -7.2.1b,
.and -7.2.lc.
- 2. . -Designate-Health Physics' personnel to man the following radiation-control
?. teams as personnel become available for duty.
'a. SBCC/ radiation Jsupport team ,(remaining Radiation Control Operators and-Auxiliary Operator Trainees),
- b. - Kewaunee/ environmental shuttle' team.
- 3. Initiate health physics radio-communications radio check (Channel.3 of FM '
radios).
4.- Receive environmental radiological survey instructions.from;the'offsiteL health physics director and direct survey team leader to conductfthe surveys.
(h . SITE BOUNDARY CONTROL CENTER-SITE' BOUNDARY CONTROL CENTER / RADIATION CONTROL TEAM RESPONSIBILITIES & DUTIES NOTE: DOCUMENT ACTIONS USING FORM EPIP-7.2'.la.
- 1. Set up and verify operational. status-of personnel friskers- .
- 2. . Establish step off pads at entrances to the SBCC as directed by the offsite health physics director.
- 3. Monitor personnel and equipment for contamination and perform decontami-nation'as necessary.
- 4. With Security, implement. control- and documentation of personnel entering or exiting the exclusion area.
L5. Implement controls for dosimetry issue, use, and documentation of personnel-exposure and control of exposure data. . Issue'TLDs and SRDs as necessary.
-6. . Coordinate all: health-physics activities with the assistant to the offsite 'i
-health physics director. 'i
.7 . Perform as. communicator / logger.in the HP area of the SBCC.
I
- 8. Perform oth'er duties as~ directed. .
3
- sb '
i' i-Mh . mum- h-m_u____..w____ _ _
7----_----
-- - - - - - ~
, y 12 ; -:. t , , 4 gj;
.W
.: r
,1 1 u !.
s'[ '
'EPIP-7.2.1
< e w Page 5-
.g
. 1 9 ,
' ~
APPENDIX "C" T-
) ,
SITE BOUNDARY CONTROL CENTER SURVEY TEAM l-RESPONSIBILITIES & DUTIES JO t.
lr # m,
).g .
.1. ; Set. up and verify, the operational status of the: SBCCr airisampling.. I
[4- j E.
- .and radiological 'urvey s equipment using form EPIP-7.2.lb. 1 l
l-
'2. Conduct all radiological surveys and air-sampling. Record all' air- .]
! ; ' sample data'and radiological. survey results. ~;
q
- 3.- Ensure'that'all air samples and radiological _ surveys are properly' -!
' logged and' identified prior to. turning them over to the' shuttle
~
?
team.
- i. .'
lc :4. Parform other duties as directed.
1
, . i.
1 J
' SITE BOUNDARY' CONTROL CENTER t j KEWAUNEE/ ENVIRONMENTAL SHUTTLE TEAM'- t
. o.
RESPONSIBILITIES & DUTIES .
f '
L
- 1. Complete form EPIP.-7.2.lc prior to' leaving the SBCC. d
'l 2-. Retrieve.-samples from mobile survey' teams and transport to TSC for. 0 Lanalysis.
i i
.3.
~ ..
4 Transport samples to Kewaunee Nuclear Power Plant.(KNPP) for analysis
. , as- directed by the assistant' to' the offsite' health physics ' director.
'W 4. If samples'are' transported to KNPP, document results of-analysis and qj report results to the health physics director.by' radio or telephone.
- 5. Perform other duties as directed.
i i
Lic: ,1; 6 -.'{-
1 s
,'r %
Pt t tt
)
EPIP 7.2.1 Page 6 j i
i APPENDIX "D" GUIDELINES FOR OFFSITE SURVEY TEAM MANAGEMENT The following is a discussion concerning tracking of radioactive " plumes" from an accidental release'of radioactivity from Point Beach Nur. lear Plant. .These items would be appropriate to use during drills / exercises, as well as an actual
{
release. These are not necessarily in the order they would be done, nor is this j list necessarily complete.
- 1. Offsite survey teams should be well briefed before they depart initially from SBCC. They should have an idea of the plume's suspected location and where they are going. The initial briefing should also include a discussion of current wind speed and direction. Throughout the drill /
exercise or actual emergency, the teams should be informed of changes in wind speed and direction.
- 2. When it can be reasonably assumed that a release has occurrec and that the wind direction will al. low the plume to be detected (i.e., the wind is blowing over land) it is appropriate to send out survey teams. When first sending teams out to find the plume, they should be sent out approximately one to two miles to find the boundaries and the centerline. Samples may be taken at this t_ime. After finding the plume at one mile, tracking the
(, plume to five to ten miles (if necessary) should be done, taking samples as desired.
- 3. When it can be reasonably assumed that the plume is nearing land (i.e., the wind direction is taking the plume from being over Lake Michigan to over land) it is permissible to send survey teams out before a release has actually been detected at the plant and is encouraged. The team (s) sent out should be instructed to proceed approximately one mile out on the road most accessible to the suspected location where the plume will make landfall. The team (s) should be told to read their meters often when doing this to avoid being taken by surprise by the plume.
- 4. The tear. should always be given specific directions, e.g., road / routes to follow from the SPCC to a sample location, one sampling location to another, to the SBCC from a sample point, etc. This can prevent the teams from needlessly traversing through the plume or from going too far out of the way.
- 5. Radio communications should be frequent between SBCC and the mobile survey teams. The teams should be asked where i. hey are, what the dose rates are, how the sampling is going, any problems, etc. Many communications will have to be initiated from the SBCC.
l
- 6. Generally speaking, the teams should be kept within the Emergency Planning Zone (EPZ) of ten miles.
(
^
EPIP 7.2.1 Page 7
- 7. Teams should be told when to don and remove bio-paks, if they don't ask, and a discussion of the need for taking KI tablets should be done before L
the teams initially leave the SBCC.
- 8. "This:is a drill" should be stated sometime during each and every communication, preferably at the beginning and end, if not a real emergency.
- 9. ' Use of pylons by survey teams should be considere'd,- especially on the-busier. roads.
L
- 10. Teams should be reminded to use and to refer to procedure EPIP 7.3.1. This should be done as part of the' initial briefing. l
- 11. Teams should perform a quick inventory of the survey. kits before initial [
departure. -This 'should include a response check of the survey instrumer.t.
Teams should ensure that the poly bottles are filled initially and that as bottles are.used, they obtain a sufficient number of filled bottles for future use.
- 12. The-teams should.be asked for.the reading from their SRDs periodically, as.
appropriate. '
r ,
s :
l.
i I
l-L
. POINT BEACH NUCLEAR PLANT.
RADIATION CONTROL TEAM EQUIPMENT INVENTORY'AND FUNCTIONAL TEST CHECKLIST
- 1. Inventory Dosimetry Devices m
Min. Required On Hand :Date. BJ 7- .TLDa 90' ~
0-500' mR SRDs- 50 0-5 R SRDs' :50'
- 2. Response Test' Type of- Serial- Check' Source Check source
' Instrument LNumber Used Criteria Results
~Ludlum 3 cpm cpm Ludlum 3 cpm- cpm-Ludlum 31 cpm- cpm
' VAMP mR/hr mR/hr
. Nuclear Chicago. _
cpm cpm 3; ! Functional Test'. Se_ rial Number .Date By
- a. :High volume air-sampler _ _ .
-(Bendix)
- b. High volume-air sampler, ,
q c. Low volume air sampler I (115~V AC)
- d. SRD charger-1 e.. FM base station radio test with TSC-Time hrs
- 4. Set up step'off pads and establish access control Time hrs
. p. . '. Reviewed by- Date
- \.c . Off-Site HP Director 1
EPIP-7.2.la-
- (07-87)
p POINT BEACH NUCLEAR PLANT 4
0FFSITE SAMPLING TEAM EQUIPMENT INVENTORY AND FUNCTIONAL TEST CHECKLIST i:,
Minimum On Item Required Hand Date By
'115 V'Radeco~ air sampler 1 Functional Test - Serial #
Scott cartridge holder. 1 Silver zeolite cartridge' holder 1 Air-particulate' filter (box) 1- !
Silver zeolite cartridge 5 Scott charcoal cartridge 5
.RO-2 survey meter 1
~
Response Test Serial Check Source Check Source Number- Used Criteria Results q
__ mR/hr mR/hr
_ mR/hr mR/hr Water-filled poly bottle 2 (1 liter) '
,. Liquid sample cubitainers 2
-(1 liter)
Stop watch with batteries- 1 Functional Test Scissora 1 Plastic suit (sets) 2 Gloves,.aurgeon's:(pr) _
6
- Self-reading dosimeters,-0-5 R 2 Self-reading' dosimeter charger 1 Functional Test Plastic bags
- '
12"x18" 6 5"x8"' 6 3"x5" 12 Flashlightivith spare bulb &
batteries 1 I
Functional Test I EPIP-7.2.'b-l Page 1 of 2 (07-87)
--- _O
, m ~
is p q- ,
s
- ,.~y' p
Minimum. Jon ~ j LItem' Required Hand Date By .A p
Smearsf(box of 100) 2 Tuck tape:(roll)
. It s . Sharpie, Flair; grease pencil-r ..
,& pencil: , 1 each Sample ID. tag (pad) 1 Sampling procedure:
.EPIP 7.3.1 Airborne. Sampling
-& Direct Dose' Rate Surv;y M Guidelines'& Attachment 5 Sampling forms:
EPIP-Ol' Airborne Radiation.
Survey Record -20 EPIP-02. Emergency Plan
' Survey Record ..
20 Survey Identification' Maps 1 pad-e CHP-34,.SRD Rezero Sheet 5 9 V batteries- 4' Cs-137 source 1 Clipboard ~ 1 Fuses. 5
. Coin envelopes'(pkg) .
,. 1 Broadbeam' flashlight with1 1- 7.5 V battery. 1 o- Functional-Test'
, 14 Q bucket- 1 T Snow,sovel (small)- 1 Plastic Petri dishes-(2" dia) 10 ,
'. l : Key,to. unlock site barricades' 1~
' Spare l site barricade key for shuttle' teant 1
. Equipment:Not.in Sample ~ Kits But' Required For Offsite Sampling:
'2200 watt generator 1
' Functional Test p
DC powered air sampler 1
' Functional Test Traffic cones- 4 Positive pressure breathing apparatus
'with at least one-backup air cylinder each 2 N .;
Portable'FM radio with roof antenna.
1 4 g
{ Functional Test.
.l
- # i j'" , . Reviewed by Date Offsite HP Director '
- j. .* .
J k j EPIP-7.2.lb Page 2 of 2
.(07-87) l
.. ]
.j: l POINT BEACH NUCLEAR PLANT
.i SHUTTLE TEAM EQUIPMENT INVENTORY 1
'AND FUNCTIONAL TEST. CHECKLIST yi
'1
]
L Minimum on !
- Item < Required- Hand Date . By . I Sit'e barricade key . .l
-i
.(obtained from Sample Kit) 1 ...
]
-Portable FM radio with roof i antenna 1 Functional Test Positive pressure breathing
.: apparatus with at least one backup air cylinder. 1 i
- Date Reviewed by. Offsite-HP Director.
!' {
i i:
(;
I i
-j i
i e
l p
S..
EPIP-7.2.lc
.(07-87).
t t i t i
-5 .
bm yf, j I
~'
ll EPIP 7.3.2-
. MINOR
[.
Revision 19 -)
I, '07-08-87 ~!
POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH LEVEL REACTOR COOLANT J1.0- INTRODUCTION i
-j
't ' 1.1 This procedure' outlines the. steps necessary to collect, handle and analyze'a high level reactor coolant sample which could result from
. gross: fuel failure.
- 1;2: Equipment' List \
A ~
set up the ~ following in' the primary ' sample hood prior to. collecting your. sample:
.1.2.1- The equipment detailed in Figures 2A and'2B, with the excep-
' tion of the sample bomb.
'1.2.2 Magne tic' ' stirrers, (120 VAC, battery or water / air powered)
-and one'50 ml poly beaker and a 50 ml beaker.
-1.2.3 pH/mv meters._(120 VAC or battery powered) and pH probe.
'i. .
1.2.4
~
A piston burette.
{
l'.2.5 A lead brick wall of sufficient size to temporarily. shihld -
-the sample in the analysis hood. '
'i
'1'.2.6 y
. Automatic pipets, continuously adjustable through 5 m1, -
,or equivalent.
1.2.7 " Remote handling tools located in-the' cabinet below thef j 1
hood.
j
.t 1.2.8- Prepare. a 1.0 liter sidearm flash with a correctly sized l solid. stopper and rubber septum over the sidearm. i
.h
- 1. 2. 9. Gas syringe ;
1 The following equipment is calso necessary for this' procedure and need to be made ready.
1.2.10 The gas partitioned for H2 analysis. Ensure adequate supply s of carrier and valve gas'(if. applicable). l i
1.2.11 The special cart used for transport of the sample bomb. 1 j
1.2.12 Tools for connecting and disconnecting sample bomb; i.e. , '
11/16" open end wrench or equivalent. j I
-/. . 1
. n'
(
1
. , 1
'I s
- hl.,. /
4
- h. l
- - - - - - - - - - - = - - - - - - - - - - - = - - - - -
3
- iy 1 M , J, ,
+
s: <:
EPIP 7.3.2 y +.
.x ,
. ,, lPage 2-i
!L b7 T / 'i; 112.13 LRemote v.alve. turning to'ol. .-This tool as well'as-those
~
m c q" ~ : mentioned inLStep 11.2.12 are nece'ssary:for sampling .
l L and: should be taken along and placed on the L sample bomb
-transport cart.
>g . _ _
.1.3i -Reagents
- The"following. reagents are also necessary and'need to:be prepared.
-1.3'1: .
0.1N'NaOH for~ boron. .0btain a-supply from normal boron y, , ' analysis.
1.3 ;2 - ; Mannitol fo;c boron analysis.
m, '
- 1. 4': Preliminary' Steps. Initials
.1. 4 .1. Standardize the~pH meter.
NOTE: IN THE EVENT OF LOSS OF AC POWER TO
'THE LABORATORY, USE OF" BATTERY,-AIR /-
OR WATER-POWERED ~ MAGNETIC STIRRER AND BATTERY-POWERED PH METER MAY BE; REQUIRED.
[ 1
, -. '(. '
. l '. '4 . 2 '
)
- K
. Organize as much of.the equipment.as possible 4
behind lead brick walls in an arrangement - '
' e
- that: allows for unobstructed view of all',
operations ~with the aid of the convex mirror q:. (See Figure 2A and 2B.)'
1.4.3 Put new rubber septum lon gas bomb.
11.4.4 Check out l and prime the piston burette with-
-, . . . '., fresh 011N NaOH: solution.
1.4.5 Make sure that the vacuum line is. attached to-the gas collection bomb at.the valve 1 location.
d Open valves.'1 and.2. Secure.. valve 3.
-1.4.6 Startup the gas chromatograph for hydrogen analysis. Ensure-calibration.-
1.4.7 ' RINSE THE. SAMPLE BOMB. DRAIN. TUBE, RECEIVING BEAKER AND TIPS OF TRANSFER PIPETS WITH DEION-IZED WATER TO REMOVE ANY CHLORIDE CONTAMINATION. li I
4
~!.
I t, . . .
EPIP 7.3.2 Page 3 1
2.0 PRELIMINARY EVALUATION Initials I NOTE: THIS EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT j TO ENTER THE AUXILIARY BUILDING OR SAMPLE ROOM TO OBTAIN A REACTOR COOLANT SAMPLE UNDER EMERGENCY CONDITIONS.
2.1 Indications of Possible Fuel Damage i
Some or all of the following would be present if fuel damage had occurred: ;
2.1.1 The letdown valve gallery monitor (RE-116) p would be unusually high or offscale.
2.1.2 The failed fuel monitor 1(2)RE-109 will be unusually high or offscale. :
i 2.1.3 The containment radiation monitors, 1(2)RE-211 '
and seal table monitors, 1(2)RE-212, would be unusually high or offscale. '
1 2.1.4 The containment low-range monitors, 1(2)RE-102 and 1(2)RE-107, would be reading unusually high or offscale.
{
2.1.5 The auxiliary building vent stack monitor, RE-214, would show a significant increase due to auxiliary building airborne activity from the letdown and charging pump areas.
2.1.6 The sample room area monitor,_1(2)RE-106, and charging pump area monitor, 1(2)RE-104, would give an indication of conditions in the auxiliary building and sample room. The chem lab area monitor (RE-103) would give an indication of lab conditions prior to sample analysis.
2.1.7 The automatic actions of E0P-0 have caused containment isolation.
2.2 Evaluation of Radiological Hazards in Access Areas Required Yor Sampling i 2.2.1 After evaluation of the radiation monitoring a system readouts, Health Physics will deter-mine what airborne and radiation surveys would be appropriate before auxiliary building l entry.
l
l \
EPIP 7.3.2 Page 4 Initials 2.2.2 Verify the requirements for auxiliary building sample room entry, i.e.,- (1) RWP requirements.
(2) clothing requirements, (3) respiratory requirements, and (4) dosimetry requirements including extremity dose nonitoring requirements, and (5) health physics coverage requirements including timekeeping.
2.3 Possible Loss of Component Cooling Or Instrument Air 2.3.1 Verify that component cooling is still in service to the affected unit. Sample cannot be obtained 3 without component cooling to sample room heat !
exchangers.
l
)
2.3.2 Verify that instrument air is still in service to the affected unit. Sample cannot be obtained without instrument air to open the sample valves.
1 3.0 REACTOR COOLANT SAMPLING PROCEDURE
( NOTE: THIS PROCEDURE SHALL NOT BE. INITIATED UNTIL THE EVALUATIONS DISCUSSED IN SECTION 2.0 HAVE BEEN COMPLETED AND REVIEWED BY DUTY & CALL SUPERINTENDENT (PLANT OPERATIONS MANAGER), DUTY HEALTH PHYSICS SUPERVISION (HEALTH PHYSICS DIRECTOR) AND THE DUTY SHIFT SUPERINTENDENT, AND THEIR APPROVAL HAS BEEN GRANTED.
3.1 Collecting a Pressurized Sample (Refer to Figure 1)
NOTE: THE FOLLOWING S"EPS WILL BE ACCOMPLISHED UNDER THE DIRECTION OF CHEMISTRY SUPERVISION.
3.1.1 Contact the control room and verify that the i
)
) demineralized water header pressure is maximized !
(approximately 100 to 120 psi).
~ NOTE: THIS STEP HAY BE DELETED IF REACTOR MAKEUP WATER IS USED FOR THE FLUSH.
i l
l I
i
_m_____.__--- __ l
t ir- P EPIP 7.3.2-Page 5 .
.)
Initi'als 3.1.2' .The'following steps '(a through'i).must be '
accomplished.before opening theincontainment sample isolation valve 955 (Step.3.1.3) and the hot leg samp.'a isolation valve'966C (Step 3.1.4).
i'
- a. ProceedLto the sample room and install.the shielded sample. bomb on the'outside wall of I the sample room using the fittings provided.
If the bomb is already installed,~ verify that the fittings.are tight.
CAUTION: BEFORE' REMOVING THE SWAGE LOCK CAPS g ._
- TO INSTALL THE BOMB,'.OPEN VALVES S
- 939, 940 AND 941 TO RELIEVE SYSTEM
- j. ,
PRESSURE. .CLOSE VALVES 939, 940 AND 941. PLACE A, WASTE BUCKET I
'DIRECTLY UNDER THE BOMB. .USE A PAPER' TOWEL SHIELD AND RUBBER GLOVES WHEN.
. REMOVING CAPS.
- b. Verify that the demineralized water line
,.. 'is connected from valve 945 to the de-l(. mineralized water manifold. Open demineralized H2 O valves 945, 947, and 948 and check for leaks on the bomb' fittings.
Shut valves.945, 947, and 948.
- c. Enter the sample room and close or verify closed the following-valves on the sample panel.
1
- 1. 961C - Normal hot leg sample bomb inlet.
- 2. 964C - normal hot leg' sample bomb outlet.
- 3. 9650 - normal hot leg sample bypass.
- 4. 968 - normal hot leg return valve. i
-j
- 5. 971 - normal hot leg sink sample valve.
(s.,
_l
-1 EPIP 7.3.2 .j Page'6. i Initials I
- d. . Notify the control room that the failed !
fuel monitor, 1(2)RE-109 will be'taken out-of-service for.. sampling'; then close E 1 938A - detector RE-109' inlet. valve 938B'- detector RE-109'outle.t valve 938C'- detector RE-109 metering valve ]j (Unit 2 only)- [
NOTE: . VERIFY THAT SC-938 IS OPEN. !
- e. Further verify that-there-is component cooling flow to the sample room heat exchangers by.
viewing the' local flow indicator (FI-603) ,
on the sample panel. i l
- f. Open or verify open the following valves on /
the sample panel.
l' 969A - sample system purge to volume control tank.
l1
- 2. 956C - normal hot. leg sample supply 'i' valve.
'f:-
- 3. 990 - residual heat removal sample }
.j supply valve. (D0 NOT USE FOR DRILLS.)
- g. Verify DI.' water system lineup.as follows:
- 1. For Unit 2, check open DI water valve
-(2-991) located on the east' wall of i sample room. -
- 2. For: Unit 1, check DI flow by momentarily opening the DI water valve in the Unit'l 4 primary sample hood. Check flow,-then .l; shut.
Le ;
i l
1
\. j l
/s t
EPIP 7.3.2
.. Page 7 Initials
- h. Leave the sample room and position the following. valves, wide open. These valves are located'en the sample room wall.
.. 1. 939 - sample bomb inlet.
- 2. 941 - sample. bomb outlet.
NOTE: FOR DRILLS AND TRAINING EXERCISES-OPEN VALVES ONLY ONE-QUARTER TURN TO. ELIMINATE N-16 GAMMAS. !
Fully open bomb valves 9B, 9A, 8A & 8B.
.i .
3 .1. 3 ' open the incontainment hot leg sample. isolation valve (valve 955) and the residual heat removal !
sample isolation valve (valve 959) by means of j the switches located outside the sample room. '
)
NOTE: DO NOT OPEN VALVE 959 FOR DRILLS.
If the valve No. 955 will not open because of-(;- containment isolation, perform the following ;
steps (a through c). '
- a. ' Request that the Control Room reset the con-
.tainment isolation signal, t
'b. Turn the local control switch positions for .-
valves 951, 953, and 955 to the "close" 1 position using switches outside sample rooms. -l
- c. Turn the local control switch for valve 955 to the "open" position. l 3.1.4 Request control room to open the hot leg sample. l isolation valve (966C). 1 1
3.1.5 Verify sample flow by an increase in the i
radiation levels around the sample bomb.
3.1.6 Leave the primary auxiliary building.
I 4
k l
.t q I
---_____A
i
.l EPIP 7.3.2 {
o.
Page 8 )
Initials a 3 ' 1. 7 '
After.15 minutes, return to collect'the sample. j Close' valves 9B ar,.d' 9A and then valves 8B and ' j 8A using the remote valve operating tool. Make note of the sample collection time.
b NOTE: .DO NOT DISCONNECT THE SAMPLE BOMB UNTIL SAMPLE FLOW IS SECURED AND THE DI FLUSH !
IS COMPLETE AS. EVIDENCED BY REDUCTION IN RADIATION LEVELS. j m.
3.1.8' Close.the in containment hot leg sample.
~
isolation valve (955) and the RHR sample iso-j lation valve (959),1f~open, using the switches outside the sample room.
- l 3.1.9 Request control room to immediately'close the hot leg sample-isolation valve 966C. :
NOTE: .IT IS VERY IMPORTANT THAT THE HOT LEG-SAMPLE ISOLATION VALVE 966C IS CLOSED PRIOR TO STARTING THE DI FLUSH. WAIT FOR CONFIRMATION FROM-THE CONTROL ROOM.
4.0 SAMPLE LINE FLUSHING
(..
4.1 Leave valve 939 open, and fully open valves.940 and 941.
Open valves 945 and 946. Allow the lines to flush for at least 15 minutes.
NOTE: DO NOT REMAIN IN THE AREA 0F THE SAMPLE STATION
,. DURING THIS FLUSH.
4.2 After about 15 minutes return and measure radiation levels.
If a chemistry or Health Physics Supervisor determines that the levels are satisfactory, close whitey valve 946 and using the remote valve tool, close valve 939. Then open valve 947 and valve 948 and allow about a 15-minute DI flush. ,
i L
1 1
.'.' A ec, . , , ' hy
[',..~ ,
EPIP ' 7. 3'. 2 "
. . y.o; Page.9.
..p v , <
N >
. Initials
' ') , ' 4.3 After about.15 minutes, close valves 940'and 941 with the.
remote valve. tool and then close valves 945,;947, and 948, m Disconnect valve 945'from the demineralized water manifold Land cap both. ends. :. Attach cart tol the sample bomb. ' Dis-connect the sample. bomb;from the. fittings'using a paper-towel tofprevent spraying. Remove'.the. shielded sample
. bomb:from.its' support. REMOVE EXCESS LIQUID FROM THE TOP:
.AND BOTTOM BOMB FITTINGS WITH'A SYRINGE'AND DISPOSE.0F g 'BEHIND. LEAD SHIELDING. . Replace the Swagelok' caps'on the y, wall' fittings andJon the bomb. Transport the. bomb,oremote k.
n t valve-tool and wrenches to.the chemistry lab on a cart.
. NOTE: 'AFTER DRILLS AND TRAINING EXERCISES, RETURN'ALL-
. EQUIPMENT AND VALVE LINEUPS TO NORMAL. (SEE
.SECTION 4.4).
~
' 4.4. Afterbrillsortrainingexercises,enterthesampleroom and. notify control room that the failed fuel monitor.
(RE-109) ic to be returned to service.and that the sample M u room' valving /isLto.be returned to normal.
Dn 4.4.11 Close or verify closed valves:
e ;A;
([$ 11'. 961Cl- Normal hot. leg sample < bomb inlet
- 2. ,964C:- Normal > hot leg sample bomb outlet--
y 1
- 3. 965C - Normal hot' leg. sample bypass-
.' 4 .' 971 - Normal hot' leg sink sample valve
- 5. 938B - Failed fuel; monitor'RE-109' outlet (Unit 2 only)-
- 6. 939'- High level sample bomb inlet
'1
- 7. 940 - High level sample bomb bypass
- 8. 941 - High level sample bomb outlet 'i t
- 9. 945, 946, 947, 948 . Demineralized water flush valves-NOTE: ' ADVISE CONTROL TO REDUCE DEMINERALIZED WATER j HEADER PRESSURE TO NORMAL.
t., /
- 4. a I
q v ;
q- ,
pg- ,
y; , , <
V.. ' .m i,
,j EPIP 7.3.2'
. n. p, r
.Page 10~
,.' \-
Initials
- 4.4.2 Open valves: ,
.1. 938A - Failed fuel monitor'RE-109 inlet
- 2. '938BL- Failed 4 fuel monitor RE-109 outlet (Unit 1 only)-
- 3. 938C ' Failed fuel monitor RE-109 metering (Unit 2 only)-
- 4. 956C - Normal hot leg sample supply valve
- 5. 968 - Normal hot. leg return valve '
- 6. 969A_ Sample system purge to volume control tank 4.4.3 Open the containment isolation valveL(955) using the switch outside the sample room. ,
0
,4.4.4 . . Call controland have.them open' valve'966C, hot leg sample' isolation valve.
,'[ 4.4;5: Establish proper flow through-the failed fuel monitor by: throttling valve 938B for'.
R Unit 1-or 938C for Unit 2. i
, ;5.0I SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASEOUS-
.i
- AND LIQUID COMPONENT- (Refer to Figures 2A and 2B)
]
5.1L Collecting the Gaseous Sample From the Pressurized 1 Sample 4
5.1.1' Place the shielded sample bomb in the sample i holder in the primary sample hood. '
5 .1.' 2 Obtain a. contact reading of the sample. bomb and i note this value on Appendix A (attached) for m possible future reference of pCi content. .l ;
5.1.3. Connect the, sample bomb to the shielded gas l collection bomb by means of the fittings provided. Place' lead bricks in the area of this connection for shielding.
5.1.4 Connect the drain tube to the opposite end of the sample bomb and verify that valve 11 on-the drain tube is open. .)
y m.i. ,
p lQ. ' Q ..
'i l
)
1 4
I 5e
l EPIP 7.3.2 Page 11 'l 1.
Initials-5.1.5: .Make sure that the vacuum line'is attached to
!~
the' gas' collection bomb.at the valve 1 location.
Open valves 1 and 2. Secure valve 3. Evacuate the gas bomb and connecting. lines. .With vacuum' l
-still'on, secure valve 1. Secure vacuum. j 5.1.6- Before proceeding, make'sure no inleakage has occurred into the gas bomb by observing the vacuum gauge reading. Using the remote valve tool, fully open valves 9A and 9B. Open valve 8A one quarter turn. Crack open valve 8B and
. control degassing by throttling valve 8B.
NOTE: OBSERVE THE VACUUM GAUGE. '.THE VACUUM SHOULD DROP VERY SLOWLY. IF THE DROP.
-IS.TOO RAPID, CLOSE VALVE BB SLIGHTLY.
DROP SHOULD BE 5-10" HG/ MIN.
Allow the system to degas for 2-4 minutes.
Check that valves 9A and 9B, 8A and 8B are
] j fully open.' Close valve 2. i 5.2. Analysis of Gaseous Sample s
15.2.1 Hydrogen l P
Use'a syringe to draw a 1 cc sample. Use the ;;
injection port on the gas partitioned for 'j this analysis. j 5.2.2 l Re,dioactive Noble Gas
],
Use a syringe to draw a 1/2 cc sample and inject I this into the flask prepared in Section 1.2.8.* j Allow 15 minutes for thermal mixing. ' Draw a :1 1 cc sample .of this . dilution and proceed as ;{'
normal.
{
- Additional dilution should be performed if the contact reading is >1'mr/ hour.
NOTE: SEE SECTIONS 7.0 AND 8.0.
1 k
.I i
, .j k
i 4
4 l i
.EPIP 7.3.2' Page 12 se
. Jj
' Initials 5.3? . Collecting the Liquid Sample From the Pressurized Sample u
W/' > . NOTE: 'IT IS EXTREMELY IMPORTANT TO VERIFY THAT VALVE:'2 4 HAS'BEEN CLOSED-BEFORE PROCEEDING.- 3 5.3.1 Open. valve 3 sl'owly. Allow the liquid sample
~
to drain'into'the.'50'ml beaker. Direct a' slow stream of air through the vent:line on valve 3
~if necessary to recover the' total-liquid sample.
5.3.2 .Close. valves 8A and 8B, 9A cnd 9B,;and' valve 3.
s, 5.4-. ' Analysis of Liquid Samples -
-5l4.1 . Boron /pH Analysis
.. j 0
1
- a. Transfer a 5 ml sample' using an automatic il
.pipetter into.a 50 ml poly beaker.containing-a stir bar.
Eb. 'After transfer is. complete,? record the pH.
m NOTE: IF NaOH HAS'BEEN INTRODUCED-INTO.THE-
,.{ .
' ~ : REACTOR COOLANT' SYSTEM (VIA CONTAINMENT
. SPRAY),-SAMPLE'pH WILL NEED.TOlBE ADJUSTED TO A.VALUE CORRESPONDING-TO THE EXPECTED'
' BORON CONCENTRATION BEFORE'BEGINNING THE, L
- BORON ANALYSIS.
a 'c. Plug 'in the magnetic. stirrer, add mannitol','-
Land proceed with the boron' analysis'.
' ~
NOTE: IF THE PRIMARY SYSTEM HAS BEEN' BORATED, , .
5 ML OR MORE'0F TITRANT MAY BE NEEDED -l '
'TO' REACH ~AN ENDPOINT.
NOTE: AFTER DRILLS AND PRACTICE RUNS,'THE i BORON TITRATOR MUST BE FLUSHED'WITH 1 DEIONIZED WATER AND PUT IN DRY LAY- -
UP. .ALL ELECTRODES SHOULD BE'PLACED IN LAYUP'SO THEY ARE CONDITIONED'FOR IMMEDIATE USE. ALSO-PURGE ANY WATEk THAT MAY BE KELD'UP=IN THE 280 ML i
> 3: GAS COLLECTION BOMB.
l -
l 0%
i '. ,
ii____________S.____'--_.-_
y _ _ - _ - - - - - - - - - _ - _ - _ - - , . ____
u _
t >
j-
,x s e ly _ 'r !
bf ,
y I) EPIP 7.3.2 .k Page 13. 'l L
5.4.2 . Chloride Analysis Initials
& )
Analyze a: suitable volume of. the remainder ofj '
l the sample using the PBNP ion chromatography "
. analyzer.
- 0. ,
m
'/
i >
NOTE: THE CHLORIDE ANALYSIS MAY NEED TO BE- .s I PERFORMED BY WE LAB SERVICES USING THEIR I: sa 100< CHROMATOGRAPHY' ANALYZER IF THE PBNP. *N
'.Ifa AND/OR EQUIPMENT...IS. NOT AVAILABLE. d KEEP THIS SAMPLE FRACTION IN THE LAB VENT '
~ HOOD UNTIL ANALYSIS HAS'BEEN SATISFAC -
TORILY COMPLETED. CONTACT THE TECHNICAL
. SUPPORT MANAGER TO ARRANGE FOR THE TRANS-PORT-0F THE NECESSARY' PERSONNEL AND .
EQUIPMENT TO PBNP. '
5.4.3 . Iodine Analysis and Gamma Scan
" .{
q Using the specially prepared 2 cc syringe or !
adjustable.' automatic pipet,' withdraw 0.3 cc-(or. :j less) of the sample from the beaker and inject . O li
,' [. , this sample.into a 1000 ml poly bottle.containing-demineralized water. Make additional dilutions.
, j
" J
'in the same manner.*- Count as normal. i. y
- Additional dilution should be' performed until the contact reading'is;<1 mr/ hour.
-l l
NOTE: SEE SECTIONS 7.0 AND 8;0. ,j 5.5 d Reporting of-Results' g ]
- )
~ Complete and forward Reactor Coolant Post-Accident
-Sampling Analysis Report (EPIP-30) to the Chemistry 6 Director, i 6.0 SAMPLE STORAGE After analysis,. store all samples (liquid and gas) in the '
decignated.high level shielded storage area located in'the atmiliary building-area outside of the gas decay tank room.
q l
i I
[~
l 4
n - - - - - - ' '
- -~ - - - - - - ~ ~ - - - ~ -
)
i r,4.;
<(.
7.. , : EPIP.743.2. ;
,Page 14 '
'7.0 SAMPLES TAKEN TO KEWAUNEE' NUCLEAR' PLANT FOR COUNTING
Reference:
Post-accident counting agreement with Wisconsin-Public Service, Kewaunee Nuclear Plant.
Kewaunee Nuclear Plant does not' utilize the 5 ce glass vial and l'cc test-
~
a tube. geometries. . Therefore, " normal": samples .will have to be diluted and
~
placed in one liter. poly bottles if they:are sent to the Kewaunee, Nuclear Plant for analysis.
8.0 LABEL 7.NG OF SAMPLES:
y h
' Lebe$allchloride,noblegas,iodineandgammascansampleswithall pertinent information such as: . sample number, name of sample,'date and is time of sampling, sample volume and dilution (s).
e
+!
(
j:
Q
~ (.:,,_U g
o' 4 N V, < 4 cy '
I i
, i 1
8.!
MA .(g. ' h l.- p gpyp 7.3.2
' th @
ijjD) ay/' .
' page 15.
gj f.
- 6 %' '!
('
h hl Q '[* i ' '
'^ '
.t c -
W$13(
'a%
j '. l O~
i.
ogglAfMggy
'T t! . ' in MSc31
( . . 'A ^ ro 90pfsunop
> v d T" y
4 96 3 Y~fN y!" ry ,, y,,;g g r l# ,
. 4 %m p'"h - M 3, s' .
.w y gg aM-(WFMc &j s ,,,,
.. De w r, t
usc
/ ..
,1
.. i.
47/
wa b g
9 -h M V. 4s
~
}3]C W "
AL t
q' z'
. 1 5'5"}$ --s . .
Y E
i i "43}A
^
-4 '/ h d%
,4 '
i
.or warza num s2 9n s1 9 I4 } {
1P .. -- --
.I *
A k wx e ><N lf i 1
ey6 N
- wtSCONSN EUiCTRC POWER COMPAt#
g Point Beach Nuclear Plant
-, ~
httffMW CNSANY -- - ~ne-1s-es N Mt0M LWit inMP&W6 ~~* ""
[
(' '
F&#W 1340&#d4PD
. 2, .
7, EPIP 7.3.2 5HEET Page 16 .
OF
- , . CALCULATION SHEET 1 FILE No, 4H'// Sk MADE BY DATE R-0'- ,
CHKD.BY DATE Va.cu,am 6 / A ' p'is W Ltwr
>ca
. K = V&
h
~ <fAS COLlfdt?CN BOM8 h2 I
$ , ' tg' ano s, swa ';
} dGMd Vg:. Yf#"%
.(
/A"
~'-- q n youes
- cm L faa h,r C'c g
ENO k ,16' d
'l
' VtEn/
1~0P //t a j.itte s 0/t)
(Qd SAAt fl)
't 00u ad . ggAnt 4 Paid.K css sams*cr n snat4lrpH 3
%e soms + 0 '""o^'
L Gite W a/YUfgjg
\
s .. .. 1 .,
'\'
- 96 4A 86 1.R
/A as 'N4Lt X eo" mig. 0/C)$ % EW ~
h
=
m *G3ad$
8c@s f.a s
g l s:s m
m o.
p4e en k m
L Z I-kc sg M A i,A -.
D f c s
p 1 e s-k
~
3 k h k
~
o a
4 2 q e
I \ b h t g g I -
o e, e 2 o a
$ a- e 1i a ku : :
gg m
7 j,,,.# 778 EPIP 7.3.2
$Hitt OF I CALCULATION $HEET FILE No.
S d. LL L<L~L~ uADE er RIs DATE 'h/u k un ,
CHKD.BY dM8 DATE Nbo
. . . ~ . . .
M I si
% - 1
. . bz,4,
- - - mE
- .u i
. .. . . . . . .. 3 ..
u "r !
.(
c
+- -
{,
7 j g - .
5
/ (
3I ;a
,t - - Q..l j i
.~ t A
i L ve t, ..
N O
e4=== Q" P o
- f f 3
1 F
3 gos - n ,_ - --
r--* e-- p s
, . . . . . . . *CC"' e f l s
^- >. s 7-= .
L D U~ b 3.M *% T==
p en r Ny FDY$,'r p -
g M et q
a.
a
- 9. M g p
~;
pfp 1 3 5 M l
t
( '
F I .C f -:
1
a;'
[$
c- >
- p.
- .g s>
> ll '
EPIP 7.3.3 1
, MINOR j
-Revision 181 ;j 07-08-87 s i
l POST-ACCIDENT. SAMPLING OF~ CONTAINMENT ATMOSPHERE n j 2
1.0?' INTRODUCTION i
-1,1- .This procedureLoutlines'the' steps necessaryLto collect,-handle and.
i analyze.a'potentially.high radioactive containment. atmosphere: sample at ;resulting from/ gross-fuel failure and loss of reactor coolant system
' integrity to determine hydrogen and radioactive gas concentrations.
1.2 . Equipment List' a
'R Set up thelfollowing equipment prior to collection of a sample: ..
L , q. .1 2.1'
. !The gas partitioned forjHy analysis. Ensure- an adequate :
-valveJand carrier gas supply'(if applicable). I 1.2.2 Two 1cc gas tight syringes with lead brick. ,one' syringe' filled.with N ice AgZ for iodine analysis. Have an extra needle for a spare.
.[ (i 1.2.3 Poly bottle-and Sec vial for radioactive gas dilution and counting.
1.2.4 Test tube for iodine' analysis.
E 1.3 i Preliniinary Steps -
l'.3.1 Startup the~ gas chromatograph for hydrogen analysis. Ensure
. calibration.
1.3.2' Place two syringes in lead brick. Use caution when closing-the cover so. that they don't accidentally break. Place spare needle in brick.
n 1.3.3- Have all bottles; vials, test tubes near work area-for easy.
accessibility.
(.:
Y _ _ - . . . - . _ _ . _ _ _ - - - - . - _ _ - - _ _
[ 4.$ ;. ' :
'P
-m EPIP 7.3.3 Page 2-
- /.
2'0 PRELIMINARY EVALUATION
' NOTE:.THE FOLLOWING EVALUATION SHALL BE COMPLETED PRIOR TO ANY: ATTEMPT
.TO ENTER THE FACADE'OR RE-111/RE-212 CUBICLE.TO PERFORM A VALVE' LINEUP OR COLLECT.A CONTAINMENT ATMOSPHERE. SAMPLE.
2.1 Indications ~of Possible Fuel Damage Some,or,all'of the following would be present'if fuel damage'or-loss of' reactor coolant, system integrity had' occurred:
2.1.1 The letdown valve gallery monitor RE-116 would be-unusually.'high or offscale.
^
2.1.2 : 'The containmentLradiation monitorsL1(2)RE-211 and:
1(2)2RE-212 would be unusually high or offscale.
T 2.1.3 The' containment low-range monitors 1(2)RE-102 and
~
seal table monitors,:1(2)RE-107 would be unusually high or offscale...
2.1.4 The automatic actions of EOP-1A'have caused containment'
. isolation. -
o 2.1.5 The failed fuel monitor-1(2) RE-109 may be. unusually high or.offscale..
2.1.6 The auxiliary building vent stack monitor, RE-214 could show a significant increase due to auxiliary building airborne activity from the letdown and charging pump-areas.
2.2 ~ Evaluation'of Rad'iological Hazards in' Access Areas-Required for Sampling Initials 2.2.1 After evaluation of the radiation monitoring
-system readouts, verify'with Health Physics that the appropriate airborne and-radiation surveys have been made before entering-the facade.
4 2
. _ _ _ _ _ . ,__i_____._--_-_.------" - - " - --
lb _
EPIP 7.3.3 Page 3-Initials 2.2.2 : Verify the.. requirements for facade-and-1(2)RE-211/1(2)RE-212 cubicle. entry.
- a. Radiation work permit requirements
'b. Clothing requirements
- c. Respiratory requirements
- d. . Dosimetry requirements-including extremity; dose monitoring _
- e. Health physics' coverage requirements
- including ' timekeeping.
2.3 Evaluation of Containment Pressure containment pressure must be less than 5 psig in. order- .
.to initiate sampling.
.R 2.4 Instrument air is necessary to open th:. sample isolation
.., values for the 1(2)RE-211/212 cubicle.
3.0 MISCELLANEOUS CONSIDERATIONS
'Take_along a flashlight in case area lights are not
-working and a-portable FM radio.
.4.0 CONTAINMENT ATMOSPHERE SAMPLING PROCEDURE NOTE: 'THE FOLLOWING PROCEDURE SHALL NOT BE INITIATED-UNTIL-THE
-EVALUATION DISCUSSED IN SECTION 2.0 HAS BEEN COMPLETED.
THE DUTY & CALL' SUPERINTENDENT (PLANT OPERATION MANAGER),
THE DUTY & CALL HEALTH PHYSICS SUPERVISOR (HEALTH PHYSICS
. DIRECTOR) AND THE DUTY SHIFT SUPERINTENDENT SHALL APPROVE
~
.THE IMPLEMENTATION 0F THIS PROCEDURE. THE FOLLOWING STEPS
'WILL.BE ACCOMPLISHED UNDER THE DIRECTION OF CHEMISTRY SUPERVISION.
'{
(', t: ,
o
< 'i ,
l ,
EPIP 7.3.3 7.: y ,
Page 4 WlJ
.g Initials 4.1' Containment Atmosphere' Sampling Using the l('2)RE-211/
h
- 1(2)RE-212 Sampling System, After Containment Isolation-
_l :4.1.1 Service-Air Setupi L' ..
- d. .. Proceed to the potable' water room to. sample
' Unit 1' containment'or'to Unit 2 nonnuclear
[ room to sample Unit 2 containment.
- b. Enter the: facade outside the-L1(2)RE-211/1(2)RE-212 cubicle
- c. Connectjthe: service air regulator /
-tailpiece section-to.the quick
. disconnect fitting attached.to valve
[,_ ~
-1(2)3200Y.' Verify that--valve-1(2)-3200Y is closed.
d' Open the service air supply Whitey valve
. (upstream of regulator).and, verify service-H. . air pressure'on the regulator inlet gauge.
k NOTE: IE NO PRESSURE, VERIFY THAT THE SERVICE' AIR GATE. VALVE ON THE EL. 66' FACADE IS OPEN
- e. Adjust the regulator to 4 psig static head outlet presssure.
NOTE: IF PRESSURE GOES ABOVE 4.5 PSIG, BACK OFF THE REGULATOR,. BLEED OFF AIR AT THE DOWNSTREAM QUICK DISCONNECT AND TRf AGAIN
' 4.1. 2 - Valve Line-Up NOTE: FOR' INTERIM SETUP P707A-HAS NO AUTO
-SECURING. IF CONTAINMENT ISOLATION o
HAS OCCURRED, FUSES FOR P707A MAY HAVE BLOWN. -FUSES ARE LOCATED IN-
'THE DAM IN THE ROD DRIVE ROOM.
'\ .'
.f r
.~
..p . . .. .
- f' 1
]
q.9 '
.EPIP 7.3.3 Page 5 g Initials #
Ta. Secure sample pamp,-P707X,= locally at iY ' pallet.
1 b .- Verify with.'het control' room that the t following conditions exist:
.I cc , (1) . Valves 3200A, B & C have closed. 'i (2) Vent control switch is in off and.
pullout (P707B secured).
~
, .(3) . Mode.~ select switch is in. septum
~
4 l position. The switch will accomplish theifollowing valve line-up: '(3200E&F. closed, 3200D.open,=
3200G aligned to' containment,~.3200Ml aligned to septum).
NOTE: THE SWITCHES ARE. LOCATED ON THE i
' APPROPRIATE: UNIT'S ASIP, PANEL. i q
- . , . , c. Enter the cubicle and. perform the_ !
L( following:
-(1) Verify 1(2)A0V-3200A&B.are closed.
L by visual observation.
(2) Verify 1(2)3200Z;is,-open.
(3) Manually close valves 1(2)3200N, P, Q, W and 1(2)3200EE &'FF.
1 (4) Manually open Whitey-valves '
1(2)3200J,& L.
- o. d .~ Request the control room perform the _l P following:
NOTE: THE SAMPLE PUMP P707A SEALS ARE RATED-FOR 5 PSIG. TO PREVENT AN INADVERTENT AIRBORNE RELEASE,
?THE CONTAINMENT PRESSURE MUST
'BE LESS THAN 5 PSIG BEFOP.E PRO-CEEDING.
i
W. ' if' ', h ,
. . .v .
4 EPIP 7.3.3 Page 6 !
9 ,
If Initials i 1
'(1) . Verify containment pressure is less o , than'5 psig.
(2) Open A0V's-1(2)3200A, B & C-(contain_ '
ment: isolation valves).
- e. Start sample pump P707A. locally at'the pallet.
- f. Verify' sample' flow by. observing a' flow
-increase on FIT-3288 and' return to the potable water /nonnuclear room. ;
1
.g. Allow 15' minutes for. sample recirculation and. return to.the cubicle with two-(2) 2 ce gas-tight syringes in a hollowed-out lead brick. One syringe should have 1 cc of AgZ.inside the syringe barrel.
1 .k.. 4.1.3 Sample Collection
( a. Obtain two 1 cc gas samples from the sample septum by means of the gas-tight yringes. '
Withdraw the syringe' plunger only once. Do not purge the syringe as the AgZ will retain
.l the iodine from each withdrawal.
" NOTE: -LOCK THE' SYRINGE PLUNGERS PRIOR TO' .
WITHDRAWING FROM THE SEPTUM. j
- b. Place the syringes in the lead bricks for transport.
CAUTION: CLOSE LEAD BRICK COVER SLOWLY TO AVOID BREAKING SYRINGES. j
- c. Note the prepurge radiation levels:in'the
-cubicle.
- d. Verify a service' air pressure of <5 psig on the regulator discharge and open (
valve 1(2)3200Y.
l l
)
u: .i
m,
- -.j ' , r .I
- l
, EPIP 7.3.3 Page 7-
,J .
r- l
Initials j 4 '.' 1. 4 " Sample Line'Purce j P
La. Return to'the potable water /nonnuclear room and requestuthe. control room close valves ] "
l1(2)3200B&C.
- b. Allow the. system.to purge forward for- ?
y 115 minutes. L
- 1 c.t c.: Secure the sample pump P707A' locally .l l' fron the. pallet, then-request the control-
~
'd L rooln-perform the -following:
(1) ' Place. mode select switch to containment position'and shut 1(2)A0V-3200A.
(2) Open 1(2)A0V-3200B&C.
)
ty 7 d. Allou the system'to' purge backwards 15
]
4, minutes and request the control room close o l valves 1(2)3200B&C.
iL e. Return to the cubicle and perform the
'following: ,
.(1). Verify the effectiveness of the purge by: measuring the reduction of the radiation levels.
(2) Close the service air _ Whitey. valve.
Close valve 1(2)3200Y and disconnect .;
the service air line quick disconnect '
at valve- 1(2)3200Y.
(3) Enter the cubicle and close Whitey valves 1(2)3200J & L.
(- ;
M_ ._:2_-______. --. . _ . . _. . _ -
., r f ,.
7 _
f ijj,,_
EPIP-7'.3.3' 1 r g '
Page 8 I
s
,., 6I
' Initials i
Notify-the_ control room _.that sampling.
E. f.
LE; .has been completed, and-that valves t
'Y
'1(2)-3200W and 1(2)-3200.EE & FF are closed.
y
- )
. NOTE: AFTER ALL' DRILLS AND_ PRACTICE-EXERCISES,.ALL EQUIPMENT AND .. ;]
VALVE LINEUPS ARE TO BE RETURNED-TO THE AS-FOUND' CONDITION. -ASK THE j.
CONTROL ROOH TO HAVE AN OPERATOR i y VERIFY /REALLIGN THE VALVES WITHIN l
@ :THE 1(2)RE-211/212 CUBICLE.
5.0 ' CONTAINMENT ATMOSPHERE ANALYSIS l 5.1 Volume Adjustments y, a.
. 5.1.1 ,Before proceeding with the. hydrogen, radioactive inoble gas.and radioactive iodine' analyses; the. i sample contentsLof both syringes.must.be brought 1
- toLatmospheric. pressure. . Use.the shielded sacri- J c 'ficial glass bomb-for.this purpose if an operat-k;<. ing vent hood'is not available.
5.1.2 Insert the syringe through the. rubber' septum of .
i
.the' glass bomb _or place' deep'inside'the' vent' hood.
Unlock the syringe locking device and let.the- j
- syringe 'and bomb equilibrate _ for_ approximately 1
.30 seconds. Relock the syringe and withdraw. d Store the syringe in the lead brick. -i 1
5 .1 '. 3 Repeat _ Step'5.1.2 for the other syringe.
.]
'1 5.2- -Hydrocen !
1 E Assuming normal equipment setup'and preparations are
- complete,:use.the sample injection port on'the gas .
'. . partitioned,-inject a 1 cc-gas-sample'from the syringe
. without the AgZ, and proceed using normal. hydrogen analysis procedures.
5.3 - Radioactive Noble Gases &-Iodines it Noble Gases 5.3.1 Use the'2 cc syringe with the 1 cc of AgZ for the noble gas and iodine separation / analysis.
can__1___u___ _______ _ _
N ]_$ _
4w: ,
EPIP 7.3.3
,m
- m. w; Page 9 5.3.2 Inject.theil ce? containment. atmosphere sample into' a one liter poly bottle. Purge the syringe once cri twi'ce while in the~ poly. bottle in order to recover'all of.the. noble gases., Remove the-
- y~- syringe and' store in the lead brick. .Tapti over the syringe hole.in the poly bottle. Let the -
,, gas come: toLequilibrium for a minimum of 15 .
minutes.while proceeding with the iodine analy =
sis section.
'5.3!3 Withdraw'a 1.cc gas.sr.mple from the poly; bottle in, Step 5.'3.2. If,the contact reading on the
'i syringeLis;less1than 1 mR/hr,-inject.thecsample-into~a'5 ce vial and count as normal. If.the
' con _ tact reading-is greater'than 1 mR/hr, further
~
E ,
dilutionsLare necessary.
Dilution. procedure: Inject 1the.1 cc' sample,into a one liter poly bottle and allow to equilibrate. ,
, Withdraw ILcc frem'the poly; bottle. 'If the' con-tact reading is less than.one mR/hr, inject'into j' o a 5 cc vial and-count as normal. .Iftthe contact' n reading is greater than 1 mR/hr, dilute further.
NOTE: 'FOR EACH DILUTION, USE A NEW SYRINGE OR MAKE CERTAIN THE OLD SYRINGE IS COMPLETEL '
. PURGED. LABEL NOBLE GAS ~ SAMPLES AND IODINE
' SAMPLES.WITH ALL PERTINENT INFORMATION SUCH AS: SAMPLE NUMBER, NAME OF SAMPLE, DATE AND TIME OF SAMPLE, SAMPI.E VOLUME AND
' DILUTION (S).
Iodines i 5.3.4 . Unscrew the syringe top and remove-the internal plunger.
PourJthe silver zeolite into a counting test tube and cap.
L5.3.5- If the silver 1 zeolite / iodine sample is less than one mR/hr contact, count the sample directly on the MCA
- using'the test tube geometry.
)
e 1
l r 1
EPIP 7.3.3 Page 10 5.3.6 If the iodine activity is too high to count directly, -
=
determine the radiation level in mR/hr at one foot. .
Also, determine.the percent isotopic composition using the MCA and attenuating the sample if necessary. +
~~~
Determine the total iodine activity using the following '
equation; R/hr @ l' C(CI) = 6E T
The following table can be used as an aid in determining __
the " Total Gamma Energy / Disintegration" T(E ) f r the .,
above equation. - -
. (1) (2) (1) x (2)
Total y % Composition Weighted y Isotope Energy / Dis (Fraction) Energy I-130 2.130 I-131 0.380 -
I-132 2.260
. I-133 0.608 k I-134 2.600 I-135 1.560 Total Weighted y Energy: (ET )
Each individual iodine isotopic concentration (pci/cc) is calculated as folis:>s:
pCi/cc I g) = C(Ci) x 1 x 10+6 x (Fractional % Composition) 4 l
I..
/
EPIP 7.3.3 Page 11 6.0 CALCULATIONS Initials 6.1 Pressure & Temperature Correction Ask control room supervision for the temperature and pressure in containment (psig and *F). Determine atmos-heric pressure (mm Hg) and temperature (*F) from the barometer in the laboratory. Convert this to psia.
Apply the following correction factor to all results:
Concentration (pci/cc) x (Pc + 14.7) x ( lab + 459)
Pg (T + 459).
P (mm Hg)
P ye3 (p,g,) = 14.7 psi x 760 mm Hg.
Pc = containment pressure, psig l
Tc = containment temperature, *F 6.2 Complete and forward Containment Atmospheric Post-Accident
~
Sampling Analysis Report (EPIP-31). ,
7.0 Sample Storage After analysis, store all samples (AgZ and gases) in the designated high-level shielded storage area located in the auxiliary building outside of the gas decay tank room.
f
3 h.
. L,32 E x
e
- s. e ,
~ ' g r
, Y
'a ,
, L
~
E
, N p gS N .
2 mu p .r T
O 12P O 2 N
~ T C. O O V0 0
I 4
3 A
/
1 1
e L 2 3 b I T
C2G 7 0
2 lp A
. 3 7 Em M P RaS R
O s S
$7* F
, O V0
}
0 L r3 2 N I
< C R 0 J 3
._ 4 3 a O w_ l E'g cE F l
N
~_
g n
@ i 8
r O
ip n 'n,.
t n
T8 2 0 O
2 l e 3 P 3 p U' 0
, m 0M .
2P
._ i n 2ma e
,t a @3 2 I#
D.
N J e r
.tl 3 I 5
Sin MFi n I
]
o [ LF S0
& < C 1y P4 L s.
p 3 L e m re ~. u P'
dev ~
G0 3 t n B nhl a spVo a V4 V e 7 r[OP
~ 3 0
_ 1 d 7
/o . Y L O c e
O l O 4 m2 t -
r O < O 0 3 o :
F it/ Ai > 2m 1 hD
_ 2 F4 -
U nA2 -
L.
~
~
e ic 3
3u t p
e 3
H l
0
" 8 tEn v
r S N eR ,
S e
s[-
~
p e
%' MI )E M0N 2 3 O O
I n/ m/
a 1
2 f u 3
=.
ei
- JS ra/2 ut gn ~
X2 O
O
)E 1 I
{
T8 9
i o E- 3 9 R1 I 2 F
FCR
. 2 3 4
_ . =
- E.
_ . N
-. 5 R VO
. - C
~
hC D. . D. C
? IO O 2 N E N I2 3 3 (E u"'") y 9 l
~-
[
C20F 0
3
) C 32 0
0
- f l
_ d-l ,
F
.. F E o8E l m - x8g e O O
E
_ < d
_ o 2 k O c 3 c s.
[l
,lI F
o l
o t
S Il MO 2 3
l:
l
, Q S
EPIP 10.1-MINOR.
4.;. , Revision 3 t
07-08-87 i L <
, FIRE FIGHTING g
' 1.0 GENERAL '
The purpose of this procedure'is to (1) establish the location.of.the'
-implementing ~ procedures for fire. fighting; (2) provide the' general content ]
-of'those' procedures; and (3). direct the. issue.of dosimetry to offsite firefighters.
1 l
2.0 REFERENCES
' Fire Protection Manual- '
-3.0 PROCEDURE. L 3.1' ' Location j(
.1 I: The implementing procedures for ' fire fighting 'are found in '
x "
the Point' Beach Nuclear Plant " Fire Protection Manual". A
- " controlled" copy of this document is kept in the control room.
3.2 Content'- Fire Protection Manual This document'contains procedures for fighting fires in.both. '
the. controlled area and the clean area,. brigade training requirements,-Jpersonnel. call.' lists,-and interfacing with q.
other organizations' .
3.3 Issue of Dosimetry for Offsite Firefighters
.Firefighters will be provided with personal radiation monitoring devices whenever contamination is involved or whenever such per-- j sonnel.are required on. site or within any evacuated area. 1
. 3.3.1- Acce'ss Levels- ,
J
.There' are two levels of access- that may be required-by
.offsite firefighting personnel:
4 i
I l
l
h '
j.
f EP2P 10.1 Page 2 7
- a. Nonradiological area access
.i' Access to the protected areas of Point Beach Nuclear l Plant
- b. Radiological Area Access Access to the radiological controlled zone or other radiological controlled area'within the plant site.
3.3.2 Control room When the determination is-made that offsite firefighters will need access'to the plant site, the control room should:
- t
- a. ' Determine if the fire is within a radiological or non- i radiological controlled area. '
r
- b. . Notify'the'southgate security officers that offsite firefighters will or will not require access to a ,
radiological controlled area.
- c. --
If radiological controlled area access is required, i
}- notify the health physics station or on-shift qualified health physics personnel of the fire's location and that firefighters will be entering a radiological controlled area. 3
]
3.3.3 Southgate security officers Upon being notified that firefighters will be arriving, the southgate security officers will:
-g
- a. Obtain the preassembled and numbered fire fighting team packet, consisting of a TLD, 0-500 mR dosimeter and a 0-5 R dosimeter. 3 I
- b. Rezero each dosimeter,
- c. Upon arrival of the vehicle at the southgate, issue one dosimetry packet to each fire fighting team member.
Retain the card and record the team member's last name.
om,
[ _ _ _ _ _ _ . . - - - - - - - - - - - -- - - - - -
y :-c :
I '.
p ,
-EPIP 10.1-Page 3- ..,
q
' il T
- d. 'Upon' departure of the vehicle!from the site, the dosi-metry packets should be collected from.the team members.
- e. As: time permits, after departure'of.the vehicle, security will obtain the.necessary information and-
)
complete. CHP-33c, " Dosimeter and Spare TLD Assignment oc : Sheet," for each team member entering the plant site.
[ 4.0 RECORDS-
' Records.of-fire training and. drills as well as' records for. fire equipment testing are maintained by the fire protection and safety coordinator'(FPSC),
i n
?
.i j
+
t
,.} ,
\,
__ i__._._.i___.-____-=--_----- -- -
e f , ,
-c- i NAMES AND PLANT PERSONNEL EMERGENCY CALL LIST
DELETED
- 1. : . Duty & Call' Superintendents (Pager Group No. 501)
Name . Pacer No. Plant Ext. .Home Phone Time Notified
- 2. ' Shift Superintendents Name- Plant Ext. Home Phone Time Notified' i
i ]
i I
)
l l
1
'[.
- s. !
a EPIP-22 '
(07-87) Page 1 of 4 l
- w. l
i 1
.a l
d 1
- 3. . Chemistry' (Pager Group Nos.' 540 & 530)
'Name Pager No. Plant Ext. 'Home Phone Time Notified-i 5
l
.t l
?
I 1
- 4. liealth' Physics'.(Pager Group Nos. ) .
'l Name. Pager No. Plant Ext. Home Phone Time Notified
'i ,
1 i
l l
5., Instrumentation & Control (Pager Group Nos. )
Name .Pager No. Plant Ext. Home Phone ' Time Notified i
~
'\[
EPIP-22: ;
(07-87) Page 2 of 4 1
i W 'g 1
- 6. ; Maintenance(Pager Group'No. )-
Name>. ,
. Pacer No. Plant: Ext. Home Phbne Time Notified-I l
u.
c
_( :,.
- 7. Reactor Engineering.
Name Plant Ext. Home Phone Time Notified ]
i i
8, . Plant Administration & Security 1
'Name. ']
Pacer'No. Plant Ext. Home Phone Time Notified ~ d
(
i
< ,a f
l i
N ;i .
M.
ll EPIP '
..(07-87 ) Page 3 of 4 i
-z_2_-_________-_____-__._____
i e .[',
T lf- -4 I
.)
' , I 9.. Emergency Planning i l
l O Name. Pacer No- . Plant Ext. 'Home Phone Time Notified -
i l
q 1
,1
.3
')
P 9. L10. . Duty Technical Advisors- (Group Nos.'510, 520, & 530) , ;
- s Name- ~ Pager No. Group No. Plant Ext. Home Phone Time Notified i
r .
-! 1
-i
.j 7 :l
-j :.
i
, o I
l
.l
- - Public Service Building, Milwaukee
- Page through system' control,'Pewaukee
- 11 '; Fire Brigade Members-NOTE: REFER TO PBNP FIRE PROTECTION MANUAL CALL LIST,
'SECTION FEP 2.0. -
-i
-EPIP-22
-_'(07-87) Page 4 of 4 i
^
l
- _ _ = _ - - _ - _ _ - - _ - - - - _ ._- -- - - _ _ - - - - - -- - 1
g .
= - - -
/Vi
? '
' NAMES LAND
/ -f ,
TELEPHONE NUMBERS:
.OFFSITE AGENCY' EMERGENCY CALL LIST.
M FEDERAL AGENCIES:
- 1. . United' States' Nuclear Regulatory Commission
, Telephone'. Person. . Time pjh
' .Name1 . Frequency , Number Notified . Notified:
' Initials
.7
'NRC. Operations:
.All hours' Red Phone
' Center.
NRC' Office: Of- All hours Inspection;and (Ask for Enforcement,: Duty. Officer)
Region'III: '
.NRC Project Manager,,
'NRC Resident Inspectors: Pacer Plant Ext. ;Home s
- i _. , .
1
- 2. . United. States' Department of Energy.
Telephone- Person Time Name. Frequency: Numbel' Notified. ' Notified Initials Chicago Operations- Weekdays'. 1-312/972-4800
. r. , Center,-LRegion V- '(8AM-5PM)
(Radiological . ..
Assistance Team)s All other. 1-312/972-5731 -i
'3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />'
-3;- United States Coast Guard
. Telephone Person Time.
IName Frequency Number Notified Notified . Initials
'MS0;. Milwaukee Day . 1-291-3788 Night .1-291-3165 1
-USCG, Sturgeon All-hours 1-743-3366 .j
-Bay.
USCG, Two' All hours 793-1304 1 Rivers
- (-. .
A i f
EPIP-23 Page 1 of 5.
-(07-87) 1 1
_ _ - _ _ = _ _ _ _ _ _ _ _ _ - - - _ _
ry
, MT '
s n.'
)
- ' i4$ United States National Weather Service i'
. Telephone. Person . Time
- p. Name' '!
Frequency- Number ' Notified Notified' ' Initials NWS,. Green; Bay' All, hours .NAWAS. '
1-494-7478, 1
{
1-433-3876'.
STATE OF WISCONSIN-AGENCId3 Telephone Person: Time .. .
- Namei
[ -. Frecuency- Number Notified- : Notified Initials
'. Wisconsin Dept. of Weekdays. 1-608/273-5180 __
' Health-and Social- .(9AM-5PM)
Services,;Seetion-of Radiation Pro-tection N?
.. -Wisconsin' Division All hours 1-608/266-3232'
'of Emergency: or NAWAS
- W.. Government
~. Wisconsin State All hours 1-608/266-3212
' Patrol - Madison or NAWAS h
?
Wisconsin State - All. hours 1-929-3700 Patrol ' Fond du. Lac- _ !
' Wisconsin National (8AM-4PM) 794-7521. 1 i
= Guard-- Two Rivers Armory I
.t t
I
, p.
- n. , ?
- EPIP-23 Page 2 of 5
'(07-87). <
i
, 7 .
, .\
', l F :. i 7 ? '
s
.j 0?-
.\'.
~
l l
.,. ICOUNTY! AGENCIES:
1 ~, - 'Manitowoc-County n ;- . a-
- .. ? Telephone LPerson. Time-Name? Frequency- Number Notified. Notified- ' Initials
, Mand.tovoc. County 'All hours 688-911 1 Sheriff 683-4200 .i or-NAWAS:
or radio'~
r Manitowoc County LFollowing 683-4208 n
(
Activation-
~
EOC- -or
+ - 683-4210.
'. 2 . !Kewaunee County 1 i
. Telephone Person Time'
'Name Frequency Number: Notified- Notified Initials <
- Kewaunee County All. Hours .1-388-3100- '
, : Dispatcher -or NAWAS q
C' Kewaunee-County .
Following .
.EOC Activation .'l-487-5257' j(?
. \(' '0FF-SITE' AGENCIES' SUPPORTING JPIC ACTIVATION.
-q Telephone . Person' Time. .i
- Name-Frequency Number Notified lNotifiedL . Initials.
i Phone' Service at Community House All Hours. 1-800/362-7385 All Hours 1-800/428-6115 Superintendent of- -Office 388-3230' Schools , Kewaunee
'l City of Two Rivers. All-Hours 911
, . Police Dept All Hours 793-5511 __
c . 1
- b~ .
1 EPIP Page 3 of 5
.(07-87)'
1 +
3i
4 & '
fl j
,,, .4 i
.)
- r. PRIVATE AGENCIES N :
.. . Telephone Person . Time'
- Name- Notified-p7 Frequency. ~ Number Notified Initials. ._
1 l
.Kewaunee Nuclear 'All hours "793-2229 R -Power Plant-
/,
'. EOF. . ;
~, 'After. .
Activation ~cDial Select 23 '
gj i
TSC' After.
' Ti Activation. Dial Select 33 '
l
.Instituteiof- i
.g All hours.' 404/953-0904 M' *:e tNuclear Poweri 1-404/953-3600
'~ Operations:
m .American Nuclear' i
- Insurers'. , 'All h'ours ;l-203/677-7305-i westinghouse 1
-Electric" Corp.
Office
~ Site-> Services Rep. ' '
o -
Home_
.i
' Area Hanager. Office.
Home.
. _ _1st" Alternate. : office Home
$ '2nd: Alternate Office 1.h. Home.
Stone'& Webster office Engineering Corp.
~ , .. 'i
.'Bechtel Power i Corporation Office-
- Home. '!
Office ,
Home University of office '
Wisconsin-i- <
Hilwaukee' JSeismic Center-Office.
Home Office Office. _
I 4
Wisconsin Public Service Corp.
(EOF Power) 4 k
'EPIP-23: Page 4 of 5
- l
- (07-87 ):-
I m_._______.____ c_______ _m- --- -
. q' .
6(,
. FIRE AND' MEDICAL' AGENCIES-
'l'. Fire Emergency
'1 Telephone
. Person Time
..Name Frequency Number Notified Notified
- s. . Initials Two Creeks Fire.- All hours 688-911 Department _
~
- 2L Medical ~ Assistance
-Telephone Person Time.
'Name Frequency ' Nurnber ' Notified Notified Initials cEmergency All hours 688-911 or Vehicle 683-4200 Ambulance-Community Hos- All hours 793-1178 pital':Two ,~ Rivers-Doctors Clinic,-Ltd, 793 1281 University Hos-pital,'Hadison
, , , (. .
Emergency Room .
All hours 1-608/262-2398 1
"w._
.EPIP-23 Page 5 of 5
-. (07-87 )
i e t
^] ,
] ,
' NAMES: AND
- TELEPHONE. NUMBERS-f p"" ;
DELETED y
J '
POINT BEACH NUCLEAR: PLANT EMERGENCY RESPONSE FACILITY TELEPHONE DIRECTORY' q
Extension Phone 1 Technical' support Center Site Manager Plant operations' Manager.: ,
h - Health Physics Supervisor & Chemists Gre Physics Coordinator:
E Systems Ana'l'ysis & Procedural'
!~ . Support Coordinator-Offsite Communicator:-
a'
- Operations Support Center M A( '
Health' Physics counting Area Emeroeucy Operation' Facility i
Emergency Support Manager
- Offsite Communicator Rad / Con Waste Manager
- kadiation Dose-Projection
. Telecopier
~ Offsite Communicator SJ;e Boundary Control Centet L.. , ,< ,..
.-( Offsite Health Physics Director
-g r e :.EPIP-24; Page 1 of 2 s(07-87).
- ^
~
{ Q
.....a.,. M r.ll ..
.l
p.
U74 4
!ffv .
, ! Joint Public Information Center T-I, ,
~
m 1
' JPIC - Director.:-
- 7. .. + ,
Corporate Emergency Center Emergency Direhtor-
)
, nt
, ; Alternate Emergency Operations' Facility-(Two Rivers) U
. Emergency Support. Manager Rad-Con / Waste. Manager-
'Offsite' Communicator JPIC Communicator
...(-~
',Telecopier. ' ~'
~
7 ,
Modem:
NRC Office t
d
- a. .l o
h!T 1
i t
. ?' ' i
.- t . :
y
-Ac.
- EPIP-24 Page.2 of 2 .l
- (07-87).; j s
l
./4 I J4. u., ,
j m__s _. .-
-- - - J
POINT BEACH NUCLEAR PLAE
-NAMES AND WISCONSIN ELECTRIC ' TELEPHONE NUMBERS HEADQUARTERS SUPPORT PERSONNEL DELETED
/, . EMERGENCY CALL LIST
' NOTE: ALL TELEPHONE NUMBERS WITH A 221 PREFIX MAY BE DIALED FROM POINT BEACH ON THE' PBX SYSTEM WITH AN "8" FOLLOWED BY THE LAST 4 DIGITS OF THE NUMBER.
(E.G., WE SWITCHBOARD 8-2345) l NOTE: ALL TELEPHONE NUMBERS ARE.IN THE "4I4" AREA,,UNLESS OTHERWISE INDICATED.
- 1. : NUCLEAR POWER DEPARTMENT Time
'Name Pager No. Company Ext. Home Phone Notified.
- t. i
.f-t l
]
.g
\;. ;
'EPIP-25 Page 1 of 3 l
(07-87)-
i.
1
i
( ? '-
E
,, ' 1,7 NUCLEAR POWER DEPARTMENT'(Cont'd.)
7- :
Time
. Nr.me , Company Ext. Home Pt.one Notified I
1 g-.
fi q
l l
'. 2 . COMMUNICATIONS DEPARTMENT NOTIFICATION (A)_ 0700 - 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> ~ Monday - Friday '(Media Line)
- .( B) After Hours Listing
Call the following list of Communications Department Personnel, in order, until one~is reached:
~.r .Home' Business Phone Home Personal Phone
{
.i f
J
- 3. COMPANY ADMINISTRATION & DEPARTMENTS- l 2
Time !
Name Company Ext. Homs Phone Notified -!
i, i
.I
.. l l
l- 1 N.l.
EPIP Page.2 of 3
'(07-87).
__ _ _ -1
,y.- - --- -
7_, ,,_
w..
\* t ; !
- - - '}'-
L
, sq /
. _{--_- , ,
4 z #u ,, I. '
i
,,> , ., 3
~j 4 4
.y. ,
\ o
. 3,4 a, ... v 4,: - OTHE_RS -
. Time:
',...f, Name: Company Ext. ^ H_ome Phone- Notified:
o y y
J.'- , /
, i'r n..
m
- (m b':
I' r
e h [,-
-t; I
.t .,
.'lI g _d s ,. 3 I
k 3
+
+
l --
t ,
f .
g 1
.~
';%[ .
- EPIP-251 ' Page 3 of 3 f
'(07-87) ,
i
, k ,
I :
.i
'i
- c. .
n"q z 1._' ' ! ' _ _..._.m_ _ . _ . _
i EPIP APPENDIX A NNSR Revision 0 07-08-87 EMERGENCY PLAN - ABBREVIATIONS AND ACRONTMS i
ABVNT ~ Auxiliary Building Vent AC l) Alternating Current 2) Air Conditioning ;
ADC Analog to Digital Converter I AEOF Alternate Emergency Operations Facility AgZ Silver Zeolite AHU Air Handling Unit ALARA As Low As Reasonably Achievable AMS Air.Honitoring System ANP.LYR Analyzer A0T Auxiliary Operator Trainee A0V Air Operated Valve ASIP Auxiliary Safeguards Instrumentation Panel AT&T American Telephont.& Telegraph A&E Architect / Engineer I
BAST Boric Acid Storage Tank i CAE Combined Air Ejector 1
' CAS Central Alarm Station <
CB0 Contained Breathing oxygen CC Cursor. Channel' CCWHX {
. Component Cooling Water Heat Exchanger CFM Cubic Feet per Minute i CFR Code of Federal Regulations CHP Chemistry and Health Physics ,
CM Common Multiplier CC4G AE Combined Air Ejector (or CAE) f I
cpm Counts Per Minute !
'CPR Cardiopulmonary Resuscitation CRT Cathode Ray Tube CT Co.7puter Terminal CTH County Trunk Highway CVCS Chemical Volume & Control System CW Circulating' Water DA Digital to Analog DAM Data Acquisition Module DAVNT Drumming Area Vent Stack i DBA Design Basis Accident DC 1) Dose Commitment 2) Direct Current DCS- Duty & Call Superintendent DEG Division of Emergency Government DHSS Department of Health & Social Services DA. De-ionized; Demineralized DNB Departure froin Nucleate Boiling DNBR Departure from Nucleate Boiling Ratio
1 1
EPIP APPENDIX A Page 2 i
DOE Department of Energy DOH Division of Health DPM Disintegrations Per Minute h DSS Duty St.ift Superintendent i DTA Duty Technical Advisor I EAL Emergency Action Level EBS Emergency Broadcast System ;
ECCS Emergency Core Cooling System
{
EDG Emergency Diesel Generator l EIC Energy Information Center ENS Emergency Notification System (Red Phone)
EOC Emergency. Operations Center EOF Emergency Operations Facility ;
EOP Emergency Operating Procedure '
EP Emergency Plan EPIP Emergsney Plan Implementation Procedure j EPMP Emergency Plan Maintenance Procedure EPP Emergency Preparedness Program EPZ Emergency Plt.nning Zone EQRS Engineering, Quality, & Regulatory Services ERD Estimated Release Duration ERD Energency Response Plan ESIV Estimated Safety Injection Volume i ESM Emergency Support Manager (
FCC Federal Communications Commission FEMA Federal Emergency Management Agency FI Flow Indicator FM Frequency Modulation FSAR Final Safety Analysis Report FX Foreign Exchange (RE: Telephone Circuitry) ;
i GC Gas Chromatograph j
GM Geiger Mueller "
gpm Gallons Per Minute GSBVNT Gas Stripper Building Vent GTE General Telephone and Electronics Health Physics i
HP j HPCAL Health Physics Calibration Procedure i HPIP Health Physics Implementation Procedure HPN Health Physics Network HVAC Heating Ventilation and Air Conditioning IBM-PC International Business Machines Personal Computer j ID Identification INPO Institute for Nuclear Power Operations I&C Instrumentation & Control )
I/O Input / Output l l
2
Fo i
V, !
i jl -
EPIP APPENDIX A.
Page 3 1-JPIC Joint Public Information Center KNPP Kewaunee Nuclear Power Plant kV Kilivolt LCD- Liquid Crystal Diode
.LCO Limiting Condition for Operation
.LI Level Indicator LIN Lc;ation Identification Number I
LLD Lower Limit of Detection !
LOCA LPZ-Loss of Coolant Accident
' Low Population Zone j '
MA Mega Amps .
l MAD -Emergency Meteorology And Dose Assessment Program MASP Modified Amended Security Plas Multi-Channel Analyzer HCA _
MPBB' Maximum Permissible ' Body Burden l MPC Maximum Permissible Concentration '!.
' MPH Mile Per Hour i
' mR - Milli-Roentgen j MSA Mine Safety Appliance i
MSR . Moisture-Separator. Reheater j iMW- Megawattt 1 1
NAWAS National Warning System '
-NFAR: Nuclear First' Aid Room !
t NGSD- LNoble Gas Skin Dcse-1 NLR No: License Required-NNSR 'Non-Nuclear Safety Related i NPERS' Nuclear Plant Engineering & Regulation Section.
' NRC Nuclear Regulatory Commission ,
NSEAS. Nuclear Systems Engineering & Analysis Section NSR Nuclect Safety Related.
NSSS Nuclear Steam Supply System ;
NWS National Weather Service ?
NA Not Applicable' OA Outside Air
.0HPD ~Offsite Health Physics Director OI' Operating Instruction OP Operating Procedure OSCL Operations Support Center OSHP Offsite Health Physics OSRC Offsite Review Committee i
PA' Public Address PAB Primary Auxiliary Building
, PAC Portable' Alpha' Counter !
'- PAG Protective Action Guides PAR Protective Action Recommendation 1
1 1
I EPIP APPENDIX A Page 4 I
PBNP Point Beach Nuclear Plant '
PBSP Point Beach Security Procedures Private Branch Exchange PBX 1 PDP Portable Data Processor (Digital Equipment Corporation) pH Hydrogen Ion Concentration P Pressu e ndi ato !
PIC Pressurized Ion Chamber !
POM Plant Operations Manager PORV Power Operated Relief Valve ;
ppm Parts Per Million 1 PSB Public Service Building psia Pounds Per Square Inch (Absolute) psig Pounds Per Square Inch (Gauge)
PSS Procedure Summary Sheet (EPIP 1.1)
Q . Quart QA Quality Assurance QAD Quality Assurance Division l QAS Quality Assurance Section .!
QF Quality Factor i
R Roentgen !
V RAP Regulated Air Pump RAS Regulated Air Sampler RAT Radiological Assistance Team i RCS Reactor Coolant System RCT Radio-Chemical Technician RCWM Radeon/ Waste Manager RDW Radioactive Waste .
REM Roentgen Equivalent Man '
RM Radiation Monitor RMS Radiation Monitoring System RMSASRB Radiation Monitoring System Alarm Setpoint Response Bcok RO 1) Reactor Operator 2) Rod Owl (Radiation Survey Instrument)
RTD Resistance Temperature Detector RWP Radiatioi Work Permit RWST Refueling Water Storage Tank SAF Site Access Facility (Kewaunee Nuclear Plant)
SAS Secondary Alarm Station SBCC Site Boundary Control Center SCBA Self Contained Breathing Apparatus SFP Spent Fuel Pool SG Steam Generator SGBD Steam Generator Blowdown
\s.
EPIP APPENDIX A Page 5 SI Safety Injection SOP 1) Standard Operating Procedure 2) Step Off Pad SP State Patrol l
SRC State Radiological Coordinator l SRD Self Reading Dosimeter '
SRO Senior Reactor Operator SSO Safety Standing Order (These have all been canceled)
STH State Highway STP Standard Temperature and Pressure Tc Temperature, cold TC Thermocouple Th Temperature, hot TI Temperature Indicator TID Temperature Indicating Device TLD Thermoluminescent Dosimeter TR Temperature Recorder
'tS Technical Specification TSC Technical Support Center TSO Time Sharing Option ULD Upper Level of Detection USCG United States Coast Guard
'( USEPA United States Environmental Protection Agency USNRC United States Nuclear Regulatory Commission V Volt V AC Volts, Alternating Current VAMP Victoreen Area Monitor Package V DC Volts, Direct Current WB Whole Body WE Wisconsin Electric WEPCO Wisconsin Electric Power Company WIS STATS Wisconsin Statutes WOG Westinghouse Owners Group WPS Wisconsin Public Service WT Water Treatment k.
_ .. _-___--l___ - _ - - _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -