ML20010H054: Difference between revisions
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, t C ~ | , t C ~ | ||
. call, and: | . call, and: | ||
P- -(A) Describe the Emergency conditions to him. | P- -(A) Describe the Emergency conditions to him. | ||
:- (B) Direct.him to initiate the call out of additional operations shif t,'if required (by alert, site or | :- (B) Direct.him to initiate the call out of additional operations shif t,'if required (by alert, site or General Emergency) or if deemed necessary by the | ||
General Emergency) or if deemed necessary by the | |||
. Emergency Director. | . Emergency Director. | ||
L | L | ||
| Line 188: | Line 185: | ||
b b' | b b' | ||
I i | I i | ||
3 4~ | 3 4~ | ||
i a | i a | ||
| Line 206: | Line 202: | ||
l l | l l | ||
1 i EPIP 1 10 ATPOSPERIC STABILITY CLASS A $"I1 , ,og 9... _ _ _ _ | 1 i EPIP 1 10 ATPOSPERIC STABILITY CLASS A $"I1 , ,og 9... _ _ _ _ | ||
8... M5UFEUIU-7... gj 5... - | 8... M5UFEUIU-7... gj 5... - | ||
| Line 242: | Line 237: | ||
$ 1 i, .n,n , | $ 1 i, .n,n , | ||
a ' ' | a ' ' | ||
:/ , | :/ , | ||
veLU N !C P_.WMO | veLU N !C P_.WMO | ||
| Line 305: | Line 299: | ||
--- w -- | --- w -- | ||
4 e, - g __ | 4 e, - g __ | ||
3_5 - t | 3_5 - t | ||
-= | -= | ||
| Line 431: | Line 424: | ||
si 6-M - | si 6-M - | ||
g 5- .__.--------------.a, . - - - - . .. - - . . - - - - - - | g 5- .__.--------------.a, . - - - - . .. - - . . - - - - - - | ||
=- =_e == s;t- | =- =_e == s;t-y .__.____p.-- | ||
y .__.____p.-- | |||
2 = | 2 = | ||
4 - | 4 - | ||
| Line 504: | Line 495: | ||
- s. | - s. | ||
: 2) er to - | : 2) er to - | ||
9 -- | 9 -- | ||
10 =s | 10 =s | ||
| Line 559: | Line 549: | ||
}[, ._i._ _ _ _ - . - - . _ _ | }[, ._i._ _ _ _ - . - - . _ _ | ||
Ie i i . i iei i e/Iit itieie 4 a t e i i i eit i It il i 9-- L--- | Ie i i . i iei i e/Iit itieie 4 a t e i i i eit i It il i 9-- L--- | ||
._ . _ . - - ~.=-.---T | ._ . _ . - - ~.=-.---T | ||
: g. ._--_ | : g. ._--_ | ||
| Line 689: | Line 678: | ||
.-w f j M r y 3 N [h y f | .-w f j M r y 3 N [h y f | ||
--= | --= | ||
a a a . | a a a . | ||
a f | a f | ||
| Line 806: | Line 794: | ||
4 g | 4 g | ||
' -- 2 1 | ' -- 2 1 | ||
:: Ei .8;?$3 , % | :: Ei .8;?$3 , % | ||
: ' __ 3) ,s - | : ' __ 3) ,s - | ||
6 < | 6 < | ||
? g 6 | ? g 6 | ||
.5 | .5 g 70 -- | ||
g 70 -- | |||
4 .2 | 4 .2 | ||
=.g | =.g | ||
| Line 821: | Line 806: | ||
* l -2.09 | * l -2.09 | ||
( tost 600 AT mY otsimcE (stEs) wne=setw, cnits nw nnum x 7.63 x 1(T'8 x(e.LEs)-2.m 3 | ( tost 600 AT mY otsimcE (stEs) wne=setw, cnits nw nnum x 7.63 x 1(T'8 x(e.LEs)-2.m 3 | ||
4 4 . e O | 4 4 . e O 1 | ||
l l | |||
2 | |||
*M EPIP 1 , | *M EPIP 1 , | ||
| Line 1,009: | Line 993: | ||
C 3._- | C 3._- | ||
T1 L EC I i 1.TL_ w CwK ~ .~.; .I Am I u u"-' F-"" m R I .9. . | T1 L EC I i 1.TL_ w CwK ~ .~.; .I Am I u u"-' F-"" m R I .9. . | ||
2... 1 | 2... 1 i 6 i l i #- | ||
i 6 i l i #- | |||
! #' i | ! #' i | ||
, y + . | , y + . | ||
| Line 1,153: | Line 1,135: | ||
_3 | _3 | ||
= x n -- | = x n -- | ||
' 8 1 _ | ' 8 1 _ | ||
m 8 - | m 8 - | ||
| Line 1,284: | Line 1,265: | ||
:o .. | :o .. | ||
.. _ _u -- .. | .. _ _u -- .. | ||
2 -:: | 2 -:: | ||
_ to to 3 2 zo ._ - ,, .. | _ to to 3 2 zo ._ - ,, .. | ||
| Line 1,291: | Line 1,271: | ||
.. l5 . | .. l5 . | ||
4 .. | 4 .. | ||
f 5 | f 5 | ||
_ 3. :: z= __ leeg4 g /.w 3 .- ~ | _ 3. :: z= __ leeg4 g /.w 3 .- ~ | ||
| Line 1,397: | Line 1,376: | ||
;Q 10_. '_''_''.'/.'.'.-..'.'._'_'_'._'.'_,_'..'.'._'.,'._7_ | ;Q 10_. '_''_''.'/.'.'.-..'.'._'_'_'._'.'_,_'..'.'._'.,'._7_ | ||
,=-_.-_'_'.__'__ | ,=-_.-_'_'.__'__ | ||
_.-___'''_'''''_'_'ii''._'i'_''.-.'_'___- | _.-___'''_'''''_'_'ii''._'i'_''.-.'_'___- | ||
y, 9_ .- - | y, 9_ .- - | ||
| Line 1,417: | Line 1,395: | ||
L 7 I I 2- "/ ' | L 7 I I 2- "/ ' | ||
1 - | 1 - | ||
(. . | (. . | ||
g i . | g i . | ||
| Line 1,511: | Line 1,488: | ||
.+. .2 .2 g __ | .+. .2 .2 g __ | ||
i | i | ||
-+- 2 h 70 | -+- 2 h 70 | ||
! -- .1 1 | ! -- .1 1 | ||
| Line 1,562: | Line 1,538: | ||
-''-s h l 07 | -''-s h l 07 | ||
, - 1 , | , - 1 , | ||
$f ' | $f ' | ||
~l , , - | ~l , , - | ||
| Line 1,600: | Line 1,575: | ||
.I . | .I . | ||
I . I i i g , | I . I i i g , | ||
, , . . .i . , , , , . , , ,.,. , i , , , ,, . , . | , , . . .i . , , , , . , , ,.,. , i , , , ,, . , . | ||
,ii. ie i i .j i .4 ii . . . . . . ... ..,, ,...j,, . | ,ii. ie i i .j i .4 ii . . . . . . ... ..,, ,...j,, . | ||
| Line 1,631: | Line 1,605: | ||
_ .- 4 m ,,, | _ .- 4 m ,,, | ||
) - -- | ) - -- | ||
_ z. -- - | _ z. -- - | ||
ii 5 3o 3 | ii 5 3o 3 | ||
| Line 1,657: | Line 1,630: | ||
2 . | 2 . | ||
j 3o - -- __ | j 3o - -- __ | ||
- -- a : | - -- a : | ||
7- -. | 7- -. | ||
| Line 1,692: | Line 1,664: | ||
s== | s== | ||
g,,, | g,,, | ||
_ :=-_-_-.=_< .__ . ._-:x===. a- ===mSIP/==nm g _-yr ruRTEF:Pyf. ---- - -- . --- __- - - - - - - - - __ _ | _ :=-_-_-.=_< .__ . ._-:x===. a- ===mSIP/==nm g _-yr ruRTEF:Pyf. ---- - -- . --- __- - - - - - - - - __ _ | ||
7... - | 7... - | ||
| Line 1,718: | Line 1,689: | ||
scc.<'... . | scc.<'... . | ||
.,.~.~.~~_~~X~^.^^~'^ ~_'L^~~~ C '*?. ^_ T : 7 | .,.~.~.~~_~~X~^.^^~'^ ~_'L^~~~ C '*?. ^_ T : 7 | ||
<+'' ' - .. | <+'' ' - .. | ||
' ~ | ' ~ | ||
| Line 1,918: | Line 1,888: | ||
8- - -- | 8- - -- | ||
7 ., | 7 ., | ||
6 l, | 6 l, | ||
5= | 5= | ||
| Line 1,939: | Line 1,908: | ||
. . . - - _ . g- -- .- ._. - _55 =---=.-=s73_-.------..--------- | . . . - - _ . g- -- .- ._. - _55 =---=.-=s73_-.------..--------- | ||
El 8- Z------- - - - 7 , | El 8- Z------- - - - 7 , | ||
8* 7 ' | 8* 7 ' | ||
~ | ~ | ||
| Line 2,109: | Line 2,077: | ||
4 _ _ . . _ ___ _ | 4 _ _ . . _ ___ _ | ||
: 3. - | : 3. - | ||
: 2. , | : 2. , | ||
/ 1 l I t 1 3 | / 1 l I t 1 3 | ||
| Line 2,158: | Line 2,125: | ||
, 33 :" 6 = _w j *~=: - ;- 7 2 e | , 33 :" 6 = _w j *~=: - ;- 7 2 e | ||
. 2"n e-d s"o - =_ | . 2"n e-d s"o - =_ | ||
5 -~i: | 5 -~i: | ||
}_ - | }_ - | ||
| Line 2,273: | Line 2,239: | ||
.I 1 s i 1 w -r f M g I I | .I 1 s i 1 w -r f M g I I | ||
. - . .j r | . - . .j r | ||
YA I '/- | YA I '/- | ||
* g /. . E i .,. . .f i . . . . . | * g /. . E i .,. . .f i . . . . . | ||
| Line 2,285: | Line 2,250: | ||
. = _ - . . - - - | . = _ - . . - - - | ||
e 8. " - - - - - - - - | e 8. " - - - - - - - - | ||
'- DIERGENCY ALERT 7-x' 8.4 23 6. , | '- DIERGENCY ALERT 7-x' 8.4 23 6. , | ||
W g 5- _ _ _ . . _ _ _ _ _ , _ _ ''_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ | W g 5- _ _ _ . . _ _ _ _ _ , _ _ ''_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ | ||
| Line 2,334: | Line 2,298: | ||
3 - | 3 - | ||
3 30 7-- | 3 30 7-- | ||
o :: la | o :: la g" . .- | ||
g" . .- | |||
6 3- - | 6 3- - | ||
a 50 O 5 | a 50 O 5 | ||
| Line 2,412: | Line 2,374: | ||
.i i Q i . .. .. . . . . . 6 . f i . l | .i i Q i . .. .. . . . . . 6 . f i . l | ||
.,.4 , | .,.4 , | ||
30 e i i i e i i e i I e i e e t t t | 30 e i i i e i i e i I e i e e t t t | ||
* fs t 6 e t i i . I i e i I a VEPd. .[~E C-R Cf 6 i i r i ii e i , i . e to v .. | * fs t 6 e t i i . I i e i I a VEPd. .[~E C-R Cf 6 i i r i ii e i , i . e to v .. | ||
| Line 2,491: | Line 2,452: | ||
sterwy aAss G unE m Evanat SIE RUDRt nuas ' | sterwy aAss G unE m Evanat SIE RUDRt nuas ' | ||
g GENERAL SITE KDI)DCSE E8 a REM E n u 1 R m * -- W . | g GENERAL SITE KDI)DCSE E8 a REM E n u 1 R m * -- W . | ||
'3 W -'* | '3 W -'* | ||
goog *_ i 1- .= --=EE- | goog *_ i 1- .= --=EE- | ||
| Line 2,533: | Line 2,493: | ||
g lo - -to | g lo - -to | ||
= | = | ||
=. s .. | =. s .. | ||
M. = .a-a 4 i | M. = .a-a 4 i | ||
| Line 2,562: | Line 2,521: | ||
.os .os w ,, | .os .os w ,, | ||
jo .ou .os __ | jo .ou .os __ | ||
l | l | ||
_ m p | _ m p | ||
| Line 2,579: | Line 2,537: | ||
MX 2 , | MX 2 , | ||
s I . | s I . | ||
l EMERGENCY CLASSIFICATION AND ORGANIZATION FORFATION, NOTIFICATION AND COMMUNICATIONS APPENDIX 2 l | l EMERGENCY CLASSIFICATION AND ORGANIZATION FORFATION, NOTIFICATION AND COMMUNICATIONS APPENDIX 2 l INITIATING CONDITIONS | ||
INITIATING CONDITIONS | |||
. O. | . O. | ||
tI 4< | tI 4< | ||
| Line 2,634: | Line 2,590: | ||
Spec. limits. | Spec. limits. | ||
: b. Unit is in other than a normal condition during. - ' | : b. Unit is in other than a normal condition during. - ' | ||
operation and the abnormal condition is of such | operation and the abnormal condition is of such a nature as to warrant notification. For. | ||
a nature as to warrant notification. For. | |||
} | } | ||
example, cracking is found in primary system piping during operation. | example, cracking is found in primary system piping during operation. | ||
| Line 2,705: | Line 2,659: | ||
'/"), | '/"), | ||
q,, [)/ . (v ., | q,, [)/ . (v ., | ||
.- M Y d" | .- M Y d" | ||
~sM | ~sM | ||
| Line 2,782: | Line 2,735: | ||
* 0.1 mR/hr, above background, .or | * 0.1 mR/hr, above background, .or | ||
: c. The Process Vent High Range Monitor reads greater than - | : c. The Process Vent High Range Monitor reads greater than - | ||
1.3 x 10" mR/hr, and | 1.3 x 10" mR/hr, and i d. Reports from monitoring teams indicate these doses are present at the site boundary. | ||
i d. Reports from monitoring teams indicate these doses are present at the site boundary. | |||
.12. Imminent loss of control All Conditions Shif t Supervisor, judgment, based on the advice of the' Security _ | .12. Imminent loss of control All Conditions Shif t Supervisor, judgment, based on the advice of the' Security _ | ||
of the physical security Shift Supervisor, of the station. | of the physical security Shift Supervisor, of the station. | ||
| Line 2,870: | Line 2,821: | ||
1 i i | 1 i i | ||
+~ | +~ | ||
i Y | i Y | ||
i - | i - | ||
j :- | j :- | ||
| Line 2,880: | Line 2,829: | ||
; h _ | ; h _ | ||
[ | [ | ||
h 1 | h 1 | ||
i. | i. | ||
| Line 2,916: | Line 2,864: | ||
f' , | f' , | ||
l EPIP-1 APX 4 PAGE 2 of 3 | l EPIP-1 APX 4 PAGE 2 of 3 NOTIFICATION OF EMERGENCY RESPONSE PERSONNEL 1.0 FURPOSE The purpose of this appendix is to implement the actions required to notify the personnel deemed 3 | ||
NOTIFICATION OF EMERGENCY RESPONSE PERSONNEL 1.0 FURPOSE The purpose of this appendix is to implement the actions required to notify the personnel deemed 3 | |||
necessary to assist in the response effort,following the declaration of an energency condition. | necessary to assist in the response effort,following the declaration of an energency condition. | ||
2.0 SHIFT SUPERVISOR , | 2.0 SHIFT SUPERVISOR , | ||
| Line 2,975: | Line 2,921: | ||
, EMERGENCY I | , EMERGENCY I | ||
O-I T | O-I T | ||
i | i i | ||
4 I | |||
i 4 | i 4 | ||
l l | |||
t , | |||
LO l | LO l | ||
| Line 3,031: | Line 2,976: | ||
+ | + | ||
4 I | 4 I | ||
LO | LO I | ||
e | |||
.~.... m c . | .~.... m c . | ||
I'. | I'. | ||
| Line 3,073: | Line 3,017: | ||
: HEALTH PHYSICS AREA FONITORING PERSONNEL | : HEALTH PHYSICS AREA FONITORING PERSONNEL | ||
~ Health Physics NOTE: The first Health Physicist or Assistant Health Physics Supervisor reporting to the Health Physics Area shall assume supervisory responsibility for the monitoring teams.until relieved by an individual appointed by the Emergency Director, Other stction personnel shall report to their normal assembly area and await further instructions. The first supervisor to | ~ Health Physics NOTE: The first Health Physicist or Assistant Health Physics Supervisor reporting to the Health Physics Area shall assume supervisory responsibility for the monitoring teams.until relieved by an individual appointed by the Emergency Director, Other stction personnel shall report to their normal assembly area and await further instructions. The first supervisor to | ||
' . report to each of these areas shall assume supervisory respon- | ' . report to each of these areas shall assume supervisory respon-sibility until relieved by a more senior supervisor as directed by the Emergency Director. | ||
sibility until relieved by a more senior supervisor as directed by the Emergency Director. | |||
f s | f s | ||
4 | 4 | ||
| Line 3,187: | Line 3,128: | ||
3.0 3.2 averaged over 24 hours would exceed 500 times unrestricted MPC's'. | 3.0 3.2 averaged over 24 hours would exceed 500 times unrestricted MPC's'. | ||
3.3 10CFR20.405 Thirty day report - see 10CFR20 for details. | 3.3 10CFR20.405 Thirty day report - see 10CFR20 for details. | ||
a 4.0 . Minimum Information on Release Report | a 4.0 . Minimum Information on Release Report 4.1 The following data should be included in any report submitted to the NRC concerning the unplanned or uncontrolled release of 4 . radioactive material. | ||
4.1 The following data should be included in any report submitted to the NRC concerning the unplanned or uncontrolled release of 4 . radioactive material. | |||
: 1. A list of the nuclides released, indicating their MPC's (unrestricted arra) and the curier released for each. | : 1. A list of the nuclides released, indicating their MPC's (unrestricted arra) and the curier released for each. | ||
: 2. The amount of dilution medium available, either air or water. | : 2. The amount of dilution medium available, either air or water. | ||
| Line 3,225: | Line 3,164: | ||
Second Gust QQO. ,'140 s. 21_0 [ D h'';+jh] !l (Pt.B) i ,5llihllllllp'! I' : . , | Second Gust QQO. ,'140 s. 21_0 [ D h'';+jh] !l (Pt.B) i ,5llihllllllp'! I' : . , | ||
+ | + | ||
Second Gust Pt.A to Pt.B l ! ! | Second Gust Pt.A to Pt.B l ! ! | ||
(Pt.A) j o. | (Pt.A) j o. | ||
| Line 3,256: | Line 3,194: | ||
39 d .I ,300; k'lf * * | 39 d .I ,300; k'lf * * | ||
* 60' -J i l120 w y d gy)40..y)J.1 .;. M 1 iii.WUlllEl Ii | * 60' -J i l120 w y d gy)40..y)J.1 .;. M 1 iii.WUlllEl Ii | ||
- l | - l | ||
' i - | ' i - | ||
| Line 3,338: | Line 3,275: | ||
: %};~ | : %};~ | ||
UNPLANNED OR UNCONTROLLED RELEASE OF ^ RADIOACTIVE MATERIAL | UNPLANNED OR UNCONTROLLED RELEASE OF ^ RADIOACTIVE MATERIAL | ||
, 4 | , 4 APPENIDX 3 . , | ||
APPENIDX 3 . , | |||
i i | i i | ||
e | e | ||
; BLANK FORMS EPIP 2.1 t | ; BLANK FORMS EPIP 2.1 t | ||
i b . REPORT ON INFORMATION SOUGilT BY EMERGENCY COORDINATOR OR DIRECTOR 1 | i b . REPORT ON INFORMATION SOUGilT BY EMERGENCY COORDINATOR OR DIRECTOR 1 | ||
-i i-EO | -i i-EO I , | ||
I , | |||
1 f | 1 f | ||
I e | I e | ||
| Line 3,357: | Line 3,289: | ||
2 0 | 2 0 | ||
4 6 | 4 6 | ||
{ | { | ||
h~ | h~ | ||
| Line 3,384: | Line 3,315: | ||
EPIP-2 l 8-22-77 APX 4 1 - | EPIP-2 l 8-22-77 APX 4 1 - | ||
Page 1 of 2 UNPLANUED OR UNCONTROLLED ~ RELEASE OF RADIOACTIVE MATERIAL o | Page 1 of 2 UNPLANUED OR UNCONTROLLED ~ RELEASE OF RADIOACTIVE MATERIAL o | ||
. APPENDIX 4 1- | . APPENDIX 4 1-BLANK PORM EPIP 2.2 GASEOUS RELEASE EVALUATION 9 | ||
BLANK PORM EPIP 2.2 GASEOUS RELEASE EVALUATION 9 | |||
h. | h. | ||
I j ,. | I j ,. | ||
n II . | n II . | ||
k 3 .. | k 3 .. | ||
| Line 3,437: | Line 3,365: | ||
:O , | :O , | ||
e 3 | e 3 | ||
f- | f-s r | ||
s r | |||
5 . | 5 . | ||
4 | 4 | ||
| Line 3,534: | Line 3,460: | ||
t | t | ||
>. 8 3 | >. 8 3 | ||
4 | 4 4 > | ||
4 > | |||
d E | d E | ||
& I s | & I s | ||
| Line 3,556: | Line 3,480: | ||
4 1 | 4 1 | ||
l j | l j | ||
i-t i | i-t i | ||
m 4 | m 4 | ||
| Line 3,624: | Line 3,547: | ||
l | l | ||
\ | \ | ||
O | O i | ||
i | |||
EPIP-4 Pago 2 of 2 6-21-78 FUEL HANDLING ACCIDE'TT 1.0 Shift Supervisor Response 1.1 Notify Health Physics to initiate HP response in EPIP-4, | EPIP-4 Pago 2 of 2 6-21-78 FUEL HANDLING ACCIDE'TT 1.0 Shift Supervisor Response 1.1 Notify Health Physics to initiate HP response in EPIP-4, | ||
| Line 3,658: | Line 3,579: | ||
l.1 1.2 As soon as practical, advise Health Physics of the following items. | l.1 1.2 As soon as practical, advise Health Physics of the following items. | ||
1.2.1 Steam Generator affected 1.2.2 Personnel in Containment when Air Ejector diverted? | 1.2.1 Steam Generator affected 1.2.2 Personnel in Containment when Air Ejector diverted? | ||
YES NO GPM. | YES NO GPM. | ||
1.2.3 Blowdown rate prior to rupture Turbine Blag. Aux. Bldg. | 1.2.3 Blowdown rate prior to rupture Turbine Blag. Aux. Bldg. | ||
| Line 3,738: | Line 3,658: | ||
I l | I l | ||
VIRGINIA ELECTC AND POWER COMPANY _ ! | VIRGINIA ELECTC AND POWER COMPANY _ ! | ||
t SURRY POWfR STATION LOSS OF COOLANT ACCIDENT-1.0 Shift Supervisor Response | t SURRY POWfR STATION LOSS OF COOLANT ACCIDENT-1.0 Shift Supervisor Response 2.0 Energency Direstor Response , | ||
2.0 Energency Direstor Response , | |||
. 3' .0 Health: Physics Response | . 3' .0 Health: Physics Response | ||
. APP I. Containment Atmosphere Sampling O . | . APP I. Containment Atmosphere Sampling O . | ||
| Line 3,804: | Line 3,722: | ||
. ... ~ . , . . . . - . . . - . . - _ . - . . - . - - . . = . - . - _ - . . . --. __ --_-- __.~... . | . ... ~ . , . . . . - . . . - . . - _ . - . . - . - - . . = . - . - _ - . . . --. __ --_-- __.~... . | ||
m | m | ||
* EPIP-7 ; | * EPIP-7 ; | ||
s+ APX-I : | s+ APX-I : | ||
| Line 3,825: | Line 3,742: | ||
t POST ACCIDENT , | t POST ACCIDENT , | ||
CONTAINMENT ATMOSPHERE SAMPLING f - | CONTAINMENT ATMOSPHERE SAMPLING f - | ||
1 i- | 1 i- | ||
) | ) | ||
| Line 3,887: | Line 3,803: | ||
-1.8 Turn off vacuum pump i | -1.8 Turn off vacuum pump i | ||
Change No. 18 L-- | Change No. 18 L-- | ||
1 | 1 i; | ||
i; | |||
- , a v ,- , - ~ - .-,n,. r . . . ., .n-, --m,-,--n, - , -, | - , a v ,- , - ~ - .-,n,. r . . . ., .n-, --m,-,--n, - , -, | ||
| Line 3,930: | Line 3,844: | ||
EPIP-8 Page 1 of 5 JUN 7 1973 VIRGINIA ELECTRIC AND PoliER CO'eANY SURRY PO;JER STATION | EPIP-8 Page 1 of 5 JUN 7 1973 VIRGINIA ELECTRIC AND PoliER CO'eANY SURRY PO;JER STATION | ||
~ | ~ | ||
EVACUATION AND ACCESS CONTROL ONSITE | EVACUATION AND ACCESS CONTROL ONSITE 1.0 Onsite Evacuation 2.0 Onsite Access Control (O | ||
e O | |||
1.0 Onsite Evacuation 2.0 Onsite Access Control (O | |||
e | |||
O | |||
EPIP 8 j . | EPIP 8 j . | ||
| Line 3,980: | Line 3,890: | ||
< 1.1.2 Etcurity Building Guard (s) 1.1.2.1 Access to the Station shall be by normal security procedures. | < 1.1.2 Etcurity Building Guard (s) 1.1.2.1 Access to the Station shall be by normal security procedures. | ||
V | V | ||
e y - | e y - | ||
| Line 4,054: | Line 3,963: | ||
- j,.. . N - , . . . . | - j,.. . N - , . . . . | ||
~ .... | ~ .... | ||
., .G, ., , | ., .G, ., , | ||
.!f h,. c. ,$!ks.C'h., | .!f h,. c. ,$!ks.C'h., | ||
5 f | 5 f | ||
%' ..: jib *[',p.S}~ .. e 'h / | %' ..: jib *[',p.S}~ .. e 'h / | ||
i | i | ||
, v( 1 | , v( 1 | ||
| Line 4,075: | Line 3,982: | ||
,a . .g. - 7 , y %g. g;e:kg, . | ,a . .g. - 7 , y %g. g;e:kg, . | ||
.c... | .c... | ||
l /s ,- . , | l /s ,- . , | ||
_ . 4 .,... | _ . 4 .,... | ||
| Line 4,088: | Line 3,994: | ||
.\ | .\ | ||
. . y, | . . y, | ||
: q . y-.,6 , | : q . y-.,6 , | ||
,' s .,. r)w* I , | ,' s .,. r)w* I , | ||
| Line 4,098: | Line 4,003: | ||
.P g' gg,. ;-.,,.{}4- | .P g' gg,. ;-.,,.{}4- | ||
/ - | / - | ||
gl A ,. .- | gl A ,. .- | ||
',9 t; . . t/ -- < | ',9 t; . . t/ -- < | ||
| Line 4,139: | Line 4,043: | ||
EPIP-9 Page 1 of 9 | EPIP-9 Page 1 of 9 | ||
> NOV 211930 l | > NOV 211930 l | ||
VIRCINIA ELECTRIC AND POWER COMP __AN_Y SURRY POWER STATION | VIRCINIA ELECTRIC AND POWER COMP __AN_Y SURRY POWER STATION PERSONNEL ACCOUNTABILITY . | ||
PERSONNEL ACCOUNTABILITY . | |||
d (O 8 t | d (O 8 t | ||
i t | i t | ||
| Line 4,709: | Line 4,611: | ||
,3 we mt sw i . | ,3 we mt sw i . | ||
i e i i is v , | i e i i is v , | ||
as $ { _ k'T- ) ; - '] ''. '.-}': i. i -~ Y T | as $ { _ k'T- ) ; - '] ''. '.-}': i. i -~ Y T hmm z | ||
hmm z | |||
. ; , * . - . + - , | . ; , * . - . + - , | ||
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. m __t?-t | . m __t?-t | ||
-is _.J | -is _.J | ||
: d. ,_ 4 - . . . _ _ _ . . _ __ .t._. .- . _ _ . __ r____.-.- .. _. | : d. ,_ 4 - . . . _ _ _ . . _ __ .t._. .- . _ _ . __ r____.-.- .. _. | ||
| Line 4,739: | Line 4,638: | ||
. 4r | . 4r | ||
,_; .~_: - : | ,_; .~_: - : | ||
n. | n. | ||
w 1.,f) | w 1.,f) | ||
| Line 4,863: | Line 4,761: | ||
Q) - | Q) - | ||
Q | Q | ||
:::=.t ,--- p - + .y-~_-...+-e-_. _rg,-~.-~ r | :::=.t ,--- p - + .y-~_-...+-e-_. _rg,-~.-~ r i O I . I [ ! ] I x ,1 1 ] i g g u | ||
i O I . I [ ! ] I x ,1 1 ] i g g u | |||
1 g s I i 1 | 1 g s I i 1 | ||
: g. IC , _2c m . | : g. IC , _2c m . | ||
| Line 4,908: | Line 4,804: | ||
_ m | _ m | ||
:I RL..s.- | :I RL..s.- | ||
~ | ~ | ||
= y__. r.y mm | = y__. r.y mm | ||
| Line 5,040: | Line 4,935: | ||
10 e-- | 10 e-- | ||
m- .: . -- m m # m. | m- .: . -- m m # m. | ||
Am. | Am. | ||
~ , | ~ , | ||
| Line 5,064: | Line 4,958: | ||
6__ m _ _._ | 6__ m _ _._ | ||
a m_ | a m_ | ||
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pe ._ _n . | pe ._ _n . | ||
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| Line 5,135: | Line 5,027: | ||
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" ~~ ~ E ' Y . -_- .. | " ~~ ~ E ' Y . -_- .. | ||
| Line 5,195: | Line 5,086: | ||
" , gpgeta=e-== _ {~ =2 =n T__ | " , gpgeta=e-== _ {~ =2 =n T__ | ||
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, , , , 1 . | , , , , 1 . | ||
| Line 5,314: | Line 5,204: | ||
- . . a:. :: w. 4. y:. . | - . . a:. :: w. 4. y:. . | ||
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| Line 5,322: | Line 5,211: | ||
_3, 4 .r- " -- C. | _3, 4 .r- " -- C. | ||
g 3 .- : | g 3 .- : | ||
ed h * * | ed h * * | ||
* _m ._ _ -.e..-_. , | * _m ._ _ -.e..-_. , | ||
| Line 5,669: | Line 5,557: | ||
i- . | i- . | ||
5 4 | 5 4 | ||
i l- , | i l- , | ||
L J 'k | L J 'k | ||
| Line 5,848: | Line 5,735: | ||
i | i | ||
. 2-+,! 1 h~" | . 2-+,! 1 h~" | ||
8 c. _f. , _.g , | 8 c. _f. , _.g , | ||
e . _ _ | e . _ _ | ||
| Line 5,960: | Line 5,846: | ||
4 s,. - | 4 s,. - | ||
g i | g i | ||
) | ) | ||
!. i l | !. i l | ||
| Line 5,995: | Line 5,880: | ||
4 0 | 4 0 | ||
0 t | 0 t | ||
4 l | 4 l | ||
LO. | LO. | ||
| Line 6,002: | Line 5,886: | ||
..p - ' | ..p - ' | ||
* EPIP ' ~ | * EPIP ' ~ | ||
8-22-77 APX 2 Page 1 of'2 | 8-22-77 APX 2 Page 1 of'2 | ||
| Line 6,011: | Line 5,894: | ||
1 b' : | 1 b' : | ||
;f | ;f | ||
'' ~ | '' ~ | ||
ESTIMATING RELEASE FROM'OFFSITE DATA | ESTIMATING RELEASE FROM'OFFSITE DATA | ||
| Line 6,027: | Line 5,909: | ||
O 4 | O 4 | ||
a | a | ||
~ | ~ | ||
i' I | i' I | ||
| Line 6,065: | Line 5,946: | ||
a | a | ||
^ | ^ | ||
X = | X = | ||
__ __s X x | __ __s X x | ||
| Line 6,118: | Line 5,998: | ||
w - - | w - - | ||
EPIP-16 | EPIP-16 | ||
.Page 1 of 3-s | .Page 1 of 3-s | ||
| Line 6,175: | Line 6,054: | ||
" Part -Subject 1.0 General Monitoring' Considsrations 1 | " Part -Subject 1.0 General Monitoring' Considsrations 1 | ||
2.0 Monitorin3 of Locations not Proselected 3.0.~ Factors Controlling the Area Affected by a Release | 2.0 Monitorin3 of Locations not Proselected 3.0.~ Factors Controlling the Area Affected by a Release | ||
'1 e | '1 e | ||
J d | J d | ||
| Line 6,195: | Line 6,073: | ||
If a release results in having a large amount of heat associated with the released activity, the cloud may rise and settle in an unpredic-tchle man.1er. In such cases higher concentrations could exist at points further away from the station, and the monitoring teams should be instructed to monitor locations downwind other than preselected ones. The team should also transverse the anticipated path of the cloud more than once to minimi=o the effect of any cloud meander. | If a release results in having a large amount of heat associated with the released activity, the cloud may rise and settle in an unpredic-tchle man.1er. In such cases higher concentrations could exist at points further away from the station, and the monitoring teams should be instructed to monitor locations downwind other than preselected ones. The team should also transverse the anticipated path of the cloud more than once to minimi=o the effect of any cloud meander. | ||
F-EPIP-16 8-22-77 APX 1 Page 3 of 5 | F-EPIP-16 8-22-77 APX 1 Page 3 of 5 y | ||
12.0 Monitoring of Locations Not Preselected-Y'- The preselected locations have already had the necessary con',*ersion factors calculated based on the current atmospheric stability class. | |||
If it is necessary to mohitor.elsewhere the conversion factors will e-have to calculate which will require the actual monitoring locations be described, preferably by reference to a known landmark such as a bridge or intersection. All such monitoring must be documented. | If it is necessary to mohitor.elsewhere the conversion factors will e-have to calculate which will require the actual monitoring locations be described, preferably by reference to a known landmark such as a bridge or intersection. All such monitoring must be documented. | ||
4 e | 4 e | ||
| Line 6,235: | Line 6,112: | ||
d 8-22-77 APX 2 | d 8-22-77 APX 2 | ||
~ | ~ | ||
Page 1 of-3 | Page 1 of-3 T. | ||
T. | |||
I t .:. | I t .:. | ||
...y.gi- f + , | ...y.gi- f + , | ||
| Line 6,261: | Line 6,136: | ||
* I | * I | ||
: j. , | : j. , | ||
i. | i. | ||
f . | f . | ||
| Line 6,275: | Line 6,149: | ||
[ \ | [ \ | ||
l | l | ||
.c | .c li . | ||
li . | |||
[ .F f '. | [ .F f '. | ||
In - | In - | ||
| Line 6,347: | Line 6,219: | ||
(nE) | (nE) | ||
C 5 | C 5 | ||
,g N u ch | ,g N u ch 5" 17&618 'm M - , | ||
5" 17&618 'm M - , | |||
'ksg. - | 'ksg. - | ||
; ' 'D .:. - '3' | ; ' 'D .:. - '3' | ||
| Line 6,410: | Line 6,280: | ||
+s.,/Ml(y'.89'~ | +s.,/Ml(y'.89'~ | ||
Q, | Q, | ||
\''' l | \''' l | ||
-Qlf,if | -Qlf,if | ||
| Line 6,431: | Line 6,300: | ||
. I'4 ' I',A' m,,* at-..t . u.. . l ., yJ, 1l17,l^,/,Fw. | . I'4 ' I',A' m,,* at-..t . u.. . l ., yJ, 1l17,l^,/,Fw. | ||
r " | r " | ||
e , | e , | ||
r s.i.t , | r s.i.t , | ||
| Line 6,487: | Line 6,355: | ||
g g..: f. %g4j ., ,- | g g..: f. %g4j ., ,- | ||
7 | 7 | ||
,w i | ,w i | ||
* + | * + | ||
| Line 6,502: | Line 6,369: | ||
_..7 NI ./Ny' g , | _..7 NI ./Ny' g , | ||
,Q# l' y | ,Q# l' y M,% | ||
M,% | |||
Ne w | Ne w | ||
( | ( | ||
| Line 6,584: | Line 6,449: | ||
ONSITE AND OFFSITE RADI0 IODINE AIR SAMPLING UNDER CONDITIONS OF HIGH NOBLE GAS CONCENTRATION t | ONSITE AND OFFSITE RADI0 IODINE AIR SAMPLING UNDER CONDITIONS OF HIGH NOBLE GAS CONCENTRATION t | ||
1' 1 | 1' 1 | ||
a c | a c | ||
e . | e . | ||
| Line 6,638: | Line 6,501: | ||
1 EPIP-17 ' | 1 EPIP-17 ' | ||
~ | ~ | ||
%2y7 q Page l'of 2' i | %2y7 q Page l'of 2' i I | ||
I | |||
? | ? | ||
0FFSITE WATER AND FOODSTUFF MONITORING : | 0FFSITE WATER AND FOODSTUFF MONITORING : | ||
| Line 6,649: | Line 6,510: | ||
.I Part Subject . | .I Part Subject . | ||
1 Significance of Water and Foodstuff Monitoring . | 1 Significance of Water and Foodstuff Monitoring . | ||
Evaluation of Offsite Data | Evaluation of Offsite Data 2 | ||
O, i i | |||
I d I I | |||
d I I | |||
f l' . | f l' . | ||
t 4, | t 4, | ||
| Line 6,698: | Line 6,556: | ||
h, . * $ | h, . * $ | ||
l- , | l- , | ||
- 5 . 1 | - 5 . 1 z, '* | ||
z, '* | |||
(- i ' | (- i ' | ||
I~ , | I~ , | ||
| Line 6,711: | Line 6,567: | ||
i 4 | i 4 | ||
4 5 | 4 5 | ||
4 i | 4 i | ||
* i* | |||
i* | |||
s 8 s P | s 8 s P | ||
4 a | 4 a | ||
| Line 6,727: | Line 6,581: | ||
l- ' , | l- ' , | ||
' = | ' = | ||
_i. 4 | _i. 4 7 7 -w '_ . | ||
7 7 -w '_ . | |||
p . | p . | ||
| Line 6,784: | Line 6,635: | ||
~> - | ~> - | ||
. EPIP Pass 3 of 3 JUN 7 578 | . EPIP Pass 3 of 3 JUN 7 578 | ||
- (s' 2.0 Health Physics Response-2.1 When notified by the Emergency Director of the initiation of | - (s' 2.0 Health Physics Response-2.1 When notified by the Emergency Director of the initiation of | ||
' EPIP 18. Health Physics 'is to initiate EPIP-10, Personnel | ' EPIP 18. Health Physics 'is to initiate EPIP-10, Personnel | ||
| Line 6,793: | Line 6,643: | ||
. sufficient data to advise the Emergency Director of radio-l l | . sufficient data to advise the Emergency Director of radio-l l | ||
logical conditions. > | logical conditions. > | ||
l | l 2.5 Evaluate the applicability of Appendix 1, Emergency Exposure Significance and Evaluation, of this procedure. | ||
2.5 Evaluate the applicability of Appendix 1, Emergency Exposure Significance and Evaluation, of this procedure. | |||
s> | s> | ||
~-) | ~-) | ||
| Line 6,806: | Line 6,654: | ||
EPIP-18 APX 1 i Page 1 of 6 JUN 7 378 (7_ . . | EPIP-18 APX 1 i Page 1 of 6 JUN 7 378 (7_ . . | ||
Gy i I : | Gy i I : | ||
'EMERCENCY EXPOSURE CRITERIA | 'EMERCENCY EXPOSURE CRITERIA | ||
( | ( | ||
| Line 6,862: | Line 6,709: | ||
General Body 0.06 Hands 0.3 Shoes - Inside 0.3 Shoes - Outside 0.6 Clothing 0.25 | General Body 0.06 Hands 0.3 Shoes - Inside 0.3 Shoes - Outside 0.6 Clothing 0.25 | ||
) | ) | ||
* Measured 5 cm above the surface NRC 10CFR20 QUARTERLY LIMITS Whole Body 1.25 rem 3.00 rem if 5 (N-18) permits Hands / Feet 18.75 rem I Skin | * Measured 5 cm above the surface NRC 10CFR20 QUARTERLY LIMITS Whole Body 1.25 rem 3.00 rem if 5 (N-18) permits Hands / Feet 18.75 rem I Skin 7.5 rem Inhalation 520 x MFC for 1 hour | ||
7.5 rem Inhalation 520 x MFC for 1 hour | |||
F EPZP-18 APX 1 Page 6 of 6 JUN 7 578 | F EPZP-18 APX 1 Page 6 of 6 JUN 7 578 | ||
| Line 6,896: | Line 6,741: | ||
''' EPIP-19 s | ''' EPIP-19 s | ||
b ff$'dYII79 | b ff$'dYII79 | ||
( | ( | ||
-($ | -($ | ||
| Line 6,958: | Line 6,802: | ||
I i | I i | ||
EPIP- 19 Pzg2 4 of 6 8-22-77 ar.d acknowledged. If the public address system is lh used,.the individual announcing the alarm should inter-mittently announce " FIRE IN (Location of fire)." | EPIP- 19 Pzg2 4 of 6 8-22-77 ar.d acknowledged. If the public address system is lh used,.the individual announcing the alarm should inter-mittently announce " FIRE IN (Location of fire)." | ||
Example: Fire in #1 Turbine Building; turbine floor; | Example: Fire in #1 Turbine Building; turbine floor; 8 west side. Continue to make the announcement until it is acknowledged by a Supervisor, Operator or Engineer. | ||
8 west side. Continue to make the announcement until it is acknowledged by a Supervisor, Operator or Engineer. | |||
NOTE: Acknowledgement cannot be received if the "Page Button" is held in the transmit . | NOTE: Acknowledgement cannot be received if the "Page Button" is held in the transmit . | ||
. position. The "Page Button" must be re-released between announcements in order to hear acknowledgement. | . position. The "Page Button" must be re-released between announcements in order to hear acknowledgement. | ||
| Line 7,010: | Line 6,852: | ||
!!E'4S AND INFOR!!ATION RELEASES. l | !!E'4S AND INFOR!!ATION RELEASES. l | ||
. l I | . l I | ||
I l | I l | ||
} i i i | } i i i | ||
| Line 7,018: | Line 6,859: | ||
t l | t l | ||
!(g - | !(g - | ||
I s | I s | ||
. I i | . I i | ||
Revision as of 10:04, 17 February 2020
| ML20010H054 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/27/1981 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139B534 | List: |
| References | |
| PROC-810227-02, NUDOCS 8109230083 | |
| Download: ML20010H054 (200) | |
Text
{{#Wiki_filter:y. EMERGENCY PLAN IMPLEMENTING PROCEDURES EPIP-1 Emergeny Classification and Organization - Formation, Notification and Coursunications EPIP-2 Selected Occurrences - Unplanned or Uncontrolled Release of Radioactive Material EPIP-3 Selected Occurrences - Injuried Personnel EPIP-4 Selected Accident Actions - ?uel Handling Accident EPIP-5 Selected Accident Actions- E team Generator Tube Rupture EPIP-6 Selected Accdient Actions - Main Steam Line Rupture EPIP-7 Selected Accident Actions - LOCA EPIP-8 Evacuation and Access Contrc 1 Onsite EPIP-9 Personnel Accountability EPIP-10 Personnel Monitorin2 and Decontamination EPIP-ll Estimating Release from Radiation Monitoring System Data EPIP-12 Estimating Release from Station System Inventory Data EPIP-13 Estimating Release from Offsite Radiological Data EPIP-14 Estimating Doses from Released Data EPIP-15 Estimating Doses from Environmental Data EPIP-16 Offsite Air, Contamination and Radiation Monitoring EPIP-17 Offsite Water and Foodstuff Monitoring EPIP-18 Emergency Exposure Criteria EPIP-19 Fire Protection EPIP-20 News and Information Releases EPIP-21 Training and Emergency Preparedness F I 8109230083 810909 PDR ADOCK 05000280 F PDR
www .. EPIP-1 PAGE 1 of 11 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION DIERGENCY CLASSIFICATION AND ORGANIZATION FORMATION, NOTIFICATION AND COMMU'11 CATIONS _ 1.0 Initial Assesment and Corrective Action 2.0 Classify the Emergency 3.0 Itemediate Notification 4.0 Protective Measures . 5.0 Subsequent Notifications and Reports 6.0 Securing From the Emergency Appendix 1 - Emergency Classification Graphs & Nomographs
. , Appendix 2 - Initiating Conditions Appendix 3 - Area Sector Map - ICAO Phonetic Alphabet Appendix 4 - Notification of Emergency Personnel Appendix 5 - Report of Radiological Emergency Appendix 6 - Organizatian During Emeugency Conditions
yy-~ EPIP-1 PAGE 2 of 11 EMERGENCY CLASSIFICATION, NOTIFICATION AND ORGA'lIZATION 1.0 INITIAL ASSESSMENT AND CORRECTIVE ACTION 1.1 When notified of an emergency condition, the Shift Supervisor on duty shall initiate the following procedure (s) when appropriate. Check every applicable space. Note the date and time that the space was checked and initial. INITIALS DATE/ TIME
/ () Loss of Coolant; EPIP-7
/ () Steam Generator Tube Rupture; EPIP-5
/ () Main Steam Line Rupture; EPIP-6
/ () Fuel Handling Accident;' EPIP-4
/ () Unplanned / Uncontrolled Release; EPIP-2
/ () Personnel Injury or Overexposure; EPIP-3 O(-c
/ () Fire; EPIP-19
/ () Natural Event; ADM-25
/ () Other; Briefly Describe the Emergency 1.2 The remaining EPIP's will be initiated by cbove EPIP's or as deemed necessary during the course of the emergency.
NOTE: Return to this step as necessary,during the course of the emergency to reassess the situation and initiate additional corrective actions. Change No. 15
l EPIP-1 PAGE 3 of 11 l 1 8 2.0 Emergency Classification: 2.1 Classify the Emergency as soon as possible using the following guidelines. Check appropriate space, write date and time, and initial. INITI ALS DATE/ TIME
/ () Individual Judgment of Shif t Supervisor (A) Determine the emergency condition by personal judgment using guidelines set forth in Appendix 2.
(B) Cere appropriate, confirm monitor readings with sampling and analysis by chemistry and/or health physics.
/ () Appendix I, EPIP I (A) Determine stability class, wind speed and direction as per EPIP-2.
r3 V' (B) Obtain source data (curies rele sed) by initiating eit.her of the following EPIP's EPIP-ll Radiation Monitoring System Data EPIP-12 Station System Inventory Data (C) Complete Form EPIP-2.1, from EPIP-2. Emergency Classification l I may be obtained from graphs in Appendix I of this Procedure. '
/ () EPIP-7 (LOCA) (loss of coolant accident resulting in actuation of of CLS HI-HI) l (A) Follow EPIP-7 for initial classification l NOTE: Return to this step to descr!be the method used to reclassify the emergency.
2.2 Declare an emergency classification and check the appropriate space. Note date and time the emergency was classified and initial. n x - / () Notification of unusual event. Change No. 1.~
EPIP-1 PAGE 4 of 11 I. 2.0 Emergency Classification (Cont.) IWITIALS DATE/ TIME
/ () Alert
/ () Site Emergency l
I
/ () General Emergency NOTE: The Emergency Classification may change at any time during the course of the Emergency. Return to this step to reclassify.
2.3 Declare the position of Director as described in Appendix 6 and indicate the individual filling that position.
~
~
Name Date/ Time Name Date/ Time _ . Name Date/ Time NOTE: The Shif t Supervisor will be relieved as the Emergency Coordinator or Director in accordance with Appendix 6. 3.0 Immediate Notification 3.1 Once the Shif t Supervisor has classified the Emergency and declared himself the Emergency Director, he shall initiate the immediate notification as listed below. 3.2 Make each of the following notifications. Note the date and time the .fication was made and initial in the space provided. NOTE: During notification of unusual events, notification should be made only if any fatality or life threatening injury or multiple injury to personnel, occurring onsite and requiring transportatica to offsite medical facility for treatment; or,1f a contaminated individual is transported to an offsite hospital. O l Change No.15
y EPIP 1 PAGE 5 of 11'
~
3.'0 Inspediate' Notification . (Cont.) ' . f4 . L INITIALS 1DATE/ TIME . 3, .
'/
. Notify;the Superintendent of Operations or the S.R;0.on
@- 'c , t C ~
. call, and:
P- -(A) Describe the Emergency conditions to him.
- - (B) Direct.him to initiate the call out of additional operations shif t,'if required (by alert, site or General Emergency) or if deemed necessary by the
. Emergency Director.
L
/ Notify the NRC Operations ' Center using the NRC red phone and maintain an 'open and continuous communications channel with them. (This notification shall be made as soon as
- possible, but no later thanone hour af ter the discovery of the emergency conditions).
O. If .the callout of Emergency Response Personnel is required [- / or is deemed appropriate by the Emergency Director, direct Security to initiate the callout process in accordance to l-Appendix 4. I NOTE: Local rescue squads and the First Aid Team are called out- by EPIP-3. Local Fire Departments and Fire Brigade are called out by EPIP-19. 1
/ Notify. Corporate Headquarters. Emergency Classification of alert, Site and General Emergency will activate the 1
. Corporate Emergency Response Team and upon arrival vill l activate the near-site Emergency Operations Facility.
/ Complete Form EPIP.1.2" Report of Radiological Emergency" Change No. 15 l
, . _ _ _ - ~ 3 EPIP-1 PAGE 6 of 11 3.0 Immediate Notification (Cont.) (See Appendix 5) using currently available information. Using this form, notify the following agencies and transmit the recorded information: NOTE: Telephone numbers are on the Emergency Notification list in the Surry Personnel-Log. This should be done from a low noise area. INITIALS DATE/ TIME
/ State Of fice of Emergency and Energy Services
/ Surry County
/ < sic of Wight County
/ \:.tliamsburg
/ Newport News
/ York County
/ James City County O
NOTE: Upon declaring General Emergency or an Emergency requiring site evacuation, notify the affected jurisdiction (Surry in case of site evacuation) and then the State Office of Emergency and Energy Services. NOTE: See Appendix 8 for Subsequent Notification and Reports. 4.0 Protective Measures 4.1 The Emergency Director shall evalute the emergency conditior.s and determine the protective measures required. He should consult with appropriate personnel (such as Health Physics, Fire Marshall, Security, Operations Superintendent, etc.)to aid in the decision of appropriate protective measures. O Change No. 15
" EPIP-1 !
PAGE 7 of 11 14.0 -Protective Measures (Cont.) g i k' NOTE: Consider evacuation of on-site personnel if 1 Rem Whole body exposure,or 5 Rem thyroid exposure due to inhalation is proj ected. 4.2 The Emergency Director shall check every appropriate box below and initiate corresponding action. Note the date and time that each box was checked and initial in space provided. INITIALS DATE/ TIME.
/ () Limited Evacuation of Personnel from a potentially unsafe building or area; Sound Alarm and make appropriate announ-cement using the Gai-Tronics.
/ () Personnel Accountibility; Initiate EPIP-9.
() Site Evacuat in
/
l (A) Initiate EPIP-8 (Perform Personnel Accountability if k time allows). (B) Notify Surry County and then the Virginia Office of Energy and Emergency Services that an evacuation is being initiated. (C) Notify NRC Operation Center that an evacuation is being
' initiated.
/ .( ) Emergency Exposure limits; see EPIP-18.
/ ( -) Other Emergency Measures Required; Briefly describe, s
"L).
Change No. 15
. - . . .- - . - . ._. . . . . - . -._ -. - -.~,.
n - EPIP-1 PAGE 8 of 11 9 6.0 SUBSEQUENT NOTIFICATIONS AND REPORTS 6.1 As soon as conditions allow, the Emergency Director shall initiate the subsequent notifications listed below. 6.2 Check every applicable box below and initiate the corresponding notification. Note the date and time the notification was made and initial in the space provided. INITIALS DATE/ TIME
/ ( )Immediately notify NRC Region II by telephone and telegraph, mailgram, or f acsimile if the emergency involves radioactive material and causes or threatens to cause any of the following:
(A) Exposure of the whole body of any individual to 25 rems or more of radiation; exposure of the skin of the whole body of any individual of 150 rems or more of radiation; or exposure of the feet, ankles, hands or forearms of any individual to 375 rems or more of radiation; or (B) The release of radioactive material in concentrati- ,s which, if averaged over a period of 24 hours, would exceed 5,000 times the merimum permissible concentra-tions for such materials in unrestricted areas as listed in Appendix B, Table II of 10 CFR 20. (C) A loss of one working week or more of the operation of any facilities affected; or (D) Damage to property in excess of $200,000.
/ ( ) Notify the American Nuclear Insurers (ANI) within eight hours of the initiation of the emergency if: $
Change No. 15
EPIP-1 PAGE 9 of 11 6.0 Subsequent Notifications and Reports (Cont.) (A) The emergency required notification of state or federal agencies, or (B) It is believed that offsite persons are affected and l may require financial atsistance. INITIALS DATE/ TIME
/ ( ) Notify NRC Region II within 24 hours by telephone confirm by telegraph, mailgram, or f acsimile if the emergency involves a Reportable Occurrence as listed in Techincal Specification 6.6-5, Part 2.
/ ( ) Notify NRC Regicn II within 30 days by written report if the emergency involves an unplanned or uncontrolled release of radioactive materials in excess of the limits given in applicable Technical Specification 6.6 - 8.b.
/ ( ) Notify NRC Region II within 24 hours by telephone and 9 telegraph, mailgram, or fc.csimile if the emergency involves radioactive material and causes or threatens to cause any of the following:
(A) Exposure of the whole body of any individual to 5 rums or more of radiation; exposure of the skin of the whole body of any individe 2 to 30 rems or more of radiation; or exposure of the feet, ankles, hands, or forearms to 75 rems or more of radiation; or (B) The release of radioactive material in concentrations which, if averaged over a period of 24 hours, would exceed 500 times the maximum permissible concentration for such materials in unrestricted areas as listed in Appendix B, Table I' of 14 CFR 20; or Change No. 15
EPIP-1 PAGE 10 of 11 6.0 SUBSEQUENT NOTIFICATIONS AND REPORTS (Cont.) (C) A loss of one day or more of the operation of the station; or (D) Damage to property in excess of $2,000. INITIALS DATE/ TIME
/ ( ) Notify the Vepco Insurance Dept. as soon as possible if the emergency condition involves any of the following:
(A) A fatality, (B) 5 or more injured persons, (C) Damage to public property due to fire or other causes. (D) Damage to Company owned property due to fire or other causes, or (E) Notification of the American Nuclear Insurers
/ ( ) Initiate EPIP-20 NOTE: All news releases concerning the emergency shall be made by appropriate senior management personnel as designated in the Corporate Emergency Response Plan.
7.0 SECURING FROM THE EMERGENCY 7.1 Once recovery from the emergency condition is complete, the Emergency Director shall declare that the emergency condition is no longer in effect and shall insure that all completed EPIP's, forms and other applicable records are assembled and forwarded to the Station Nuclear Operating and Safety Committee for review prior to being filed in the station files. O Change No. 15
EPIP-1 PAGE 11-of'11 ; F': ...:f
.lU PROCEDURE COMPLETED:
i- Emergency Director DATE: TIME-REVIEWED: i l Chairman, Station Nuclear Safety and ' Operating Committee 4-2- -DATE: ) T l ' FORWARD TO STATION RECORDS + 4 i i l Oi ! i k I j-_ b b' I i 3 4~ i a 4 5 1 j k .: i 1 a i- O-1 Change No. 15 i
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MX 2 , s I . l EMERGENCY CLASSIFICATION AND ORGANIZATION FORFATION, NOTIFICATION AND COMMUNICATIONS APPENDIX 2 l INITIATING CONDITIONS
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( HH INITIATING CONDITIONS: NOTIFICATION OF UNUSUAL EVENTS Dk CONDITIONS APPLICABILITY INDICATION
- 1. ~A non-spurious SI Anytime not at SI initiated by valid signal (s) as listed in Tech. Spec. 3.7-4.
Initiated (ECCS) ' cold shutdown
- 2. Tech. Spec. radiological All Conditions Receipt of effluent' monitor _ alarms (s).and analysis by Health effluent instantaneous Physics ~ confirms that limits listed in Tech. Spec. 3.11 A or 3.11B limit exceeded. have been exceeded.
- 3. Fuel damage indicated. All Conditions liigh reactor coolant activity indicated by:
- a. Reactor Coolant ~ specific activity exceeds limits of,iech.
Spec. 3.1-15D as determined by sampling and analysis, or i
- b. Reactor Coolant liigh Range Letdown Radiation Monitor exceeds 1 x 10s cpm and analysis indicated Tech. Spec. 3-1-15D has been exceeded.
- 4. Tech. Spee. Safety Limit All Conditions Safety Limit (s) of Tech. Spec. are exceeded as indicated by exceeding exceeded. any of the Limiting Safety System Settings listed in Tech. Spec.
2.1, 2.2 and 2.3.
- 5. Unit shutdown' required by Reactor Critical Unit is shutdown as a result of exceeding a Tech. Spec. Limiting Tech. Spec. Conditions for Operation.
- 6. Failure of a safety or Anytime not at Failure of the following valve (s) to close:
relief vavle to close cold shutdown. that may affect the health a. Pressurizer Safety Valve (s) or Power Operated Relief Valve (s) and safety'of the public, as indicated by valve monitoring equipment,
- b. Steam Generator Safety Valve (s), Power Operated Relief Valve (s) or Decay llent Release Valve with appreciable primary ot secondary leakage.
Yn Nx f3't INITIATING CONDITIONS: NOTIFICATION OF UNUSAL EVENTS 4 CONDITION D LICABILITY INDICATION
- 7. Fire in Protected Area or All Conditions Shif t Supervisors judgement Switchyard which lasts mort than ten (10) uinutes 8 Security threat, attempted All Conditions Shif t Super.isors judgment, based on advice of the Security unauthorized entry, or Snift Supervisor.
attempted sabotage.
- 9. Natural phenomenen being All Conditions a. Earthquake near-site which activates the Event Alarm on the experienced or p'rojected Strong Motion Accelerograph on the Seismic Panel, or,r beyond unusual levels
- b. Flood in the James River with indicated river level greater than 22 feet MSL, o_rr
- c. Tornado near-stte as indicated by a visual sighting, or
- d. Ilurricane near-site with wind speed as measured at the Metcorological Tower exceeding 70 mph.
- 10. Other hazards being experienmad or projected All Conditions a. Report of aircraft crash within the Exclusion Area or judge-ment of the Shift Supervisor that unusual aircraft activity has occurred over the facility, or
- b. Report of detection of an unplanned explosion within the Exclusion Area, o_rr
- c. Report or detection of the release or toxic or flammable gasses in such quantities that, in the judgment of the Shif t Supervisor, the potential exists that the ability to operate the station may be impaired.
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DI INITIA1ING C0:lDITIONS: NOTIFICATIONS OF UNUSUAL EVENTS i'4' APPLICABILITY INDICATION CONDITION
- 11. Other station conditions All Conditions Shif t Supervisor judges that:
exists that warrant increased awareness on the part of a. Unit shutdown is other.than a normal controlled State and/or Local off-site shutdown. l authorities. For example, the cooldown rate exceeds Tech. Spec. limits.
- b. Unit is in other than a normal condition during. - '
operation and the abnormal condition is of such a nature as to warrant notification. For. } example, cracking is found in primary system piping during operation. I
- c. Any other condition exists which has the potential for escalating into an emergency and, therefore, warrants noti?1 cation.
- 12. Personnel Injury All Conditions Fatality of life threatening injury or multiple injury to personnel, requiring transportation to offsite medical facility.
Contaminated individual transported to offsite
- 13. Contaminated Individuals All conditions hospital
r N D >: b @! INITIATING CONDITIONS: ALERT CONDITION APPLICABILITY INDICATION
- 1. Severe loss of fuel cladding All Conditions Reactor coolant activity is equal to or greater than 300uCIA1 Ercept Refueling Dose Equivalent I-131,as determined by sampling and analysis.
- 2. Steam generator tube Unit Greater Than a. Steam generator tube failure indicated by radiation failure with loss of 3500F and 450 psig readings exceeding 1 x 105 cpm on the Condenser Air off-site power. Ejector Monitor or 1 x 10' cpm on the Steam Generator Blowdown Monitor, and
- b. Loss of off-site power indicated by the under voltage on 4160V Busses D, E and~F.
- c. Automatic SI initiation not required.
- 3. Cross steam generator Unit Greater Than a. Steam generator tube rupture indicated by radiation tube failure 350 F and 450 psig. readings exceeding 1 x 105 cpm on the Condenser Air Ejector Monitor or 1 x 10' cpm on the Generator Blow-down Montior, and b Automatic SI initiated as indicated by actuation of the safety injection equipment.
- 4. Steam line break with sign- Unit Creater Than a. Steam line break indicated by a SI initiated by exceeding ficant primary to secondary 350 F and 450 psig. the Pressurizer Pressure-Low-Iow or the Differental leakage or f a: lure of a Pressure between Steam Lines-liigh or_ the Steam Flow in Main Steam Triy Valve to Two Lines-liigh coincident with either Tavg Low-Low or close. Steam Line Pressure-Low setpoints listed in Tech. Spec.
Table 3.7-4, and
- b. Significant primary to secondary leakage as indicated by the last calculated primary to secondary leak rate prior to the steam line break exceeding onu-half of %e primary to secondary leak rate limt given in Tech. Spec.s 1.c, or_
- c. Failure of n Main Steam Trip Valve to close as indicated by continue high steam line flow on any steam line
- following steam line isolation.
- 5. Primary coolant leak rate ex- Not at cold shutdown a. Unable to maintain pressurizer Level >57.,
ceeding the capacity of (.ne chargi 9 pump. 9 e
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[ R1%! CONDITION APPLICABILITY INDICATION
- 6. High radiation levels or All Conditions Any one or more of the following Area Radiation Monitors or. Caseous
.high airborne contamination and Particulate Monitors exceeds the indicated levels and surveys 1cvels which indicate a by Health Physics confirms that a severe. degradation in control of envere degradation in the radioactive materials has occurred:
control of radioactive materials a. Ventilation Vent Sampler Gaseous Monitor exceeds 4 x 10' cpm 5 and Particulate Monitor exceeds 8 x 10 ' cpm.
- b. Control Room Area Monitor exceeds 100 mr/hr.
- c. Auxiliary Building Control Area Monitor exceeds 10" ar/hr.
- d. Auxiliary Building Drumming Area Monitor exceeds 10" ar/hr.
- e. Decontamination Building Area Monitor exceeds 10' mr/hr.
- f. Fuel Pit Bridge Area Monitor exceeds 10 3mr/hr.
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- g. New Fuel Storage Area Monitor exceeds 10 mr/hr.
- h. Laboratory Area ibnitor exceeds 103 mr/hr.
- i. Sample Room Area Monitor exceeds 10' mr/hr.
- 7. Loss of" of f-site AC power and All Conditions a. Undervoltage on 4160V busses D.E F, and loss of all AC on-site power ,
- b. Ammeters and voltmeters for 4160V Busses H and J all read 0 i
Amps or Volts.
- 8. Loss of all on-site DC All Conditions All Battery Voltmeters read 0 Volts and there is no light' indication power. of control power available.
- 9. Reactor coolant pump locked Power Operation a. Complete loss of flow in one loop, and rotor at power leading to fuel failure. b. Reactor coolant specific activity exceeds the limits of Tech.
Spec. 3.1-15D as determined by sampling and analysis.
c --- in , Dx b% INITIATING CONDITIONS: ALEP.T CONDITION APPLICABILITY INDICATION
- 10. Failure of the reactor pro- Reactor Critical Any reactor trip annunciator actuating oj; any reactor trip set-tection system to initiate point being exceeded with no rod bottom lights, cnd complete a trip when required.
- 11. Fuel damage accident with All Condicions An accident occurs while handling spent fuel or while moving objects release of radioactivity over the spent fuel in the spent fuel pit which causes:
to the containment or fuel building. a. The readings on the Containment Caseous and Particulate Monitors or the Ventilation Vent Gaseous and Particulate Monitors to in-
- crease by a factor of 1000, and
- b. Analysis by Health Physics confirms the release of fission products due to fuel handling accident.
- 12. Fire potentially affecting All Conditions Shif t Supervisors judgment, safety systems.
- 13. All annunciators lost with Reactor Critical Annunciator Panels A through K are all inoperalle.
unit not in a shutdown condition.
- 14. Radiological effluents All Csnditions Analysis of effluent samples confirms that instantaneous limits greater than 10 times listed in Tech. Spec. 3.llA and 3.llB have been exceeded by more Environmental Tech. Spec. than a f actor of 10.
instantaneous limits.
- 15. Ongoing security compromise. All Conditions Shift Supervisors judgment, based on advice of the Security Shift Supe rv isor.
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INITIATING CONDITIONS: ALERT CONDITION APPLICABILITY INDICATION
- 16. Severe natural phenomenon All Conditions a. A earthquake confirmed near-site which activates the Event being experienced or Alarm on the Strong Motion Accelerograph on the Seismic Panel projected and activates on alarm light,59;
- b. Flood in the James River.with indicated river level greater than 26 feet MSL, og;
- c. A tornado strikes the Protected Area or the Surry Switchyard, og;
- d. A hurricane near-site cause wind speed as measured at the Meteorological Tower to exceed.100 mph.
- 17. Other hazards being All Conditions a. Aircraft crash within the Protectad .~.rea or the Surry Switchyard, experienced or projected fn;
- b. Turbine failure resulting in casing penetration 53; any other event which produces missiles which impact within the Protected Area, or
- c. Known explosion, damage which, in the judgment of the Shif t Supervisor, affects the safe operation of the station..or;
- d. Release of toxic or flammable gases into the station which, in the judgment of the 9hif t Supervisor, affects the safe operation of the station, fl8. Evacuation of the Control All Conditions Shif t Supervisors judgment.
Room is anticipated or required, with control of shutdown systems established from local stations.
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INITI ATING CONDITONS: AI.ERT CONDTION APPLICABILITY INDICATION
- 19. Other station conditions All Conditions Shif t Supervisors judgment exist that warrant pre-cautionary activation of the on-site Technical Support Center and the near-site Emergency Operations Facility O O O
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INITIATING CONDITIONS: SITE EMERGENCY CONDITION APPLICABILITY INDICATION
- 1. Known major. loss Unit Temperature SI initiated by exceeding the High Containment Pressure - oj; Low. .
of coolant accident >3500 F and 450 psig Pressurizer Pressure - setpoints as listed in Tech. Spec.- Table 3.7-4, where it is known that_these initiating signals are not spurious.
- 2. Loss of core subcooling Not at cold Core Cooling Monitor or saturation curve indicates subcooling of shutdown OcF or less and this reading.is confirmed.
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- 3. Cross . Steam generator Unit Temperature a. Steam generator tube rupture indicated by radiation readings tube'i'ailure with loss >350 F and 450 on the Condensor Air Ejector Monitor exceeding 1 x 10' cpm of of f-site ' power ' psig. and on the Steam Generator Blowdown Monitor exceeding l'x
' "'IEN cpm, which are confirmed by. Health Physics, and
- b. Automatic SI indicated by actuation of the safety injection
. equipment, and
- c. Loss of off-site power indicated by the under voltage on 4160V Busses D,E and F.
- 4. Steam line break with Unit Temperature a. Steam line break indicated by a SI initiated by exceeding the significant primary to >350 F and 450 i Low Pressurizer Pressure - og; the.High Differential Pressure secondary leakage and psig. Between 9tesw Lines - og; the Low Steam Flow in Two lines- High indication of fuel leakage coincident with either Tavg Low-Low or Steam Line Pressure -
Low setpoints listed in Tech. Spec. Table 3.7.4 and
- b. Significant primary to secondary leakage as indicated by the last calculated primary to secondary prior to the steam line break exceeding one-half the total primary.to secondary leak rate limit given in Tech. Spec. 3.1.c and
- c. Fuel damage indicated by reactor coolant specific activity exceeding the limits of Tech. Spec. 3.1-15D as determined by sampling and analysis.
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1 ed NM D S! IMITIATING CONDITIONS: SITE EMERGENCY CONDITION APPLICABILITY INDICATIO*4 l
- 5. Loss of off-site power and All Conditions a. Undervoltage on 4160V Busses D,E,6 F and on-site AC power for more than 15 minutes
' b. Voltmeters for 4160V Busses ll,and J read O Volts, and
- c. The above conditions last for more than 15 minutes.
- 6. Ioss of all on-site DC All Conditions a. All Battery Voltmeters read 0 Volts and there is no light power for more than 15 indication of control power available on breakers ISBl and minutes 15Cl, and
- b. The above condition lasts for more than 15 minutes.
- 7. Loss of all functions Reactors Critical Loss of all the following systems, equipment, or controls:
needed to take the unit to hot shutdown. a. Auxiliary Feedwater System, and mainfeed H 2O system.
- b. Charging pumps or flow path to the core.
- c. Pressurizer Heaters cg; controls.
- d. Steam Generator not available for heat transfer as defined in T.S. 3.1.
- 8. Major damage to spent fuel All Conditions a. Cross damage to more than one fuel assembly in the Contain-in the containment or fuel ment ur Fuel Building while handling spent fuel or related building activities.
- b. The water level'in the reactor vessel or the spent fuel pit drops below the top of the spent fuel.
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- 9. _ Fire affecting any All Conditions Shif t Supervisors judgment.
safety system
- 10. Loss of all annunciators Reactor Critical Annunicator Paneln A through K are all inoperable for more than?
for more than 15 minutes - 15 minutes. with the unit not shutdown . or with a unit transient occurring while the annunciators are lost. ,9-
- 11. Projected doses at the All Conditions a. Projected doses estimated by Emergency Plan Implementing site boundary.of'from Procedures, exceed 0.5 REM whole body or 1. REM Thyroid i _0.5' Rem to 2 Rem whole exposure, or body exposure or 1 Rem The Ventilation Vent High Range Monitor reads greater than I to 12 Rem thyroid exposure b.
- 0.1 mR/hr, above background, .or
- c. The Process Vent High Range Monitor reads greater than -
1.3 x 10" mR/hr, and i d. Reports from monitoring teams indicate these doses are present at the site boundary.
.12. Imminent loss of control All Conditions Shif t Supervisor, judgment, based on the advice of the' Security _
of the physical security Shift Supervisor, of the station. 1
f a 4" t* 54 k INITIATING CONDITIO*;S: SITE EMERCENCY APPLICABILITY INDICATION CONDITION Severe naturdl Not at cold Unit (s) are not in Cold Shutdown and any of the following 13. ' phenomenon being shutdown phenomenon are experienced or projected: experienced or pro-jected with the unit (s) a. Earthquake near-site which results in a lost of external load or the loss of function of numerous non-seismic systems or not in the cold shut-components. down condition
- b. Flood in the James River with indicated river levels greater than 29 feet MSL, or_
- c. Low water in the James River with indicated river level less 24.4 feet MSL, cg;
- d. Winds in excess of 100 mph as measured at the Meteorological Tower.
Other hazards being Not at cold Unit (s) are not in Cold Shutdown and any of the following 14 experienced or pro- shutdown phenomenon are experienced or projected: jected with the unit (s) Aircraft crash which, in the judgment of the Shif t Supereisor, a. not in the cold shutdown af fects vital structures by impact or fire, cg; condition.
- b. Explosion or missile damage which, in the judgment of the Shif t Supervisor, causes severe damage to safe shutdown equipment, og;
- c. Entry of toxic or flanmable gasses into vital areas which, in the judgment of the Shift Supervisor, affects operation of safe shutdown equipment.
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CONDITION APPLICABILITY INDICATION.
- 15. Evacuation of the Control All Conditions . Control Room is evacuated and control of the following systems Room where control of the or equipment is not established within 15 minutes:
shutdown systems'is not established within 15 a. Auxiliary Feedwater System, mainfeed water system, and minutes.
- b. Charging pumps or flow path to the core, and
- c. Pressurizer Heaters, and-
- d. Steam generators not available for heat transfer as per T.S.
3.1.
- 16. Other station conditions All Conditions Shif t Supervisors judgment.
exist that warrant activa-tion of emergency centers and monitoring teams and a precautionary public notification. i r I I 1
Yn INITIALING CONDITIONS: GEND2.L DIERGENCY ( INDICATION CONDITION APPLICABILITY All Conditions Site boundary doses, as calculated by Health Physics or determined
- 1. Projected dose at the site from the projected dose nomographs or curves based on stability boundary exceeds 2 rem class, exceed 2 rem whole body exposure or 12 rem thyroid exposure.
whole body exposure or 12 REM thyroid exposure. All Conditions a. Confirmed loss of core geometry, and
- 2. Loss of 2 of the 3 fission product barriers with a Except Refueling g
- b. Confirmed loss of Reactor Coolant System integrity, and potential loss of the 3rd I barrier.
- c. A high potential for loss of containment integrity.
Shif t Supervisors judgment, based on the advice of the Security
- 3. Loss of control of the All Conditions Shift Supervisor, physical security of the station i
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Yn INITIALING CONDITIONS: GENERAL DIERGENCY gg D& CONDITION APPLICABILITY INDICATION
- 4. 0ther station conditions All Modes Any core melt situation,'such as one of the following examples:
exist, from whatever cource, that make possible a. A loss of coolant accident with failure of the Safety Injection a release of large System to perform, leading to severe core degradation or amountsoof radioactivity melt. With a core melt, ultimate failure of the Containment in a short period of time, is likely with several hours available for responsa.
- b. A transient initiated by a loss of the Feedwater System or the Condensate System, followed by a failure of the Auxiliary Feedwater System for an extended period of time. Core melt is possible in several hours with ultimate failure of the Containment likely.
- c. A transient requiring operation of the shutdown system with a failure to trip the reactor, followed by a failure of the core cooling and makeup systems. A core melt would result,
- d. A failure of both on-site and off-site AC power coincident with a total loss of the Auxiliary Feedwater System for several hours. This would lead to an eventual core melt with f ailure of the Contaimnent likely.
- e. A maall loss of coolant accident where the Safety Injection l System initially operates, but subsequent failure of the Quench Spray and Recirculation Spray Systems for several hours could Icad to a core melt and ultimate Containment failure.
NOTE? The most likely Containment failure mode is a melt-through l with release of gases only. Quicker and large releases are likely for a failure of Containment Isolation Systems.
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. MAP OF AREA SURROUNDING THE SURRY POWER STATION AG TABLE INDICATING f' ; SECTORS AND ZONES FOR USE IN OFF SITE. RADIOLOGICAL RESPONSE PLANS 1 1 4 \'
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TABLE OF WIND DIRECTION AND AFFECTED SECTORS s _. WIND ICAO e AVERAGE- DIRECTION SECTORS PHONETIC DEGREEP FROM AFFECTED ALPHABET 349-11 N H J K HOTEL 12-34 NNE J KL JUL%TT 35-56 NE K L M KILO 57-79 ENE L M N LIMA 80-101 E M N P MIKE 102-124 ESE N P Q NOVEMBER h 125-146 ' SE- P Q R PAPA 147-169- SSE Q R A QUEBEC 170-191 S i A B ROMEO 192-214 SSW % S C ALFA
.215-236 SW S C D BRAVO 237-259 WSW C D E CHARLIE 260-281 W- D E F DELTA
~282-304- WNW E F G ACHO
'305-326 NW F G H FOXTROT 327-348 NNW G H J GOLF e
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... EPIP-1 APX 4 PAGE 1 of 3 4 - :
EMERGENCY CLASSIFICATION AND ORGANIZATION FORMATION,
.- NOTIFICATION AND COMMUNICATIONS APPENDIX 4 NOTIFICATION OF EMERGENCY
. RESPONSE PERSONNEL i
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f' , l EPIP-1 APX 4 PAGE 2 of 3 NOTIFICATION OF EMERGENCY RESPONSE PERSONNEL 1.0 FURPOSE The purpose of this appendix is to implement the actions required to notify the personnel deemed 3 necessary to assist in the response effort,following the declaration of an energency condition. 2.0 SHIFT SUPERVISOR ,
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Following the declaration of an Alert, Site Emergency, General Emergancy, or at any other time it is deemed appropriate, the Shift Supervisor shall notify Security and instruct them to commence notification of emergency response personnel in accordance with the Emergency Notification List. O 3.0 SECURITY 3.1 Following notification by the Shift Supervisor, Security shall begin notification of E.mergency Kespcnse Personnel by using the Emergency Notification List. 3.2 Security :nall use all available Security personnel and telephone lines to make the required notifications as rapidly as possible. 3.3 Security shall telephone in order, each of the individuals listed fromeach of the departments denoted on the Emergency Notification List until one individual in each department listed has been contacted. Once at least one individual in that department has been notified that an emergency exists , Security will commence calling individuals in the next department. ".iis notification process will continue until at least one person in each department listed is contacted.
I4 EPIP-1 .y , ' 4 PAGE 3 of 3 ( I L/"',r( 3.6 -SECURITY (Cont.)
'3.4' Security shall commence notification of the Security shift which'is scheduled to relieve them and have the members of
.this shift report.to the station immediately. Notify relief Shift Supervisors of' potential need to call out relief sh'if t.
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4.0 INDIVIDUAL DEPARTMENTS L0nce an individual in one-of the departments listed in the Emergency Notification List has been notified by Security that an emergency condition exists at the station, that in-dividual shall commence notification of emergency response personnel frem that department, as listed on the appropriate 3 2h departmental Emergency Notification List. These emergency
- response personnel.shall be notified that an emergency L condition exists at the station and that they are to report to the station immediately.
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EPIP-1 APX 5 PAGE 1 of 2 O F i APPENDIX 5 ! REPORT OF RADIOLOGICAL
, EMERGENCY I
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EPIP-1 1 APX 5 Page 2 of 2 REPORT OF RADIOLOGICAL EMERGENCY TO: (Local Jurisdiction & State OEES) FROM: (Nuclear Facility or State OEES)_,
- 1) Dhte and Time of Emergency
- 2) Classes of Emergency Action Levels: (Circle)
- a. Notification of Unusual Events c. Site Emergency b.. Emergency Alert d. General Emergency
- 3) Wind Direction From: Wind Speed: MPH:
- 4) Area Affected: (Alphanumeric Designation)
- 5) On-Site Situation: (Circle)
- a. Evacuation of on-site personnel: Yes No Some
- b. Recommended protective actions: None Shelter Evacuation
- c. Assistance needed: Fire ' ice Ambulance Other
- d. Prognosis of situation: Termination Worsening Other
- e. Emergency response actions underway:
- 6) Name/ Position /Telphone No.:
FOR STATE OFFICE OF EMERGENCY & ENERGY SERVICES ONLY-
- 7) Type of Release: (Circle) Airborne Waterberne Surface Spill
- 8) Estimated Duration / Impact Times of Release:
- 9) Description of Released Material: (Chemical & Physical Form, Estimate of Equivalent Curies of I-131 & Xe-133 Released, Iodide / Noble Gas Ratio)
- 10) Wind Speed: 11) Temperature: 12) Form of Precipitation Meters /Sec. OF
- 13) Atmospheric Stability: (Pasquill Category)
- 14) Actual or projected dose 15) Projected integrated dose rates at site boundary: at site boundary es: 2 5 10
- 16) Projected dose rates at:
Projected integrated dose: O
- 17) Estimate of surf ace radioactive contamination:
- 18) Remarks : Use additional sheet (s)
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i L D EMERGENCY CLASSIFICATION AND ORGANIZATION FORMATION, 4 .
-NOTIFICATION AND COMUNICATIONS
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- APPENDIX 6 ORGANIZATION DURING EMERGENCY CONDITIONS 1
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} k i EPIP-1 APX 6 Pag 2 2 of 5 1.0 RESPONSIBILITY AND AUTHORIQ l.1 EMERGENCY DIRECTOR Following the declaration of an , Alert, Site or General Emergency, the Shif t Supervisor acts in the capacity of Emergency Director until relieved. As additional personnel arrive onsite, the Shif t Supervisor will be relieved of his duties as Emergency Director by, in descending order of preference, the.: a) Station Manager b) Assistant Station Manager c) Superintendent Operations d) Superintendent Technical Services e) Superintendeat of Maintenance t) Operating Supervisor Once one of the above individuals has relieved the Shift Super-visor as Emergency Director, the Emergency Director shall re-locate to the Onsite Technical Support Center (OTSC) and shall additionally act as OTSC Supervisor. The Emergency Director shall have overall authority and responsiblity for directing the emergency response activities. 1.2 EMERGENCY ORGANIZATION The following individuals or their alternates shall report directly to the Emergency Director: a) Assistant Station Manager b) Superintendent Operations c) Superintendent Technical Services d) Superintendent Maintenance d) Supervisor Her.lth Physics
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EPIP ' ' APX 6 Page 3 of 5 . i
.m s 1.0- RESPONSIBILITY AND AUTHORITY (Cont.)
f) Onsite Operations Support Center Supervisor g) Supervisor Administrative Services h) Resident QC Engineer
- 1) Nuclear Training Supervisor These superintendents and supervisors shall, in turn, direct the activities of the departments which normally report to them.
. The emergency. response organization is basically the same as the normal station organiuation, with the superintendents and super-visors ~ being responsible for supervising and directing the emergency response activities as directed by the Emergency Director.
2.0 COMMUNICATIONS
- (N '.1 ONSITE COMMUNICATIONS t,
s-i i The lines of communication during the emergency response effort will be from the Emergency Director, through the superintendents and supervi ers which report to him, to the supervisors in charge of .the Emergency Response Personnel located at the various assembly areas in the station. Communications to the Emergency Director will take the reverce path. l 2.2 0FFSITE COMMUNICATIONS l All communications to and from the offsite response groups will be made by the Emergency Director, or his designee. Requests for assistance from offsite response groups, such as Vepco or vendor emergency response groups, will be made by the Emergency Director and these personnel will be directed to report to the (i appropriate station superintendent or supervisor at the approp-
. L) riate assembly location; i.e. , of fsite engineering support
7 EPIP-1 AP7 6 P:ge 4 of 5 2.0 COMMUNICATIONS (Cont.) Q personnel would report to the Engineering Supervisor at the OTSC, offsite operations support personnel would report to the 00SC Supervisor at the 00SC, offsite electrical support personnel would report to the Electrical Supervisor in the Electric shop, etc. All off sita emergency response personnel will come under the direction of station supervision once they report to the statien. 3.0 REPORTING TO THE SThTION Upon arriving onsite, personnel shall report to the locations listed below: ONSITE TECHNICAL SUPPORT CENTER (OTSC) Station Manager Assistant Station Manager lll Superintendent Operations Superintendent Technical Services Superintendent Maintenance Supervisor Health Physics Shif t Technical Advisors Not on Shif t Nuclear Training Supervisor OJ.ST% uiEFATIONS 50 PORT CENTER (00SC) Operators not required for plant operation Operators scheduled to relieve the ou duty shift Fire Brigade members First Aid Team Memberc NOTE: The first Shif t Supe
- visor or Assistant Shif t Supervisor llh reporting to the 00SC shall assume the duties of the 00SC Supervisor and shall act in this capacity until relieved by an individual appointed by the Emergency Director.
EPIP-1 APX 6 Paga 5 of 5
- wi
' ~
l M 13.0 REPORTING TO THE STATION (Cont.)- ,
- HEALTH PHYSICS AREA FONITORING PERSONNEL
~ Health Physics NOTE: The first Health Physicist or Assistant Health Physics Supervisor reporting to the Health Physics Area shall assume supervisory responsibility for the monitoring teams.until relieved by an individual appointed by the Emergency Director, Other stction personnel shall report to their normal assembly area and await further instructions. The first supervisor to ' . report to each of these areas shall assume supervisory respon-sibility until relieved by a more senior supervisor as directed by the Emergency Director.
f s 4 'O 4 _- (L 4
r' EPIP-2 Page 1 >f 5 AUG 3 0 G73 VIRGINIA ELECTRIC AND PO'w'ER COWANY SURRY POWER STATION UNPLANNED OR UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL 1.0 Operations (Shif t Sapervisor) Response 2.0 Operations Response 3.0 Health Physics Response . Anoendix 1 General Release Significance and Evaluation
/- .
~ Appendix 2 Stability Class Determination
( t Appendix 3 Blank Forns EPIP 2.1, Repc on Information Sought by Emergency Coordinator or D ' tor Appendix 4 Blank Forns EPIP 2.2, Gaseo. . Release Evaluation Appendix 5 Blank Forms EPIP 2.3, Liquid Release Evaluation Appendix 6 Dose Equivalent Factors and MPC's for Various Nuclides
F EPIP-2 8-22-77 Page 2 of 5 1.0 Operations (Shilt Sopervisor) Response 1.1 Obtain from Appendix 3 of this procedure a FOPJi EPIP-2.1,
" Report on Information Sought By Emergency Coot v tor or Director".
- 1. 2' Check, as appropriate to the exice.ing situation, the blocks opposite the do desired under gaseous or liquid release.
NOTE: If radidian monitoring sys.te u'da is checked, .b1i-
.tAage EPIP 11, Estimating Re: ease from Radiation Moni-toring System Data.
NOTE: Dose estimates are going .co require radiation surveys and/or sampling and thenefore require tzme to complete. To obtain results sooncr, strike out any data not considered applieable. 1.3 Assign responsibility of the FOR!i EPIP-2.1 to someone.in Operations and to the Senior IIP Representative presently on site. Sign the Form following " requested by", enter the date and time. Person 0 1y ensure the assigned operator receives the Form.
- 1. 4, Evaluate the applicability of Appendix 1, " General Release Significance --d Evaluation".
1.5 Evaluate the applicability of Appendix 1, " Significance and Evaluation of Release Estimates Based on Station System In-ventory Data", of EPIP 12, " Estimating Release from Station e System Inventory Data". 4 e s.
EPIP-2 AUG S 0 S78 Page J of 5 g i , i s) '.0 Operations Response' Follow the instructions for the applicable blocks as indicated on FORM EPIP-2.1. 2.1- Meteorological Data Stability Class - 0otain the delta T from the computer
~
2.1.1' in the Control Room and determine the Stability Class from belcw. Pasquill *F/?l5 ft.
' Categories 'C/35m
<-0167 <-1.20 A -1.20 to -1.07 B -0.67 to -0.60
-0.60 to -0.53 -1.07 -to -0. 94 C -0.94 to -0.31 D -0.53 to -0.18
-0.18 to 0.53 ' -0.31 to 0.94 E 0.94 to 2.53 F 0.53 to 1.40
>1.40 >2.53 G
If dalta T not available, use alternate methods given in ,((~)_4 Appendix- 2, " Stability Class Determination", of this procedure. Wind Speed - Obtain.from computer in Control Room. Use 2.1.2 150 foot elevation, if not available use 35 foot eleva-tion, and if neither available, use the backup meteorological data. Visual. observations may be used.if both primary and c.. ' backup. system' fail. 2.1.3 Wind Direction - Obtain from computer i Control Room Use using approximate average of previous 15 minutes. 150 foot elevation, if not available, use 35 foot eleva-tion, and if neither svailable, use the backup meteorological data. Visual observations may be used if both the primary and backup systems fail. 2.2 Radiation Monitoring System Data 2.2.1 Initiate EPIP-ll, " Estimating Relea:e from Radiation Y_ (~/ L. ' Monitoring System Data". CHANGE NO. 7
-- l l
EPIF -2 8-22-77 Page 4 of 5 2.0 Operations desponse (cont.) 2.3 Source Evaluation Data 2.3.1 Source of Release - Identify the sov-:ce as per tank number or in the case of a pipe or tube break the source supplying the pipe or tube, describe system malfunction or any other useful information. 2.3.2 Possible Paths to Environs - Indicate possible paths the liquid or gases may get offsite, such as storm drains or process venc. This will aid HP in selecting sampling locations. 2.3.3 Estimated Cu'oic Feet or Gallons Released - Indicate cubic feet or gallons of gas or liquid actually or , projected to be released. 2.3.4 Dilution Water - Indicate the available dilution water lll flow rate. s 2.3.5 Present Status / Remarks - Provide any information which vill aid HP such as indicating if the release is still in progress and if so when will it be terminated. 2.4 Forward FORM EPIP-2.1 to the assigned HP representative as soon as the above steps are complete.
. h s
\
EPIP-2 8-22-77
~
Page 5 of 5 3.0 Health Physies Response k'- 3.1 Determine the Activity Released or Dose Estimates as requested on FORM EPIP 2.1 per the following steps as appropriate. - 3.2 Activity Released 3.2.1 (Reserved) u. 3.2.2 Select and initiate (based on available information) one or more-of the following EPIP's to estimate re-lease: EPIP-ll Radiation Monitoring System Data EPIP-12 Station System Inventory Data EPIP-13 Offsite Radiological Data 3.2.3 As release data is cbtained the results are to be O entered on FORM EPIP 2.2, " Gaseous Release Evaluation", or FORM EPIP 2.3, " Liquid Release Evaluation", as appropriate. Blank forms and instructions are in Appendix 4 or 5, respectively.
, 3.2.4 Perform the calculations of equivalent Xe-133 and I-131 and percentage MPC as indicated on FORM EPIP 2.2 or 2.3 -
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EPIP-2 8-22-77 APX 1 Page 1 of 3
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UNPLANNED OR UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL s
- APPENDIX 1 GENERAL RELEASE SIGNIFICANCE AND EVALUATION Part Subject
.5. 0' Emergency Plan Commitments 2.0- Technical Specification Requirements 3.0 Environmental Technical Specification Requirements 4.0 '10CFR20 Requirements 5.0 Minimum Information on Release-Report' 4
I . t 4 l r o e n n -
-e-+ -m-,,-w.,,,-,n, , ,
EPIP-2 8-22-77 APX 1 Page 2 of 3 1.0 Emergency Plan Commitments i 1.1 Notification of the Virginia State OES and Local Agencies is implemented in EPIP-1. 1.2 The Commonwealth of Virginia - Health Department - Radiological
" Health is to be notified as soon as practical f or any unplaanad release of radioactive material which requires the notification o_r r reporting to the NRC.
2.0 T*cchnical Specifications Requirements 2.1 6.6.1.b.2.f (annual report) "a report of any single release of radioactivity....specifically associated with the outage which accounts for more than 10 percent of the allowable annual values". 2.2 6.6.2.b.4 (thirty day report) " Abnormal degradation of systems
.... designed to contain radioactive material resulting.from the fission process". For example, a through-wall leak in a liquid waste storage tank.
2.3 6.6.2.c.2 "If levels of station coatributed radioactive materials
.... exceed 3% of 10CFR20....".
2.4 '6.6.3.c.3.(e) "An estimate of th'c likely resultTnt exposure to the public if it exceeds 10 mrem". 3.0 10CFR20 Requirements 3.1 10CFR20.403(a) Immediate notification to NRC, Region 11 if the release c: radioactive materials in concentrations averaged over 24 hours would exceed 5000 times unrestricted MPC's. 3.2 10CFR20.403(b) Twenty-four hour notification to NRC, Region II if the release of radioactive materials in concentrations
- - - . _ ~ _ . . _ _ _ . _ . _
EPIP-2 8-22-77 MX 1 i. Page 3 of 3 6 -10CRR20 Requirements _ (cont.)
)- :
3.0 3.2 averaged over 24 hours would exceed 500 times unrestricted MPC's'. 3.3 10CFR20.405 Thirty day report - see 10CFR20 for details. a 4.0 . Minimum Information on Release Report 4.1 The following data should be included in any report submitted to the NRC concerning the unplanned or uncontrolled release of 4 . radioactive material.
- 1. A list of the nuclides released, indicating their MPC's (unrestricted arra) and the curier released for each.
- 2. The amount of dilution medium available, either air or water.
, F
- 3. The percent of 10CFR20 (unrestricted area) for each V
nuclide.
- 4. The total percent of 10CFR20 limits the release resulted in causing.
'5. .The times MFC averaged over 24 hours.
- 6. The percent of the applicable Tech. Specs.
NOTE: Ant) aecidental release of radbactive mater.tal must also be .htetuded along teitit the planned releases in tJte semi-aniutal cffluent release reports. Ensure the release h aeeoanted fon. only onee however. l O - l
. 'EPIP-2 8-22-77 APX 2 Page'l of 5 l(
'I -
UNPLANNED' OR UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL 9 :. I APPENDIX 2 , o CTABILITY CLASS DETERMINATION THIS APPENDIX IS TO BE USED TO DETERMINE STABILITY CLASS IF THE, DELTA T RECORDER IN THE CONTROL ROOM IS INOPERABLE I 1. Fluctuation of tJind Direction .
. 2. Rules of Thumb p
O o t t s e e
, e
, _ . , - , . , .- - - -, er . , . - - - - , . - - . . -
. I EPIP-2 8-22-77 APX 2
- Page 2 of 5 1.0 Fluctuation of Wind Direction g Place a sheet of paper on the wind direction chart on the portion that includes the most recent 15 minute period. Stability shall be determined by a measure of the wind direction range defined as distance in degrees betweert the second, peak in, from the extreme left peak, to the second peak in from the extreme right peak of i.he 15 minute wind direction trace. Place a sheet of paper so its left edge is on the second (left side) peak in or point A and mark a line on the sheet where the second (right side-) peak in or point B is located. Place the edge of the sheet on the left side edge of the chart paper and note the degrees between Point A and Point B. Refer to Table 1 and determine the stability class. In Figure 1, approximately 110 are iaeasured indicating Class B stability.
FIGURE 1 0
]
I i fl {! i['il'!l h l ! Y}Iho 60 l. I !U 330 4 a.m.
"N.1 p l l I yj 300j /
Second Gust QQO. ,'140 s. 21_0 [ D h;+jh] !l (Pt.B) i ,5llihllllllp'! I' : . ,
+
Second Gust Pt.A to Pt.B l ! ! (Pt.A) j o. l l, l
- g{ ,l j {
-Ill
'-Q
_ _~ --)m - [ _ M .: % -3, - N { l ! s !.L._ - . . .Q ; ,' 'I
%.,i .;;i..:IE??-
i llLsd_ .NpW-*i l ilgli.'~ N'jy:-4 %
-if 4 *- ig _ N Extreme Gust gg#-h? Q [' ? d.r--.--
[ l (Pt.S-1) G +: %j Extreme Gust
/ -
7 3 l " SE "q- '1 1-t [ N -~-~
-j ! M W~".
l (Pt.A-1) 7 l0 - .: ipe ~ l l 4 7 .,.A. l' ;g 2 39 d .I ,300; k'lf * *
- 60' -J i l120 w y d gy)40..y)J.1 .;. M 1 iii.WUlllEl Ii
- l
' i -
e
EPIP-2
. 8-22-77 APX 2 Page 3 of 5 Modification of Section 1 is necessary when the direction trace occurs pq both at the right and lef t hand margins, t.nich occurs when the wind passes through the north direction as illustrated in Figure 2. In this instance place a sheet of paper on the left mart 6n of the chart paper and mark it where the recond gust in or point A occurs during the most recent 15 minute
- o '
period. The sheet of paper is then put on the right hand margin of the chart paper with the mark made at point A being in alignment with the edge of the chart paper. Mark the sheet where the' second gust in or point B occurs during the point of interest. This last mark now denotes the sum of point A and point B in degrees. Now place the sheet of paper with its edge on the left margin of the chart paper and note the total degrees or the degrees indicated at. point B. The following example indicates point A = 32 and point A plus point B = 100 (point B gust measures 68 ). Figure 2 indicates Class C stability. (] llllllllllllllll l
-~~
[ g QUy' Second C
+--- A+B W (Pt.B)
!! l Y N, 4 .m.
Second Gust
'g l o
.s 30, E
120 ..Y- _' 33
~ e 150 +- 210 =24o ~
(Pt.A) 6
/
w d.,ig, g
! iM.iT c FIGURE 2
= M[j , ;
P i fif; :;. s j
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+ 1
' hlllW'
/ E' Extreae Gust / w] CNE (Pt.A-1) MT'-
L I bT - - - -,a i j+=, aps . _
-[-
h i l 'l $'0s Extreme Gust
- s. M. i$ l I
S 'P ' l (Pt.B-1) [g;{Jg, h. LL2o D E I w 3 a.m. l iso s 21'o 249,.,i.pl 300ge ;
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EPIP-2 B-22-77 APX 2 Page 4 of 3 9 TABLE 1 Obtain the stability class from the following table. , o DEGRESS FLUCTUATION STABILITY CLASS
> 135 ,- A 105 to 135 B~
75 to 104 C 45 to 74 D 23 to 44 E 8 to 22 F
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d , EPIP-2 8-22-77 APX 2 Page 5 of 5
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- 2. 0 - Rules of Thumb ,
If appropriate met tower data is not available, use the following table to determine stabiIity class. s DAYTIME NIGl! TIME ESTIMATED Amount of sunlight reaching-the surface Thin overcast Little
- WIND SPEED MPH -STRONG - MODERATE ' SLICitT or cloudy 'Cloudliness
-B B F G
<4 A B C E F 4 B
. C- C D E 9 B
> 13 C D 'D D D LO.L e
.)
O' . 4 9 9 a- .- --
EPIP-2 2 , 8-22-77 APX 3 t Page 1 of 2 (
- %};~
UNPLANNED OR UNCONTROLLED RELEASE OF ^ RADIOACTIVE MATERIAL
, 4 APPENIDX 3 . ,
i i e
- BLANK FORMS EPIP 2.1 t
i b . REPORT ON INFORMATION SOUGilT BY EMERGENCY COORDINATOR OR DIRECTOR 1
-i i-EO I ,
1 f I e 3 1 ) J i i i 2 0 4 6 { h~ l t.
. , . -----.-y--.-, --,,,eq-r-e -- - -- e . -
- r,-,,.-., m .w,,- ,,,,,w -w r emy.+w.-. --
e ww , e , 3w,- e c --m-p
l A FOM EP,IP 2.1 JUN i 1978 REPORT ON INFORMATION SOUGHT BY EMERGENCY COORDINATOR Oh DIRECTOR Requested By: Date: Time: lll 1 Assigned to: OPS HP GASEOUS RELEASE DATA OPS !!eteorological Data. By: date/ time Stability Class Determined by AT, Wind a Rule of Thumb Wind Speed HPH Meters per second (MPH x 0.45) Wind Direction OPS Radiation Monitoring System Data for Unit . EPIP 11 initiated by: Date/ Time: OPS Source Evaluation Data. By: Date/ Time: Source of Release Possible Paths to Environs Cubic Feet Released Present Status / Remarks HP Activity Released. By: date/ time Equivalent Curies Xe-133 Equivalent Curies I-131
- x MPC (10CFR20)
HP Dose Estimates. By: date/ time Offsite Whole Body rem Onsite Whole Body rem Offsite Thyroid rem Onsite Thyroid rem LIQUID RELEASE DATA OPS Source Evaluati.on Data. By: date/ time Source of Release Possible Paths to Environs Estimated Gallons Released Dilution Water GPM Present Status / Remarks OPS Radiation lionitoring System Data for Unit . EPIP 11 initiated by: Date/ Time: HP Activity Released. By: date/ time Gross Curies of Non Tritium or Gases Curies Tritium Curies Gaaes 'x MFC (10CFR20) HP Dose Estimates. By: date/ time h Offsite Whole Body rem Offsite Thyroid rem 0ffsite Any Orgat. rem Onsite Whole Body rem Onsite Thyroid rem
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EPIP-2 l 8-22-77 APX 4 1 - Page 1 of 2 UNPLANUED OR UNCONTROLLED ~ RELEASE OF RADIOACTIVE MATERIAL o
. APPENDIX 4 1-BLANK PORM EPIP 2.2 GASEOUS RELEASE EVALUATION 9
h. I j ,. n II . k 3 .. 1 i a J d 4 i l e .g . i: 0 4 i
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' +
Tom EPIP 2.2 ' ' 8-22-77 CASEOUS RELEASE EVALCATICN Date/ Time of Associated Form EPIP 2.1 Results Obtained from j Cnsite d Offsite Data Reinarks/ Additional Information: DCSE EQUIVALENT CURIES I3 CURIES MPC PII. EASED . PIMARKS EQUIVALENT RELEA*CD TACTCRS RELEASED MPC A B Ax3 C A*C To illustrate rethod
,h l
l 1 i i 1 1 1 ! I I I I l I I - I i, ' -
- i i l I I
Sum of Equiv. Ci Xe-133 Released I Total ! l l Sum of Equiv. Ci 1-131 Released l Total l Calculation of the nurter of time MPC exceeded averaged over 24 hours 0 x MPC = 4 x (Total Ci/MPC for Xe + Total Ci/MPC for I) 8.64 ,x 10
" *#O + ) = Times MPC 4
x( 8.64 x 10 Results Bys c.te ,ime, ,
~~r->-- .
EPIP-2
~ '
'. . 8-22-77 APX 5
. Page 1 of 2 6' ,
j i 0
- UllPIANNED OR UNCONTROLLED RELEASE OF RADIOACTIVE IfATERIAL
-o
' APPENDIX 5
't
\
t _s BLANK FORMS EPIP 2.3 j t-LIQUID RELEASE EVALUATION , s O e
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e 3 f-s r 5 . 4 ) 5 i . p 4 j . . ?.1
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I j * [. . b r LO! f ?. ' _ ,. 2 s {- . s ,ew.4 _ - - - , . , , . . .-n_w,-.,m.m.<wc -cm.. , .,-,c.-~~,..ve-+- .--m_m---.--m.w-,*--w._...m,w ..w. - ~ . . . -,-..,y--.
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- FOPM EPIP 2.3 8-22-77 LIQUID RILEASE EVALUATION Date/ Time of Associated Fors EPIP 2.1 Sample obtained from Remarks / Additional Infor=ation uCi mis uCi uCi Released Nuclide E Released Released TOC MPC . REMARJJ l
i l i I l 1
! I i
i I l l l l 1
- I i l l t Total Non-Tritium or Non-Radiogases l l I n-3 l- I I I 3c-3 I I (
+ l
. I
~
Totai Dissolved Radiogases j l Calculation of the n'unbey of times MPC exceeded averaged over 24 hours 1.83 x 10 X To ,ls for all uCi Released /:GC X MPC Dilution Water G?M
= 1.83 x 10" X ( + + )
=_ X MPC Results Dy
- Date/ Times m y
. _ = _ _ _ ._ _ . . . . _ . . . ..___. ___. . . _ _ _ .. .
- EPIP-2
~ 8-22-77 +
i APX 6 Page 1 of 2
/
d T l UNPLANNED OR UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL A i APPENDIX 6 e -! DOSE EQUIVALENT FACTORS AND MPC's FOR VARIOJT(NUCLIDES 2 i A e i 4 4 LO: 4 4 5 6 1 9 4 s i a d I i i ' 1 b _ t s t l
- 5. .
i t - b. t . ; DL . v . ,
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,,,---.----r-w----m a+ m ee- - - , e, e** -w--w--'v_ - .w- we% *-m-*w-
EPIP
- 8g2g77 Pzs3 2 cf 2 I DOSE EQUIVALE*lT FACTORS AND MPC's FOR VANIOUS NUCLIDES a
- DOSE f EQUIVALENT HPC - AIR MPC - VATER l NUCLTDE FAC" TOR WRESTRICTED UNRESTRICTED
' E-3 6.4 E + 0 2 F. - 7 3E-3 Er-85 8.8 E - 2 3E-7 3E-6 l l
Er-85s 3.2 E + 0 1E-7 3E-6 ,
. Er-87 5.2 E - 3 2E-8 3E-6 o
Er-58 6.1 E + 1 2 E - tl 3E-6 Ze-131m 1.1 E + 1 4E-7 3E-6 Ie-133 1.0 E + 0 3E-7 3E-6 Ie-133m 1.1 E + 0 3E 3E-6 , Ie-135 8.4 E + 0 1E-7 - 3E-6 Mn-54 7.0 E + 2 1E-9 1E-4 s , Mn-56 1.9 E + 2 2E-8 1E-4
, Fe-59 1.6 E + 3 '2E-9 5E-5 Co-58 7.7 E + 2 2E-9 9E-5 ,
Co-60 , 2.0 E + 3 3 E - 10 3E-5 Cr-51 3.3 E + 1 8E-8 2E-3
~
Sr-89 1.6 E + 4 3 E - 10 3E-6 Sr-90 1.7 E + 4 3 E - 10 3E-7
. St-91 2.9 E + 2 . 9E-9 5E-5 Er-95 1.4 E + 3 .,1 E - 9 6E-5 Mo-99 1.0 E + 2 7E-9 4E-5 Ru-106 9.1 E + 3 2E - 10 1E-5 Te-132 3.9 E + 2 4E-9 2E-5 Co-134 5.1 E + 3 4 E - 10 9E-6 f
co-136 9.1 E + 2 6E-9 6E-5 Cs-137 2.8 E + 3 5 E - 10 2E-5 E Ba-140 2.0 E + 3 1E-9 2E-5 Ce-144 8.6 E + 3 2 E - 20 1E-5 1-131 1.0 E + 0 1 E - 10 3E-7 1-132 3.8 E - 2 3E-9 8 E -6 1-133 2.5 E - 1 4'.E - 10 1 E - _6 1-134 1.9 E - 2 GE-9 2 E'- 5 1-135 9.0 E - 2 1E-9 4E-6
+ e .
, ._- + - . , . i EPIP-3 Pap 1 of 4
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4-VIRGINIA ELECTRIC AND POWER C05SANY SURRY POWER STATION b ,I' . t INJiJP2D PERSONNEL l
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EPIP-3 P2:ga 2 cf 4 8-22-77
' INJtIRED PERSONNEL 1.0 Purpose To ,rovide guidance for.the care of injured personnel (provisions of Vepco Accident Prevention Manual, Article 103, apply).
o 1.1 Minor Injuries - No Assistance Recuired Personnci experiencing an injury of such a nature where assistance from the First Aid Team is not required will assure appropriate treatment is received and that the accident is reported in accordance with Article 103.05 of the Accident Prevention Manual. 1.2 Injuries Requ' iring First Aid Team Assistance - On Site Treatment Only_ 1.2.1 The following actions shall be taken expeditiously to insure responsive treatment.
- n. Call the First Aid Team- use the most convenient means availabic (nonnally Gaitronics) informing team members where the injured .
party is located. Exampic: First Aid Team Report To The Control hsom. ll
- b. First Aid Team Actions
- 1. Respond to the call for assistance.
- 2. Senior member of team assumes leadership and directs treatment.
- 3. Obtain additional assistance or release unnecessary personnel as appropriate.
- 4. Notify the Shift Supervisor (name, condition, treatment) of injured individual (s).
~
- 5. Notify injured individual (s) immediate supervisor. .
- 6. Notify Health Physics of injury and location of individual and where injury was sustained.
7.* Complete First Aid Team Accident Report.
- c. Immediate Supervisor's Action
- 1. Ensure accident injury report is submitted as specified in Article 103.05 of the Accident Prevention !bnual.
- 2. No,tify the Station ibnager.
6
, 7 v
EPIP-3 P:g2 3 cf 4 T < 8-22-77 4 1.3 Injuries Requiring Off-Site Treatment i.3.1 For injuries of such severity that treatment beyond the capability of the First Aid Team is considered necessary, perform the following in addition to Step 1.2 above:
- a. First Aid Team. *
- 1. Ensure that Health Physics has completed the contamination survey, if applicable, and removed the injured personnel's dosimetry prior to his leaving the site.
- 2. Notify security to assist with gate openings, traffic control, etc.
- 3. The senior member of the First Aid Team Shall assign a team member (s) to accompany the injured individual in the ambulance or vehicle to the treatment center in those instances consider-ed appropriate. CONTAMINATED INDIVIDUAi,3 SHALL BE TAKEN TO THE MEDICAL COLLEGE OF VIRGINIA IN RICHMOND - A HEALTH PHYSICS TECHNICIAN SHOULD ACCOMPANY THE INJURED IN THE TRANSPORTATION VEHICLE.
- 4. Provide Shift Supervisor with follow-up report as to treatment center used, disposition of injured party and other information
='-f"-) relevant to the accident. Call in additional information to the Shif t Supervisor or First Aid Director as it becomes available at the treatment center.
- b. Health Physics
- 1. Remove personnel's radiation dosimetry.
- 2. Survey the injured individual for contamination expeditiously as possible prior to his departure, if appropriate.
- 3. Survey the area where the injury occured, if applicable.
- 4. If the injured party is contaminated, accompany him in the transportation vehicle. .
S. Read the individual's TLD chips and Self-Reading dosimeter and record (BOTH) readings on Form HP-2, as appropriate. Notify the Shif t Supervisor of the results obtained.
- c. Sh*ft Suoervisor
- 1. If the individual is contaminated and being taken to the Medical College of Virginia proceed as applicable in Appendix
-m 8.2.2, HCV/VEPCO Nucicar Disaster Plan, of the Surry Station's
[) > Emergency Plan. l l
l EPl?-3 i c Page A of 4 AUS 2 0 373
- d. Inmediate Supervisor
- 1. Designate fornan or other responsible individual to lh accompany tehicle and to assist as necessary in providing information to treatment center personnel to assist in establishing proper duty restrictions for the individual of concern.
1.4 Injuries Occurring During Absence of First Aid Team The Shift Supervisor shall assu=a responsbility and call a local rescue Squad, if appropriate. Surry Rescue Souad - available by . rect radio through Station Security (normally the fastest means) or phone the Sheriff's Of fice 9-1-294-3156. Isle of Wight Rascue Scuad - Phone 9-357-32?7. Refer to Form EPIP 1.1 for additional telephone numbers. O O
I I
. EPIP-4 Page 1 of 2 6 .1-78
( , VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION FUEL HANDLING ACCIDE'iT 1.0 Shift Supervisor Response 2.0 Health Physics Response 4 O 9 l
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EPIP-4 Pago 2 of 2 6-21-78 FUEL HANDLING ACCIDE'TT 1.0 Shift Supervisor Response 1.1 Notify Health Physics to initiate HP response in EPIP-4,
" Fuel Handling Accident" and that operations is initiating EPIP-ll, " Estimating Release f rom Radiation Monitoring System Data".
1.2 Inform Health Physics of the location of the Fuel Handling Accident and the status of the containment perge valves. 1.3 Ensure EPIP-2 is initiated and that EPIP-ll is initiated through EPIP-2 on FORM EPIP-2.1. Health Physics Res,-msa 2.0 . 2.1 Initiate, to the extent deemed necessary, EPIP-lO, " Personnel - Monitoring and Decontamination" to evaluate the status of individuals exposed to radioactive materials resulting from this accident. 2.2 Restrict access to affected areas and initiate surveys, paying particular attention to filter banks and ventilation intakes. 2.3 Change out the particulate and charcoal filters in Vent Vent A and B as soon as feasible and initiate the appropriate RF response of EPIP-ll. 2.4 Forward release results through EPIP-2 and personnel results, as appropriate, through EPIP-10.
EPIP-5 Page 1 of 3 06-21-78 i l VIRGINIA ELECTRIC AND P0ilER COMPANY
,SURRY POWER STATION STEAM CENERATOR TUBE RUPTURE 1.0 Shift Supervisor Response
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EPIP-5 Page 2 of 3 06-21-78 _ STEM 1 GENERATOR TUBE RUPTURE _ 1.0 Shift Supervisor Resoonse_ Notify Her .h Physics to initiate H.P. Response in EPIP-5. l.1 1.2 As soon as practical, advise Health Physics of the following items. 1.2.1 Steam Generator affected 1.2.2 Personnel in Containment when Air Ejector diverted? YES NO GPM. 1.2.3 Blowdown rate prior to rupture Turbine Blag. Aux. Bldg. 1.2.4 Blowdown rout.ed to BD Tank terminated. 1.2.5 Estimated time from rupture before bicwdown trip valves closed (S1 initiation) 1.2.6 Atnospheric Power Operated Relief Valve opened on affected steam generator. NO YES _ _ 1.2.7 Main Steam Safety Valve Lifted on affected steam _YES _NO generator. 1.3 Ensure EPIP-2 has been initiated per EPIP-1 instructions. 1.4 After cooldown is completed, estimate the primary gallons of the VCT, RWST, lost to Secondary 1.e., change in levt_ BAST, Pressurizer- i 2.0 Health Physics Response 2.1 Perform appropriate surveys to determine radiological con-Pay ditions, roping off and posting areas as necessary. special attention to the blowdown heat exchangers, area near relief valve outlets and hotwell look for airborne activity and contamination.
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-4 EPIP-3 l Page 3 of 3 06-41-18
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' 2.2 Monitor any. personnel who were in' the containment when
~
Air Ejector was diverted to the Containment. U 2.3 Obtain (or request from Chemistry) samp. as of steam generator liquid and reactor coolant after the trip valves have been reopened and count for gamma emitters. ry 1 2.4 Based on surveys, count room results, and relief valve status, estimate the noble gases, radiciodines, particulates, and tritium released and report results as specified in EPIP-2. . NOTE: Initially assume that 17,000 gallons of primary coolant was lost to the Secondary. A t s 4 N L 1
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EPIP-6 i Page 1 of 3 ; 06-21-78 [h
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POUER STATION MAIN' STEAM LINE RUPTURE 1 1.0 Shift Supervisor Response 2.0 Health Physics Response
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' EPIP-6 Pag: 2 of 3 06-21-78
.s MAIN STEAM LINE RUPTUPI s 1.0 Shift Supervisor Response 1.1 Notify Health Physics to initiate 1;P Response in EPIP-6.
1.2 Advise Health Physics as soon as prace.ical as to the location of the rupture, if the rupture has been isolated, and if any MS or BD trip valve failed to close. 1.3 Initiate EPIP-2. Note: Fuel integrity may have been compromised, have Chemistry obtain coolant sample to determine status. 2.0 P--ith Physics Response 2.1 Perform appropriate surveys to determine radiological conditions, roping off and posting areas as necessary. Pay special attention to arcos downwind of break. 2.2 Initiate, to the exte.nt deemed necessary, EPIP-10,
" Personnel Monitoring and Decontamination" to evaluate the sritus of. individuals exposed to radioactive materials resulting fr om this accident.
2.3 Give the Shift Supervisor a quick estimate of I-131 released if rupture was unisolatable using the following assumptions: 2.3.1 Etcam Generator has blowdown, Primary to Secondary leah rate is 250 gpm and Primary to Secondary leakage terminated in 30 minutes, s
t f EPIP-6 Pega 3 of 3 g JUN 7 1978 , ::O 2.0 Majth Physus Response (continued) 2.3.2 The steam generator's liquid volume was 1 x 108 ds. 2.3.3 The UCi/mi dose equivalent I-131 can be obtained , from chemistry logs. l 2.3.4 10% of the I-131 in affected steam generator - P l is available for release (latest blowdown samples analyzed). 2.3.5 Insignificant noble gases are released. 2.4 If it is determined that significant activity was released (i.e. greater than 10 mrem calculated doses offsite) initiate appropriate monitoring offsite, refer ".c EPIP-16 and EPIP-17. f
2.5 Forward results as specified in EPIP-2.
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EPIP'- 7 Page 1 of 5 i NOV 211990
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I l VIRGINIA ELECTC AND POWER COMPANY _ ! t SURRY POWfR STATION LOSS OF COOLANT ACCIDENT-1.0 Shift Supervisor Response 2.0 Energency Direstor Response ,
. 3' .0 Health: Physics Response
. APP I. Containment Atmosphere Sampling O .
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i EPIP-7 Page 2 of 5 ( LOSS OF COOLANT ACCIDENT e NOTE: THIS PROCEDUFI IS TO BE USED ONLY IN THE EVENT OF A LOSS OF COOLANT ACCIDENT UHICH PISULTS IN AN ACTUATION OF CLS HI-H1 (23 PSIA) OTHERWISE, RETURN TO EPIP-1. 1.0 Shift Superviser Respons% 1.1 Notify Health Physics that EPIP-7 has been initiated and that HP is to initiate their response. 1.2 Perform the following through the indicated step in EPIP-1. Initiate EPIP-2 if nor already done (get met. (I data), Step 2.1. l Begin notkfication of all members or alternates of SUSOC, Step 3.0. Declare a Station Emergency, Step 2.2. Declare the Emergency Director position, Step 2.3. Continue with EPIP-1 at Step 4.0 " PROTECTIVE MEASi1RES" with the following considerations and the Emergency Director is then to return to this procedure. On Form EPIP 1, hpx. 5
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Indicate Radiological response as below Site Emergency. Indicate description of released material as UNKNOWN. Indicate all projected doses l UNKNOWN. Advise as additional information that a loss of coolant has occurred
EPIP-7 Page 3 of 5 V l-1.0 Shift Supervisor Response (continued) and a follow-up report will be forthcoming as soon as more data is obtained. (all other information on Form EPIP-1.2 should be entered as appropriate). 2.0 Emergency Director Response 2.1 ]g[ any one of the following circumstances should occur during the first two hours following the LOCA, declare General Emergency in all sectors, Surry County, zones 1 through 2; declare all sectors and zones 1 through 10 as Site Emergency;deel are General Emergency in the three downwind j
^
sectors, zone 1 through 6.
; .)
CIRCQ STANCES REQUIRING REACTION 2.1.1 Sustained loss of both (energized) emergency busses. 2.1.2 Containment pressure exceeding 55 psia. 2.1.3 Sustained loss of both low head safety injection pumps. 2.1.4 Sustained loss of service water to recire. spray heat exchangers. 2.1.5 Sustained loss of at least three recirculation spray pumps. 2.1.6 RWST level greater than 50% more than 1 hour after LOCA. 2.1.7 liigh Range Gamma Monitor Reading greater than 1000 R/hr. s_-
r-- 1 EPIP-7 Page 4 of 5 JUN 7 573 2.0 Emergency Director Response (continued) 2.2 Keep offsite agencies advised on the course of events, as appropriate, through EPIP-1. 3.0 Health Physics Response 3.1 The senior Health Physics representative on site is to initiate f.o the extent possible this portion of this procedure upon notification by the Shif t Supervisor that EPIP-7 has been initiated. The steps are listed in order of preference based on manpower available. 3.2 Start an air sampler for particulates and radioiodines in the HP office, turn on a high range survey meter, contact at least one HP tech. offsite and give the names and phone numbers of all other HP Techs not presently on sitc and instruct him to contact those techs, to im=ediately report to work . O 3.3 Obtain copies of EPIP-10 " Personnel Monitoring and Decon-tamination" and EPIP-18 " Emergency Exposure Criteria" and begin preparations to initiate these procedures. 3.4 Initiate EPIP-16 "Offsite Air, Contamination and Radiation Monitoring". Obtain wind direction and speed from FORM EPIP 2.1 or from operations and instruct the monitoring teams such that they will sample at least three locations downwind and radio the results in. They are to take an he a,ergency kit and are not to return to the station, but are to remain near the selected locations and await further instructions. NOTE: Establish radio communications between the monitoring team and a hand held radio in the RP Office prior to
, the team leaving the site.
. J gprp_7 l Page 5 of 5 JUN 7 1978 Health' Physics Response (continued) i 3.0
- n. 3.5 Initiate EPIP-13 " Estimating Release from Offsite Radiological Data".and prepare to estimate the release based on Radiogas Radiation Levels or Contamination Rad'.ation Levels as the situation warrants upon receiving data from the monitoring team.
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,2 NOV 211980 ,
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t i 4 i i r 1 4 f, - , i s I HEALTH PHYSICS RESPONSE $ APPENDIX I i . ] h. t POST ACCIDENT , CONTAINMENT ATMOSPHERE SAMPLING f - 1 i- ) 4 I f 4 i t 4
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E7L2-7 APX-1 PAGE 2 of 4 NOV 211980 0 A. REFERENCES Letter f rom the U.S.N.R.C. , October 30, 1979,
SUBJECT:
Discussion of lessons learned short term requirements. B. CENERAL 1.0 Purpose 1.1 This procedure provides a means for obtaining a reactor coolant sample in a post-accident condition, which will allow and in-dividual to draw the sample without incurring a radiation exposure in excess of 5 and 18 3/4 Rems to the whole body and extremeties, respectively. 1.2 This sample is for analyzation to provide information related to the extent of core damage that has occurred or may be occurring during an accident. 2.0 Initial Conditions 2.1 Ventilation System is operable per OP-21. 2.2 Radiation Monitoring System is operable per OP-56. 2.3 Operating conditions indicate possible fuel core damage. 2.4 The containment atmosphere sample panel is located on the 27' 6" elevation of the Auxiliary Building adjacent to the elevator entrance. 2.5 contact operations to have flow initiated to the sample panel. 3.0 Precautions and Limitations 3.1 Note the dose rate reading on radiation monitor RMS-154A prior to entering the Auxiliary Building. 3.2 The " Buddy System" will be utilized for entry into the Auxiliary Building and the sampling crew will utilize a high range dose O rate instrument ( 0-1000 R/RR), Change No. 18
e: EPIP-7 APK-1
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PAGE 3 of 4 'f
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NOV 21 H50 _ f' 'y
'+ 3.0 ' Precautions and Limitations (continued) '
3.3 Pull protective clothing will be worn while obtaining the sample. 3.3.1 ' Righ and low range dosimetry will be worn. 3.3.2 Extremity TLD will be worn on the wrist, head and ankles. 3.3.3 Full f ace fresh air respirators with fresh air bottles will be worn.
~ 3.4 Stay- times may be utilized based on readings taken prior to and t
during sampling. 3.5 Sampling apparatus, consiscing of a vacuum pump (optional D.C". power) two sections of Tygon Tubing with quick disconnects, and a 5 ce gas
~ bomb, is located in the Counting Room.
3.6 After sample is collected, handle it with extreme care to avoid unnecessary exposure. Remote handling tools and a mobile shielded box are available to transport gas bomb to hot lab for analysis h preparation. C. PROCEDURES 1.0 Sampling Unit #1 Containment Atmospher_e 1.1 Assure that sampling apparatus is assembled as per Attachment 1 and valves on gas bomb are open prior to entering Auxiliary Building.
' 1.2 Insert open end sample hose over the drain line at right bottom of panel, CW-103 (See Attachment 2).
1.3 Open drain line valve for GW-103. 1.4 Turn on vacuum pump. 1.5 Allow several seconds for, gas bomb to completely purge. !- Close valves ' and disconnect gas bomb via quick disconnects.
' 1. 6 r-
- 1.7 Close drain line valve for GW-103.
l
-1.8 Turn off vacuum pump i
Change No. 18 L-- 1 i;
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r-EPIP-7 I APX-1 I PAGE 4 ef 4 NOV 211c20 } l 2.0 Sampling Unit #2 Containment Atmosphere 2.1 Same as 1.0 Above except use GW-203. 3.0 sample Preparation and Analysis 3.1 Extract I cc of gas from the gas bomb and inject into a clean 100 ce gas bomb. 3.2 Now extract 1 cc from the 100 cc bomb and inject into another clean 100 ce bomb. This will give 1 : 10,000 dilution. 3.3 Count sample on multi-channel analyzer as per H.P-3.4.13. 3.4 If sample is too hot, i.e. dead time >10", repeat step 3.2_with a third clean 100 ce gas bomb. This will give a 1 : 1,000,000 dilution. 3.5 Recount sample on multi-channel analyzer as per H.P.-3.4.13. O O Change No.18 .
EPIP - 7 Apx - 1 Cg
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CONTAINMENT AINOSPr 6RE SAMPLING APPARATUS NOV 211980 i 4 l Vacuura Gas Bomb PunrP Q AC or DC
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Quick Disconnects O i
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Apx - 1 Attech::nt 2 NOV 21 1980 ( CONTAINMENT AIMOSPRERE SAMPLING __ PANEL g Unit-#1 Unit #2 GW - 103 GW - 203 O @ 0 . Sample Connections O V Samp' a Return . Valves Sample Supply Valves i h4 DRAIN 'IINE VALVES T
' - DRAIN LINES Unit #1 Unit #2 Sample Point Sample Point O:
- Not Used For Containment Atmosphere Sampling Change No. 18
EPIP-8 Page 1 of 5 JUN 7 1973 VIRGINIA ELECTRIC AND PoliER CO'eANY SURRY PO;JER STATION
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EVACUATION AND ACCESS CONTROL ONSITE 1.0 Onsite Evacuation 2.0 Onsite Access Control (O e O
EPIP 8 j . Paga 2 of 5 8-22-77 EVACW TTC'I AMD ACCESS CONTROL ONSITE Onsite Evacuation (After I. countability) G,-
, 1.0 1.0.1 Emergency Director /Emercency Coordinator 1.0.1.1 Inform the Sheriff of Surry County to set up a road block at the Remote Assembly Area.
1.0.1.2 Have Form EPIP 8.1 completed indicating the names of those o indfviduals who are to remain onsite during the emergency. 1.0.1.3 Inform each department supervisor of the individuals from his section who are to remain onsite and where they are to assembic for further directions. 1.0.1$4 Inform Security that station evacuation is imninent and to place in the access mode the Service Building Co. ridor ~
- catranec/ exit door and the Security Building door. Also open the motor controlled gate by the Security Building.
Dispatch a guard to the Remote Assembly Area. 1.0.1.5 llave announced over the Gaitronics system, while intermittently sounding the emergenc'; alarm, the following: " Station Personnel l
. not responding to the emergency evacuate to the Remote Assembly Area". Repeat several times. If radiological conditions pre-clude evacuation to the Remote Assembly Area, inf orm station personnel to the extent possibic advising them of the necessl (
precautions to be taken. o ' 1. 0.1. 6 Assign individuals to assist in the evacuation. L ju. ?. 1.0.2 Department or Section Suoervisor/ Foreman 1.0.2.1 Maintain strict control of those personnel ur. der your super-vision. 1.0.2.2 Inform such personnel evacuation may be necessary and each individual should:
- a. Ensure his dosimecry is worn at all times.
- b. Await the evacuation ANNOUNCEMENT. '
- c. Evacuate from the station to the parking lot rapidly and orderly bypassing portal moniters and station security.
- d. Proceed to the intersection of Routes 650 and 617, the Remote Assembly Area. Vehicle windows and vents should '
remain closed with air conditioners / heaters off. NO ONE Sil0ULD RIDE IN TIIE BACK OF AN OPEN TRUCK. 1.0.3 Station Personnel - Not Responding to the Emergency ls 1.0.3.1 Remain orderly - assume evacuation is imminent. l.0.3.2 Listen to supervisor's/ foreman's comments. p.
1: EPIP 6 Page 3 of 5 1.0'.3.3 AFTER evacuation ANNOUNCEMENT, rapidly proceed to t e D v parking area, bypassing portal monitors and security G personnel. DO NOT REMOVE RADIATICN DOSIMETRY - WEAR IT AT
.ALL TIMES.
1.0.3.4 Proceed to the Remote Assembly Area, the intersaction of Route 650 and 617 (see Figure 1). Vehicle windows and vents should remain' closed with air conditioners / heaters off. 1.0.3.5 Await in vehicle'for further directions. 1.0.4. Sta tion Security Personr.el 1.0,4.1- Assume evacuation is imminent and await Shif t Supervisors instructions. 1.0.4.2 Prepare to send one or more guards to the Remote Assembly Area with portable communication unit (s). 1.0.4.3 As per the shif t supervisor's instructions, place in the
" access mode"'the Service Building Corridor entrance / exit door and the Security Building door. Also open the Motor Control Gate.
1.0.4.4 Send guards (with protective clothing and respirators, iodine cannisters.if available) to the Remote Assembly Area as per the shift supervisor's instructions. 1.0.4.5 Allow station personnel to bypass pertal monitors and security (_ (~)N when exiting station. 1.0.4.6 Have guard (s) at Remote Assembly Area assist police in traffic control. Individuals shall remain in vehicles and avait further directions. Evacuation from the Remote Assembly Area shall be by Surry County Officials. 1.1 Onsite Access Control 1.1.1 Security Guard at Remote Assembly Area 1.1.1.1 Any individual desiring station access beyond the Remote Assembly Area must have proper identification or be recognizable by station personnel at' the assembly area. 1.1.1.2 Communications must be established between the Security Guard and station management and approval granted before the individual is allowed beyond the assembly area. < 1.1.2 Etcurity Building Guard (s) 1.1.2.1 Access to the Station shall be by normal security procedures. V
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EPIP-9 Page 1 of 9
> NOV 211930 l
VIRCINIA ELECTRIC AND POWER COMP __AN_Y SURRY POWER STATION PERSONNEL ACCOUNTABILITY . d (O 8 t i t j L/ s
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EPlP-9 Page 2 of 9 APR 3 0 '93 PERSONNEL ACCOUNTABILITY , 1.0 Ceneral a) When the Emergency Signal is sounded, Plant Operations Personnel with portable loudspeakers shall be dispatched to the following areas:
- 1. #1 and/or #2 Containment (a) 47'-4" Level (around annulus)
(b) 18'-4" Level (around annulus , A&B cubicles) (c) -3'-6" Level (A, B, & C cubicles) (d) -13' Level (e) -27'-7" Level (around annulus) Note: Necessary only if Unit is not operating and personnel are known to be in containment.
- 2. #1 and #2 Safeguard Buildings (all levels) t
- 3. Auxill.ary Building (all IcVels) . ,
- 4. #1 and #2 Turbine Buildings (all icvels)
- 5. Service Building. ,
(a) 58'-6" Level (b) 27'-0" Level (Diesel Rooms , Laundry) (c) 9'-6" Level And shall warn all personnel present in these areas by announcing the following message:
"The E=ergency Signal has been sounded-report immediately to the area where your work day begins".
b) No individual shall remain outside immediately af ter the Emergency Sig-nal is sounded. Such personnel shall rapidly take cover in the following building nearest their work location: Low Level Intake Building, Switch-
- yard / Gas Turbine Buildings, Biologist's Building, South Annex, Security Building, Administration Building, Turbine Building, Auxiliary Building, or Training Building.
c Change No. 15
EPIP-9 4 Pcg2 3 of 9 NOV 211980
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). c)
Personnel including contractural, shall, with the exception of the above,
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report to those arecs where their work day begins. d) Personnel shall not evacuate the station site during the accountability phase of the Emergency (Evacuation shall be announced if such is deemed necessary), e) Signs shall be posted in the Low Level Intake Building Switchyard / Gas Turbine Buildings and Biologist's Building indicating whom they are to notify for accountability purposes during the emergency. f) Ventilation shall be secured and all windows and doors closed in those buildings containing personnel to the extent practicable. g) Each department supervisor shall send a representative to the Cafeteria R to report those individuals missing or unaccountable.O_R to report all accountable. (The Supervisor, Engineering Services and Resident QC Engineer
~N will call Security.)
(V Alert Warning
-1.1 Shift Supervisor-Af ter Station Emergency 1.1.1 Have announced intermittingly on the intercom the following:
"Staion Personnel Take Cover-Follow the Accountability Procedure for Emergency Conditions.
Remain inside, Secure Ventilation, Shut All Doors and Windows". 1.1.2 Secure as much ventilation as feasible. 1.1.3 Account for shif t operating personnel, other opera *1on personnel re-port to the onsite operations Support Center (Emergency Switchgear Roo for accountability) . complete form EPIP-9.2. 1.1.4 Dispatch an individual to the Cafeteria to 1.1'. 5 Dispatch a team, in protective clothing with respirators (iodine removal cannisters) to Hog Island to warn those individuals working /living on h~.q__ the Game Reserve. i Change No.18 l M we #
l s EPIP-9 Page 4 of 9 APR 3 0 390 O
.[ 1.1.6 Account for all on-site individuals.
1.1.7 Dispatch " search teams" if applicable. 1.2 Supervisor, Health Physics, Che=istry Supervisor, Supervisor of Electrical Maint enance , Supervisor Mechanical Maintenance, Instrument Supervisor or Their Designated Appointee 1.2.1 Obtain the names of all individuals under your supervision, including contractural personnel, WHO ARE MISSING OR UNACCOUNTABLE. 1.2.2 Proceed to the Cafeteria and give the list of those personnel unaccount-able to the individual in charge of "Acccantability" or report all accountable. 1.3 Supervisor, Engineering Services, Training Coordinator, and Biology Supervisor or Their Designated Appointee
- 1.3.1 Ensure that all building vaatilation is secured and all windows and doors shut. gg 1.3.2 Obtant the names of those individuals in the building who do not normally work there.
1.3.3 Obtain the names of those individuals who repo: ted to work but are presently unaccountable. 1.3.4* The Quality Control Engineer, Records Clerk in Charge and Nurse. 1.3.4.1 Ensure that area ventilation is secured and all windows and doors are shut. 1.3.4.2 Obtain the names of those individuals in the area who do not normally work there. 1.3.4.3 Obtain the names of those individuals whu reported to work but are presently unaccountable. 1.3.4.4 Forward the list of names to the Supervisor, Engineering Services or his Appointee. 1.3.4.5 Avait further directives. Change No.15
l
. EPIP-9 Pcga 5 of 9 PhDV 211980 79 v.2 individuals
~
' .1.3.5' . Call Station Security and give ' them the names of those
' obtained in steps 1.3.2 and 1.3.3 above or, inform them that all personnel are present and accountable.
1.3.6 Remain in the building and swait further directives.
- 1. 4~
Personnel Normally Reporting to Work in the Administrative Building or Service Building and Present -in Such_
- 1. 4.1' LReport to work area where work day begins.
1.4.2 Innnediate Supervisor 1.4.2.1. Obtain the names of those individuals under your supervision (including contractual) who are missing or unaccountable. 1.4.2.2 Porward list of names to department supervisor or his de-signated appointee. 1.4.3 Remain in area and await further directives. () 1.5 Persor.nel in the Restricted Centrolled Area Proceed to the Personnel Change and Decontamination Area. 1.5.1 1.5.2 Monitor for contamination (decontaminate if feasible). 1.5.3 Proceed as in step 1.4 above. 1.6 Personnel in the Administration Building, Turbine Building, Service Building, or Auxiliary Building who do NOT Normally Begin Their Work Day in Such
#1 Turbine Building for accountability 1.6.1 Report to the basement of Unit purposes.
1.7 Individuals in the Low Level Building or Switchyard / Gas Turbine Buildings _ 1.7.1 Ensure that all building doors and windows are shut. 1.7.2 Call Station Security giving them your name and area location. 1.7.3 Await further directives. 1.8 Station Security Supervisor or Designated Appointee i 1.8.1 Secure building ventilation and ensure all windows and doors are r shut. Dispatdt an individual to the Cafeteria to take charge of
" Accountability" and to complete Form EPIP-9.2 Change No.18
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r EPIP-9 Paga 6 cf 9 NOV 211980 e l' Obtain the names of all individcals under your supervision who are 1.8.2 missing or unaccountable and log on Form EPIP-9.1. 1.8.3 Obtain the names of all individuals in the building who do not normally work there and record on Fora EPIP-9.1. 1.8.4 Record on Form EPIP-9.1 the names given by the Supervisor, Engineering Services, Training Coordinator, Biology Supervisor, Individuals in the Low Level Building and Switchyard / Gas Turbine Buildings. 1.8.5 Check Form EPIP-9.1 for those individuals listed as being unaccount-able against those individuals being in a building where they normally do not work. Strike through the names of those individuals who have thus been determined accountable. 1.8.6 Forward the completed Form EPIP-9.1 to the Cafeteria and present it to the individual in charge of " accountability", and assist with G accountability. 1.8.7 Remain alert (assume site evacuation is pending) and await further directives. 1.9 Emergency Committee Members 1.9.1 Report td the onsite Technical Support Center (control room annex) .
# Report the results of accountability to the Shif t Supervisor as soon as .
possible. . 1.10 Health Physics 1.10.1 Assist in monitoring and decontamination of those individuals in the Personnel Chenge and Decontamination Area.
'1.10.2 The Senior Health Physics Representative (H.P. Supervisor Health Physicist, Assistant H.P. Supervisor or H.P. Technician) shall dispatch an individual to the control room annex.
O Change No.18
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EPIP-9 Page 7 of 9 APR 3 0 1980 gU ?~'T -
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?; . 1'.11 First Aid Team and Fire Brigade
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1.11.1. Af ter reporting for accountability, report to the staging assembly area. (Do not leave a protective building unless told to do so).
- 1.11.2 Remain alert and await further directives.
1.12 Individuals in Charge of AccountabMity
- 1.12.1 Complete Form EPIP-9.2.
1.'12.2 Compare For EPIP-9.1 with Form EPIP-9.2 accounting for as many
. individuals as possible.
1.12.3 Forward list to Shif t Supervisor and indicate who is missing or unaccountable.
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- l. 1 l Change No. 15 i
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r a F m EPIP-9.1 Pcg3 8 of 9 NOV 211980 ACCOUNTARILITY
,BY STATION SECURITY _
-DATE: _19 h
Security Staff;. ( ) All Accountable ' Personnel Unaccount_ ble a Personnel in Building
- _
l l l ( ) Engineering Dept; __ South Annex - All Accountable: ( ) Q. A. Dept. ; ( ) Station Records; ( ) Nurse Personnel Unaccountable Personnel in, Building
- l' I
I _ _ _ ( ) Biologists Biology Building - All Accountable : Personnel Unaccountable Personnti in. Building *
/
19 J Training Building: ( ) All Accountable ' Personnel L*taceountable Personnel in, Building
- 1 m_
l' _ i Switchyard / Gas Turbine Buldings Low Level Intake Building Personnel in Building
- Personnel in Building
- l l-t Beginning
- Personnel in Building M Nomally Reporting to Area a of their Work Day.
O Change No. 18
+ _-, . , -Form EPIP-9.2 I
' ~ ' ' SbY 21 1980 l ACCOUNTABII.ITY_
I -
;;f}' BY STATION SECURI_TY 'DATE 19,_
- v~ 7"'
l [IAdividuals' Reporting to Turbine Building Basement Who Work Day In The Admin. or Service Bldg. Names of Individuals Present L ( ) All Accountable ble
- Mechanical Mainterece Dept. Names of Personnel.Unaccounta H
-I __
i 2 i __ ( ) All Accountable _ Electrical Mainterance Dept. Names of Persoenel Unaccountable l I J l__ i ~ l ) _
.- -Operations Dept. ( ) AllNames Accountable of Personnel Unaccountable I -
l ._ 4 (- ) All Accountable Chemistry - Health Physics Depts. Names of Personnel Unaccountable ._ _ I t I! ( ) All Accountab0 < j
'- Instrument - Adminsitrative StaffsNames of Personnel Unaccountable i
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l' Change No.18
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EPIP-10 7 Page 1 of 5 $ JUti 7 1973
'is i
VIRGINIA ELECIRIC AND POWER COMPANY SURRY POWER STATION t PERSONNEL MONITORING AND DECONTA'fINATION 1.0 Implementing EPIP 10 2.0 Injured or Overexposed Personnel 3.0 Personnel lianitoring - External 1 4.0 Personnel Monitoring - Internci 5.0 Personnel Decontamination m Appendix 1, Personnel lionitoring and Decontamination - Significance and Evaluation Appendix 2, Blank Forms EPIP 10.1, Emergency t~ rker Radiological Exposure Record
7"*"" h EPIP-10 t Prge 2 of 5 JUN 7 1373 PERSONNEL MONITORING AND DECJNTAMINATION 1.0 Implementing EPIP-10 1.1 EPIP 10 uses routine personnel monitoring and decontamination techniques which are carried out under non-rout!.ne situations and will require careful dose control methods and evaluation along with certain non-routine record keeping. 1.2 EPIP 10 is initiated by EPIP 3, Injured Personnel, or EPIP 18, Emergency Exposure Criteria, but may be initiated at any time by the Emergency Coordinator or Director. 1.3 Health Physics has the primary responsibility in insuring this procedure is carried out to the extent necessary. < l.4 As used in this procedure, Health Physics Technician (HP Tech) implies any member of the HP staff at the Station.
- 1. 5 A completed Form EPIP 18.1', Emergency Exposure Authorization, should be received from the Emergency Director er at least a verbal authorization prim: to issuance of dosimeters for ex-posures in excess of 10CFR20 limits.
1.6 Evaluate the applicability of Appendix 1, Personnel Monitoring and Decontamination Significance and Evaloation, of this pro-cedure.
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EPIP 10 Page 3 of 5 JGi 7 WhL 2.0- *njured or Overexposed Personnel
)s-2.1 At least one RP: Tech. with an RM 14 meter with HP210 probe or equivalent, is to report .'.o - the scene of the injured
' person;to monitor-for contamination and assist in first aid if required.-
2.2 If the injured person has a self-reading dosimeter, observe its reading as a quick indication if.an overexposure is likely to be involved.
'2.3 If the injured individuals clothing to which the dosimeter (s) are attached has been or is going to be removed, attach, somehow, the dosineters to the individuals bcdv until he is to leave the station.
~2.4 If the injured person (s) were working in a Restricted Control Area- and they are to be sent for medical treatment,
(~%v) read their TLD badges as soon as practiccble. 2.5 Necessary first aid is to take p. tity over personnel decontamination efforts. 2.6 If a contaminated injured person must be sent to the hospital, a Form HP-3, Personnel Decontamination Record, is to be filled out and a copy of the Form is to accompany the in-dividual. Someone with Health Physics knowledge should also accompany the individual and fresh dosimetry provided to all individuals in the transport vehicle. 2.7 If an individual is potentially overexposed and EPIP 18 has not been initiated, determine the extent of the overexposure and forward the results to their immediate supervisor. Note j the reporting requiremect of 10CFR19 and 10CFR20 concerning
\' 'i
~
overexposures.
- T
EPIP 10 Pcg7 4 of 5 JUN 7 1976
,, 3.0 Personnel Monitoring - External 3.1 Initiate a Form EPIP 10.1, Emergency Ucrker Radiological Exposure Recor;;, for each individual obtaining emergency dosimeters' (blank forms are in Appendix 2, this procedure).
Do not use the computer basad monitoring system except as a backup, if desired. 3,2 Issue an additional TLD badge to each worker. ENSURE THERE ARE TLD CHIPS IN EACH BADGE PRIOR TO ISSUNICE. 3.3 If supply permits, issue two high range dosimeters alang with the TLD badge. 3.4 Instruct individuals they must leave an area when told to do so by a HP Tech., regardless of the circumstances. 3.5 As emergency workers exit from exposure area, read self-e readers and TLD badges, if possible, and record results on their Form EPIP 10.1 and if it is estimated they have exceeded 3 rem total for the current quarter, advise the Emergency Director of the dose received. 4.0 Personnel Monitoring - Internal 4.1 Monitor workers as they exit for en ernal contamination and if found around nose, mouth, throat or chest, suspect internal contamination, (monitor for internal contamination as per procedure HP-3.10-3). 4.2 Af ter all removable exterrul contamination has been removed, supply clean clothing to the individual and whole body count using procedure HP-3.1-15. Whole Body Counter Operation if applicable. A full 10 minute count may not be required in which case the estimated body burden must be prorated based on actual counting time.
(? s EPIF-10 Page 5 of 5 b Juri 7 578
- 4.O' Personnel Monitoring : Internal (continued) )
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~ ~,z If the whole body counter is not available or usable and is ~
14.3. expected to remain so.for more than 5 hours and the individual has external radiation levels greater than 5 mR/hr e7 contact.
- send him to the North Anna Power Station for counting or to MCV Hospital in Richmond for evaluation if the North Anna counter is not available.
4.4 Advise'the Emergency Director of results. 5.0 Personnel Dect.7tamination 5.1 Decontaninate : individuals as given in the Health Physics Manual,.Section 2.4.c, Decontamination Procedures. 5.2 - Record reralts on Form HP-3, Personnel Decontamination Rece,d.
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PERSONNEL MONITORING AND DECONTAMINATION A"PENDIX 1
' PERSONNEL MONITORING AND DECONTA!!INATION-SIGNIFICANCE AND EVALUATION Part Subj ect 1 -- Personnel Monitoring' 2 Personnel Decontamination
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I EPIP-10 APX 1 Page 2 of 3 JUN 7 1978 1.0 Personnel Monitoring 1.1 High range dosimeter dose estimates may vary from the response of the TLD Badge by as much as 25 percent. 1.2 Exposure rates indicated by portable survey instruments may be in error by as much as 35 percent. 1.3 Checks of the following, as applicable, should be considered:
- a. All available high range dosi=eters located.
- b. All available high range survey instruments located.
- c. Several friskers and probes placed in poly Sags to prevent possible contamination.
- d. Extra TLD Badges ava116 a with blank identification for marking as needed.
- e. Whole body counter operational.
1.4 If the general area of the HP Office has radiation levels in excess of 100 mR/hr, place a supply of TLD chips in the annealing oven or behind lead bricks to minimize residual doses on chips when issued. 1.5 The manual TLD reader may be removed to another location if appropriate for personnel monitoring. Nitrogen will not be necessary since exposures can be expected in the high millirem range. 1.6 10CFR20 requirements concerning overexposure to individusis are given below. HP is to advise the Emergency Director or Coordinator accordingly. 10CFR20.403(a): Immediate notification by telephone and telegraph, mailgram, or facsimile, to URC Region II if either: Whole Body Exposure Exceeds........ 25 rem Skin Exposure Exceeds ............. 150 rem Extremity Exposures Exceeds........ 375 rem
~
;c EPIP-10
- APX 1 Page 3 of 3 i Personnel Monitoring (continued)
JUN 7 373
/"'r .l.0 v /' 10CFR20.403(b): Twenty-four hour notification by telephone f and telegraph, mailgram oc facsimile, to NRC Region Il if either:
Whole Body Exposure exceeds...... 5 se.: v.
-Skin Exposure exceeds .......... 30 rem Extremity Exposure exceede ..... 75 rem
-10CFR20.405: Requires 30 day reports on any exposure exceeding 10CFR20 limits - see 10CFR20 for detalls.
1.7 See 10CFR19 for reporting overexpusures to individuals.
- 2.0 - Personnel Decontamination i
2.1 The decontamination materials used for personnel decon-tamination, need to be readily available. Some e,hould also be placed in poly bags fer possible transfer to another location.
.b v 2.2 Blocking agents (such as a 100 mg NaI or KI tablet *) are of some value after exposure to radiciodines to reduce thyroid doses if administered shortly after the exposure.
*Seven (7) drops of a satu ated solution may be administered to the individual as a substitute, are approximately of the same value.
u
( 4 EPIP-10 APX 2 i Page 1-of 2 l i
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I i
' PERSONNEL MONITOKlNG AND DECONTAMINATION APPENDIX 2 l d
..q-. BLANK FORMS EPIP 10.1 4 ,
.$ . t j . . . } ' EMERGENCY WORKER RADIOLOGICAL EXPOSURE RECORD i
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FORM EPIP 10.1 APX 2 Page 2 of 2 JUN 7 7973 EMERGENCY WORKER RADIOLOGICAL EXPOSURE RECORD NAME: AGd: YEARS LAST FIRST MID. INIT. Soc. Sec. No.: : Current Quarterly Exposure: rem Authorized Emergency Exposure: rem Authorized By (Form EPIP 18.1): Name: at hours. On Date: 19 . NaI administered time Date By SELF-READING DOSIMETER RANGE STARTING R7ADING J STOP RvADING < DOSE - INTEGRATED BY ROENTGEN R TIZE DATE R TIME DATE R DOSE R INIT.
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I TLD BADGE NO. NO. CHECK (/) DOSE INTEGRATED dY ISSUE READ TILE DATE REM DOSE /REI LOCATION (S) INIT. I O
m' c EPIP-ll Page 1 of 4 FEB 0 2 1730 VIRGINIA ELECTRIC AND POWER COMPA'.T SURRY PO'nT.P. STATIO'i ESTIMATING PILEASE FROM RADIATION MONITORING SYSTEM DATA 1.0 Operations Response 2.0 Ecalth Physics Response Appendix 1, Significance and Evaluation of Release Estinates Based on Radiation Monitoring System Data Appendix 2, Blank Forms EPIP 11.1, RMS Release Data Worksheet i Appendix 3, Determining Release Rates and Dose Rates Using the Interim High Range Ef fluent Monitors on Main Stean, Process Vent, and Ventilation Vent Systems ( Appendix *4, Flow Rate Determination
,m EPIP-11 8-22-77 Page 2 of 4 ESTIMATING PSLEASE FROM PADIATION MONITORINO SYSTE't DATA ? 1.0 Operations Response 1.1 Obtain, from Appendix 2 of this procedure, a FORM EPIP 11.1, "RMS Release Data Workshct1". 1.2 Obtain the count rate of the monitor of interest from the radiation system panels as appropriate, and enter the monitor type (or number) and the count rate in CPM which is to be evaluated on FORM EPIP 11.1. 1.3 Obtain from Table EPIP 11.1, "Respor=e of Potential Release Path Radiation Monitors", the Ci per Hr Reloased per CPM value and the Selected Flow Rate for each monitor of interest and enter on FORM EPIP 11.1. I 1.4 Obtain, by appropriate methods, the flow rate of the path being monitored (in the same units as entered on FORM EPIP 11.1) and enter on FORM EPIP 11.1. If this is not practical or desired, a " default" value equal to the Selected Flow Rate (design) may be used, g 1.5 Perform the indicated math to obtain the gross curies of ac-tivity indicated as being released per hour. The total amount of activity released can then be estimated based en the known or expected time duration of the release. 1.6 Use these results for preliminary evaluation, forward the completed FORM EPIP 11.1 to HP for use in determining the need for further monitoring. The release data to initiate any offsite action will come from HP on a FOFO! EP!? !.l.
~
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8-22-77 Page 3 of 4'
.,. ;~ C, 2.0 ' ' Health Physics Response T. 2.1- If a release point has a continuous in line radiation sampler (such as process or ventilation) vent, remove the filter (s) and/or obtain a sample (s) and count using the appropriate count room equipment.
2.2 If the filter removed or the sample taken will affect the routine records of the Power Stations radioactive affluents, use the appropriate Releese Record as described in the 3.2 series of HP Procedures concerning radioactive wa'ste and cal-culate the release ac=ordingly. 2.3 Based or the information shown on FORM EPIP 11.1, determine the need for obtaining additional samples or other monitoring. ( A)^s I t L I .. r s_. V
EPIP-11 I 9-14-77 Page 4 of 4 4 TABLE EPIP 11.1 ( ** RESPONSE OF POTENTIAL FMASE P ATH FMIA"' ION MONI'IORS g LCi/ml SELECTED Ci per Hr Released REFERENCE CPM FIDW RATE CPM MONITOR
- NUCLIDE Cs-137 1.4 E-8 50 GPM 1.6 E-7 SGBD .
Cc-60 2.2 E-9 8.4-E + 5 GPM 4.3 E-4 Darun 1.0 E-8 18,000 GPM 4.1 E-5 CCWSW I-131 1.0 E-8 6,100 GPM 1.4 E-5 RSCSW I-131 LW Co-60 3.8 E-0 60 GPM 6.9 E-7 . Xe-133 2.5 E-7 300 CFM 1.3 E-4 PVG PVP I-131 1.15 E-12 300 CFM 5.9 E-10 2.5 E-G 1.2 E + 5 CFM 5.1 E-j VVG Xe-133 VVP l-131 1.15 E-12 1.2 E + 5 CFM 2.3 E-7 C .*.E Xe-133 1.21 E-5 26 CFM 5.3 E-4 0
*SGBD - Steam Generator Blowdown: SS-ll2, 113, 212, 213 DsTun - Discharge Tunnel Liquid SW-120, 220 CCWSW - Component Cc: ling Water Hx Service Water SW-lO7.
RSCSW - Recire. Spray Cooling Service Water Outlet: SU-114, 115, 116, 117, 214, 115, 216, 217 LU - Liquid Uaste Discharge: LW-108. PVG - Process Vent Radiogas: GW-102. PVP - Process Vent Air Particulate: GW-101. VVG - Ventilation Vent Radiogus: VG-104 VVP - Ventilation Ven't Air Particulate: VG-103. CAE - Condenser Air Ejector Radiogas: SV-111. 211 , O
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EPIP-il 8-22-77 APX 1 Page 1 cf 2
~
) l ESTIMATING RELEASE FROM PADIATION MONITORING SYSTEM DATA APPENDIX 1 l
l. l l' l i. SIGNIFICANCE AND EVALUATION OF RELEASE ESTIMATES l i BASED ON RADIATION MONITORING SYSTEM DATA l i l' Part Subject l t i 1.0 Consideration on the RMS i lO- 2.0 Estimating Release of Airborne Activity Exceeding Monitor's Range i S l t L 4
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EPIP-11 8-22-77 APX 1 Page 2 of 2 O
. 1.0 Considerations on the RMS The detectors in the RMS respond to gross activity ar.1 for this reason the response of the monitor must be interpreted using know-ledge of the system involved. For instance, liquid monitors will detect any gamma emitters, which includes dissolved radiogases which do not necessarily present the radiation hazard the monitor could be implying.
Air particulate monitors have detectors which are NaI scintillation devices and therefore count essentially only gamma emitting parti-cles. It should not be assumed radioiodines can be collected and counted on the filter paper. Air radiogas monitors have relative thick (30 mg/cm ) walled G-M detec' tors, and therefore have a much lower efficiency for weak beta emitters, for instance the Xe-133 cpm /uci is more than 10 less than that for Kr-65. O The electronics used in the RMS are designed in a manner which should prevent a meter from reading low even if that channel's G-M dets. is in continuous discharge. 2.0 Estimating Release of Airborne Activity Exceedine Monitor's Range If activity collected by the monitor results in full scale reading the activity released can be estimated by count room methods as described in Step 2.0 of this procedure or if a quick estimate is considered essential the following method may be usea. Measure the dose rate one foot frem the actual collection point of the monitor. Estimate the curies released using the following equatica. Ci = 0.00024 x Ebhr x CFM of Sampling Rate
6 EPIP-11 8-22-77 APX 2 Page 1 of 2 r O- . . ESTIMATING RELEASE FROM RADIATION MONITORING SYSTEM DATA
.I APPENDIX 2 i
t i BLANK FORMS EPIP 11.1 r P RMS RELEASE DATA WORKSHEET O 4 I l J G l r. I 9
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FORM EPIP 11.1 8-22-77 Page 2 of 2 PMS RELEASE DATA WORXSHE Q Cate/ Times . + Ci per Hr RELEASED SELECTED ACTUAL Ci ter Hr CPM FLOW RATE FIDJ PATE RELEASED MONITO'A CPM
=
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=
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=
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+ X =
- X
=
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i Ci per Hr Estimated or Known Estimated Curies Number of Hours of Release Released Released X X X X X X i O
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EPIP-11 API-3 Page 1 of 10 g FEB 0 21980 ESTIMATING RELEASE FROM RADIATION MONITORING SYSTEM DATA APPENDIX 3 DETERMING RELEASE RATES AND DOSE RATES USING THE INTERIM RIGH RANGE EFPLUENT MONITORS ON MAIN STEAM, PROCESS VENT, AND VENTILATION VENT SYSTEMS PART SUBJECT. 1.0 Release Estimation Procedure p 2.0 Release Concentration Data Graphs Figures la,1b, ic, Units 1.& 2 Main Steam Safety Relief Lines Figures 2a,2b, 2c, Units 1 t. 2 Ventilation Vent 3.0 Release Data Worksheet
.9 I
~ EPIP-11 1- . APX-3 Page 2 of 10 FEB 0 21980 0 1.0 Release Estimation Procedure 1.1 Effluent stream concentration is determined as a Krypton-85
. equivalent. The graphs depicted in Figures 1 and 2 display dose rate in mRH4/ER. sys Krypton-85 equivalent concentration in uCi/cc and pertain to the main steam relief and process vent and ventilation vent respectively. The Krypton-85 equivalent concentration is obtained directly from the graph at the point on the curve which corresponds to the dose rate reading from the respective radiation monitor.
1.2 System Flow Races Are Calculated as follows:
- a. Main Stean Lines 0
F, = fi x (2.8317 X 10 ) P 3600 Where: F,= Volume Flow Rate Main Steam ec/sec. lll M = Mass Flow Rate Main Steam, LBM/hr. (See Appendix 4) P = Density of Fluid (Main Steam @ Steam Generator Temperature and Pressure), LBM/FT 3
- b. Ventilation Stacks and Process Vents FE= SCFM x (2.8317 X 104 )
60 Whera: Fg = Volune Flow Rate of Gas, cc/sec. SCFM = Measured Volume Flow Rate of Gas at Standard conditions (Note: Difference between Actual & Standard Conditions are negligible), SCFM (See Appandix 4) 1 O
7 EPIP-11 APX-3
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60 V 1.3 The release rate of Krypton-85 equivalent can now be calculated by multiplying the concentration (uCi/cc) by the Flow Rate (cc/sec.).
. The formula is as follows:
R = CF Wheret R = Release Rate (uC1/sec.) Krypton-85 equivalent C = Concentration -(uci/cc) Krypton-85 equivalent F = Flow Rate (cc/sec.) For Calculations, refer to Form EPIP-11.2
- 1. 4 ~ Upon Determining the Release Rate of Krypton-85 Equivalent,
.the Whole Body Gamma Dose Rate (mrem /hr) can be calculated by incorporating the dose rate conversion factor for Krypton-85 and the X/Q for the location of interest from current MET Data.
The dose rate is calculated as follows: D = K x R x X/Q Where: D = Whole Body Gama Dose Rate, (cREM/Hr) K = (Constant) Dose Rate Conversion Factor for Krypton-85, 1.8 X 10-3 MREM /HR uCi/M3 R = Release Rate (uci/sec.) Krypton-85 equivalent X/Q = Atmospheric Diffusion Factor (sec/M3) l For Calculations, refer to Form EPIP-11.2. J
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EPIP-11 APX-3 Page 10 of 10 Torm EPIP-11.2 m FEB 0 21980 O 3.0 INTERIM HICH RANGE EFFLUENT MONITORS RELEASE DATA VORKSIEET DATE/TDC A. Release Rate: MONITOR CO'ICENTRATION (uCi/cc) FLOW RATE (ce/sec.) . RELEASE RATE (uCi/sec)
- X =
- X =
- X =
B. Whole Body Gamma Dose Rate: ATMOSPHERIC DOSE DIFFUSION RATE MONITOR CONVERSION FACTOR RELEASE RATE (uCi/see) FACTOR (sec/M3) (R".M/Hr . ) 1.8 X 10-3 mRee -M3 X X .
~
HR - uCi
- 1.8 X 10-3 mrem- M3 X X =
HR - uCi
- 1.8 X 10'3 mR'm-e M3 X _
X = HR - uCi O
g e -sa _ m 4 .--... e& O EPIP-11 APX-4 Page 1 of 3 FEB 0 2 E80 J .
. I FLOW RATE DETERMINATION 2
, APPENDIX 4 1 4 4 i O i r 4 i e Q
- -, --r -
y _ . . .
' Pag 2ef 3 EPIP-11 APPENDIX 4 FEB 0 21980 FLOW Pl.TE DETERMINATION Min. Flow for Source of Accurate Ref.
Monitor _ Service Flow Measurement Measurement (MF) Notes - RM-GW-122 Process Vent FT-GW-100 90 CFM* 1,3 RM-GW-123 Vent Vent FT-VS-100 96,000 CFM 1,4 (IT-VS-116**) (45,000CFM**) RM-MS-124 Main Steam Safety FT-1474 Line (30"-SHP-22) RM-MS-125 Main Steam Safety IT-1484 30% Flow
- 1, 2 Line (30"-SHP-23)
RM-MS-126 Main Steam Safety FT-1494 30% Flow
- 1,2 Line (30"-SHP-24)
RM-MS-224 Main Steam Safety FT-2474 30% Flow
- 1, 2 Line (30"-SHP-122)
RM-MS-225 Main Steam Safety FT-2484 30% Flow
- 1, 2 Line (30"-SHP-123)
RM-MS-226 Main Steam Safety FT-2494 30% Flow
- 1, 2 Line (30"-SHP-124)
.
- or as determined by operating data
** val 6es to *ue used after the Auxiliary Bufiding Ventilation Modification has been completed.
- 1. If flow rate indicated is less than minimun flow for accurate measurement (MF), the flow must be detemined using the methods outlined in Notes 2 through 4, as applicable, or a flow of MF may be assumed.
- 2. Based upon valves being determined open by inspection for a given period of time, determine local flow using design flow rctes given below.
SV-MS-101/201 A, B, C 361,750 lbm/Rr (ea) SV-MS-(102, 103, 104, 105 202, 203, 204, 205, A, B, C) 855,850 lbm/Rr (ea) HCV-MS-104/204 181,000 lbm/Hr (ea) RV-MS-101/201 A, B, C 373,000 lbm/Hr (ea) O
~
EPIP-11 APX-4 fj f l$30 v
~3. An eva2ustion of paths open to process vent must. be performed to detemir.e total flow.
- 4. Based on fans operating, determine total flow based on the following
- design flows:
~
(Pre. Mod.) ** Post Mod . Design Flow Design Flow FAN AREA (GEMr each) (CFM each) VS-F-5A, B Reactor Containment Purge 15,000 VS -F-7A, B Puel Building 17,500 17,500 VS -F-3A, B Auxi Bldg., Control Area 27,000 24,000 V5 -F-9A,B Aux. Bldg., General Area 21,500- 16,000 VS -F-40A,B ' Safeguards Area 6,150 6,000 VS -F-56A, B Decontanination Bldg. 6,150 6,000 VS .F-53A,B Safety Related Filtered 36,000 E:chaust VS -F-59 lion-Safety Related Filtered 43,000 Exhaust 1 O a. e
- , - . - . .w- - . -
m__..-..,... __ EPIP-12 8-22-77 Page 1 of 2 VIRGINIA ELECTRIC A':D POWER COMPA:PI_ SURRY POWER STATION ESTIMATING RELEASF. FROM STATIOt! SYSTEM IINEtITORY DATA 1.0- Ifcalth Physics Response Appendix 1,-Significance and Evaluation of Release Estimates Based on Station System Inventory
'^3
\., ,/
4 1
EPIP-12 8-22-77 t Pago 2'of 2
^ ESTIMATI!!S RELEASE FROM STATIO:1 SYSTEM ItNE:ITORY DATA s 1.0 llealth Physics Rosponse 1.1 Obtsin camples of that part of the cystem which was the source of the release. The types of samples should be the same as a
specified in the !!P Radioactive Waste Procedures, depending on the system involved. 1.2 Use an appropriate Radioactive Reloase Record to record the results of the Count Rcom. Analyses. 1.3 Obtain f rom FORM EPil 2.1, or from operations, the volume of the reltAso and calculate t'.ie activity released. 1.4 Evaluate the applicability of Appea dix .1, Significance ar <1 Evaluation of nelcano Estimatos Based on Stat lon Systeta Invc7-toty of this procedure. e e
i* EPIP-12 l s 8-22-77. , APX 1 , l
' i
-Page 1 of 3 g .
O - i
~
ESTIMATING RELEASE FROM STATION SYSTEM I?NENTORY DATA _ t o I APPENDIX 1 , SIGNIFICANCE AND EVALUATION OF RELEASE ESTIMATES " r BASED ON STATION SYSTEM IINENTOP.Y Part Subject 1.0 Scope of Procedure 2.0 General Methods to Determine Release 1 l i 1 O 4 f 4 i i e ? s- . a LO . 4
,- ,- e e r . e- r- ++. e+,v,,.-n,- e - - -w---w ,
,- -----.,--o--~- -e --n,---- - --- - . - -c,-, w n, ,_-e-~, - - , w- - - ~--n-,,.-n.-- ---- -
EPIP-12 8-22-77 APX 1 Pago 2 of 3 O 1.0 Scope of Procsdure The procedure is intended as a source of general information and methods to be used in estimating releases which may not be applicable to offsite monitoring or radiation monitoring system data. The actual sampling and analysis will have to be selected on a case by case basis. Other EPIP's will treat release estimates in more detail. It can be assumed the nnalypes resulting from this pro-cedure will not result in a requirement to initiate of fsite protective measures. 2.0 General Methods to Determine Release If a release results from a system containing gases, the volume of g gases released may be calculated if the pressure in the system beforo and after the release is known and the gas space volumo is known or may be estimated. Use the relationship that the volume released is the beginning pressure divided by the ending pressure times the gas space volume. If the radiogases remaining in the gas spacc are at ambient pressure or greater and have not been changed significantly by addition of other gases, a sample may be taken and considered representTtivo of what noble gasos were released. Due to unknown plate out value for radiciodines and 1 articulates, these nuclides are l l best determined using the Anplace ventilation and process vent sam- l
- plers, if the release passed through those systems.
If'the release results from a system containi:.g liquids, the volume of the release may bc calculated using indicated tank levels before and after the release. If a pump is driving the release the run time
. 1 EPIPa12 ,
8-22-77 APX 1 Page 3 of 3
'2.0 General Methods to Determine Release of the pump and its rated capacity may be used. Samples may be
]
' obtained of the liquid remaining in the tank or from pools or puddles 1
formed by the release if possible.
. . t 4
6 i 1 i O. 4 1 L 4
! i 1
i- . 5 4 i l- , L J 'k
-O s
a n wr, ,w- ,
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= .
= .
P , . EPIP-13 8-22-77 Paga 1 cf 5 VIRGIIIIA ELECTRIC A!!D POWER CCMPA'IY
- SUIUtY PO'JER STATIO!!
ESTIMATIt!G PILEASE FRO!! OFFSITE RADICIDGICAL DATA o 1.0 Health Physics Response 2.0 Release Estimates Based on Air Samples 3.0 Rolcase Estimatos Based on Contamination Levolc 4.0 Release Estimates Based on Radiogas Radiation Levels 5.0 Release Estimates Based on Contamination Radiation Leveln Appendix 1 Signific ance and Evaluation of Releaco Estitaates Based on Offsite Data Appendix 2 Blank Forms'EPIP 13.1, Of fsite Data nelease Workshoot O 4 9 r W.
-, , ~
EPIP-13 8-22-77 Pnga 2 of 5 ESTIMATI;;G RELEASE FRO!! OFFSITE PADIOLOGICAL DATA 1.0 Itcalth Physics Response 1.1 If offsite data is not already available, initato EPIP 16, "Offaite pir, Cont mination and Radiation Monitoring". 1.2 Evaluate the applicability of Appendix 1, " Significance'and Evaluation of Rolcase Estimates Based on Offsito Data", of this procedure. 1.3 Obtain a FORM EPIP 13.1, "Offsito Data Release Worksheet",'from Appendix 2 of this procedura. Entor the stability class, Wind speed in MP11 and date. 1,4 Based on the type of data received, use one or more of the following four methods to determino reloane. 2.0 Release Estimates Based on Air Samplos 2.1 count the sample (s) for gamma emitters or other activity as desired and exprcus the results as pCi/ml.
~
2.2 For cach location from which air sample were obtained and counted, enter the lccation designation, campling time and wind speed on FOPM EPIP 13.1.in the section "FOR USE WITH AIR SAMPLE - DATA". 2.3 Obtain from TAnLE 13.1, " Factors for Presclected Monitoring Locations Based on Stability Class", a conver sion factor for each location based on tho stability class at the time of sampling and enter this number on FORM EPIP 13.1. 2.4 Calculato, as indicated, a n ultiplication factor for each location and Osc this factor to convert the pCi/ml moasured to ( estimated curies being released per second.
r. 11 . _ _ _ . _ ._ _. . . . EPIP-13 S-22-77 Page 3 of 5 i- 2.0 Release Estimates Based on Air Samples (cont.) 2.5 Based on the knob or best guess time duration of the release, the total curies of each nuclide can be calculated and the results entered on FORM EPIP 2.2, " Gaseous Release Evaluation". 3.0 Release Estimates Based on Contamination Levels 3.1 Count the sample (s) for gamma emitters or other activity as desired and express the results as Ci/m . 32 For each location where contamination levels were measured,
- enter the location designation, sampling time and wind speed on FORM EPIP 13.1 in the section "FOR USE WITH CONTAMINATION DATA".
3.3 Obtain from TABLE 13.1, " Factors for Preselected Monitoring l _
Locations Based on Stability Class", a converrion factor for each location based on the stability class at the timo of sampling and enter this number on FORM EPIP 13.1.
- 3.4 Calculate, as indicated, a multiplication factor for each 2
location and use this factor to convert the C1/m measured to estimated curies released up to the time of sampling.
~3.5 The total curies released of each nuclide measured can then bo calculated and the results entered on FORM EPIP 2.2, " Gaseous Release Evaluation".
4.0 Release Estimates Based on Radiogas Radiation Levels 4.l' Use appropriate precautions to give reasonable assurance the
-~ measured radiation 1svels were due mostly to radiogases and not A ground or instrument contamination.
4
- h. _
- - - - _ = - _ . - _ _ _ _ . , . . . . . _ _ . _ . EPIP-13 8-22-77 Page 4 of 5 4.0 Release Estimates Based on Radiogas Radiation Levels (cont.) lh 4.2 For each location where radiation levels were measured, enter the location designation, time, the nR/hr measured and the vind speed on FORM EPIP 13.1 in the section "FOR USE WITH RADIATIOff DATA FROM RADIOGASES". 4.3 Obtain from FIGURE EPIP 13.1, " Relationship of Radiation Levels to Radiogas concentrations as a Function of Time Af ter Shut-down", the pCi/ml of radiogases based on the measured radiation level, considering the time after shutdown (use 48 hours for releases which do not r.ontain fresh fission gases) and enter this number on FOR{! EPIP 13.1 in the column "pCi/ml From Graph". 4,4 Obtain from TABLE 13.1, Factors for Proselected Monitoring Locstions Based on Stability Class, a conversion factor for each location based on the stability class at tho time of sampling and enter this number on FORM EPIP 13.1. 4.5 Calculate, as indicated, the release rate in Ci/sec ,radiogases. 4.6 Calculate tbo equivalent curies Xe-133 released per second, as indiccted. The mR/hr and pCi/ml are the same numbers as pre-viously entered for each associated location. 4.7 Calculate tho equivalent curies.I-131 released por second, as indicated. Release fraction will be a matter of judgement
~4 based on the nature of the release and may vary from 10 for a steam generator tube rupture to 0,25 for the LLCA.
4.8 The equivalent curies of Xe-133 and I-131 may then be calcu- . lated based on the known or best guess time duration of the release and these results may be entered on FORM EPIP 2.1,
" Report on information Sought b.y Cnorgency Coordinator or Di-rector".
L - , . .. . .
- . . . - . }
EPIP-13 8-22-77 Page 5 of 5
.( ;
- 5.0 Release Estimates Based on Contamination Radiation Levels p.
5.1 Use appropriate precautions te give reasonable assurance the measured radiation levels were due mostly to ground evicami-naticn and not by submersion in a radioactive cloud or instru-ment contaminatica. , 5.2 For each location where radiation levels were measured, enter the location designation, time, the mR/hr measured and the wind speed on FORM EPIP 13.1 in the secrion "FOR USE WITH RADIATION
- DATA FROM CONTAMINATED GROUND".
5.3 Obtain from TABLE 13.1, " Factors for Proselected Monitoring Locations Based on Stability Class", a conversion factor for l , each location based on the stability class at the time the l-levels were reasured and enter this numbor on FORM EPIP 1*. 1. t Calculate, as indicated the curies I-131 released and this 5.4 result may be entered on FORM EPIP 2.1, " Report on Information Sought by Emergency Coordinator or Direct.or". t
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EPIP-13 p ,1/M M 4~ ~ 8-22-77 P g31 cf 1 P .( ) TABLE EPIP 13.? FACTORS FOR PRESELECTED MONITORING IDCATIONS BASED ON STABILITY CLASS STABILITY CLASS B C D E F G A
@ TION 4.$ES 2.1E4 7.1E4 2.7E4 1.6E3 8.5E2 5.6E2 SD 1.1E6 5.3E4 3.5ES 1.1ES 5.6E3 2.8E3 1.5E3 MIR 1.2E6 .2.1E5 4.5ES 1.4E5 6.8E3 3.3E3 1.8E3 SI .
SCOT WF 3.4E6 2.4E6 3.2E6 7.8E5 3.2E4 1.4E4 6.oE3 3.1E6 1.9E6 2.6E6 6.7E5 2./E4 1.2E4 5.4E4 CP , XM 3.1E6 1.9E6 2.6E6 6.7ES 2.7E4 1.2E4 5.4E4 FE 3.3E6 2.2E6 2.9E6 7.4E5 3.0E4 1.3E4 5.8E3
- BC 3.3E6 2.3E6 3.0E6 7.6E5 3.1E4 1.4E4 5.9E3 ALL 1.9E5 2.7E6 3.5E6 8.6ES 3.4E4 1.5E4 6.4E3-fx b '
JtrNN 3.8E6 3.2E6 4.0E6 9.6E5 3.8E4 1.6E4 7.0E3 DOW 3.8E6 3.1E6 3.9E6 9.5ES 3.7E4 1.6E4 6.8E3 4.6E6 4.8E6 5.5E6 1.3E6 4.9E4 2.1E4 8.6E3 LEE flL BUD 4.6E6 4.8E6 5.5E6 1.3E6 4.9E4 2.1E4 8.6E3 10-676 4.2E6 4.0E6 4.7E6 1.1E6 4.3E4 1.9E4 7.8E3 SMFD SUB 8.0E6 1.8E7 1.6E7 3.2E6 1.1ES 4.6E4 1.6E4 NN SUB 1.1E7 3.8E7 ,2.9E6 3.5E6 1.8E5 7.2E4 2.4E4 mG me O e
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J EPIP-13
' "' 8-22-77
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APX 1 j Page 1 of 3 1
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a ESTIMATING RELEASE FROM .OFFSITE RADIOLOGICAL ' DATA APPENDIX 1 ,
- SIGNIFICANCE AND EVALUATICM OF RELEASE ESTIMATES BASED ON OFFSITE, DATA Part. Subject 1.0 Basic Considerations
- 2.0 Conversion Factors for other than Preselected Locations-0 e
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EPIP-13 8-22-77 XPX 1 Page 2 of 3 (~ 1.0 Basic Considerations , All release estimates are calculated using factors derived from standard atmospneric dispersion models which give average values. All the graphs and nomographs in EPIP 1 were calculated similarly so 8 s, that any inherent errors in the methodology should cancel themselves to a certain extent. The Virginia plan calls for declaring RED if radiation levels exceed 50 mR/hr sustained for greater than 30 minutos. The use of calcu-lating the release rate e,hould give an indication of the severity of the release much sooner. 2.0 Conversion Factors for Other Than Preselected Locations Results of monitoring from other than preselected locations will require the calculation of conversion factors for use with FORM EPIP 13.1. Use the following equation to obtain the conversion factor. 1 Factor = X)B Where: A and B are a function of stability class: Stability Class A B A 1.2 E-6 . -0.895 B 1.1 E-5 -2.09 C 4.4 E-6 -1.68 D 1.3 E-5 -1.48 E 2.5 E-4 -1.32 F 5.0.E-4 -1.24 G 8.6 E-4 -1.05
. . .~ .. . _- .
EPIP-13
- 8-22-77 ,
APX 1 Page 3 of 3 fN .
- Q l-
,(. 2.0 Conversion Factors for other Than Preselected Locations _ (cont.)
X'is distance, in miles, from release point to monitorlag location. The scale -on FIGURE EFIP 16.1 is 1 inch = 2 miles. EXAMPLE: Incalion P2 is 2.5 miles from station (1.25 inches on
-FIGURE 16.1), stability class is E.
l'
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Factor = 2.5 x 10 . x (2.5) 1
" -4 2.5 x'10 x 0.298 4
= 1.33 :. 10 a
4 0 0 t 4 l LO. m
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- EPIP ' ~
8-22-77 APX 2 Page 1 of'2 . ;O : - l
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.i ,. 1 b' :
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~ ESTIMATING RELEASE FROM'OFFSITE DATA
- i. * ,
r .s 1- , f 1 e-i
- APPENDIX 2 4
+ 4 4 4 . a e E e t 4 1 BLANK FORMS EPIF 13.1 OFFSITE DATA RELEASE WORKSHEET 4 1 i. i 4 O 4 a
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l FORM EPIP 13.1 8-22-77 OFFSITE DATA RELEASE kVPJSHEET Stability Class Wind speed (MPH) date Results By
-FOR USE WITH AIR SAMPLE DATA---
MULTIPLICATION FACTOR WIND SPEED CCNVERSION IV CONVERT pCi/ml 'IO TIME MPH FACTOR Ci/sec RELEASE RATE
-IDCATION o
X = X = X = a
-FOR USE WITH CONTAMIt3ATICS DATA-MULTIPLICATIONFgCTOR WIND SPEED COtNERSION TO COtNERT Ci/m '!V TIME MPH FACTOR CURIES RELEASED IDCATION
- 3 X X 67 =
- X X 67 =
t , X X 67 =
--FGR USE WITH RADIATICN DATA FRCit RADIOGASES---
WIND
- DCi/stl SPEED CO!NERSION Ci/sec Ci/sec Ci/sec FACTOR RADIOGASES_ Xe-133_ I-131 IOCATION TIME mR/hr FROM GRAPH MPH
[_a X X = X K = a
^
X = __ __s X x Equivalent curies Xe g { released per second = 3 x 10" C1/sec Radiogases x p (from above) Equivalent curies I-131 released per second = 0.5 x Ci/sec Radiogases x Release Fraction (0.25 for IOCA)
---FOR USE WITH RADIATION DATA FROM CONTAMINATED GROUND---
WIND SPEED CONVERSION CURIES I-131 TIME mR/hr MPH FACTOR RELEASED IOCATION s X X X 0.0084 = X X X 0.0084 = X X X O.0084 = G
i EPIP-14 Page 1 of 3 JUN 7 1978 4
- VIRGINIA ELECTRIC AND POWER COMPANY SURRY PO'JER STATION ESTIMATING DOSES FROM RELEASE DATA 1.0 External Submersion Dose - Wole Body 2.0 Internal Inhalation 71ose - Thyroid
/*N __ _ _/
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qw EPIP-14 l Pzge 2 Of 3 { JUN 7 1973 ESTIMATING DOSES FROM RELEASE DATA The purpose of this procedure is to provide the methods which may be used to estimate doses resulting from the accidental release of airborne radio-active materials. It is intended to provide, as appropriate, dose esti-mates if requested through EPIP-2. This procedure is riost applicable ,1f the release can be expected to result in essentially non-detectable radia-tion IcVels when measured by portahic survey instruments. 1.0 External Submersion Dose - Uncle Body 1.1 Obtain through EPIP-2 the equivalent curies of Xe-133 (ci Xe-133) that are considered released. 1.2 Site boundary doses based on the stability class and wind speed may be obtained from the appropriate "Whole Body Evaluation" , nomograph which are included in EPIP-1, Appendix 1. In cases where the Curies Xe-133 released are below scale, multiply the curies by' appropriate factores of ten to get on scale and then divide the indicated dose by the same factor. 1.3 Offsite doses at other locations can be estimated using the equation at the bottom of th e nomograph. 'his equation should only be applied to locations between 1 and 10 miles from the release point. 1.4 Onsite doses can be estimated by the following equation: Whole Body Dose (Rem) = Ci Xe-133 released X 2 X 10 Wind Speed MPH f
EPIP-14 Pego 3 of 3 JUN 7 B78
^~-/' 2.0 Internal Inhalation Dose - Thyroid 2.1- Obtain through EPIP-2 the equivalent curies I-131 (Ci I-131)
-that are considered released.
'2.2. - Site boundary doses, based on the stability class and wind speed may be obtained from the appropriate " Thyroid Evaluation" nomograph whfch are included in EPIP-1, Appendix 1. In cases where the curies I-131 released are below scale, multiply the curies by appropriats factors of ten to get on scale and then divide the indicated dose by the same factor.
2.3 Offsite' doses at other locations can be estimated using the equation at the bottom of the nomograph. This equation should only be applied to locations between 1 and 10 miles from the release point. 2.4 Onsite doses can be estimated by the following equation: Thyroid Dose (Ren) = Ci I-131 released X 1.5 Wind Speed MPH 4 I 4 s
EPIP-15 Page 1 Of 2 JUN 7 1578 k VIRGINIA ELECTRIC AND POWER COMDANY SURRY PC'JER STATION ESTDIATING DOSES FROM FNVIRONMENTAL DATA 1.0 External Dose'- Whole Body 2.0 Internal Inhalation Dose - Thyroid 3.0 Internal Dose - Any Organ (~, ( E,!
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EPIP-15 Page 2 of 2 JUN 7 578 ESTIMATING DOSES FROM ENVIRONMENTAL DATA Ys The purpose of this procedure is to provide the methods which may be used to estimate doses resulting from the accidental release of airborne or waterborne radioactive materials. It is intended to provide, as appro-priate, dose estimates if requested through EPIP-2. .This proceduro is most applicable if the release can be expected to resul. in measurable radiation levels with either portable or Count Room equipment. 1.0 External Dose - Whole Body 1.1 Estimate the whole body dose using the results of surveys done G;- ~ vith survey instruments or from reading inplace TLD badges which have been exposed by the incident. 2.0 Internal Inhalation Dose - Thyroid 2.1 If the uCi/ml I-131 concentration is known, the dose to the thyroid per hour of exposure can be estimated by: Dose to Thyroid (Rem) = uCi/ml I-l'1 x 1.9 x 10 6 3.0 Internal Dose - Any Organ 3.1 The dose factors given in Regulatory Guide 1.109 " Calculation of Annual Doses to Man from Routine Releases fo Reactor Efflu-ents for the Purpose fo Evaluating Compliance with 10CFR50, ( Appendix I" can be used based on the concentrations of various nuclides found in food pathway samples collected. i
w - - EPIP-16
.Page 1 of 3-s ,( ,NU;' ';> _ - ,
DEC 3 I G79 ft;. A lw-) . . f 4
- 3. < ;
VIRGINIA ELECTRIC AND POWER C0!!PAliY - SURRY POWER STATION OFFSITE AIR,L CONTAMINATION AND RADIATION MONITORING F; . i: , '~ 1.0 . Health Physics Response . 2.0c Monitoring Team Response
- Appendix l-- Offsite Monitoring Significance and Evaluation Appendix :2 --Blank Forms EPIP 16.1, Off site Air, Contamination and Radiation Monitoring l f.p (f.
Appendix 3 Figure EPIP 16.1, 16.2, 16.3; Surry Power Station
.LPZ Map Showing Preselected Monitoring Locations i- Appendix 4 -- Onsite and Offsite Radioiodine Air Sampling Under Conditions of.lligh Noble cas Concentration u n l
j ..
e EPIP-16 CEC 31 1979 Fage 2 of 3 OFFSITE AIR, CO!!TAMIIIATIO!I A!!D RADI ATIOt3 MO lI_TORITIG 1.0 Health Physics Response 1.1 Assign two ind!"iduals per monitoring team, one individual must be qualified in emergency HP techniques and the other indivi-dual to drive the vehicle and otherwise assist as directed. Request assistance from the Emergency Coordinator or Director if needed. 1.2 Instruct the monitoring team to perform instrume,nt functional checks and arrange for a vehicle. . 1.3 Evaluate the applicability of Appendix 1, "Of fsito Monitoring Significance and Evaluation", of this procedure. 1.4 Obtain from Appendix 2 of this pro _edure a FORM EPIP 16.1, "Offsite Air, Contamination and Radiation Monitoring", and fro 16.1, 16.7, 16.3, Appendix 3 of this procedure a copy of FIGURE EPIP Surry Power. Station LPZ Map Showing Preslected Monitoring Locations". 1.5 Check, as appropriate on FORM EPIP 16.1, the block oppo3ite tho monitoring desired and indicate the locations per the dosig-nations .n FIGURE 16.1, 16.2, 16.3 (The LPZ Map). 1.6 Turn the completed form and map over to the monitoring team. 2,0 Monitoring Team Response 2.1 Locate a vehicle and make a quick check of its operability (check to ensure it will start, that it has at least a 1/4 tank of gas and it has a good spare tire) . m Change No. 12
V
' EPIP-16 Page 3 of 3 i L a 1 Ei3 2.0 ;Nbnit'oring Team Response (Continued) {
7p-s
- 8 -
s- 2.2 Obtain and source check at least two survey instruments, one i with a HP210 probe..
= 2 '. 3 Obtain a radio ( auf spare battery pack if available) and check
-it's operability.
.2.4 Upon instructions or receipt of FORM EPIP 16.1, obtain addi-tional supplise as needed.
2.5 After sufficient supplies have been obtained, perform the monitoring as indicated on FORM EPIP-16.1, and FIGURE 16.1,.16.2, 16.3, i following any special instructions. 2.6 Report results to the station as indicated. 2.7- Notify,'by radio or telephone, the Power Station of any situ-ations which may warrant attention and carry out any subsequent
) instructions.
~
l
- ' i
? +- Change No. 12
+
- - . . ,.. 1 '
t EPIP-16 8-22-77 ' APX 1 Page 1 of 5
'; ' W("~h' :g
. r OFFSITE AIR, CONTAMINATION AND RADIATION MONITORING
- APPENDIX 1 OFFSITE MONITORING SIGNIFICANCE AND EVALUATION p:
" Part -Subject 1.0 General Monitoring' Considsrations 1 2.0 Monitorin3 of Locations not Proselected 3.0.~ Factors Controlling the Area Affected by a Release '1 e J d
+
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, EPIP-16 APX 1 Pago 2 of 5
( . 1.0 General Monitoring Considerations
" ~
Appropriate methods should be used to avoid or minimize the conta-mination of monitoring equipment prior to the monitocing team leaving the power station site. s A r'elease cloud can travel no faster than the wind carrying it, therefore due consideration must be given to assure the monitoring team is located and sampling at the appropriate time. Do not have the monitoring team don protective clothing and respi-rators unless it is considered absolutely necessary, since members of the general'public may misunderstand the purpose.
. Consider administering NaI or KI tablets, see EPIP-10.
The monitoring team should seek the highest radiation / airborne areas near the preselected sampling locations, since the conversion factors (i which may be used to estimate the velcase are based on centerline or maximum concentrations. Air samples of particulates. radiciodines and radiogases counted on the multichannel analyzer are, of course, more accurate than estimated concentrations based on radiation levels. However, in the event a Site or General Emergency response level is a possibility the measured radiation levels should give satis-factory rssults much sooner. If a release results in having a large amount of heat associated with the released activity, the cloud may rise and settle in an unpredic-tchle man.1er. In such cases higher concentrations could exist at points further away from the station, and the monitoring teams should be instructed to monitor locations downwind other than preselected ones. The team should also transverse the anticipated path of the cloud more than once to minimi=o the effect of any cloud meander.
F-EPIP-16 8-22-77 APX 1 Page 3 of 5 y 12.0 Monitoring of Locations Not Preselected-Y'- The preselected locations have already had the necessary con',*ersion factors calculated based on the current atmospheric stability class. If it is necessary to mohitor.elsewhere the conversion factors will e-have to calculate which will require the actual monitoring locations be described, preferably by reference to a known landmark such as a bridge or intersection. All such monitoring must be documented. 4 e d 4 I O 4 h a e
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EPIP-16 8-22-77 APX 1 Pagn 4 of 5 3.0 Factors Controlling the Area Affected by a Release The arca a release cloud may affect is dependant on the atnospheric stability class and the wind speed and direction, among other vari-ablos such as precipitation and the terrain. From a practical stand-point only stability class, which offects the " width" of the affected area, and wind speed and direction which affects the longth and direction of the area, will be considered. The width of an affected arca as a function of stability class and distance from the release point is illustrated by the following table. The tabic lists the different stability classes and lists tho width of an area in feet which will contain a certain percent of the maximum calculated concentrations (or doses) . The percentages con-nidered are 90, 50 and 10%. The distances aro 1 and 2 miles from a O release point. These tables may be used as guidelines on what to tell the monitoring team to expect, such as in stability class F they are looking for a small area of rapidly increasing concontrations if the cloud is approached from the side. Area Width - Feet Stability Percent of Class Maximum 1 Mile Distance 2 Mile Distanco 90 , 878 1632 A 50 2256 4195 10 4109 7641 90 653 1227 D 50 1676 3152 10 3053 5741 90 472 887 C 50 1213 2279 10 2209 4152
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EDIP-16 8-22-77' APX 1
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3.0' Factors Controlling the Area Affected by a Release (cont.)
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Stability. Percent of Class Maximum 1 Mile Distance 2 Mile Distance 90 319 595 D 50 819 1530 .
, 10 1492 2787 90- 235 433 E 50 603 1112 10 1098 2027 90 161 299 50 414 768 F
10 754 1399 90 97 179 G 50 249 460 10 453 843 1-Wind speed affects the area by tho fact that higher wind speeds cause the cloud to arrive sooner, but the concentrations are reduced. The affected area will be downwind of the release point, if the direction is variabld, the area with the highest average downwind direction will be affected the greatest. i P (h
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- OFFSITE AIR, CONTAMINATION 'AND RADIATION MONITORING v .
1 ; - 4 4 i 4 APPENDIX 2 A. ir~ . I 1- 1 'I . b t - 1' !- BLAUK FOFMS EPIP 16.1-t- [ b r + - OFFSITE AIR, CONTAMINATION AND RADIATION MONITORING , i-l- . 4
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v ;p_ FORM EPIP 16.1 8-22-77 ( ,-w OFFSITE AIR," CONTAMINATION AND RADIATION MONITORING x_j ' o- . Prepared by: Date/ Time: 1.0 The monitoring team-is to accomplish the following as indicated. h Air Samples:_ h Environ Monitors h SD o - g HIR g SI g j Grab Samples Near Locations: Type of Sample: h Low Volume h High Volu ne
' h Air Particulato h -Charcoal j 100 cc Radiogas
- Tritium I
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'y' - h Contamination: Near Locations:
U Smears I h Radiation Levels Near Surfaces ! ' U Soil Sample O ' y h Radiation: Near Locations: 2.0.. Supplies t h Rope, Barrier Tapc, Signs h Soil Containers / Shovel h Radio h Flashlight i.~()~ h Pens . I
%. 2 h Protective Clothing / Respirator (CONTDIUED)
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8-22-77 j &
'U OFFSITE AIR, CONTAMINATION AND RADIATION MONITORING
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-(cont.) .
3.0 Additional Instructions:-_ o-i. Monitoring. Team Data Record 4.0 .
. REMARKS S?JCI.E* (DESCRIBE OTIIER S74tPLES TT. '.C:!)
I. LOCATION TIME-. mR/hr_ VOLUMU
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- Indicate area sampled if contamination measured.
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' Data By: Date/Titno :
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.,' .c-DEC 31 1979
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4 OFFSITE AIR, CONTAMINATION AND RADIATION MONTORING T k. APPENDIX 4_ < .s .
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ONSITE AND OFFSITE RADI0 IODINE AIR SAMPLING UNDER CONDITIONS OF HIGH NOBLE GAS CONCENTRATION t 1' 1 a c e . t iL . Change No. 12
. . _ s___ . . _ _ . _ . _ . - . . _ _ . . . _ _ _-. _ . . . _ . . _ . _ _ _ _ _ - - - - .~ _. . _ . . _ ._.
p -- EPIP-16 APX - 4 P g2 2 of 2 DEC 31 1979 h i A. Purpose The purpose of this procedure is to provide a method of sampling the atmosphere for radioiodines in an area of high noble gas concentration without noble gas'setturation of the acquired air sample. B. References
- 1. Document entitled: Retention of Noble Cases By Silver Zeolite Iodine Samplers By James E. Cline, Science Applications, Inc.
C. Precautions
- 1. Ascertain that air sampling device used is currentJ y within it's calibratica period.
- 2. Check iodine cartridge used to assure that it is of the silver zeolite type.
O D. General-Noble Gas (Xenon) retention in the silver zeolite sample cartridge 6 percent. These has been calculated to be less than 5.0 x 10 cartridges can be obtained in the Health Physics Supervisor's Office.
. E. Instructions
- 1. Silver zeolite sample cartridge shall be installed in air sampling device in same manner as standard iodine sampling
~
cartridge.
- 2. Sample flow rate should be adjusted to approximately 28 liters per minute (1 SCFM).
- 3. Air sample should be run from 10 minutes to 120 minutes for best results.
s 4. Run an isotopic analysis on sample using existing counting procedures and geometry. Change No. 12
EPIP-17 l 8-22-77 Page 1 of 2 { VIRGIIIIA ELECTRIC A!!D POSTR CO!!PA!;Y SURRY POWER S'l ATIO:! OFFSITC WATER A!!D FOODSTUFF _ MO:IITORII!G 1.0- Health Phynacs Response Append 1x 1, General Monitoring Significance and Evaluation
" Appendix 2, Blanifrornu EPIP 17.1, Water and Foodstuff Monitoring e
(O 4
EPIP-17, 8-22-77 Page 2 of 2 OFF3ITC UrsTUR 7J D FOODSTUFF l'O:!ITORIts 1.0 llealth Physics Rouponne 1.1 ObtLin from Appendbc 2 of this procedure a FOPJ1 EPIP 17.1, .
" Water and Foodstuff 11onitoring".
c, . 1.1.1 Check, as appropriate to the existing situation (flote Appendix 1 af this procedure) , tho block opposite the
. samples desired.
~
1.1.2 Indica *e the minimum supplies to be cbtained. 1.1.3 Indicate the desired disposition of the camples. ' 1.1.4 Indicate the desired analytical work. 1.1.5 Indicate any spe :ial instructions. 1.1.6 Accign the FOTO1 EPIP 17.1 to a monitoring tenn. 0' 1.2 The assigned monitoring team in to act to obtain the requested monito.ing. 1.2.1 Obtain indicated suppl.ics and appropriate transpor-tation. 1.2.2 Obte.in samples indicated, identifying by location, date and time. 1.2.3 Notify,' by radio or telephone, the Power Station of any situations which may warrant attention and carry out any subsequent instructic..4. 1.2.4 Transport sampics as indicated on FO!Of EPIP 17.1. 1.3 The Itcalth Physics Coordinator in to arrange for the disposi-tion and analytical work as best suits the existing situation.
p- .. 1 EPIP-17 '
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0FFSITE WATER AND FOODSTUFF MONITORING : l x y . APPENDIX 1 : i
. t GENERAL MONITORING SIGNIFICANCE AND EVAUJATION I
.I Part Subject .
1 Significance of Water and Foodstuff Monitoring . Evaluation of Offsite Data 2 O, i i I d I I f l' . t 4, s
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1
' EPIP-17 8-22-77 APX 1 Pago 2 of 2 ~
1.0 Significance of Water and Foodstuff Monitoring Monitoring water and foodstuff for initiating' protective mea-sures offsite is not normally within the scope of involvement oftthe Power Station. State and Local abencies plans call e for their own monitoring. The time required for these pathways to begin accounting for exposure to individuals is typically on the order of hours as a minimum and goes up to many days. The procedure should generally be initiated only to the extent of obtaining selected samples to document no or minimal increasc in environmental radioactivity following an unplannod release from the station. It is to be initiated to the extent possible upon requcst of a responsible stat": or local agency followf.ng a report by the Power Station of a radiological emergency. NOTE: Sampic collection should_bo considered as an additional information sourcc if EPIP 16, Off.* ite Air, Contami-nation and Radiation Monitoring, is initiatod. 2.0 Evaluation of Offnite Data . One of the most limiting pathways following an airborno release is cow-milk-human due to radiciodines concentrating in the cows milk and human thyroid. Other items of interest are harvestable foods such as vegetables from gardens or fruit trees and animal forage such as grass, grains or hay. Lignid pathway doses are by direct consumption and from har-verting and consuming fish from contaminated waters. Potential doses can be calculated using similar methods specified,in Regulatory Guide 1.109 dated March 1976. llh
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gpyp 17 8-22-77 i
, - APX 2 Page 1 of 3 )
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- 0FFSITE WATER AND FOODSTUFF MONITORING f
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APPNDIX 2 h i WATER AND FOODSTUFF MONITORING , 7 BLANK FOlWS EPIP 17.1 't i- .
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p . EPIP-17 8-22-77 APX 2 Page 2 of 3 FORM EPIP 17.1 WATER A!!D FOODSTUFF mot 1ITORI!!G Prepared By: Date/ Time: 1.0 The monitoring team is to obtain the indicated samples, h Water h Discharge Canal O Intake Canal O Hog Island Point h Hog Island Pond (s) U Direction (compass)
, 6 Surface Water Runoff Well Water frcs / / Hoe Island: / / Bacons Castle h Williamsburn /7 Station U
h Foodatuffs h Milk Dairy 9 U Milk Individual Cow h Crop (Specify) _ . _ _ _ h Fowl j Vegetables _ ._ h Fruit h Animal Forage U U
2.0 Supplies
O Plastic Bottles, in number. h Bucket with Rope (for surface Vator)' h Marking Pen U Flashlight h h Radio (CO:ITItiUED) ,
g-
- * $hE~h APX 2
! Page 3 of 3 FORM EPIP 17.1 WATER A!!D FOODSTUFF Mot!I'1 CRIT!G (cont.) 3.0 Sample _ Disposition [f Return to Station
, 6 Turn over to Vepco at f
6 Turn over to Stato at 4.0 Analytical Work:
,Samplo _
Preparation: U Acidify and Store h Split-Sample O Prepare for Counting h ' Prepare for Shipment to f*- i"'
~
Analysis: 6 Gamma Isotopic ( counted first)
~
Lf Tritium 0 Gross Gamma 0 Beta Gamma 5.0 Additional Instructions: k i t e
EPIP 18 Page 1 of 3 J'JN 7 1978 ( ,. VIRGINI A ELECTRIC A!Q PO',TER COMPANY SURRY PO'ER STATI(3 EMEP.GE':CY EXPOSURE CRITERIA 1.0 Emergency ui;cctor Response 2.0 IIcalth Physics Response Appendix 1, Emergency Exposure Significance and Evaluation Appendix 2, Blank Forms EPIP 18.1, Emergency Exposure Authori::ation (O 4
m EPIP-18 Page 2 of 3 JUN 7 1978 EMERCE!!CY EXPO 5CP.? CRITERIA 1.0 Energency Director Resacnse 1.1 1;otify Health Physics that EPIP-18 has been initiated. 1.2 Ensure that high range self-reading donimeters have been issued to all emergency r.diation workers. Send workers to HP, if tequired to obtain dosincters. 1.3 Complete a Form EPIP 18.1, Emergency Exposure Authorization, (blank forms in Appendix 2 of this proced'.re) and forward to Health Physics. 1.4 Instruct any worker who is expected to exceed 30CPR20 exposure limits to report to HP for dosimetry issue and instructions. Renind ucrkers they nust follow HP in truct icas. 1.5 If advised by HP that any individual has received a whole body dose in cxcess of 3 rea, the indivicucl is to be evacuated as soon as practical and sent to MCV Hospital in Richmond for examination. 1.6 If advised by IIP that any individual has received a whole body dose in excess of 25 rc=, the individual is to be evacuated immediately (after any practical decontamination) and sent to MCV Hospital in Richmond for examination. 1.7 Evaluate the applicability of Appendix 1, Emergency Exposure Significance and Evaluation, of this procedure. l
\
~> -
. EPIP Pass 3 of 3 JUN 7 578
- (s' 2.0 Health Physics Response-2.1 When notified by the Emergency Director of the initiation of
' EPIP 18. Health Physics 'is to initiate EPIP-10, Personnel
. Monitoring and-Decontamination.
2.2 - Na1 or KI tablets are of value if exposure to radioiodines above P.PC are expected. (Seven (7) drops of a saturated solution may act as a substitute).. i 2.3 Verify supplies of respirators, SCBA and Proective Clothing. 2.4_ Minimize exposure to monitoring personnel while obtaining
. sufficient data to advise the Emergency Director of radio-l l
logical conditions. > l 2.5 Evaluate the applicability of Appendix 1, Emergency Exposure Significance and Evaluation, of this procedure. s>
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EPIP-18 APX 1 i Page 1 of 6 JUN 7 378 (7_ . . Gy i I :
'EMERCENCY EXPOSURE CRITERIA
( APPENDIX 1 i i
, '-EMERGENCY EXPOSURE SIGNIFICANCE AND EVALUATION !
Part
'l. Basic-Considerations 2 -Radiation Effects Versus Whole Body Exposure 3 VEPCO and Virginia Exposure Limit Sumary 4 Dose Conversion Factors and MPCs for Selected Nuclides 7
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EPIP-18 APX 1 Page 2 of 6 JUN 7 M4 1.0 Basic Considerations 1.1 Workers for emergency exposures should be selected, in addition to other considerations, such that those with the highest unused permissible accumulated dose receive the highest emergency exposures. 1.2 Women of childbearing age should be excluded, if at all possible, from working ir amergency operations where the exposures could excead 10CFR20 limits. 1.3 As time permits, emergency exposures should be preplanned to minimize doses received. In recovery operations, 10CFR20 limits should be considered the maximum allowed. 1.4 lf LIFESAVING activity is warranted, authorize volunteers to receive 75-100 rem exposure each. 100 Rem is the upper range beyond which the risk of adverse response in the rescuer ex- lll posed warrants serious consideration of discontinuing life saving activities (other circumstances should also be con-sidered, i.e. , number of and dose accumulated by persons to be saved; the rescuers may have already received maximum author-ized exposures, etc.). Authorization should be granted only when the total probable total dose the rescuers will receive has been estimated on the basis of reasonable data and the exposure is deemed necessary to save lives. 1.5 If the potential risk of the radiation hazard is such that life would be in jeopardy or that severe effects to health or loss of property adverse to the public welfare would result, author-ize 25 rem exposure (cnce-in-a-lifetime occupati.onal dose limit for non-lifesaving activity recommended by the scientific ggg community).
33
.i EPIP-18 APX 1 Page 3 of 6 JUN 7 378 tr, 1.0 Basic Jonsiderations (continued)
'l. 6 - Use $1000 per estimated man-rem exposure for monetary evalu-stion if such is-desired.
L 1.7 The risk of thyroid cancer due to iodine inhalation per rem is approximately one-fifth of the total cancer risk following whole xdy exposure. 1.8 The use of blocking agents such as potassium or sodium iodide
- .can substantially reduce the radiciodine uptake.
1.9' Positive pressure SCBA should be worn by all individuals if exposure to airborne activity is expected, but do not exhaust the supply of bottled air on site as merely a safety precau-tion.
- i. ,_
1.10 Unless it is censidered absolutely necessary, HP personnel
\_)- should not remain witn emergency workers during high exposure races, since it can be expected that HP will have to make repeated entries into high radia: ion areas.
p i-i l r M b-m
EPIP-18 APX 1 Page 4 of 6 2.0 Radiation Effects Versus Whole Body Exposure 5 - 25 rem Changes it. blood count; changes in chromosomes of white blood cells; temporary reduction in sperm count. 25 - 75 rem Loss of appetite in 19 to 50% of exposed individuals; nausea and fatigue in 1 to 30%; vomiting and diarrhea in 1 to 10% of those exposed; temporary sterility; chromosomal changes in the skin.' 75 - 100 ren Increase in the above effects; loss of hair in 10% of e.xposed indi-viduals; 1 to 57. of those exposed will die within 60 days. 230 - 310 rem 100% incidence of actute effects; 50% of those exposed will die within 60 days. lll 320 - 480 rem 90% of exposed individuals will die within 60 days. O
W EPIP-lE APX 1 Page 5 of 6 3.0 Vepco Virginia and 10CFR20 Exposure Limit Su==ary VEPCO ON-SITE DIERGENCY EXPOSURE LIMITS CLASSIFICATION WHOLE BODY - REM THYROID - REM l Emergency Worker 25 75 Lifesaving Activities 75
- VIRGINIA STATE OES OFF-SITE EMERGENCY EXPOSURE LD!ITS POPULATION AT RISK WHOLE BODY - REM THYROID - REM Non-Essential Personel 2 . 12 Emergency Workers 25 75 Lifesaving Activities 75 *
- No Limit given since in extreme cases complete thyroid loss may be ac-ceptable for a saved life. This should not be necessary if respirators and/or blocking agents are available for rescue personnel.
( ,/ STATE - OES OFFSITE CONTAMINATION LIMITS
- SURFACE BEIA-GAMMA OR ITEM mR/hr*
General Body 0.06 Hands 0.3 Shoes - Inside 0.3 Shoes - Outside 0.6 Clothing 0.25
)
- Measured 5 cm above the surface NRC 10CFR20 QUARTERLY LIMITS Whole Body 1.25 rem 3.00 rem if 5 (N-18) permits Hands / Feet 18.75 rem I Skin 7.5 rem Inhalation 520 x MFC for 1 hour
F EPZP-18 APX 1 Page 6 of 6 JUN 7 578
^ 4.0 Dose Conversion Factors and MPCs for Selected Nuclides Rem ml MFC Rem Dose - One ibur Exposure Nuclide sec pCi (uCi/ml) 100 x MPC 1000 x ktPC Mn-54 4.8 E O 4E-8 0.069 0.69 Mn-56 1.3 E O SE-7 0.23 2.3 Fe-59 1.1 E+1 SE-8 0.20 2.0 Co-58 5.3 E O SE-8 0.095 0.95 Co-60 1.4 E+1 9E-9 0.045 0.45 Cr-51 2.3 E-1 2E-6 0.17 1.7 .
Kr-88 4.2 E-1 lE-6 0.15 1.5 Xa-133 6.9 E-3 lE-5 0.025 0.25 Ru-106 6.3 E+1 6E-9 0.14 1.4 Te-132 2.7 E O lE-7 0.097 0.97 Cs-134 3.5 E+1 lE-8 0.13 1.3 h Cs-136 6.3 E O 2E-7 0.45 4.5 Cs-137 1.9 E+1 lE-8 0.068 0.68 I-131 5.2 E+2 9E-9 1.7 17 Thyroid I-132 2.0 E+1 2E-7 1.4 14 Thyroid I-133 1.3 E+2 3E-8 1.4 14 Thyroid 1-134 9.9 E O 2E-7 0.71 7.1 Thyroid I-135 4.7 E+1 lE-7 1.7 17 Thyroid
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l' EPIP-18 APX 2 Page 1 of 2 JUN 7 1978 gs
's .
EMERGENCY EXPOSURE CRITERIA APPENDIX 2 BLANK FORMS EPIP 18.1 DIERGENCY EXPOSURE AUTHORIZATION O 0; i 1 l
FORM EPIP 18.1 APX 2 Page 2 of 2 DfERGENCY EXPOSURE AUTHORIZATION JUN 7 1979 PERSONNEL AUTHORIZED TO RECEIVE DiERGENCY EXPOSURE 9 O Surry Power Station Employee C Operttions Personnel C H2 and Chemistry Personnel C Mechanical and Electrical Maintenance Security Other by Name: O
~
EXPOSURE LIMITS - MAXD1UM Whole Body: O 5 Rem O lo Re= 0 23 Rem C 30 Rem 73 Rem O loo Re= Thyroid: C 13 Rem 73 Rem O Greater than 73 Rem Airborne - One hour average 100 x MPC 1000 x MPC NOTE: Issue one Na1 tablet to each individumi to be exposed to Radioiodines, llealth Physics is to advise the Emergency Director when the following has been exceeded at which time this authorization is voided. Han Rem Accumulated:C 10 0 loo n 1000 0 10.000 0 N/A Special Instructions: 1 9 Authorized By: , Time: ,_ Date:
, - ~ _ . - _ _ . . . _ - . - - - - . . . - - . - - - . - . . . . . - - - - - - _ _ _ . ---- -.
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- j. i FIRE PROTECTION 1
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e ! EPIP- 19 } Page 2 of 6 8-22-77 FIRE PROTECTIO:' 1.0 Purpose 1.1 This procciure shall assist in fighting fires at the Surty Power Station and t,he area surrounding the station site. 1.2 Fires shall be classified in the following manner, ranging in degrees of severity and/or compicxity: 1.2.1 Minor Fire: One that can be easily extinguished with portable extinguishers and with littic or no danger to personnel. 3.2.2 Major Fire: A fire of a riagnitude that requires the use of additional manpower and/or equipment and may endanger personnel safety. Evacuation and/or of f-site assistance
+. may be required. O(,
CAUTION: Note that certain areas are protected by auto-matically actuated CO2systems. These systems
*give audible alarns 30 seconds prior to initf a-tion. If at any time tite alarru sou nd s', allfersons in the area must imrnediately evacuate that area unlesa wearing a.self-contained breathing-apparatus.
1.3 The Shif t Supervisor shall be notified of ali fires and is respon-sible for notifying the Fire !!ar hall who shall investigate and prepare the necessary reports. These reports shal.1 be evaluated by management in order to improve the Fire Protection Program. Tmmediate Action for Fire 1.A 1.4.1 The individual discovering the fire must quickly evaluate
t . pt EPIP- 19 Peg 3 3 of 6 l" -
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B-22-77
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for a minor' or a. major fire and use the appropriate
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steps in either 1.4.2 (minor fire) or 1,4.3 * (major 1. fire).
' '1.4.2 Action 'for Minor Fire 1.4.2.1 The individual discovering the fire shall immediately notify the control room of the fire
.c location using the most conve'nient method. This
'will either be telephone or public address system.
~ In either case, in'sure that the message has been properly received and acknowledged. If the public
- address systen is used, the individual shall
/~1 announce the alarm by intennittent announccm:nt
\) of " FIRE IN (location of-fire)".
. Example: Fire in First. Aid Room.- Continue announcement until it is acknowledged by the Shif t Supervisor or Control Roon Operator
' NOTE: Acknowledgement cannot be received if the page button is depressed. The.page-button must' be released between announce-1 ments in order to hear the acknowledgement.
1.4.2.2 Extinguish the fire using equipment at hand. 1.4.3- Action for Maior Fire 1.4.3.lt The individual discovering the fire shall immediately. notify the control room of the fir,e location using n the most convenient method. This will either be ( ,,p telephone or public address system. In either case; insure that the. message has been properly received e
I i EPIP- 19 Pzg2 4 of 6 8-22-77 ar.d acknowledged. If the public address system is lh used,.the individual announcing the alarm should inter-mittently announce " FIRE IN (Location of fire)." Example: Fire in #1 Turbine Building; turbine floor; 8 west side. Continue to make the announcement until it is acknowledged by a Supervisor, Operator or Engineer. NOTE: Acknowledgement cannot be received if the "Page Button" is held in the transmit .
. position. The "Page Button" must be re-released between announcements in order to hear acknowledgement.
. 1.4.3.2 The control room operator, upon learning of a fire shall sound the fi re alarn and then announce the location of the fire with sufficient detail to enable all necessary g
personnel to proceed to the fire. Example: Fire in # 1 Turbine Building; Turbine Ficor; West side. 1.4.3.3 The Assistant Shif t S6pervisor will immediately go to the scene of the fire. The Assistant Shift Supervisor shall be in charge and shall not leave the fire scene until~ relieved by an assistant fira marshall. ' 1.4.3.4 Upon hearing a fire announcement, the Shift Supervisor shall go to the control room. G e
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- EPIP-19 Pega 5 of 6 h FEB 0 71979 1.4.3.5 Upon hearing a fire announcement, the Fire Brigade members will iomediately report to :the Fire Brigade staging area outside the control room. The Fire
[ Marshall will proceed to the contogi room to get the necessary information to organize his team to proceed to the fire scene to eEfectively combat the fire. 1.4.3.6 The First Aid Team will assemble in the First Aid Room and await further directives. 1.4.3.7 If the magnitude of the fire is such that outside assistance is required, the Emergency. Coordinator / Director shall notifiy the Surry Volunteer Fire Department and the S=ithfield Fire Department and also inform the Security Shif t Supervisor so as to p) q enable security to escort the fire apparatus to the scene. 1.4.3.8 Upon hearing the fire announcement, all individuals not actively eng..ged in the firefighting activity will evacuate the affected area. Two Security Officers are to proceed to the fire scene to manage evacuation. Should site evacuation become necessary, those individuals not needed to respond to the emergency will be instructed to evacuate to the Remote Assembly Area where they will remain and avait further instructions. V Change No. 10 h
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s l' EPIP-19 P;g2 6 of 6 8-22-77 e 1.4.3.9 Reports of all fires shall be written by the Fire $ Marshall. Af ter any fire, the Fire Marshall will inspect the area of the fire and evaluate the damage. l These reports, containing information such as location
- of the fire, class, date, time, property loss, and any personnel injuries shall be recorded on proper form and a copy sent to the system Safety Department or Incarance Department, as applicable, in Richcrond.
1.4.3.10 All fire reports are to be submitted to the Station Manager. 1.4.3.11 Refer to the station fire fighting aanual for more detailed instructions. O l l t L h
e ! 1 s i EPIP 20 j Page 1 of 4 i 8-22-77 r a b $ I i i I i 4 L l l . VIRSINIA ELECTRIC M D POUER C0!!PA?iY !
, SURRY POWER STATION l
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!!E'4S AND INFOR!!ATION RELEASES. l
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EPIP 20 Pat;e 2 of 4
!!EUS A?;D II; FORM /sTION _PELEASES
( OPEl ATICJ!jS 1.0 Complete rona EPIP 20.1 of Appendix 1 of this procedure and iruaedi itely relay 'the information to the Director-1:aclear Operations or his alternate. 1.1 Periodically update Forn EP1P 20.1 as neu information is obtained and relay the inforcation to the Mana;;cr - Nuclear Operations or his alternate. 1.2 Forward Forms EPIP 20.1 to the Stat ion !!anager. 110TE: STATION PERSDN::EL ARE NOT TO RELEASE ANY IliFORMATION TO TiiE ND!S MEDIA - 2FER ALL II; QUIRES 10 VEPCO'S l'UBLIC RELATIONS DEPART ENT. ( l I l
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EPIP 20 Page 3 of 4 8-22-77 O .. o 4 i. l APPENDIX 1 News and Infomation- Releases Fom EPIP-20.1 1 0 9 e i f O. . t 4 y._p.___ .--_- - - .m ., ., y y- , - _,,s , , , , -. . . . _ . _ _ _ _ , . . _ _ . _ , _ . . . _ . _ . . _ _ _ , _ - . . , , _
Fora EPIP 20.1 Prga 4 cf 4 NEWS AND INFORMATION RELEASES 19 ; Time By Date: Date of Emergency ; Time of Emergency What llappened: Fuel llandling Accident; O Sen. cenerator Tube aupture; . Onain Stm. tine areak; OLOCA; Other - Describe Alert O Notification of unusual Event O Site Emergen,y O. ceneral Emergency Are all site personnel accot:nted for? Yes O No How ifany unaccour. table?_ ; Search in Progress? O ';es O No Injuries? O ves - How many? Hospital (s)
; O No Deaths? O Yen - Itov manyt ; O No . Off-site agency notification: OSurry O aames city county / city of W1111amsburg DOES; NRC , Region 2; Oothers Site Evacuation? O Yes No O Liquid Release: Amount ; Ounknown Gaseous Release: Amount ; unknown Isotopes Involved: O xe-133; 01-131; 01-133; co-58; O co-so; Oothers Oyes- ONo; OFires; OEquipmentSecured Incident Controlled?
O cause Isolated; OHa::ard Area Isolated Measures Instituted te Control Ingress and Egress into Hazard Area? Oves O No Survey Teams Obtaining Sampics f rom Environs and Monitoring? Oyes O No {
y . _ . _ . . _ - _ _ _ _ . _ _ _ _ _ _ i EPIP-21 i Page 1 of 6 j _: l I i i a l l + l f VIRGINIA ELECTRIC AND P01TER COMPANY SURRY P0 ITER STATION TRAINING AND EMERGENCY PREPAREDNESS l 1 1.0 Training 2.0 Emergency Preparedness I i I c I I ft
y~ w EPIP-21 Page 2 of 6 TRAINING AND DfERGENCY PREPARDNEFS 1.0 Training Training in the Emergency Plan and Impleuentating Procedures will be in accordance to the following guidelines. The Nuclear Training Coordinator will be respansible for implementing the appropiate scheduling. 1.1 Emergency Director, Alternate and the Station Emergency Flan Coordinator will have training in all cf the Emergency Plan Implerenting Procedures. A knowledge of the Vepco Emergency Plan is required. 1.2 Supervisors with emergency duties, licensed RO/SRO and Shift Technical Advisors will have a detailed indoctrination of EPIP 1 and how it relates to other EPIP's. A know?. edge of the Vepco Emergency Plan is required. 1.3 The Supervisor Health Physics, Heal.th Physicists, Assistant O( H.P Supervisors, and H.P. Technicians shall also receive training in EPIP 1 through EPIP 20 and the Vepco Emergency Plan.
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1.4 Members of the First Aid Tean will receive indoctrination in EPIP 3,8,9,10,18,19. A knowledge of the Vepco Plan is required. 1.5 Members of the station Fire Brigade will receive indoctrination in EPI 8,9,10,18,19. A knewledge of the Vepco Emergency Plan is required. 1.6 Training of Station Personnel will consist of an indoctrination in the Emergency Plan and how certain EPIP's relate to them. Figure 21.1 contains the material to be covered. 1.7 Off site Fire and Rescue units which have signed letters of agreement, have received training in the Emergency Plan. Such . i 1.
G .. - - . ~ h. E S. EPIP-21 l Pagt 3 of 6 q
.' training is provided by the State and/or'Vepco personnel. Retraining
-sessions are offered annually.
'l.8 'On site contractual personnel will receive appropriate training in the Emergency Plan. Since the majority of such personnel shall not have the ' duties associated with the. plan, emphasis will be on
. evacuation and accountability methods.
2.0 Emergency Preparedness _ _ Emergency Preparedness will be maintained as follows: 2.1 The Emergency' Plan and EPIP's will be formally received by SNSOC annually. Any proposed revisions or addition will be considered and acted upon by the SNSOC. 2.2 An exercise simulating a radiation emergency shall be performed (7 at least annually. An exercise. invclving State, Local and Station y/ Personnel shall be conducted bi--annually in coordination with the State exercise. The sunarics will be rotated each year to ensure all major elements of - the plan are tested. Once every
. six years the excercise will take place on the back shif ts to ensure radiological preparedness.
'2.3 -Letters of- agreement with outside agencies shall be subject to renewal every two years. The Starion Emergency Coordinator will be responsible for issuance of agreenents.
.2.4 Drills based on simulated Site or General Emergency will be staged to ensure maximum effectiveness of the plan. See Table 21.1 for schedule of Drills ar.d Exercises.
2.5 . Emergency Kits and supplies will be maintained by the Health Physics Section. All Emergency Kits contahing Haal+.h Physics response
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EPIP-21 P;g3 4 of 6 equipment, will. be inventoried on a monthly basis. Tuo emergency kits will be placed in the Control Room, one kit in the Health Physics Office, one kit in the first aid room, two kits at the Training building, two kits at 'the Isle of Fight Rescue Squad Headquarters and one kit at the Lebanon Elementary School. 2.6 Meetings with representatives from the off-site agencies will be held on an annual basis or as deemed necessary by the Station Manager, normally when significant changes to the Emergency Plan are made. 2.7 Bi-annual audits will be conducted by the Company's Q.A. Department to ensurc the training exercises and drill commitments are being kept current. O 5 O a
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EMERGENCY PREPAREDNESS TRAINING _ Figure 21.1
- The below listed personnel shall receive training in the applicable .
sections of the Emergency Plan and Implementing Procedures as indicated. EPIP PLAN 1 2 3 -4 5 6 7 8 9 10 11 12 13 14 15 "15 17 18 19 20 21 - EMERGENCY DIRECTOR . X X X X X X X X X X X X X X X X X X X X X X AND ALTERNATES , SUPERVISORS WITil EMERO. X X X X X X X X X X X X X X DUTIES LICENSED RO/SRO SilIFTTECIINICAL ADVISORS II.P./CIIEM. SUPERVISION AND X X .X X X X X X X X X X X X X X X- X X X X l TECilNICIANS l X X X X, X X
-I SECURITY PERSONNEL i
X X X .X X X X FIRST AfD TEAM X X X X X X FIRE BRIG ADE SUPERVISORS & FOREMAN
??9 WITil NO EMERGENCY DUTIES X X X X X X X X Sjy REGULAR EMPLOYEES &
gy X X X X X X X X . ;, - OFF-SIT" PERSONNEL , VISITOR CTR. PERSONNEL X X X X
! STATION EMERGENCY PLAN X ,X X X X X 'X X X X X X X X X X X X X X X COORDINATOR 4
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EPIP-21 Tdble 21.1 Page 6 of,6 Schedule of Drills And Exercises Full Scale Joint Exercise Once Every Two Years Small Scale Exercise Once Every Two Yeers citernating with the full Scale Exercise Fire Drills Que.iterly Medical Emergency Drills Annually Rad. Monitoring Drills Annually Heath Physis Dr'.11s Semi-Annually Comb. Communication Drills Anr": ally Radio Test Drill Monthly Telephone Test Drill Monthly Corporate Emergency Response Drill Annually G Note: Drills may be coordinate as part of an exercise. O e
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