ML20050C085
| ML20050C085 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/01/1982 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20050C081 | List: |
| References | |
| PROC-820301-01, NUDOCS 8204080119 | |
| Download: ML20050C085 (800) | |
Text
{{#Wiki_filter:;;. : _ zz- .
-- - -^ - ^ ^ -
1 EMERGENCY PLAN IMPLEMENTING PROCEDURES l l 1 SHOREHAM NUCLEAR POWER STATION UNIT No 1 i d LONG ISLAND LIGHTING COMPANY votuus1 b S!ack o!$000$2 PDR i
D g TABLE OF~ CONTENTS VOLOHE I 1.0 OH-SITE PROCEDURES Procedure Tab Proceoure Title Number Humber Technical Support Center (TSC) Activation.......... SP 69.005.02 ....... 1 Operational Support Center (OSC) Activation........ SP 69.005.03 ....... 2 Communications Equipment........................... SP 69.007.01 ....... 3 Notifications...................................... SP 69.009.01 ....... 4 Classification of Emergency Action Levels.......... SP 69.010.01 ....... 6 Unusual Event...................................... SP 69.013.01 ....... 7 A l e r t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SP 69.014.01 ....... 8 S i t e A rea Emer ge ncy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SP 69.015.01 ....... 9 Ceneral Emergency.................................. SP 69.016.01 ...... 10 Downwind Surveys................................... SP 69.020.01 ...... 12 Determination of Offsite Doses..................... SP 69.022.01 ...... 13 Waterborne Release Dose Projection................. SP 69.024.01 ...... 14 Protective Action Recommendations.................. SP 69.026.01 ...... 15 i Evacuations During an Emergency.................... SP 69.030.01 ...... 16 1 s Personnel Accountability........................... SP 69.030.02 ...... 17 Contamination Control During Emergencies........... SP 69.030.03 ...... 18 Personnel Injury................................... SP 69.040.01 ...... 20 Offsite Medical Assistance......................... SP 69.041.01 ...... 21 Radiation Doses During an Emergency................ SP 69.050.01 ...... 22 Thyroid Blocking................................... SP 69.051.01 ...... 23 Emergency Response Facilities Equipment Control and Readiness Check. . . . . . . . . . . . . . . . . . . . . . . . SP 69.062.01 ...... 24 , Re-Entry........................................... SP 69.070.01 ...... 26 l Termination of the Emergency and Recovery.......... SP 69.070.03 ...... 27 Search and Rescue.................................. SP 69.080.01 ...... 28 Documentation and Record Keeping During an Emergency.......................................... SP 69.090.01 ...... 30 i VOLUME II i
- 2.0 0FF-SITE PROCEDURES l
2.1 Corporate Corporate Notifications........................... CIP-1 .......... A Communications Equipment.......................... CIP-2 .......... B Emergency Operations Facility Activation. . . . . . . . . . CIP-3 . . . . . . . . . . C 7-. Support Corporate Headquarters Activation......... CIP-4 .......... D 1 ( r i
p V 2.1 Corporate (Cont'd.) Procedure Tab Procedure Title ilumber flumber O f f si te Secu rity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CIP-6 ......... F Recovery.......................................... CIP-10 ......... 3 Administration.................................... CIP-11 ......... K Documentation and Record Keeping.................. CIP-12 ......... L Thyroid Blocking.................................. CIP-15 ......... 0 2.2 Public Affairs Emergency llotification Procedures................. CIP-16 ......... P Emergency Communications Centers - Action Sequence................................... CIP-17 ......... Q 2.3 Administrative Emergency Organization............................ CIP-21 ......... U Revision and Approval of Plans and Procedures..... CIP-22 ......... V Distribution of Plans and Procedures.............. CIP-23 ......... W \q 3.0 ATTAClit1EllTS Attachment 1 - Classification of Emergency Action Levels - SP 69.010.0! 11
~
Submitted: pproved: (Plant Manager) te . p -- (,) t G:.r. > r e .5, i l!r. . . C p, [~,'e - ti a l DRAFT PRELIMINARY. SP Number 69.005 02 Revision: B Date Eff.: TPC TPC TPC__ TECIINICAL SUPPORT CENTER (TSC) ACTIVATION i 1.0 PURPOSE This procedure provides instructions for activation of the Technical Support
. Center. It is concerned with the duties of personnel before and during the activation process.
1 2.0 RESPONSIBILITY The Energency Director is responsible for ensuring compliance with this procedure. 1 P PF 1021. 6 N-6. 4 21 ,g p As Qh-
/
. p. s.
.we o 4p>w
/
},z.4 4 -*M sppt y
3.0 DISCUSSION 3.1 The Technical Support Center ( Appendix 12.2) is an onsite facility which
<~' S-- the capability to display and transmit plant status information to
(,)s individuals responsible for engineering and management support during emergency situations. 3.2 The Technical Support Center (TSC) serves as the emergency response facility responsible for accident assessment and emergency classification during Alert and higher level emergencies. Command and control of the emergency is handled at the TSC until the Emergency Operations Facility (EOF) assumes command or the emergency terminates. 3.3 Activation of the TSC consists of 3.3.1 Arrangement of tables and equipment 3.3.2 Installation of phones and communications 3.3.3 Assumption of responsibilities by personnel assigned to the TSC. 4.0 PRECAUTIONS N/A 5.0 PREREQUISITES . 51 An Alert, Site Area Emergency or General Emergency has been declared in accordance with Emergency Plan Implementing Procedure SP69 010 01, () " Classification of Emergency Action Levels". Emergency Plan Implementing Procedure SP69 009.01 " Notifications" has been 5.2 initiated. 6.0 LD11 TAT 10NS AND ACTIONS N/A 7.0 MATERIALS AND EQUIPMENT N/A
- 8. 0 PROCEDURE 8.1 Activation 8.1.1 Af ter receiving notification either by phone or over the Public Address system, all TSC support personnel should immediately proceed to the TSC.
3.1.2 0.w r ge nc y Director, cal.1 the :ihiit Scpe rd so r im! inf o rm him that the TSC is to be opened. (~\ Nj s SP 69.005.02 Rev. B
/ / Page 2
8.1.3 Shift Sacurity Supsrvisor, dispatch a security officer with prepar key (s) to unlock the TSC. The TSC is located adjacent to the Office and Service Building. p) (, 8.1.4 The security officer will remain at the TSC until the arrival of staffing personnel. The officer may then leave the TSC, return the key, and resume his normal security duties. Stay for access controll 8.1.5 If an evacuation has been ordered, personnel shall use the frisher monitor at the TSC entrance;before entry. Contaminated individuals should not enter the tenter. They shall report to the personnel decontamination facility in the Office and Service Building. 8.1.6 The first person to arrive at the TSC should: 8.1.6.1 Complete the TSC Readiness List (Appendix 12.1) 8.1.6.2 Log personnel in and out of the TSC using the TSC Accountability Log (Appendix 12.4) 8.1.7 As initial emergency respense personnel and/or their reliefs arrive, they should fill out their respective checklists (Appendices 12.5) to assure that they are. prepared to assume their duties and support activation of the TSC. 8.1. 7.1 Emergenc'y Director Checklist - Appendix 12.5 8.1.7.2 Radiation Protection Manager & Support Checklist - () s Appendix 12.6 8.1.7.3 Administrative Supervisor Checklist - Appendix 12.7 8.1.7.4 Maintenance Manager Checklist - Appendix 12.8 . 8.1.7.5 Plant Technical Manager Checklist - Appendix 12.9 8.1. 7. 6 Core / Thermal Hydraulic Engineer checklist - Appendix 12.10 8.1.7.7 Emergency Planning Advisor #2 Checklist - Appendix 12.11 8.1.8 Upon Completion of the Emergency Director and Radiation Protection Manager & Support Checklist, Plant Manager call the Control Room and, upon agreement with the Watch Engineer, declare the TSC activated and assume direction and control for the emergency. Make this announcement over the station PA system. 3.2 Operatioq d.2.1 1.iG personnel, perf ora dr ies Ln accordr.e ith Ew rgency Pian implementing Procedure SP 69.0$1 01 " Emergency Organization". l SP 69.005.02 Rev. B
/ / Page 3 l
l [
8.2.2 TSC personnel, requsst manpower support by contacting tha OSC supervisor in the OSC. 8.3 Documentation and Records b;
/
8.3.1 Upon deescalation of an emergency and subsequent deactivation of the TSC the following guidelines apply:
~
8.3.1.1 All forms, attachments and logs, shall be completed before any individual is relieved of his position. 8.3.1.2 All documentation shall be forwarded to the Administrative Supervisor following deactivation of the TSC and forwarded to Document Control. 9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS The Radiation Protection Manager & Support and Emergency of Director Checklists have been completed and the TSC has been activated.
11.0 REFERENCES
Shoreham Nucicar Power Station, Emergency Plan, section 7.1.3. 7-s12.0 APPENDICES v 12.1 TSC Readiness List 12.2 TSC Layout (Later) 12.3 TSC Phone Diagram (Later) 12.4 TSC Accountability Log 12.5 Emergency Director Checklist l 12.6 Radiation Protection Manager & Support Checklist 12.7 Administrative Supervisor Checklist 12.8 Maintenance Manager Checklist 12.9 Plant Technical Manager Checklist l 12.10 Core / Thermal llydraulic Engineer Checklist l 12.11 Luergency Planning /ulvisoc 42 Cheellist (J~' SP 69 005 02 Rev. B Page 4 l
/ /
Appendix 12.1 TSC READINESS LIST hte/ Time Initials Action Items (
/ 1. Set up tables as shown in Appendix 12.2
; if necessary.
/ 2. Remove phones from communications plug
,them into like jacks bearing their
' 'numbe r s. See Appendix 12.3 for the location of these jacks. Test for a dial tone on all phones.
/ 3. Test dedicated lines by contacting the
< party on the other end of the line.
/ 4. Ensure each desk has a in-out mail basket. If not, obtain them from the supply cabinet.
/ 5. Place name plates on each desk. Use Figure 1 for guidance.
/ 6. Ensure that the three Area Radiation
- Monitors are in their prooper place and turn on the Continuous Air Monitor.
/ 7. Set up the status boards (if necessary).
w I i i i l l SP 69.005 02 Rev. B
/ / Page 5
- , , * . _i
, P1 . , .
i . i
.L . . .ta t. ...;. . 1
,".._}'_
.uq ~_.1
+ .- - i *
- . .a. ..A.,.
w_4 ..i.' u. 9. __._ y m X0M3X _j. _,.. .p _,. __.2
. .t . .
_It a __
.__, . . + +.._
21.
.t I _
2_.....,
. _.t __._ .
; +_. . _ .
_.c+t , 9 + 7,y9,. +_7_.e
._ M_ u .97,.c q ..- _~_._f __.
{. s ._ _ _ g. _ }. _____ rn 3__ ._ .
. y.
- r. ;
- n. _r EQ pn._
.~ 4 1,-
v ;,g ..r
~g .I. 7 g ., Q~n+ _. ,. ..
L ._ _ 7p . . , ,
.3
-+
_r_, .. . . , .. . ..., . .
. _ei, it_. . , _
W/,,S . - - _r7 ,+-.__-+ _7 ,.
"1 .
-.,r,e co
.u , i, ... . .- ,, . , ,, .u m_ .
._ L ,f l, 4.._ ,_j_ l' ll [' {
f i
+- -
-y_h -y._'
11 j I
. i, ei # ,
q _;
. .,424
_ _1 ei t' 1- 'i
-4 4l ' ap_~ !-j i . ' ' i y lj)
- p. l l ., ,
t>_ .a e : 2- 2 . .
.mp :.
.l.b .p!
4L __Ay _74
, , .p.___. . . .g__ ..}.[ ,
4 .
.}. _g l , ,
i r ! w; __u i . , _(.~j- g_ _.- 1 ;, _,__ T
, f I I c_ . .-1 .p wdlO tjuy.+_._._ .
m, . .. .
' 1 g.i O ._ _
- g. * . .
.d;f- i ' 7 lI
' ~*~
~ - ~
r'i I ! h i **t. ::::: ,. . a_ p- o_up 3 A__ ; . __._ _ .__ _ . __ _.__ _. _g_ .p _
.p g_AF
, g it. ; r- ,
r- r .
.s ..
- k. a w s. e! ...: _4 s.
W 4_b
'tI'.t~t~_.
l -. W~k~ Y ~~
~~' - ,O 1
A A_ A .,'.
. ._ g. ,
- o. -. __ __. __,. .___ ..
1
'I__.4 AO.
-'2" [
O :p g9 { ,
' a;
- -- O m; f y ..' .
f.. . -_._ . '. .__- . . j_.__. /i: .
'.Z:
- p. g iy .. p_ +p
, I ,_ , ,
r_
.7
..q _g _ . .__- . _
m,3. ..} ; . p.,g. { ,,,4 g 4 M[ :,[ 7
~
'r ~
/
~ { [_ y- 'r
. ]
q .p 4 1 . _p .,__ _ ___ . __ _ .s .
.7 _-. } . -
_.7 ..} __--. .. .
.,,.}.- . .. ,( _7.,
. .. .A --
. . _ .1
' .t '
a .f ' ' *' -. ' . L 7_ , 5 _. . p .i n
-4_ ,
h
;l
.}_ T
'- -- ' -'~ - ' ~~
1"-
-'r"'- T'-'
"- -~~~ ~ -- - -
4.l_d-. .- -.7--'- -t*P ' -~}- -h '%* K 1- 4 - j 1. ; _.14 . .1 ij { .,._ $; ' _ ._p
*y}I i 4
_j.. ._ .. ~.__.__.._ __. __.. . . __. _,_ _ . _ , ___ a_ .
- 4. ,. .,J , ,, 6 .
'I _
. i. . .
y ..,..J. - Al . ! f ' .,.
.t !I _
4, .e s
;e.!e
. . .g jg 4, . 7'*
m..y ,{. I I i_ b*~. ..., _. . Q. h.1 p$ 4 ! ;. j s ,. g .y ;* .g J. 7 _1A (. i
- y. j __ . _.1 .4 Ap_p4 t _,
- 4 .
.g g g
,. {.7, ..+ ,- y ._,._
g,
.r .
.a 1 o g [, _ _ _
_tg +_.._ __p .g 4 rI 1__q1_+_., 3 ,- g
.\
,7 v su \ , . .
_T. ._,_g.
'*' ~
].
g, []4 ;_ . q_}_.. _ 47 - _- _ _, .._ ... ~_p.}.4 p_ j ,__. Q [_ . ._ ., 4. _.hfpp . / .]g g'.g %.-Fr ig, .-- jj
. "-~~
*' r<L,t --{.~.p p ..A.,.}jJ _.g 73 9,_
i
. q]. p e, :n r- . .. . . ,
m . .. .. . , - - . ; y ; : G'G " ;
* ~'"'-
P g ,,) .!i . lJ _ . . . J ...__. .._.. f $/3 1 . . o
% h 't E... t. E..
J LF:Hg m ;F...[.. - h* &-
-r
?- .p A.i__ .
.ri .s_ ____g_. .
ll}
-t-bh h a
- .t , ,,
!l 'l Yb- Y h ~ _ j h---h4-Q,, f,*h- lF-fi}-i-t---},-
- -- - ~
l [f
.ge; wm g ._ _g p q 4 : qt__._ ____
# g, Ap4p l l M -
, -t r rr u/W Hmy :_2 Re, .g':.I't. ,
r> 6 p__ 4'f ,p zu : *
. ___ . . t .___ _
~, r, 1 l 1-I t' ' 'l 'L-- --
p, - W
; 'l q,.,:gp ;,_; ,; [, .__g4.e ,p:p_._4, q l4, ,,_,:r _
..q..__ _p i.p( . .. _ _ _
.p, . _ . ._.,_7 4 _a.. p ,_ ,g,
_,_ g _
- p. .
g j
.- .- __n .
.p .g g A _- q.:r A _g
+ 4
.p .A . _ _.2 _ _._. __ _ _
,_g_ .
3 r , 4,___ l- F - 9,_p_ , 1 4. , .
- r _--
o -r+ ~~+-
$_ 1_ ....' '
_11 T~ le i _ <f ' [; "F ~ yd. ... .__ [ . - _ ..__ _ ..
+
.. , 2.
4 }a}. .r- -- - -- -- -- - - - - - -
.M_ d -
- -H-- b__l_ -
r 4F Af 4-- -
-F- --
M . g -p_h a
.. l.,
+_,_4,7#. _+. 1 . i _ .
.g.,p.43,. 9 ..,
p
.pp_p; i
i 1 , _. g _p . 3 i _ _ __I.. ,
- I . .
_ J +, m- r ; pm.= m . b r, + ; _. m_.._. u ; _.__ %_ __.+
. . . . r - r. .r. -. _ L . r . . - , . .- .
.T .
.. cr.._-
! h d ---) 2 7lj 1 l-{ 4-hi - F?-l1-pl '-i-f, f ? f, ,- -{ p [ - - [ 4 __r_- .L .pp j _ f_ _ _._ .._ ..,___l r . .. L.,{ .~g ;
p lJ i.4__ ' _ _ _. ,
, , , , , _17 h..L{ ,. h. m. . . . _. ,; ._ _ ... ,.
. 1. . _y , . . .
- c. -r_g. p ,
..._..,_) _.
- 4 .~(, .
i,, t__ 2 t
,,_r,_1.
, g.
- g. ..7 _p a ,p,
. g 4. . . _
h,.- 7 71 e, .. p _
.7 77 H. 7 -_
7_. p.; . p;_ _ .;_ . __g . q. __. p ;__ p _,
,, - a ,
+4 ,4., .pp_7. .7 ' .- _
p .p.a_ Ab -- y
,-o J . , .
-;_i .,.$.._ .p:
.n . .;, ; ,_L
+
E 2 _ e t
., b~/ v.t.-t
..'j
-+-
__g_v ; .
. p. _r .T_.1..__-...-r .A i.
i .t.+ y., .&.r . ;.i, _ t, . .
&* .53,
- L.,L, $
. p .
. .,h-. 7 ,.
&_7 .
. .(
_kL _q ._-gf 4 g. 1, w__p _4 . . a.
. ._.,q
-i, -
}
._ p._ 2_ Ap :
N 2; .~ .a_ 4.,p .
. 9.
- s. _.
o G, %p __p . r. .J___ m . #C.L__._._.i . 4
.$.'_.__ . ,- ._.2 _ , . . _
T
.; ___._-..y __.7 .7 _..
a ____ (, -g,. s _yxy Au 4 .u. .1r L=;--
'., .g' '--r - - ;-
..a.--.- H_._,-:--
l L A. - _-y_wQ.- -e- =- -r-
.a ,& , u._ .u. ._1 _
-p ,y q - J. .
,. ., ,. . . . _ .___ 25 . . .a. _p_. . _i,. . __
.:.y___t _y[ q_ .____q ._:..
,.y._ 7_
gv .}%__+. 1p 7 v ,_ .. .a g 7, . , _ _._
., __, i , . .
1 4d. _&. .?_ L- d-
._h1. _.y.r'-
h t--.- ,_1
}3_.--,_T.. .7 ,_ ..
,,,1.
.a' ..a. .hg *. _ - _ _A_
y -3 4*T-. ; .f 3 _ y. _ ._g a. ..,,- ,p_p._ . .r4_ ,. g_, ,
9 020I / / - U * ^WI Zd*5ds)*69 lS t-5 i-e HibON C _ . _ . - _ _ t :s -~ +.-~-~>.~ --. ' ~:. ; O. a 1
'j- e an j j y i ;r o
. -b i i r.r.nnr;a ; I l>
s = f.0 , .1 . .= w g ,.,y. .i ,
. . - . , _ . , 3. r.* .
. . . . i .
I
,s L- - i 2
l <-g 4 ll . , , . . . .. _- ... ; j .-
.e ::. <,- 3maf
. '.'.: vuay I
! .,,: I U ;1 '-
- i *-
.o ] o 1 n :
*j,
"-~
- .' e'*3 j 3 ., l'. t,2 ^^ ^ 8 l
'~ ~1 O. .
, s .
. .il !
- i vv 't i e l , t . ;
q a
-l l 1,,; H' .i i _D g
J 3 1
. t I
. t y l, y,.l Af1 A i 1 Af.1.A .o m q") ,Lg :- by-f
.1 c.
a j
,aM1.'l,1 .
~l31 'i 3 JJ
-- -- _rh., '. b '-
*ag a , .
*
- L,-'
9 X O;tl X i ! i
~~l__.. .
. . . . - ~ s n a.aa .l i u..msI - - -
1 { Y'I I
'. f. ,, . f}T l f.fl - *
. f. i +l .. l!
a i-tva ~ v s -
- l *
'.!g< ., l-I'
. [,
* ~
< ._ . . . .:.i)
I #
~~~-
.i
- y t' [ . # .
- t. > -
",,- .:'m l'.l f% l _. _-._ . . .
t's a: *i '
- 7l e a. .=
i 1
', m __ l
") __l g' t
. .; . _ _. ] , .,
(e . iLIN
,5 ({ l_- s ti
.=> em e m
.. .f
- e -e *-
f,-], a s _. ._ J ' h H ll
- t. .1 j "
i t'll td a: u 10 jllij{ . .; I - a
>- l .
'e e *- ..W.y1 j ] '$) l I l. *1 i fj ,,, [";%~'su r !
- v' 0 ] .*
l ,,, l.. j { *,,
.e.
i
. .c i .. --
'. ..~*'
C ** ' l ,, . ,,,
.- e ~
u. _ ns.g
.oo
- ) es nn r - - -- ___--- nese s .
68 "4
} . ,,._j o j
,g, .= .
WU
...l m r .w.a<. .s. w p-vsec.-l nu . : r- _ : --- . i
{..m- ' -- % GA. m-. we.a - - * --w + -
.cwn I I 3a..e - r : s ll' W
( ~i . I,> , i
- 1,l1 i fI f I,.
- l
.I l
%.* w *lI-
. ww ~ .t
.i.td- ~* - - ~ .) old- -' ~
~'N T 1
L D'A'.I / / - il
- Aall 20'5dd* 69 .lS
}.
l l li l Hf!?! L H r.w ~- - a; i i i 1I .n
".".<3
.l .
i
- \ l "#
-e l
p , i r.,, s. . J . , . _ . .
...,.~. .
I.r.o ( ; ,
.. ..i.....
e,
' f -
7 lA !' .! I: j 1 .,
~
3
, Y,y .i i d(y9 c _.vun, ,.__.. I m .. .
t
. .. .i n ; ,
.. r, ,, ! ., ~ ~ ~
i
.i. .I ' ", r; - ,) m .n r \I. f;~ i s
+ ,_ - _ ..ij*, ?. i n L-i_ . ..
, i
., - i nim .,
~Np '- * " ' " " y
; it }9, / g ,_. -.J
{ A A .A i.A ' u L l. c> lca cgl c; 3 r-
*..a
'c ~. .; 6
.-~~ .
AfDill ) ' t . naaea smses.wn
.L O l l C3 l -
o.!.H. lUlhl, -
.~
i C) <
.. ,,. q .
l' 9 ., . c,a cJ.s ;:,, t - -
., - 1 .
t _ I t .,.,, i i
.!. ! U '? 8 -
- 3, L,i i
;. y
.I.j 1 G - ..
, ;5 i.<. i -
l
. a. '7
- 6. . O O - f:C i r .h-'I ' ' .
i 5
. c 9 el ~- 'l N: ,
.. . e.. . .,
; .l L
4
- i e el e. ] :,.. .
m. i, i ..
.=
) :'; dI l. i ! l "i .s
.4..
.\.-.r - - - m -.
"o j.5
\. .
~. / ..
.t i
- . t I a n '.'a ' '
'i ;
' 4 v# ,
- e. Hij ;
, , , - _ - - g-rM . --r .., ..~ r ,. .: ~. .. . . - e .,m,. - ,t g
_. ~w ~~ _%m m cw
'; U ; j h; , .
'. llI, i
, ?
h ; ,
, li .
,I..- I ',.%I r .~ . l _ _ .. .._4_-. i .
l
. ..i.u . . -
.2 . , .: -
.. . - - . - - . - . . . - . ~ . . . . . . . .
p- , a I TDCl!NICAL SUPPORP CEN'IER ' TELEPiiONE COtO7JNICATIONS ,
@ ' Radiation Protection Manager Five Direct Dial Lih.cs (DD-Ol' DD-02, ', DD-02, DD-04, DD-05)
Three Internal Extensions (IE-01, 'IE-02, IE-03) Plant Technical Manager Direct Line to Dnergency Operations Facility (DL-03) . Five Direct Dial Lines (DD-01, DD-02, DD-03, DD-04, DD-05)
~
i Three Internal Extensions (IE-01, IE-02, IE-03) h Core Tne mal /IIydralic Engineer . t h Mechanical Engineer - 1
@ Ouality Annurance Engineer l
b i i Chemical Enginmr 4 I i . SP 69.005.92 Rev. B
/ / Page 7A
TECIMICl\L CUP 10RP CENTFR .' O
- TIEWiIE COCC4UNICATIONS (cont'd) h Electrical ~ Engineer h Ib3ntenance lunager h Ocerations Ihnag&
u) h Emergency Director Direct Line to Control Prxm (DIc01) Direct I.ine to Fhurg2ncy Oparations Facility (DIc02)
. Five Direct Dial Lines (DD-01, DD-02, DD-03, DD-04, DD-05) h Nbtinistrative Staff h /thinist:rativ; Sumtvifq.
O S1' 69.0;15.02 nev. B
/ / Page 7B
- u, l TIrl!NICAL SUPIMP CIA"I' Eft . l TELEPlICHI? CXJIUN1 CATI (WS (cont'd) . .
, . ,i
- h. rgency Planning Mvisor
. Five Di.roct Dial Lines (DD-Ol', DD-02, DD-03, DD-04, DD-05) :
Three Internal Extensions (IE-01, IE-02, IE-03) ! h . nerhency Comunications Liason
- t h '
Carr1unicator 5 Fivo Direct Dial Lines (DD-01, DD-02, DD-03, DD-04, DD-05)
. Four Internal Extensions (IE-01, IE-02, IE-03, IE-04)
Direct Line to Operational Stpport Center (DIc04) , l , !~ . ! t f [
- l. h Comunicator 2 -
[
?
h Ccurmunicator 3 ! l (ENS) NIC llotline ' t N.Y.S./S.C. Ilotline YM. ."f, . O:n Idcatic D.irtler i
, i
.e 5
SP 69.0i15.'02 Rev. B
./ / Page 7C ,a-,--,...,,-.- -- - .,. - - , , - . . . . - . - . . . . . - - . - - - - . . - - - . . . . - - - - - - . . . . . - - - - - - - - - -
App ndix 12.4 TSC ACCOUNTABILITY LOG Name Department Date/ Tine n Date/ Time Out W r
%j.
4 6 w n- e hM Ne +ese e m [ SP 69 005 92 Rev. B
/ / Page 8
) i
4 Appzndix 12.5 EMERCENCY DIRECTOR CHECKLIST Ste/ Time Initials Action Items 1
/ 1. Contact the Watch Engineer and discuss:
/ a. Status of plant conditions including emergency classification and corrective actions underway.
y 3 / b. Which Emergency ction Level (EAL) was exceeded to cause the emergency condition. l 1 / c. Recommended protective actions made to date and his knowledge of the implementation of these actions.
/ d. Status of EOF if activated simultaneously.
/ e. Location of Response Manager.
4 1 a SP 69 005 92 Rev. B i,
/ / Page 9
Appandix 12.6 RADIATION PROTECTION MANAGER & SUPPORT CHECKLIST Ste/ Time Initials Action items
/ - 1. Perform survey of TSC. First arrival check that all naterials needed to perform assessments are available.
t
/ a. Procedure and forms.
/ b. Walkie-talkie for field team I communications.
/ c. Check all monitoring equipment.
/ 2. Radiation Protection Manager contact the inplant Radiation Monitoring Technician and determine:
i I
/ a. Extent of radiological releases and plant conditions.
/ b. Meteorology
/ - c. Status of inplant surveys (if any)
/ d. Location and extent of any x contaminated areas.
/ c. Projected offsite doses and Protective Action. Recommendations made to date..
/ ,
- 3. Radiation Protection Manager determine that adequate staff is on hand to perform initial tasks.
i i 4 () SP 69 905 02 Rev. B
/ / Page 10
- ,-- - - -,-me + - - , , n- m - - - - -
w -, ,> .-- -,
Appendix 12.7 ADMINISTRATIVE SUPERVISOR CHECKLIST
- te/ Time Initials Action Items
/ 1. Coordinate requests from TSC and other station personnel concerning supplies, equipment and transportation.
/ 2. Determine if adequate administrative and logistics personnel are present to carry ,
out duties. l t O SP 69 005 02 Rev. B O / / Page 11
Appendix 12.8 MAINTENANCE MANAGER CHECKLIST ,
'? ate / Time Initials Action Items
/ 1. Contact Operations Manager and \
1; determine: l
/ a. Plant status as it affects
.- maintenance or fire fighting.
/ b. Status of repairs or fire (if any)
- in progress.
4 3 / 2. Determine how many support personnel are
; available at the OSC to support maintenance or fire fighting operations.
/ 3. Recommend that offsite fire fighting support be requested by the Emergency ;
Director if conditions warrant. , I e h I, l I l e 1 l i l 1 () SP 69 005 02 Rev. B
/ / Page 12 '
l s
,, ..,,--.n~- ,, .- , ., .- ,-- , . ~ . . - . - , - . - . , , , - , , , . . - - - . - . - - . - - . - - - , - . - , . - _ - . , . - - - -
., --6 .r- - -
. n. - - - . - . . - .
a
..i \'
/ , '
/
\, ,O
, Appendix 12.9 t x t> l, >
-g i
, [
'\t ~'
7 4 PLANT TECHNICAL MANAGER CHECKLIST I 1 .
.T ,
qate/ Time _ ~ Initials Action Items , s s, , 1 L s / N*
- 1. Determine plant status from the Shift i
i s' ' Technical Advisor and relay this
' 3' - information to the Core / Thermal i 1 +
1 Hydraulics Engineer, Electrical
's, k Engineer, Hechanical Engineer and i . . Chemical Engineer.
s N g 4 s
- i. t.,,
s
\
\
l
\
.I Y a 1 4 i , x N i \ ) 1'
~. -, .
s e, w % i 1 ! , s s, 2
,s ,
s l .-
\ '
j s' , A\ ' l I I
- s ,
i i l [ s.
\
-s ' s. SP 69 005.02 Rev. B
', i
/ / Page 13 s.
i '
, 4 f t i . .
' \
t 5 . 4
- r. )
)
l , ( , A
\,
( \
..n,
, s,. -
's
---4~,-.
s
-,--,,,+,r.
( i -3 s, \. -. % n ,,- s- - - . --- , . -- --, .-. , . . . - - - - , , ~ . . . -
Appandix 12.10, CORE / THERMAL HYDRAULIC ENGINEER CHECKLIST ote/ Time Initials Action Items
/ 1. Obtain information on plant status as it relates to core parameters in order to l, , determine current core conditions.
/ 2. Inform Plant Technical Manager 5~oncerning c recommendations for operation that would result in safer core conditions.
I m
)
1 I l l l ! I W l I t SP 69 095 02 Rev. B
/ / Page 14 1
I i
1 I 4 e Appendix 12.11 '
. . i
- EMERGEtICY PLANNING ADVISOR #2 CHECKLIST 2
.te/ Time Initials Action Items ;
i
/ 1. Upon arrival, lend emergency planning ,
advise to any members who request ; assistance.
.,s t
L f b J l l i l I i i i i l i l-i i t I-P t V P v SP 69 005 02 Rev. B ;
/ / Page 15 s
L
. - - . -..,,,----,~,--.y r,..w,...,.,__~,--v.., . . . , _ . _ _ .m. mm~~ . - . _ _ _ _ ~ . - - - _ _ _ - _ . _ - - - _ _ _ _ _ _ _ _
, Submitted:
Approved: 1 7 %,'~ (Plant Manager) f cc - O I' f t i n.o..h,*c 1: h
,l} s . ~..,
hf: l '?)4 *g:l 'm ,~ - . l.
~~.g':j:
.. . L
~
iNAFT-Pagyy SP Number 69 005.03 Revision: B Date Eff.: TPC TPC TPC OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION O 1.0 PURPOSE This procedure provides instructions for activation and operation of the Operational Support Center. It is primarily concerned with the duties of key personnel before and during the activatioa process. 2.0 RESPONSIBILITY The OSC Supervisor is responsible for ensuring compliance with this procedure. PPF1021.660-6.421 ,g S / s g ggy:(' . t
- j)/Sc-/631/1l'm)
3.0 DISCUSSION The Operational Support Center serves as a staging area for emergency response f- pe rsonnel. Personnel reporting to the OSC would muster until requests for (g) assistance are received by the OSC Supervisor from the Technical Support Center. The OSC Supervisor would then assign these support tasks to various persons and dispatch them as necessary. After dispatch the support personnel will be under control of the person requesting the assistance. 4.0 PRECAUTIONS 4
/
N/A 5.0 PREREQUISITES 5'.1 An Alert, Site Area Emergency or Ceneral Emergency has been declared in accordance with Emergency Plan Implementing Procedure SP69.010.01
" Classification of Emergency Action Levels".
5.2 Emergency Plan Implementing Procedure SP69 009 01 " Notifications" has been initiated. 6.0 LIMITATIONS AND ACTIONS N/A 7.0 MATERIALS 1 N/A 8.0 PROCEDURE 8.1 Activation 8.1.1 After receiving notification either by phone or over the Public Address system, OSC personnel report to the OSC. 8.1.2 The first person at the OSC should: 8.1.2.1 Turn on lights 8.1. 2. 2 Complete OSC Readiness List (Appendix 12.1) 8.1.3 The first arrival shall assume command (until the OSC Supervisor arrives) and delegate the following tasks: 8.1.3.1 Designate a person to log all actions on the OSC Status Board. 9.1.1. 2 %a! aato , percon to inttfe.c accountability of all personnel in the OSC using the OSC Accountability Log (Appendix 12.2). O l (--) SP69.005 03 Rev. B
/ / Page 2
-8.1.4 Upen arrival, OSC Supervisor casume command and dstermina tha following:
8.1.4.1 Status of plant conditions from the control room. 8.1.4.2 If manpower support available at the OSC adequate. If not, request additional manpower through a Control Room or TSC Communicator. 8.1.4.3 Announce over the PA system that the OSC is activated and notify the TSC of same. 8.2 Operation 8.2.1 As emergency response facilities request assistance, OSC Supervisor assign personnel to perform the support task (if available). 8.2.2 OSC Supervisor, ensure support task personnel are equipped for their mission or that they will pick up equipment at the center where the assistance was requested. 8.2.3 Log the following information on the OSC Task Sheet (Appendix 12.5): 8.2.3.1 Team members 8.2.3.2 Support task description 8.2.3.3 Team destination
. 8.2.3.4 Time team was dispatched l 8.2.3.5 Time task was completed 8.2.3.6 Person requesting assistance -
8.2.3.7 Other pertinent information (equipment, routes, etc.) 8.2.4 When support team is dispatched, OSC Supervisor notify person l requesting assistance and inform him that team is dispatched and that the support task personnel are under his jurisidication. l l 8.3 Documentation and Records 8.3.1 Upon decscalation of an emergency and subsequent deactivation of the OSC, the following guidelines apply: 8.3.1.1 All forms, attachments, logs, shall be completed to insure recons naction of ene rgency events. 8.3.1.2 All docuuent n .ca shall be forwarded to the Administrative Supervisor following deactivation of the OSC and then to Document Control. O U SP69 005.@3 Rev. B
/ / Page 3
- o. ,
1 . 9.0 ACCEPTANCE CRITERIA i i
- N/A ,
l 10.0 FINAL CONDITIONS The OSC Supervisor has completed the OSC Readiness List and the OSC has been activated.
11.0 REFERENCES
Shoreham Nuclear Power Station Emergency Plan, Section 7.1.4. , 12.0 APPENDICES 12.1 OSC Readiness List 12.2 OSC Accountability Log i 12.3 OSC Layout i 12.4~ OSC Phone Diagram 12.5 OSC Task Sheet i !O . 1 t j 4 i M
?
E l O SP69 0@5.03 Rev. B
/ / Page 4 4
Appendix 12.1 OSC Readiness List I-G' Action Items Date/ Time Initials
/ 1. Set up tables as shown in Appendix 12.3 if necessary.
/ 2. Remove phones from the communications locker and plug them into like jacks bearing their numbers. See Appendix 12.4 for the location of these Jacks.
4 Test for a dial tone on all phones.
/ 3. Test dedicated lines by contacting the party on the other end of the line.
/ 4. Ensure that all monitoring equipment is in its proper place and that a qualified Radiation Protection person is checking operations on each piece of equipment.
/ 5. Position status board in place (if necessary).
O l l l I l l SP69 005.03 Rev. B
/ / Page 5 l
1 (
Appendix 12.2 OSC ACCOUNTABILITY LOG l v NAME DEPARTMENT DATE/ TIME IN DATE/ TIME OUT i 1 4 9 G I s l i b V - 1 l t I i * ,g. i j a. ._ i i SP69 0@5 03 Rev. B
/ / Page 6
, ,, . STO R A G 6 ,
.CPPensix 12.3)
-. : , CLOSET -
Q Pl.n!!r iTA7US BD G/p
- +s,
<3 st-ig Elect *. Eluh Muh ose. ri .y
~
Se,* r ~ , C Itc U V \,/ N ruh
* *ll 'I
( 8eJ owe h y . Redh ) Spx Rre, Scdoin-p rl>J Techs ) ( aa a,t
)
( 1 ( Techs
]
( IE- O
)
( w.r ) Inpld I
, T'ech5
}
)
Onsile c.c.A ftcn Techs U' V V l
. Chaw.Tn
~
7 l cont RocNS SP 69.005.03 Rev . B
/ / Pan 3 7
- . . . . . - ~ . . . , , -
~
/ -
.s . celi,-> rs- ,
#: c s) - + c s. ,,
8 . osc.'
# A }Y
. = c-i.. .
Recerd S b'P'r Mech L.
- b. .
R Rad Elect was 3Q .,, Oper i . R5 Elech ; - S- tp S , 2tc RaJ Inpbd Tech Chawi
- Ed Tech McA b Tech g gn p,,j M . Rad onsle.* Mm chem kd Tech Tech -
Mm
~.h kt onsde. ine6t-
% k0 ga' men Men yny-Tah Tech Tech F.rt.
Bri R' bd Prol. i'. t j Ted TECII st-c; Fire Bri t-
'Q .
Pecf F.rt 7ach Bri
/ .,
. i.c.
t '
.f L_..-...._.. . - _ .
SP 69.0J5.03 Rev. B
/ / Page 7A
i APPENDIX 12.4 1 1 r
]
LATER i l I t 4 i I
, SP69 035 03 Rev. B l / / Page 8 . _ _ _ _ . _ . _ . . _ _ . . _ . . _. _ . _ . _ _ _ _ . _ - _ , _ . . . . . _ _ _ _ _ . _ _ _ - ~ . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
l. S UN OO EI NT AA LM LR EO CF SN O II M
]j I
- l 3
. i ;
_ - E 9 G N . e I vg TE ea SC RP EN UA 3 QT 0 ES . RI 5 S NS 0 OA 0/ S . R 9 5 E 6/
. P P 2 S 1
i x d n ET e MN p IE p TS A . D E EH MC I T TA P S I D T E N E O H MI S AT EA K TN S I A T T S E C D S O K S A T T R O P P U S S R E B M E M M - A E lT
s Submitted: Approved: l
% --.~.-----.....___.___.q k' N ?
fc N ['.i J9'l ?.I', y; I'd jj f.J .
- e. '74 ij
.s iDRAFT-PREllMINARY SP Number 69.007.01 Revision B Date Eff.
TPC TPC TPC COMMUNICATIONS EQUIPMENT O 1.0 PURPOSE , To describe the communications equipment that are available for emergency use,
- their location, and their function. Specific operating instructions are not included.
2.0 RESPONSIBILITY
~
The Health Physics Engineer shall be responsible for ensuring the availability of these conaunications equipment for use during energency conditions. t [ l
.'221.
,' O. .
am 1l?] l l l
1 l 3.0 DISCUSSION 3.1 The SNPS communications capabilities include multiple systems and redundant power supplies which ensure the transmitting and receiving of vital N information within the plant and within locations on-site and off-site. i 3.2 Figure 1 illustrates the major communication modes and paths and Appendix I lists the type of communications capability provided in each of the j emergency facilities. 3.3 Topics covered in this procedure 1nclude: Page 8.1 Hotline 2 8.2 Dedicated Lines 3 8.3 National Alert Warning System (NAWAS) 3 8.4 Commercial Telephone 3 8.5 Emergency Card Dialer Phone 4 i 8.6 Private Automatic Exchange 4 8.7 Public Address and Party Line 4 8.8 Sound Powered Telephone 5 8.9 Beepers 5 8.10 Two-Way Radio 6 8.11 Hard Copy Transceivers (Telecopy) 6 Appendix I - Facility Communications List Figure 1 - Major Communication Modes and Paths-4.0 PRECAUTIONS l 5.0 PREREQUISITES N/A ' 6.0 LIMITATIONS AND ACTIONS Specific operating instructions for the communications equipment described are not included. 7.0 MATERIALS AND TEST EQUIPMENT N/A 8.0 PROCEDURE 8.1 Hotline 8.1.1 This co.:nunications link will be the prinary means for notification of th- at ,nd C.n: , of w r; enc 20 ditions .: t Shoreham. [~) A/ SP 69.007.01 Rev. B
/ / Page 2
1 8.1.2 Th se dedicated phonn lines, mada eparational upon pick-up of the
. receiver and selection of desired-location, shall provide the capability enabling any and all of the following locations to communicate simultaneously:
!p, )
\/% .1 Control Room
.2 Technical Support Center (TSC)
.3 Emergency Operations Eacility (EOF)
.4 New York State Emergency Operations Center (Albany)
.5 New York State Southern District Office (Poughkeepsie)
.6 Suffolk County Emergegcy Operations Center 8.2 Dedicated Lines 8.2.1 In addition to the Hotline, dedicated lines will be ins?,alled as the primary means of communication with the Nuclear Regulatory Commission and for intra-Company communications.
8.2.2 The NRC dedicated phone system will allow sicultaneous communication with the NRC's Bethesda Of fice and their King of Prussia Regional Office. 8.2.3 Internally there will also be three separate dedicated lines installed as follows:
.1 Between the Control Room and the TSC.
.2 Between the TSC, EOF, and Support Corporate Emergency Response and Recovery Center (SCERRC).
\s_/ .3 Between the EOF and Emergency News Center (ENC).
8.3 National Alert Warning System (NAWAS) A dedicated NAWAS line vill serve as the primary backup communication link between the Shorehan site and Suffolk County Emergency Operations Center
- and the New York State Emergency Operations Center (Albany). This will allow simultaneous notification of the two agencies.
8.4 Commercial Telephone The commercial telephone system consists of various dial-type telephones t' connected to the New York Bell Telephone System. These phones provide a means of communication offsite, and may be used as a secondary backup to l the Hotline. They are powered by normal voltage supply and are therefore susceptible to loss of offsite power. They are located in various parts of the plant as well as the following: 8.4.1 Control Roon l l S . '. . .' 1 e.;hn ica l S.i;>po t t Leater l l j O ( ,j SP 69.007.01 Rev. B ! / / Page 3
. ~
8.4.3 Oparational Support Center 8.4.4 Emergency Operations Facility
. 8.4.5 Emergency News Center 8.4.6 Support Corporate Emergency Response and Recovery Center 8.5 Emergency Card Dialer Phone The emergency card dialer phone is connected to the commercial telephone system and has automatic dialing capability by insertion of pre-coded dialing cards. This phone will be located in the Control Room, or the Technical Support Center when activated.
8.6 Private Automatic Exchange 8.6.1 The private automatic telephone exchange consists of a network of commercial telephones that may be used in the dialing mode for intra-site communications. These phones are located throughout the plant including the following locations. 8.6.1.1 Control Room 8.6.1.2 Technical Support Center 8.6.1.3 Operational Support Center 8.6.2 Several essential members of the emergency organization shall have phones tied into this network installed in their private homes.
) They may include the following personnel: ./ .
8.6.2.1 Plant Ibnager 8.6.2.2 Chief Technical Engineer 8.6.2.3 Chief Operating Engineer 8.6.2.4 Health Physics Engineer 8.6.2.5 Operating Engineer 8.6.2.6 Reactor Engineer 8.6.2.7 Security Supervisor I 8.7 Public Address and Party Line Six separate and independent connonications channels, one page and five party lines, oxist to provide voice connunication between two or more _ s .Ithin ti p1 int , ever, in area.s of ext re:n noise. The page channel is used to call personnel over the loud speakers, issue plantwide
\ SP 69.007.01 Rev. B s/ / / Page 4 1
, .. . . , - ~
- - - . . .n ., - - . - - - , ,, - - , - - . , - ..~e.
instructions or communicate between two er more handsets. The p rty lin2s are used to carry on inter-communications af ter the page channel call is completed. Audio tone signals can be introduced into this system to allow for possible fire, system emergencies, etc. Each handset and speaker has [s) its own amplifier and they are independent of all other components in the system with respect to their operation. The page/ party system is supplied by an uninterruptible power source and is not dependent upon the on-site power supply. This system is located throughout the site, as well as the following areas: 8.7.1 Control Room 8.7.2 Technical Support Center 8.7.3 operational Support Center 8.8 Sound Powered Telephone The sound powered telepbone system consists of independent string circuits connecting critical points in the plant. Communications within the system is by means of sound powered, portable headsets which can be plugged into any jack along a string circuit located throughout the plant. The sound powered phone system requires no power and is not affected by a loss of site power. This system shall be located in the following locations, as well as various areas within the plant. 8.8.1 Control Room 8.8.2 Technical Support Center G I )
\m / ,8.8.3 Operational Support Center 8.9 Beepers in conjiinction with the call-out by commercial telephone of Company personnel essential to the emergency organizations, beepers will also be activated. Upon activation of beepers, personnel shall call in on predetermined phone numbers to be given the course of action to be taken, plus any pertinent information regarding the emergency situation. The following personnel may be issued beepers:
8.9.1 Plant Manager 8.9.2 Chief Technical Engineer 8.9.3 Chief Operating Engineer 8.9.4 licalth Physics Engineer ( 3.0.; om-r ning r.naine r i l ! 8.9.6 Reactor Engineer SP 69.007.01 Rev. D
/ / Page 5
_._.n ._ _
8.9.7 Sscurity Supervisor 8.10 Two-Way Radio f- g 8.10.1 A low powered UHF Radio Base Station with two frequencies, is () established at the plant'for communications between the Control Room Radio Communications Center, mobile car units, and portable ,
"walkie-talkic" units, as well as with off-site locations.
l 8.10.2 A third frequency on this UliF Radio Base Station shall be established to provide the capability of two-way communication link , between the station and police. 8.10.3 A VilF Radio Base Station shall be established for communications between the Control Room and the LILCO Operations Center in Hicksville. 8.11 Hard Copy Transceivers (Telecopy) (later) 9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS N/A R"FERENCES
\
C"11.0N/A - 12.0 APPENDICES 12.1 Facility Communications List ' i 1 I [~'\ SP 69.007.01 Rev. B
\~s / / Page 6
APPENDIX I FACILITY COM:fUNICATIONS LIST pm
)
A. Control Room B. Technical Support Center
- 1. Hotline 1. Hotline
- 2. Dedicated Lines 2. Dedicated Lines
- 3. NAWAS 3. NAWAS
- 4. Commercial Telephone 4. Commercial Telephone
- 5. Private Automatic Exchange 5. Private Automatic Exchange
- 6. Party /Page System 6. Party /Page System
- 7. Sound Powered Phone 7. Sound Powered Phone
- 8. Card Dialer Phone 8. (Card Dialer Phone)
- 9. Radio 9. Radio C. Operational Support Center D. Emergency Operations Facility
- 1. Dedicated Lines 1. Hotline
- 2. Commercial Telephone 2. Dedicated Lines
- 3. Private Automatic Exchange 3. NAWAS
- 4. Party /Page System 4. Commercial Telephone
- 5. Private Automatic Exchange
- 6. Radio E. New York State Emergency F. Suffolk County Emergency Operations Center Operationn Center
- 1. Hotline 1. Hotline
- 2. NAWAS 2. NAWAS
- 3. Commercial Telephone 3. Commercial Telephone
- 4. Radio 4. Radio G. Emergency News Center H. Support Corporate Emergency Response and Recovery Center
- 1. Dedicated Line 1. Dedicated Line
- 2. Comnercial Telephone 2. Commercial Telephone
- 3. Private Automatic Exchange i
SP 69.007.01 Rev. B
/ / Page 7
m_.._m___ _. MAJOR COMMUNICATIONS MODES AND PATHS NEW YORK STATE O EMERCENCY PERaTI NS O O
,l ROOM (CR) CENTER C
l t k NRC (BETHESDA AND KING OF PRUSSIA) O -! i , q l l I O SurroLK COUNTY TECHNICAL EMERCENCY o SUee0RT C O OPERarIONS CENTER (TSC) CENTER 1 SUPPORT CORP. g EMERGENCY l sua 88 g
= """ , , aus -
RESPONSE AND O RECOVERY CENTER f (SCERRC) l 1 EMERGENCY OPERATIONS EMERGENCY NEWS l FACILITY (EOF) CENTER (ENC) l _ _. _ . _ o o-------.o KEY Hot Linc NRC Dedicated Line Intra-Company Dedicated Lines (3) FIGUFE I
/8 / aeo
,M -
' Submitted:
jpproved: J L s' " iDRAFT-PREllMINARY SP Number: 69.009.01 Revision: #C Date Eff.: TPC TPC TPC
- EdTIFICATIONS O
l 1.0 PURPOSE . To specify the means by which communications for all energency levels are made for all levels of emergency classification and to delineate perconnel who would be called to augment the emergency response organization. l 2.0 RESPONSIBILITY l l The llealth Physics Engineer is responsible for ensuring compliance with this procedure. i g Yh ., J
^
p v PPP 1021.606-6.421
e 3.0 DICCUSSIO:4 3.1 Establishment of a quick effective means of notification of an emergency p) ( is a critical part of emergency response. Primary and secondary modes of communication are provided to insure the availability of proper communications. 3.2 Preplanned message statements allow for accurate and complete transfer of information. Persons making the notification simply read pre-written statements containing the necessary data. 3.3 Topics covered in this procedure:.j.' / _Page 8.1 Initial Notification 2 8.2 Personnel Injury Notification 3 8.3 Verification 4 8.4 Subsequent and Follow-up Information 4 4.0 PRECAITTIONS Only persons authorized by the Emergency Director shall make notifications as prescribed in this procedure. 5.0 PREREQUISITES An emergency has been classified in accordance with Emergency Plan Implementing Procedure SP 69.010.01, " Classification of Emergency Action Levels". 6.0 LIMITATIONS AND ACTIONS l O l N/A 7.0 MATERIALS AND EQUIPMENT l Communications equipment as described in Ref. 11.1. , , 8.0 PROCEDURE 8.1 Initial Notification , 8.1.1 Emergency Director or designee:
.1 Provide a completed Initial Notification Fact; Sheet (Appendix 12.1) for tha appropriate emergency class toy / ontrol-Room C
Operator,-TSC. Communicator-or-EOF Com.unicator.
.2 Notify the LILCO Cas Systems Operator by means of the Emergency Organization Call Phone so that he can notify appropriate corporate personnel in accordance with " Corporate Notifications".
.3 Direct a Control Moon Conmunicat or, TF.C Cor.unicator o'; EOF Communicator /Jc. call in SNPS personnel for the appropriate emergency class using the SNPS Emergency Call Document p located-in-the-Control-Room,-TSC-or-EOF.
l ( SP 69.009.01 Rev. B
/ / Page 2
1
.4 Inform the NRC using a Plant Operator (via the Emergency i
-s s Notification System, ENS) reading the Initial Notification
( ) Fact Sheet. If the TSC is activated, this function can be done at that center. Record the notification on the Offsite Agency Notification Checklist (Appendix 12.2). Use communications guidelines given in step 8.1.2. NOTE: The NRC will require the ENS line to be continuously manned if they.so desire in order to be kept appraised of the emergen'cy ' situation. Provide all information
, asked for, if possible. The Plant Operator should ask the NRC 1f they will speak to a different person so that he can resume his operational duties.
8.1.2 Con t rol-Roo& Operator;-TSC-Communicatv u ut-EOF Communicator, notify the individuals or organizations listed on the Offsite Agency Notification Checklist (Appendix 12.2) using the Initial Notification Fact Sheet as follows:
.1 Call each individual or organization using the primary mode of communication. If the party cannot be contacted using the primary method, use the alternate method.
.2 If a party cannot be contacted, bypass that party and proceed to the r.cxt one on the list. After all notifications have been completed, attenpt to contact the bypassed parties.
f-s If a party still cannot be contacted, consider other methods (j such as relaying the information through a third party.
.3 When the individual answers, identify yourself and inform the party to obtain the form on which to record the notifica-tion. Pause to permit the individual time' to obtain t.he form.
.4 Read the notification, annunciating the information which
_ . is to be entered on the form.
.5 After the notification has been completed, ask the individual to read back the notification and, if necessary, correct any errors.
.6 Record the name of the individual and the time of contact on the Offsite Agency Notification Checklist.
.7 Proceed to the next party on the Call List and continue in this manner until all individuals and organizations have been notified.
8.2 Personnel Injury Notification 8.2.1 Emergency Director or designec, provide a completed Personnel Injury Fact Sheet (Appendix 12.3) foAsEdnerol+ Room Communicator, TSC-Commu n icatto rJE_C ommunic a to r . V ' l SP 69.009.01 Rev. B
/ / Page 3
1 8.2.2 Control-Roomr>ISGr-or-EOF Communicator notify the individuals / organizations listed on the Personnel Injury Call Checklist (Appendix 12.4) using the guidelines given in section 8.1.2 of this procedure. NOTE: If the personnel injury involves contamination and offsite treatment, do not notify the Suffolk County Emergency { Operations Center as this is an emergency event and Suffolk County will' be notified by means of the Initial Notifications given i r'section 8.1. 8.3 Verification 8.3.1 Some calla made by use of dedicated lines may require verification. 8.3.2 All calls made by commercial lines require the individual receiving the notification to call back and verify that he has obtained the necessary information. NOTE: A telephone number is provided to offsite agencies for this purpose. 8.4 Subsequent and Follow-up Notifications 8.4.1 Emergency Director. fill out the applicabic portions of the Follow-up Notificctioh Fact Sheet (Appendix 12.5) and give it to a Cont-rol-Roomr--TSC-or-EOF Communicator for transmission to g offsite agencies listed on the Offsite Agency Notification ( ) Check List. l 8.4.2 Follow-up Information should be given to offsite authorities when:
.1 The emergency classification changes ,
.2 Plant conditions change substantially
.3 The emergency is terminated and/or recovery starts
( 8.4.3
- Control-RoomcTSC,or-EOF Communicator, repeat section 8.1.2 using the Follow-up Notification . Fact Sheet instead of the Initial Notification Fact Sheat.
NOTE: Read only the information on the Follow-up Information Fact Sheet which h,s been filled out. 9.0 ACCEPTANCE CRITERIA N/A l l 10.0 FINAL CONDITIONS All notifications have been logged on appropriate check lists. l -
1.0 REFERENCES
11.1 SP 69.007.01, Communications Equipment SP 69.009.01 Rev. B
/ / page 4
.- , - . _ - . - , - - . . . .. . . . . - . . - . . . . ~ . - . . . . . - , - . - . - . - - -. . ..
12.0 APPENDICES I , 12.1 Initial Notification Fact Sheet 12.2 Offsite Agency Notification Check List ! l ll 12.3 Personnel Injury Fact' Sheet - , i l 12.4 Personnel Injury Call Check List /- I .- 12.5 Follow-up Notification Fact Sheet 1 1 1 i r 5 . f i . I i 1 \ = } i t I j . i i i t-b L w t l. SP 69.003.01 nov. n l
/ / Page 5 8 1
APPENDIX _12.1 ., Date ano Ttrne of Hessage _ _ Time Date i I - Dl1TIAL NOTIFICATI0tl FACT SHEET
- 1. Nuclear Facility pr'oviding the initial report: .
/'I~/ Indian Point Unit 2 (Coned) ,. /$ Nine Mile Point Unit 1 (illHo)
@ Indian Point Unit 3 (PASHY) @ Fitzpatrick Plant (PASNY)
@ Ginna Station {RGtoE) @ shoreham cutco) ' -
57 otw-
- s. This M is h is not 'an exercise. ,.
- 3. Energench Classification: -
/ A/ Unusual Event / C / Site Area Emergency C Transportation Incidant ,
/ 8/ Alert f 0/ General Emergency , l f/ Other (Describe)~
- 4. Reported by[I7 tlame__
N _ Title .. ( , n.
- 5. There S has/ 8/ has not been a release of radioactivity to the
/ C / atmosphere f._0_/ ground (spill only) @ body of water
- 6. The release f A.] is continuing [5"7 has terminated [ C/ not applicable.
_ '7. Need for Protective Action: . A For Information Only. .There is no need for protective actions outside the Site Boundary. , B There IS need for Protective Action. (If applicable, affected area)
- include sectors or ERPAs) _ _ _ _ ,
- 8. Recomended Protective Acticos:
/_ A_/ Not applicable /C/Evacuationwithin _ alles
/ 8 / Shelter within , miles /T7 Other (or, for additional ;
informa tion) _ _
- 9. [A7Hindspeed _ miles per hour or _ _ _ meters per second, and fif'~/ Direction (from) _ degrees.
5 QGeneral weather conditions (sunny, rainy, etc.) _ _ ,
- 10. Neans of connunication contact, verification and/or additional information if different from pre-arranged comunications channels.
SP 69.009.01 Rev. B
- _ _ _ _ _ _ _ _ _ _ . _ - -_ n n ~o
s
.s y.
APPENDIX 12.2 N Page 1 of 2 s OFFSITE ACENCY NOTIFICATION CIIECK LIST (/ s
)
AGENCY COMIUNICATIONS MODE MESSAGE q
~
~
5, NAME OF RECEIVED INDIVIDUAL / CONTACTED PRIMARY PERSON ' AND VERIFIED ORGANIZATION TIME / INITIAL ALTERNATES CONTACTED TIME /TNITIAL
- 1. New York State / 1. Hotline f / - ; .
Emergency 2. NAUAS
~
Operations 3. Emerg. Organ. Center Call Phone
- 2. New York State / 1. Hotline /
Southern 2. Emerg. Organ. District Call Phone Office 1
- 3. Suffolk County / 1. Hotline / .
Emergency 2. NAWAS . Operations 3. Emerg. Organ. Center Call Phone NOTE:
)
NRC NOTIFICATIONS (#4 AND #5) TO BE PERFORMED BY CONTROL ROOM OPERATOR ONL t V .4 Nuclear '- " i
/ 1. Emers. Notif.
Regulatory System (ENS) Commission, Dedicated Line / Washington Office, 2. Emerg. Organ. Bethesda Call Phone
'5. Nuclear / 1. Emerg. Notif.
Regulatory System (ENS) Commission, Dedicated Line / Regional Office, 2. Emerg. Organ. King of Prussia Call Phone
- 6. U.S. Coast Guard _ / 1. Emer. Organ. /
Call Phone l l
- 7. INPO * / 1. Emerg Organ.
Call Phone /
- Da N0i' CALL Ir 1:"Ci'CC:CY l
l CLASSIFICATION IS UN11SUAL EVENT. i f~ ()) - SP 69.009.01 Rev. B
/ / Page 7 i
p ,
'w",
4
.. k
".', " 4 ~
x ' ' y ; ', . , '
%, t
- =
. . v
. , x. x 4
- s
,' s, , _ at 8
.: s. ,- m
'~,-
!y g s, -w
(,' ' APPENDIX 12.2 s, ,^ , ss
, s 7, sc
, x , A R Page 2 of 2 O , N t' lR- g' D' -
-e ~
s
-x, %.,i
. , ;s x y OFFSITE AGENCY NOTIFICATIOM.CUECK LIST - -
', * . , w.
? , +
i , i 's J , COMMUNICATIONS . MESSAGE AGENCY d \? MODE " N'ANE'0F RECEIVED s INDIVIDUAL / CONTACTED 4 %t PRIMARY ,/ PERSON AND VERIFIED
~ ORGANIZATION ^ r_r TIME /INITIAle;g ALTERN3TES CONTACTED TIME / INITIAL o
\'
s ( s s
,8. ' Radiation'^ 7>/_ b' ; - "
- 1. Emerg. Organ. ,
/
. MAnagementi t Phone Corporation.s ; 4
's Call,N-s I
s, ,- h.- , go s . ., __M, t a __ ' y .; .
~-
. T_s ,
'~%
r y y--
?g
,a w, y
-y
- 9. U.S. EPA - '/ s .; 1.# %ierg. Organ.
\[, , t 4 6 4
\ts (Call a
Phone / NM ---J T ** i
,D i
D h / 5 1.I Enterg. Organ. / .a 10.Dak.t.,of,[~
'-Ene sgy* _' y'!
' Call Phone i 1_
R.A;P. Teaxc , 2. Police Radio
~ 1, V ,
- e. \; ,. t s' ;
'*CATE ONLY tGLN ,VIRECTED DIT THE L' RADIATION PROTECTION'MANAUER 3
') ,. , . , . .b m
o k \ t
. . , y
.. , h ,, >
- l ,, - ,8 s i -4i ,t ,
' ~
t , 4. '. [ ' t
. , -( .
2 .. l i - i sx b
\ S
~
.s y 3
- m. q d.
? ,t 5 y g r-(' '
I., ~ \ ( s 'N
\,1 -
- s
, p< e
$~
~
> :; s~ . , N., i. ,
~
's ;s -
~
C s s., fL' 3? 4 SP 69.619.dl Rev. B ' ,_) . s I 'l / / Page 8 4 I
- 2 4
* ~xs.-'
_ (j
-- s g
4'
. > . - \ 's b s i
% (N \ l ., ) w N 4, ys s
) ')
,\
~ '
[" 5t' \ s [ , (t, c ,b;' o 3
. 1 , ,
t' l' k ( *
, --..i_--.4 I ,' %s _ -.. .
i , j .
- 1. .. ._ w,. k-1 - . - - - - - -
. , APPErDIX 12.3 PERSONNEL INJURY FACT SHEET tification for Ambulance Assistance (Usually Wading River Fire Department)
- 1. This is the Shoreham Nucicar Power Station. An injury involving person (s)
(number) } has occurred onsite which requires ambulance service. The individual (s) contaminated and will be transported to (are/are not) (hospital - usually Central Suffolk Hospital
- 2. .
(brief description of injuries)
- 3. Enter the station through the gate.
(east / west) Notification to: 1. Receiving Hospital ( Usually Central Suffolk Horpital)
- 2. Suffolk County Emergency Operations Center
( ') This is the Shoreham Nuc1 car Power Station. An injury involving person (s)
'v'
.(number) s nas occurred onsite which requires medical treatment. The individual (s)
__ contaminated and are being sent to (are / are not) l for treatment. l (hospital - usually Central Suffolk Hospital) l l
- 2. (Same as Item #2 above) .
. .t.
- 3. The entinated time of arrival at the hospital is hours.
(tire une N hr clock) l h 7% ( ) v SP 69.d@9.01 Rev. B
/ / Page 9
~ ~
APPENDIX 12.4 PERSONNEL INJURY CALL CIIECK LIST
~
CO)DIUNICATIONS MESSAGE AGENCY MODE NAME OF RECEIVED INDIVIDUAL / CONTACTED PRDIARY . PERSON AND VERIFIED ORGANIZATION TDIE/ INITIAL ALTERkATED CONTACTED TDfE/ INITIALS
- 1. ' Wading River / 1. Emerg. Organ. /
Fire Department Call Phone
- 2. Police Radio 2 Central Suffolk / 1. Emerg. Organ. /
IIospital Call Phone ,
- 2. Police Radio
- 3. Suffolk County * / __
- 1. Emerg. Organ. /
-Emergency Call Phone .
I Operations - Center C
- DO NOT NOTIFY SUFFOLK COUNTY EOC IF Tile INJURY INVOLVES CONTAMINATION AND OFFSITE TREATMENT s
l l l l t I O l SP 69.069.01 Rev. B
/ / Page 10
i 1
~ * *
' APPENDIX 12.5 y *e
- Page 1 of 3 g.
/^T U '
- 9. Type of actual or projected release and eatimateo duration and impact !
. times. .
a) Atmospheric Reicase Actual . Projected Date and Time Release Started r' ' Duration of Release hrs hrs Release Rate - cc/sec cc/sec Noble Gas Release Rate ' Ci/sec C1/sec Radioiodine Reicase Rate C1/se: Ci/sec Relesso lleight . m n Chemical and Physical Form Motcorology Data .
- tlind Speed m/sec ~
'Tlind Direction (Toward)
Temperaturo
. Stability Class .
Precipitation Time of Impact (Offsite) . Sectors Affected
, b) tlaterborno Roloase Dato and Time Release Started Duration of Reicase
__ hrs hrs Volume of Release ~ gal _ _ gal l Radioactivity Concentration uci/mi ~ uci/mi Total Radioactivity Released ci _ci Radio Nuclidos in Release
~
l Chemical or Physical Form Meteorology Data . Wind Speed - m/sec '. l l Wind Direction (Toward) . Time of Impact (Offsito) _
~
Sectors Affected c) Surface Reicate (Spill) Date and Time Release Occurred . Volume of Release Radioactivity Concontration u _= Tc:a1 P adioactivity Relea.;ed ' Radionuclides in Release
=
Chemical or Physicn1 Fom. Sectors Affected SP 69.009.01 Rev. B
/ / Page 11 o
, , s . m l -- ~ j
- APPENDIX 12.5 f ...' * . ..
. . . 3 * .
Page 2 of 3 l
. i FOLLOW:llP NOTIFICATIO!4 FACT SP.EET ,
l. The folloinng data represent the mo.it cdrrent and. acencata information, l projections and/or prognosis availabic at this time. , j Time ~ Date .
~
By . Title - , Telephone 14 umber -
- 1. Location of Emergency: stwehor>r Huchu. Pm SMim a
~
/ .
2 .- Emergency declared at -
. on (Time) (Date) .
.c
- 3. Emergency Classification: '
Q Unusual Event / Site Area Emergency
- p / Alert L_/GeneralEmergency
/ ;
- 4. Description of Initiating Event (s): ,
f v O c r . .-- on m s,3 + dnnairinns {
. t l
prognosis for Worsening or Termination of Emergency:
- 6. -
~
l 7. Emergoney Responso Nctions Undenvay: - l l . 8, Request for Offsite Support: l s SP 69.009.01 Rev. B -
/ / Page 12
. ~
* * . .. ; - APPENDIX 12.5
. ... I Paze 3 of 3_ _ _ ,
10, Doso Measurements and Projections ~ Projected _
' Actunt
- Site Boundary re/hr
- a) E/hr ~ Rem .
IfnoleBodyDesoPI5te mr/hr 10:01o Body Doso _mr/hr ~' ,:
~ ~ Rem -
Thyroid Doso Rata *
,. ~
Thyroid Dose # - Highest Sectors b) Projected Offsite s_ 2 Mile, 5 Miles _ _ ~ Whol.a Body Dose Rate (or/hr) -
~
lihoIo Body Doso (Rect) ~~
$ ~
_ ~ _. - ~ Thyroid Dosa Rate (mr/hr) ~ __ ~ Thyroid Doss (Rem) ~ _ ~] Soctors Affected
- 11. .
Recomended Protective '\Cti "S E . ww
= _
. b.
~
/ /
' Date Time
. . ' Emergency Director Approva.t 1 .
..-~.._..-.:.. ~-
'x ,. ,.
~
l . l
?. .
SP 69.003.01 Rev. B
// Page 13
,2e _ o.a , as, s na 4---*-' -= J ,_ m , _. -- - _
- u _ n _ _ _
f O THIS SECTI0fl IllTEllTI0tlALLY LEFT BLAtlK FOR FUTURE EXPAllSI0tl, O O l
Submitted: Approved: (Plant Manager) SP Number 69.010.01 Revision Date Eff. TPC TPC \ l
- CLASSIFICATION OF EMERCENCY ACTION LEVELS i
i See Attach eent 1) O O
. ' Submitted: SP Number 69.613.61 N pproved: Revision: A (Plant Manager)
Date Eff: INUSUAL EVENT 1.0 CONDITION 1.1 An UNUSUAL EVENT has been declared based on the occurrence of off-normal events which could indicate a potential degradation of the level of safety of the plant, as described in SP 69.010.01, Classification of Emergency Action Levels. 2.0 IMMEDIATE ACTIONS The Emergency Director (Watch Engineer, until properly relieved by a designated alternate) is responsible for implementation of the actions prescribed in this procedure. The Emergency Director may delegate responsibility for performance of the prescribed tasks to available personnel, except where otherwise specified in this procedure. 2.1 For All Initiating Events 2.1.1 Control Room Operator, implement corrective actions to contend with the situation and to nitigate possible deterioration in
. plant conditions in accordance with the SVPS Operating Procedures while simultaneously implementing this procedure. Perform any of the following as necessary: -
.1 Airborne Release - Step 2.2 C
h
.2 Waterborne Release - Step 2.3 [
.3 Fire / Explosion - Step 2.4
.4 Injury - Step 2.5
\
.5 Natural Event - Step 2.6 2.1.2 Control Room Operator, implement appropriate assessment actions.
Complete an Unusual Event Initial Notification Fact Sheet, (Appendix 6.1), using data derived from the initial assessment activities. e,1.3 o m r,1 R e . Operator, an - ' :re over tho cae,e/m rtv s"ste, the tollowing: 2.1.3.1 "The plant is in an Unusual Event condition" - repeat O d 2.1.3.2 The location or general area affected 2.1.3.3 Any operations / work to be halted
.- 2.1.3.4 Specific instructions to plant personnel as applicable.
fs 2.1.4 Control Room Operator implement SP 69.009.01, " Notifications" in order to: (b)
.1 Notify offsite agencies
.2 Notify additional station personnel as needed
.3 Notify the LILCO emergency response organization 2.2 For Initiating Event: Radioactivity Release to the Atmosphere 2.2.1 Inplant Radiation Monitoring Technician or designee initiate and continue offsite dose projection activities as necessary in accordance with SP 69.022.01, Determination of offsite Doses.
2.2.2 In-plant Radiation Monitoring Technician or designee, initiate an emergency onsite radiation survey in accordance with SP 69.021.01, Onsite Surveys. 2.2.3 In-plant Radiation Monitoring Technician or designee, initiate SP 69.026.01, Protective Act_fon Recommendation. 2.3 For Tnitiating Event: Liquid Radioactivity Release 2.3.1 In-plant Radiation Monitoring Technician determine the activity of the release by ef fluent nonitor reading, or by estimate in (h accordance with normal station procedure.
\'- .
2.3.2 In-plant Radiation Monitoring Technician initiate SP 69.024.01, Waterborne Release Dose Projection. 2.3.3 In-plant Radiation Monitoring Technician , initiate SP 69.026.01, Protective Action Recommendations. 2.3.4 In-plant Radiation Monitoring Technician obtain and analyze environmental samples, as necessary, in.accordance with SP 69.024.01, Environmental Samnie Collection During Emergency. 2.4 For Initiating Event: Fire /Exnlosion 2.4.1 Fire brigade members, perform fire fighting efforts in controlled areas in accordance with the SNPS Fire Plan. 2.5 For Initiating Event: Personnel Injury 2.5.1 First Aid Team, perform emergency measures for nersonnel injuries r muirini of fsite nedical treatment in accordance with SP 69.040.01, l'ersonnel _ Inj ury. SP 69.513.01 Rev. A
/ / Page 2 (J}
l
.' 2.6 For Initiating Event: Tornado / Earthquake / Storms / Flooding 2.6.1 Operations personnel, perform emergency measures in accordance
(T ( ,) with SNPS Emergency Operating Procedures (SP 29.xxx.xx series). 3.0 SUBSEQUENT ACTIONS 3.1 Complete a Follow-up Notification Form using the most current data available at the time the form is completed. 3.2 When offsite agencies call back, provide information from the Follow-up Notification Fact Sheet as applicable to the emergency condition. Accept calls and provide information to only those organizations listed on the notification call-list. Refer all other calls to LILCO public affairs personnel. 3.3 Appoint a records keeper and communication coordinator from available personnel. 3.4 Perform emergency measures in accordance with the appropriate Emergency Plan Implementing Procedures and Emergency Operating Procedures (SP 29.xxx.xx series). 3.5 If plant conditions deteriorate, reclassify the emergency in accordance with SP 69.010.01, Classification of Emergency Action Levels. 3.6 Continue emergency operations, including assessment activities, until f-~s such time as plant conditions have stabilized and other termination () criteria of SP 69.070.03, Termination and Recovery, have been satisfied. 4.0 FINAL CONDITIONS 4.1 Emergency measures are continuing for the Unusual Event, the emergency condition has been escalated, or the emergency condition has been terminated. 4.2 For initiating events related to Limiting Conditions of Operation (LCOs), the emergency condition can be considered terminated when the appropriate actions specified in the " action" section of the LCO have been taken, and all notifications have been completed. 5.0 DISCUSSION 5.1 Once an Unusual Event condition has been declared at SNPS in accordance with SP 69.010.01, Classification of Emergency Action Levels, this procedure guides the Emergency Director in the performance of major actions and provides reference to other applicable Emergency Plan Innlenearing Procedures for further actions and more detailed instructions. SP 69.013.61 Rev. A
/ / Page 3 0
L j . 5.2 In the event of emergency conditions not adequately covered by this i . procedure, the Emergency Director has the responsibility and authority ,
, to take whatever action he considers required to prevent injury to per- l sonnel or damage to the plant or to equipment and to place the plant in l 1 a safe condition. l l
6.0 APPENDICES 6.1 Initial Notification Fact Sheet 6.2 Follow-up Notification Fact Sheet 6.3 Action Checklist - Unusual Evant-Gas j 6.4 Action Checklist - Unusual Event - Liquid 1 l l i l l l i
- SP 69.913.61 Rev. A h / / Page 4 I
f f
. APPENDIX 6.1
.' Date ano Tims of Hessage -
Time Date
~
INITIAL NOTIFICATION FACT SHEET
- 1. Nuclear Facility providing the initial report:
$ Indian Point Unit 2 (Coned) $ Hine Mile Point Unit 1.(NIMo) '
/57 Indian Point Unit 3'(PASNY) @ Fitzpatrick Plant (PASNY)
@Ginna Station (RG&E) & Other
- 2. This M is $ is not an exercise. ,
.n '
- 3. Emergency Classification:
[A7 Unusual Event M Site Area Emergency O Transportation Incident J 4,,8,/ Alert & General Emergency f.f / Other (Describe)
- 4. Reported by _ _ $ __
., 5. The're $ has/ B/ has ground not been a release of radioactivity to the (spill only) E body of Water M atmosphere /_Q/ __
- 6. The release $ is continuing /B7 has terminated @ not applicable. .
Need for Protective Action:
' 7. ,,
3 A For Information Only. There is no need for protective actions outside .. the Site Boundary.
- 8 There IS need for Protective Action. (If applicable, affected areas include sectors or ERPAs) _ _ _ _ ,
- 8. Recomended Protective Actions:
h Not applicable /_C_/ Evacuation within __mfies
/ 8 / Shelter within _ miles / 0 7 Other (or, for additional informs tion) __
4
- 9. @ Wind speed __ miles per hour or ___
meters per second, and; ,, degrees. .
/T/ Direction (from) _
QGeneral weather conditions (sunny, rainy, etc.) __
- 10. Means of consnunication contact, verification and/or additional information if different from pre-arranged comunications channels. SP 69.913.01 Rev.A
/ / Page 5
_ _ _ _ _ __ _ Tricshme Number _or.Nethod _ _ _ _ _
r
' a . u
\ t __( *
~
~' * *
, ~{ APPENDIX 6.2 Page 1 of 3 FOLLO6 UP NOTIFICATION FACT SHEET O .
- V The following data represent the mon current and accurate information, projections and/or prognosis availabic at this time. ,
Time Date By . Title Telephone Number 1
*1. f.CCation of Emergency: Shoreha:a Nuclear Power Station ;
I.
~
-l l 2 .- Emergency declared at -
. on (Time) (Date)
- 3. Emergenes Classification:
l Q Unusual Event L/ Site Arsa Emergency i / Alert / / General Emergency
- 4. Description of Initiating Event (s): __
\
^
c r.. - ne piene ennM einns: '__ ~
- 6. Prognosis for 11orsening or Termination of Emergency: -
i l 7 Emergoney Response Actions Underway: , 8 ,. Request for Offsite Support: _ _ _ O : 8e ee ats ci
/ /
x< Page 6
^
^
,' .., APPENDIX 6.2 o- \
-i Page 2 of 3
() 9. Type, of actual or projected r61 ease and eatimatea duration and impact times: l a) Atmospheric Relesse Actual , Projected Date and Time Release Started Duration of Release
~
- hrs hrs Release Rate -
_ cc/sec cc/sec Noble Gas Release Rate Ci/sec Cf/sec Radioiodine Release Rate C1/sec Ci/sec Release Height . m a Chemical and Physical Form 4 Meteorology Data
. Wind Speed ~~
m/sec Wind Direction (Toward) Temperature Stability Class . Precipitation Time of Impact (Offsite) . Sectors Affected
, b) Waterborne Release l
Date and Time Release Started () Duration of Release
. Volur.e of Release
_ hrs gal' ,
~
brs _ 2a1 Radioactivity Concentration pci/mi uci/ml ! Total Radioactivity Released ci ci , Radio Nuclides in Release _
~
Chemical or Physical Form Meteorology Data Wind Speed '- m/sec ' Wind Direction (Toward) Time of Impact (Offsite) , Sectors Affected c) Surface Release (Spill) l Date and Timo Release Occurred ' , Volume of Release Radioactivity Concentration Iotal Radioactivity Released Radionuclides in Reicase Chemical or Physical Ford : O Sectors Affected _ l l SP 69.613.61 Rev. A
// Page 7 l
F
. . . APPErmIx 6.2 -
~ -
_.i Page 3 of 3 _ _- 10. Dose Heasurements and Projections ProIected_ Actual Site Boundary mr/hr a) cr/hr ~ Rem flhole Body Dese Rate
~ '
pr/hr 11 hole Body Dose _ mr/hr ] Rem Thyroid Dose Rata * , Thyroid Dose _ { __ Highest Sectors , b) Projected Offsite 20 Miles S Milos 2 Miles _ _
. ~
_ ~
~
'ilhole Body Dose Rato (mr/hr) _ ~
lihoIo Body Dose (Rem) ~
. ~
~
Thyroid Dose Rate (mr/hr) Thyroid Dose (Rem) ~~7 [ ] Sectors Affected
- 11. .
Reconnended Protective Actions:_ .
-w
/ /
* , Date Timo
- - Emergency Director Approval
~; - . . .... . . ..
..3
, \.
SP 69.013.L11 Rev. A
/ / Page 8
s Appendix 6.3 i CHECKLIST Note The use of this checklist is optional. It is provided as a convenience for the Energency Director. It need not be filled out, nor retained, UNUSUAL EVENT - GAS u. STEP OUTLINE INITIAL TIME 2.1.1 Implement corrective actions (Stop release) 2.2.2 Initiate and continue dose projection (69.022.02) 2.2.3 Initiate radiation survey (69.020.01) 2.1.2 Complete Initial Notification Form 2.1.3 Announce emergency 2.1.4 Notify on-call Emergency Director 2.1.4.2 Notify additional SNPS personnel for assistance f 3 5.4 Escalate to Ale'rt if necessary (Alert-Gas checklist)
! 2.1.4.1 Notify offsite authorities (69.009.01) 3.1,3.2 Complete follow-up notification 3.6 Terminate when termination criteria (69.070.03) have been met '
O f I SP 69.613.61 Rev. A
/ / Pnge 9 t
h
\. ' '
- Appendix 6.4 f.
. CHECKLIST I I
I T Note ; Nj The use of this checklist is optional. It is provided as a convenience for the Emergency Director. It need not be filled out. nor retained. ; { UNUSUAL EVENT - LIQUID
/
STEP OUTLINE INITIAL TITE ! 1 Implement corrective actions (Stop release) i l ! 2.1.1 2.3.2 Determine release i 2.1.2 Complete Initial Notification Form , 2.1.3 Announce emergency 2.1.4 Notify on call Emergency Director i 2.1.4.2 Notify additional SNPS personnel for 6 assistance l 1 2.1.4.1 Notify offsite authoritics (69.009.01) l i i Complete follow-up notification (m)
%./
3.1,3.2 i Terminate when termination criteria 3.6 (69.070.03) have been met I
,- s SP 69.d13.d1 Rev. A
) / / Page 10
( I s_ -
e 1 - Submitted: SP Number: 69.014.61 1pproved: Revision: A d (Plant Manager) Date Eff.: __ ALERT 1.0 CONDITION 1.1 An ALERT has been declared based on the occurrence of events which indicate an actual or potential degradation of the level of safety of the plant, as described in SP 69.010.01, Classification of Emergency Action Levels. _ 1.2 An UNUSUAL EVENT had been declared and emergency measures are being performed; and on the basis of subsequent information or upon a deterioration in plant conditions, the condition has been reclassified as an ALERT. 2.0 IMMEDIATE ACTIONS The Emergency Director (Watch Engineer, until properly relieved by a designated alternate) is responsible for implementation of the actions prescribed in this procedure. The Emergency Director may delegate responsibility for perforrance O of the prescribed tasks to available personnel, except where otherwise specified h in this instruction. 2.1 For All Initiating Events 2.1.1 Control Room Operator, implement corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions in accordance with Operating Procedures while simultaneously implementing this procedure. Perform any of the following as necessary:
.1 Airborne Release - Step 2.2
.2 Waterborne Release - Step 2.3 g Q$
.3 Fire / Explosion - Step 2.4
.4 Natural Event - Step 2.5 2.1.2 Control Room Operator imple'ent appropriate assessment actions.
Comnlete an Initial Notification Fact Sheet (Apoendix 6.1) using data derived f rom the init.al assessment activities. C.\ s - C) //w"? / f / x hg"
1 2.1.3 Control Room Operator announce over the page/ party system the following: () 2.1.3.1 2.1.3.2 The plant is in an Alert condition The location or general area affected 2.1.3.3 Any operations / work to be halted 2.1.3.4 Specific instructions to plant personnel as applicable 2.1.4 Control Room Operator impicment SP 69.009.01 Notifications in order to: 2.1.4.1 Notify offsite agencies 2.1.4.2 Notify additional station personnel as needed 2.1.4.3 Notify the LILCO emergency response organization 2.1.5 Emergency Director or designee, implement the following: 2.1.5.1 Operational Support Center Activation (SP 69.005.03) 2.1.5.2 Technical Support Center Activation (SP 69.005.02) NOTE: For an emergency situation where plant conditions are expected to deteriorate activate the Emergency Operations Facility O' , (SP 69.005. ) and the Emergency News Center (SP 69.005. ). i 1 2.2 For Initiating Event: Radioactivity Release i . 2.2.1 Direct Radiation Manager or designee to initiate and continue offsite dose projection activities as necessary in accordance with SP 69.022.01, netermination of offsite Doses. 2.2.2 Direct Radiation Manager or designee to initiate an emergency l onsite radiation survey in accordance with SP 69.021.01, i Downwind Surveys. 2.2.3 If the results of the onsite survey indicate the need, direct Radiation Manager or designee to initiate radiation surveys offsite in accordance with SP 69.021.01, Downwind Surveys, l and escalate the emergency classification as warranted. l 2 . 2 . '. Sasc-1 on the results of the downuind dose projection activities,
%!Stian Protect ion '% nam or designee reconmend an aporopriate protective action to offsite authorities as part of the initini
, and/or follow up notifications. Refer to SP 69.024.01, Protective l Action Recommendations". l l (~'% SP 69.614.61 Rev. A N_,) / / Page 2
2.2.5 If tha r2sults of ths rcdiction curysyn or if sres redicticn monitors indicate the need, Emergency Director or designee,
-s evacuate personnel from affected areas by implementing SP 69.030.01, Evacuations During an Emergency. SP 69.030.01 provides guidance as to when an evacuation should be implemented. If an evacuation is implemented, also perform as applicable:
2.2.5.1 Pmergency Director or designee account for personnel . by implementing SP 69.030.02, Personnel Accountability. 2.2.5.2 Radiation Protection Manager or designee, direct personnel monitoring efforts in accordance with SP 69.030.03, Monitoring of Personnel / Equipment During an Evreuation. 2.2.5.3 Radiation Protection Manager, direct search and rescue efforts in accordance with SP 69.080.01, search and Rescue. 2.2.5.4 Radiation Protection Manager or designee, direct re-entry efforts in accordance with SP 69.070.01, Re-entry. 2.2.6 If the results of the onsite survey indicate a dose rate at the site boundary (not the protected area fence) exceeding 20 mrem /hr or a possible accumulative dose of 170 mrem. Emergency Director, reclassify the emergency as a Site Area Emergency and perform emergency measures in accordance with SP 69.015.01, Site Area Emergency. () Immediately notify offsite authorities of the reclassi-fication of the emergency. 2.3 For Initiating Event: Liquid Radioactivity Release 2.3.1 Determine the activity of the release by effluent monitor reading, or by estimate in accordance with appropriate station procedures. 2.3.2 Radiation Protection Manager or designec, implement SP 69.024.01, Waterhorne Release Dose Proj ection. 2.3.3 Radiation Protection Manager nr designee implement SP 69.026.01, Protective Action Recommendations. 2 l* E97_.1,nitia ting Event : Fire / Ext'le aion 1.' 6 Fire b r i gmle n.:~the r s ::c d v - firefic.hting efforts in controlled areas in accordance with the SNPS Fire Plan. 2.5 For Initiating Event: Tornado / Earthquake / Storms / Flooding 2.5.1 Operations personnel perform emergency measures in accordance O' with SNPS Emergency Operating Procedures (SP 39.xxx.xx series). SP 69.614.01 Rev. A
/ / Page 3
3.0 SUBSEQUENT ACTIONS
- 3.1 Complete a Follow-up Notification Form using the most current data available at the time the form is completed.
(3} 3.2 When offsite agencies call back, provide information from the Follow-up Notification Fact Sheet as applicable to the emergency condition. Accept calls and provide information to only those organizations listed on the notification call-list. Refer all other calls to LILCO public affairs personnel. Provide updated or additional information to the offsite agencies as it becomes available. 3.3 Coordinate emergency response activities in the Technical Support Center and the Operations Support Center, keeping all LILCO support personnel apprised of the emergency situation. 3.4 Perform emergency measures in accordance with the appropriate Emergency Plan Impicmenting Procedures (SP 69.xxx.xx series) and Emergency Operating Procedures (SP 39.xxx.xx series). 3.5 If plant conditions deteriorate, escalate the emergency classification. Perform actions in accordance with the appropriate procedure. 3.6 Continue emergency operations, including assessment ' activities, until such time as plant conditions have stabilized and other termination criteria of SP 69.070.03, Termination and Recovery, have been satisfied. 4.0 FINAL CONDITIONS 4.1 . Emergency measures are continuing for the Alert, the emergency condition has been escalated / downgraded, or the emergency condition has been temminated. 5.0 DISCUSSION , 5.1 Once an Alert condition has been declared at SNPS in accordance with SP 69.010.01, classification of Emergency Action Levels, this procedure guides the Emergency Director in the performance of major actions and 7 provides reference to other applicable Emergency Plan Implementing Procedures for further actions and more detailed instructions. 5.2 Although this procedure assigns all responsibility to the Emergency Director, the various activities will be performed by the individual emergency managers. Initially, and until the TSC staffing is available, the Emergency Director will perform all functions. As the staffing arrives, the individual emergency managers will be responsible for performing activities assigned in SP 69.001.01, Emergency organizations. The EuerAcney Director will coordinate the overall response using this
& , gu th .
5.3 In the event of emergency conditions not adequately covered by this procedure, the Emergency Director has the responsibility and authority to take whatever action he considers required to prevent injury to personnel I or damage to the plant or to equipment and to place the plant in a safe C(N condition. SP 60.614.01 Rev. A
/ / Page 4
6.0 APPENDICES 6.1 Initial Notification Fact Sheet 6.2 Follow-up Notification Fact Sheet 6.3 Action Checklist - Alert-Gas 6.4 Action Checklist - Alert-Liquid SP 69.614.01 Rev. A
/ / Page 5 O
. . . APPF SiX 6.1 Date ano Tims of Hassage Time Date 4
( INITIAL NOTIFICATION FACT SHEET
- 1. Nuclear Facility providing the initial report:
/ A / Indian Point Unit 2 (Coned) [li7 Nine Mile Point Unit 1 (NIHo)
@ Indian Point Unit 3 (PASNY) / E / Fitzpatrick Plant (PASNY)
{
@ Ginna Station (RG&E) @ Shoreha m (ut.co)
W on>er-
- 2. This M is h is not an exercise. j
- 3. Emergency' Classification: -
i
/A7 Unusual Event /_Q./ Site Area Emergency C Transportation Incident
/ 8 / Alert L,,0/ General Emergency G Other (Describe) l.
- 4. Reported by @
Name N __ _ Title .. (( x :. .:
\ 5. There G has/W has not been a release of radioactivity to the '
& atmosphere /_0,_/ ground (spill only) S body of water
- 6. The release /_A] is continuing /_B./ has terminated M not applicable.
' 7.
Need for Protective Action: A For Infomation Only. .There is no need for protective actions outside the Site Boundary, , B .There IS need for Protective Action. (If app 1tcable, affected areas include sectors or ERPAs) ,_ , , _ _
- 8. Recomended Protective Actions:
/_A_/ Not appilcable / C / Evacuation within __ miles'
~
/ B / Shelter within miles / 0 7 Other (or, for additional '
informa tion)
- 9. M Wind speed _ miles per hour or meters per second, and !
$ Ofrection (from) _ degrees.
@ General weather conditions (sunny, rainy, etc.)
- 10. Means of coninunication contact, verification and/or additional information if different from pre-arranged comunications channels.
Thlephone Nimber or Hethod SP 69.014.91 Rev. A
/ / p 6 ,
. . s
_.f *
"" : APPENDIX 6.2 . g Page 1 of 3 F_OLLO'.GUP NOTIFICATION FACT SHEET The following data represent the most current and accurate information, projections and/or prognosis availabic at this time. ,
Time Date By . Title Telephone ilumber
- 1. Location of Emerjency: snwe:mne Wuk Pm sfahan .
~
-l
- 2. Emergency declared at *
. on (Time) (Date) ,
- 3. Emergency Classification:
Q Unusual Event U Site Area Emergency i / Alert / / General Emergency
- 4. Description of Initiating Event (s): .
c r..rvone pinnt ennetietnns; _
- 6. Prognosis for Worsening or Terraination of Emergency: -
7 Emergoney Responso Actions Underway: , 8 ,. Request for Off.11tc Support: O . SP 69.014.01 Rev. A
/ / Page 7
. _ _ _ . - ___a
f
~' * -
APYENDIX 6.2
Page 2 of 3
( 9. Type of actual or projected release and estimatea duration and impact .
. times:
i a) Atmospheric Release Actual ; Projected Date and Time Release Started hrs
~
Duration of Release hrs Release Rate . cc/sec cc/sec Noble Gas Release Rate Ci/sec C1/sec kadiciodine Release Rate C1/see C1/sec f Release Height a m
- Chemical and Physical Form Meteorology Data 4
. Wind Speed m/sec Wind Direction , _ _ , (Toward)
Temperature
. Stability Class .
Precipitation i Time of Impact (Offsite) _ Sectors Affected
, b) Waterborne Release Date and Time Release Started O brs
~
Duration of Release . __ hrs
- Volume of Release gal _ gal Radioactivity Concentration pci/mL uci/ml Total Radioactivity Released ci _ci Radio Nuclides in Release _ _
Chemical or Physical Form Meteorology Data . Wind Speed - m/34c Wind Direction (Toward) . Time of Impset (Offsite) Sectors Affected ' c) Surface Release (Spill) Date and Time Release Occurred _ Volume of Release Radi.cactivity Concontration
- - _ _Tntal Radioactivity Released Radionuclides in Release Chemical or Physient Fond O Sectors Affected _
SP 69.014.d1 Rev. A
/ / Page 8
APPENDIX 6.2
* ~ ~ ~ .
Pa,a,e 3 of 3 __.i ._
-- m =
10. Dose Measurements and Projections Projected
' Actual _
Site Boundary pr/hr a) ~
~
mr/hr ~ Rem [ tStole Body Dese Rnte ar/hr ilholo Body Dose ~ ar/hr ~ Rem
, l Thyroid Dose Rate Thyroid Dose _{ __
Highest Sectors b) Projected Offsite 5 Miles _ }0 Miles 2 glie3_ _ ~
'ilhole Body Dose Rate (mr/hr) ~ _
~
]'
teofo Body Dose (Rem)
~ _ ~
~
Thyroid Dose Rate (mr/hr) ] __ ~ Thyroid Dose (Rem) i _ ] _ Sectors Affected
- 11. ,
Recoraended Protectiva *\ctionst_, ww-O -
/
/ Time
' Date Emergency Director Approval
, \.
1 i . l l O SP 69.014.61 Rev. A
/ / Page 9
,m.. m.w an+rwnmvNtar+'am e " *"* "
, , . , , APPENDIX 6.3 I
CHECKLIST Note The use of this checklist is optional. It is provided as a convenience for the Emergency Director. It need not be filled out, nor retained. I Alert-Cas i STEP OUTLINE INITIAL TIME t 2.1.1 Implement corrective actions (Stop release)
- 2. 2.1 Initiate and continue dose projections (69.022.01)
. 2.1.2 Complete Initial Notification Form
- i 2.1.3 Announce emergency 2.2.2 Initiate onsite radiation survey (69.020.02) 2.2.5 Evacuate personnel if necessary (69.030.01) 2.1.4 Notify on-call Emergency Director 2.1. 4 Notify offsite authorities (69.009.01) 2.2.6 If dose rate at site boundary > 20 mrem /hr or possible accumulative dose of
- 170 mrem classify as Site Area Emergency 2.1.5 Activate Technical Support Center, Operations Support Center. Place Emergency Operations Facility and Emergency News Center on standby 3.1,3.2 Complete follow-up notification 3.6 Terminate when termination criteria (69.070.01) have been not O SP 69.614.dl
/ /
Rev. A Page 10 o
__4 . _ u- - APPENDIX 6.4 J', 4 h
. , \
l'
' 7
- 6 i \ a- ,, '
- w. . , \ I '
, 4 s i s% . CHECKLIS7 s\ ' ~s No e' ,
The Emergencyuse ofDirector. this checklist is optional.N It is provided as a convenience for the It need not be fillhJ out, nor retained. s , Alert - Liquid ( STEP OUTLINE . m. INITIAL TIME cs 2.1.1 Implement corrective actions (Stop release) f 2.3.1 Determine release (69.xxx.xx) 2.1. 2 ' ' Complete Initial Notification Form 2.1.3 Announce emergency 2.1.4 Notify on-call Emergency Director s 3s 2.1. 4 Notify offsitE authoritics (69.009.01)
. l .
2.1. 5 Activate Technical Support Center, Operations Support Center. Place j Emergency Operations Center and () Emergency News Center on standby 3.1,3.2 Complete follow up! notification 3.6 Terminate when termination criteria
- i (69.070.03) have bech met '
l i i i 1 SP 69.614.61 Rev. A
/ / Page 11 :
3
, t *.
- Submitted: SP Number 69.915.61 Approved:~ Revision: A (Plant Manager)
SITE AREA EMERGENCY 1.0 CONDITIONS 1.1 A SITE AREA EMERGENCY has been declared based on the occurrence of events
' which involve actual or likely failures of plant functions needed for the protection of the public, as described in SP 69.010.01, Classification of Emergency Action Levels.
1.2 An ALERT or UNUSUAL EVENT had been declared and emergency measures are being performed; and on the basis of subsequent information or upon a deterioration in plant conditions, the condition has been reclassified as a SITE AREA EMERGENCY. 2.0 IMMEDIATE ACTIONS The Emergency Director (Watch Engineer, until properly relieved by a designated alternate) is responsible for implementation of the actions pre-scribed in this procedure. The Emergarc; Director may delegate responsibility for performance of the prescribed tasks to available personnel, except where otherwise specified in this instruction. v 2.1 For_All Initiating Events 2.1.1 Control Room Operator, impicment corrective . actions to contend with the situation and to mitigate possible deterioration f.n plant conditions in accordance with the SNPS Operating Procedures while simultaneously implementing this procedure. Perform any
~
of the following as necessary:
.1 Airborne Release - Step 2.2
.2 Waterborne Release - Step 2.3
.3 Fire / Explosion - Step 2.4
.4 Natural Event - Step 2.5 2.1.2 Control Room Operator implement appropriate assessment actions.
Complete an Initial Notification Fact Sheet (Appendix 6.1) using data derived from the Initini assen ment activities. e
2.1.3 Control Room Operator, announca over the page/ party system ths following: 7s 2.1.3.1 The plant is in a Site Area Bnergency condition - Repeat
? I
\/~
2.1.3.2 The location or general area affected
-2.1.3.3 Any operations / work to be halted 2.1.3.4 Specific instructions to plant personnel as applicable 2.1.4 Control Room Operator, implement SP 69.009.01, " Notifications" in order to:
2.1.4.1 Notify offsite agencies 2.1.4.2 Notify additional station personnel as needed 2.1.4.3 Notify the LILCO emergency response organization 2.1.5 Emergency Director or designee, implement the following: 2.1.5.1 OSC Activation, SP 69.005.03 operational Support Center 2.1.5.2 TSC Activation, SP 69.00 .0 Emergency Operationa yacility. Activation 2.1.5.3 EOF Activation, SP 69.00 .0 Emergency Operations Facility Activation
\/ 2.1.5.4 ' ENC Activation, SP 69.00 .0 Energency News Center Activation 2.1.6 Emergency Director or designee, assenble station personnel for possible evacuation by implementing a Plant Evacuation in accordance with:
2.1.6.1 SP 69.030.01, Evacuations During an Emergency 2.1.6.2 SP 69.030.02, Personnel Accountabiligt 2.1.6.3 SP 69.030.03, contamination Control During Emergencies i 1 2.1.6.4 If personnel are found to be missing from accountability Emergency Director or designee implement SP 69.080.01, Search and Rescue. 2.1.7 Radiation Protection "anager or designec, direct itealth Physics vrmnel to perfo r vnd Stic nel a!rborne radioactivity survevs i at the designated assenbly areas. If the results of the ~ radiation surveys at the primary assembly areas indicate radiation levels in excess of 10 mrem /hr or gross airborne radioactivity (less noble gases) in excess of IE-9 pCi/ce, or if continued occupancy
% is expected to result in excess of 40 MPC-hours'for the isotopic s_,) mix less noble gases, relocate to another assembly area, or if necessary, implement a site evacuation in accordance with SP 69.030.01, Evacuations During an Emergencv.
SP 69.015.01 Rev. A
/ / Page 2
~
2.2 For Initiating Event: Radioactivity Release to the Atmocchere
,r~] 2.2.1 Radiation Protection Manager or designee, initiate and continue V offsite dose projection activities as necessary in accordance with SP 69.022.01, netermination of offsite noses.
2.2.2 Radiation Protection Manager or designee, initiate an emergency cnsite radiation survey in accordance with SP 69.021.01, Onsite Surveys. .f-2.2.3 If the results of the onsite survey indicate the need, Radiation , Protection Manager or designee, initiate radiation surveys offsite in accordance with SP 69.020.01, Downwind Surveys, and escalate the energency classification as warranted. 2.2.4 Based on the results of the downwind dose projection activities, Radiation Protection Manager or designee recommend an appropriate protective action to offsite authorities as part of the initial and/or subsequent follow-up notifications. Refer to SP 69.026.01, Protective Action Recommendations. 2.2.5 If the results of the onsite survey indicate a dose rate at the site boundary (not the protected area fence) exceeding 600 mrem /hr or a possible accumulative dose of 5 rem (25 rem thyroid), Emergency Director reclassify the emergency as a General Emergency and perform emergency measures in accordance with SP 69.016.01, General Dnergency. Immediately notify offsite authorities of the reclassification of the emergency. 2.3' For Initiating Event: Liquid Radioactivity Release 2.3.1 Liquid releases are not identified as initiating events for,a Site Area Emergency since it is unlikely to have offsite doses in excess of 170 mrem (any organ) due to the release. A liquid _ release could occur, however, concurrent with the events which initiated the Site Area Emergency. Corrective and assessment measures for liquid releases are provided in Section 2.3 of SP 69.014.01, Alert. 2.4 For Initiating Event: Fire /Exolosion 2.4.1 Fire brigsde members perform firefighting efforts in accordance
- with the SNPS Fire Plan.
2.5 Fo_r Initiating Event: Tornado / Earthquake /Storns/ Flooding 2.5.1 Onerations personnel nerf=. >mergency measures in accordance with SNPS F.nergency Oyrett i c Procedurea (SP xxx.xx serie='s. SP 69.615.01 Rev. A
/ / Page 3 V
' 3.0~ SUBSEQUENT ACTIONS gg 3.1 Complete a Follow-up Notification Form using the most current data availabic at the time the form is completed.
( ) 3.2 When offsite agencies call back, provide information from the Follow-up Notification Fact Sheet as applicable to the emergency condition. Accept calls and provide information to only those organizations listed on the notification ~ call-list. Refer,all other calls to LILCO public affairs. personnel. 3.3 Appoint a records keeper and communications coordinator from available personnel if one has not already been assigned. 3.4 Perform emergency measures in accordance with the appropriate Emergency Plan Implementing Procedures and Emergency Operating Procedures (SP 29.xxx.xx series). 3.5 Periodically disseminate information on the status of the onsite operations and conditions to the offsite authorities and to LILCO personnel in-the emergency response centers. In particular: 3.5.1 Notify offsite authorities of any significant (>100 mrem) i change in dose projections, or other significant changes in plant status. . 4 3.5.2 Periodically (about once an hour) provide a situation report to the LILCO representatives at the Emergency Operations Facility, () and to the LILCO public affairs staff at the Emergency News Center. Coordinate energ9ncy response activities in the LILCO emergency response 3.6 - facilities, keeping all LILCO support personnel apprised of the emergency situation. 3.7 If plant conditions deterior3tv, reclassify the emergency in accordance with SP 69.010.01, Classification of Emergency Action Levels. 3.8 Continue emergency operations, including assessment activities, until such time as plant conditions have stabilized and other termination criteria of SP 69.070.03, Termination and Recovery, have been satisfied. 4.0 FINAL CONDITIONS 4.1 Emergency measures are continuing for the Site Area Emergency, the emergency condition has been escalated / downgraded, or the emergency condition has been terminated. 5.0 Di5CU.sSION 5.1 Once a Site Area Energency condition has been declared at SNPS i.n accordance with SP 69.010.01, classification of Emerger.cy Action Levels _, this procedure guides the Emergency Director in the performance of major actions and provides reference to other applicable Emergency Plan [~] L./ Implementing Procedures for further actions and more detailed instructions. SP 69.015.01 Rev. A
/ / Page 4
52 Although this procedure assigns all responsibility to the Emergency Director, the various activities will be performed by the individual emergency managers. Initially, and until the TSC staffing is available, ()s (, the Emergency Director will perform all functions. As the staffing arrives, the individual emergency managers will be responsible for performing activities assigned in SP 69.001.01, Emergency organizations. The Emergency Director will coordinate the overall response, using this procedure as a guide. 1
-5.3 The Emergency Director is the only ndividual authorized to determine and reconmend a protective action to offsite authorities (directly or via Communications Coordinator). Therefore, the Emergency Director shall approve all initial and follow-uo notification messages for Site Area Emergency ar.d (hneral Emergency.
5.4 In the event of emergency conditions not adequately covered by this procedure, the Emergency Director has the responsibility and authority to take whatever action he considers required to prevent injury to personnel or damage to the plant or to equipment and to place the plant in a safe condition. 6.0 APPENDICES 6.1 Initial Notification Fact Sheet 6.2 Follow-up Notification Fact Sheet f-ss 6.3 Action Checklist - Site-Release (v) '
;P 60.015.01 Rm. A
/ / Page 5 O
, APPENDIX.,6.1 ,
Date ano Time of Massage ( O INITIAL NOTIFICATION FACT SHEET 1, Nuclear Facility providing the initial report:
$ Indian Point Unit 2 (Coned) @ Nine Mtie Point Unit 1 (NIHo) ;
/lI'7 Indian Point Unit 3 (PASNY) / E'7 Fitzpatrick Plant (PASNY) '
I
@ Ginna Station (RG&E) @ Shoreham (uzco) f B E 7 o m o-- l
- 2. This / U is /,,_B_/ is not an exercise. [
l
- 3. Emergenc Classification: ! i
/ A/ Unusual Event / C/ Site Area Emergency M Transportation Incident 4 ,8f Alert L,p/ General Emergency G Other (Describc)
- 4. Reported by/ A 7 Hame N ._
Title .. I l S. There N has/ 8 / has not been a release of radioactivity to the
/ C / atmosphere /_,_0_/ ground (spill only) S body of water i
- 6. The release /_A] is continuing / BBf has terminated @ not applicable. !
' 7. Need for Protective Action:
A For Infonnation Only. .There is no need for protective actions outside the Site Boundary. ,, I B -There IS need for Protective Action. (If applicable, affected areas l include sectors or ERPAs) _
- 8. Recomended Protective Actions:
/_ Aj Not applicable / C / Evacuation within _ miles l [8 7 Shelter withir$ niles / 0 / 0ther (or, for additional infonn tion)
- 9. @ Wind speed miles per hour or meters per second, and
/T/ Direction (from) __ degrees.
D General weather conditions (sunny, rainy, etc.)
- 10. Neans of communication contact, verification and/or additional information if different from pre-arranged comunications channels.
SP 6900.15.01 Rev. A IP lenhonn_Mumher_or_Me thod_ E '
u v -
~~
. APPENDIX 6.2
.g . ,
. ; Page 1 of 3 FOLLOW-UP NOTIFICATION FACT SHEET C
d The following data. represent tile most current and secucate information, projections and/or prognosis availabic at this time. , Time Date By . Title _ Telepitone (4 umber
- 1. Location of Emergency: snorehom fluck Pm Sta/ren .
- 2. Emergency declared at '.
on (Time) (Date)
- 3. Emergency Classification:
Q Unusual Event C/SiteAreaEmergency
- , / Alert / /Coneral Emergency
- 4. Description of Initiating Event (s): .
c- c. . ~ ,. n e mn+ cnnM +4nns. _ _ _ _ _ _ \ l
- 6. Prognosis for Worsening or Termination of Emergency:
l 7 Emergency Response Actions Underway: I
- 3. Re o,aest for Offsite Support:
- s O -
SP 64.015.01 Rev. A
/ / Page 7 l
APPENDIX 6.2 Page 2 of 3 ( 9. Type of actual or projected release and estimateo duration and impset . tim.es : a) Atmosoneric Release Actual_
. Projected Date and Time Release Started
! Duration of Release hrs hrs Release Rate cc/see cc/sec Noble Gas Release Rate Ci/see C1/sec Radioiodine Release Rate Cifsee C1/sec Relesse He'vit m m
- Chemical at.u f..ysical Form Meteorology Data
'. Wind Speed ~~
m/sec Wind Direction (Toward) Temperature Stability Class . Precipitation Time of Impact (Offsite) _ Sectors Affected
, b) Waterborne Release Date and Time Release Started s Duration of Release __ hrs brs gal __ gal Volume of Release Radioactivity Concentration uci/mi uci/ml Total Radioactivity Released ci _ _ci Radio Nuclides in Release Chemical or Physical Form Meteorology Data .
Wind Speed - m/sec Wind Direction (Toward) Time of Impact (Offsite) Sectors Affected -- c) Surface Release (Spill) l Date and Time Release Occurred Volume of Release Rad!.oactivity Concentration Ictal Radioactivity Released Radionuclidos in Release Chemical or Physient Ford () l Sectors Affected SP 69.015.01 Rev. A
/ / Page 8
o
~ .. .. APPE$ DIX 6.2 Page 3 or 3
__.. i 10. Dose Measurements and Projections Protected
' Actual Site Boundary str/hr a) ar/hr Rem WholeBodyDosekAte ~
mr/hr Whole Body Dose - f.r/hr ~ Rem Thyroid Dose Rate
}
Thyroid Dose _ Highest Sectors b) Projected Offsite 5 Miles, 10 Miles 2 Miles, _ 13hola Body Dose Rate (nr/hr) _ ~ WhoIo Body Dose (Rem) - Thyroid Dose Rate (mr/hr) _ _ Thyroid Dose (Rem) 1 i E _ _ Sectors Affected
- 11. Recommended Protective i\ctions t_
~
O -
=
l
/ /
Timo
' Date
- limergency Director P.pproval
.i.
S" 64.015.01 gey, 3
/ / Page o n aime gi 3. . w.=di*A 3rM.C4%Cf.MTM3t'sMimCFD3WAN7N
.. 5, Appendix 6.3 CllECKLIST
-~
Note
\_ /
The use of this checklist is optional. It is provided as a convenience for the Energency Director. It need not be filled out, nor retained. Site Area Emergency STEP OUTLINE INITIA1 TIME 2.1.1 Implement corrective actions 2.2.1 Initiate and continue dose projections (69.022.01) 2.1.2 Complete Initial Notification Form 2.1.3 Announce Emergency 2.2.2 Initiate onsite radiation survey (69.020.01) 2.2.3 Initiate Offsite-radiation survey
)
(69.020.02)
-g 2.2.4 Recommend protective actions (69.xxx.xx) -
y ) (to be included in all subsequent notifications) 2.1.4 Notify on-call Emergency Director i 2.1.4 Notify offsite authorities (69.009.01) 2.1.5 Activate Technical Support Center, Operations Support Center, Emergency Operations Center, and Emergency News Center
- 2. 2. 5 Reclassify if necessary l
3.1,3.2 Complete follow-up notification 2.1.7 Implenant station evacuation (69.030.01) (69.030.02) (69.030.03) _ _ _ . _ _ _ ______
- 3. 5 Periodically disseminate info to offsite authorities l
- 3. 7 If plant conditions deterioriate, escalate g) classification l' 3. 8 Terminate when termination criteria (69.070.03) have been net SP 69.015.01 Rev. A
/ / Page 10
l Submitted: SP Number 69.016.01
'Appresed: Revision: C ,
(Plant Manager) j
/ Date Eff.:
O l " i asmMHlj GENERAL EHERGENCY ' n qy ta
.[ ~
,,F conot m "
E E "fgp ,0 19 l ARL?-PRElMNhRY 1.1 A GENERAL EMERGENCY has been declared based on the occurrence of events which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity, as described in SP69 01%.01, Classification of Emergency Action Levels. 1.2 A lower classification emergency condition had been declared and emergency measures are being performed; and on the basis of subsequent information or upon a deterioration in plant conditions, the condition has been reclassified as a CENERAL EMERGENCY. 2.0 IMMEDIATE ACTIONS That individual charged with Overall Direction and Control (Response Manager or Emergency Director) is responsible for implementation of the actions prescribed in this procedure. That individual may delegate responsibility for performance of the prescribed tasks to available personnel, except where otherwise specified in this instruction. O j 2.1 For All Initiating Events 2.1.1 Control Room Operator implement corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions in accordance with Operating Procedures while simultaneously implementing this procedure. Perform any of the following as necessary:
.1 Airborne Release - Step 2.2
.2 Waterborne Release - Step 2.3
.3 Fire / Explosion - Step 2.4
.4 Natural Event - Step 2.5 2.1.2 Control Room Operator implement appropriate assessment. Complete an Initial Notification Fact Sheet (Appendix 6.1) using data derived from the initir.1 assessment activities.
- (if a . Fo :- those t,. ne rn i energency situation.1 protective actlans are pre-determined and located in Appendix 6.4 where O
U
~
l
- U'f}i; ;
pp. .
'r ; .!)/SW $ C ~~
3pg/g;g' l _
nsither tima nor adequate infor=atien exists to perform
, offsite dose assessment calculations.
/s 2.1.3 Control Room Operator, announce over the page/ party system the ( ,) following:
.1 The plant is in a General Emergency condition - repeat
.2 The location or general area affected
.3 Any operations / work to be halted.
.4 Specific instructions to plant personnel as applicable.
2.1.4 Control Room Operator, implement SP 69.009 01, " Notifications" in order to:
.1 Notify offsite agencies
.2 Notify additional station personnel as needed
.3 Notify the LILCO cmergency response organization 2.1.5 Emergency Director or designee, implement the following:
.1 OSC Activation, SP 69 003 03, Operational Support Center Activation
.2 TSC Activation, SP 69.005.02, Technical Support Center (si V'
Activation
.3 EOF Activation, Emergency Operations Facility Activation
.4 ENC Activation, Emergency News Center Activation 2.1.6 Emergency Director or designee, assemble station personnel for possible evacuation by implementing a Plant Evacuation in accordance with:
.1 SP 69 030 01, Evacuation During a Emergency
.2 SP 69 020.02, Personnel Accountability
.3 SP 69.030.03, Contamination Control During Emergencies
.4 If personnel are found to be missing form accountability Emergency Director or desigt se implement SP 69 080 01, Search and Rescue.
4 ' P lon Pr- >t e c t i on it' -ar or dest'. nee, direct itealth Physics p- =.o mw i to peri o r i c . ; .a:; ion and a irburae radioactivi.ty surveys at the designated assembly areas. If the results of the radiation \s / SP 69.016.01 Rev. C
/ / Page 2
~
k i surveys at the primary assembly areas indicate radiatien 1svals in '
, excess of 10 mrem /hr or gross airborne radioactivity (less noble gases) in excess of IE-9 uCi/cc, or if continued occupancy is gg expected to result in excess of 40 MPC-hours for the isotopic mix
() less noble gases, relocate to another assembly area, or if necessary, implement a site evacuation in accordance with SP 69.030 01, Evacuations During an Emergency. 2.2 For Initiating Event: Radioactivity Release to the Atmosphere 2.2.1 Radiation Protection Manager or designee, initiate and continue offsite dose projection activities as necessary in accordance with SP 59 022 01, Determination of Offsite Dose. 2.2.3 Radiation Protection Ibnager or designee, if the results of the onsite survey indicate the need, initiate radiation surveys offsite in accordance with SP 69 020.01, Downwind Surveys. 2.2.4 Based on the results of the downwind dose projection activities, Radiation Protection Ibnager or designec, recommend an appropriate protective action to offsite authorities as part of the initial and/or subsequent follow up notifications. Refer to SP 69.024.01, Protective Action Recommendations. 2.3 For Initiating Event: Liquid Radioactivity Release 2.3.1 Liquid releases are not identified as initiating events for a General Emergency since it is unlikely t o have offsite doses in f-~ excess of 170 mrem (any organ) due to the release. A liquid I release could occur, however, concurrent with the events which
\'j initiated the Cencral Emergency. Corrective and assessment j measures for liquid releases are provided in Section 2.3 of SP69 014 01, Alert.
2.4 For Initiating Event: Fire / Explosion . , 2.4.1 Fire brigade members perform firefighting ef forts in accordance. I with the SNPS Fire Plan. l l 2.5 For Initiating Event: Tornado / Earthquake / Storms / Flooding 2.5.1 Operations personnel perform emergency measures in accordance with SNPS Emergency Operating Procedures (SP 29.XXX.XX series). l 3.0 SUBSEQUENT ACTIONS 3.1 Complete a Foll';w up Notification Form using the most current data availabic at the time the form is completed. c
- 3. > >
,cittian to offsito 1: wies f ro, t% Follow-up Noti fication sa.< .ume t ws applicaale to the caergency coadition when sheet has been completed and time permit. Update the Follow up Notification Fact Sheet in
\ -) Sr 69.016 01 Rev. C
/ / Page 3
a timely manner and centinue to provide information to offsite estacias as needed. Accept calls and provide information to only those organizations listed on the notification call-list. Refer all other calls to LILCO public af fairs personnel. 3.3 Periodically disseminate information on the status of the onsite operations and conditions to the offsite authorities and to LILCO personnel in the emergency response centers. In particular: 3.3.1- Notify offsite authorities of any significant (>l9$ mrem) change in dose projections, or other significant changes in plant status. 3.3.2 - Periodically (about one an hour) provide a situation report to the LILCO respresentatives at the Emergency Operations Facility. 3.4 Coordinate emergency response activities in the LILCO emergency response facilities, keeping all LILCO support personnel apprised of the emergency situation. 3.5 Perform emergency measures in accordance with the appropriate Emergency
- Plant Implementing Procedures (SP 69.XXX.XX series) and Emergency Operating Procedures (SP 29.XXX.XX series).
3.6 Continue emergency operations, including assessment activities, until such time as plant conditions have stablized and other termination criteria of SP 69.079.03, Termination of the Emergency and Recovery, have been satisfied. 4.0 FINAL CONDITIONS 4.1 Emergency measures are continuing for the General Emergency, or the emergency condition has been downgraded or terminated. 5.0 DISCUSSION 5.1 Once a General Emergency condition hoi been declared at SNPS in accordance with SP 69.019 91, Classification of Emergency Action Levels, this procedure guides the Emergency Director in the performance of major actions and provides reference to other applicable Emergency Plan Implementing Procedures for further actions and more detailed instructions. 5.2 Although this procedure assigns all responsibility to the Emergency Director, the various activities will be performed by the individual emergency managers. Initially, and until the TSC staf fing is available, the Emergency Director will perform all functions. As the staffing arrives, the individual emergency managers will be responsible for performing activities assigned in SP 69.001.01, Emergency Organizations. The Emergency Director will coordinate the overall onsite response, using this procedure as a guide.
. a <!nt & ryd 4 :. t r _ . : .1 Directi.m :J !antrol (Respo m Manager or Lmergency Director) is the only individual authorized to i
O(,/ SP 69 916 91 Rev. C
/ / Page 4 s - - ,. - , - . - + . , - , - - , - . , .~ , ,. , _ - - - - , , , . - . - - , , , e < , , - -
)
determine and recommend a protective action to offsite authorities (directly or via Communications Coordinator). Therefore, that individual shall approve all initial and follow-up notification messages for Site Area Emergency and General Emergency. 5.4 In the event of emergency conditions not adequately covered by this J procedure, the Emergency Director has the responsibility and authority to take whatever action he considers required to prevent injusf to personnel . or damage to the plant or to equipment and to place the plant in a safe condition. 6.0 APPENDICES 6.1 Initial Notification Fact Sheet
' 6. 2 Follow up Notification Fact Sheet 6.3 Action Checklist - General - Release 1
I l l
+
[ [d
\
SP 69 016 91
/ /
Rev. C Page 5
i APPENDIX 6.1 Date and Time of Message Time Date Q INITIAL NOTIFICATION FACT StillET - IN NOTIFICATION PROCEDURE i
- 1. Nuclear Facility providing the initial report: ;
F Shoreham (LILCO) I
- 2. This _
A is B is not an exercise. l 1
- 3. Emergency Classification: '
A Unusual Event ', Site Area Emergency E Transportation Incident B Alert Ceneral Emergency 'l D F Other (Describe)
- 4. Reported by "
Al B Name Title
- 5. lhere A has B has not been a releauf radioactivity to the C
latmQhere 'D] ground (spill only) E body of water p6. The release [ s continuing [ has terminated C not applicable.
- 7. Needf'or Protective Action
- A For Information Only. There is no need for protective actions outside the Site Boundary. .
i B There IS need for Protective Action. (If applicable, affected areas include sectors or ERPAs) , , , ,
- 8. Recommended Protective Actions: l b Not applicable b Evacuation within miles I:E Shelter within miles { Other (or, for additional information) l I
P
- 9. _1. Utnd . p e e .1 niles per hour or _no ters per second, and I.
- t. < o ') deirees.
. -n.. .u_ Ge c cw
- t t has (cuany, rainy, etc.)__
- 10. Means of commun'ication contact, verification and/or additional information if dif f erent from pre arranged communications channe:s. ;
V Rev. C { SP 69.016 01
/ / Page 6 _f 9
1 i 6 t APPENDIX 6.2 . Page 1 of 3 FOLLOW-UP NOTIFICATION FACT SHEET (D
s_)Ihe following data represent the most current and accurate information, projections ;
end/or prognosis available at this time. l 1 Time Date t
'By Title Telephone Number l
- 1. Location of Emergency: Shoreham Nuclear Power Station
- 2. Emergency declared at on (Time) (Date)
- 3. Emergency Classification:
l
==e Unusual Event 7
== Site Area Emergency
_j Alert __ General Emergency
- 4. Description of Initinting Event (s): ,
- 5. Current Planc Conditions: _
- i. ch
\~.-l
- 6. Prognosis for Worsening or Termination of Emergency: .
- 7. Emergency Response Actions Underway:
1 i
- 8. Request for Offsite Support:
. -. - - - - - - _=.
O) SP 69 016.;* Rev. C
/ / Page 7
APPENDlX 6.2 Page 2 of 3
- 9. . Type of actual or projected release and estimated duration and impact times:
() a) Atmospheric Release Actual Projected Date and Time Release Started . Duration of Release hrs hrs [ Release Rate cc/sec cc/sec ; Noble Gas Release Rate Ci/sec Ci/sec Radioiodine Release Rate Ci/see Ci/sec ? Release Height m a , Chemical and Physical Form ___ Meteorology Data Wind Speed m/see Wind Direction ___ (Toward) . Temperature - Stability Class ; Precipitation f Time of impact (Offsite) Sectors Affected ; b) Waterborne Release Date and Time Release Started ' Duration of Release hrs hrs Vclume of Release gal gal Radioactivity Concentration pei/ml pei/ml Total Radioactivity Release ci ci
) ,
Radio Nuclides in Release : Chemical or Physical Form l Meteorology Data ; Wind Speed m/s,ec Wind Direction (Toward) , Time of Impact (Offsite) Sectors Affected c) Surface Release (Spill) Date and Time helease Occurred Volume of Release Radioactivity Concentration . Total Radioactivity Release Radionuclides in Release
~~
U 4!c il or Physical Forn
~ ~ ~~ ~ ~ ~'.. .- --' ".'
I SP 69.016 01 Rev. C i
/ / Page 8 t
APPENDIX 6.2 Page 3 of 3
- 10. Dose Measurements and Projections a) Site Boundary Actual Projected Whole Body Dose Rate ar/hr ar/hr Whole Body Dose mr/hr Rem Thyroid Dose Rate Rem Highest Sectors b) Projected Offsite 2 Miles 5 Miles 10 Miles Whole Body Dose Rate (mr/hr)
Whole Body Dose (Rem) Thyroid Dose Rate (mr/hr) Thyroid Dose (Re.) _ Sectors Affected
- 11. Recommended Protective Actions:
s
/ /
Emergency Director Approval Date Time or Response Manager Approval 6 l I I O SP 69 916.91 Rev. C
/ / Page 9
, APPENDIX 6.3 CllECKLIST l
t NOTE kY j ( The use of this checklist is optional. It is provided as a convenience for the Emergency Director and/or the Response !!anager. It need not be filled out, nor retained. General Emergency STEP OUTLINE Initial Time 2.1.1 Implement corrective actions 2.1.2 Complete Initial Notification Form 2.1.3 Announce Emergency
- 2.1.4 Notify offsite authorities (69 009 01) 2.1.5 Activate Technical Support Center, Operations Support Center, Emergency Operations Center, and Emergency News Cer.te r 3.1,3.2 O
Complete follow up notification k e i t 2.1.7 Implement site evacuation if a release ' is or is about to occur (69.030 01, .02, .
- 03) #
2.2.1 Initiate and continue dose projections (69 022 01) 2.2.2 Initiate onsite radiation survey l (69.020 01) 4 2.2.3 Initiate offsite radiation survey (69 020.01) ; 2.2.4 Recommend protectis actions (69.XXX.XX) 2.16 Use respirators if necessarv 3.> .et _a L ly . tis se: tin ic 2 v._- to off-Lte s authorities 3.6 Terminate when te rmi.tation. criteria (69 070 03) have been met SP 69 016 01 Rev. C
/ / Pase'10
O THIS SECTION INTENTIONALLY LEFT BLANK FOR FUTURE EXPNISION. O l O
Submitted: Approved: . (Plant Manager) SP Number 69.020.61 Revision 0 Date Eff. TPC ' TPC TPC DOWN WIND SURVEYS 1.0 PURPOSE To describe the procedures used by the Offsite Radiological Monitoring (ORM) Teams to conduct downwind radiological surveys and samplings during a radiological emergency. 2.0 RESPONSIBILITY 2.1 Overall - RPM /RCM or designees O 2.2 Manpower Assignment - OSC Coordinator 2.3 Briefing - RPM /RCM or designees at TSC/ EOF 2.4 Dispatching & Communication - Dose Assessment Staff #1 at TSC/ EOF 3.0 DISCUSSION 3.1 There are five major objectives that any one or a combination of them, may become the reason of sending out an ORM team. They are: (1) To provide or confirm radiological EAL data at the appropriate site boundary; (2) To track down or verify the location, size and direction of a radioactive plume if there has been an airborne release; (3) To provide or confirm dose or exposure rates inside the plume exposure zone, which are needed or projected by the Dose Assessment Group for protective action recommendations; Such dose concerns include whole-body and inhalation (thyroid), at the plume centerline and the plume
-s boundaries; V
dw1160002-02 03/18/82
, J
4 g-~g (4) To provide samples (air, soil, vegetaticn, etc.) taken t y,/ from within the plume exposure zone,- which will enable I the Rad / Chem Lab staff to determine the plume composition ; and hence aid them in the further analysis of the release ! characteristics; (5) To check surface contamination, if any, that are above acceptable limits, due to fallouts or precipitation from the plume within the plume exposure zone, for exposure i control and recovery planning. 3.2 Staffing and emergency organization are such that one ORM team will be available at ALERT level and two more will be available at SITE or GENERAL level. 3.3 Timing on when and locations of where, to send an ORM team, are important. Selection of survey and sampling locations should consider the prevailing wind speed, and the estimated time of plume arrival over the selected area vs. ORM team travel time under the circumstances. Routes planned for the team should avoid those saved for evacuation if it is in effect or soon to be. 3.4 If extended duty cycle is anticipated, the Dispatcher should consider and coordinate efforts to relieve field teams at
~
reasonable time periods. He may also exercise his judgment to ('m,N) send special dispatch to meet a team in the field to: 3.4.1 Retrieve air or other environmental samples for detailed lab isotopic analysis to be performed timely, and/or 3.4.2 To replenish the team with needed fresh supplies, while keeping the team in a mobi34 field position. 3.5 Summary of overall Sequence of Actions: 3.5.1 RPM /RCM/ designee issues an ORM request to the Dispatcher; 3.5.2 The Dispatcher calls the OSC Coordinator for manpower / team assignment; 3.5.3 Team report to the TSC (or EOF) for briefing; 3.5.4 After briefing, team members pick up equipment and radio at the Main Security Bldg. (or EOF) and perform pre-deployment checks of equipment and vehicle; (3 (.) dw1160002-02 03/18/82
r~w 3.5.5 Before departure, team establishes radio (,,)g communication with the Dispatcher and then proceeds according to preplanned routes to the survey area; 3.5.6 Upon termination of an ORM mission, team returns to the site (or EOF) to submit survey records to the Dispatcher (the Dose Assessment Group) and turn in samples to the Rad / Chem Lab, check fcr equipment contamination and take note of individual exposure records. 4.0 PRECAUTIONS N/A 5.0 PREREQUISITES 5.1 An ALERT or higher Emergency Classification has been reached and an ORM request has been issued by the RCM/ RPM or their designees to a designated dispatcher. 5.2 The dispatcher, or the RPM /RCM/ designee himself, has gathered the necessary information to brief the team (see Attachment 1, ORM Briefing Form). 5.3 Emergency ORM Kit and proper communication means are available to the team. 6.0 LIMITATION AND ACTIONS 6.1 Site-responsible ORM activities are generally limited to within the 10-mile EPZ zone. 6.2 For SITE and GENERAL emergencies, at least one ORM team must be deployed within 60 minutes of the first classification of such emergencies. 7.0 MATERIAL AND EQUIPMENT See Attachemtn 2, Offsite Downwind Survey (ORM) Kit Inventory. 8.0 PROCEDURE 8.1 RPM /RCM/ Designee 8.1.1 Check that Prerequisites 5.1 and 5.2 are met. If no dispatcher has been on duty, assign one. Dose Assessment Staff #1 normally will be designated as the Dispatcher. 8.1.2 Contact OSC Coordinator (Ext. ) for formation of an ORM team, and have team members assemble at the TSC (or EOF) for briefing. (~')
%)
dw1160002-02 03/18/82 j
4 t' () 8.2 RPM /RCM/ Designee or ORM Dispatcher 8.2.1 Complete Attachment 1 to the fullest extent possible. (See 3.1, 3.3, 8.2.4, 8.2.5 and 8.2.6). 8.2.2 On Attachment 4, outline a route leading out from the site (or EOF) to the intended ORM/ Survey area to be followed by the team. 8.2.3 Briaf the team according to Attachment 1. Describe the release situation and types of survey / sampling desired over the survey area. 8.2.4 Protective Eculpment
~
A. Instruct team members to put on Full-face Mask when projected I-131 concenyratiogs at downwind survey sites exceed 3 x 10 C1/m . Obtain an estimate of this concentration by the product of I-131 release rata in Ci/see from the gtack and the appropriate X/Q in units of sec/m for the survey area. For ORM activities near the site boundary, use Full-face mask protection for all emergencies where an airborne release is known to have happened or is impending. B. For additional protection against thyroid exposure to radiciodines, execute SP #69-051,
" Thyroid Blocking," when either one of the following conditions is met, to determine whether there is a need for KI:
- a. when In-plant Radiological EAL's indicate GENERAL EMERGENCY release level, or
- b. when projected downwind,gurvey 3 "#** ~
concentration is 3 x 10 Ci/m or greater. C. Require donning of Hoods, Booties, Coveralls, and Gloves when airborne release occurs and precipitations prevail. Use judgment in other Cases. 8.2.5 Exposure and Personnel Dose Limits A. The following 10CFR20 limits apply to the ORM Teams for their survey / sampling activities: W.B. Quarterly: 3 rems p-, W.B. Annual: 5 rems t s s-dw1160002-02 03/18/82
6 [~')
\/
provided that Form NRC-4 and the 5 x (N-18) criteria are satisfied; otherwise, use 1.25 rems as the W.B. Quarterly limit. B. If for any reason the above limits must be raised, refer to SP #69.050, " Radiation Doses During An Emergency," for authorization and limits. 8.2.6 Communications A. Assign each team a radio channel. B. Remind team te radio in prior to departure to report team color code ID (from the Survey Kit). C. ORM Dispatcher, use the following in radic communication to identify.self: At TSC: "Shoreham Dispatcher TSC" At EOF: "Shoreham Dispatcher EOF" 8.2.7 After the Fric'ing, designate a Company vehicle for the team : y i ud over the key.
, (' 8.3 ORM Team Members 8.3.1 ORM Tech. (Team Leader)
- ORM Tech. has the responsibility of operating the Survey and Sampling equipment to obtain required results.
8.3.2 ORM Asst. (Team Member) ORM Asst. has the responsibility of driving, logging > results, and radio communication. Give assistance to the ORM Tech. when situation requires. 8.3.3 Make sure at this point that survey points and routes to be taken are marked on Attachment 4, and that all needed information on Attachment 1 are filled out. 8.3.4 Proceed to the Main Security Building to sign out an Emergency Downwind Survey Kit and perform: A. Inventory Check B. Operations Check 8.3.5 Replenish any missing itens from the inventory list. () 1 I Install batteries if necessary. Perform source 4 ' dw1160002-02 03/18/82
4 () checks to observe proper meter response. Check equipment calibration stickers. 8.3.6 Use an AC source to check the TCS EAS-1 Air Sampler motor. Do not put on the filter canister. I 8.3.7 Log pre-survey pocket dosimeter readings on Attachment 1. 8.3.8 Don protective clothing and dosimeters as required. 8.3.9 Proceed to the survey vehicle. Check for gas, cigarette lighter socket, lights (if after dark) and operability. Start the engine and with it on, plug the TCS EAS-1 Air Sampler (w/o the filter) cable into the cigarette lighter and observe proper running (it should sound like a small vacuum cleaner). 8.3.10 ORM Asst., establisa radio communication with the Dispatcher, report the Team's ID (color code on the Survey Kit picked up) and that the team is ready to roll out. 8.4 Survey - ORM Team (') 8.4.1 Proceed to the survey point following marked routes on Attachment 4. 8.4.2 While enroute: keep a survey instrument on and begin recording periodic open-window readings of 1 mR/hr or greater on Attachment 3. (Assign a number to such non-fixed points sequentially, mark the location and exposure rate reading on the map, then enter the point number assigned and the exposure rate onto Attachment 3). Report any abnormal events or conditions to the Dispatcher via radio. 8.4.3 At the survey point, report arrival to the Dispatcher with time and survey point number. 8.4.4 If plume tracking is not required, proceed to step 8.4.7. 8.4.5 If " Plume Center Exp/ Dose Rates 6 Location" (item 10.(1) on Attachment 1) is checked. continue driving until the dose rate (open-window) appears to peak and begin to decrease. Return to the peak concentration area, b U dw1160002-02 03/18/82
9 () 8.4.6 Report the maximum plume U.B. dose rate measured at 4 feet-above the ground and the measurement location to the' Dispatcher immediately, and mark this location on the map as well. 8.4.7 At the first survey location,'obtain gamma measurements (closed-window) at 3 inches and 4 feet above the ground, d record these readings on Attachment 3. A. If the 4' reading is noticeably higher than the 3" reading, it should be assumed that the predominant gamma source is the airborne plume. B. If readings increase with decreasing height above the ground, assume that source is on the surface. In this case, take several smear samples (with gloves) over a 4" x 4" area of the ground, and/or a soil sample when condition permits. Use a plastic bag for the soil sample and fill out a label to tag the bag. Label the coin envelopes for the smears with proper ID information. C. Periodically check beta reading at 3" and 4' above ground with probe window open. Record say readings significantly different from the window-closed readings. 8.5 Air Sampling - ORM Team 8.5.1 Obtain air sample in plume center or at the fixed survey point as required (Attachment 1, item 10). 8.5.2 Leave car engine running, plug in the TCS EAS-1 Air Sampler to run it for a 1 min. warm-up period without the filter canister. 8.5.3 Use a quarter or equivalent, pry open the quart can containing the canister, turn off the warmed up sampler and center the canister over the suction opening on the side of the sampler. Stretch the clastic retainer over the outer end of the canister and make sure the fit is tight. 8.5.4 Sampler should be placed or held about 4 feet above the ground. Use top of vehicle away from its exhaust pipe side if desired. O dw1160002-02 03/18/82
. 1
) 8.5.5 Set the timer for 5 minutes (rotate dial past the 5
("'/ x_ min, mark then turn back), turn on the sampler, and ' adjust the flow rate to 5 CFM. Use a wrist watch to verify run time is 5 min + 6 seconds. 8.5.6 When the air sample is completed, carefully remove the canister from the sampler and put it in a plastic bag. Avoid contacting the white filter cloth outside around the bare filter. Record start /stop times and flow rates on Attachment 3. 8.5.7 Connect the brass-shell GM-1 probe with a cable to the RM-14 count rate meter " DETECTOR" input BNC. Switch " RESPONSE" to " SLOW". At this position, i allow 20 seconds meter response time at each j measurement. 8.5.8 Use the above setup, measure the background at 4 feet above the ground and inside the vehicle. Use the spot with lower background for the following measurements. Record this lower background cpm on Attachment 3. 8.5.9 Insert the GM-1 probe into the center hole of the canister and downscale the RM-14 as necessary. j Record the stabilized cpm reading on Attachment 3. 8.5.10
, Carefully remove the white fiber cloth which'is wrapped around the canister by pulling the red tape on the top rims of the canister. dold the canister in the plastic bag while doing this to avoid contacting the cloth, and to prevent silver gel crystal bits from falling out after the cloth wrapping is removed.
8.5.11 Return the fiber cloth to the quart can. Repeat step 8.5.9 on the bare canister and record the reading on Attachment 3. 8.5.12 Replace the bare canister with the plastic bag into ! the quart can. Put a label marked with the proper j time, date, sample # and location flow rate information on the sealed can. Air sample #'s should be assigned sequentially. 8.5.13 Report the three epm readings measured with the GM-1 probe : the background, the filter / canister cpm, and the bare canister cpm, to the Dispatcher by radio. 8.5.14 If plume tracking is not required, go to step 8.6.1 below. Otherwise, continue to drive through the plume and identify the other boundary of the plume (exposure rate, window open, at approximately dw1160002-02 03/18/82
1 mR/hr). At this boundary, record and report the [\d) exposure or dose rate measured with the location to the Dispatcher, j 8.6 Continuation - ORM Team 8.6.1 Check personnel pocket dosimeters readings and number of canisters remaining before continuing on. Report any overexposure or shortage. 8.6.2 Continue on to the next survey point as preplanned and repeat steps 8.4 through 8.6 or as otherwise directed by the Dispatcher.
- 8.7 Conclusion of Survey - ORM Team 8.7.1 When all survey and sampling activities are completed and the team receives no further ORM request through the Dispatcher, or the team is relieved by a second team, conclude the mission and return to the station unless instructed otherwise by the Dispatcher.
8.7.2 Upon arrival, notify the Dispatcher and take the
- site access road near the LILCO 69KV substation.
Stop before the substation and perform a I )~ contamination check of the vehicle (inside and
' '- outside) using the RM-14/HP-210.
8.7.3 If gross beta and gamma counts exceed 50 cpm above tne background, call in and wait for decontamination or other instructions / assistance from the Dispatcher (Reference SP #69.030, " Contamination Control During Emergencies"). 8.7.4 If vehicle checks out clean, return to the Main r Security Building. 8.7.5 Remove protective clothing. Bag clothing, used masks and equipment, suspected or being contaminated. Replenish Survey Kit items and return it in l
- ready-to-use condition.
t 8.7.6 Frisk out each other using the RM-14/HP-210. Frisk samples brought back to check for unusually high deposits before transporting to Rad / Chem Lab area for analysis. I 8.7.7 Send all samples and bagged items in 8.7.5 to the
- Rad / Chem Lab.
O \ _9 dw1160002-02 03/18/82 i .__ . _ _ , , , . - _
8.7.8 Record post-survey dosimeter' readings on Attachment 1, cnd send all records and data sheet to the Dispatcher (Dosc Assesment Group). 8.7.9 Report back to the OSC Coordinator. Mission completed. l 8.7.10 If team is to return to EOF, request suitable locations to perform steps 8.7.2 through 8.7.7. 9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS 10.1 The Dispatcher shall examine all records and data sheets turned in by the team, make copies of those needed for dose assessment activities and forward all records to the
-Administrative Section for filing in accordance with permanent plant procedures.
10.2 Rad / Chem Lab and Health Physcis: All field samples, contaminated clothing and equipment should be disposed or decontaminated according to regular plant procedures. I 11.0 REFERENCE
- 1. LILCO Shoreham Nuclear Power Station Emergency Plan, Rev. 1, 1/11/1982.
- 2. Code of Federal Regulations. Title 10, Part 20, Revised as of 1/1/1981.
! 3. LILCO Shoreham Procedure SP #69.050, " Radiation Dose During An Emergency." , 4. LILCO Shoreham Procedure SP #69.030, " Contamination Control During Emergencies."
- 5. LILCO Shoreham Procedure SP #69.051, " Thyroid Blocking."
- 6. Eberline llealth Physics Catalog, 1981 edition.
- 7. TCS Industries Instruction Manual for Emergency air Sampling System, 1981 edition.
12.0 ATTACIDIENTS
- 1. Offsite Radiological Monitoring (ORM) Briefing Form
! 2. Offsite Downwind Survey (ORM) Kit Inventory dw1160002-02 03/18/82 _- =
t , i I i
- 3. Offsite Emergency Survey Data Sheet
- 4. Offsite Downwind Survey (ORM) Map (Later) i I
f 1 i 1 r l 1 i i i .
; e l
l 1 l l . i l 4 k l9 I i
, I dw1160002-02 03/18/82 i
ATTACHMENT 1 OFFSITE RADIOLOGICAL MONITORING (ORM) BRIEFING FORM
}
- 1. Date: Time: Briefing at:
- 2. Survey reguested by: Briefed by:
- 3. ORM Dispatcher: Back-up Tel #:
- 4. Team Radio Ch. Team ID: "Shoreham "
- 5. Alternate Connunication Tel/#:
RPM-TSC: RCM-EOF: C.Rm:
- 6. a. Primsry dw Sector (letter): Adjacent Sectors: ,
- b. ORM/ Survey Locations / Points:
- 7. Projected WB dose rates at survey area (if available):
At ORM Pt Sector Dist mi, D/R mr/hr At ORM Pt Sector Dist mi, D/R mr/hr At ORM Pt Sector Dist mi, D/R mr/hr
- 8. Team member names & authorized doses (rem):
ORM Tech. , dose rem ODI As s t. , dose rem
- 9. Protective Equipment (check applicable):
(1) Dosimeters (200 mR & SR) (5) Glove Other (2) TLD (WB) (6) Bootie (3) F.F. Mask W I/P Canister (7) KI (4) Coverall (8) Hood
- 10. ORM data to be collected:
(1) Plume Center Exp./ Dose Rates & Location l (2) Plume Center Air I/P Sample l (3) Plume Boundaries down to 1 mR/hr
- (4) Other (Specify) i l 11. Team dosimeter readings (Before/After Mission)
ORM Tech. (200 mR Scale) / ; (SR Scale) / ORM Asst. (200 mR Scale) / ; (SR Scale) /
- 12. Special instructions:
i dw1160002-02 03/18/82
ATTACHMENT 2 (~N OFFSITE DOWNWIND SURVEY (ORM) KIT INVENTORY 'mJ
- 1. (1) Eberline R0-2A
- 2. (1) Victoreen 496 w/HP-270 Probe
- 3. (1) Eberline RM-14 w/HP-210 Probe
- 4. (1) TCS EAS-1 Air Sampler w/one GM-1 Probe & 3 Canisters
- 5. (6) Spare TCS Air Sampling Cansiters
- 6. (1) Shield Assy w/Sil-4 Sample :lolder
- 7. (100) Smears & Envelopes
- 8. (50) Plastic Sample Bags with Labels
- 9. (1) Check Source
- 10. (2) Flashlight w/ Spare Bulb
- 11. (1) Portable 2-Ray Radio
- 12. (1) Roll of Dimes, 50 per Roll
- 13. (1) Roll of Masking Tape
- 14. (1) Clipboard with;
- a. This Survey Procedure
- b. Completed ORM Briefing Form
- c. Survey Locations Diagram (Map)
- d. (5) Survey Data Sheets (Blank)
- e. (2) Writing / Marking Pens
- 15. Protective Equipment
- a. (2) 0-200 mR, (2) 0-5R Pocket Dosimeters
- b. (2) Personnel TLD, (1) Control TLD
- c. (1) DRD Dosimeter Charger
/} \s > d. e. (2) F.F. Ultraview Mask w I/P Filter Canister (1) Vial of KI
- f. Protective Clothing, 2 each, of
- Coveralls
- Pairs of Gloves w/ Liners
- Pairs of Booties
- Hoods
- 16. Environmental Station
- (1) Key
- (2) Replacement TLD
- (2) Replacement Silver Zeolite Filters
- (2) Replacement Particulate Filters
- 17. Spare Batteries, 4 each, of
- AA Size
- A Size B Size
- C Size
- D Size
/7 k i tj dw1160002-02 03/18/82
l 1
. OFF-SITE EMERGENCY SURVEY DATA SHEET
- 1. Team Members: ,
Date: em ( ,) 2. Time Sur/ey Started Time Survey Completed
- 3. Air Sancie Data 4. Dose Rate Measurements AIR SAMPLE 8:
Location (mark mar O sal C vv HT. I suavey exe. stare . eTu r quos m Canister e P o e *a i Len R/hr) r.x (en r% v") e Time: Star:J5:ap / Ficw Rate: Start /Stop / j Area Backgrcund icpm; y Filter / Canister Reading (cpm 1
- Bare Canister Reading (cpm) *
- REPCP,T THE LAST THREE VALdES TO THE Digntchs ;
AIR SAMPLE *: ; i. Location (mark map) Canister # Time: Start /Stop / () Flow Rate: Start /Stop Area Background (cpm)
/
l Filter / Canister Reading (cpm) 4 Bare Canister Reading (cpm) , '
- REPORT THE LAST THREE VALUES TO THE i DISPA'IO!FR ,
I AIR SAMPLE #: , Location (mark map) , Canister # Time: Start /Stop / Flow Rate: Start /Stop / Area Background (cpm) _
- l
{ Filter / Canister Reading (cpm) g [ Bare Canister Reading (cpm) , f
- REPORT THE LAST THREE VALUES TC THE
- DISPATUER l( Attachment 3
' ' ' Sub. ' t te d :
. Approved: (Plant Manager) .- .. O -'
~
DRAFT-PREllMlllARY , SP Number 69 922 91 Revision: A Date Eff.: TPC TPC
'TPC DETERMINATION OF OFFSITE DOSES O
1.0 PURPO'SE The purpose of this procedure is describe the method to determine offsite doses. 2.0 RESPONSIllILITY The RPM /RCl1 shall be responsible for the implementation of tnis procedure.
.c t \
~
(Ty b b ,e an a O j)/ h ti /, j6 _ - __ - _____ __. \
i 3.0 DISCUSSION
, 3.1 This procedure is used to determine offsite doses based upon short term, g- g abnormal release conditions. The dose calculations are based upon finite ,
( j cloud analyses. i 3.2 There are two methods described in this procedure. One makes use of the computerized radiation monitoring system (RMS), while the other is a manual method to be used in cases of RMS failure. 3.3 The computerized RMS method described in the procedure assumes that the software is running in the ACCIDENT mode. This mode is selected either manually or automatically by the RMS. It is important to note that initial dose assessment, prior to grab sample analyses, is based upon an assumed inventory mixture of nuclides (i.e. LOCA, fuel handling). 3.4 The manual methe. described in this procedure employs the use of nomograms for dose assessment. There are ten (10) nomograms from which to select. , Each nomogram is based upon assumed LOCA nuclide release mixtures. When using this method, it is important to understand the bases and assumptions described on each nomogram. 3.4.1 Only whole body dose calculations are provided for the normal station ventilatinn exhaust monitor. These doses assume 100% noble gas LOCA mixtures. 3.4.2 Both whole body and thyroid dose calculations are provided for the reactor building standby ventilation system monitor. These doses assume 100% noble gas LOCA mixtures for the whole body, and 25% halogen LOCA mixtures with 99% filtration for thyroid doses. 3.5 Topics covered in this procedu.e: Page 8.1 Determination of offsite doses using the 3 comuterized radiation monitoring system 8.2 Determination of offsite doses using the 3 nomograms 4.0 PRECAUTIONS N/A 5.0 PREREQUISITES
- 's, 4
!I.. -a = 1.4 % .*d h . 't 4b 55. . I o.1 t'e r soa ne l us ing '.'. p r mW . 4 .m ! he a.: : r e a: .. hm, for the assumed nuclido mixtures uw1 la the d w calculatLans.
() Se 69.022.01
/ /
Rev. A Page 2
I i
- 7.0 t!ATERIALS AND EQUIPMENT
. 7.1 Radiation Monitoring System
() . O PROCEDURE l
\- /
l 8.1 Determination of of fsite doses using the computerized radiation monitoring j system. (RMS) : l4 (LATER) i 8.2 Determination of offsite doses using the nomograms. ! 8.2.1 To calculate the gross release rates of radioactive isotopes from the station vent or the RBSVS exhaust and/or the doses resulting from such releases, proceed as follows, using a copy of the , worksheet (Appendix 12.1) to record the results of each step: l
- Step 1 4
Record the current date Step 2 1 Record the current tiac I i l Step 3 Record the wind speed u (mph) at the upper (150-f t) and the lower ("'N (33-ft) tower levels. Convert their values to (m/sec) according to Q u (m/sec) = 0.447 X u (mph)
^
Step 4 Record the 33-ft and the 150-ft indicated wind directions and I determine the affected downwind sectors,as follows: Indicated Wind Direction Affected Downwind Sector I O to 11.25 S 11.25 to 33.75 SSW j 33.75 to 56.25 SW 56.25 to 78.75 WSW 78.75 to 10l.25 W 101.25 to 123.75 WNW
! !!.h t i t '. n . '" Nu 1 > . . ..
ina./3 to 191.25 N 19i.!i to 213.7) NNE 21J.75 to'230.2) N!;
'b :s t o M s.75 Ev l
i SP 69 022.01 Rev. A
/ / Page 3 1
J
I Indicated Wind Direction Affected Downwind Ssetor ] 258.75 to 281.25 E .. (T 281.25 to 303.75 ESE ' (,,/ 303.75 to 326.25 SE 326.25 to 348.75 SSE 348.75 to 371.25 S 371.25 to 393.75 SSW 393.75 to 416.25 SW 416.25 to 438.75 WSW ; 438.75 to 461.25 W 461.25 to 483.75 WNW. 483.75 to 506.25 NW 506.25 to 528.75 NNW 528.75 to 540.00 N Step 5 Determine and record on the worksheet the current atmospheric stability class as follows: a) Record the current 33-150 ft. temperature difference (delta-T) on the meteorological tower (data available ! directly from the tower or the control room). Choose the correct stability class from the following list: Delta-T (*F) Stability Atmospheric 33-150 ft Class condition () Less than
-1.22 to
-1.22
-1.09 A
B Extremely Unstable Moderately Unstable
-1.09 to -0.96 C Slightly Unstabic
-0.96 to 0.32 D Neutral 0.32 to 0.96 E Slightly Stable 0.96 to 2.57 F Moderately Stable Greater than 2.57 G Extr,emely Stable NOTE: For borderline cases, choose the class with higher stability (e.g., if delta-T = 0.32, choose stability Class E).
b) If the delta-T between the 33-ft. and 150-ft. levels is not availabic, record the standard deviation of wind direction fluctuation (d'e-) f roa either the 33-f t. Icvel of the primary tower or the backup tower, and choose the c > re; t stabilt:: class fro " !ailowing list. (. a ;rees ) 5ta .iity . , . . .c . 33 ,t. I.evel C; m C ;:.c. i a r; r , , . ,i.,. ?,s i r r ,3 t,' n g e a hi a I . 1, .,ta 12.5 to 17.5 C Slightly Unstable 7.5 to 12.5 D Neutral 3.8 to 7.5 E Slightly Stable
' 2.1 3.8 Moderately Stable to F i.e s s than 2.1 G Extre,21y Stabic w um i
iw. c) If no-dalta-T or 'If?, data is available choosa thm stability class using the wind creed from Step 3 and the following table: i [\' ) 33-ft Wind Speed Day Incoming Solar Radiation-Night Degree of Cloudiness (mph) Strong Moderate Slight >50% <50%
<4 A A-B B
- 4-7 A-B B C E F 7-11 B B-C C- D F.
! 11-14 C C-D D D D
>14 C D D D D 1
- The degreelof cloudiness is defined as that fraction of the ski above the local apparent horizon that is covered by clouds. The neutral Class D, should be assumed for heavy overcast conditions during day or night.
l , Step 6 Determine the type of release (ground-level or elevated) as follows: l t a) Record the station vent average flow rate F (cfm)
- l. b) Compute the vent exit velocity Wo (m/sec)
() c) Wo (m/sec) = 8.47 X 10-5F(cfm) Compute the velocity ratio Ry according to the formula: R y= Vent Exit Velocity Wo(m/sec) Prevailing wind bpeer at lau It (m/sec) .i I d) If R y is less than 5, the rel'ase e is to be assumed to be at ground 1cvel; if Ry is greater than or equal to 5 the release is elevated. i Step 7 !- Record the distance X to the subject receptor in miles. Use 0.19 ;
! mile for the nearest sit boundary.
4 Stey H for 1 r i t.ed re l. 6,e s a . e, uu .ae U t au !.a t e d ercaia heights
.\pp 1 li x 11.2 to deterninc *V rN eptor aiote MSL). Set ht " 0 22r gound-level
. Olev:*.lon (ht) (in neters r.4 l.n . u;.
. For elevated releases only, carry out the following calculations to determine the plume rise hur(m). Set hpr = 0 for ground-level
, releases. Compute the following for all atmospheric stability
- classes (using the velocity ratio Ry and the vent exit velocity SP 69 922.01 Rev. A
/ / Page 5 , .
t Wo (m/sec) from Step o and the distance X (miles) from Step 7): f 2 hpr (1) = 32.4 Rv /3 X hpr (2) = 7.08 Rv i Compute the following for atmospheric stabilities E, F and G hpr (3) = 30(Wo)l/2 for stability E
=
24 (W o )l/2 for stability F i t i
= 21 (Wo)1/2 for stability G f
hpr (4) = 6.4(Rv Wo)l/3 for stability E
=
5.5(R y go)l/3 for stability F
= 4.9(Rv Wo)l/3 for stability G The final plume rise value to be used is as follows:
For stabilities A, B, C and a:
; hpr = lesser of hpr (1) and hp r (2)
For stabilities E, F and G: h pr = lesser of hp r (I). h r (2), h r (3) and h r (4)
, p p p d
Step 10 For elevated releases only, compute the effective height of the !
; plume above the receptor:
I > 'h e = 75.9 + hp r - ht (meters) . i
- For ground-level releases he " @a0 Step 11 i
Record the atmospheric dispersion factor of interest accordirg to ! the following procedure: [ a) Select the " concentration Xu/Q" tables ( Appendix 12.3) l %r rhyr.itd do4" :pam t r v. r *he "1 mt Xu/Q" tahics l . - ..l i x L. thu . .:v '. ba.! : .h u s r it e. l
'O Choim the propar atmospheric dispersion factor (Xu/y)
! 'c r- t tio o. n c h t! t Ma,unin:- th2 fol' mei a; inf ar .at lon:
. Release mode (ground-level or elevated with 11 = 35,
! 70, 105m or 140m, whichever is closer to the plume l effcctive height he computed in Step 10). I ! . The distance to the subject re:cptor (fran Step 7) SP 69 022 01 Rev. A
/ / i9 , . A
(interplate if need bs). ;
, Step 12
( Select the radiation monitor paat of interest: a) Station ventilation exhaust b) RBSVS exhaust Step 13 , Select the type of exposure of interest a) Whole body gamma (station vent and RBSVS) b) Thyroid (RBSVS only) Step 14 Based on your selections in Steps 12 and 13 choose the proper nomogram for the release point and the nuclide composition of interest from the list which follows. Record the nomogram number on the worksheet and get a copy of the nomogram. Nomogram No. Description i Station vent routine effluent monitor
. noble gas release 7- s . wholebody gamma dose
() 2 Station vent high-range monitor
- . noble gas release
. wholebody gamma dose 3 RBSVS low-range monitor
. noble gas release
. wholebody gamma dose 4 RBSVS low-range monitor
. potential halogen release rate
. potential thyroid dose rate 5 RBSVS intermediate-range monitor
. noble gas release
. wholebody 3amma dose o RSSV3 i n te rmed i a t e-ca nt;u aan i. to r
. potential halor,en release rate
. potential thyroid dose n,' 2 4 ca m. . ir
. noble gas e.iaase
. wholebody gamma dose 8 RBSVS high-range monitor
. potential halogen release rate
. ,* c ot t il thyroid h w r,te ,
i 6 I
Step 15 -
. Record:
a) The radiation reading (rad /hr or epm) at the selected monitor, oj; b) The Xc-133 or I-131 dose-equivalent concentration (Ci/ce) as determned from grab-saeple analysis for the release point. 5 Step 16 Record the air flow at the duct saapled or nonitored (in efm). Step 17 Record the time since reactor scram on the worksheet (hours). THis time may be 0 if the reactor is not yet shutdown. In this case use the smallest time marked on the nomogram. Step 18 Use the selected nomogram and the following information to compute the radioactivity release rate and the dose rate at the receptor of interest:
. Monitor reading or grab sample concentration (from Step 15)
. Vent flow (from Step 16) .
Time since reactor scram (from Step 17) [') .
. Prevailing wind speed (from Step 3 in mph; use the 33-ft data for a ground-level release and the 150-ft data for an elevated release as determined in Step 6)
. The Xu/Q value (from Step 11)
Each nomogram consists of 5 distinct sections, as follows: Section Y-axis Variable 1 Monitor Reading or Flow rate grab-sample concent-ration 2 Effluent Radio- Parameter Z (time dep.) activity
'+r' cY (t!.ne d.y.)
4 None Preva illy 'lind Speed 5 Offstro Dase a r. e Arnospheric Dispersion
.u - ^ (\ond,,
The nomogram procedure is presented graphically in the " Sample Nomogram Procedure" attached as Appendix 12.5 and is as follows: (}
\_s i
Sp 69.0,22_.01 Rev. A ___ __
a) Locate either of the following paramaters on ths left-hand Y-axis j
=
J r i' . Monitor reading (Point A1 ), or
. Grab sample concentration (Point A2) I b) Move horizontally to the right until you intercept the slanted line corresponding to the flow rate (Point B);
interpolate if need be. c) At Point B reflect vertically down until you intercept the slanted line corresponding to either (a) the number of hours elapsed since reactor scram if your starting point is Al or (b) the line marked "I-131 equivalent" or "Xe-133 equivalent" if your starting point is A2 (point C). d) From Point C move horizontally to the left and intercept the Y-axis at Point D. The reading at Point D corresponds to the. radioactivity release rate to the atmosphere. The Y-axis label identifies the isotopic mix (halogens or noble gases, in gross uCi/sec if your starting point is A1, or dose-equivalent uCi/see if your starting point is A2 c) Return to Point A, move to Point B, and reflect c vertically up until you intercept the slanted line corresponding to either (a) the elapsed time after reactor scram if your starting point is A1, or (b) the O line marked "I-131 dose-equivalent" or "Xe-133 dose-equivalent" if your starting point is A2 (Point E). f) From Point E reficct horizontally until you intercept the line corresponding to the prevailing wind speed (Point F). g) From Point F move vertically'down to Point G which corresponds to the current atmospheric dispersion factor as established 16. C.ep 11. h) From Point G move horizontally to the right until you intercept the Y-axis (Point H). The reading at Point H corresponds to the dose rate at the downhill location of interest. Record this dose rate on the worksheet. O
- - (
~
APPENDIX 12.1
.Page 1 of 2 q Sil0REllAM NUCLEAR POWER STATION k /
WORKSilEET RADIOACTIVE EFFLUENT MONITOR NOMOGRAM Your N' ame:
- 1. Date: 2. Time: .
- 3. Wind speed: u(33-ft level) mph; X 9 447 = m/see u(150-ft la. vel) mph; X @.447 = m/sec
- 4. Wind direction: 33-ft icvel degrees; sector 150-ft level degrees; sector
- 5. Delta Temperature: 33-150 ft degrees; stability (Sigma Theta if not available, see procedure for instructions)
- 6. Station vent flow: F cfm Exit velocity : Wo = F(cfm) X 8.47 X 10-5 = m/sec Velocity ratio . Ry = Wo(m/sec) / u(150-ft; m/sec) =
If Ry is less than 5 circle " ground level release" If Ry is greater than or equal to 5 circle " elevated release"
- 7. Distance to downwind receptor: X= miles
- 8. Receptor elevation: ht m above MSL (from tables; set ht - @ for ground-level releases)
- 9. For ground-level releases set hpr = @ and go to Step .10. For elevated releases compute the following for all stablilities:
hp r (1) = 32.3 Ry 2/3 X I/3 = m hpr (2) = 7.98 Ry = m For stabilities E, F, and G only: hrp (3)
= 31 V., i 1/ 2 = _, , , , _ , ,_ ,,,n (stahtlity E)
.' 3 % - ..... . ._____.' M "biliLY I)
I "o ".______......._.; (stablLity G)
" 'flity
.s , ,_ __ '. < : -
= 5.57 Ry ug 1/3 = a (stability F)
= 4.92 Ry Wo I/3 = n (stability C) im * - .bt n ',9 SP 69.022.01 Rev. A
APPENDIX 12.1 i Page 2 of 2 Choose the final plume rise as follows: Stabilities A,-8, C and D 1 hpr = lesser of hpr (1) and hpr (2) = m Stabilities E, F, and G hp r = lesser of h pr (1) through hpr (4) = m
- 10. Height of plume above receptor (he - 9)' for ground-level releases) he = 75.9 + hp r - ht = m Tabulated plume height in (xu/Q) tables closest to he is 11 (choose 35, 70, 105 or 140) = m
- 11. Atmospheric dispersion factor: (1/m2 ) (from tables)
Circle one: concentration (xu/O' for thyroid dose gamma (xu/Q) for finite-cloud wholebody gamen dose f
- 12. Release point (circle one): Station Vent; RBSVS Release composition (circle one): noble gases and halogen; j 0 13. noble gases
- 14. Numbe.r of nomogram selected:
- 15. Radiation monitor reading: rad /hr, or cps
- 16. Air flow at the duct sampled or monitored: -
cfm
- 17. Time since reactor scram: hours i.
- 18. Radioactivity release rate: uC1/sec (n.g. and/or hal.)
l Offsite dose rate: mr/hr thyroid or wholebody gam. i . ;- 69.02? t -? ' l l SP 69 022.01 Rev. A
--.. . - - ..-.. .. - - - - - - - . - - - - - - - -- - ~ - - - . . ~ - ~ ~ - - - ~ - - -
~
APPENDIX 12.2 - SHOREHAM STATION - TERRAIN HEIGHTS (METERS ABOVE MSL) ~ MILE 3 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW , .19 ,i .23
.50 1
.7,
! 1.0 l 1.5 1 l 2.C s
> .- r. .
l 3.0 i l 3.~ L A T E 'R - 4 . (: 4.5 5.0 '
'\
x t ,, ;t .' i
- i . .>
l 1 J. 10. i , 15. l 20. - f 25. . 30. .l j 33. - j j 40.
.45.
50. i i i e t i SP 69 522 91' Rev. A i i
/ / _Page 12
. - - - - . . . . . - _ . . , , . . _ , i
~
APPENDIX 12
~ Page 1 of 5 S.2:5frW1 STATION - PL17E-CENTERLINE COEENTRATION (X*U/G) (1/M2)
GROUND-LEVEL RELEASE - DIVIDE RESULTS BY ONE MILLION MILES A B C D E F G
.19 d.G24 142.587 218.895 451.874 733.325 1526.773 3529.499
.25 ' .552
. 93.968 155.855 307.503 517.204 1038.091 2177.300
.50 c. 33G 25.814 56.855 134.300 203.135 42S.991 849.132
.75 2.669 10.212 29.689 80.633 132.640 244.169 499.947 1.0 2.089 4.932 18.422 55.140 94.347 165.540 336.834 1.5 :.488 2.004 9.447 .31.746 55.471 106.474 195.837 2.0 1.147 1.561 5.844 20.616 38.311 74.644 137.574 2.5 .945 1.295 4.019 14.791 28.672 57.294 106.706 3.0 .816 1.089 2.959 11.342 22.585 47.484 89.414 3.5 .720 .944 2.283 9.000 18.490 40.239 76.541 e.
N 4.0 .544 .838 1.825 7.503 15.572 34.709 66.653 4.5 .585 .758 1.495 6.342 13.396 30.134 58.595 5.0 .536 .693 1.258 5.469 11.722 26.607 52.261 7.5 .366 .497 .713 3.206 7.151 17.112 34.340 10.0 .288 .390 .524 2.164 5.020 12.601 25.580 15.0 .214 .274 .360 1.204 3.036 8.003 16,872 20.0 .166 .215 .291 .811 2.185 5.861 12.691 25.0 .138 .179 .245 .603 1.709 4.592 10.209 30.0 .120 .155 .213 .478 1.415 3.793 8.580 35.0 .106 .136 .188 .393 1.203 3.225 7.408 40.0 .096 .122 .168- .333 1.044 2.800 6.526 45.0 .097 .110 .148 .291 .927 2.482 5.R53 50.0 .080 .100 .135 .258 .829 2.222 5.302 SP 69.022.91 Rev. A
/ / Page 13
APPENDIX 12.3 Page 2 of 5 i Eh3EHAM STATION - PL17E-CENTERLIE CONCENTRATION (XeU/G) (1/R2) ELEVATED RELEASE (H = 35 M) - DIVIDE RESILTS 8Y OhE MILLION
! MILES A 8 C D E F G
.15 E .S28 108.063 113.557 26.242 1.460 .000 .000
.25 34.736 81.890 109.985 58.158 12.023 .006 .000
.50 .352 25.347 52.257 85.824 75.274 9.315 .021
.75 .S78 10.179 28.570 63.928 79.719 36.060 1.999 1.0 2.094 4.932 17.998 47.501 68.012 53.482 9.535 1.5 ;.490 2.007 9.336 29.294 46.335 57.480 25.584 2.0 .!49 1.563 5.803 19.517 33.068 49.653 31.496 l
i 2.5 .945 1.296 4.000 14.198 25.067 42.113 34.222 3.0 .817 1.089 2.948 10.S84 20.847 36.862 35.929 3.5 .720 .945 2.277 8.843 17.257 32.300 30.481 i 4.0 .S44 .838 1.821 7.337 14.657 28.644 34.054 4.5 .595 .758 1.492 6.220 12.700 25.335 31.933 5.0 .536 .693 1.256 5.375 11.174 22.693 29.973 f 7.5 .3SS .497 .713 3.169 6.917 15.173 23.013 i 10.0 .233 .390 .524 2.146 4.888 11.407 18.379 15.0 .214 .274 .360 1.197 2.976 7.488 12.914 20.0 .166 .215 .291 .808 2.149 5.495 10.097 25.0 .138 .179 .245 .601 1.685 4.338 8.305 30.0 .120 .155 .213 .476 1.397 3.601 7.063 35.0 .106 .136 .186 .392 1.189 3.073 6.159 40.0 .096 .122 .168' .332 1.033 2.678 5.470 45.0 .087 .110 .149 .251 .917 2.380 4.841 50.0 .000 .100 .135 .257 ' .821 2.137 4.503 7 ef4
f5
'EHAM '4 TION - PLUPE-CENTERLINE CONCENTRATION (X*U/G) (1/M2) i l
Z:.EVATED RELEASE (H = 70 M) - DIVIDE RESULTS BY ONE MIL 1. ION MILES A B C D E F G
.1S 3E.107 17.438 3.011 .000 .000 0.000 0.000
.25 L.S50 29.170 12.598 .048 .000 .000 0.000
.50 6.220 20.704 27.534 7.216 .625 .000 .000 1
.75 2.678 9.557 20.869 15.801 5.276 .017 .000 1.0 2.094 4.811 14.825 18.538 10.678 .306 .000 l
1.5 :.420 2.005 8.453 17.158 15.615 2.668 .009 2.0 :.148 1.563 5.464 13.491 15.683 5.811 .065 2.5 .945 1.296 3.838 10.754 14.247 7.869 .218 3.0 .817 1.089 2.859 8.824 12.511 8.982 .548 3.5 .720 .945 2.223 7.383 11.092 9.449 .957 q 4.0 .644 .838 1.787 6.292 9.929 9.519 1.366 i 4.5 .585 .758 1.470 5.442 8.993 S.2SS 1.679 S.0 .536 .693 1.240 4.774 8.187 8.979 1.956 7.5 .3S8 .497 .711 2.928 5.563 7.417 2.955 10.0 .299 .390 .524 2.025 4.105 6.240 3.237 15.0 .214 .274 .360 1.155 2.611 4.668 3.058 l 20.0 .166 .715 .291 .786 1.930 3.687 2.878 i 25.0 .13S .179 .245 .588 1.535 3.046 2.839 30.0 .120 .155 .213 .468 1.283 2.600 2.382 25.0 .106 .136 .188 .386 1.100 2.272 2.181 40.0 .096 .122 .166 .328 .961 2.021 2.019 45.0 .087 .110 .149 .268 .857 1.829 1.891 I 50.0 .000 .100 .135 .255 .770 1.668 1.778 SP 69 022.01 Rev. A
/ / Page 15
____m
APPENDIX 12.3 - Page 4 of 5 _iEHi#. STATION - plt #E-CENTERLINE C3 CENTRATION (XeU/8) (1/M2) ELEVATED RELEASE (H = 105 M) - DIVIDE RESULTS BY ONE MILLION MILES A B C D E F G
.13 :2.291 .834 .007 .000 .000 0.000 0.000
.25 ;3.69G 5.221 .340 .000 .000 0.000 0.000
.50 5.SSS 14.777 9.464 .116 .000 .000 0.000
.75 2.678 8.602 12.364 1.538 .057 .000 .000 1.5 2.094 4.617 10.730 3.864 .488 .000 .000 1.5 1.490 2.001 7.162 7.036 2.548 .016 .000 l 2.0 ;.148 1.563 4.S43 7.291 4.347 .163 .000 l 2.5 .945 1.296 3.583 6.768 5.205 .481 .000 3.0 .817 1.089 2.717 6.125 5.342 .854 .001 3.5 .720 .945 2.137 5.464 5.310 1.213 .002 4.0 4
.644 .838 1.731 4.871 5.188 1.518 .006 4.5 .585 .758 1.432 4.355 5.059 1.743 .012 5.0 .536 .693 1.215 3.919 4.876 1.915 .021 7.5 .358 .497 .707 2.566 3.869 2.250 .037 10.0 .288 .390 .523 1.837 3.070 2.283 .179 15.0 .214 .274 .360 1.087 2.100 2.124 .277 20.0 .156 .215 .291 .752 1.614 1.896 .355 25.0 .138 .179 .245 .567 1.313 1.690 .390 30.0 .120 .155 .213 .454 1.115 1.511 .389 35.0 .106 .136 .188 .377 .967 1.374 .387 40.0 .0SS .122 .168- .321 .852 1.264 .383 45.0 .087 .110 . .148 .282 .765 1.179 .381 50.0 .080 .100 .135 .251 .691 1.104 SP 69.922.91 Rev. A l
.378 Page 16
/ /. ]
~
APPENDIX 12.#~ . Page 5 of 5 , En 2DC.M STATION - PLUME-CENTERLIE CONCENTRATION (X*U/G) (1/M2) ELEVATED RELEASE (H = 140 M) - DIVIDE REStA.TS SY ONE MILLION MILES A B C D E F G
.19 2.719 .012 .000 .000 0.000 0.000 C.000
! .25 r.SSS .470 .002 .000 .000 0.000 0.000
.50 5.GSo 9.216 2.122 .000 .000 .000 0.000
.75 2.678 7.424 5.942 .059 .000 .000 0.000 1.0 2.094 4.358 6.824 .430 .006 .000 .000 l
!.5 1.490 1.995 5.679 2.020 .201 .000 .000 2.0 1.148 1.563 4.295 3.0S0 .721 .001 .000 2.5 .945 1.296 3.254 3.539 1.'271 .010 .000 1 3.0 .817 1.089 2.530 3.674 1.623 .032 .000
, 3.5 .720 .945 2.021 3.566 1.893 .069 .000 e 4.0 .G44 .838 1.656 3.404 2.091 .116 .000 4.5 .585 .758 1.382 3.188 2.261 .168 .000 5.0 .535 .693 1.181 2.S72 2.360 .220 .000 7.5 .358 .497 .702 2.134 2.327 .424 .001 10.0 .238 .390 .522 1.604 2.043 .559 .003 15.0 .214 .274 .360 1.000 1.548 .705 .010 20.0 .156 .215 .291 .706 1.256 .747 .019 25.0 .138 .179 .245 .540 1.056 .741 .027 30.0 .220 .155 .213 .435 .915 .707 .031 35.0 .106 .136 .188 .363 .806 .675 .034 40.0 .056 .122 .168 . .312 .720 .655 .037 45.0 .C87 .110 .149 .275 .652 .638 .041 50.0 .000 .100 .135 .246 .594 .619 .043 SP 69.922.01 Rev ,
l *
~
O O " :Th' O
~
EJCREHAM STATION - GAUSSIAN PUFF G##tMA (X*U/G) (1/M2) GR3UND-LEVEL RELEASE - DIVIDE RESULTS BY ONE MILLION MILES A B C D E F G
.19 :2.619 60.098 77.110 113.774 144.884 205.687 302.182
.25 :'.073 46.390 63.374 82.961 121.875 171.481 242.415
.50 .548 18.542 33.169 57.965 73.915 110.505 155.705 -
i
.75 . 285 8.629 20.653 42.003 57.529 81.965 118.798 1.0 .374 4.483 14.175 32.469 46.510 65.669 97.599 1.5 .597 1.597 8.0C3 21.733 32.606 50.222 72.387 2.0 .539 .788 5.250 15.523 25,008 39.911 58.816 2.5 .445 .608 3.716 11.829 20.109 33.347 50.291 3.0 .384 .512 2.785 9.448 16.694 29.220 44.929 3.5 .339 .444 2.174 7.787 14.217 25.926 40.582 i 4.0 .304 .394 1.751 6.577 12.347 23.241 36.990 4.5 .275 .357 1.439 5.655 10.886 20.889 33.859 5.0 .253 .327 1.209 4.941 9.718 18.882 31.273 7.5 .174 .235 .630 3.005 6.301 13.346 23.056 10.0 .138 .184 .400 2.065 4.568 10.342 18.410 15.0 .101 .129 .217 1.168 2.854 7.032 13.192 i 20.0 .079 .102 .151 .793 2.084 5.264 10.399 25.0 .065 .084 .116 .591 1.644 4.206 8.827 30.0 .057 .073 .101 .469 1.368 3.520 7.409 l 35.0 .050 .064 .089 .385 1.168 3.022 6.503 1 40.0 .045 .058 .079' .326 1.016 2.643 5.803 l 45.0 .041 .052 .071 .283 .904 2.355 5.257 SP 69 022 01 Rev. A 50.0 .033 .047 .064 .249 .810 2.118 4.803 / / Page 18
O O O APPENDIX. 4
~~
Page2okI
~~
SHCREHM STATION - CAUSSIAN PtJFF GMMA (X*U/G) (1/M2) ELEVATED RELEASE (h = 35 M) - DIVIDE RESLt.TS BY ONE MILLION MILES A B C D E F G
.13 :3.247 58.930 72.641 80.5S0 77.465 73.502 72.221
.25 :!.5ES 46.090 61.S84 79.208 80.137 75.124 72.785
! .50 5.584 18.565 33.349 58.622 72.219 80.618 77.128 l
.75 1.290 8.851 20.805 43.178 58.763 75.802 80.544 1.0 .577 4.505 14.285 33.443 48.144 68.050 79.403 1.5 .639 1.601 8.119 22.309 33.933 53.806 71.608 2.0 .540 .789 5.280 15.910 25.994 43.099 63.938 2.5 .445 .609 3.734 12.0S8 20.879 36.032 57.228 3.0 .365 .512 2.797 9.639 17.331 31.518 51.451 3.5 .339 .445 2.182 7.931 14.744 27.932 46.651 4.0 .304 .395 1.757 6.688 12.788 25.018 42.635 4.5 .276 .357 1.443 5.743 11.254 22.482 39.179 5.0 .253 .327 1.212 5.014 10.032 20.422 36.256 7.5 . 74 .235 .632 3.040 6.471 14.320 26.714 10.0 .136 .18+ .400 2.085 4.678 11.060 g 21.300 15.0 .101 .130 .217 1.176 2.912 7.472 15.242 20.0 .073 .102 .151 .797 2.121 5.564 11.951 25.0 .065 .085 .116 .594 1.671 4.430 9.880 30.0 .057 .073 .101 .471 1.389 3.699 8.474 35.0 .050 .064 .089 .337 1.184 3.167 7.427 40.0 .045 .058 .078 .327 1.030 2.764 6.615 45.0 .041 .052 .071 .284 .916 2.458 5.981 50.0 .038 .047 .064 .250 .820 2.206 5.454 SP 69 922 01 Rev. A
/ / Page 19 A _ _ . . _ _ _
APPENDIX A Page 3 of 5 SHOREHAM STATION - GAUSSIAN PLFF GAMMA (X*U/G) (1/M2) ELEVATED RELEASE (H = 70 M) - DIVIDE RESULTS BY ONE MILLION l1ILES A B C D E F G
.19 29.371 33.441 32.128 28.762 27.885 27.372 27.171
.25 21.688 31.315 33.466 30.080 28.462 27.582 27.285
.50 5.201 16.452 26.065 33.428 32.223 29.097 27.838
.75 1.282 8.211 18.126 30.384 33.434 31.300 28.744 1.0 .S73 4.391 13.055 26.114 31.873 32.973 29.989 1.5 .597 1.589 7.732 19.209 26.371 32.984 32.354 -
2.0 .539 .787 5.121 14.374 21.718 30.356 33.385 2.5 445 .607 3.657 11.223 18.181 27.419 33.347 3.0 . ':84 .512 2.755 S.090 15.498 25.068 32.599 3.5 .339 .444 2.158 7.563 13.431 22.950 31.47S 4.0 .304 .355 1.741 6.429 11.807 21.074' 30.192 4.5 .278 .357 1.434 5.554 10.500 19.332 28.842 5.0 .253 .327 1.206 4.871 9.436 17.845 27.526 7.5 .174 .235 .630 2.990 6.229 13.083 22.183 10.0 .136 .184 .400 2.063 4.554 10.332 18.487 15.0 . 01 .130 .217 1.170 2.867 7.146 13.836 20.0 .079 .102 .151 .794 2.098 5.387 11.098 , 25.0 .065 .085 .116
.593 1.657 4.320 9.302
':0.0 .057 .073 .101 .470 1.380 3.623 8.053 35.0 .050 .064 .089 .386 1.178 3.113 7.105 40.0 .045 .058 .079 .326 1.025 2.723 6.362 45.0 .041 .052 .071 .284. .912 2.426 5.775 50.0 .038 .047 .064 .250 .817 2.181 5.284 SP 69 022 91 Rev. A
/ / Page 20
"'NCH=uh--.- u -
i
' APPENDIX Page 4 of 5 SH3REHAM STATION - GAUSSIAN PLFF GNW1A (XoU/0) (1/M2)
ELEVATED RELEASE (H = 105 M) - DIVIDE RESULTS BY ONE MILLION MILES A B C D E F G t
.19 C.921 15.998 14.109 12.907 12.618 12.432 12.357
.25 :C.204 17.623 15.546 13.309 12.818 12.509 12.393
.50 d.177 13.490 17.600 16.043 14.160 13.009 12.601
.75 1.267 7.521 14.463 17.823 16.022 13.734 12.901 1.0 .954 4.198 11.250 17.611 17.430 14.691 13.280 1.5 .693 1.565 7.122 15.042 17.661 16.737 14.235 2.0 .537 .781 4.857 12.160 16.216 17.827 15.262 2.5 .443 .604 3.524 9.909 14.493 17.823 16.249 -
3.0 .383 .510 2.681 8.240 12.896 17.367 17.048 3.5 .338 .443 2.113 6.980 11.515 16.699 17.574 4.0 .303 .393 1.712 6.010 10.347 15.938 17.84S 4.5 .276 .353 1.414 5.243 9.356 15.105 17.920 5.0 .253 .326 1.192 4.632 8.518 14.306 17.836 7.5 .174 .234 .627 2.902 5.836 11.271 16.406 10.0 .136 .184 .299 2.022 4.346 9.226 14.660 15.0 .101 .129 .216 1.157 2.785 6.626 11.795 ! 20.0 .079 .102 .151 .789 2.056 5.094 9.814 ! 25.0 .065 .085 .116 .590 1.631 4.132 8.411 30.0 .057 .073 . 101 .468 1.362 3.492 7.390 35.0 .050 .064 .088 .385 1.165 3.017 6.591 40.0 .045 .058 .078 .326 1.016 2.650 5.951 45.0 .041 .052 .071 .283 .905 2.369 5.438 SP 69 922 91 Rev. A 50.0 .038 .047 .064 .249 .812 2.135 5.003 Page 21
/ /
_ _ _ _ _ _-mm __
y ge 5 of 5 SHCREWJt STATION - CfUSSIAN PtFF CfJfm (X*U/G) (1/M2) E_EVATED RELEASE (H = 140 M) - DIVIDE RESULTS BY ONE MILLION 3:ILES A B C 3 E F G
.19 0.E31 7.641 6.784 6.286 6.158 6.074 6.041
.25 10.331 8.996 7.408 6.460 6.247 6.109 6.057
.50 4.725 10.263 10.556 7.667 6.E05 6.331 6.150
.75 1.245 6.662 10.612 9.371 7.655 6.634 6.283 1.0 .352 3.942 9.158 10.547 8.741 7.024 6.448 1.5 .59S 1.530 6.357 10.770 10.499 8.109 6.835 T.0 .533 .773 4.512 9.651 10.931 9.381 7.274 2.5 .441 .600 3.345 8.341 10.621 10.273 7.786 3.0 .3C2 .506 2.578 7.195 10.007 10.714 8.358
- !.5 .337 .440 2.050 6.247 9.307 10.908 8.925 4.0 .302 .392 1.671 5.475 8.619 10.917 9.442 4.5 .:75 .355 1.387 4.840 7.976 10.784 9.890 S.0 .252 .325 1.173 4.320 7.395 10.562 10.247 7.5 .173 .234 .622 2.781 5.333 S.170 10.931 10.0 .136 .184 .3S7 1.964 4.072 7.888 10.670 15.0 .101 .129 .216 1.139 2.674 5.970 9.460 20.0 .079 .102 .151 .781 1.996 4.714 8.280 25.0 .035 .084 .116 .585 1.594 3.885 7.318 30.0 .057 .073 .101 .466 1.336 3.317 6.563 35.0 .050 .064 .089 .384 1.147 2.886 5.942 40.0 .045 .058 .079 .324 1.002 2.550 5.427 45.0 .041 .052 .071 .283 .894. 2.289 5.003 50.0 .038 SP 69.922.01 Rev. A
.047 .064 .24ti .803 2.070 4.637 / / Page 22
- CZ WN / /
. vm ic t20*69 dS l . ..._ -.-.--,.
p
.. p
\
. .. . - .__ .~ -
,4 !
.q .- . A- $, .-.. .7 - . -.
'>M m h, _ " * " - "
g ff i _ g .4 -
..+ t .
2
.!. 7 ; Wf"
'r.
M e h
* ' -" E='==
grk'-- .22Eh..jE:E*] !$+ -
=-
IRE
/
F.'dSE 3=[" Iq: NH =- 2 = -
--- -Eg. i g Q eIMA}, lIe i i
/ ! ! ///M / 8 **
. ! t I / / l
/////~ Hf hM';F+k2Mth h .i fh. '3 j~"! CiN T ""-"~h [,3 .
n [ D r%sa Fm < r WWr*F"9enasi == 4 ,A =
!y S ! ,
,_/[/ -
/g DG-S \ j //g g E y - ._ _ ___. , ,
7 , y_ p p j w y > ^ v" i 7mM y una asoa e p. ^
=t d
"^
%-* i-
~
<a t.:h--- **.i T '
'**ty -++
.. ._1.g.
- .A. :t t _, ' -+++
t g rp.gm;*+ g_
.p 2
.j_7; :e r :r".pe r=- t3: t+-wV UhM;b-th?-*$' i I
' : -. .--.4 -n t:s=' ":*n = 4-- :
9:. g
=
h l .-#/h /// .. (/ / l I\, jh) { / i' A l9 -
? .h - / A '
/ ./bff f/ / [ %.N0!llV 1.+4 4 1 '~i , ,
}};. //, !
/ Ml ;-._^ r' l._^ ^p ,4 ,,
I i Jf- i I f I y
. , ++L 7 :*si &&@.+ - o en
--r::=;E : ; N ~~
b, :.m b*-
- E" 3
=4 / ' f // /b //p [ Ny#
3 ------"- --
//
i I b / / r
;/
2 Q L.' hf// h I I l l b I .) b@ i u if b'>_- -M
...z._<_,.j. . a.~ , , , . J.,y, ,, p .
e $ m.s M
*t '.1 _t- U+. @.
MC.:- -
;i.Utk:r+_
':t+ _
c+' M- . . qd @ :1.i
- i**t 5 + =M' h.b . .f: Ct'/ Tft '
i1 '5-~ *T [._
==w " &' * ,= --^
'. l"IIII;2[- ~4*:---* "' *n -!/U
' ^
' ^^'
~
_/g'. , %
/ ' W'. 4/l, '
/
'L'00'hl z q,/
4,_'1/ +z _o/y. f /, 'l i A ll '. /// P
/ 4,-
.. -l l l
.m.
!. p' ..
, i de gg_ z.<
g.
'd.um - -
/ $.h" I
[
,s o .a ._. /ap a -
m, ; a.yi --A,m _ I. 4 w-gO
'*tftTl' ,
d : :
.i ' '
r* b **
.' aO!hi .l'I;' 1 Y'J' t 111 * * .M.y
- M,. .J h:sa :
lp j,J k.*t
. wr. ', ; f n:*#/ l' l, 1
th.IhfT."$..*ttgN.,
.' //
. ~ 3
'j[
m
.' u
;+t
_-.m
--- 1** 4 ._. -- J 48'
+
~.1
. -. ? ""~_ -
.4 -y
, s a/ f
/ -,
lv
., 7rs i l l s., , ,[' /
r1
/
2 Of g- '
/ /h [ $ , z._L,g I ! i
-E7/A
- 1 J 'A& i ./ J 1 J l 3 -
Q.4-W+us x; a. R,).a:+ ++Q*",L my ~.&'$ % I JY / L ' 3 ' t -
- l>=
* " *-* ~'
t:w 1 -
.d V -
, ' ,J
.g =/j / '/"t'.*w @,"'/ +-.
,g*z';2'n-*; .
- 4. _ =1 =:;--
.+t T-rj -
-= =;
':*+--.._.
w-= .. r
-_,E 1:
I - c: = _.,h */ n
1 o,
;-/ /
/ :
> '- l
/ y
; -t / '
s_ j l l 4-- s O% s -. - - U_421 ,, .f J./.g
'y
- 1. -4 _;_ =
1. q v _ __ w
'M* ~,; z _m k "mu
.g.
-_._.J4.l..
=
b : . _ . - i
; ==
_;^
.$..L k.y6 _M.a.r: 3' 7)pk M[.m
._ . t_ .. /.. . .u - -___ .. :'.h t.
.. -Pe- ,ni
- ' h H O J 53E =-"~1 3' I ~-[rU# .a %d.2Ri ..I 1[R II[
/p. .
lg II / i hi [ ..= == . E -.a ,'
; ::n -
y&gg 7- J f z / h
. /
i,t
. ; if M .f[-En9 g 1 t c ..g' L._g &of. c
_a i l Lit" ! !, I p;/M W -.M k
- p 0 .p!p Wy_.._c.Jh i
L i 1
.< /rn wwww -
= -
- qr
-a
.. u: .t.w.
- t w: c s p. w -
~q :7Q"'". t
%;w g M W;+r -= =q; u m ==:1 -~--
F.,;rttw
=:i -
A q bs=r_- ndF-M - i 4 s- pp+: J , q Z p / m. f i. b,._ c
..__. _ _ l l
1[
- ..l .
.{4_.J.e ph i.E_ i L_
!!n..I $
&A. pops i h9 a S-
. m,
, , ___. - }.oi,t. - y,,
yd. 7-m _ w m %_u@o -._i.3.m..
- 3. #.-- im
- .w -..am. m __ L-i .7~7. e
. _ 6 I p.u_ . --..4s. ... -s___ a , g. -
-. 4 ; - 3"'
, ~:-
pi..:ttrh w:hp.- trJ a...q*.4.r 1tn:t:tsome: ra--;c*:M.... r
- meqp=.:*n-at.*t.t -: Inm'" y ::::xr:14:rraut:
....h re rr:nd12pc:*:::m.t::':. .
m m. . x r . 2m: rt :. _ : -: =.: _=; .=. m .m m . .p =. =.m a ;,:r.
,o m t - =_.n - = =:rr.:m
*~ .=.:. m , , u ._=. ;= ~ , ,
. . , . J .. . . i . , . . . . .
- m. g . . , , , . , . > .s. n3 .
- f. y . '
_.7M,,. ... g
....t .a... . . . . i . h . . g. . . . . [. g l ... . . . .cq.W> . . . .,. 4. __L . 4. . . . _.e. __g;p
.;: .m-
. . . . m q--n:Lt t=a:S g_.
5
... u : k. .c..n :a:u.: ..-
. . .. .e. . -cr . . :. r p-~ mP.e 0+e - 4t
. :, . . . . . . r :om,% m n :A. .: _ . nr:p;c -- r:n gH
...;p ..nt.., : : _ __
.-,t : ;r:q:.r..:::"o.q:rFr.#[;:::
tpn m ' I v i ;,, w t t eg r ,p .q..- - . pe, m ; qwn s.: ...j a r : r -
,1
. . - j. . t .- .g ..... , p ! _
, . . . i _ . r .. . p.g ., .. .g y, . . -
t e;_,. q,0 . . q u.. ,. c. .,: % , ,
,.g.;- M .. .,g,. r
. 4--- _'.".4te ;4 tt-b--*
d";r_tz1-'n?*p3...f3"t!q.d. g 1 M i "' gy._:.g* t :tt.t.(* tr- : n *". -*_- M 1t *.. . N .g., - -- rd!!- t:nt p v: t t:M,d"* .. . vn rh.7 ' --yt*2.r wn ". p d t r t ._ --- .: : , t.m n=- p rs=s= at p*t ~ g$p 4:: +#-t.-
- - - ~ *:I^P" t- - -
_ . tim.::.= -=
=)= [
0 u d . b I. 2 d$_ .. d } ! ! M i_3L ,..w.. I
~g..=.&.fhj_[ _ U_m, . _
I _ L.L .q.., L G'~uW_ ...m t._4_* :.m,r. rt : bre _ . _m.aa-..mm-. ('%sGW,,ai Q ar.. W;. m.
- ay; .,., p.9::,.
1 d ~. rt. 1 l t .
'~
.i ' ' : ~ - -". . - ~. :-
9 %. .. gLg'~ . . .
, x
,. , - 3..m . ,
l
.w__m. ~A - a
. 5
~
~
. l
. Submitted:
(Plant Manager) DRAFT-PREUMNARY SP Number 69.624.61 Revision _ A Date Eff. TPC TPC TPC WATERBORNE RELEASE DOSE PROJECTION ] l 1.0 _ PURPOSE This procedure provides instructions for the calculation of projected whole body and skin doses received while swimming in or boating upon Long Island Sound water contaminated by a radioactive release from the_Shoreham Nuclear Power Station. 2.0 RESPONSIBILITY The Radiation Protection Manager ,is responsible for ensuring compliance with this proceduro. l l 4g O I 1 a\ i PPF 1621.666-6.421
\, -
--.-7--- .-. , . , :w , ,- . . . . - , , - ,,-, _ , ,,-_.,n ,v.,-e, ,,_,.,._n.en.,, , , , , , . - - - - - ,-.--,e"e--,
, - <,- , _ . ,e -v-r,-
, 3.0 DISCUSSION .
3.1 These projected whole body and skin doses: (3
\s-) 3.1.1 Identify locations where it is appropriate to initiate water sampling efforts in the Long Island Sound.
3.1.2 Provide a basis for initial selection of a protective actions recommendation by comparison with Environmental Protection Agency (EPC) Protective Action Guides (PAGs). 4.0 PRECAUTIONS N/A 5.0 PREREQUISITES An inadvertent release of radioactivity has occurred as indicated by the Liquid Radwaste Effluent Monitor or Reactor Building Salt Water Drain Tank Monitor. 6.0 LIMITATIONS AND ACTIONS Terminate the release. 7.0 MATERIALS AND EQUIPMENT, N/A A (,,).O PROCEDURE 8.1 Radiation Protection Manager or Designee, Perform the Following: 8.1.1 Determine release concentration (UCi/ml) from the Liquid Radwaste Effluent Monitor or the Reactor Building Salt Water Drain Tank Monitor. 8.1.2 Determine projected duration of exposure. This may be conserva-tively estimated to be equal to the projected duration of release. The projected duration of release is calculated from the beginning of the release until the release is expected to be terminated by either corrective action or depletion of source. 8.1.3 Calculate nrojected swimming whole body and skin doses and boating whole body projected dose on the Liquid Release h'eiksheet (Attachment 12.1) using the following equation: Proj ec t ed Due (n'len) = O(uCi/nl) x T(hrs) x CF(mRe .-nl/uCi-hr) chere O concentration of radioactivity in release (uct/nl) T = projected duration of exposure (hrs) CF = conversion factors of dose rate per radioactive concentration in water (mrem-ml/pCi-hr) for swimming, whole body or skin, es and boating, whole body only ('-' \ 8.1.4 Determine waterborne protective actions by initiating Emergency Plan Implementing Procedure SP 69.026.01 " Protective Action SP 69.024.01 Rev. A
/ / Page 2
- I
; Recommendations."
9.0 ACCEPTANCE CRITERIA-
-- N/A 10.0 FINAL CONDITIONS Waterborne projected dose has been calculated.
11.0 REFERENCES
11.1 Final Environmental Statement Concerning Proposed Rule Making Action: Numerical Guides for Design Objectives and Limiting Conditions for Operation to Mee.t the Criterion "As Low As Practicable" for Radioactive Material in Light-Water Cooled Nuclear Power Reactor Effluents Volume 2 Analytical Models and Calculations, Directorate of Regulatory Standards, U.S. Atomic Energy Commission July 1973 Table A-4, pgs 4-6, NUCLIDE MASTER LIST - MASTER LIST OF ADULT DOSE FACTORS 11.2 Final Safety Analysis Report, Shoreham Nuclear Power Station Unit 1 Long Island Lighting Company, Revision 7, August 1977 11.2.1 Part 11.6.2.1 LIQUID EFFLUENT PATHRAYS - Used to Determine Dilution of Release 11.2.2 Table 11.2.6.1 ESTIMATED LIQUID EFFLUENT RELEASES 2.0 APPENDICES , 12.1 Liquid Release Worksheet i 4 I SP 69.024.01 Rev. A
/ / Page 3 O
,. BJPtNDETlfM.11 1 LIQUID RELEASE WORKSHEET l t
ACTIVITY RELEASE PROJECTED DUPATION CONVERSION PROJECTED CONCENTRATION OF EXPOSURE FACTOR DOSE C/ ( u C I / ML ) , (HR) (MREM-ML/ u CI ML ) (MREMI O T CF" WHOLE BODY 9.64X10 1 (SWIMMING) SWIMMING SKIN 1.33X10 2 (SWIMMING) WHOLE BODY (BOATING 1 DOATING 6.67X10 1
\
(~J L
'CF I MREM-ML/u CI -HR = G X M X DCF ( MREM-ML/ u CI -HR )
0: GEONETRY OF EXPOSURE (UNITLESS): 1.0 FOR SWIMMING. 0.5 FOR BOATING H= OlLUTION OF RELEASE =1/8.8S: .113 (UNITLESS) REFERENCE-2A DCFIWtiOLE 80DY)=8.S3 X 10 2 ( MREM-ML/u C1 -HR) REFERENCES 1.28 DCF (SKIN) 1.18X10 3 ( MREM-ML/ u CI-HR) REFERENCES 1.2B CF(SWINNING. WtiOLE BODY)= 1.0 X .113 X 8.S3 X 10 2 (MREM-ML/ u C1 -HR 1 I
= 9.64 X 10 (MREM-ML/u C1 -HR 1 3 (MREM-ML/ u CI -HR )
CF(SWIv1NU. SKIN) = 1.0 X .113 X !.18 X 10
- 1.33 7 .: i N R E P' - P' L / o[ - H' ;
c' i A ' '
..m. . .. t0 L L UCD1 ) 1 0.5 x . .: x 1.10 X lu' .H i " - . i. C : - < 1
= 6.67 X 10 (I MREM-ML/u CI -HR )
rx SP 69.024.01 Rev. A
/ / Page 4
Subnittsd _
, Approvad .
(Plant Manager) i 'N s I l *?) 0 - IU$
%l7 30 'Y' DRAFT-PRE ' y 4
SP Number -69.926 01 Revision: A Date Eff.: TPC TPC TPC i PROTECTIVE ACTION RECOMMENDATIONS O . 1.0 "URPOSE This procedure provides guidelines for determining protective action recommendations to be given to state and local officials.- 2.0 RESPONSIBILITY The Radiological Control Manager, Radiation Protection Manager or In plant Radiation Monitoring Technician is responsible for ensuring compliance with this procedure. PPF 1021.6@@-6.421
\
g% 9 0 . \ n/<T2nd
/J L. . . . -
3 3.0 DISCUSSION 3.1 The decision - ess used in determining a recommended protective action is based upon a waber of factors. These factors are release duration, f-- magnitude of re10,se, plume travel time, evacuation time estimates, ( dilution factors, shelter factors, dose limits, and dose savings. 3.2 After ,s mining a protective action, the Response Manager or Emergency Director will give approval to such an action before it is recommended to offsite authorities. 3.3 Because protective action recommendations could be influenced by factors not considered here, use this procedure with common sense and judgement. 3.4 Topics covered in this procedure include: PAfd* 8.1 Waterborne Protective Actions 3 8.2 Airborne Protective Actions 4 Appendix 12.1 - Waterborne Protective Action Guidance Chart Appendix 12.2 - Airborne Protective Action Guide Worksheet Appendix 12.3 - Evacuation Times Appendix 12.4 - Shielding Factors from a Gamma Cloud Source Appendix 12.5 - Thyroid and Whole Body Guidance Charts Appendix 12.6 - Protective Action Map
)4.0 PRECAUTIONS N./
- N/A 5.0 PREREQUISITES Energency Plan Implementing Procedure SP69 022 01, " Determination of Offsite Doses and/or SP69.024 91, Waterborne Release Dose Projection have been initiated.
6.0 LIMITATIONS AND ACTIONS N/A 7.0 PMTERIALS N/A 8.0 PROCEDURE ilaterbarne Protective Actions 6.1 Radiation Protection Manager or Designee, perforn the following: b N _/ s SP 69 026.91 Rev. A
/ / Page 2
8.1.1 Compare projected swimming (whole body and skin) and bosting dases ' obtained from SP 69.024.01 Waterborne Release Dose Proj cticn with
. the Waterborne Protective Action Guidance Chart (Appendix 12.1).
__ 8.1.2 Take the recommended protective action and report it to the
) Response Manager or Emergency Director for approval and inform the :
./ appropriate agencies (e.g. , Coast Guard) in accordance with Emergency Plan Implementing Procedure SP 69.009 01 Notifications. t Airborne Protective Actions 8.2 RadiologicalControlManager,RadiktionProtectionManager, In plant '.
Radiation Monitoring Technician, or applicable designee, perform the following: 8.2.1 Csmplete whole body and thyroid calculations, recording the following information in the appropriate items of the Airborne , Protective Action Guide Worksheet (Appendix 12.2). 8.2.1.1 Obtain area of concern (Item 1), expe .ed release duration (Item 2), windspeed (Item 3), and projected thyroid and whole body doses (Item 11) from SP 69.022.01 Determination of Offsite Doses. > 8.2.1.2 Calculate Item 4 and 5 of Appendix 12.2. V 8.2.1.3 Determine weather condition and evacuation time (Items 6 and 7). Determine the prevailing weather conditions and record this in Item 6. Adverse weather consists of t conditions which will significantly reduce traffic (T speeds, such as rain and light show. If severe weather , (m,/ (e.g. flooding or blizzard) conditions exist, a separate evacuation time will have to be estimated. 8.2.1.4 Complete Item 8-14 to determine projected, shelter, and evacuation doses. ~ 8.2.1.5 Complete Item 15 to determine whole body and thyroid indicated actions. 8.2.2 Based upon the results of Step 8.2.1.5 above, take the higher indicated action as the protective act!)n recommendation (Item 16) and record this on the Protective Actiou *!ap (Appendix 12.6). 8.2.3 Repeat this procedure for 1, 3, and 5 center line values. 8.2.3.1 Consider recommending the same protective action for adjacent zones. 3.2.3.' Coasider recommendint; the s a::e protective action for y v m as diet nu fr,, t% 91, u increases. 8.2.4 Transmit worksheet and the Protective Action >bp to the Emergency Director or Recovery Manager for approval. v SP 69 026.01 Rev. A
/ / Page 3
. .. g APPENDIX 12.1 Page I cf 1
. WATERBORNE PROTECTIVE ACTION CUIDANCE CHART i
)
; IF THEN Projected whole body or skin Instruct the U.S. Coast Guard dose due to swimming is equal to remove all swimmers within
; to or greater than I rem. a 1 mile distance of the plant i ,
- i Projected whole body dose duc Instruct the U.S. Coast Guard !
; to boating is equal to or to evacuate all boats and i greater than I rem. vessels within a 1 mile t distance of the plant I-i 4
i i 4 4 l' I i, l 4 I I h O l SP 69.026.01 Rev. A i /. / Page 4 i _ _ . - . . _ . , . - - - _ . - . _ _ _ ~ _ . _ , _ _ _ _ .._ _ _. _ . _ _ - - _ _ .
Appendix 12.2 Page 1 of 3 AIRBORNE PROTECTION ACTION CUIDE WORKSHEET
- 1. Area of Concern ( )
Location
- a. Distance miles la. miles
- b. Direction (degrees)
C. Zone
- 2. Expected release duration 2. hours
- 3. Windspeed =
meter /sec X 2.24 3. miles /hr.
- 4. Plume travel time = item la item 3 4. hours
= ;
- 5. Time uniti exposure begins (a cy; b) 5. hours (a or b) -
~~~
- a. If release has begun:
Time = item 4 - time celease has been in progress Time = - NOTE: If item Sa is a negative number, enter zero hours for item 5 ()T
\. .
- b. If release will begin later:
- Time = item 4 + time untti release Time = +
i 6. Weather condition and season (circle one for a,b and c):
- a. Normal Adverse Severe
- b. Seasonal Non-Seasonal
- c. Day Night
- 7. Evacuation time: 7. hours Use Appendix 12.3 along with information recorded in items 1 and 6 to determine the time.
- 6. E <;yggt ,ing t = lten 7 - iteu 3 8. __
hours l
- 9. Evacuation Exposure Period: Smaller of item 8 or item 2 9. hours
- gm l SP 69.026 01 Rev. A
/ / Page 5 l
t _ . - - - . -
Appendix 12.2 Page 2 of 3 AIRBORNE PROTECTION ACTION GUIDE WORKSHEET (CONT'D) THYROID- WHOLE BODY .
- 10. . Projected Dose (from SP69.922 91) 10. rem- 10. rem i
111. Measured dose from field monitoring teams (if applicable): . 4 Monitoring Team Dose Rate X item 2 rem /hr Thyroid X hrs. 11. rem rem /hr Whole Body X hrs. 11. rem
- 12. Most reliable projected dose 12. rem 12. rem (item 10 or,11)
- 13. Evacuation Dose
=
item 9 X item 12 item 2 I X (Thyroin) 13. rem X y (Whole Body) 13. rem
- 14. Shelter Dose Thyroid (a or b)
- a. For item 2 less than or equal to 2 hours item 12 X 0.33 = X 0.33
- b. For item 2 greater than 2 hours item 12 X (item 2 - 1.33) h item 2
=
X( - 1.33) 4- 14. rea (a or b) ' l Whole Body i lten 12 X Structural Shielding Factor s ie nmd .s 12. 3) i
.\ 14. rem i
O SP 69 026.01 Rev. A
/ / Page 6 i
_ . . _ . . _ _ . . . . . . . . . _ ~ . . . _ . _ _ . , _ _ _ _ . . . _ _ - - , _ , , . . -
r s_ Appendix 12.2 Page 3 of 3 AIRBORNE PROTECTIVE ACTION GUIDE WORKSHEET (CONT'D)
- l THYROID WHOLE RODY
- 15. Refer to the thyroid and whole Body No Action No Action {
Cuidance charts (Appendix 12.6) and ; Circle the appropriate action for each Shelter Shelter j i Evacuate Evacuate I
- 16. Protective Action Recommendation (Circle One)
No Action Shelter Evacuate (
- 17. Indicate item 16 on the Protective Action Map '
(Appendix 12.6) for the area of concern e i I I I O SP 69.026.01 Rev. A
/ / Page 7
\
_. ONG IS_.AND S
- 1 e O e O o O
- I
~ n w*;aff be'4 I' L e%, .*
'N*
g- , 7 s
%,,, c _ ;
gst,yu
- y '.
y
, z i
~
j f,c'- - 4
.$z*% . ,sf.
- tsee y
*;* n U
utco sat s e;;e. k c i} ) pr, *r wl,>,u\;
+ z. - .
_ \ ' 5 e ,,, 9
*/'
/ gb ,.
\., t
~
\
)' [,f' - %2 e
\
,c' .
'hg b 1 .
.c
) '; ;
p N m! d, s.,
,s ,
~
1
. e 9 i --
- " 3 ,h r
o' 1% a i
' 5 ,
. 1.
,C --l, v. a f = ~ tr *W ,
.u,,
Q # j
,,,,1~
.CW -
e 5"" " +: e Q : *
/d{VN Y's, p h j f 1
n ; ei x . 1 mh e n<n !. e" , E '
.? .,
t,.% wi c-
~ 5 -
e > r-@ e 4 ti@ = ' s =
.A
< .x.
s , , . s 1.--- ;r>,#: x . (...
- cs r ..
w @r 3 8 ,f - I R q I f k e ? R c,, e, : ig'e -;
. , errt'*3,M e\ *o -
g , e-s !*** 6,
,1 n
f , ad
-Q- x g N
--f
+f f ***
r ' i. a, s., i , g
'. f
- .4 w p.
hi Al .
~~"
' ge 6 .-
s # , s'
,i s -
.. "'3 s ,- .
l^ '
\
/
z. s% N e
?.
O cato 5 #
~ d e
j
APPENDIX 12.3 )UA J , Page 3 ,,' g LEGEND IONE BouNorgggg (vD ,...
. LILCO PLANT
- PRopgg o ' , .,.,.
*.= . . f ~ ' .
e f i x
*e i;
s ' b ,
- 1, -
, If A u y*.~ .4%.
A s to 8 ah
't, ii g g
r- w ( s s'@ t
,3, l
\'\
i yf 00 . ' s h#' .4 j"-\{t
.'g .
~
\s :
Qn $a s~ j ,N-- ;
?}s, ~\
e 3,c . s t ?.
\ . ,\.
?
3 [a t*\, s ,., < \ u ., y r .., I .. t f' ~ -s., t ,. ~~ %. 9 R
%+, .
n ;, ^ z .~ [ ; y, Rs pA n,3.,p=
,- t s ,,
V * (p! / a.)_ r
%. ! ,,- 9. 5/ _
< p}
@ u %h '%, y fi=~j i'~ ',r .
e s^ / ' ' )j %[L f"h '%u
\s
(
'4 c I
} e 4 i
- (
h 1
.1--- j f ""' !( N, f ,,,
m :::s ,, ./p
,s
,fj
.1 n%,,
f f
. en,*
'*:v .% c e
d
' s' ^_ s ..
, t .
" lh 7
s 3 YQt u . fs Q w[.s m-
,,f, -
Y wor, / ' u e n 4 SP 69.026.01 Rev. A
- Page 8
/ /
3
w Page 2 of 6 . 1 ,,
,A
- g. g s .
, s J ,g ,.
I
. /
~ n J tJ '
5 . . k> <-. . g
.' ..'., iL . j .\ J) we
- l
- r'* #
mn R .- s II 4
! .' . 'l'N-- s g9 , 5 ..
, v>d ;a ga
~
.,.,- 4 .
; .._,), ,.,\,
o' [xg.g,j, ' .*. 14 .t. .
, i,, +, . ,, g, .
5 -
=
, cp
{ g
... e
}
T* - . ,- e.,* I , A' { eN l
,g=-
- g ) ,3 **
- l l j- 1 A e m
*-
- U') * %, , %D l t ,'% .
.l y :
- e \ *,. c.
c' .,*~ *
.,) ,- st t,fJ
@l, . i
. g
-, i ~~ ; - C)s' v' \
~}
. , * - , $ }- . . ~l nt
- i
, , / \
;', p I '" -- ~ s
- 4.
'/
g
'.: ' .,p 0,y
.h
- 15. h. .!' if.y h.
- g. x v n, s, .ev n o -. ,f
.) , ..fy '2 0 \.,
t f .t >$ _, N <P ..
\ .,! ?:; ._i. -
' ,L ., . i ~ , ,
~
? l,
,\
O
,, ,;. p - \\y y ., - ,:n -
. . i q, -
(n gj ...q . -
- .= . g . .
/y.
1 g - ~e,4, ;. . _ ,, ,
.;n y-s,] __.
3 o . o g s 1 e- - 3s z d- Q"N '* ,l/ %- 9%. . . i
. )p.
3' iD l
- g. .
f . . ' ". j .. 3
<n
- c. @
i
.,, - .y.. - .
.. s. <
,, # s W .
* @ .i
.,. s, Il l
8'
, , f 4 s s m-/..
.- s.
, g 2.
INj =
,K ' .%
=
g
/N. q/
O
'J l (i
l (r) ,t -. 6 ,.. ,-l *- ~
.' -,e 2
' ,/ i I ',
;f
) .
Q g O l - '
( (
...c. . :,-de
,'fy ,
.s . - 8
.i
.-I ., ...
ga i g' ,# ,.a g ib ' g ufS Q ,.,I j > .pg- ,
-. n c . ., :l.
- 1 : <
. ha;l y
. \. ><' w}.T f <.jg'N j'
'x G' , ,;-l.
(~O s
\ [I (
- a. p' s. _.. .,.;, >.
ys
; .,y t./ \ j.- .-
, J f .,,, ,
. Q,' ' ;
~
Q \ -IA.'r ' / . - .. / ,7 , ( fe g'd , l V \ /. . ,, , .
,,wl j q _..,,, n. - ) . / . },.
1 Q 5 i a. < % 3
%(
y \.% t , , a , [ / ( - , _4
() s EVACUATION Tl BY WIND DIRECTION , O sEAsonm (ipernt. eo+./Drnews) 0-2 MILES ! O-5 MILES 0-10 MILES WEEK WEEK WEEK WEEK WEEK WIND DIRE ,6 ON Z ONE(S)f W E EK NIGHT ZONES ZONES DAY NIGHT i DAY DAY _ _.tU_G H.LT (towar , 2.25 225 ' Af f. 02 3~ o f AFKO S. .f 8 C. Cf W by W Vi A 2.25 AFG f.o 1 AFGKQ S~CB 3~.CY W _ A f.25 S~e3 _ S. 0f 50f ADFGKO S.fB S TS W by_ W W ,_ AD _ 2.50 2 55 ' ADFG
- f. 0 7 Sof S~ f6 f. l~B l' W S Vi AD l J.So 2 50 ADFG ADFGKO'.
4 W S W b'/ iW AD JSo 2,6b ADFG Sof 5 08 - : ADFGKRL f /7 f./ 7 3.n ADGKnLM 4.33 J.33 2.s0-. __ADG SW AD 3 ro
- - . . . - - . - - - . . _J. 5o . - -
SW by ' V/
. ADC J.So 2 56 ADCGH 4.f3 4.83 ADCGHKRLM 4.f7 4.47 ADCGH 4.E3 ADCGHRLMN S~#D S S V/ ADC 2 50 2.ro _ 3.17 _ _ _S.'#D SSW b n oc f, g f.s g DCGH 3.17 3./ 7 DCGitLMN J. / 7 J./ 7 S DC 2.42 2. -f 2 BConi 3.s 7 3.17 DCGulMND 3 47 3. o 7 2.t? CDHI 3.17 2 47 CDulunO 3.67 2 7f S by i' '. E lCD 2.17 SSt -._ j CD 2.17 2.s 7 CDHI 3. s 7 2 47 CDulNO 3.t 7 z.7f
- SSE by nE CD g 17_ Coni 3.17 267 CDulNO 3.67 2 75"
, . .l . . . . _ _ _ . . . _ . _ . 2. _.17. _ - - __ _ ~fo SE CDE 2.25 2 2f CDElJ 4.47 J.o f C D ElJ O S 4.47 3 73
- 2. 2 f CDElJ 4.67 4. 0/ CDElJOPS 4.47 4 83 S S E b y F fi r. cDE ,,
2.2f _ 4.67 4.0f CDElJOPS 8.47 J 83 3 ESE: CDE 2 25 22f CDElJ ESE by E DE 2. r 7 DElJ 4.47 g.0f DElJOPS g.f 7 3.I3
. >: 2. / 7 a ca p_._- a
.T.3 9 l EJ d.0D 3.33 EJOPS 4.of i? E E 2. c o 2.av EJ d.#7 3 33 EJP /, ## 33.3
'c~, " - - . - . _E by Et!E __ E 2.00 2 00 ADCDE 2. 5D f.fD N/A HIA w.
NO WIN: j o m g TIMES ARE EXPRESSED IN HOURS AND INCLUDE 20 MIN. FOR MODlLIZ ATION
A"*h-.
\
q s t !
'v/ EVACUATION Tl BY WIND DIRECTION ,
V . NCAl- JG4sCUAl. ( /DEM. CoND'T!adfd O-2 MILES ' O-5 MILES O-10 MILES WEEK WEEK WEEK WEEK WEEK WEEK ZONES ZONES i.ll N D D I R E ,. , ION Z O t3 E ( S ) DAY NIGHT DJ_Y NIGHT DAY NIGHT (toWare'
._. W by W' _
.'l _ . -
A
/. f3 /*13 AF J. 7f J. 7f AFKQ C. 3 S 5 33 W A /. f3 /./3 A F G- 4'. 7f 4. 7f AFGKQ 5~ 33 f. 3 3 W by w fi AD 2. Cb 2 Zb ADFG d.7f J.7f ABFGKO 5~ 3 3 .T. 3 9 WSW AD .2 .R .2.JD ADFG 4.7T 4. 7f ADFOKQL f33 f. 3 3 WSW by /.' _ AD J.ro 2,JD ADFG 4.7f 4. 7f
- ABFGKRL 4.92 4'.92 SW AD .2.tv 2,#a ADO J. aD J.as ADGKRLM J.92 J.9 2.
_ SW by SSW ., ABC 2.(D 2.fD ADCGH d'.4 B 4.J3 ADCGHKRLM 4. / 7 4./7 2 ra ADCGH d.33 SSW ABC 2.ZD
- f. rg ADCGHRLMN 4.fr 4.S8 SSW by :; BC 2. (2 2 42_ DCGH J. / 7 3.17 DCGHLMN J. t 7 J./7 S DC 2.42. 2. 4-2. DCOHI J.t 7 J./7 lBCGHIMHO J. / 7 J./7 S by S: E CD t.3 3 /,33 CDHI 2.33 f.7f CDHIMHO 2 23 2.2r SSE CD l.33 /.33 CDHI 2 33 /.7f CDHINO 2 !3 23f l_
SSE by E CD , . 33 1 53 CDHI 2 33 /. 7f CDHINO 2.C3 23f g p _ ._ _ _ .
~
SE CDE t. 6 f. t.7 CDElJ 2.23 2.r3 CDElJOS 2.13 p.J3 es . _ . _ _ _ _ _ _ _ __ _ ._ _7 - s?o SE by l' :E l CDE /.67 /. f 7 CDElJ 2.E3 2. P3 CDElJOPS 2.13 U.IS
'$ ESE CDE h67 f. f 7 CDEIJ 2.Z3 2 23 CDEIJOPS 2 73 2 33 2 ESE by C DE f. 67 /. i.7 DEIJ 2.s3 2.F3 DEIJOPS 2.23 2 13 m, c,,x E . _ I. E -
/.5D . _ _ _ /.rD EJ 2.33 2.33 EJOPS . _ _
2.23 2 33 3? E by EUE_. E /.fD /.I3 'EJ 2 33 2 39 EJP 2 33 2.33 m R; e.,
" i Ts NO WIND ABCDE 2,5D 7.53 N/A NtA TIMES ARE EXPRESSED IN HOURS AND INCLUDE 2D MIN. FOR MODILIZ ATION o -ey- e _ _ _ . - -
EVACUATION Tih BY WIND DIRECTION ,
.SEASo@l, ( ADVECKB" CdA/Dr774A&
0-2 MILES ! O-S MILES l O-10 MILES W i tJ D D I R E '. lbij ZONE (S) WEEK DAY WEEK NIGHT ZONES WEEK DR_ JRG H T WEEK ZONES WEEK DAY WEEK NIGHT (towarc l W b y V!: ?! A 2.67 2,47 i AF 4.cf 4 0f AFKQ C47 &&7 W A 2 67 2 67 AFG C. o f 4 37 AVGKO 4 67 4.$7 p. W by W! */ AD { J dD 3. N ADFG f.o f _ _ _ _ 4 87 l ADFGKQ [. 47 /*E7 WSW AD l 3. 4 3. G l ADFG /*0f (47 ADFGKQL 4.47 (,67 WSW by , ?/ AD 3 FD J rD ADFG g. o f 4. df .' ADFGKRL (d 7 6./7 [ _ _ _ _ _ _ _ _ _ _ _ _ _ _ SW Au 3.co 3 00 ADO J.J"7 J.Jf ADGKRLM (./ 7 C/7 SW by O ' '. W ADC Jeo S.ev ABCGH J~. 7[ 4 7f' ABCGHKRLM #f8 f(F SSW ABC J 3D J. e ABCGH ,fyr' g.7f ADCGHRLMN 4.FD 4.co SSW by <; DC p. r3 2.T3 ( DCGH g. 7f' g. 7f ,DCGHLMN 3 7f J 7f G ,f U C I
- 2. /3 2.f3 l DCGHI 37f 3 7f ' Ly c G H I M N O A33 3 7f S by St ~ : CD z. cr z.r7 CDHI JW 3. r 7 CDHIMNO 433 3'f SSE CD 2.C V rf CDHi J 7f' 3 t1 CDHINO 4.35 33f SSE by '; E CD 2.re 2.s7 CDHI 37f 3.17 CDHINO 433 3*f q SE by E '. E CDE 2 2 67 CDElJ S/2 4.73 CDElJOPS J~ 4~T #.#7
~
$ ESE CDE 2.67 2 67 CDElJ J~. Z*r 4.13 lCDGlJOPS #sr 4.r8
'h ESE by E (DE 7. f7 z.r# DElJ 5'57 4.r3 l DElJOP S J'#f 4 f# E _ 2 33 _ EJ 4. 7f 4. @ EJOPS Af.2 3 A.F1
'o - . _ . E_ _
- 2. 3 3_ _
~
E by ENE __E___ )k Z 33 233 EJ J77 4.FD EJP (P3 /. #9
- g :%
ss = J.FD sa p NO WitJo lADCDE J #D N/A lNIA ] u$ N O m k TIMES ARE EXPRESSED IN HOURS AND INCLUDE 20 MIN. FOR MODILIZ ATION g
*s,
n g ( ) ( ) EVACUATION Tl BY WIND DIRECTION AfC+ .SCnseA/M [4DW=cC9 CwD e vioMC) 0-2 MILES O-5 MILES 0-10 MILES V/ ! N D DI R E , EON Z O fi E ( S ) DAY f ZONES DA H ZONES N[ N (towar j f _ , _ _ . . . . . . . . _ 7_ "AFKQ 6 33 4 33 V/ b y V! '.' A 2. / 7 2 17 Af 4 67 f. ( 7 V/ A 2.17 2.f7 A F G~ # 47 5 47 AFGKQ 633 4 33 W by Y!. // AB J a0 .3. #D ADFG C &7 J"47 ABFGKQ (.3 3 4.73 W S V! AB J FD & #8 ABFG C &7 T47 - ABFGKOL 4 33 633 WSW by ' : V/ AD J.#D J #' ABFG Cs7 f.67 E ADFGKRL #;f3 .S~#5 SW AD J.r* 38 ADG Jst J.." ? ADGKRLM 4.47 g.67 SW by '; ; V/ _ [ ADC
]J.a3 .
J '* ABCGH c.d f./7 ADCGHKRLM E s'D 2'#D _ __ __ S, S W ABC J,#o l '8 ADCGH J~ff f/7 ADCGHRLMN #ft CTI S S W b ,, :; DC z.r3 z.s2 DCGH 3 7f' 3 75 DCGHLMN 8 7F" 3 7J' S DC 2 73 2 73 BCGHI 3 77~ J. 7F" 'DCGHlMNO 3 7T* 3. 7f S by S'~ CD t. .s r t.r2 CDHI z.1s- 2. or CDHsMNO 3 2 ~3 2 67 [ SSE CD t.cf I. TT CDHl 2. 7.r* 2. or CDH1NO 3 33 2 67 SS3 by aE CD /.cr J.rr CDH1 27s* 2. o r CDHsNO 3.23 2.67 y> SE lCDE 2.os z.so CDEIJ 333 339 CDElJOS 3 33 3 33 $E oa CDE 2.av 2 00 CDEiJ 3 33 3 33 CDE1JOPS 3 39 J 33 o 5. _ . _ _ _ _SE by VuE . . - 3 13 ** ESE CDE .2* eo .2*!v CDEtJ 3 33 5.~3 3 CDElJOPS 3.33 N
- ESE by E DE X.a, DEIJ J. 89 J3S f DEIJOPS 5 33 - #39 .
s.
$ . ._ . . . . L . .2. #o_ _ ._ -.._. ._ -
u
- 2. 7f E
-7 / f EJ .7.15. ..' . 2 7f* lEJOPS .. 2.7f ;@ . . . . ._ E . .- .- - _I.7s' . . _ ....
E by EfJE E / 'Jr' /.75* EJ 2 77~ 27f EJp g.yr 2 7/* mx 3 #* yQ N O W lt): ABCDE 3.0D NIA NIA O* + w TIMES ARE FXPRESSED IN HOURS AND INCLUDE 20 MIN. FOR MODILIZ ATION r ex .
APPENDIX 12.4 Page 1 of 1 i REPRESENTATIVE SillELDING FACTORS FROM CAFDIA CLOUD SOURCE (1) StilELDitiG STRUCTURE OR LOCATION FACTOR (a) REPRESENTATIVE RANGE Outside 1.0 --- Vehicles 1.0 -- Wood-frame house (b) 0.9 -- (no basement) Basement of wood house 0.6 0.1 to 0.7 (c) Masonry house (no basement) 0.6 0.4 to 0.7 (c) Basement of masonry house 0.4 0.1 to 0.5 (c) Large office or industrial 0.2 0.1 to 0.3 (c), (d) building I l 4
\
(a) The ratio of the dose received inside the structure to the dose that would be y recci,ved outside the structure. 4 (b) A wood frame house with brick or tone vencer is approximately equivalent to a masonry house for shielding purposes.
.(c) This range is mainly due to dif ferent wall materials and different geometries.
(d) The shiciding factor depends on where personnel are located within the building (e.g. the basement or an inside room). (1) Ref: Sand 77-1725 (Unlimited Release)
.l SP 69.026.01 Rev. A
/ / Page 14 I
APPENDIX 12.5 Page 1 of 1 THYROID GUIDANCE CilART O U 1F THEN *
-Projected dose (Item 12) is less than 5 rea No action Shelter dose (Item 14) is less than 25 rem Shelter
- for children and women of childbearing age.
Shelter dose (Item 14) equal to or greater than 25 rem and evacuation dose (Item 13) Shelter
- equal to or greater than shelter dose.
i Shelte dose (Item 14) equal to or greater than 25 rem and evacuation dose (Item 13) Evacuate less than shelter dose. Shelter is to be with ventilation control. Ventilation control means turning off air conditioners or fans, closing doors and windows thus preventing access of outside air. W110LE BODY GUIDANCE CHART IF TilEN . Projected doke (Item 12) less than 1 rem No Action Shelter dose (Item 14) less than 5 rem Shelter
- Shelter dose (Item 14) equal to or greater Shelte r*
than 5 rem and evacuation dose (Item 13) equal to or greater than shelter dose. Shelter dose (Item 14) equal to or greater Evacuate than 5 rem and evacuation dose (Item 13) less than shelter dose.
'6. . a i u, L. .w . :t; i.on c. acal. Ve n t i u. ; & coatrol neaus turning off air conditioners or fans, closing doors and w.ndows thus preventing access of outside air.
O SP 69 026 91 Rev. A
/ / Page 15
PROTECTNE ACT lo l e
- C .
f c !
,9 L % ,**
W! '"",g, yr* * , .e *; o
$!,W6 '>
'n; .,
N s&W.- g
' taco en '~~'
=
'a
' ,R{4l,% ..,,
g A
\g ,
xi mme*M W 3
,.
- i\
.-~.- j , -
\eh*
g ss o'
%\ ay e
.^
e
.i,.
0 N- ,
*R t
5
\
\
/
/ h i
q \ } .. ~
' y e x,e
,, )' / ) Ms]W.i'1R@
jy \! *: l
/ '
/ .
get,
. ~- "*- '@
1
- d
., g f m# i
%^ ,
s i - a 5 J t ,f . y
-p ' mf 4 /.o
' %, gg
- s,
-r # e =' '
e
& e;;~7-
~s- e. :
I a fo j, ' e e
% BN' R,,
\
1
=
7.' l' K-H , ,v I
, bi g
- y \ 'i f \
- l '%% l '
m~. s f j i !; @ il ~ . y ,'n - @ ! A
~
' A qq f g ,- ;
lj
%{~ f~/ ' i; g -- !. f@ ;;J
%x
, - y4,[ i i
N e. 6; ,g 4 f[, g
- w .:
,c
- g
.s% s. -
\ r 3,.. v ;
~ .,,.
r w'
~}*
ts - M 3 a
. Y p - ' ...-
r * * *
- i '*. 4 e !. -
" , / *^ -) i N i. Y g
> l
'w '
4 * [ a n, se 8AY t' . a 3 - __ p W
APPENDIX 12.6 I r se 1 a 2 DN MAP 1 R i LEGEND ! 5 f i I ZONE BOUNDARIES . b i LILCO PL ANT ' PROPERTY 1.9 { I i ! I
. [
4 N ! - I,
\. . ? **
Y , s I;
. '%, -,., imc%t
,w , @ ,; n4s ..
i. 1
\,3 s ~
..a ,
s
.. yr b % ,
*T 3
\ s. M
~ g l.
k '\\. j R /[.v ' N '[Ri h r A 9[ k '
; y P
r .h-g
~
f [l _
<, \ b ~
j, . s y &, t . y x, +.,.
, % ~p f a
* '* x y 9o y
(
, ; y
,y - ~m; ,,
- . u.,
,hW S i. ?
k ! " R' , h3
' s
's ..
I r i ~ m.a , e, , ,m.
@ ...' S' k ,
'C m ..,,
/
.. ..R s h . . , , % .'
j_ Jy, I f"*L %,
g A y p g g
} * ),
t i p IS s 1 f I,
,,,,,,., e.srwr y SA ,1
%. /
9 #*i m DESIGN ATE ARE AS WITH RECOMMENDED i ./~' lx ,/ PROTECT!VE A CTI O N S Y.S C L S AS FOLLOWS: i i
/ o Q N-NO ACTION E-EVACUATE I S-SHELTER F-FOOD,W ATER & MILK pRnCu t s e CONTROL -
$]- g . O-O'T H E R ( S P E CI F Y ) SP 69 026.01 Rev. A
/ / Page 10 l
^ m m 12.6 PROTECTIVE ACTION g MAP -
Page 2 of 2 LEGEND j ,
, 1 .
x zmt souscaanics V\ ' f i * , , V c '.:: tn.co rtant enoetaty CAA
. y ,
~
($ * ; t,* .w, e =
- . w-W=.. .a 15 #. ~ ' F- T.k M7" * ' Z "sY . y
,~-g '. D .Wx: ,
's
*/ w.;J yp. - --
~
~
N.__.jr "; , -
\* ;- . n a
y 0- e ,/ .t ,' I)g :
). , ,' 'h.,$ ,
l k., I y N ,/ f h @'{; .
\-,
- '. : 3.@
t
@ ,W .: - g is .
f,
.< '~ 3
[/'7N h/,. ,[' ,O h@ \ ,flk;I,.g ) ',; ',s
- 2 3 \
N it ( , t /
.y 2 .. ' .// -
x,v vu a ; u'i.,1
.)
~
,D p',e e' A h4 T [ "
s h- - of 4 . .
/
,%r5.,1 ~i ..,'.&o*
~ - c. gE l . \/ l . p~}')
' "~ ' ;
i h
'l~,... , & .s:?-\- A\M
? 1
~
w! xi i @ i' ,
~~
'~
~
'- ~
f CQ , K L..:. '~ [, ,-
~.1 @ ;; wk--7~}u- &~ . . t g
..e
, p' -
v -
% 8' 3' C j;
*- % r } , y s
[- 1, .
' /. % .
r *. r ,.
, 4 .- i
-u . . . // f - . t.-
'- ....< ......-- D SIGN ATE ARE AS WITH RECOMMENDED O$ f j ~
* ! "~j 'N PROTECTIVE ACTION SYMBOLS AS FOLLOW g"
.~ .], d
/ .
., I.(., / 'e .f, bN N-NO ACTION E-EVACUATE
\ N .' ( ) \ /
# S-SHELTER F-FOOD. WATER & MILK
- wcaic t s o . CONTROL -
* . e s ,
^ A
- O-OTHER(SPECIFY) sacar i sm.g / ;sa< - .
J -e./ y
- l - ,-
i . #^ 1 [l SP 69 026 01 Rev. A
// Page 17
1 9,* ,
' Submitt.*d:
^ ^pproved:
(Plant Manager) S
, / DRAFT-PREUMBIARY SP Number 69.636.61 Revision B Date Eff.
TPC TPC TPC EVACUATIONS DURING AN EMERGENCY 1.0 PURPOSE This procedure provides instructions for implementing an emergency evacuation of areas within the Shoreham Nuclear Power Station and adjacent areas onsite. This procedure does not apply to the evacuation of members of the general publi: from affected areas offsite,. as this is described in the emergency response plans of the risk jurisdictions. ! 2.0 RESPONSIBILITY The Emergency Director (Watch Engineer, until relieved) is responsible to ensure that an appropricte evacuation is implemented when conditions warrant
- such action.
t , g -
,s
/ _.., .%
\ 4 PPF Id21.6d6-6.421 \ \h 7 ,
1-
- l. . - - - . --.- . --,-.- .-. . . . . - - , _ - . _ . - _ . . . - . - . - - - --
4 3.0 DISCUSSION 4 3.1 This procedure is primarily directed at evacuations initiated by actual p or imminent radiological conditions. The. basic actions' described herein also apply, where appropriate, to evacuations related to other habitability hazards such as toxic gases or fire. 3.2 An evacuation is the orderly, accelerated relocation of non-essential
; personnel from a plant area as a means of reducing their exposure to radiation or another health hazard.- An evacuation may be implemented in response to 'already existing condftion(s),. or in preparation of imminent
- conditions, which are described in the protective action guides which follow. The following types of. evacuation are discussed in. this procedure:
3.2.1 Local Evacuation - a localized condition affects a small area, i such as a room or cubicle. Evacuation is to the nearest unaffected location. 3.2.2 Local Evacuation Reactor Drywell - Similar to local, but involves the reactor drywell. Applicable during shutdown periods. 3.2.3 Restricted Area Evacuation - A widespread condition affects j several areas within the restricted area. Evacuation is to a designated assembly area within the protected area, but outside the restricted area. 4 3.2.4 Site Evacuation - a widespread condition has affected, or could effect, areas outside of the restricted ' area. Evacuation is to an onsite assembly area, with subsequent dismissal to an.offsite location. 3.2.5 Immediate Site Evacuation - widespread conditions have resulted in radiological conditions onsite, which mandate immediate evacuation to an offsite, remote assembly area. The primary difference between the site evacuation and an immediate site 4 : evacuation is the location where personnel and vehicle monitoring will'be performed. ! .k* 3.3' Contractor / vendor organizations with more than 20 employees-onsite are .
',' (' -
- O responsible for developing and maintaining an evacuation plan applicable j % to their employees, and in the event of a restricted area or site evacuat'r:..
gare responsible for implementing that plan.
~
In particular, contractor ( ' organizations are responsible for personnel accountability for their own {pirsonnel. Such plans shall be submitted to the Emergency Planning
? ,
Coordinator and the Review of Operations Committee for approval. [ " sCont'ractor organizations' with less than 20 persons onsite will be treated s as station personnel for the purposes of evacuation. s ; 4 r , + + t SP 69.63d.61 Rev. B
- / / Page 2 i ..
~
-y-n.
m _ . , . - _ _ . _ _ . _ _ _ . _ _ . , , . _ . _ . . _ _ _ , _ . . _ _ - ,. ._ , . _ _ _ . ~ . _ _
I
~ 3.4 Topics covered in-this procedure:
Page 8.1 Local Evacuation - Except Reactor Drywell 4
-O 8.2 8.3 Local Evacuation of the Reactor Drywell Restricted Area Evacuation Guidelines 8.4 Restricted Area Evacuation 8.5 Site Evacuation Guidelines 8.6 Site Evacuation 8.7 Immediate Site Evacuation, Guidelines 8.8 Immediate Site Evacuation' ,
- Appendix 12.1 Criteria for Mandatory Evacuations Appendix 12.2 Evacuation Summary Appendix 12.3 Shoreham Remote Assembly Area (s) Map Appendix 12.4 Site Evacuation Route and Traffic Control Map 4.0 PRECAUTIONS _
l 4.1 The implementation of an evacuation must be based on the protective acti::: which will result in the lowest personnel exposure. Site evacuations I should be initiated either before or after the passage of the release, and evacuation routes should be chosen to lead personnel away from the path :f the plume. The Emergency Director should consider the dose rates at the personnel assembly area, dose rates onsite, dose' rates along evacuation routes, number of personnel onsite, and whether or not the emergency can ':+ mitigated prior to personnel receiving significant. exposures in making a:
-s evacuation decision.
\' l 4.2 The evacuation criteria of Appendix 12.1 are based on the recommendatic s of the National Council on Radiation Protection (NCRP), and apply only. t:
emergency situations in which the increased personnel exposure ~is necess12--
- to mitigate the consequences of an accident. Such exposures, although -
, technically justifiable, are in excess of Federal radiation exposure
, standards and are therefore not applicable to non-emergency situations, <
or to most recovery operations following an emergency. Evacuation or any other appropriate protective actions should be implemented to maintife; personnel exposure as low as reasonably achicvable and with normal stati:: radiation exposure guidelines and limits. 5.0 PREREQUISITES _
-5.1 A-local evacuation (section 8.1) shall-occur if any of the following
- limits are exceeded
5.1.1 General access area radiation monitor alarm (>5 mr/hr) 5.1.2 Building airborne monitor indicates airborne activity in excess of I x 10-9 pCi/cc unidentified mix or in excess of IMPC for identified mixes in areas not posted as Airborne Radioactivity Area. . 5.1.3 Alarms on continuous air monitors (CAMS) SP 69.636.61 Rev. B
/ / Page 3 I _~ - _ _ _ . -_ _ . _ . . _ _ _ . _ . _ _ _ . __ _
~
5.1.4 Results of surveys with portable survey equipment indicate significant unexpected increases in area radiation levels. p ( I 5.1.5 Commencement or a plant operation which is known or projected to cause significant increases in radiation levels in occupied areas (eg: movement of traversing incore probes (TIPS), ' starting Engineered Safeguards Feature (ESP) equipmer under core damage conditions, etc.) 5.1.6 Fire in any occupied area 5.1.7 Toxic or flammable gases or heavy smoke observed or reported in any' occupied area. 5.2 A local evacuation of the Control Room should be implsnetited upon the decision of the Watch Engineer that the Control Room is no longer
'nabitable. Respiratory equipment and other protective measure should be implemented as the primary protective action, with evacuation u3ed only in the event of:
5.2.1 Uncontrollable fire in the control Room 5.2.2 Ileavy smoke or toxic or flammable gases in the Control Room 5.2.3 Any other severe condition, ubich in the judgement of the Watch Engineer, warrants controlling the plant from the remote shutdown panel. (d) NOTE: A Control Room evacuation is implemented in accordance with emergency operating 1rocedure SP 29.022.01. 5.3 A local evacuation of the reactor drywell (during shutdown periods) may be implemented in response to the existence of one or more conditions identified below: 5.3.1 Criticality accident / fuel. handling accident 5.3.2 One or more of the conditions identified in section 8.1.1 of this procedure. 6.0 LIMITATIONS AND ACTIONS N/A 7.0 MATERIALS AND TEST EQUIPMENT 1 N/A
.0 PROCEDURE 8.1 Local Evacuation - Except Reactor Drvuell NOTE: A local evacuation may be initiated by personnel in the affected
() v area in response to observed conditions, portable survey instrument SP 69.630.61 Rev. B
/ / Page 4
The procedure readings, or locally alarming radiation monitors. steps below assume that the evacuation is initiated by indicati::s 7-s, alarms observed in the Control Room. As a result, some steps
) may not be applicable to all local evacuations.
(J 8.1.1 Based on reported conditions, the Watch Engineer or designee shall select an assembly area for personnel in the affected area. This assembly area should be located just beyond the affected area, but should be in a low radiation area. 8.1.2 The Watch Er *neer or designee shall announce over the page party system:
" Attention, all station personnel. There is a high radiation level (or other hazard) indicated in the (specify area) .
Personnel in the area should evacuate to (specify location .' Continue with additional instructions as necessary. 8.1.3 Repeat the announcement three tines at approximately one-minute intervals. 8.1.4 Personnel evacuating an affected area should proceed to the assigned assembly area and standby for personnel monitoring as determined by Health Physics personnel sent to 'the scene. 8.1.5 The work crew foreman /lendman, the senior individual present, or the Health Physics technician assigned to the area (if applicable) will ensure that all personnel have evacuated the ('}' x- affected area and report this fact to the Control Room. 8.1.6 If reports indicate the need, search and rescue measures shall be initiated as provided in SP 69.080.01, Search and Rescue. 8.1.7 The Watch Engineer (Emergency Director, if applicable) or designs
- shall direct Health Physics personnel to conduct air sampling and radiation surveys in the affected areas to identify the extent.
nature, and if possible, the source of the problem. Direct Health Physics personnel to perform radiological surveys in the assembly areas also. 8.1.8 If the results of radiation surveys at the designated assembly area indicates the need, personnel should relocate to another assembly area. Radiation Protection Manager or designee evaluate the need for a Restricted Area Evacuation. 8.1.9 On the basis of surveys performed in the affected area, Radiatic: Protection Manager shall allow personnel to return to the area, or have health phystes persennel establish nopropriate access control provisions in accordance with the health physics procedures until radiological conditions permit relaxing access controls. (N SP 69.036.d1 Rev. B V / / Page 5
8.2 Local Evacuation of the Reactor Drywell
,s NUTE: A local evacuation of the reactor drywell may be initiated
( ) by personnel in the reactor drywell area in response to observed
'- conditions, portable survey instrument readings, or locally alarming radiation monitors.
8.2.1 Based on reported conditions, the Watch Engineer (Emergency Director if applicable) or, designee shall select an assembly area for personnel vacating the reactor drywell. This asse=bly area should be in a low radiation area. An announcement of the following shall then be made over the page-party system:
" Attention all station personnel in the reactor drywell. There is a high radiation level (or other hazard) indicated in the reactor drywell. Personnel in the reactor drywell should evacuate to the drywell access control point."
Continue with additional instructions as necessary. 8.2.2 Repeat the announcement three times at approximately one-minute intervals. 8.2.3 Personnel in the drywell should stop work, and immediately proceed to the drywell access control point. At che drywell access control they should remove all protective clothing, unless otherwise directed by Health Physics personnel, and clear the access control point, signing out on the appropriate radiati::
, work permit.
f)\ 8.2.4 The Watch Engineer or Health Physics Engineer (Emergency Director or Radiation Protection Manager if applicable) shall direct health physics personnel at the check point to review radiation work permit sign-in sheets to determine if all personna*. have exited the drywell. 8.2.5 If necessary, search and rescue measures shall be initiated as provided in SP 69.080.01, Search and Rescue. 8.2.6 Health physics personnel at the drywell access control point shall conduct air sampling and radiation surveys in the dryvell to identify the extent, nature, and if possible, the source of the problem. In addition, appropriate surveys will be perfor:+i in the vicinity of the access control point. 8.2.7 If the results of the radiation surveys at the access control point indicate the need, personnel should relocate to another assembly area. Radiation Protection Manager or designee, evaluate the need for a Restricted Are evacuation. 8.2.8 On the basis of surveys performed in the affected area, Radiati: Protection Manager, allow personnel to return to the area, or have Health Physics personnel establish appropriate access ( control provitions in accordance with the health physics pr::edur es.
\s -} until radiological conditions permit relaxing access controls.
SP 69.630.01 Rev. B
/ / Page 6
8.3 Restricted Area Evacuation Guidelines
,_s 8.3.1 A restricted area evacuation shall be implemented upon occurrence q of one or more of the following abnormal conditions:
w/ 8.3.1.1 Multiple valid area radiation monitor or ventilation monitor alarms indicate a widespread, unlocalized problem. In the event area radiation monitor alarms occur in two out ,of three plant buildings (reactor building, radwarte building, turbine building), a Restricted Area evacuation should be implemented within the times specified in Appendix 12.1 for each range of dose rates or radiciodine concentrations prevailing in the affected area. 8.3.1.2 Other safety hazards, such as toxic gases, fire, flammabic gases, uncontrolled live steam, affect widespread areas. 8.3.1.3 On-going security compromise. 8.3.2 Any condition which makes a site evacuation likely. A Restricted Area evacuation may be implemented first, if time permits, to facilitate accountability and to minimize confusion. 8.4 Restricted Area Evacuatio'n 8.4.1 The Emergency Director or his designee shall sound the " PULSE"
/l evacuation tone using the multitone generator and announce the
(_ - ) following over the page party system:
" Attention all personnel. A high radiation. level (or other hazard) exists in the (specify location) . All personnel evacuate the Restricted Area and proceed to your designated assembly area and await instructions. Personnel with emergency assignmer.ts at the Technical Support Center or the Operations Support Center proceed to your assigned location".
8.4.2 Repeat the alarm and announcement three times at approximately one minute intervals. 8.4.3 Implement appropriate personnel accountability measures as provid a d
~
in section 8.2 of SP 69.030.02, Personnel Accountability. 8.4.4 Personnel within the Restricted Area shall proceed directly to the Health Physics Access Control Point, removing protective clothing and performing appropriate personal contamination monitoring at the local control points in accordance with the Shoreha, Ucalth Physics prowdures. If conditions at the Ice d control points nake tinely evacuation necessary, or preclude personnel monitoring, monitoring shall be performed at the Health Physics Access Control Point. Health Physics personnel at the local control points will direct personnel appropriately. kg)_ SP 69.633.61 Rev. B
/ / Page 7
8.4.5 Once clear of the control point, personnel will proceed to their
/ss designated assembly area.
i
'/ 8.4.6 If necessary, based on the outcowe of the accountability efforts or other reports, search and rescue measures shall be initiated as provided in SP 69.080.01, Search and Rescue.
8.4.7 If a radiological hazard exists, the Emergency Director or the Radiological Protection Manager shall direct Health Physics personnel to perform radiological surveys in the affected areas to_ identify the extent, nature, and if possible, the source of the problem (health physics personnel shall also perform radio-logical surveys in the designated assembly areas). 8.4.8 If the results of the radiation surveys at the designated assembly area (s) indicate radiation levels la excess of 5 mrem /hr., or gross airborne radioactivity (less noble gases) in excess of IE-9 uCi/cc, or if continued occupancy is expected to exceed 10 MFC hour for isotopic mix less noble gases; relocate to another assembly area, or if radiological conditions are widespread, initiate a site evacuation. 8.4.9 On the basis of radiation surveys performed in the affected area, Radiation Protection Manager or designee, shall allow personnel to return to their normal work stations (Section 8.5.11), effect an orderly early dismissal (Section 8.4.11) or implement a Site
, Evacuation as described in section 8.6. \
N 8.4.10 If personnel are to be allowed to return to their normal work stations (with 'the exception of those areas still affected, if applicable), Control Room Operator shall announce three times:
" Attention, all station personnel, all personnel may return to their normal work locations and resume their work. Access to the-following areas (specify areas) , is restricted. All personnel stay clear of these areas'" .
8.4.11 If non-essential personnel are to be released early, and no significant release has occurred, the Emergency Director shall direct craf t forenen/ supervisors to release their crews in an orderly manner. If an early dismissal is desired, but significant airborne releases have occurred such that monitoring of personal vehicles is necessary, implement a site evacuation as described in Section 8.6. 8.5 Site Evacuation cuidelines 8.5.1 A site evacuation shall be innlenented upon occurrence of one or more of the following abnormal conditions:
.1 Radiological conditions in any previously Unrectricted Area, (including areas onsite but outside of plant buildings).
(} N._- which will result in personnel dose rates in excess of 5 nrem/hr or a projected dose in excess of 100 mrem whole body SP 69.03d.01 Rev. B
/ / Page 8
and/or airborne radioactivity in excess of 1 MPC or 40 MPC-hrs / week from uncontrolled sources of radiation.
\
('- .2 Significant ground level atmospheric releases have occurred or are projected to occur.
.3 Other safety hazards, such as toxic gases, flammable gases, and/or fire affect widespread areas onsite and, in particular, the prim y assembly area.
.4 Adverse weather conditions such as floods, hurricanes, or tornadoes are. present or are expected to occur. Normally in the case of adverae weather, advance weather warnings will provide adequate time for an orderly dismissal of station personnel without the need for evacuation.
8.6 Site Evacuation 8.6.1 Control Room Operator sound the " WARBLE" evacuation tone using :~ne multitone generator. 8.6.2 Control Room Operator announce the following over the page party system (including all buildings and area within the exclusion area):
" Attention all station personnel. All personnel except those with emergency assignments shall evacuate the site promptly and orderly. Proceed to the guardhouse, turn-in your security badge and dosimetry, pass through the portal monitor, proceed ::
(~)/
\s the employee parking lot, and await further instructions. Do not leave the parking lot until directed to".
If the secondary guardhouse is in operation, add the following:
" Contractor and vendor personnel who entered the site via the secondary guardhouse, should use that guardhouse, and proceed ::
the warehouse to await further instructions." Continue with additional instructions as necessary. 8.6.3 Repeat the alarm and the announcement three additional times at one minute intervals. 8.6.4 Impicment appropriate personnel accountability measures as pre riisi in SP 69.030.02, Personnel Accountability. 8.6.5 Personnel within the Restricted Area should proceed to the designated assembly area, without delaying at the Health Physi: 5 Access Control Point for monitorint. If nersonnel suspect excessive contamination on their protective clothing, they should don a clean pair of coveralls over their contaminated clothing. Otherwise, personnel should proceed to the designa:ai assembly area, b(_/ SP 69.630.01 Rev. B l / / Page 9 l
~
8.6.6 Parsonnel monitoring of station personnal will be cccrmplished ':7 passage through the guardhouse portal monitors. If the guardhousa portal monitors are not functioning, or if background levels renda them unusable, direct Health Physics personnel to the assembly area
.(-~.) with portable friskers. Personnel found to be contaminated should be returned to the station for decontamination, if conditions permit.
8.6.7 If necessary, based on the outcome 'of accountability efforts or other reports, search and rescue measures shall be initiated as provided in SP 69.080.dl, Search and Rescue. 8.6.8 The Radiation Protection Manager shall determine the need and extent for personal vehicle monitoring and additional personnel monitoring and will establish appropriate monitoring stations consistent with the guidelines of SP 69.030.03, Contamination Control During Emergencies. 8.6.9 Security shall provide appropriate personnel to direct traffic onsite and at the intersections of North Country Road and the sita access roads. If monitoring is to be performed at the LILCO substation, Security shall be notified to direct-all site traffic towards the substation. 8.6.10 When traffic control and radiological monitoring stations are read (as applicable) and accountability efforts are essentially comple:s. a Control Room Operator shall announce over the page system (including all buildings and areas in the exclusion area): f)
\- /
" Attention all personnel. All personnel except those with emergency assignments, proceed to your automobiles, and exit the site orderly and promptly. Obey the directions of traffic control personnel. Proceed to the radiological monitoring station , located on the site access rood near Route 25A. Following monitoring proceed to the (remote assembly area) _ (or to your homes) ."
011 (No monitoring required)
" Attention all personnel. All personnel except those with emergency assignments, proceed to your automobiles and leave the site orderly cad promptly. Obey the directions of traffic contre; personnel. Proceed to the (remote assembiv area) (or to ycur home s) " .
8.6.11 Repeat the announcement three additional times at one minute inte rvals. 8.6.12 At the radiological monitoring station, vehicles found to be contaminated shall be directed by health physics personnel to the i RCO substation for decentamination efforts. 8.6.13 When the site evacuation is comple*e, Security personnel not necessary to maintain an appropriate security posture should be directed to the remote assembly area to await further instructiers. (
\__) SP 69.036.01 Rev. B
/ / Page 10
8.7 Immediate Site Evacuation Guidelines An immediate site evacuation shall be implement at upon occurrence of g ~g radiological conditions in widespread areas onsite of such magnitude ( j that personnel exposures in exc_as of 5 rem whole body or 25 rem thyr:id would be likely if a normal site evacuation was implemented. 8.8 Immddiate Site Evacuation 8.8.1 Control Room Operator soun,d-the "
" YELP" evacuation tone using the multitone generator.
8.8.2 Announce the following over the page party system (including all buildings and areas within the exclusion area):
" Attention all station personnel. All personnel except those with emergency assignments shall evacuate the site immediately.
Proceed in your automobile to (remote assembly area) and await further instructions. Personnel monitoring will be perfornei at the remote assembly area. Continue with additional instructious as necessary. 8.8.3 Repeat the alarm and the announcement three additional times at one minute intervals. 8.8.4 Imolement appropriate personnel accountability measures as provided in SP 69.030.02, Personnel Accountability. [\ 8.8.5 Personnel within the Restricted Area should proceed to their . vehicles, without delaying at.the Health Physics Access Contr:1-Point for monitoring. If personnel suspect. excessive contamina:i: on their protective clothing, they should dan a cican pair of coveralls over their contaminated clothing. 8.8.6 If necessary, based on the outcome of accountability efforts er other reports, search and rescue measures shall be initiated as provided in SP 69.080.01, Search and Rescue. 8.8.7 Security have appropriate personnel direct traffic onsite and at the intersections of North Country Road and the site access roads (if applicable). 8.8.8 The Radiation Protection Manager shall deternine the need and
- extent for personal vehicle monitoring and additional personnel monitoring and will establish appropriate monitoring stations at the remote assembly area, consistent with the guidelines cf SP 69.030.03, Contamination Control During Energenci,es.
8.8.9 Coataminated vehicles should be isolated pending decontanim:L:-
- Contaminated personnel shall be decontaminated at the (La
- er
)' SP 69.03G.01 Rev. B
/ / Page 11
(} 4
- _ ,_ _ __ . , . , _ _ _ . _ _ _ __- _ _ _ _ _ . - . , , . . , _ , _ , ~ . _ ~ . , ,__,.,,,y _ _ . _ _ -.
8.8.10 When the site. evacuation is complete, Security personnel not necessary to maintain an' aporooriate security posture should be directed to the remote assembly area to await further assignment. 8.8.11 When personnel monitoring efforts are complete at the remote assembly area, and onsite accountability efforts are essentially I complete. the Emergency Director shall release personnel to their homes, or if an offsite evacuation has taken place, to the i designated reception center for'his home community. f 9.0 ACCEPTANCE CRITERIA I , 'N/A 10.0 FINAL CONDITIONS All non-essential station personnel have been evacuated from the affected areas to areas of safety and, where applicable, have been appropriately monitored for contamination.
11.0 REFERENCES
11.1 Shoreham Nuclear Power Station-Emergency Plan and Emergency Plan j Implementing Procedures. , t 11.2 Shoreham Nuclear Power Station llealth Physics Manual 12.0 APPENDICES 12.1 Criteria for Mandatoty Evacuations ( 12.2 Evacuation Summary 12.3 Shoreham Remote Assembly Area (s) Mao _ - 12.4 Site Evacuation Route and Traffic Control Map f j _]
^
l j SP 64.036.01 Rev. B
- / / Page 12 i
. ~ . . . _ - . , - - . , , , , - , _ . . - , , - - ., . . . , , _ . , . . , - . , , , - , - - . _ , . - , _ , - . . . _ - - - - . - ,
.V PCriDI.T 12.1 C?.ITMI A FOR ?!.CD.iT02Y EVACt!ATIOTSI
'T.iOLE ?,0DY2 IllPLE:fE:iT hDIGIODINE3 DOSE RATE EVACUATIO!! CONCE:ITRATIO !
O (oren/ hour) 'JIIIII:3 //'Ci/ce ) Up to 600 8 !!ours Up to IE-5 1 600 to 1000 4 ilouEs IC-5 to 2E-5 1000 to 2500 2 ilours 2E-5 to 4E-5 2500 to 5000 1 liour 4E-5 to 7E-5 5000 to 10,000 - 30 !!inutes 7E-5 to IE-4 , 10,000 to 20,000 15 flinutes IE-4 to 3E-4
>20,000 I}DtEDLiTELY >3E-4
- l. It is inportant to realize that there is no direct correlation between the whole body dose rates and the radiciodine concentrations; and the ueasurements or projections of each nuat be performed independently. In the event that only a direct radiation determination is available, with no corresponding knowledge cf the concentration or fraction of the total which is attributable to radiciodine, the nost conservative assunptions specified in the USE??- anual for Protective Action Guides would be required. Such assunptions, base., only on direct d radiation daterninations, would likely result in grens ove,c estination of thyroit dose coa.tienent.
- 2. Whole bo ty dose to non-energency personnel should not exceed 5000 nren fbou the event. The whole body dose races specified aliove are based on 5000 nren. This value is based on the USEPA PAC !!anual specified upper limit for nenbers of the general public. Although this table specifies mandatorf evacuatic.s eines, in t! e absence of significant constraints evacuations should be 'inplenented to :aintain personnel exposure as low as reasonably achievable and within r.pecified quarterly exposure linits.
- 3. Itiximum concentrations for specified time corresponds to approxim.ately 25,000 nren adult tyroid dose connittent. Radiciodine concentration vs adult thyroi:1 dose connitnent Nsed on Appendix D, (January,197')) to USEPA ?!anual of Protective Action Guides. Radiolodine nuclide distribution corresponds to 4 hoi.r3 followins, reactor shutdown.
d SP 69.03d.dl Rev. B
/ / Page 13
- - - - ~ ~ - - - - - ~ ~ - - - - - ~ ~ ' - - - ~ - - -
,o 6...J1 A i 2. i
,a p, , /3 . ..-
(O) EVACi
'~'
CUT STTMMARY* (s
)
Ass m ' !*. Personnel . 3pe A rr .i tionitoring Accountability Follow-up Suhecquent !!onitorini-1,r c a l !!carby *.re, Local Control Point Job Forenan Exit Restricted Area ficalth Physico Access (by observation) Control Point Return to Work fionc IIP Personnel at !)ryrr 11 I?ryue ! ! .ccesa Drywell Access Exit Restricted Arca !!colth ."hysics Access Co'it r o l Point Control Point Acccas Control Control Point Point (via RMPs) Return to Work lione l'es t ric te ! Aren .* !a ch i n. - Shop I.oen1 Control Points Crnft Forenen/Supvrs Early Disnissal florn.71 Cuarditouse and/or IIenith Physics (by ruster) !!onitorinr. Acceco Control Point Site Evacuation Site Access T!ond Checkpoir Return to Work lione o, .; . e l'a r k i n g Lo t f;unrdhouse Portal Pmdge Turn-in nt. Sign'ificant Release ' Site Acccan Road Checkpolr l1onitors Guardhouse IIan Occurred Release !!asn't Occurrer! !Tonc ?> 1 t e Innediate Renote .*scsembly Renote Asocnbly Badge Turn-in at fi/A Vehicle and Personnel Arca Arcri Gua rdhonne !!onitoring at Renote Assenbly Area
- Doca not include contractor groupn with greater than 20 onsite employees.
SP 69. 639.91 Rev.3'
/ / Page 14
) :
Submitted: ;
. Approved:
(Plant Manager)
.O DRAFT-PRELMNARY SP Number 69.03@.02 Revision D Date Eff.
TPC TPC TPC
- PERSONNEL ACCOUNTABILITY
!O i ! 1.0 PURPOSE , l This procedure provides instructions for accounting for SNPS personnel, onsite
- visitors, and selected contractor / vendor personnel in the event of an evacuation j of plant areas. This procedure applies to Local, Restricted Area, and Site j evacuations.
2.0 RESPONSIBILITY i The Emergency Director is responsibic to ensure that appropriate accountability j measures are implemented following an evacuation at SNPS. 1
/
gg 19 $N
., N PPF 1921.600-6.421 '\
4 D' j
.N 68p)NNs ,
O ' p. s; . /
+,,,
'pll n ,
4 4
~
i 3.0 DISCUSSION 3.1 This procedure addresses general methods for establishing accountability following an evacuation. The means of establishing accountability may vary from area to area, particularly for a local evacuation. In many cases, ( '-)
- radiation work permit sign-in sheets may identify personnel known to be in an area, in other cases, the computerized security system may be able to identify those personnel suspected of being in the area. Responsible LlLCC personnel are expected to take appropriate action to facilitate accountability by use of all personnel data available for a given evacuation. T'
- 3. 2. When the emergency organization is activated, the Administrative Superviscr will assume responsibility for accountability efforts and will advise the Emergency Director on the need for search and rescue efforts, if necessary.
3.3 Topics Page, 8.1 Accountability Following a Local Evacuation 3 8.2 Accountability Following a Restricted Area Evacuation 3 8.3 Accountability Following a Site Evacuation 4 8.4 Action to Locate Missing Personnel 5 8.5 Accountability of Emergency Organization Personnel 5 Following a Site Evacuation Appendix 12.1 Accountabil,ity Checklist 4.0 PRECAUTIONS 4 Security personnel shall remain alert to the computerized personnel ss ,- accountability system operating conditions during evacuations. If it appears i that the demands of personnel movement throughout the station are exceeding the capability of the system security personnel should promptly respond to these movements (by opening doors, operating turnstyles, etc), the system should be placed in free-wheeling to minimize delays in evacuating personnel, or delays in providing necessary access to plant areas for emergency personnel. Personnel accountability, however, shall not be compromised under such conditions. 5.0 PREREQUISITES A condition at the Shoreham Nuclear Power Station has made personnel evacuation to unaffected areas necessary. l 6.0 LIMITATIONS AND ACTIONS N/A 7.0 MATERIALS AND TEST EQUIPMENT N/A () SP 69 030 02 Rev. D
/ / Page 2 w r- ----,--e , ,-
. - _ - - - - .-- , , , - , -r-- ,
8.0 PROCEDURE 8.1 Accountability Following a Local Evacuation The number of personnel involved in a local evacuation is normally small, O' . and involves areas which, when occupied, are normally attended by supervisory and/or llealth Physics personnel. Accountability is performed as follows: 8.1.1 Upon receipt of a local area radiation monitor or continuous air monitor alarm, or upon obCJrvation of abnormal radiation levels (via portable survey instruments), personnel in the affected area will evacuata the affected area and relocate to an unaffected area. The senior individual present will ensure that all personnel clear the affected area and will notify the Control Room for further instructions. 8.1.2 If access to the affected area is controlled by a manned Health Physics control' point, such as the reactor drywell during shutdown periods, llcalth Physics personnel will account for all personnel in the area using the radiation work permit sign-in sheets. The llcalth Physics personnel will notify the Control Room when all personnel have been accounted for and are clear of the affected a rea.
- 8. 2 Accountability Following a Restricted Area Evacuation 8.2.1 Following an announcement of a restricted area evacuation, a supervisor from each craft or section will report to the machine shop.
8.2.2 As personnel gather in the machine shop from the restricted area, the 1cadman/ foreman of the pertinent work parties shall account for all the personnel directly assigned to him by visual contact or verbal communication, and report the names of missing personnel to his immediate supervisor. 8.2.3 As cach station craft /section is accounted for, the applicable supervisor shall notify the Control Room, or TSC if activated, that accountability for his section/ craft is complete, or identify the names of missing personnel. 8.2.4 Control Room /TSC personnel will relay the incoming reports to the Administrative Supervisor (Watch Engineer, until relieved). 8.2.5 The Administrative Supervisor will contact designated individuals in the contractor / vendor organizations for the results of their accountability. 3.2.6 As the mports are collect.d, the results shall be recorded on the Accountability Checklist, Appendix 12.1. O' SP 69 030.02 Rev. D
/ / Page 3
8.2.7 I' personnel are discovered to be missing, proceed to section 8.4 of this procedure. 8.3 Accountability Following a Site Evacuation O 1
\s / 8.3.1 Following announcement of a site evacuation, the Shift Security Supervisor shall assign additional security personnel to the guardhouse (s) to facilitate handling of badges and clearing personnel out of the protected area.
8.3.2 If the emergency organization is activated, the Administrative Supervisor shall proceed to the main guardhouse to coordinate accountability efforts. If the emergency organization is not yet activated the Emergency Director (Watch Engineer) or the most senior individual shall appoint a coordinator from available manpower to coordinate accountability efforts. 8.3.3 Personnel inside the protected area, exit the station, via the guardhouse through which you entered the site, you turn in the security badges and dosimetry to the security personnel, and pass through the portal monitors and proceed to your designated assembly area. NOTE: Dosimetry is not turned in at the Security Building during an immediate Site Evacuation. It will be turned in at the offsite assembly area. 8.3.4 Security personnel will place the badges on the badge racks as they are turned in. 8.3.5 The senior supervisor in the Technical Support Center, the Operations Support Center, and the Control Room shall compile a list of the names and security badge numbers.of those personnel in these locations. These lists shall be called in to the guardhouse. 8.3.5 Personnel outside of the protected area fence, when a site evacuation is called, shall proceed to the designated assembly area. Personnel outside the protected area, and who have emergency assignments within the protected area shall pick-up their security badge and dosimetry at the guardhouse and proceed to their emergency assignment. 8.3.6 After all personnel have exited the site, the badge racks shall be inspected by the Shif t Security Supervisor and missing badges identified and listed. This list will be compared to the lists reported by the Technical Support Center, the Operations Support Center, and the Control Rooa, to determine personnel not accounted for. ' 8. 3. 7 If personnel are discovered to be alssing, proceed to Section 8.4 of thh, procedure.
) SP 69 030 02 Rev. D
/ / Page 4
- - - - - - . - ~ _ _ _ _ - - _ __.
8.3.8 The Operations Support Center, Technical Support ( 'nter, cnd the Control Room shall maintain accountability for personnel parforming emergency measures under their direction. I) 8.3.9 At the direction of the Administrative Supervisor, SNPS security
\~~/ personnel shall implement a building by building search of buildings and trailers onsite but outside of the protected area fence, and search parking lots and site roads for stragglers and others who may not have heard the evacuation alarm and announcement. All personnel found shall be directed to the appropriate assembly area,;or in the case of visitors, offsite.
8.3.10 Following coupletion of accountability efforts and any search and rescue operations, or as directed by the Emergency Director, the security force (with the exception of those necessary to maintain a minimum security posture) will relocate to the assembly area to await further instructions. 8.4 Action to Locate Missing Personnel The following genaral actions may be taken by the Shif t Security Supervisor to determine the whereabouts of missing personnel before search and rescue efforts are initiated. If the following actions fail to account for missing personnel, commence search and rescue activities in accordance with SP 69.0b0.01, bearch and Rescue. 8.4.1 Verify that the in~dividual was inside the Protected Area with the computerized personnel accountability system and/or the visitors-log in the security building. I 8.4.2 Page the missing personnel using the page party system and request response. 8.4.3 Contact the individual's supervisor, or co-workers, to determine the missing personnel's last known whereabouts. 8.4.4 If applicable, contact other assembly areas, to determine if the missing individual went to the wrong assembly area. 8.4.5 Contact the Technical Support Center, the Operations Support Center, and the Control Room to determine if the whereabouts of the individual is known to them. 8.5 Accountability of Emergency Organization Personnel Following Site Evacuation NOTE: Only those personnel with express permission f rom the Technical Support Center shall be authorized access to the site.
- 8. 5.1 The security force will establish an appropriate security posture, D ueordance with the SSPS %curity Plc ta control access, unti.
such time as conditions permit re-establishing the normal security () SF 69 030 02 Rev. D
/ / Pag. 5
t k ,.. , , , program (or an appropriately modified program). 9.0 ACCEPTANC.E.-. CRITERIA l N/A
~10.0 FINAL CONDITIONS i
Personnel have been accounted for, or appropriate search and rescue operations ! are in progress. , L
11.0 REFERENCES
11.1 Shoreham Nuclear Power Station Emergency Plan !- 11.2 SP 69.989 91, Search and Rescue f j 12.0 APPENDICES i I ' j' 12.1 Accountability Checklist I i l f i. 1 l
! l l
I I i 5 4-SP 69 930 92 Rev. D
/ / Page 6 f
i
--,.,.,.,.,.n._ , . . . . . , .. . - - - - . . , - - - - . . . . . . _ . . - , - _ . . - ~ . . _ . _ _ - . ,
Appendix 12.1 ACCOUNTABILITY CHECKLIST i I d Check Here if i -Supervisor All Accounted For Names of Personnel _ Unaccounted For Date/ Time / Initials Reactor Engineering e** 3 Health Physics : i Radiochemistry . i Instrumentation and Control Operations I Haintenance () D , f Security PAC i { SPAC 4 i ( OQA I 1 i
.0ther . _ _ _ _ . . - - . - -
spF 6'J7dJd.V2-1
~
{-... SP 69.@3@.$2 Rev. D Page 7
] / /
i 5 _. _ _ . _ _ _ _ - . - . - - . . . , , - _ _ . . . . . ~ . = . _ . , -.
+
. Submitted:
Approved: _ (Plant Manager) O nr 1! iib.rr~l I5" .. DRAFT:PREllMINARY SP Number 69.030.03 Revision A 4 Date Eff.
/ TPC TPC TPC CONTAMINATION CONTROL DURING E}ERGENCIES
.0 PURPOSE This procedure provides general guidance to Emergency Organization Members to supplement the guidance contained in the Health Physics Procedures.
1 ,
- 2.0 RESPONSIBILITY 4
The Radiation Protection Manager is responsible for insurf ng the proper implementation of this procedure. t
'gL-iMg}
m LLL {< /
"p PPF 1921.60@-6.421 N4fj ,g @8/
O i&J>R
,3. 0 DISCUSSION l l
During an emergency condition, substantial quantities of radioactive material =ay ) f~ be released to the Station or to the environment. As a result, there will likely l be an increase in contamination levels. The normal contamination control cethods established in the Health Physics Procedures may not be adequate, or suitable, under these circumstances. This procedure provides guidance on alternate contamination control methods which may be used in addition to, or in lieu of, the methods established in the normal operating Health Physics Procedures. 4.0 PRECAUTIONS 4.1 Skin contamination less than one (1) rad per hour is unlikely to be i immediately life-threatening, and therefore, skin decontamination efforts should never take precedence over necessary first aid. 4.2 Accidents related to fuel degradation and leakage of reactor coolant may result in alpha contamination in addition to the typical beta gamma radionuclides. If alpha activity is suspected, a random selection of swipes (and air samples) should be counted for alpha activity. The size of the random selection should be decreased or increased on the basis of the initial alpha count results. 5.0 PRCREQUISITES The provisions of this procedure should not be implemented unless: 5.1 An emergency condition has been declared at the Shoreham Nuclear Power g Station as provided in the SNPS Emergency Plan. 5.2 As a result of the emergency condition, significantly abnormal contamination levels may be present. 6.0 LIMITATIONS AND ACTIONS 4 N/A 7.0 MATERIALS OR TEST EQUIPMENT ~ Contamination control and/or decontamination supplies identified in the SNPS Health Physics Manual. l l l l i l b
's- / SP 69.030.03 Rev. A
/ / Page 2 l
l
8.0 PROCEDURE 8.1 Contamination Control g_,) 8.1.1 It may become necessary to extend the boundaries of the Restricted Area. Appropriate access control and associated contamination control measures shall be established for any area in which contamination exists at levels higher than that specified for an Unrestricted Area in the Health Physics Procedures. 8.1.2 Normal personnel and equipment monitoring and release procedures and criteria shall remain in force to the extent possible. There may be exceptions applicable to emergency conditions as follows: 8.1.2.1 If background at normal monitoring locations preclude detection of levels of contamination equivalent to the clean limit, monitoring shall be moved to a location where this can be done. Ilowever, if significant levels of contamination exist, it may be appropriate to perform a gross screening at the exit of grossly contaminated areas, to be followed by a complete monitoring at a more suitable location. 8.1. 2. 2 If dose rates within the contaminated area (or Restricted Area) warrant an immediate evacuation, personnel monitoring shall not be required prior to evacuation. If possible, personnel exiting such areas should remove any clothing thought to be contaminated, or don clean
"'g coveralls to minimize the spread of potential g_,) contamination, pending subsequent monitoring. In this case, appropriate monitoring should be performed at the designated assembly area.
8.1. 2. 3 Contamination limits specified in the Health Physics Procedures for release of persannel, equipment, and areas shall remain in effect to the maximum extent possible. The Radiation Protection Manager will determine when a change in contamination limits is warranted. However, under site evacuation conditions, decontamination is normally mandatory if the contamination exceeds 100 cpm above background on RM-14/ IIP 210 (1000 dpm/100 cm2) beta gamma activity. 8.1. 3 For rescue efforts in which there is a potential for the imminent death of the victim, and for which the magnitude of radiological conditions in the affected area are generally known, a rescue term member (s) should proceed to the scene witt.out protective clothing to assess the situation and render first aid. Other members of the rescue team should don appropriate protective clothing and proceed t> the area to assist. The initial rescue teaa neuber(s) should leave the area and be monitored and/or decontaminated as soon as possibic. V SP 69 039 03 Rev. A
/ / Page 3
8.1.4 For fira-fighting efforts, normal fire-fighting g_ar (hslacta, coats, boots, gloves, etc.) may take the place of protective clothing. The apparrel is as likely to provide protection from
.S contaminated water spray.
I 8.2 Contamination Monitoring During a Site Evacuation In the event of site evacuation, the extent and nature of personnel and automobile monitoring will depend on the amount and physical nature (particulate, noble gas, etc.) of the radioactive material released, and release and meteorological parameters (ground level or elevated release, wind direction, stability, etc.). The Radiation Protection Manager sill determine the need for and extent of personnel monitoring beyond that required during normal operations. The following guidance should be considered in establishing personnel monitoring and/or vehicle monitoring requirements. 8.2.1 If personnel exit the site via the portal monitors in the guardhouse, monitoring can be considered complete. If background levels in the guardhouse preclude use of the portal monitors, monitoring should be performed at the offsite assembly area. 8.2.2 If iodine or particulate releases have occurred such that contamination of vehicles and the site access road is probable, monitoring of personnel automobiles should be performed prior to releasing the vehicle to the public highways, subject to the following: 8.2.2.1 If the release has resulted in extensive offsite contamination such that evacuation of the general public d is being implemented, monitoring and decontamination of vehicles prior to exit from the site would probably be superfluous in light of the potential for re-contamination offsite. Under these circumstances, site personnel and vehicles wil.1 be monitored for contamination as provided in the emergency plans of the affected jurisdictions. 8.2.2.2 If vehicle monitoring is performed, it should be performed along the site access road near the LILCO substation in order to prevent backups on site. Vehicles found to be contaminated should be directed into the substation for decontamination. Document results on Appendix 12.1. 8.2.2.3 The Radiation Protection !!anager should determine whether spot-checking or complete mon.itoring will be performed, consistent with probability of contamination.
- 8. 2. 'l once personnel have evacuated the site. consideration should be
,;i vea to est ablishing a shuttic bus systen la order to ninimize the number of vehicles requiring monitoring.
O V SP 69.030 03 Rev. A
/ / Page 4
, 8. 3 Decontsmination 8.3.1 Personnel decontamination shall be performed as provided in Health Physics Procedures.
O 8.3.2 contaminated / injured personnel should be decontaminated prior to transfer to the hospital, if possible, and if compatible with the extent of the injuries. Even a superficial initial decontamination to remove the loose contamination will help minimize the contamination of ambulances and hospital facilities and personnel. Refer to SP 69.041.01, Offsite Medical Assistance. 8.3.3 Most cases of skin decontamination with radioactive materials can be decontaminated using r.thods established in the Health Physics Procedures by Health Physics personnel. If the contamination is not removed by these initial methds, if decontamination has resulted in excessive irritation of the skin, or if contamination has entered wounds or body openings, medical assistance should be sought. The urgency of such treatment will depend on the dose rate attributable to the contamination. Except in cases of high-level contamination, over about one rad per hour including beta radiation, as measured with an ion-chamber instrument (4-7 mg/cm3 window), there is no urgency to complete skin decontamination. If the skin contamination is the primar3 health hazard, Radiation
' Management Corporation should be consulted, and the individual transferred to the Central Suffolk Hospital for evaluation and treatment, at the direction of RMC. Refer to SP 69.041.01, Offsite Medical Assistance.
(U ) 8.3.4 Decontamination of persons with'significant internal contamination shall be referred to medical personnel from the Radiation Management Corporation for evaluation and treatment. In the event of a significant uptake of radioiodine, potassium iodide may be administered in accordance with SP 69.xxx.xx (Later). 9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS All personnel who have exited the site have been appropriately monitored for contamination, and where applicable, have been properly decontaminated.
11.0 REFERENCES
11.1 Shoreham Nuclear Power Station Emergency Plan 11.2 S"PS llealth Physics Procedures l 12.0 APP 6NOIES 12.1 SPF-69 030 03, Vehicle Survey Form O SP 69.030.03 Rev. A
/ / Page 5
. . . - . . .. . .. . . . ~. . .
~
Appendix 12.1
, VEHICLE SURVEY FORM 3 als form should only be filled out for contaminated vehicles. Ensure that all license 4 %,i's and names are' recorded.
4 i Driver's Side ) _j s~- - ^ ~
--)
~
..--~~~
f s (L( < g~ y< ) .-- - < -
-}
gLl -
/
< d i / Passenger's' Side f*',,s
^
/ m
~
~~--- .- - ._ -~ ~
/
r '\ { kq$"bN j h.% l
...A 1-___. _-
~ - _ _ -
NAME i j LIC #
, Signature Date I
i-ser 69-s30.03-i lO SP 69.030 03 Rev. A i
- ~ Page 6
/ /
l c,- - - , = . , - - - , , - - , , n .,,.---,..,-,,-,n., - - - - -
- - . s e_,- ,
j'
, ,/' -
b! ,
- * , !I
's f l w- ./ ,
% l
~
s
~ n l
< -)
u
- c. . <
1
-w EP THIS SECTI0tl IttTEilTI0tlALL LEFT BLAtlK FOR --
FUTURE EXPAtiSI0tl. ~. 4 9-f P q4 D M
+,,LM e
.s O . .
s s, f
, + . .
w l 6 l l l l l a. l b O l l l
i.,' .. SP Number 69.040.61
. Submitted:
Approved: Revision d [] (Plant Manager) (_/ Date Eff. PERSONNEL INJURY
/ DRAFI PREllMINARY 1.0 PURPOSE To describe the actions to be taken by station personnel in the event of a injury which may or may not involve radioactive contamination at SNPS.
2.0 RESPONSIBILITY The Health Physics Engineer is responsible for ensuring compliance with this procedure. 3.0 DISCUSSION 3.1 All injuries shall be reported to the control room so that effective measures such as dispatch of first-aid teams and offsite transportation can be performed in an expeditious manner. 3.2 In the event of a severe or life threatening injury, immediate medical D) treatment is given a priority over any radiological considerations. 3.3 If offsite transportation of a contaminated injured person occurs, the event is classified as an Unusual Event in accordance with the Shoreham Nuclear Power Station Emergency Plan and appropriate actions should be taken accordingly. 3.4 Topics covered in this procedure: Page 8.1 Minor Injury 2 8.2 Major Injury 2 8.3 Treatment of Non-Contaminated Injured Personnel 3 8.4 Treatment of Con enminated_ Injured EarsonnaL 3 4.0 PRECAUTIONS ') 0[l~[i,ulwh] I
)
111 Jnt n: N/A 5.0 PREREQUISITES / h pgg A person has become injured and/or requires medical attention. 6.0 LlMITATIONS AND ACTIONS
-The individual may require offsite medical treatment, and if contaminated
' require SNPS personnel to classify the incident and take emergency measures
) purr +uant to the SNPS Emergency Plan.
7.0 mar _HRTALS AND TEST EQUIPMENT See Section 8.0
--)
; 't
- t 3:
3 4 06. PROCEDURE
'8.1 Minor Injury y
'(V'
~ 8.1.1 Any station personnel who comes across another individual having
.; an injury shall render qualified first-aid, if possible.
8.1.2 If the injured person is ambulatory, perform the following:
.1 Notify health physics 3 personnel to check the injured person for any contamination.
.2 Health physica person, decontaminate any wounds in accordance with normal practices (e.g., flush wound with luke warm water), if applicable.
.3 Person finding injured individual, accompany him to the first-aid room for subsequent medical treatment and examinat. ion.
- s 8.2 !!aloLLnjyrv 8.2.1 Any station personnel who come across another individual having an injury shall render qualified first aid, if possible.
8 . 2.' 2 Report the following information to the Control Room using the page-party system or another phone system:
.1 Number of affected individuals
.2 Location of injured individual (s)
.3 Injury description .
y .4 Extent of contamination, if any
.5 Additional assistance required 8.2.3 Watch Engineer or designee, based on information received on r the injured person (s) condition dispatch the Fire Brigade
. (First-aid) Team by sounding the " siren" tone and making the following announcement over the page-party system three times at one-minute intervals:
N
" Attention all station personnel. There has been a personnel
; . injury involving (number) of personnel which (are/are not) contaminated. First Aid Team (and in-plant Radiation Monitoring Technician - if contamination is suspected) reoort to (location) ine.ediately" 8.2.4 Implement Section 8.3 or 8.4 of this procedure depending on whether injured person (s) is contaminated.
C)[ SP 69.040.61 Rev.
/ / Page 2
,. o 4
- y ,
8.3 Treatment of Non-Contaminated Injured Personnel
/"'T 8.3.1 First Aid Team members, obtain first aid kit, communications (s,/ equipment and other equipment as necessary and proceed to the scene of the incident as directed by the announcement over the page-party rystem.
8.3.2 First Aid Team members, determine the extent of medical injuries 1 and administer first aid.5.e 8.3.3 First Aid Team Leader, determine if hospitalization is required.
.1' If hospitalization is not required, transport injured person (s) to First Aid Room for further treatment, examination and release.
.2 If hospitalization is required, perform the remaining steps in this section.
8.3.4 First Aid Team Leader, notify the Watch Engineer that the injured individual (s) medical condition warrants of fsite assi ,tance and transportation to the hospital. 8.3.5 Watch Engineer or designee, impicment SP 69.041.01_"offsite Medical Assistance". 8.3.6 First Aid Team members, prepare the injured individual (s) for ambulance transport as follows:
.1 Request stretcher by contacting
.2 Load the injured person (s) into the stretcher in accordance with normal medical practices.
NOTE: If the injured person (s) .cannot be moved, keep him warm with blankets and await ambulance personnel.
.3 Wheel the stretcher to the nearest building egress point and await ambulance.
.4 Notify the Watch Engineer of your location.
8.4 Treatment of Contaminated Injured Personnel 8.4.1 First Aid Team members and In-plant Radiation Monitoring Technician, obtain first-aid kit, communications equipment and other equipment as necessary and proceed to the scene of the incident as directed by the announcement over the page-party , system. SP 69.640.61 Rev. p / / Page 3 b
- t 8.4.2 If the injury has occurred in a high radiation or contaminated area, First Aid Team members and In plant Radiation Monitoring Technician, proceed to the main health physics checkpoint IsI
\_ /
and don appropriate clothing and respirators. NOTE: For severe or life threatening injuries and/or high radiation areas, time is of the utmost importance. Use judgement when performing step 8.4.2. For severe injuries in a contaminated area, immediate medical treatment is of the highest priority and radiological , controls are considered seco dary. 8.4.3 First Aid Team members and In-plant Radiation Monitoring Technician, move the injured person (s) out of a high radiation area if the injury is not severe and the exposure is life threatening. 8.4.4 First Aid Tcam Members, implement appropriate first aid techniques making efforts to prevent contaminating or spreading any contamination which might be on the injured person. 8.4.5 First Aid Team Leader, determine if hosp'italization is required. 8.4.6 If hospitalization is required; Watch Engineer or designee implement SP 69.041.01 "Offsite Medical Assistance". 8.4.7 In-plant Radiation Monitoring Technician, perform the following: (m N--
.1 Survey any wound areas for contamination and complete a Body Map (Attachment 12.1) showing contaminated and/or injured areas of the body. If hospitalization is required the body map will accompany the individual.
- .2 Attempt to remove any contaminated clothing. Ensure that t removal of contaminated clothing does not aggravate the injury or cause cross-contamination.
1
.3 If conditions permit, flush any wounds with luke warm water.
.4 Request plastic sheets, blankets, stretcher and other necessary equipment be dispatched to the injured person (s) location by contacting the Watch Engineer.
.5 Load individual onto the stretcher taking care to ensure medical and contamination control measures are followed.
_ NOTE: If the injured person (s) cannot he moved, keep hin varn with v.,rn binnhets and atnit ambulance personnel.
.6 If hospitalization is not required, transport the individual to the first-aid room for further examination, treatment g
and release. If hospitalization is necessary, perform s the remainder of this procedure. SP 69.646.61 Rev.
/ / Page 4
_. __ . . . _ _ __ - _. __ _ _ - - - - _ . _ ._ _. __ _ _ _ _ ____- - .~ _ __. c 1 8.4.8 First Aid Team members, wheel the stretcher to the nearest ! building egress point. j j
- 8.4.9 First Aid Team member, notify the Watch Engineer of your !
, location. i ! 8.4.10 Watch Engineer,. initiate SP 69.010.01 " Classification of_ _ Emergency Action I,evels". i
~/
l 9.0 ACCEPTANCE CRITERIA , N/A - 10.0 FINAL CONDITIONS 10.1 Appropriate first aid has been cdministered. , 10.2 Appropriatu decontamination has been performed. 11.0 , REFERENCES _ l
- Shoreham Nuclear Power Station Emergency Plan 12.0 APPENDICES
! I 12.1 Body Map { . f 2 s 1 0 1 j sp r,9.csc.dt teo ,
/ / Page 5 i
gm,e+-r,--y =e, ,,,&-_-w --ie-e y c.w + %,,e-w-we --c-m-- . e - m . %, vi wyew- - -, . - - - -w r-e---v-e----r- - -+-- -----w~ - - ,----e-+-- ----u-.-- m a-,--ww
.. /
Subnitted: SP Number 69.041.01 Approved: Revision C O (Plant Manager) Date Eff. OFFSITE MEDICAL ASSISTANCE l.0 CONDITIONS . f 1.1 One or more station personnel have'bcen injured and require (s) immediate offsite medical assistance. 1.2 Immediate first aid activities are being carried out in accordance with SP 69.040.01, Personnel Injury. 1.3 A personnel radiation overexposure has occurred requiring offsite medical treatment. 2.0 IttfEDIATE ACTIONS } 2.1 Emergency Director or designee, perform the following: 2.1.1 Complete a Personnel Injury Fact Sheet (Appendix 6.1) and give it to a Control Room Operator, TSC Communicator or EOF Communicator for transmission to the following offsite organizations in accordance with Sp69.009.01 " Notifications".
.1 Wading River Fire Department
.2 Central Suffolk Hospital
.3 Suffolk County Emergency Operation's Center ,
NOTE: Suffolk County EOC will $c notified only if the injury does not involve contamination. l 2.1.2 Notify the Shift Security Supervisor and provide the following information:
.1 Cate at which emergency vehicle is arriving.
.2 Area or plant site to direct emergency vehicle to (building and door location).
.3 Issue emergency dosimetry to ambulance personnel.
l TP ' 9132 _- im , A .) 5
v .. 3.0 SUBSEQUENT ACTIONS 3.1 All Incldents C) (, 3.1.1 Site Security shall perform required access control measures to - ensure rapid arrival of emergency vehicles to designated building /docr location. 3.1.2 Health Physics personnel shall ensure that appropriate personnel dosimetry has been provided to emergency vehicle attendants. 3.1.3 Whenever possibic, without further risk to the individual injured, transport the victim to the assigned door location to meet the emergency vehicle. 3.1.4 Health Physics personnel shall perform required vehicle survey while victim is being placed into ambulance. 3.1.5 Site Security shall provide escort for the ambulance offsite. 3.2 contaminated Victim 3.2.1 The Inplant Radiation Monitoring Technician shall prepare the ambulance as follows:
.1 Lay blotting paper and/or plastic shecting inside the ambulance.
3 .2 Lay plastic sheeting or blankets over the surface of the stretcher. 3.2.2 A person qualified in health physics "Self-Monitoring" shall accompany the victim in the ambulance. This individual should have appropriate protective clothing, survey instruments, and pe'rsonal dosimet ry. NOTE: If there are multiple casualties, the health physics qualified person should accompany the first ambulance. Additional qualified personnel should be sent as they become availabic to facilitate ambulance surveys. 3.2.5 The staff of the hospital should prepare for receipt of the contaminated victims in accordance with the hospital incident response plan. Upon arrival at the hospital, the health physics qualified person should assess the contamination control preparations and assist hospital personnel in upgrading the preparations if necessary. 3.2.6 Assist hospital and ambulance personnel in transferring the victim to th" trett m ut room.
'# SP 69.041.01 Rev. C
/ / Page 2
-r .
3.2.7 After the contaminated victim (or last victim if there 10 more than
, one) has been placed in the treatment room, the health physics qualified person shall perform the following:
/s 3.2.7.1 Roll up any blotting paper that was laid down between the
(\s) ~ ambulance and the treatment room. Place this blotting paper in plastic bags for transfer back to SNPS for disposal. 3.2.7.2 Recommend appropriate protective clothing to persons entering the trcatment rooms and assist these personnel with removal of protective clothing and monitoring when leaving the room. 3.2.7.3 As time permits, monitor the ambulance attendants for contamination. If contamination in excess of detectable levels is found, these personnel should be decontaminated at the hospital, otherwise, they niv be released. Document the results of this survey.
~
Collect dosimeters from ambulance attendants. 3.2.7.4 As time permits, monitor.the ambulance for contamination. If contamination in excess of detectable icvels is found, the ambulance should be returned to SNPS for decontamination, otherwise, it may be released. Document the results of this survey. 3.2.7.5 At the direction of the attending physician, monitor the victim (s) for contamination and apprise the phyr'aian of (~'N the results. It may be necessary to repeat this process
\~- as the hospital staff decontaminates the victim.
3.2.8 At the completion of treatment and at the direction of the physician, restore the treatment arca(s) to normal use as f.ollows: 3.2.8.1 Monitor all fixed equipment, floors, tables, and any other surfaces that may have been contaminated. Decontamination of contaminated equipment and surfaces will be performed by LILCO personnel at the direction of hospital personnel and health physics supervision to levels less than detectable, prior to release to other uses. Document all surveys. 3.2.8.2 Collect any protective clothing, and any other potentially contaminated waste for transport back to the station. 3.2.8.3 When SNPS personnel are no longer needed at the hospital, they should report back to the site.
/
n/ x,, SP 69.@41.01
/ /
Rev. C Page 3
e ,. 4.0 FINAL CONDITIONS e 4.1 Injured victim has been transported to the hospital for further medical assistance. 4.2 llospital facilities and the ambulance have been cleared for further use. 4.3 Notifications have been completed in accordance with SP 69.009.01, , Notifications. j 5.0 DISCUSSION 7' 5.1 First aid and health physics personnel providing assistance to injured personnel must remain alert to their own exposure. Emergency exposure limits for life-saving activitics are provided in SP 69.050.01, Radiation Doses During an Emergency. 6.0 APPENDICES 6.1 Personnel Injury Fact Sheet U W SP 6'9.041.01 Rev. C
/ / Page 4
s PERSONNEL INJURY FACT SHEET r ( }!otification for Ambulance Assistance (Usually Wading River Fire Department)
- 1. This is the Shoreham Nuclear Power Station. An injury involving person (s)
(number) has occurred onsite which requires ambulance service. The individual (s) +
./
contaminated and will be transported to (are/are not) (hospital - usually Central Suffolk llospital 2. (brief description of injuries)
- 3. Enter the station through the gate.
(east / west) i 1 Notification to: 1. Receiving Ilospital ( Usually Central Suffolk llospital)
- 2. Suffolk County Emergency Operations Center This is the Shoreham Nuclear Power Station. An injury involving person (s)
' O,1. (number) has occurred onsite which requires medical treatment. The individual (s) contaminated and are being sent to (are / are not) i for treatment. ] (hospital - usually Central Suffolk Hospital)
- 2. (Same as Item #2 above)
- 3. The estimated time of arrival at the hospital is hours.
(time use Z4 hr clock) SP 69.041.01 Rev. C l
/ / Page 5
-. - - - - . , - .. - , = - , .-
a Submitted:
. Approved:
(Plant Manager) O
!=-- -
bb]?[i Y*$l
=
SP Number: 69.050.01 Revision: B Date Eff: TPC TPC TPC RADIATION D0'SES DURING AN EMERGENCY l 1.0 PURPOSE To provide a guide for the authorization of radiation exposure during a declared emergency. - l 2.0 RESPONSIBILITY j . The llealth Physics Engineer shall be responsible for ensuring compliance with this procedure. l 1 i
. i.,k f h s'.
! PPF1021.600-6.421 Q'
/ _ - .
N\-l "l .. . s' e- , D wy g ,7 J4
'f ,/r
- 3.0 DISCUSSION
. 3.1 Persons involved in emergency activities may be exposed to high levels of radiation. The guiding principle is to minimize personnel dose As Low As Reasonably Achievable. However, control of exposures should be consistent
() with the immediate objective of the necessary actions. 3.2 Authorization to expose individuals to the levels of radiation presented in this procedure shall only be given during a declared emergency. Only the Radiation Protection Manager or the Emergency Director shall give authorization to expose individuals.to these levels. 3.3 Persons performing emergency activities should be volunteers broadly familiar with radiation dose consequences if expected dose exceeds normal limits. 3.4 If possible, volunteers who are authorized to receive emergency exposure limits should be more than 45 years of age. 3.5 Topics covered in this procedure: Page 8.1 Authorization of Exposure 3 , 8.2 Life Saving Activities 3 8.3 Substantial Reduction of Public Exposures 3 8.4 General Emergency Operations 4 4.0 PRECAUTION , 4.1 Emergency exposures should be limited to once in a lifetime occurrence. PREREQUISITES h)$.0 u 5.1 One of the four emergency classifications established in Ref.11.4 shall have been declared. 5.2 Dosimetry equipment capable of measuring the anticipated maximum levels and types of radiation shall be worn by personnel receiving emergency exposure. 5.3 Review radiation dose history of volunteers. if time permits. 6.0 LIMITATIONS AND ACTIONS 6.1 Women of child-bearing age shall not be permitted to receive doses which exceed 10CFR20 limits. 7.0 MATERIALS N/A
) SP 69.050 01 Rev. B s' / / Page 2
8.0 PROCEDURE 8.1 Authorization of Exposure 8.1.1 The Radiation Protection Manager shall be responsible for (~~)S (, authorizing exposure of individuals to the levels presented in this procedure. 8.1.2 The Emergency Director may authorize exposure of individuals to the levels presented in this procedure. 8.2 Life L2ving Activities W 8.2.1 For the rescue of persons trapped or incapacitated in a dangerous situation which includes high radiatior levels, and there is no time for adequate planning and protection, exposures of rescue personnel should be limited as follows: (See references 11.2 and 11.3) 8.2.1.1 75 Rem Whole Body 8.2.1.2 No specific thyroid limit NOTE: No specific upper limit is given for thyroid exposure since in the extreme case complete thyroid loss might be an acceptable penalty for a
-life saved.
8.2.2 For the rescue of persons trapped or incapacitated in a dangerous fs situation which includes high radiation Icvels, and time permits .( ) adequate planning and protection, exposures of rescue personnel should be limited as follows: 8.2.2.1 12 Rem Whole Body 8.2.2.2 75 Rem thyroid 8.3 Substantial Reduction of Public Exposure 8.3.1 These actions are deemed essential to reduce a hazard or hazard potential to acceptable levels. They may entail equipment repair, fire control, effluent control, etc. These activities are considered to be less urgent than life saving activities. 8.3.2 If there is no time for adequate planning and protection, exposures should be limited as follows: (See references 11.2 and 11.3) 8.3.2.1 25 Rem Whole Body 8.3.2.2 125 Rem Thyroid SP 69.050.01 Rev. B C,)) // Page 3
. 8.4 General Emergency Oparations 8.4.1 Exposures to individuals performing emergency actions other than those covered in Sections 8.2 and 8.3 shall have exposure limits as set forth in 10CFR20 (see reference 11.1).
9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS ,, 10.1 Evaluation of doses received shall be made after emergency exposure by the Health Physics Engineer. 10.2 Dose Records shall be updated to indicate these doses. I
11.0 REFERENCES
11.1 10CFR20, Standards for Protection Against Radiation 11.2 EPA-520/1-75-001, Manual of Protective Action Guides and Protective Actions for Nuc1 car Incidents 11.3 NCRP Report No. 39, Basic Radiation Protection Criteria 11.4 SP 69.$10.01, Conditions for Emergency Action Levels 12.1 APPENDICES () N/A d i i SP 69 050 01 Rev. B Page 4
I V, .
-N Submitted:
C' pproved: (Plant Manager)
< DRW.pngzgygy SP Number 69.051.01 Revision '
,N b _
Date Eff. TPC TPC TPC THYROID BLOCKING 1.0 PURPOSE The purpose of this procedure is to provide guidelines and instructions for the administration of potassium iodide (KI) to station personnel. 2.0 RESPONSIBILITY _ The Radiation Protection Manager shall be responsible for ensuring compliance with this procedurn. s c ,
~ /
f$
?$ gM PF 1d21.60d-6.421 ,,
I e 3.0 DISCUSSION
'i Radioiodines inhaled or ingested by the thyroid gland may be blocked by the s_ f
/ ingestion of stable iodine. The administration (oral) of approximately 130 milligrams of potassium iodine (KI) will result in sufficient accumulation of stabic iodide in the thyroid gland to prevent significant uptake of radioiodine.
KI as a thyroid blocking agent is only effective if the radiation exposure is from radioiodines and the administration of the stabic iodine is accomplished shortly before or after uptake. 4.0 PRECAUTIONS O' KI, as a thyroid blocking agent, is normally administered by prescription and its distribution must be in accordance with existing New York State health laws. 5.0 PREREQUISITES KI is administered when the calculated actual or potential thyroid absorbed dose is equal to or greater than 10 rad. 6.0 LIMITATIONS AND ACTIONS N/A 7.0 MATERIALS AND EQUIPMENT , N/A
- 8.0 PROCEDURE 8.1 Dete rmina tion 8.1.1 The Radiation Protection Manager (TSC), the Radiological Control Manager (EOF) or their designees, shall determine the need for administration of potassium iodide (KI) as follows:
.1 Determine the I-131 concentration (pCi/cc) in the affected area (s) .
.2 Divide the I-131 concentration by the protection factor of the respiratory equipment, if applicable.
.3 Determine the length of time (ninutes) of the individual (s) in the affected area.
.4 Locate the intersection of these points on the thyroid graph (Attachment 1).
.5 If the projected dose in equal to or greater than 10 rad, KI adninistration is recocaended.
s~s SP 69.051.01 Rev. A
/ / Page 2
F l 8.2 Administration b]
/
8.2.1 Affected personnel will report to one of the locations that stock KI tablets (See Section 8.3). 8,2.2 liealth ,P g. iyggngg(t eyeQqc,a,tggg3pa g Mge I a*c f I a t'f5 that taking of KI is voluntary. ~l f WNMse advise Pa c i rtof d ff pA F5 W[0424-f he skall rtoi he givest Mr. 8.2.3 Health Physics personnel at these locations shall log the person's name, social security number, employee number, company / department and date on the KI Administration Form, Appendix 12.2. 8.2.4 Administer one KI tablet (100 mg iodide per 130 mg tablet) to each individual who requires KI. 8.2.5 After administration, the names of persons who have received KI are reported to the Radiation Protection Manager (TSC) or the Radiological Control Manager (EOF). 8.2.6 The Radiation Protection >!anager (TSO or the Radiological Control Manager (EOF) shall notify the LILCO Medical Director of persons who have received KI. (s 8.2.7 KI is administered daily to each person on the forn until h the accumulated dose is 1 gm of iodine or as otherwise directed by the LILCO Medical Director. The time required to accumulate 1 gm of iodine is 10 days. 8.3 Location of KI Supplies 8.3.1 KI supplies are stored in the following locations:
.1 Emergency Operations Facility (EOF).
.2 Technical Support Center (TSC).
.3 First Aid Room.
.4 Downwind Survey Kit.
8.3.2 Potasslun Todide (KI) tablets to be administered are generically equ ival ent to Pott.ssiut t Iodine, U.S.P., 130 ng each (103 ng iodide). 8.4 Maintenance 8.4.1 K1 tableta, hxic a hel f I!.f e of approxinately tuo years. The Radiation Protection ' tanager (TSC) or the Radiological Control Manager (EOF) is responsibic for ensuring that inventories are v' maintained and that tablets whose shelf life has been exceeded are replaced. SP 69.051.01 Rev. A
/ / Page 3
~ - . . - . . .
9'. 0 ACCEPTANCE CRITERIA ~ N/A f
- 10.0 FINAL CONDITIONS All records shall' be forwarded to the Administrative Section for filing in accordance with permanent plant procedures. :
11.0 REFERENCES
/
NCRP Report No. 55, Protection of the Thyroid Gland in the Event of Reicases l of Radiodine, (National Council on Radiation Protection and Measurements,
. Washington 1977).
4 12.0 APPENDICES _ 12.1 Thyroid Dose Graph 12.2 KI Administration Form i 5
- O l I
I I i l i i O , SP 69.d51.01 Rev. A
/ / Page 4
-w--, ,-,,.,..-y- . - , , , - - . - - , , - - - - , - - . , - - - - - , - - - - -._...,.,.,m..
F 1 e
- e
[%,,. 88E [ ) STAY TIME (MIN) g E r } ** O O o O N* / , w w
- e o w n,O w w ***wm*O w w a eowmeO O
w w a ..we.oo a w a eewoeo o O..-- ' '
=
*. . . m. . + - ....y.
= i
- i 1,***,
** =
e .* * . .. * , . * -~I l_6 -6: n:M - i y ;, . 1 ;;- * *----r-
. . . q' 3.- ......m.___,_
;...;.11
....:'- 6 -4
,_: : :- !-~ '::::t 1.. ::" ; - -- - - - - - - 7:!" -- **
.. . . . _ ... t~.
t *t . . .: r, _. _ _ .-- :.-
--2-m.. 7__-rn ...
. t }j ...M........._.____
L. 4. _..
=:7 --- c - g.2 x:_ . j ; . ; a; 4 -
*r ;J :. c' .. "
--- ~~~~ --
5 -'
- k.:b.::. . i'.i !
q:. :-+r =. _ _ . ; :.t a;;;- : ;; ;- . . :r : ~ e.
-} +.1l,. .er:
,.p 4u
. .2.
1: 4-r 1 2...+. =-f t s7c -"+-. . i r..37
- -1 m _ , , .-+y::, F :.: : - . - . -:::
- 5. s. m.:- q m-_3 m -= .%.
V;; =;- =. ,=
. _23 i :.: .]=
--w h. _ ..=:i i
=
=L*. gr ty .y=Mgq:
i=
= =. ;r_. m--.?
= .._
.+_. .qj tal M i 1 h_ y.[h q! I-9 . u . . _. - ._ .
r 4 , . , -,f4 hi
, h -
k_ . _7 g -- : I. : .,4 h Qg, .u %p # - 2 i
- - - - .5 7hgh j+,
t_ w .,,
'M,... . . _ ; f?"4, y4- _ . b;;
, ; E -- M.J_* w4aM ear
r-
^
M ev-Ne+ o '
-:1 w 4 4 _W3 h[ h),j.4w4.a irg { g.3 "jC fI + Ff '" r. : *T ~g: '.it'-I 3-E M ;I-- %1 1 **':'y+:-1
't. . . b ".. *; T .-- ,-r._
- - ~-:- +7 -#iJ N - ' : q--~- 2F .c sc. ;-is- :' -%-N- _n L -
y "
-j s e, .pe.-..-
- :- u g.c i_-f. m i t; yI . _ - - -
- s. - m e s.
r-- m - 2
-W
.: I-. _ . . - ..yi?
, 3 . .- _. _- ,* * .
' ,a@- m. v h. ., , e,-w a-7wI.' 1
, ,i ! s i ._ ;,w.w r 'a 4 ', [ la. ,i _a c j ; .__..,.; ; m. j f r .33 ;j- _, W} '. -_' y j } , ,, ,q.
.e .
t mm_m m m . . . . . - . , ,e e- ; m 7 .* % A_ ,.n_ . , ,
, m
,..y
.;,m .o .,g c 34 Og ~ ~ ~ - * ** *
..'.4...-.4 m ... .. ... . . . .
;h..,
m
/.~ .
gy: --.* - - - - . _-, . _ . . _ ...-[._ m._. n.* .g _.w r' : ! g --- h-.;;
.~.
*A; 4 Q:
--+
-r:..,.,_D*3-_.- ,- r--- ' : .
-~~
. . -- N-ih ,i ! m* k;pv .bh. . . - h.-. 's. hiM* #.5 5^-C_- db8M !*!: ..i*NN*Yh;T[* t!: L :
fib.MU-
> -- e , . . h. . -+=I:h.
}5 p b jf,*1 - _8.---"; gI' :- =.- ! 7 y ^ i . 4 - s -~r---r-e r
2 p =r r g tj 3 7 g g .d. 2 ..g-.._. .
-p,.: E_g2
--- - s
,pp;j:] *.= -.=.g,g
. x-
- p. f_q q j,,._ - -g- g + g ; j p;ff, j- - - - _g, ;.y pg~g_,4 -
-u -
.(-:. s '.y .7, s Q .b p...c c.
$,.d E-S h.:3~ r.i: , . + , , ;j nt aw ::
i.n ._: r alb n e Q.:' i E- E L . :4 g
+i4 j , E - arrse ie r. J - g rs " .._- --
.. r - Q_s 4-4f f 1 ' 4 Tf- Au -
- ;. J }. - , Mqcem- p.M-
,.4.c.u~
r + ~t . p . .< ,;.,p g, ,
}4 -: ,. , 4 .A '-
!.- p- 4,.. Q q. ;14 &c.v. i hq;~.
. . -- e
,, t:, ..u,a .
[ q 4.- 7 h.. J+.- H- y . ._ 7
, M..y.
.- .: m..-m M*4 .Mg4Pt"7+{,
+ . .
y. y- .gmq - 3,far.7.- . 4A.kv. w a. ; 4._
.1. -
af ~_
. ,,g.: , .h_ a. _.a.
,. . . ,- c. . u_
- t ;;y.:e r _p- t y;. -- r ? tes.
y-[-. e. j - ry g i-f. {.-. - . . -i ,.ir:q #s.3 cr.e : ti r 8 -p ' r-.?'.' :
- p, ..q,. ;
m g,.: y ~4 e+.+.-
. +
,.,e.7.
3
. . . e i p..
_ t
. . ....__. :r.. y
.. . c- :: w, c.y c &:a-w
.: riajr i -": t = 6 --F;:HE -:. --
ne.: ,,u, 4, ;i . i .w. . ,-c, m_ g - n i8 it ; - -*=7._._.
'8 ++
t"'*? . ;* - .
. ; ;. M. .T.. f ..a.,j . , , '- , m ^ q #. ' g .',y. . e- t.
.7 4 A. A-
** .7.'
m r J'-9, .4 4e
. r.n y, -
....en ,+ ..a a'J f.s d.f [2bir' + t;+ ,
" ' . ,.2, o, . --.o e .+ -
w.p. ..f4ht, :. . n,, , 444.a.644 .ad1444 4.aC4.m p mLn.Eamw .4-
--t* n-' w- *1ga., . n . ,
sa. p ..g. gs 4 , ., 6 we. hm
. . .s. ,2w .. g-( .n.- i.c.. . . f age
'4! .t... ., , . , ; s., aa..g:, ,
o . ... ~... . .
. . . l i 6 i . * ~~
~..~i. ; up. ~ * * * .
' .;d*d g e . ".- - - - + - - - - -- _ + - + - - n,j ; -
,r:: p; .g _w g ,
i i , - m; e-g- t
.. l -
_-..-:tr.r.v1 : :- .- m-:r r- : ::::: : .,n:- p _ _- _f r .=--- -
- dn. ,...- ;- - _- - -M _ _ .- t-- ;1._ ,.,. , . yg_ , , g . .._____ .._t- _ r.:]
- .i nw::::ur -i -J
_.E_u r=__:pI:: ..-d I- If .. wws_+pj3 . 2f i} - N
,-r. c i.w- :j._--
;F ~e;= ~"=~~b .: J* !.T hr*J: M%f;; . 2 2 tM nt /*"
- p zts- a-e:-: s y y +.sq &t ess r -n # i i i.2 *i'id.r:E.=di-81'.G.m ; h @- c.Q:=-Eis p:- y:::i.
-'E w; } i: ' JaJ - y=M1
- s{qiii ,".".E.E~rWJ.2Ud.-},
ti
- fr: :ie -;A Ma.,7.- s- s :th
.: +*-
?* 13-t; m
- . n. 3-r A+4 E ii s:_ 2 g , .:.M
- -- -r{ i 'd..4-1 4.-J.;..d._i1 e q e,
] r +, . f t - s.e.r - :- 4 .- .J:
- p,if.q( "rTONM M- M+i.- y 'f.f.,._N.c..s[_ , ~-p%Q I t.i j . .t .w.
O . kyt+.p-A
' :dPtfM:QQ.My]:;fWO_ I Sl. ,, @H.LD u M..,,,N@
n .
,M, g *... _.,.r .v.e, wp. .. -
- a. i M e
c..+ iW . . ,,
... ,_.a%l. O n.4.- . t. ~~,, ,-w ,-. t
.s w.u ,%. - ; zJ I,. ..,u'f;rq .
.n b.2 . _t A3 m = u ~*--*----s-att...i .'"i :- +.
-+ - -
.-* - e a+ D e p4 ia4. "-{ .a*]+;i- ; M i , -**t r-- -i i ?.:4-s. ..i a -r 4' *s
/ ~N ap b r: -J ".; -~ -
.iif
- e eH: ,1 g : - 8; r*
ex s
* +:' } c7- F-A :-
r + . .y- $ - :. '.4 - -W qft a-
- q : #.~r ;- .4 - :
-.u.;.
----- .:i . -i .-'i. - . ,b. ? :. ' t i. e ' , r. .;E .*. .:z.' :
Q
- b' N ** p*I ! 5 I bS 5h' -h*f bd . [u'[h*A ( 4. ~.~/ I.
- M.'5 _r ..h -ht .. Mh hr'f'M.! U :* L.i /..5
===
tM
- o % ~ W H.h.'{..s.
eL 9 s6 . h @. ~.k N -i' y%.s -
+ -Hh W -a.n.M ~--Wo - &e-y.&. . .m , av i.-+:+" +-9-..e.. - 9w /,; .6. I.7 ' - .u p
-> w f . . ~y. . W.
4
.n uw; sa., :.y. -u e > 0 y _, q . ..r W' y y }:#.n . ,.
- 1 :
w u.. n . ~_ ~~b..- ~-e.n ., sw, p. . w . O * + -+-tT* 3- - + ^ . n. 4 ..
."I ...-...4 ; 4
- t. f. * .- . - ~-.*p
. &. 4"_ 4 . ' 1 F .+
- --+p.'.* 3 O
--+-w...--"*-
.,_..1,...
.. . . i g
--4. g++--- -.g .:
-9 y O .e _ ; m -+- +:- *----4 ; - .. ..
+ .. . . . .
-~
Z am **,
- .. :.:rm.:~3.
= :.-:- -- yt- 2 :* -- ..-
r *cTO-*J : ..:j;. mn:-:cr7*h.
- 2 4**q* ; '-t .r.9
*- T T t .
n: : .
"*~~;g
-+
?~&;_ ;,..- _.. ,::: ::p- :md : . :t r: ::... ::-- . 1 J _., -jr!".?:;n;;
=...~.a...
-- h
. . ., .g_ . :- r :-:T
....j .. ~ . g:7 =:_.c .. . . 3. ig- L. . N. . q- ;
y. n + . l -- '--
.g p g.:q) g :. a. . 7 ; . g ;;E 7; ;j- t..... --4. . . :. ,-d g- _ ..g: . . . . ~.w-i .t
.. t F r2;m.y:. ~m - --7 4 - A. v- - - + -.- p--4-l-7. 1:. Q, e.r.n.y:- 7
;_.4.,.:
. _1e a u....
c -..m, O ..-. 4 pH : : :.- - - 3 ,. - ....tzr . _ . r. r. : w: , . .- t.
. y3qr g,r+ -
~ .
- s -
, ,3 w . m_ .@.: 4 ;% -- . 2.2. p ;..- r.i
.L.f--
- g. ,. - . . 4+6. g - . . +.
- y: - +- . 4 3: . .. . e . 'p 4 hp-e p .$$7dcP y! J +p .9. g y
[ .a.a.so.u.4.-. M A [#,he_% hT M; i j h. .i; . -4'M-4--@27J 7- yh h+ hy $.}~i,,' !.k.($
* * '# A-[
*" .'-'-N "~d I 7' + D f
b ^
?-+--*-- --*E+
~..{$ i. h4j ) p
- Mapew~'
,0 _'".e..s.w---'W"'N'-'."+W.., . .d
'{t**W1.,d r. .% ' ' ."b 6 d &' .yi W. -- d .t. 6 . .;,, h' s.4 -4.h '6";- . 44 . t. g.4. ,.C. .,h. *.J."h* m ).T n.a *r A,
' . m m--r**
.p e . - .1 .& - - -- - - -- - - ' - ~ -
- 84. w4
*g+ .-+
..i.i,.i
+
.h i-. a t i-*
w '. t +44 rsi .. :. t
+r.-3T :- q. .E- . . . 3 . .mi# tr *Er es a v. [9 6++.m
- id n -4 7-:ir hi +- r: rn H 3-i-..s -t - .3 zi + , :i .
+, .d,._:-2
. - : .:% ;- - w w e t4 M w-r, i ,. %.
e+ i- .~u -*g --e--- p. -6 ., : . 15 r,. ; i U 9,sa MLp,t e: s er. 4. .+92
.ua . M.*
't- d.4 n"-y a . W i' ee 4 s .-t g- t pr . ie6 .e: a .- i. site. cs3 .
W .' I'*. --
4
- <* l. n .- n , 4
-1 -*e*
."i.- We#
e { { %g,r.-- -.) lW .".f4 . ai.t +. y- . ,. . . - . =, ., t,t+- i
*ty*h*b": *** f- -
t+wh-
* ' ^
' l' 5 -.r-'T"4
+- a 4? : ' N'- {.L W.- (_- p t4 ' - r .-hh,M
,,
- ttim. ,y+% , .-he.rtO4m i m
. . . .._,_4f i Lw .
*+mM+r ~ { yd*..;1.=.*did}. 'E .'mad.
- M o ..... . . . . . _ -+ L%. : ...... . g. .... ..
6
..*.."p... . . . _m /,-
.p ....
8 * - - " - -
. . 4.2 : * * " " - ' -
- 64 . . . n.x._._,_ i *n**--"* -*-
f- N
,. . . . ....._.-..--sm i, *****C1....-.^ ---*: . - . . .. ~C-**-"-*...._ _ _L i
"*i... _/t -- *L ,. .t, T. t0. ;. * ;* W .. r....n. .- t .T. .r _O, ! - -. .
- t. :. ..:. -* ; : . . . . . _. _ ._. _4. ; LO. . , * -
*:*::',. . . . . . - .___T.-:_2,._.._.... . . _ . _. ..
_t t =':i;. . : f .: rn
- ater : : ; :. n.::.w .- t;.T.=
M;.4. : =L;r .- J.3 % . W
**f*:!iM u h.,;...=.:rin:nc s.... .-5 s, E n, M a ,-{ N . n. m M a N $ - S h --N-N- r5 ti- .r z s nmM u-:- M N -.n.2 Naa-.1.11 r=-da ;.:-h -N.nm a
m N, _ _3iYMDN 8
. ; : n. ! r j -z . :. -+ : - 2 4;I .4, 14 ua. t,v a.-:L.+1 w ~11=1 m m4t;g.d ' .: r st V*'~. p f : i' f.
2; . . 2.,
/. f - M** "-'iM'. 'r+*'}.
. sf*:*4 n nt ? p Y t"T , *gt
+ .- ,r.t.' t 4"= r t lt:h.:
. . a a' h ..j i .4.-9 ,=
o<; r. % .y b' 4 e ;-t
- 4 g-*4.y Ht 2
+3 ; --*-d* * ?
- n pa1
~ .
gi s. F.%:
.n..,. . _ 4.'b. . sW h., 4,J d. Ly 6
+m., '
+m..l.+^ m.
".' r i .p*fi .im
.;-r a . 4.- sw.. , .gJw..,n,.. a !!h.,M.u.m.3 .
- a. 'o 0.
. _~./.'t "9-1 pN - '-1* J, .* 1.
i%. o...-.',a - . ; - a u. . :a
' . .. ; .,y.
1
- . h. . [ t - .
' i -
t ye- . :tj & r ::
. o .t r.
7 i- . ' . : . > : i.a.,... p'.. : - :
. . _. : . .. *2- E- i t.%i : i i .nga . l . ... : 4_.:_.- .. 1 . i_':.j . *. u 4.--
..a., y- .a . < . . , . t: ,m.....
. 3__ .,
G = t 3.i..... . . , _ , - , , . .
-r .. id -...t-. . , . _ . ,pl c...-
. . , + . .= l.*.;-...--.-. .
N *
=
j , . . a. & . h ~. . _. J - m 4 . 1{,._ib._i. . p. - _.__-u-._- r ._4_ +M**1A. 4". - 4.--4 . j~
- ...s. w L
.. .a- . ~ .- _ .
._ 2 a_ t .'
- ; . p.a
..w %. ;
. . . . f.
~_.*
, , ,V, ' O
...-.,I-#.-.o.....d. .__/..
++
.._.,...m..+ . .. ...- . .*-- - * .
. ... . . .+ . - ..._%. . .. .. . 7 , . 4 4
. ,:~. r *
. _ .j*
.~.1.II*
. ...Z **" .rCC*.*. -.
. . . . --. -- *- - -- ~ ~ - * ' .~ .. _~
.-.4-.""7.-..-..
.. ^ ^ .'-*-M U
[ .
- .c r _ . .; ' : : * ! * *
.r ;----tm .rrr t : :.n ' . : .1J': T r:? !=:_.
" .:~*-* ;f --" r _
- _ :r : * . "1::- .; .._c.r.;rt: >
.{- -. . ,*2 j;;*:. . _ _ . .
** . . . . ..;. .;* - rii: - - - !
* ** ~ 1 2 ; . ' ; *S -
...---T?;*-~_
)- . m.-
N
--n------
---. _-+: ._-. ;.
g __ .
- -__---;&._.r r : ,,n: g;- ....-:n:r f w;m n m,,
. ) tnz. ,:
.t : : .; ; . .; e : .. . . . . . -
- f. t L.x. .4 j L .: ..- - . p_ 4 . s. .;_ y. -- -
t. g ;. a a
-k__.- -
r .I - -h-- . .
-}.( L. - L -- -.l---.
"f-
. f. +i dN.-c'e. t - ---[-
_ _ .. . .i. J. :. ^2 i W. M
- .- -- - 4 W4 1. . c .. . - -
. ,ut'W . g..N.*.Ilmv. , -*,
G. t *: - - l-i ' m E----- - n . i..
- o .;
7., d* -*- . -~ c + -> 6..~,--- -. >
. bM . , . --+
- x o . ,c- ..a L4 < .-Lat ~ m.tv. . .t! .pu.m u Li;. L.q_
s
. . *
- p p. .u .
g l..,a. , 4 b. ..
. m.p a+:* . . *.
~1. :-F. .t c=qtt* I-I
....1 ; s!- : j 44 i i : 4ed d.i ?:- .-i MWM ,' 3-d
- m. = m. .
. ! . i ... i . . ry.f -i :- .
tn i *
~+tm e. i . r H; L.. ..:
a ! --* ' :- H i si $' :r; +-': " c W M h MN , .d - ' .f '.*~7-- s ' GW. -1 d e. ".i i w J - 4,tt. t+m.m**e s.,m %.: u !1 q e g . .
~"l 9+.
- m. ~'----mq. .
.w+ e W . M, h.* m.u.=.
*t, Jc::-A v 4,_.Gv-T t_ = :.t++t-+**-----+-+-.-*+n9+*+-+--+---~>--m
.:r 'q # a mc av. gg. %wm a.c h s h - m s re srm O t=* ' '
l
- m. . -
f ,. m -e -e ,-P q ,.
w ... S E T A D T N 2 E U 2 Q A6 1 E . e S vg X B I U ea S RP Q _ E' _ l P @ P . A 1/ 5 0
. /
. - 9 6
E T . P A S D T
. M P R E
_ O D _ F / Y _ N N O A I P _ T M A O R C T S T _ _ N I M D ._ A _ I O K N . .. - e,,l ,. , :.
. E g} -
s . .. E
~
. Y r.'
,. :.s O g.
L s-i. P c. .- . M .: , . E . -*
._-.: . s
-.,t
. . .,.1
. ,t
_ O . s. N -
. g*
. ..!s C ;-
. ,.e E >I,
. c,:l S
- C O _ S E M A N
. -. < f
E ] i I y '.. r Subbitted l
. l
. Approved: ,
(Plant Manager) DRAFT-PREllMINARY SP Number 69.662.61 Revision B Date Eff.__ TPC TPC _ TPC EMERGENCY RESPONSE FACILITIES EQUIPMENT CONTROL AND READINESS CHECK 1.0 PURPOSE This procedure describes the method by which emergency equipment and instruments are inspected, inventoried, and operationally checked. It also describes how instrumants removed for calibration are replaced by spares. 2.0 RESPONSIBILITY The Ilealth Physics Engineer is responsible for ensuring the inspection, inventory, and operational checking of emergency equipment. (f [OI. b O , ll . :il' c .i Iri . ' __ v s n 4 0 #05 10 21. M 0-6. '. 21 i i
y > .. ,.r 8 . 3.0 DISCUSSION 3.1 This procedure is utilized in performing periodic inventories, inspecti::4-and operational checks cach calendar quarter and af ter each use for the [/T N-s following emergency equipment: 3.1.1 Emergency Kits placed at various facilities, of the following types:
- 1. Downwind Survey Kits
- 2. Decontamination Kits
- 3. First Aid Kits 3.1.2 Additional emergency equipment located in the Technical Support Center (TSC), Emergency Operations Facility (EOF), Operational Support Center ( OSC) LILCO First Aid Room, Main Control Roo=,
and Central Suffolk Hospital. 3.1.3 Communications equipment in these facilities including telephones and radios. 3.1.4 Facility environment monitoring equipment. 3.1.5 RMS System located within the facilities. 3.2 The following attachments are promulgated by this procedure: 3.2.1 Equipment Discrepancy List, SPF 69.062.61-1 is utilized for documenting and correcting discrepancies discovered during inventories, inspections, and operational checks. 3.2.2 Emergency Kit Inventory Forms, SPF 69.062.01-2a through c, are used for inventorying, inspecting, and operationally checking the kits and for recording general results. 3.2.3 Emergency Facility Inventory Forms, SPF 69.662.61-3, a through g, are used for inventorying the emergency facilities. Separate copies of SPF 69.662.01-2 must be used in conjunction with the Facility forms for kits located within the Facilities. 3.2.4 Inventory Form Instructions, SPF 69.062.01-4 describe the use of SPF 69.d62.01-2 and -3.
- 3. ,i l l ewir vnt with intearal rechar; Ole batteries shall be kept charn :
in anordance id th Lhe MnufacturerS rN00 Nndat ica.l . 1 :u t -im :n h rc w d .cd storo' after merr i'aal. che ss on the "U at r o n r. e_ darage. SP 69.662.d1 Rev. B
/ / 3 age 2
F-r
,. s 4.0 ' PRECAUTIONS N/A s
).O _P_REREQUISITES 5.1 Obtain the necesssary Inventory Forms, SPF 69.662.61-2, 3 and 4 for die inventory.
5.2 Review the previous Emergency Equippent Inventory forms for a list of equipment that will require recalibration in the next four months and obtain replacement equipment. 5.3 Obtain replacement TLDs if their previous anneal date is more than months ago. All TLDs in a facility or kit should be replaced at the same time to preserve the validity of the control TLD. 5.4 Obtain replacement Direct Reading Dosimeters (DRDs) for those that will require recalibration in the next four months. 5.5 If the Central Suffolk Hospital facility is to be inventoried, phone to coordinate and arrange ' access. 6.0 LIMITATIONS AND ACTIONS N/A , 7.0 MATERIALS AND/OR EQUTPMENT 7.1 Seals for the emergency kits and lockers. ( 7.2 Sealing tool and removal tool. 7.3 " Incomplete Inventory" tags for labeling discrepant kits and lockers. 7.4 Sufficient Inventory Forms. 7.5 Keys to Facilities to be Inventoried. 7.6 Two way Radio of same frequency as those in Kits and Lockers. 8.0 PROCEDURE 8.1 Inventory S.I.1 3reak the s.ml on tim Inckcr or kit. 8.1.2 Stens 8.1. s thru 8.1.10 are riost efficiently acconolished sequant f.ille for cach item. 8.1.3 O m.1t the ninher of units rse a foc un 1:r a :' . enter :' amount found in the appropriate column of the inventory shai:. 7~
\ -
SP 69.062.01 Rev. B
/ / Pace 3
~
. 8.1.4 Rscord tha SNPS ID numbsr of the actual equipm:nt found. Wh:n replacing equipment that requires recalibration, enter the SNPS ID number of the new equipment under " Action Taken".
N 8.1.5 Enter the recalibration date for the equipment with the exception of Direct Reading Dosimeters. Review the recalibration dates of all DRDs and remove those that will require recalibration within four (4) months. If the recalibration date has been passed, make an entry on the " Equipment Discrepancy List". 8.1.6 Assure that DRDs, TLDs, at d other dosimetry are stored as remotely as possible frem the check sources. 8.1.7 Perform an operational check of those items for which preprinted "N/A" has not been entered on the " Emergency Equipment Inventory" form in accordance with the "Special Instructions". 8.1.8 Inspect the items for evidence of unacceptable physical conditions or damage. 8.1.9 Record discrepancies by assigning a sequential number and other required information on the " Equipment Discrepancy List SPF 60.662. 61-1". The following types of findings shall be recorded:
.1 Shortages of major equipment (note that numbers given for disposable items such as swipes are target numbers and that numbers of such items may be estimated rather than counted).
w
) .2 Damaged or missing items.
.3 Out of date or spoiled items.
.4 Broken or improper seals on cabinets or kits. .
~
.5 Items that are beyond their recalibration date upon inventory.
8.1.10 Record the numbers of all discrepancies entered against a particular item. 8.1.11 When inventory is complete, rescal the kit. Tag it with a label " INCOMPLETE INVENTORY" if discrepancies exist. 8.1.12 Return all Inventory and Discrepancy Forms to the llealth Physics Engineer for resolution. 8,3 ilealth Physics Engineer. perform t.h2 f ollottinc . M.1.' R 2 mIt 111 ii scrertnn Im ' h we a W N 1 indivi<!ual real e.i? c~ ;rge wy Rits or lackers . :-l reseal. O (s / SP 69.062.01 Rev. B
/ / Page 4
8.3.2 Enter the date that the inventory was closed (by the resolution of all discrepancies) on the SNPS Scheduled Activity
~s Worksheet, complete the worksheet and return it to data processing.
8.3.3 Assure that " Instrument Malfunction and Calibration History," SPF 61.986.89-1, for each kit or facility is updated and refiled from the results of the inventory. 8.3.4 File and maintain all records of the inventory. 9.0 ACCEPTANCE CRITERIA The numbers of units specified in the " Emergency Equipment Inventory" must be present in the kits and cabinets, the equipment must be in good functional condition, and the calibration due date must not be passed before the next scheduled inventory. 10.0 FINAL CONDITIONS All outstanding discrepancies shall be resolved and the seal applied before the inventory can be considered complete.
11.0 REFERENCES
Shoreham Nuclear Power Station. . Emergency Plan, subsection 8.3. 12.0 APPENDICES () 12.1 Equipment Discrepancy List, SPF 69.@62.01-1 12.2 Downwind Survey Kit Inventory, SPF 69.962. 1-2 1.3 Decontamination Kit Inventory, SPF 69.962.61-3 - 12.4 First Aid Kit Inventory, SPF 69.962.91-4 12.5 Main Control Room Inventory, SPF 69.662.61-5 . 12.6 Technical Support Center Inventory, SPF 69.962.61-6 12.7 Emergency Operations Center Inventory, SPF 69.d62.61-7 12.8 Operations Support Center Inventory, SPF 69.062.01-8 12.9 Firs t Aid Rmn T m.mnt ory , SPF 69.062.01-9 12.10 vehicles Inventory, SI'F 69.062.01-10 11.11 Qut r i! " t f o l;- ,;itil Inventorv, SIT 69. 06 2. l1 '. ! 12.12 Inventory Form Instructions, SPF 69.062.01-12 i Cs SP 69.062.01 7ev. B
/ / Page 5
D E R A E. CI N! e E . _ _. T . h _ g' D e _ l i ti 1
. O
)'2 N _
E - - _. . K _ _ . A T N O I T C A T S l. t Y t N 2 A 8 l' / i H 3 1 C / S 1 l i l N _ T O N I E T I t' A i C l O l lj L s. l' Y C N A P E R C S I D 1 E - T 1 A 0 D 2 Y 6 R 0 O T . 9 N O 6 E N F V P N S , I
iist i.: : - a DOWNWIND SURVEY KIT INVENTORY ID~
~
NU51NAL QiF5iTI'TY ~5EUAL~ 'Ott k 111:. ft FGUND kWBER DATE SPECIAL INSTRUCTIONS Ct!K l No ACTtoh TAkt N NO. EQUIPMENT QUANTITY 1 R0-2A (Eberline) 1 Check eattery and Test with " Check Source"
~
Check aattery and Test
~2 496 (Victoreen)/HP-270 1 with " Check Source" 3
RM-14/HP-210"(Eberline) 3 [**",,$***g],*j,.
, rest 4
TCS Air Sampler 1 Check operation with (Bat Oper.) , 12 volt Power Supply 5 Shield Assy with Samplo 3 gj, ,j, ,j, gj, Holder for Item 3(SH-4) ~ ~ 6 Filters.For Item 4 30 ,,, ,j, ,j, ,,, 8 Smears 100 N/A N/A N/A N/A
~
'9 Ultraview Respirator Vith 2 N/A N/A ~ Check Expiration Date N/A GMR Cartridge of Cartridres INVENTORY BY DATE REVIEVED BY M i E __ _
SPF 69.962.91-? SuEET 1 0F 4 I/13/82 id2
*;P W ,' '.01 Rev. "
'e o Ea t .
N. l k E A . T . i. N o
. v e
~ R T
C A l E
- 1 T 8 A 3
~
i l d. s s ; s t il ho e
~
l I
~
A A A A. A A i/ / i ilEK E11
/
N
/
N
/
N
/
N
/
N
/
N N N dC ~ k c e y h r s C t e e t d m S a n i s N D a o O D' I p s A T x e A A A A _ Y C E i / / ms ot
/
N
/
N
/
N U r N N R R d e rn , O T r t F e a Y T S o t yu B N c a N I e B n a r D 2 E N o wt E 8 V L A tD s li l t As n V / N I oR aa eI E 4 3 1 I C nD t r r I E s e od V / np t n E F 1 T P of SA R O I S Do IO 2, K T Y A A A A E E E L k cy A A A / / / / l V i AE / / / N N N N N S CT el N N R EA tn U RD CO S D N R E A A A A s A A A I DB / / / / / / / W N I M U N N N N N N N N W E O T D Y T A I D D _ TN NU AO UF Q Y LT _ AI 1 1 1 NT / / / I N MA OU _ 2* i 0 5 1 1 1 2 2 NQ s y r h e e t F t i e W o n g / m n i s i s g t i o a a k B r D t r a S e T g *O e e M r N n l l p / E i p a e a g u M d r m t c P n d P a e a n r / i e e g S e u d t c I U R r m o r i o 2 a c n S a r r - Q R o W P E t M h i s o 1 c 0 R C tl r k b p s
/
s . 0 e 0 s e i c _ r 2 5 D ab v e i n p i - - R l a n h l e a Y 2 D D PL E C C P M B 0 0 6 Y R O 9 T N 6 E V F ' 0 a' 1 2 3 4 a0 5 7 8 N O. 1 1 1 61 1 1 I P N 1 1 1 S
i ( e A eM-s w 1 A e Q C a
. O W. C-e
' ** s i s.
l t 'na 4r g
? 3 .
a c.
~
. . C
~
LC , T 7 I 2.- a [r ' t I
'4 ,.C iG 4 *C
- C aC 4 <C aC *C I,%
tea M % % % %%%% % l% = a -: x z i
= =z=x x iz QU 9e 9 en C > Q M ew e O e G &
N e& e e se
<C U U U = g
- 4 % *m
- e o c3 M se % se u e e.e e g l cs.
v a a 4 g g >e us 4 a.* a a g - ac <C *C aC
%%%% % u e a3 g,1 x % ar a 80 De R22M M C Q M 2. 53 C C Q Q N h
t 4 M
=C aC i e3 4 a-4 ce h -4 sal p'.s - %
4 ee t.e ** pa e e M Jd A haa e4 e& U M M en 4l U e,b M e e5 W % & > % H A3
'm 40 e ao ae a a a U
sq m
- ee Q
e-4 M MH mb U V g a nl
>=
a
=C aC .a4
.J 4 =C =C aC aC <C *C aC aC aC
'2 4 ta? % % % X X M
>* E 2 A X X X22X E M .M R. . M laJ *C *C *C aC =C =C aC aC aC 4 4 Q a3* % %
X E Z M 2 iX M 2 X2ZX wt.
)3 Eo 5
?t ac O O Lee O
- - 3$- . e 2.e $* N **
.3*
- O
- N NNNN M O n AQ
/
ee A
.ee -
se o O 3 ne e a3 g O to N en g a b O o be me es a .e U. Q * .e M S 9 as. Q w 4 e u me o O 4 en V3 e las og ' , A e 4 g he
% % ee C y
- V3 % a g
4 o -=0 e4 O A e e .e me e 4 he e 3 3 o u - a .4 W tJ B 5 w A as w as
- to O 4
Q
- 6 N e.s e Je m -e =J.
** a e m. o a > e- W e N 3 b W= we ** 3 es* C 9
c ** l C7 ans .e 3*. .at e -.3 e w eo a o ' g saa o >= 4 a ve he e ee .e.e o
& 4 4 at e g a
as he ed Q
> og ed W > es q I ** ed as e ., o>ooo a. as a >
f g o 6. 7 6e o - o wo-oo g w o m I K va b h m huom= p & v j-
>e M l a.
a . i i w t
== >
. Z b
= lO 'N l N M 4 eAW9 en 4 gf **
O e .-=
'N N I N N N N N *= CLe Z M
- t e
$ eO I M W
N
. M R A
T N v; O ea l I T RP C A i E - l I n ' i e _ t _ 0 IIl k 9! 6 o mh P R EK
' I I
0C d rrrrr e eeeee c
- t t t t t a
- s sss s l eeeee p
- S TTTTT e
. N r O yyyyy I rrrrr e Y eeeee R -
T b e C t t t t t m . U t t t t t ti O k a aaa a st T T BDBBB u N S me Y B N hhhhh m E I t t t t t s a V iiiii Ds D 2 N L A WWWWW I Te E W 8
/
I I kkkkk h E 3 C ccccc l t I 4 1 E eeeee l V / - T P hhhhh At E F 1 s I S CCCCC
- a R 0 K
Y
- 4 T
E F E V ~L AAAAA l R IE ///// i S CT NNNNN U ~E A S RC D N R I E AAAAA 0B ///// W 1 t N 'liNNN W L N O E D iT T A
- iD D IN U
- 5O UF
-Q Y
LT AI 5T
! N )))))
hA( U ((((( NQ e eeeef ff ffi iiiil LLLLp ggggo T nnnno N ooooL E: LLLL t - P - - - - I s l U e ll ll l 2 Q i ll l l e E r ea eeC e CCCC 1 t t '
* "A 0
a D C "B "A A Y B " " " " " B Y R - 0 O - T - 9 - N E - 6 V O. 8 ab cl e i N - F I N 2 - P ' S
.: ll16 l % I i
_ DECONTAMINATION KIT INVENTORY ._ _ NCHINAL QUANTITY' ID RECAL OPER lit : i ti NO. EQUIPMENT QUANTITY FOUND NUMBER DATE SPECIAL INSTRUCTIONS CilK ha ACTION T.\kEk I Radiac Wash in Spray Bottle 2 N/A N/A N/A N/A
' ~ ~
2 Washcloth 2 N/A N/A N/A N/A ~
~ ~ ~
3 Paper Towels, roll 1 N/A N/A N/A N/A
~' ~
4 Soap, bar O 3 N/A N/A N/A N/A 5 Plastic Sheet 4' x 8' 1 N/A N/A N/A N/A
~ '
6 Scissors With Comb 1 N/A N/A N/A N/A 7 Tongs 1 N/A N/A N/A N/E
~
8 Protective Clothing a Coveralls 4 N/A N/A N/A N/A b Cloves With Liners 4 N/A N/A N/A N/A c Booties 4 N/A N/A N/A N/A d Hoods 4 N/A N/A N/A N/A e Dust Hasks, Disposabic 10 N/A N/A N/A N/A
'9 Plastic Bags With Labels -
10 Callon 3 N/A N/A N/A N/A 10 Q-Tips, box 1 N/A N/A N/A N/A 12 tape, Masking, roll 1 N/A N/A N/A N/A INVENTORY BY CATE , HEVIEVED BY I: A l'E S!!EET I 0F 1 13
- 3/13/82
. SPF.69 .01-3 sy r, ,c, ,
,gg Pa c , . 11
i e i t ill t *, t , FIRST AID KIT INVENTORY NOMINAL QUANTITY ID l OFEa o t:el<
'.0 EQUIPMENT QUANTITY FOUND nut 1BERDATE ' RECALSPECIAL INSTRUCTIONS Cl!K No ACTION 1 ARN 1 Small oxygen Tank and N sk 1 N/A N/A Check Tank Pressure N/A 2 Tourniquet - ! suckle Type i N/A N/A N/A N/A 3 Stethoscope 1 N/A N/A N/A N/A 4 Bandage Scisso s 1 N/A N/A N/A N/A
'5- Emesis Basin 1 N/A N/A N/A N/A' 6 Pentite Flashlight 1 N/A N/A Check Operation With N/A Battery 7 Sterile Gauze Pads 2" x 2" & 4" x 4" 6 ea. N/A N/A N/A N/A 8 Gauze Roller Bandage, Roll 1 N/A N/A N/A N/A 9 Roll Adhesive Tape 1" 1 N/A N/A N/A N/1~
10 Klang Bandages - 2" & 3" 3 ea. N/A N/A N/A N'/A~ II Plain Absorbant Gauze 24" x 72" 3 N/A N/A N/A N/A 12 Sting 1 N/A N/A N/A N/A 13 Annonia Inhalants 6 N/A N/A Check Expiration Date N/A INVENTORY BY DATE _ REVIEWED BY IdTE .___ _ _ _ _
-- - . - - - _ _ _ _ _ _ _ SilEET 1 OF 2 1/12/82 1P
', SPF.69 .01-4 SP ' 01 R
)
N. t 1 k A . T '
. ~ e N ~
e ' O I _ K l T _ C _ _ A _ E M 3 A l i ~ a i I. r u 4 t i k IMoh D R A A A A 8 A "A A A A EK / / / / / / / / / / l' l l N N N N l A N N N N N OC e t a D e e e n S t t t o N a a a i O D D D t I a T n n n r Y C o o o i R U R i t i i t p x O T a t a a E T S A r r r A A A A A Y N N / N i p i p i p k c
/
N
/
N
/
N
/
N
/
N B E I x s x e D V L E E E h E N A I k k k C V E I C c c c I 1 E e e e V T. _ P h h h E F. I S C C C R 0 K- g D T E 2 I L A A A A A A A A A A E 8 A AE / / / / / / / / / / t i / CT EA N N N N N N N N N N S 2 1 T RD / S 1 R I F 'RE A A A A A A A A A DB I tt
/
N
/
N
/
N
/
N Wt
/
N
/
N
/
N
/
N
/
N u N E Y T T A I D D TN j Nl AO UF Q Y 0 LT 0
- AI 1
!NTN t A 1 1 1 1 i 1 1 1 i OU NQ e
d i x l o o r s p e e o s i b P r n r u e o t T n A i t S e t e e , g , c k cg e o y r u c i a v rb r a e e r a T t k l d l t t P N s c a ly p t e s t E a a S e S t m n e g M P l P P e f l rt c b o o m I k n i n ._ I , t ot i r d a s 4 U d s t o t n, e i l s s - Q ee p l B p h A B r e - E t g e o e i T e r 1 ra s hl s r t e z D 0 od i ol i i l s c e sn t c a t p a r a e e s a n l m n s r i p w y Y 2 AB A AS A A O F S T E B 6 Y 6 R O 9 _ T N 6 E _ V F 4 5 1 8 9 0 1 2 3 N M P 61 1 1 1 1 1 2 2 2 2 I S
61 f * ,s i t t ', MAIN CONTROL ROOM INVENTORY NOMINAL QUANTITY ID RECAL 01'f k b ! :.4 is NO. QUANTITY FOUND NUMBER DATE SPECIAL INSTRUCTIONS CilK so ACTioM 1 Akt N EQUIPitENT 1 First Aid Kit 1 N/A Inventory per FAK Emerg Equip Inv Sheets N/A 2 Emergency Plan, Shorcham i N/A Updating done in accordance with procedure N/A 3 imergency Ope 6ations 1 N/A Updating done in accordance gjg Procedure with procedure
~~ ~ ~ ~ ' ~ ~ ~ ~
4 Emergency Plan Implementing Procedures 1 N/A Updating done in accordance with proceJure N/A s 5 Logbooks 1 N/A N/A N/A N/A
~6 Eberline RO-2 1 Check Battery and Test with check source
' ~ ~
7 Duct Tape, Roll 2 N/A N/A N/A N/A' 8 Batteries For RO-2 7 N/A N/A Check with Battery Tester l I
._ i ! .__
INVENTORY BY DATE REVIEWED BY MTE _ , SPF 69.062.01 -5
--- - -- _ _ - _ _ _ _ S!!EET 1 OF 1
- I/13/82 58 2 17 Rev. n
- - / Pa ,
> I l i t ! ?, l 4 TECHNICAL SUPPORT CENTER INVENTORY ID RECAL OPER Ot.* ia NOMINAL QUANTITY NL?!BER DATE SPECIAL INSTRUCTIONS CllK ho ACTION TM EN NO. EQUIPMENT QUANTITY FOUND 1 First Aid Kit 1 N/A Inventory per FAK Emerg Equip Inv Sheets N/A 2 Emergency Plan, Shoreham 1 N/A Updating Donc in Accordance with Procedure
~
N/A l '~ l
'3~ Emergency Plan ,'aplementing Updating Done in Accordance Procedures 2 N/A with Procedure . N/A l 1
~
I~
~4 Emergency Operating i N/A Updating Done in Accordance N/A Procedures with Procedure _
5 Logbook i N/A N/A N/A N/A 6 Paper / Clipboard 10/5 N/A N/A N/A N/A 7 Pens / Pencils 30/30 N/A N/A N/A N/A ! k 84 Eberline RO-2 2 Check Battery and Test with i Check Source ! 8b Eberline RO-2 _ Check Battery and Test with l Check Source l 1 l l t
! ENTORY BY DATE REVIEWED BY n i l E _ __
__SPF 69.062.01-6 SliEET 1 Or I 17* 1/14/82
'"). ' . 01 Rev. n
' Pa,
l' 6'l !!! t t - 1 e TECHNICAL SUPPORT CENTER INVENTORY
~ -
NOMINAL QUANTITY ID HECAL UPiii~ ' IH n H f No. EQUIPMENT QUANTITY FOUND NUMBER DATE SPECIAL INSTRUCTIONS CIIK Na i ACTlo.N l' Ah th 9a Eberline RM14 with Check Battery and Test with ifP 210 Probe , Check Source Check Battery and Test with Check Source o i b l Ila RADECO Air Sampler Check Operatien with 12 Volt !' 1 Power Supply lib TCS Air Sampler 1 12 Teletector-Ili Range Survey Inst Eberlisw 6f12 1 Check Battery and Test with Check Source
~
13 Calculators with chargers 4 N/A N/A N/A N/A 14k TLD N/A N/A Check Anneal Date N/A 50 INVENTORY BY DATE HEVIEWED BY P il E . _ . . __ SPF. 69.662. 0.1:6- SutET 2 or I 1/14/82 5/2 9.'hl.dl
u n oi.i x 1 / e. TECHNICAL SUPPORT CENTER INVENTORY NCMINAL QUANTITY ID RICAL OPER Is l S. s { W. EQUIPMENT QUANTITY FOUND NUMBER DATE SPECIAL INSTRUCTIONS CI:K ho ACTION TAht.N 15 Direct Reading Dosimeters _ __ a 0-200 mR 100 N/A Check Do Not Record Expiration N/A i Only Dates of DRDs b 0-1 R 100 N/A Check Do Not Record Expiration N/A Only Dates of DRDs c 0-5 R .' 20 N/A Check Do Not Record Expiration N/A Only Dates of DRDs 4 0-20 R 10 N/A Check Do Not Record Expiration N/A Only Dates of DRD.
-- ~
IE DhD Charger 2 ' N/A Install Batteries and Check Operation 17 Particulate Filters For Item II, boxes 2 F/A N/A N/A N/A
~
l5 Canisters for I' w iib 30 N/A N/A Check Expiration Date N/A lE Smears 500 N/A ; N/A N/A N/A 20~ Flashlight 10 N/A N/A Check Operation with Batt N/A INVENTORY BY DATE REVIEWED BY HE __ _ SPF 69.062.01 SHEET } OF 1 1/14/82 L'
- E' +0
. .31 Rev. l',
-
- P. t ;
I l'l llhi 1 e. TECHNICAL SUPPORT CENTER INVENTORY
~~
Nott!NAL QUANTTTY ID RECAL ~0P5R ~ ' II M.Cic teo . EQUIPttENT QUANTITY FOUND NUMBER DATE SPECI AL ' INSTRUCTIONS Cl!K Na ACTlhN TAM N 21 Absorbant Pads. case i N/A N/A N/A N/A 22 Plastic Bags - Large, box 1 N/A N/A N/A N/d 23 Plastic Sample Bags, 100 N/A N/A N/A N/A Assorted 24 Plant Floor Plans 1 N/A N/A N/A N/A 25 Lead Bricks / Blankets 18/2 N/A N/A N/A N/A i 26 Protective Clothing Disposable 4 Coveralls 50 N/A N/A N/A N/A l le Surgeon Caps 50 N/A N/A N/A N/A , c lloods 25 N/A N/A N/A N/A il Booties N/A N/A N/A N/A 50 N/A e Shoe Covers N/A N/A N/A f Poly Disposable Cloves 50 1000/ Box 2 N/A N/A N/A N/A N/A N/A N/A N/A g Latex Clove" 50
~ '~
27 ~ Masking Tape 2" Width 4 N/A N/A N/A N/A 5~ Radiation Sign With 4 N/A N/A N/A N/A Inserts 29 Radiation Rope, Feet 100 N/A N/A N/A N/A DATE REVIEWED BY DATE INVENTORY BY SPF 69.062.01-6
- -. S!!EET 4_ OF 7 It' 1/14/82
' M ' '.di Rev
, n..
i , .:te l s .. TECHNICAL SUPPORT CENTER INVEhTORY NCil!NAL QUANTITY ID RECAL OPEk I.1:.f H NO. EQUIPMENT QUANTITY FOUND NU'!BER DATE SPECIAL ;NSTRUCTIONS CHK 80 AT!oN 'l ut N 10 Tape, " Radioactive Material" w Dispenser 1 N/A N/A N/A N/A 31 Tag, " Radioactive Material" 100 N/A N/A N/A N/A 32 Kraft Paper, 36" Width 1 N/A N/A N/A N/A 53 Plastic Sheet 24" Width, Roll I N/A N/A N/A N/A 14 Herculite, Roll I N/A N/A N/A N/A 15 Duct Tape, Roll 2 N/A N/A N/A N/A 16 SCBA - Pressure Demand Type-MCA 463831 4 W/A N/A Check Pressure N/A
~
Replacement Cylinder - MSA 460320 4 N/A N/A Check Pressure N/A as Keys for Downwind 2 Survey Vans _ _ INVENTGkY BY DATE REVIEWED BY DATE SPF 69.d62.61-6 SilEET 5 0F 1 I/14/82 II* 7 Vf- - '.01 'c
sn i onix l i. TECHNICAL SUPPORT CENTER INVEhTORY
~
NOMINAL QUANTITY ID RECAL CPEH 1. l :H'h
- 10. EQUIPMENT QUANTITY FOUND NUttBER DATE SPECIAL INSTRUCTIONS Cith No ACTION TAkt.N 19 Single Channel Analyzer-Eber line 21S-2 1 Check Battery and Test with 4 With SPA-3 Scantillation l
Probe Assy Test with Check Soart8
. IIP 210 with Aluminum Probe lloider Sh 4 1 Test with Check Source Loa Two Way Radio; tufz 2 N/A Check Battery, Transmit and receive 4Cb Two Way Radio, tula -
N/A Check Battery, Transmit and receive 41 Air Purifying Full Face Respirator With Particulate e and Iodine Cartridges tiSA 457111 6 N/A N/A Check Exp Date of lodine Cartridges N/A l r.5- Replacement Cartridges-MSA 88182 6 N/A N/A Check Exp Date N/A r j~ Bullborn 1 N/A ti/T Check Op with Batteries 4'4- Tool Kit i N/A N/A- N/A N/A 45-INVENTORY BY DATE REVIEVED BY _ MTE _ _ _ _ . . SPF 69.062.01-6 SilEET 6 OF 7 1/14/82 $1*
J ' t , .t el \ t 1. _ TECHNICAL SUPPORT CENTER INVENTORY NCrilNAL QUANTITY ID RECAL OPER DISCH No. EQUIPrtENT QUANTITY FOUND Nut 1BER DATE SPECTAL INSTRUCTIONS CI!K No ACTION TAkLS 46 Radiological ifcalth flandbook i N/A N/A N/A N/A
'.~ 7- Batteries For Instruments Long Life N/A N/A N/A N/A 4 "D" Cell N/A N/A Check with Battery Tester ti "C" Cell N/A N/A Check with Battery Tester c "2" Cell N/A N/A Check with Battery Tester
,1 "A" Cell N/A N/A Check with Battery Tester i "AA" Cell N/A N/A Check with Battery Tester i
INVENTORY BY DATE
- REVIEWED BY inTE _,__.
__ _ SPF 69.062.01-6 SHEET { OF 7
- 1/14/82 1/*
N1
ii : . i l '. l .'
- EMERGENCY OPERATIONS FACILITY INVENTORY NOMINAL QUANTITY ID RECAL OPER D i !.r t No. QUANTITY FOUND NUMBER DATE SPECIAL l'NSTRUCTIONS CilK No ACTION 1 AKLh EQUIPMENT First Aid Kit I N/A Inventury per FAX Emerg Equip.Inv Sheets N/A 2 N/A Inventory per SK Emerg Downwind SurVCy Kit 3 gy oip 3,y su,,t, n/a 3 Decontamination Kit 2 N/A Inventory per DK Emerg Equip Inv Sheets N/A T Emergency Plan, Shoreham i N/A Updating Done in Accordance with Procedure . N/A 5 Emergency Operating
. Procedures Set 2 N/A Updating Done in Accordance with Procedure . N/A 6 Emergency Plan Implementing Procedures, Set i N/A Updating Done in Accordance with Procedure . N/A
~
T Logbooks 4 N/A N/A N/A N/A 8 Paper / Clipboards 20/5 N/A N/A N/A N/A t f . ._ _ 9 Pens / Pencils 50/50 N/A N/A N/A _.N/A DATE ' REVIEWED BY HATE INVENTORY BY SPF 69.062.61-7
- --- - S!!EET I 0F 4 t/14/82 ilk
\lti' :1 X [2,/
_ _ _ _ . _ _ EMERGENCY 0PERATIONS _ FACILITY INVENTORY NOMINAL QUANTITY' ID RECAL OPEli DISUR' NUMBER DATE SPECIAL INSTRUCTIONS Cl1K NO ACTION 'iMrN so. EQUIPMENT QUANTITY FOLND 10 Calculators with Chargers 4 N/A N/A N/A N/A 11 Particulate Filters For Air Samplers, boxes 10 N/A N/A N/A N/A N/A N/A Check Expiration Date N/A 13 Smears 500 N/A N/A N/A N/A
~ ~ ' '
14 Flashlight 10 N/A N/A Check Operation with Batt 15 Absorbant Pads, Case 2 N/A N/A N/A N/A 16 Plastic Bags-Large, Box 1 N/A N/A N/A N/A 17 Plastic Sample Bags-Assorted 100 N/A N/A N/A N/A 18 Plant Floor Plans 1 N/A N/A N/A N/A 19 Lead Bricks / Blankets 18/2 N/A N/A N/A N/A id ~ Protective Clothing N/A N/A N/A N/A a Coveralls 100 N/A N/A N/A N/A b Surgeon Caps 100 N/A N/A N/A N/A e floods 25 N/A N/A N/A N/A DATE HEVIEWED BY D.\TE INVENTORY BY SPF 69.062.01-7 S!!EET 2_ 0F 4 1/14/82 37' o - . j
; i l'l - l'l l .' , /
EMERGENCY OPERATIONS CENTER INVENTORY NOMINAL ID RECAL OPER 11W G QUANTITY FOUND NL21BER DATE SPECIAL INSTRUCTIONS CIIK Ni ACTIu. IAktN t.o . EQUIPMENT QUANTITY
>I Booties 50 N/A N/A N/A N/A i Shoe Covers 50 N/A N/A N/A N/A f Poly Disposable Gloves N/A N/A N/A N/A 1000/ Box 1 g Lates Clowes 100 N/A N/A N/A N/A h Dust Masks, Disposable 100 N/A N/A N/A N/A 21 Masking Tape 2" Width, Rolls 2 N/A N/A N/A N/A Ei - Radiation Rope, Teet 200 N/A N/A N/A N/A 23 Tape, " Radioactive Material" w Dispenser 1 N/A N/A N/A N/A 24 Tags, " Radioactive Material" 100 N/A N/A N/A N/A 25 Kraft Paper 36" Width, Roll 1 N/A N/A N/A N/A' 26 Stretcher 1 N/A N/A N/A N/A 27 Blankets 2 N/A N/A N/A N/A i8- Plastic Sheet 24" Width, Roll I N/A N/A N/A N/A 29 !!erculite, Roll 1 N/A N/A N/A N/A 3U- Duct Tape Roll 2 N/A N/A N/A ~5[A INVENTORY BY DATE REVIEWED BY :4TE _ .
SPF 69.0_62.0_1 _7 _ ._ _ siiEET _3 or._4
$1A s 1/14/82
- .01 Re
;r: i i. I .' , /
EMERGENCY CPERATIONS CENTER INVENTORY NOMINAL QUANTITY ID RECAL OPER i. i s ' NO. FOUND NUMBER DATE SPECIAL IN$fRUCTIONS Cl;K Ni ACTION TAhth EQUIPMENT QUANTITY i il Batteries For Instruments Long Life N/A N/A N/A N/4
,. "D" Cell N/A N/A Check with Batterv Tester b "C" Cell N/A N/A Check with Battery Tester i "B" Cell N/A N/A Check with Battery Tester
,1 "A" Cell N/A N/A Check with Battery Tester i "AA" Cell N/A N/A Check with Battery Tester 32 Eberline R0-2A 2 33 RM-14 W/HP-270 1 34 TCS Air Sampler 1 35 Caninisters for TCS 30 Air Sampler INVENTORY BY DATE 'r'!L
_ _ _ I.EVIEWED BY SPF 69.062.01-7 SitLET 4 0F 4
~
., 1/14/82
/ p 7
"i;: mix l .' . :t OPERATIONS SUPPORT CENTER INVENTORY NOMINAL QUANTITY ID kECAL EPER~ b t :k.a NO. QUANTITY FOUND hV1BER DATE SPECIAL INSTRUCTIONS CIlK So ACTioh TAM N EQUIPMENT I First And Kit 1 N/A Inventory per FAK Emerg N/A Equip Inv Sheets 2 Survey Kit 1 N/A Inventory per FAK Emerg N/A Equip Inv Sheets 3 Decontaatnation Kit 3 N/A Inventory per FAK Emerg N/A Equip Inv Sheets 4 Emergency Plan, Shoreham i N/A Updating Done in Accordance N/A with Procedure
~ '
5 Emergency Plan Implementing 2 sets N/A Updating Done in Accordance N/A' Procedures with Procedure , 6 Logbooks 2 N/A N/A N/A N/A , 1 7 Paper / Clipboards 5/5 N/A N/A N/A N/A t 8 Pens / Pencils 30/30 N/A N/A N/A -N/A 9 Forms N/A N/A N/A N/A 10a- Eberline RO-2 2 Check Battery and Test b Eberline RO-2 _ with Check Source {
. . _ . . ! I _ _ _ _ __
DATE REVIEWED BY D \l E INVENTORY BY SPF 69.062.61-8 S!!EET I 0F 6
;3A 1/13/82 O e -
;;;e
N. g' M A 1 .
~
h. v t' t . a .
, i T
nP 1 C A '
~ .
E k l T, l i j' e i s J o i,h
}II j
R A A A A A A ^A EK / / / / / / / Pl l N N N N N N OC 'N y r e t Y t a R B r 0 _ e 7 h S N _ h t t t u E O i h I w V T n S N C U o t I- R i s T t e R S A A a A A A A T Y N / / r / / / / B E I N N e N N N N & D T. h L O p t E 2 8 E A c V / I k e E 4 C- C c p I 6 1 E e s V / P h n E F 1 T S C I R 0 R 2 O_ P- T P. _ E U L A A A ~A A
/
A
/ /
A A
/
E S AE / / / N
/
N N N N N S CT N N EA S RD N O. I. T. R E A A A A A A A A A DD / / / / / / / / R. I t N N N N N N N N E U P_ _ N E O ._ Y T T A I D D TN NU AO UF Q - _. Y LT _ AI INT N 0 5 1 1 0 1 1
? A t
0 0U 1 0 0 1 NQ 5 d e t r x o o x s B o s B A s x , s r o e g e B g a s t r B n l . a a T i s L e l N F d - l P E a s p 0 M e P g m r 7 P t t a a o - 8 I a h t B S o X - U l g n l S 1 Q u i a c c F 0 E c s l b i i a i r h r t t t r t a s o s s n e 2 r e a s a a a m 6 a m l b l l l a Y P S F A P P P C B 5 Y R 9 O 6 T N E F _ _ V P . O. N _ 4 1 61 7 1 8 1 9 1 0 2 'il 2 2 N I S
o"iunix I . OPERATIONS SUPPORT CEhTER INVENTORY
~'
NOMINAL QUANTITY ID RECAL GPTR~ DI SCli t.o . EQUIPMENT QUANTITY FOUND NCIBER DATE SPECIAL li.STRUCTIONS CllX f40 ACTION TAkt.N _C _ . _ _ 23 Film For SX-70, pack 10 N/A N/A Check Expiration Date N/A 24 Protective Clothing
.. Coverall 100 N/A N/A N/A N/A I, Surgeon Caps 100 N/A N/A N/A N/A e floods 25 N/A N/A N/A N/A
'l Bootics 1000 N/A N/A N/A N/A Shoe Covers 100 N/A N/A N/A N/A f Poly Disposable Gloves 1000 1 Box 1 box N/A N/A N/A N/A g Latex Gloves 100 N/A N/A N/A N/A h Dust Masks, Disposable 100 N/A N/A N/A N/A 25 Masking Tape - 2", Roll 4 N/A N/A N/A N/A
.' 6 Radiation Signs With Inserts 4 N/A N/A N/A N/A 27 Radiation Rope, Feet 200 N/A N/A N/A N/A 28 Tape, " Radioactive Material" {
With Dispenser, roll 1 N/A N/A N/A N/A l 29 Tags, " Radioactive Material" 100 N/A N/A N/A N/A~ 60 Kraft Paper, 36" Width, Roll I "/A N/A N/A N/A , INVENTORY BY DATE EEVIEWED BY dih SPF 69.062.01-8 Sl!EET 3 OF 6 1/13/82 uia r ;-;
M TI'.N1)I.X t?.a OPERATIONS SUPPORT CENTER INVENTORY NOMINAL QUANTITY ID RECAL OPER DI rh NO. EQUIPMENT QUANTITY FOUND hutBER DATE SPECIAL INSTRUCTIONS CilK w ACTION IhlN
- 11 Stretcher 2 N/A N/A N/A N/A 12 Blankets 4 N/A N/A N/A N/A' 53~ Plastic Sheet 24" Wide, Roll I N/A N/A N/A N/A
~ ~~
54~ Herculite, Roll I N/A N/A N/A '~N/A i
.35 Duct Tape, Roll 2 N/A N/A N/A N/A '16 SCBA Pressure Demand Type -
MSA463831 4 N/A N/A Check Pressure N/A
'If Replacement Cylinder 4 N/A N/A Check Pressure N/A MSA460320 II Batterie. For Instruments -
Long Life a "D" Cell N/A N/A Check with Battery Tester j lo "C" Cell N/A N/A Check with Battery Tester c "B" Cell N/A N/A Check with Battery Tester
,1 "A" Cell N/A N/A Check with Battery Tester e "AA" Cell N/A N/A Check with Battery Tester
'19I TLD 100 N/A N/A Check Anneal Date N/A l
~
40~~ TLD Reader 1 Check Op with 115 VAC INVENTORY BY DATE REVIEWED BY _ M I E __ _ . _ _ _ _ _ SPF 69.062.01-8 . s SbEET4_0F6_ 1/13/82 d*
, y
it'i'!N)IX I ? .o
._ _ OPERATIONS SUPPORT CENTER IhTENT0_RY NOMINAL QUANTITY ID RECAL OPfli ! tm c h FOUND NLMBER DATE SPECIAL IWS7RUCT10NS CitK r." ACTitd TAKLN NO. EQUIPttENT QUANTITY 41 Direct Re: ding Dosimeters
.a 0-200 mH 100 N/A Check Do Not Record Calibration N/A Only Dates of DRDS le 0-lR 100 N/A Check Do Not Record Calibration N/A Only Dates of DRDs e 0-5R 20 N/A Check Do Not Record Calibration N/A Only Dates of DRDs
,1 0-20R 10 N/A Check Do Not Record Calibration N/A Only Dates of DRDs !
4'2I DRD Charger 2 N/A Install Battery and Check Operation 42b DRD Charger N/A 1 Check Battery ~~~ f
- l 1 Check Battery ;
1 Test with Check Source 1 Test with Check Source
~
Check Battery. Transmit l 45 7 Two Way Radio, tulz 10 N/A 45b Two Way Radio, MHz _ N/A and Receive INVENTORY BY DATE ' REVIEWED BY ___
!ME _. . _ _ _ . .
SPF 69.062.01-8 SilEET 5 0F p 1/14/82 $1'
' ' ' ~.01 'e l>
. : m i '- I OPERATIONS SUPPORT CENTER INVENTORY NOMINAL QUANTITY ID RECAL Ol=Ek til:0 No. EQUIPMENT QUANTITY FOUND NUMBER DATE SPECIAL INSTRUCTIONS Cl!K N1 ACTION TAkth 46 Air Purifying Full Face Respirator With Particulate and Iodine Cartridges MSA 45711 6 N/A N/A Check Emp Date of Iodine N/A Cartridges 41 Replacement Cartridges MSASS182 6 N/A N/A Check Exp Date h/A 58 Bullhorn 1 N/A N/A Check Op with Batteries 4I Tool Kit 1 N/A N/A N/A N/A ,
50 Radiological Health liandbook 1 N/A N/A N/A ~h/5 "
~
. SI Harnesses and Rope i N/A N/A N/A N/A
*All TLDs must be replaced at the sasic time i
l r I
+ !
i i t INVENTORY BY DATE REVIEbED BY iLIE __ _ _ _ . SPF 69.062.01-8 sutET 6 cF 6
- 1/13/82 il Rt' . B PP
A!'" .NDIX 12.') FIRST AID ROOM INVENTORY
~ ~ ~ ~ ' '
NOMINAL QUANTITY ID RECAL ll'E'N ' lit:;nt ' No. EQUIPMENT QUANTITY FOUND NUMBER DATE SPECIAL ICSTRUCTIONS CllK .w ACTIO.N T A k t.N la First Aid Kit 3 N/A Inventory Per FAK N/A I t. First Aid Kit - N/A Emerg Equip Inv Sheets N/A Ic First Aid Kit - N/A N/A t i l f i
! I f
l
.._ .i ._ .__
INVENTORY BY DATE REVIEWED BY .O.E SPF 69.062.01-9 sutET 1 of I
- . 1/13/82 iM
'I Re v . ;)
Pa;
s Ji:NDIX 1'.Ii CEYrRAL SUFFOLK HOSPITAL INVENTORY
~~~ ~~~
NOMINAL QUANfITY ID REDAL ' OPER' l li t.h N l NUMBER DATE SPECIAL INSTRUCTIONS CitK Na l ACTION T REN
- 90. EQUIPMENT QUANTITY FOUND l 1 Decontamination Kit I N/A Inventory Per DK Emerg Equip N/A Inv Sheets 2 Logbook I N/A N/A N/A N/A I ~
' ~ ~ ~
Paper / Clipboards 5/2 N/A N/A N/A N/A ! 3
~~ ~' ~~
10/10 N/A N/A N/A ~N'/A~~ > 4 Pens / Pencils Eberline RO-2 1 Check Battery and Test with j 5 ' Check Source E Eb.RM14/HP210/Sil-4 i Check Batter and Test with -" ! ! 1 I Check Source 7- RADECO Air Sampler 1 Check Operation with 12 V i Power Source , 3 I 8 Par *iculate Filters, box 1 N/A N/A N/A N/A f
~~ ~~
9-Silver Zeolite Filters N/A N/A Check Expiration Date 'N/A
'~
I 10 Smears 100 N/A N/A N/A N/A ' l il Flashlight 2 N/A N/A Check Operation with Battery N/A , _ _ . . . . I - -- 12__ Absorbant Pads, case 1 N/A N/A N/A N/A IdTE INVENTORY BY DATE _ REVIEWED BY SPF 69.062.01-11 sittET I of 5 iM
. 1/13/82
( " .61 I;cv . 1 .
"ENDIX 12.1)
CEhTRAL SUFFOLK HOSPITAL INVENTORY
' ~ '
N0t11NAL QiTA3'TITY ID RE' CAL 6Etik' ! l! V\
'm '
t,0. EQUIPMENT QUANTITY FOUND NL2tBER DATE SPECIAL INSTkUCTIONS C11K ACT16N 1AshN 1[ Plastic Bags, Large, box 1 N/A N/A N/A N/A i 14 Plastic Sample Bags, Assorted 100 N/A N/A N/A N/A 15 Camera, SX-70 I N/A N/A Inspect and Test. Shutter 16 .'ilm For SX-70, pack 2 N/A N/A Check Expiration Date N/A II Protective Clothing Coveralls 25 N/A N/A N/A N/A l i
. Lab Coats 50 N/A ' N/A N/A N/A ^
Surgeon Caps 100 N/A N/A N/A N/A , 1 Iloods 25 N/A N/A N/A N/A Booties 25 N/A N/A N/A N/A , t Shoe Covers 25 N/A N/A N/A N/A
!; Poly Disposable Gloves '
1000/bou ! N/A N/A N/A N/A la Surgeon Gloves 100 N/A N/A N/A N/% i Surgeon Masks 25 N/A N/A N/A N/A Dust Masks, Disposable 25 N/A N/A N/A N/A 18 Masking Tape 2", roll 2 N/A N/A N/A N/A 19 Radiation Signs with Inserts 6 N/A N/A N/A N/I~
~ ~ ~ ~ '
jo 7 Radiatton Hope, feet 200 N/A N/A N/A N/A ) l __{ ..l t _ _ _ . INVENTORY BY DATE REVIEED BY liilE SPF 69.062.01-11 StirET 2 or 5 1/13/82 53 G e .
;g;
"iT3!)l > l'!!
9 CENTRAL SUFFOLK HOSPITAL INVENTORY W INAL QUANTITY ID HECAL 014.N , l. . ' !- FOUND NUMBER DATE SPECIAL INSTRUCTIONS Cl!K ? >> ACTION 4 /. r.I '. No. EQUIPMENT .JUANTITY __ w+w- +=ramumime w = ZI Tape, " Radioactive Material" w Dispenser, roll I N/A N/A N/A N/A 22 Tags, " Radioactive Material" 100 N/A N/A N/A N/A j fl Kraft Paper 36" Width, 8 N/A N/A N/A N/A l roll ', s
. I 24 Stretcher i N/A N/A N/A N/A 25~ Blankets 2 N/A N/A N/A N/A 26 Plastic Sheet 24" Width, 1 N/A N/A N/A N/A roll 27 licrculite, Roll i N/A N/A N/A N/A
~
5~~ Lead Contanner,liigh Activity Specimen . N/A N/A N/A N/A f ,
~
29' ~ Movable Protectiv7 S!Ic~llt. Wsth Adjustable 4 Inch Thick i i Viewing Window I N/A N/A N/A N/A
' ~
10~~ ~ Decontamination Tatsle Top f With Splash Guards, Stretcher, liose, raucet, and Plastic Water Recepticle I N/A N/A N/A N/A , _ _ _ t i DATE HEVIEVED BY 'lE
=
INW.NTONY BY SPF 69.062.01-11 StiaT 3 or s
! ~.
1/14/82 .'. * * 'N -
~ _.
~ _.
~
N e l 1 n. t 2 1 o ' iT '
~
X C . A _
~
L I _ E L 1
'I ~
I ll H C S u I h . D -
',jt! i tl ll ! i .
R A E. 5
/ /
_A
/
A EK / / N .N N Ph - N E ~ _ OC n o i t a k rr r c ee Y b e t t R i h C ss ee O l a TT T S C d S N n yy O e D a rr E I R ee V T C t a D y t t N I U D d r e t t aa N l r t BB T A A a o t Y L S A / e c a hh B N / / A I N N N n n R
= B n o
t t i D 2 T A l i wwi E 8 I L A t l t W E
/
4 o aa kk P I k c N e t r cc I s 1 S C e t se ee V / O E oa np hh E F 1 P h R o H S DD IO CC _C 4 K L O F F U S L AE CT EA RD A
/
N A
/
N A
/
N
/
A N k cy el h n CO
/
A N AA
//
NN T E E u s e L A R R E A A A A A\
/l TS DB I M
/
N
/
N
/
N
/
N liN E U N C E T Y A T D I D TN NU AO UF Q Y I .T AI NT
!. N 2 0 0 i A 1 D YU SQ I
_ 1 1 s e _ r . u s s d r t e e n c t e e e m r u P m r i y s t c o s n D n e g b l l g I T r o n r - N r o 1 E e i d r F 1 t E m , a e g se - i l s e e r 1 - U l g p RR a ef ll J Q a n a M ii l l E t i T t h rL ee . i c0 C e CC 2 t e0 t g p 6 s c D r2 D t n ' " Y o u L i - R ao 'O C B 0
! T D _T D0 D BL " "
O Y 9 R 6 _ O T _. N F _ E P o . 1
~2 _
) ~ _* ~h 4 5 7
~8
.l e V
h t S - 3 1 1 s 1 3 i 1 1 . N
=
P
~ - _
~
1N t r e
' ' b
\ u.
I l iM ,e l. i l
~ CT _
R c N ~ A _ . E _ E l l'
\
l A i [ ;{ . !!, !t6h . i Ht I y . !lj I :i i X . t K : l' l OC - rr Y e. ee
. t t R sss O eee S TTT T N N O yyy E I T
rr r eee V C t t t N U R t t t a a a I T BBB S Y L N hhh B A I t t t D 2 T L iii www E s I A W / P I C kkk cc c E I } 3 1 S E eee V / O P hhh E r 1 H S CCc R o g e K T L E O L AAA t F AE /// u F CT NNN s U EA S RD L A R R E AAA DB TN I M U
///
NNN E N C E Y T T A I D D TN NU AO t F Q
.YT ,
IAI NT N
!oUA t
t NQ T b h E 1 M 1 P I l - U ll l 1 Q l l e 0 E eeC CC "A 2 "B "A A Y 6 e
" " " B 0 Y
k 9 o 6 T h _ E F
. V P .
o.t _ e I. . N I S
_7 . 'e ri ^ ,- APPENDIX 12.12 INVENTORY FORM INSTRUCTIONS O 1. NO. Sequential number of item - pre printed. Assign number for all items added to inventory list by hand.
- 2. EQUIPMENT Name or description of equipment pre printed.
- 3. NOMINAL QUANTITY Approximate 'uanber of units of item required to be stocked at this location - pre printed.
- 4. QUANTITY FOUND Enter actual number of items found at this location.
Make an entry on the " Equipment Discrepancy List", SPF69.064.01-1, if the Quant found is significantly less thsn the nom quant.
- 5. ID NUMBER If this column spaces does not contain a preprinted "N/A", enter the SNPS ID Numbct of the inventoried equipment
- 6. RECAL DATE If this column space does not contain a preprinted "N/A", enter the recalibration date of the inventoried equipment.
If the date has been passed remove the equipment from service, return it to the calibration facility, and make an entry on the
" Equipment Discrepancy List".
- 7. SPECIAL INSTRUCTIONS :nstructions how to perform the operational check or inspection pre printed.
O 8. OPER CHECK Enter "P" for passed or "F" for failed. entry on the " Equipment Discrepancy List". If "F" make an
- 9. DISCR NO If there is any visible evidence of damage make an entry in the " Equipment Discrepancy List". In this case, or if another discrepancy has been recorded, enter the discrepancy number in this space.
~
- 10. ACTION TAKEN Record action taken if applicable.
,, '1_;
SP 69.062.01 Rev. o
/ / Page 38 O
-- + - ,_q ,
--A--- ma -a. -,u. ,- i-,-_ - >----,L-a u A,_,- -- -w--- - - A-a.'-; & a -_ ,_a _ __
O THIS SECTI0tl IllTEllTI0t! ALLY LEFT BLAtlK FOR FUTURE EXPAtlSION. 4 O O
A n. -
$ Submitted:
Approved: (Plant Manager) O
~
DRAFT PR - y g-SP Number _ 69.d7d.61 Revision gB Date Eff. TPC TPC TPC RE-ENTRY O 1.0 PURPOSE This procedure provides guidance and instruction concerning re-entry to 'an area (s) in which the magnitude of radiological conditions is either uncertain
- or unknown during emergency operations.
Normal access control methods and standard safety precautions should be observed, in lieu of this procedure, for re-entry to areas for which the habitability of the area is not in question, or has otherwise been determined to be safe. 2.0 RESPONSIBILITY _ j The Daergency Director (ED) and/or the Radiation Prerection ?!anager is reapon-sible for insuring the proper implementation of this procedure. MAR 19 ~ '
/. , ..%
~'., ,
PPF 1021.600-6.421
- - - . . . ~
=>'.
,3. 0 DISCUSSION 3.1 Re-entry to an affected area during emergency operations may be made s
for such purposes as life saving, search and rescue, equipment operations, damage control, and survey of plant equipment status and radiological conditions. 3.2 Since emergency incidents may create radiological and industrial hazards, not commonly encountered during normal operations, only the Emergency Director, with the concurrence of the Radiation Protection Manager (RPM) if readily available', shall authorize re-entry to an area for which the habitability is unknown. 3.3 Radiation exposures during re-entry operations shall be maintained as low as reasonably achievable consistent with the urgency and necessity of the operations being performed. Emergency radiation exposure limits i may be established in accordance with SP 69.050.01, Radiation Dose,s During an Emergency, if necessary. 3.4 mmbef presee - To the extentjoysg}ble the ut'i-11zat-lon of personnel performing re-entries should be EANimIzM. For example, radiation monitor personnel may be called upon to assist with the re-entry operation to reduce the number of persons involved. Also, monitoring could be performed concurrent with the re-entry rather than as a separate activity. 4.0 PRECAUTIONS - 4.1 Re-entry teams shall be comprised of a nininum of two individuals. These individuals shall remain in visual / voice contact with each other ' at all times when in the affected area. 4.2 If the ventilation to the area has been isolated, and/or if there is
~
reason to believe that the air within the area is toxic or there is - . is an oxygen deficiency, appropriate scif-contained breathing apparatus 1 shall be used. In this case, in addition to the two man entry team,
- . one or more additional individuals shall be' assigned to remain outside of the affected area, in appropriate protective clothing and wearing SCBAs on standby, ready to enter the area to af fect rescue if needed.
4.3 Non-metallic life-lines should be used in areas containing heavy smoke, or in areas where visual contact cannot be maintained with the re-entry i team. 4.4 Protective clothing should be chosen on th? basin of the nuspected conditions, or if a reasonable projection cannot be made, the protective clothing affording the highest protection should be worn. 4.5 Survey Instruments should be continuously monitored and personnel dosimeters read neriodically while in the affected area to ensure detection of unapected localized areas of hi;;her radiation levels. SP 69.070.61 P.ev. A p / / Page 2 V c
._--.- ,, - - - .m., - -,m T- g- 9 ----.3,m-y ..
v
.: L. ,
5.0 PREREQUISITES ! 5.1 Re-entry personnel should be issued appropriate additional dosinetry (eg: high range dosimeters, alarning dosimeters, etc) to supplement l the normal TLD and self-reading dosimeter. 6.0 LDtITATIONS AND ACTIONS 6.1 Personnel radiation exposures shall be maintained, as low as reasonably achievable, within normal Shoreham administrative limits, except as provided in SP 69.050.01, Radiatic. Doses During an Emergencv. 7.0 MATERIALS OR TEST EQUIPMENT The following equipment' may be required as directed by the Energency Director / - Radiation Protection Manager: 7.1 Appropriate radiological protective clothing 7.2 Appropriate protective clothing for other hazards (fire gear, electrician gloves, etc) 7.3 Appropriate respirators 7.4 High range scif-reading pocket dosimeters
~
7.5 Additional TLD badges 7.6 Valkie-talkies O 7.7 Appropriate high range survey instruments 7.8 Contamination swipes 7.9 Air sampler and sample media - 7.10 Personal lapel air samplers and/or personal alarming dosineters (or chirpers) 7.11 Damage control equipment 7.12 First aid kit 7.13 Life-lines 7.14 Flashlights J) 7.15 Equipment necessary to perform re-entry operation (tcols, etc) S.O PNCEt!nRC This procedure is divided into two parts, each of which nay be perforned independently or in sequence. The first is re-entry to an affected area e within plant buildings. The second is re-entry to the evacuated site fro t n remote location. SP 69.076.61 Rev. A
/ / Page 3
8.1 R2-entry to Arxes Within Pinnt Buildings 8.1.1 The Emergency Director / Radiation Protection Manager should
- utilize all pertinent data availabic, including that from area radiation monitors, process instrumentation, adjacent area
('s)
'- survey data, observations made by evacuated personnel, and any other available source to deternine:
.1 Extent and location of affected area; 2 The conditions (hazarls,' temperature, air quality, etc) in the area;
.3' If any personnel are trapped or disabled in the area;
.4 If it is practical to reduce the potential hazards to re-entry personnel (ventilating, stopping equipment, etc);
.5 Determine which route to take. to the repair / operation location to minimize radiation exposure;
.6 Determine if Potassium Iodido administration is required in accordance with SP 69.G50.01 Thyroid Blocking; and
.7 If re-entry can be deferred without affecting plant safety to allow for, radioactive decay.
8.1.2 Form an appropriate re-entry team (s). The Radiation Protection 73 Manager should be called upon to organize and direct re-entry surveys. The re-entry team should be briefed prior to commencing () re-entry. Topics should include specific assignments, the number of people the work requires, what tools, spare parts, and equipment are needed, expected or projected' hazards and radiological conditions, applicable dose limits, equipment and' protective clothing to be used, and other similar topics. The Radiological Protection Manager should also:
.1 Determine each team members allowable dose and calculate the stay time for each; and
.2 Arrange, in advance, for any anticipated reliefs needed for re-entry teams.
8.1.3 At the direction of the Emergency Director or the Radiation Protection Manager, obtain appropriate equipment nnd don appropriate protective clothing and respirators. Typical re-entry equipment is identified in section 7.0 of this procedure. 8.1.4 As appropriate to 'the radiological conditions, and/or the re-entry teau assigunent the following shouH be perforned by re-entry team members:
.1 Prior to entering the area, turn on and check operation of the survey instrument.
SP 69.070.01 Rev. A
/ / Page 4
.1 NOTE: If at any time during the re-entry, the survey instrument appears to be malfunctioning, immediately retreat to a
,- safe area. Be especially suspicious of survey instrument
) readings lower than expected. Most CM survey instru-
> ments will read "0" or a lov value if the detector is saturated by extremely high radiation levels.
.2 Approach the affected area, continuously monitoring dose rates.
h'OTE: When using an instrument with a telescopic probe, remain alert to the dose rate where you are standing, in addition to the dose rate where the detector is located.
.3 Continuously apprise the Technical Support Center of the progress of the re-entry team, conditions observed and dose rates.
.4 Re-entry team members shall check their cocket dosimeters -
periodically and report the results to the Technical Support Center. The frequency of these checks should be consistent with the observed dose rate.
.5 If at any time during re-entry, the observed dose rates exceed 100 mrem /hr (or another pre-deternined level) or if the exposure of any team member exceeds 3 ren or other specified maximum allowable dose, the entire re-entry
- team shall retreat to a safe area, notify the Technical
[) s_ - . Support Center, and standby for further instructions.
.6 Perform appropriate surveys and obtain air samples as directed by the Radiation Protecticn Manager or the Emergency Director. If possible, perform this survey -
concurrent with other re-entry team activities, in order to minimize stay time.
.7 Perform appropriate inspections, repairs, and/or equipment operations, as directed.
.8 Perform appropriate rescue and first aid functions if trapped or disabled personnel are discovered in the area in accordance with SP 69.040.01, Personnel Injury, and SP 69.030.01, Search and Rescue, as necessary.
.9 At the completica of the assigned functions, 1 cave the affected area and return to the Health Physics checkpoint removing protective clothing and frisking for contamination as directed by Health Physics personnel.
8.1.5 Notify the Technical Support Center when clear of the affected area, and brief the Emergency Director on the conditions observed and any other data obtained during the re-entry. O tj
\
SP 69.070.01 Rev. A
/ / Page 5
~
.r A. . e
, 8.2 Re-aatry to the Site This section of the procedure assumes personnel have evacuated the site /~N and have assembled at one of the offsite assembly areas, or at the remote k,) Emergency Operations Facility (EOF), and that the EOF is staffed and operational. Control of re-entry team personnel will be performed by EOF staff.
8.2.1 Form an appropriate re-entry team (s). The senior LILCO supervisor at the assembly. area or at the EOF should organize and brief the re-entry team. If possible, at Icast one member of the re-entry team should be from the IIcalth Physics section. 8.2.2 Re-entry team personnel should obtain necessary equipment and don appropriate protective clothing. In particular, obtain a walkie-talkie that can be used for communications with the EOF and/or the Technical Support Center. Emergency kits containing typical re-entry equipment are located at the Emergency Operations Facility. . N0fE: Protective clothing and respirators should not ba worn in public areas, unless absolutely warranted, to prevent undue public concern. This is especially inportant if evacuation of public areas surrounding the site have not been implemented. 8.2.3 Obtain a vehicle for transportation to the site. If possible, use a LILCO vehicle, otherwise use a personal automobile. S Note gas tank level. If the level is less than 1/2, usa another d , vehicle. 8.2.4 If available, spread plastic sheeting on the seats and along the floor of the vehicle, and perform any other readily applied techniques to minimize contamination of the . vehicle.
. 8.2.5 As appropriate to the radiological conditions and/or re-entry team assignment, the following should be performed by re-entry team members:
.1 Prior to leaving the Emergency Operations Facility, turn on and check operation of the survey instrument and the walkie-talkie.
NOTE: If at any tine during the re-entry, the survey instrument appears to be malfunctioning, inmediately retreat to a safe area. Be especially suspicious of survey instrument readings lower than expected. Most Git survey instruments will read "0" or a low value if the detector is saturated by extreaely high radiation levels.
.2 Using the prepared vehicle, approach the site from upwind as much as possible. Continuously nonitor radiation levels by extending the instrument probe out the vehicle p window.
b SP 69.07d.01 Rev. A
/ / Page 6
- : ).
.3 Unless otherwise directed, continuously apprise the Emergency Operations Facility of the progress of the re-entry team, conditions observed, and dose rates.
sp- i
\'
.4 Re-entry team members shall check their pocket dosimeters periodically and report the results to the Emergency Operations Facility. Th'c frequency of these checks should be consistent with the observed dose rate.
, ./
.5 If at any time durinkit he re-entry, observed dose rates exceed 100 nrem/hr (or another predetermined level) or i.f the exposure of any member of the re-entry team ex,ceeds 3 rem (or other predetermined Icvel), the entire re-entry team shall retreat to a safe area, notify the Emergency Operations Facility, and standby for further instructions.
.6 Perform assigned surveys in accordance with SP 69.020.01, Downwind Surveys. Document all survey results.
.7 At the site boundary, enter the site and perform additional surveys as directed.
.8 If instructed to re-enter the plant, approach the guard-house, continuously monitoring dose rate.- Upon entering the guardhouse, notify the Technical Support Center or Emergency Operations Facility of the progress and dose
,s rates observed.
i i
~'
.9 If directed further, re-enter the plant and continue na provided in section 8.1 of this procedure.
9.0 ACCEPTANCE CRITERIA n/A 10.0 FINAL CONDITION _S 10.2 Upon completion of the re-entry, team members shall report to the Radiation Protection Manager for exposure evaluation and follow-up.
'".2 When warranted, the Emergency Director should restore access to the af fected areas upon the advice of the Radiation Protection Manager and -
based upon the remtits of the re-entry surveys. The Radiat.lon Protection l Manager will determine appropriate access control measures for subsequent entry to the area for recovery operations.
11.0 REFERENCES
11.1 Shorehan Nuclear Pouer Station Emergency P.lan 12.0 APPENDICES fL wJ N/A SP 69.676.61 Rev. A
/ / Page 7
9 4 j "r j Submitted: a
';oved:
j (Plant Manager) 1 l DRAFT!PRELMNARY 2 4 H 1 J SP Number 69.070.03 y Revision A g Date Eff. p TPC TPC f TPC .
},
i I O f h TERMINATION OF THE EMERGENCY AND RECOVERY l A J 1.0 PURPOSE This procedure outlines instructions and provides guidance for terminating 5 an emergency condition at the Shoreham Nuclear Power Station and restoring 2
'i' the plant to near pre-emergency conditions.
II i, 2.0 RES PONS IBIT,ITY_ il That person charged with Overall Direction and Control (Response Manager i or Emergency Director) is responsible for insuring the proper impicmentation f of this procedure. E y., n- ,9
+3 y."O,hi O
PPF 1021.600-6.421
3.0 DISCUSSION S Activation of this procedure is not essential for emergencies minor in nature or that require little or no recovery efforts. Recovery for such emergencies may be done on an informal basis through the use of normal operating procedures. 3.1 Progression from Emergency to Termination / Recovery
/
3.1.1 Actions taken during an emergency situation can be categorized into two general phases: response and recovery. Response actions are the corrective and protective measures taken to mitigate the consequences of the event and to place the emergency under control. Recovery actions are longer-term actions taken to restore the plant, as nearly as possible, to its pre-emergency condition. 3.1.2 The extent and nature of the corrective and protective measures and the extent of recovery operations will depend on the emergency conditions at hand and the status of plant areas and equipment. In many emergency situations, the emergency condition may be resolved without significant plant damage, and thus, the plant can be restored to a normal operation mode without a definitive recovery phase and without extensive outside assistance. In the event of more extensive damage, a long-term recovery may be necessary, and the man-power and resources demand of such a long-term recovery will require the establishment of a recovery organization. 8.1.3 At the onset of an emergency condition, response actions to mitigate the consequences of the accident take precedence over recovery actions. The Emergency Director mcy initiate some limited recovery operations during the response phase. Gradually as the response effort begins to abate, recovery efforts gain more importance. Finally, a point is reached where the emergency situation has decreased to the exten. that it can be considered, for all practical purposes, to be resolved. At this point, the emergency may be declared terminated, and a recovery organization implemented if necessary. 3.1.4 If following termination, an emergency situation recurs, the Emergency Director will re-activate the onsite emergency organizations, and if necessary, reactivate or recommend the same for the offsite emergency organizations. Recovery efforts will be suspended until they are allowed to resume. 3.2 Termination Criterin
.\n emrynm condit ton can be considered resolved, and n recovery organization established (if necessary) when the following guidelines 4
have been met: () SP 69.076.03 Rev. A
/ / Page 2 1
3.2.1 Rediation icvals in all in-plant grens are stable or are d;crecoing with time. gs 3.2.2 The reactor and associated systems are considered to be in a g ) safe, stable condition. 3.2.3 Any fire, flooding, earthquake, or similar initiating events are under control or have ceased. 3.2.4 Releases of radioactive material to the environment are under control or have ceased. 7 3.2.5 For contaminated / injured personnel, when the victim (*s) has been transferred to a hospital, or has received appropriate medical treatment. 3.2.6 For emergency conditions classified as Unusual Events, when.the specified corrective action has been taken or when the plant has been placed in the appropriate operating mode (LCO-related EALs), and when notifications are complete. 3.3 Authority 3.3.1 That person charged with overall direction and control (Response Manager or Emergency Director) will make the determination of when an emergency, condition is resolved, in accordance with the above criteria, and may declare the termination of the emergency. s 3.3.2 Upon declaring the termination of the emergency, that person () charged with Overall Direction and Control shall assume or appoint the position of Recovery Manager. The Recovery Manager shall review and approve the adoption of a recovery organization if such is needed. The position and the authority of Recovery Manager may later be transfered to another qualified personnel as applicabic. 3.3.3 For any emergency condition involving plant systems and/or a plant shutdown, the Recovery Manager will make a determination as to when it is safe to return the plant to a normal operating mode. LILCO _(licensing) will resolve any license or technical specification concerns related to the emergency. 3.4 Recovery organization l Although the planning for recovery and the extent of the recovery efforts j will vary according to the nature of the specific emergency situation, a long-term recovery organization is defined in Section 9 of the SNPS Emergency Plan. 3.5 Ryp;e'_rn_Oppytt,tp,TI i
- 3.5.1 Recovery activities not covered by existing approved procedures
- shall be pre-planned and approved by the Review of Operations
! Committee prior to their implementation. O
- l. -- SP 69.d76.63 Rev. A
/ / Page 3 l
F 3.5.2 Plant recovery activities shall be in accordance.with the SNPS Technical Specifications and other license. conditions. Specifically, during recovery operations, the radiation-( exposure limits of 10CFR20 shall apply. Como11ance with these limits shall be the responsibility of the Recovery Manager via the Radiation Protection Managet. 3.5.3 Recovery actions that plan for or may result in radioactivity
. releases will be evaluated ,by the Recovery Manager and his staff as far in advance oCT t he event as is possible. Such events and data pertaining to the release will be reported to the appropriate offsite emergency response organizations and agencies, even if the release is within normal technical specifications, for as long as the recovery operation continues.
3.5.4 The recovery operation will continue until the plant is returned to its pre-emergency status. 4.0 PRECAUTIONS N/A 5.0 PREREQUISITES 5.1 The energency has been declassified in accordance with SNPS Emergency Plan Implementing Procedures and 5.2 Any of the following conditions exist: 5.2.1 Extensive or significant plant damages are known to have occurred. 5.2.2 Repair, decontamination, or radwaste disposal work is expected to be sizable and long-term (e.g. , beyond three weeks)..
- 5. 2.1 Re-licensing process is foreseen.
8.2.4 Advisory and technical support from outside sources (e.g., GE,'S&W, NRC) is anticipated to te long-term. 8.2.5 Deficiencies in operational or safety related procedures or equipment are revealed in the course of the -emergency. 6.0 LIMITATIONS N/A 7.0 MATERIALS OR TEST EqHII" TENT As required. SP 69.676.63 Rev. A
/ / Page 4
8.0 PROOF.0URE 8.1 The decision to relax protective measures shall be reached in and by
, ) a meeting between the Emergency Director and, if applicable, the Response Manager. They shall base their decision upon input from their advisors.
Federal, State, and local entitles shall be notified of the decision and any resulting changes to the emergency organizations with the formation of a recovery organizaticn. The command center for recovery operations shall be located at the highest level emergency response facility (i.e., EOF, TSC, etc.). However,4he Recovery Manager, once assuming responsibility, may relocate the command center after proper consideration of operational needs when conditions permit; or he may divide the functions needed between the Station and Support Corporate Headquarters. NOTE: SNPS personnel should be informed that the emergency has been terminated and recovery operations are underway, if applicable. 8.2 The Emergency Communication Director should be notified to make a press release (via the LILCO Public Affairs Dept.) on the termination of the emergency (and the start of recovery effort). 8.3 Any emergency radiation exposure limits shall be terminated and normal radiation control measures re-established except as specified in SP 69.070.01 Re-Entry and/or SP 69.080.01 Search _and Rescue. 8.4 Any procedural waivers instituted during the emergency should be terminated, or formally documented by procedure changes. (l 8.5 Emergency organization personnel should be directed to assemble all documents generated during the emergency and submit them to the Communications Coordinator. The Communications Coordinator shall keep chronological records of events and decisions using the Recovery Operations Log (Appendix 12.3) . 8.6 Any emergency equipment used during the emergency shall be serviced, as necessary, and returned to designated storage locations. Any damaged or defective equipment shall be brought to the attention of individuals responsible for its naintenance. These actions shall be documented. 8.7 If a long-term recovery operation is indicated, a recovery organization will be established in accordance with the SNPS Emergency Plan. 8.8 For Alert and higher emergency conditions, the Emergency Director, with the assistance of the Technical Support Center staff will prepare a report of the emergency and submit this report to the Review of Operations Committee. For Unusual Events, the Licensee Event Report (LER) satisfies this requirement. Appendix 12.1 provides a suggested format. 8.0 The Re f e' of 09 erat ions Committ ee, 'mder the ausMces of the Recovery
?lanager will review the Energency Director's report and will evaluate and assign responsibilities for corrective actions.
(N/ ) SP 69.070.63 Rev. A
/ / Page 5
8.10 The Review of Operations Committee, under the auspices of the Recovery Manager, shall review / approve procedures for plant recovery that include h v as applicable: 8.10.1 Procedures for decontamination 8.10.2 Procedures for repair 8.10.3 Recommendations for specia3' inspections and tests that must be performed to assure the integrity of the plant and adequacy of the repairs. 8.10.4 Radioactive waste processing and handling procedures 8.10.5 An estimate of the radiation exposure that will be accumulated by personnel in executing these procedures. 8.10.6 Exposure reduction methods (ALARA) to minimize the projected exposure of personnel. 8.10.7 The Emergency Planning Coordinator should review the various reports on the emergency to identify deficiencies in the Emergency Plan and implementing procedures, if any, and should initiate appropriate corrective action, if necessary, in a timely manner. - 8.11 If the emergency involved radiological hazards in the plant, consider the following: (V) 8.11.1 Extensive surveys of affected plant areas should be performed. This should include direct radiation, contamination and airborne levels. The Radiological Protection Manager shall, if conditions warrant, develop an updated plant radiological status map.' This status map may be used in conjunction with SP 69.979.61
. . * 'l
~ ~~'
Reentry and/or SP 69.089.91_ Search and Rescue. 8.11.2 Posting, decontamination and shielding efforts should be initiated when hazardous and contaminated areas are identified. Posting should restrict access to hazardous areas. Decontamination should begin in least contaminated areas and progress toward most highly contaminated areas. Man-rem benefit of installing shielding should be considered. 8.11.3 Radiation exposure should be maintained as low as reasonably achievable during recovery operations. 8.11.4 Assessment of plant operations effect on decontamination or other efforts should be considered. Plant Operations may result in elevatml radiat ion level s or increased airborne and surface contamination.
/D
( ,) SP 69.070.63 Rev. A
/ / Page 6
8.11.5 Any parsonnal who used (mergency self-contained breathing apptratus for radiological protection or was potentially exposed to airborne radioactivity should undergo bioassay analysis, f)N (, 8.11.6 Personnel exposure assessment should be performed. Individual total man-rem, internal and external exposure should be considered. 8.11.7 Information gathered by reentry, rescue, damage assessment and repair teams may be useful for assessing radiological conditions and planning aJpropriate recovery operations. 8.12 If the emergency involved offsite release of radioactive effluents, consider the following: 8.12.1 Increased environmental monitoring should be performed. Increased monitoring should provide a means to assess the envi-ronmental inpact of the release. SP 69.024.01, Environmental Sample Collection During an Emergency, gives guidance. 8.12.2 The site and environs should be surveyed for contamination, airborne and direct radiation levels. Any areas with levels above normal background should be decontaminated. 8.12.3 Equipment, vehicles, buildings and other structures that may have been in the effluent plume should be surveyed for contam-ination. If contamination is found, these areas should be decontaminated. () 8.12.4 New York State Department of Health may request assistance from LILCO. LILCO personnel should be available for assistance in radiological matters. 8.12.5 It is unlikely that a member of the public would be exposed. to substantial amounts of airborne contamination, but if this might have occurred, bioassay analysis and/or dose estimation should be considered. 8.13 If the emergency involved damage to plant systems, consider the following: 8.13.1 Damage assessment of plant systems should be performed. A list of damaged systems should be developed. Estimates of 2 manpower requirements and man-rem exposure for repairs should be included to ascertain the total effort necessary. Meetings, where applicable, shall be convened to determine plant conditions and damages, and detailed recovery objectives. 8.13.2 Exposure control nethods such as temporary shielding should be med for repair ef forts if ran-ren benefits result. 8.13.3 Procedures may already be developed for testing and startup of systems but these should be reviewed for possible variances
- from a nornal startup.
D SP 69.076.93 Rev. A
/ / Page 7
8.13.4 If extensive damage was sustained, or prolonged shutdown is anticipated, projected repair and startup schedules should be
/~'N developed.
b Njgji: Startup of damaged systems after repair or rework may require USNRC approval. 8.14 Additional Considerations are:
~
8.14.1 Flooding: Flood barricade 5 should be returned to storage as the situation allows 8.14.2 High Winds: Damage to buildings and structures should be assessed. 8.14.3 Fire: Fire fighting equipment should be maintained and returned to storage. 9.0 ACCEPTANCE CRITERIA 9.1 The Recovery Manager's review shall include, but not be limited to, i the following before terminating the recovery phase: 9.1.1 Plant conditions; 9.1.2 Offsite radiological conditions; s 9.1.3 Onsite and/or offsite long-term radiological monitoring requirement; 9.1.4 Recovery program objectives (accomplished as applicable); 9.1.5 Licensing status; 9.1.6 Radwaste handling, storage; 9.1.7 Legal and insurance; 9.1.8 Other corporate and public concerns; and 9.1.9 Satisfactory conditions onsite and offsite. > 9.2 All participating Company groups and organizations shall conduct I applicable reviews. 9.3 Close-out of emergency is with concurrence of NRC. 9.4 Necessary LER and other reports have been filed in accordance to anali M le em;ul a t ionn . 9.5 Notification to onsite and offsite personnel and agencies that recovery operations are terminated, by use of the Follow-up Notification Fact Sheet, Appendix to SP 69.009.01 Notifications, has been carried out. f- s i SP 69.070.03 Rev. A
// Page 8 4
-- - ,, -. , - - - --n n ,.,- ,
._ _ _=. . _ _ _ _ _ _ . _ . _ _ - . _ . .____.. -_ . _ . ._.-. - _ _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ . _ . _ ,
. f 1 - !
t 10.0 FINAL CONDITIONS 10.1 The station has been returned to a pre-energency condition. j 11.0 ' REFERENCES _ ! 1 11.1 Shoreham Nuclear Power Station Emergency Plan i i 11.2 'SNPS 69.xxx.xx series Emergency Plan Implementing Procedures 12.0 APPENDICES i 12.1 Suggested Report Format i l i i i l i ! t I i -l 4 i . r t' L I i i . t F i i l i P l 1 f i l h s 1 i i i SP 69.67@.$3 Rev. A , i / / Page 9 J l .t i 1 i . 4
~
e
-,e -,w__ , ' ' ,,.,.4....,.m.-._,,r. -
, _ , m_%.._, _ _ ,.,,_ _ , . . , _ ___.._,,__.,,,n.,,. _
_ , , ....--.m..,..,, , , , _ , ,...m_.., _m_,,r., . . ..y.3,,
. f .: ! ) I j-APPEtIDIX 12.1 ]
l 1 1 i i I SUCCESTED EMERCENCY REPORT FORMAT
- 1. Description of the. emergency conditions (causes, pertinent events, etc.)
- 2. Plant radiblogical survey data j 3. Site and environs radiological survey
- 4. Environmental monitoring, and projected impact
'5. Damage assessment; plant /public
- 6. Radiation exposure data (plant and general public) l
- 7. Personnel injurico 1
1
- 8. Plant operating e shutdown conditions a
j Emergency Organizat.lon operation critique
- 10. Corrective actions; start-up and repair schedules F
l f 3 h 1 1 f I l-i
- l SP 69.676.63 Rev. A
/ / Page 10 i
l l .
. , - - - - , - . , - - . , . . . . . . - - - - , , , _ , . - - - - . - - , ~ , , , -. . , - . , - , , - , - - - - - - . - - - - .-..,-,-,-,-r--
h APPENDIX 12.2 INVEtTTORY FORM INSTRUCTIONS O
- 1. NO. Sequential number of item - pre printed. Assign number for all items added to inventory list by hand.
- 2. EQUIPMENT Name or description of, equipment - pre printed.-
- 3. NOMINAL QUANTITY Approximate number of units of item required to be stocked at this location - pre printed.
- 4. QUANTITY FOUND Enter actual number of items found at this location.
Make an entry on the " Equipment Discrepancy List", SPF69.064.01-1, if the Quant found is significantly less than the nom quant.
- 5. ID NUMBER If this column spaces does not contain a preprinted "N/A", enter the SNPS ID Number of the inventoried equipment
- 6. RECAL DATE If this column space does not contain a preprinted "N/A", enter the recalibration date of the inventoried equipment.
If the date has been passed remove the equipment from service, return it to the calibration facility, and make an entry on the
" Equipment Discrepancy List".
- 7. SPECIAL INSTRUCTIONS Instructions how to perform the operational check or inspection pre printed.
- 8. OPER CHECK Enter "P" for passed or "F" for failed. If "F" make an entry on the " Equipment Discrepancy List". -
- 9. DISCR NO If there is any visible evidence of damage make an entry in the " Equipment Discrepancy List". In this case, or if anoi.her discrepancy has been recorded, enter the discrepancy nmnber in this
. space.
- 10. ACTION TAKEN Record action taken if applicable.
R 64.070.M Rev. A
/ / Page 11 O
_ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . m._ .
APPENDIX 12.'l 4 SNPS - RECOVERY OPERATIONS IX)G 1 Logger ._ Page of Date/ Time: / Event:
- Action / Decision by: AuthIrizedby: Remarks F
J ^ ' Logger / Date/ Time: Event: - _ Action / Decision by: Authorized by: Remarks i 4 Logger / l Date/ Time: Event: Action / Decision by: Authorized by: - Remarks l-
- Logger _ /
Date/ Time: Event: l Action / Decision by: Authorized by: Remarks 3 SP 69.676.63 Rev. A i / / Page 12 J
..-m-+ , . . - . . . . . .s . - . , w. _,.m., ,.~. ___m-. , _ , v-.,_-- - ,y--y ,, ,v,- --- , -v, . , ,-- -,.,
...y,.
"Submittzdr SP Numbsr 69.686.01 Approved: Revision: B (Plant Manager)
O Date Eff: ) SEARCH AND RESCUE 1.0 CONDITIONS This procedure provides instructions and guidance for locating missing individuals and for the rescue and treatment of individuals once they have been located. 2.0 IMMEDIATE ACTIONS 2.1 When an Individual's T.ocation is Known or has been Reported 2.1.1 Control Roon Operator, announce the following over the page-party system three times at one-ninute intervals.
" Emergency Rescue Team menbers report to (location). (Name of Emergency Rescue I,cader) contact the Control Room (or TSC).
2.1.2 Perform section 2.3 of this procedure. 2.2 .When an Individual's Iocation is not Known 2.2.1 As soon as it is recognized that one or more individuals are missing, the Plant Technician Manager or designee shall attempt to determine the individuals location by performing the following:
.1 Page the individual over the public address system.
.2 Contact the individual's supervisor and co-workers to determine his last known work location.
2.2.2 If ef forts fail to locate the missing individual (s), the Tiant Technical Manager shall contact the Control Room or TSC and provide the following information:
.1 Nane(s) of individual (s)
.2 Summary of efforts performed to locate the individual (s)
.1 1.ast kncun location of the individual (s) ,
p l n* W o su N ' , #
~
Y' . .
. 2.2.3 Upon receipt of a report of a missing person (s), Control Room Operator, announce the following over the page-party system
[-s \ three times at one-minute intervals.
" Attention, all plant personnel. The following individual (s)
(name of individual (s)) is missing within the plant. Personnel knowing the whereabouts of the individual (s) contact the Control Room. 2.3 Emergency Rescue Team 2.3.1 At the emergency kit location, Emergency Rescue Team Leader, contact the Control Room and be briefed on the situation. 2.3.2 " Rescue Team Leader, ensure that the rescue team is equipped with the following (if applicable).
.1 Low range self reading dosimeter (0-200mR)
.2 Medium range self reading dosimeter (0-5R)
.3 Iligh range self reading dosimeter-(0-200R)
.4 Personal TLD capable of recording doses in excess of 100R
.5 Protective clothing
/ .6 Respiratory protection equipment b) 2.3.3 Radiation Protection Manager or designee, determine if potassium iodide administration is necessary in accordance with SP && cs/.0/
" Thyroid Blocking" and advise Emergency Rescue Team members to take the tablet.
2.3.4 Radiation Protection Manager or designee, obtain approval from the Emergency Director for team members to obtain doses from 3 rem to 75 rem. Refer to SP 69.050.01, " Radiation Doses during an Emergency". 2.3.5 Emergency Rescue Team Leader, maintain communications with the Radiation Protection Manager during nearch and rescue operations by the use of walkie talkies. 2.3.6 Emergency Rescue Team Leader, ensure the team is equipped with-the following.
.1 liigh range survey equinment (if applicable)
. :' Fire.t-aid hit 2.3.7 Emergency Rescue Team, proceed to the last known location of the individual (s) and if necessary, expand the scarch to adjacent areas.
O(h SP 60 d86.61 Rev. B
, / Page 2
i .,. 2.3.8 Emergency Rescue Team Leader, inform the Radiation Protection Manager or designee of any significant actions. 2.3.9 Emergency Rescue Team members keep within sight or voice range of each other unless directed otherwise by the Radiation Protec-tion Manager or designee. 2.3.10 Emergency Rescue Team Leader, inform the Radiation Protection Manager immediately upon locating any personnel. 2.3.11 Emergency Rescue Team, provide First Aid in accordance with SP 69.040.01 " Personnel Injurf'and transport or escort the individual to a safe location as soon as possible. 2.3.12 Radiation Protection Manager, recall the Emergency Rescue Team when search and rescue operations are no longer necessary as determined by the highest ranking official onsite or when all missing persons are accounted for. 3.0 SUBSEQUENT ACTIONS 3.1 Energency Rescue Tean personnel, report to the Radiation Protection Manager for follow-up. 4.0 FINAL CONDITIONS _ All missing individuals have been accounted for. 5.0 DISCUSSION 5.1 If an individual is trapped or disabled in a high radiation area, the rescue must be performed as expediously as possible to minimize the dose to the victim and the doses to the rescue personnel and to ensure that first aid can be provided as soon as possible. 5.1.1 In an emergency situation, each individual in the rescue team and first aid personnel may receive an exposure of 75 rem if necessary to save a life. Refer to SP 69.050.01 Radiation Doses During an Emergency. 5.1.2 If the situation is not one of life or death but requires action to minimize the further excessive exposure of the victims, rescue personnel may be allcwed to receive doses up to 12 rem. Refer to SP 69.056.01, " Radiation Doses During an Emergency". 5.1.3 If the situation is other than that described in Step 5.1.1 and/or 5.1.2, normal Shorehan Nuclear Power Station Administrative erliat ion enosure quidem M regulatory exposure linits anniv. 5.1.4 Rescue of a victim shall take precedence over fire-fighting efforts unless the fire nust be suppressed to effect rescue
-'s or if the fire poses an innodiate threat to the lives of others.
SP 69.680.01 Rev. B
/ / Page 3
.* - t o.
5.1.5 Rescue of a victim shall take precedence over isolation of high energy fluids (Steam, hot water under pressure, hydraulic fluids, etc.) unless isolation of the system is necessary to effect rescue or if failure to isolate the system will seriously affect reactor safety or will place.the lives of other personnel in immediate danger. 6.0 APPENDICES S' N/A P I E i 4 i i l . -
< P 6 9. 0 3',1,01 Rev, n l
/ / Page 4 l
-e.-y,,yy - ,-v,<-+----- ---.y -.,-w..- , - ..-.,_--._--,w., - - - . - - - - - - - - - ~ - - - -
...s,, -.4---4, ,--e - ,L--u- .4_ . - __.___.-w a -u- -- 4 -_ _-. 2-, -mma C - -- am ._. _ _
F l . O THIS SECTI0tl IllTEllTI0ilALLY LEFT BLAllK FOR FUTURE EXPMISI0tl. O O
. Submitted: - -
Approved: (Plant Manager) O
< DRAFT PRELMNARY SP Number 69.696.61 '
Revision - A' N Date Eff. TPC TPC
~
TPC
^
UtMGEWQ/ DOCUMENTATION AND RECORD KEEPING DURING AN EMERENCY-- O . 1.0 PURPOSE This procedure provides the method for maintaining a complete and accuraie record of a declared emergency. 1 2.0 RESPONSIBILITY i The maintenance of logs and records onsite and offsite during an emergency I shall be the responsibility of the Administrative Supervisor (TSC), and the Records Supervisor (EOF), respectively. A summary shall be prepared by the j Health Physics Engineer af ter the termination of the energency. e i I i
\q \hll. l W W3
,/ g // .
/ y ryy/ ..
PPP 1d21.660-6.421 \ -/'
- - - , -n- . - , , , - _ - - , - , , . - , , - - - - .. n - - . - - ,. - - , -- - - -- - . , . ,a -,r,n .,,,-.,..,,,,,,-.,-----w. ,,,, ,, ,,,,
, _ . w
~
3.*0 _DISCUSSI_0N 3.1 Emergency Function Lons [~') Emergency Function Logs shall be maintained for all emergency classifications
\s_/ (i .e., Unusual Event, Alert, Site Area Emergency and General Energency)-
by all functions that are activated. During a declared emergency, personnel performing emergency response organization functions as listed in paragraph 12.3 shall maintain logs while responsible for an emergency, response function. The Emergency Function Log Form, SPF 69.090.61-1, shall be used for logging pertinent data while Appendix 3 is a list of potential itens that may be included in the Emergency' Function Log. 3.2 Communication Record Keeping Form During a declared emergency all incoming and outgoing communications shall be recorded by the person responsible for that message. Communications Record Keeping Form, SPF 69.090.61-2, a 3 copy color coordinated form shall he used for recording all communications as well as any renarks as applicable. - 3.3 Emergency Summary At the termination of a de,clared emergency the Health Phycies Engineer shall prepare an Emergency Summary. This summary report shall be a chronological compilation of all logs and records that were prepared during the emergency. p 3.4 Other Records Essential portions of the records for an event vill.be generated under existing operational procedures and other Emergency Plan Impicmenting Procedures. A list of anticipated records is included as "Other Emergency Records," Appendix 5, which may be included in the Emergency Summary. 4'. 0 PRECAUTIONS n/A 5.O PREREQUISITES N/A 6.0 T.TMITATIONS AND ACTIONS
- a. ,
N/A 7.0 }!AT_Eltl ALS AND/Olt EQUl P lEN"F 7.1 Emergency Function Logs [ 7.2 Communication Record Keeping Forms 7.3 Accurate Clock or Synchronized watches SP 69.090.61 Rev. A
/ / Page 2
~
r- .+ 3 , VE r 8.0 PROCEDURE i 8.1 Energency Function Logs G ' ,
' The logger shall initiate the log by:
T 8.1.1 Using Sk'P_ '69.696.61-1, enter the appropriate title.
~
Emergency I'd Function Logs shall be filled out for each position given in g Section 12.3. 8.1.2 Enter name of the person filling out the log. 8[1.3 Enher date, time (24 hour clock), and location.
.i 8.k.4 Enter page number for all pages.
8.1.5 Enter chronologically those events pertinent to the function,
,' ; as recommended in Appendix 3. Emphasis should be placed on all decisions and recommendations.
8.1.6 If additional pages are needed, enter title usin;; SPF 69.096.61-1, pg 2.
'I 8.1.7 At the termination of the event, submit the completed onsite Ibgs,to the Administrative Supervisor (TSC) and offsite' logs toi the -Records Supervisor (EOF) .
8
,.2 Communication Record Keeping Forn O
'%)
'[ The commurifcator shall initiate the form by:
- 8. 2. lt Using SPF 69.696.61-2, circle RECEIVED or TRANSMITTED.
8.2.2 Enter time (use 24 hour clock time). , 8.2.3 Enter the date in month day and year.
', 8.2.4 Circle the location From which the message was transmitted.
8.2.5 Circle the location A which the message uas transmitted. 4 8.2.6 Enter the nessage as accurately and completely as possible. If not totally cicar on message have it repeated. , 8.2.7 Af ter cennuntention in to-f r.ated, enter any re.- arks as applicable. 8.2.8 The conmunicator shal? si- th e form once it is completed. 8.2.9 The White Copy shs! . n? 3 over to the Energency Director / 4 Renponw '!anager a' the i., ' or EOF for info:7. tion routin,t and recon! heepin,;, depeading on 4tc*.her it is an 2, site or offsite
,\' communication.
k k { / SP 69.096.61 Rev. A 7 7.l ; y
/ / Pa;;e 3
.(
s
?
r
- 8.2.10 The Canary copy shall be sent to Addressee.
8.2.11 The Pink copy shall be kept in the communications file. () 8.2.12 The Emergency Director / Response Manager shall turn over all forms to the Health Physics Engineer for inclusion in the Emergency Summary at the end of the emergency. 8.3 Emergency Summary. The Health Physics Engineer shall:0 8.3.1 Obtain the Emergency Function Logs and Communication Record Keeping Forms from the Administrative Supervisor, the Records Supervisor, and the Emergency Director / Response Manager. 8.3.2 Obtain the records and documents called out in Appendix 5. 8.3.3 Review all records, documents and logs for completeness. 8.3.4 Compile all items in chronological order on the Emergency Function Log Form,SPF 69.096.61-1 page 1 and 2.
.1 Do not paraphrase if direct quotation is feasibic.
.2 For redundant entries select the one that most cuncisely describes the item.
.3 Enter source of the item, i.e., the docmaent or log on
( .) which the item appeared originally.
.4 If multiple sources reference the same item with conflicting details, enter the items verbatin from- differing sources.
8.3.5 The complete Emergency Summary will be reviewed and signed by the Plant Manager. 9.0 ACCEPTANCE CRITERIA N/A 10.0 FINAL CONDITIONS All logs, records, and documents shall be forwarded to the Administrative Section for f LIN; in accord,nce eith permnent pl mt procedures.
11.0 REFERENCES
11.1 Shotchan Nuclear Power Station, Emergency Plan, May 1981 11.2 Emergency Plan Implementing Procedures 12.0 APPENDICES
/~'N
() , 12.1 Emergency Function Log Form, first page, SPF 69.696.61-1 SP 69.d96.61 Rev. A ,
/ / Page 4
~ ^
' - ' - - ' ~~ --
12.2 Emergency Function Logs 12.3 Items that may be Included in Emergency Function I,og 12.4 Communication Record Keeping Fom, SPF 69.096.61-2 12.5 Other Energency Records ;
./
l SP 69.090.01 nev. A
/ / Parc 5
D o APPENDIX 12.1
* *
- Paga 1 cf 2 TITLE CF LGL
/ / :
(NITIATED OT DATE ((ng (C;AfgCN}}