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| document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST/INSPECTION/OPERATING PROCEDURES | | document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST/INSPECTION/OPERATING PROCEDURES | ||
| page count = 6 | | page count = 6 | ||
| project = TAC:67442 | |||
| stage = Other | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:- _ _ - | ||
, _ m. - -- - | |||
'' q . | |||
PROCEDURE REQUEST FORM FNP-0-AP-1 | |||
: 1. Procedure Number FWO-EIPM Revision Number /,3 Procedure Title C k .,4~. a.J m:ttt' /Lv.es Lsd s J, g>+.u. .p 'u | |||
\ 1 Safety Related C Non-Safety Related C New Procedure Request C Procedure Revision, New Revision Number Change of Intent | |||
,. 3 Temporary Procedure Change, Effective until next permanent | |||
'4 change, TCN /oA r 0 Temporary Procedure Change, Req'd. by Plant Codn, di't Eo'asNTIC(gMTROL C Temporary Procedure Change, One Time Use O ROLLED COPY | |||
: 2. Change Sumeary "" | |||
2.1 Procedure Page Numbers Af cted by Change COPYNo d([ | |||
r mes CA -fo los a.*1u ara ,su ,ne, t &6 | |||
^ | |||
2.2 Description of Changes | |||
: a b .9 d h es e4 +L LMrnsl,.od h 4 mud su>r + 4 hy,'*A Z - | |||
2.3 Reason for Change To we & m nwces dAtJ-W:0 | |||
: 3. Prepared By 70 v , c/w L /.,,b6 , 2 f83 Sign 4]ture Title Date | |||
. 4 Reviewed By 4 // b 6AO,es ,fedn-, d 843 Signature / Title >-fe viin. Date | |||
: 5. Cross-Disciplinary /PORC Review Group Signature Title Date | |||
: 6. Temporary Change Approval (Signature /Date) | |||
Member Group Staff , /) M | |||
/,4 ,f' N C ' ~~ | |||
''~ | |||
fShift Foreman M / | |||
r Senior Reactor Operator uf(L h / 2- Y-4 i Plant Manager / | |||
C - | |||
: 7. Final Approval (Signature /Date, required within 60 days of temporary approval) | |||
; C Group Supervisor <Md[ /8-h/7 | |||
, C Plant Superintendent / | |||
C MSAER / | |||
C Vice President - | |||
Nuclear Generation / | |||
C / | |||
/ Plant Manager ( / . #. b "'/ -- / %-/-O 8 | |||
i 8303090207 830302 PDR ADOCK 05000348 F PDR | |||
~ | |||
q . . | |||
FNP-0-AP-1 FARLEY NUCLEAR PLANT i | |||
NUCLEAR SAFETY EVALUATION CHECK LIST (1) UNIT J[;; | |||
(2) CHECK LIST APPLICABLE TO: fv#A.G7?. V Revision TCN /D4 l (3) SAFETY EVALUATION - PART A The procedure, procedure change or modifcation to which this evaluation is applicable represents: | |||
i (3.1) Yes No / A change to the plant as described in the FSAR? | |||
!l (3.2) Yes No / A change to procedures as described in the FSAR? | |||
1: (3.3) Yes No < A test or experiment not described in the FSAR? | |||
1 (3.4) Yes No ' A change to the Technical Specifications? | |||
i- If the answer to any of the above questions is "Yes," complete Item (4) | |||
!; and attach a 10CFR50.59 evaluation. If the answer to all of the above is "No," omit Item (4) and Item (9). | |||
l. | |||
!; (4) SAFETY EVALUATION - PART B l, (4.1) Yes No Will the probability of an accident previously | |||
]' evaluated in the FSAR be increased? | |||
i: (4.2) Yes No Will the consequences of an accident previously I' evaluated in the FSAR be increased? | |||
! (4.3) Yes No May the possibility of an accident which is different than any already evaluated in the i FSAR be created? | |||
(4.4) Yes No Will the probability of a malfunction of equipment important to safety previously | |||
,, evaluated in the FSAR be increased? | |||
j' (4.5) Yes No Will the consequences of a malfunction of equipment important to safety different than 3 | |||
any already evaluated in the FSAR be increased? | |||
i (4.6) Yes No May the possiblity of a malfunction of equipment , | |||
important to safety different than any already | |||
. evaluated in the FSAR be created? | |||
(4. 7.) Yes No Will the margin of safety as defined in the j basis to any Technical Specification be reduced? | |||
i If the answer to any of the above questions is "Yes," an unreviewed i safety question is involved. Explain the basis for each answer provided i in Section 4. | |||
(5) REMARKS: (Attach additional pages if necessary) | |||
(6) PREPARED BY: fb b _ , DATE a -S 4 3 | |||
, (7) REVIEWED BY: //M/Wm A Z/om& | |||
' ~ | |||
DATE 2-7-P7 (8) PORC REVIEW: / / DATE | |||
, (9) NORB REVIEW: DATE l Distribution | |||
: i. - Original: Document Control File A21 6226 i, i i i Figure 3 Rev. 7 | |||
_-__ge_w_-m_-___.;_----v.--r,- | |||
. . - - - - - - r--.n--, -- | |||
.~ | |||
FWs'-o- Em y' | |||
* . I Cwp/y w:K UP-13 J sgydb de b ,,,s d, e f,,, | |||
4.1 b f* | |||
s< ce b x uf a /< - en h'*y 1.1.4 c, _,Q E77-IV lh 9..t.5- * ^ A | |||
* C th3 A r y );7/ o /-es. k is t g/cg, yI ,yt cj *?9 Vf**'* | |||
MPdem n dl.la1i e,) Jarv n3 e datees) j 4.14 D o es ~~+ M/ Jarvey CO 'k l | |||
4.2.~1 fa& nod es t%l,//r4 cdol/ed .,aceess Ar'<+5 M "P/' | |||
( ] | |||
is 10 72c/mJ hpr+ Co.A T~f C. . | |||
y33. gape + 4 n' d A e p l | |||
8, s n eam m a<,4 n- nssi,- a s -,a :s e a ~+ | |||
l (wO4 ud ol&4.) skAP: ' | |||
) ;/di.vy . CJu.K cpeids 44., | |||
; LI.3.1 0+ | |||
Obk 1Re kr1T xi+ Jun }& cx t,aA,i%> peces d2 eg.,,p d, | |||
: &erf *ey 3.:.p 9 4 3. 2 fietc up & +tes e el.ie~,,%<ersik7, focsikd i~ R Pr:ra pd preead f gz | |||
)) ceeis A'd U/IP.) go;Idia, t/efiele or A maltale p/d <<kele-H.3 3 fer L n a.d;iee+ r & A gi,po,pcat,&, m g ,g ;,;,g,y,, ,,,,,,, | |||
bhe k c, g fj ,;cs y | |||
'^' M*4S d** y "+ kl 117 14 ew<yecy | |||
/ s .2A, desiydea n;.4,.; ,,, y ,,, | |||
' 1%,u. Rek +> @</ci . | |||
/ on., TLD tocp,te<f ju 94 4 , g,g 4.3 4 8</ p eTt b s e 4,iu.4 A i e | |||
.1./f W | |||
. b* O(,J L imliv&w j | |||
q,3. 4> ? i e is &h % Tsc. vj& ,d,'o, spct I,en%s p a.y,a As>.'y<uf fo mmlhn- n+ A Sode+s+ AI M ; | |||
Tem y,q, & &% &a h>r<< P: | |||
' p1e dic.s/ CnL s P | |||
U M *h* | |||
i 4.q.I p w kJo 19 loy An JM f'*wd er ~n1a av bl v &A '4 ''* I h * * ** * | |||
* h | |||
* Cas'-fJ7 leee :q 8 | |||
I 7~CA/ /04 | |||
-ey _ | |||
_w.__- | |||
__.-m-.---- | |||
PROCEDURE REQUEST FORM FNP-0-AP-1 | |||
: 1. Procedu;a Number vin _o Revision Number 11 Procedure Title nanT ATTON EXPOStrRE ESTIMATION AND CLASSIFICATION OF EMERGENCIES | |||
\ g Safety Related C Non-Safety Related C New Procedure Raquest C Procedure Revision, New Revision Number Change of Intent IX Temporary Procedure Change, Effective until next permanent | |||
; change, TCN 11A C Temporary Procedure change, Req'd. by Plant Conditions, TCN _ | |||
l C Temporary Procedure Change, One Time Use DOCUMENT CONTROL | |||
: 2. Change Summary CONTROLLED COPY | |||
; DO NOT REPRODUCE t 2.1 Procedure Page Numbers Affected by Change COPY NO. Gy 3 PAGE 3 4.1.2 2.2 Description of Changes SEE ATTACHED PAGE Z . | |||
2.3 Reason for Change CORRECT ERRONEOUS INFORMATION | |||
: 3. Prepared By b' e , C/HP TECHNICIAN, 02-08-83 S)4 nature Title Date | |||
[. | |||
\ | |||
: 4. Reviewed By $ , C/hP DA -wd , 02-08-83 Sftnatutd Title Date i | |||
: 5. Cross-Disciplinary /PORC Review Groun Signature Title Date . | |||
, e * , | |||
: 6. Temporary Change Approval (Signature /Da Member Group Staff f br L/ 8 C A ift Foreman ._ _ / / ' | |||
V Senior Reactor Operator /A'/C5/ A - - /?-T-Y1 C Plant Manager - | |||
/ | |||
: 7. Final Approval (Signature /Date, required within 60 days of tempora:; | |||
I approval) | |||
C Group Supervisor / | |||
i O Plant Superintendent / , | |||
C MSAER / ' | |||
. O Vice President - | |||
: Nuclear Generation / __ _ l C / l | |||
/ Plant Manager A/.J ./4 I' s f't -s - f ? l l ! | |||
N. ! | |||
Figure 1 Rev. *0 . l r | |||
i L -c & . .__ - -- ~ _m =. --s ..m v _+e vm e a ve+ i .3.-iem e m.....m- - - - | |||
l FNP-0-AP-1 l FARLEY NUCLEAR PLANT NUCLEAR SAFETY EVALUATION CECK LIST l | |||
(1) UNIT 1&2 ! | |||
~~ | |||
(2) CECK LIST APPLICABLE TO: EIP-9 Revision 11 TCN 11A i (3) SAFETY EVALUATION - PART A > | |||
i The procedure, procedure change or modifcation to which this evaluation , | |||
is applicable represents: | |||
(3.1) Yes No / A change to the plant as described in the FSAR? l (3.2) Yes No - A change to procedures as described in the FSAR? | |||
(3.3) Yes , No V A test or experiment not described in the FSAR? | |||
(3.4) Yes No / A change to the Technical Specifications? ! | |||
If the answer to any of the above questions is "Yes," complete Item (4) - | |||
and attach a 10CFR50.59 evaluation. If the answer to all of the above is "No," omit Ites (4) and Ites (9). , | |||
(4) SAFETY EVALUATION - PART B i | |||
(4.1) Yes No Will the probability of an accident previously [ | |||
evaluated in the FSAR be increased? | |||
(4.2) Yes No Will the consequences of an accident previously i evaluated in the FSAR be increased? l j (4.3) Yes No May the possibility of an accident which is different than any already evaluated in the i FSAR be created? | |||
(4.4) Yes No Will the probability of a malfunction of , | |||
m equipment important to safety previously l evaluated in the FSAR be increased? ; | |||
(4.5) Yes No Will the consequences of a malfunction of l equipme.nt important to safety different than i any already evaluated in the FSAR be increased? [ | |||
(4.6) Yes No May the possiblity of a malfunction of equipment l important to safety different than any already ! | |||
evaluated in the FSAR be created? ; | |||
(4.7) Yes No Will the margin of safety as defined in the ! | |||
basis to any Technical Specification be reduced? ; | |||
If the answer to any of the above questions is "Yes," an unreviewed i safety question is involved. Explain the basis for each answer provided in Section 4. , | |||
(5) REMARKS: (Attach additional pages if necessary) | |||
(6) PREPARED BY: b- DATE o 2.oe-V 3 (7) REVIEWED BY: St K f LN DATE t - r - Sg (8) PORC REVIEW: O dr DATE (9) NORB REVIEW: DATE Distribution l' Original: Document Control File A21 6226 Figure 3 Rev. 7 l | |||
I i | |||
f i - _ _ , | |||
. .- -_ - -- I - . - .- - - - . .- Y- | |||
.. i VOL. 14 - | |||
FNP-0-EIP-9 l | |||
, - 4.1.2 The ApMS will generate whole body and thyroid doses.at the site boundary and plume centroid positions for the ground level plume and the elevated plume. | |||
Note that these two plumes may not ' | |||
overlap. For the purpose of emergency classification the~ grouna level and elevated l | |||
. plume at the site boundary should be considered. While other values may be useful for dose assessment in the surrounding countryside, the ground level plume at the site boundary serves as the reference ~ | |||
for classification. | |||
4.1.3 Determine classification level and protective action recommendation from paragraph 4.3 4.2 Manual Dose Assessment 4.2.1 Obtain meteorological information on wind speed, wind direction, and atmospheric stability (AT) from plant meteorological instruments using Tab 1. | |||
~ 4.2.2 If at least one value for wind speed, | |||
(~''; one value for wind direction, and one value for atmospheric stability are not available from 4.2.1 above, obtain this information from the following offsite sources in the order listed until all information needed is obtained: | |||
4.2.2.1 Dothan Flight Service 1 | |||
4.2.2.2 National Weather Bureau-Montgomery ' | |||
4.2.2.3 National Weather Bureau -Birmingham 4.2.2.4 Great Southern Paper Company (windspeed and wind direction only). | |||
NOTE: Refer to Tab 2 for specific instructions. | |||
,; 4.2.3 Once the atmospheric stability class has been determined per 4.2.1 or 4.2.2, determine dose rates, projected doses, projected plume boundaries, and projected i | |||
TEN 11A 3 -Rev. 10-j_ _ _ _ _ . _ _ __. .._ . _ _ _ _ _ . . _ ._ . _ _ _ . . _ | |||
. _ _ . _ _ . _ _ _ . - . _}} |
Latest revision as of 05:13, 31 May 2023
ML20071D134 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 02/08/1983 |
From: | ALABAMA POWER CO. |
To: | |
Shared Package | |
ML20071D117 | List: |
References | |
PROC-830208-01, TAC-67442, NUDOCS 8303090207 | |
Download: ML20071D134 (6) | |
Text
- _ _ -
, _ m. - -- -
q .
PROCEDURE REQUEST FORM FNP-0-AP-1
- 1. Procedure Number FWO-EIPM Revision Number /,3 Procedure Title C k .,4~. a.J m:ttt' /Lv.es Lsd s J, g>+.u. .p 'u
\ 1 Safety Related C Non-Safety Related C New Procedure Request C Procedure Revision, New Revision Number Change of Intent
,. 3 Temporary Procedure Change, Effective until next permanent
'4 change, TCN /oA r 0 Temporary Procedure Change, Req'd. by Plant Codn, di't Eo'asNTIC(gMTROL C Temporary Procedure Change, One Time Use O ROLLED COPY
- 2. Change Sumeary ""
2.1 Procedure Page Numbers Af cted by Change COPYNo d([
r mes CA -fo los a.*1u ara ,su ,ne, t &6
^
2.2 Description of Changes
- a b .9 d h es e4 +L LMrnsl,.od h 4 mud su>r + 4 hy,'*A Z -
2.3 Reason for Change To we & m nwces dAtJ-W:0
- 3. Prepared By 70 v , c/w L /.,,b6 , 2 f83 Sign 4]ture Title Date
. 4 Reviewed By 4 // b 6AO,es ,fedn-, d 843 Signature / Title >-fe viin. Date
- 5. Cross-Disciplinary /PORC Review Group Signature Title Date
- 6. Temporary Change Approval (Signature /Date)
Member Group Staff , /) M
/,4 ,f' N C ' ~~
~
fShift Foreman M /
r Senior Reactor Operator uf(L h / 2- Y-4 i Plant Manager /
C -
- 7. Final Approval (Signature /Date, required within 60 days of temporary approval)
- C Group Supervisor <Md[ /8-h/7
, C Plant Superintendent /
C MSAER /
C Vice President -
Nuclear Generation /
C /
/ Plant Manager ( / . #. b "'/ -- / %-/-O 8
i 8303090207 830302 PDR ADOCK 05000348 F PDR
~
q . .
FNP-0-AP-1 FARLEY NUCLEAR PLANT i
NUCLEAR SAFETY EVALUATION CHECK LIST (1) UNIT J[;;
(2) CHECK LIST APPLICABLE TO: fv#A.G7?. V Revision TCN /D4 l (3) SAFETY EVALUATION - PART A The procedure, procedure change or modifcation to which this evaluation is applicable represents:
i (3.1) Yes No / A change to the plant as described in the FSAR?
!l (3.2) Yes No / A change to procedures as described in the FSAR?
1: (3.3) Yes No < A test or experiment not described in the FSAR?
1 (3.4) Yes No ' A change to the Technical Specifications?
i- If the answer to any of the above questions is "Yes," complete Item (4)
!; and attach a 10CFR50.59 evaluation. If the answer to all of the above is "No," omit Item (4) and Item (9).
l.
!; (4) SAFETY EVALUATION - PART B l, (4.1) Yes No Will the probability of an accident previously
]' evaluated in the FSAR be increased?
i: (4.2) Yes No Will the consequences of an accident previously I' evaluated in the FSAR be increased?
! (4.3) Yes No May the possibility of an accident which is different than any already evaluated in the i FSAR be created?
(4.4) Yes No Will the probability of a malfunction of equipment important to safety previously
,, evaluated in the FSAR be increased?
j' (4.5) Yes No Will the consequences of a malfunction of equipment important to safety different than 3
any already evaluated in the FSAR be increased?
i (4.6) Yes No May the possiblity of a malfunction of equipment ,
important to safety different than any already
. evaluated in the FSAR be created?
(4. 7.) Yes No Will the margin of safety as defined in the j basis to any Technical Specification be reduced?
i If the answer to any of the above questions is "Yes," an unreviewed i safety question is involved. Explain the basis for each answer provided i in Section 4.
(5) REMARKS: (Attach additional pages if necessary)
(6) PREPARED BY: fb b _ , DATE a -S 4 3
, (7) REVIEWED BY: //M/Wm A Z/om&
' ~
DATE 2-7-P7 (8) PORC REVIEW: / / DATE
, (9) NORB REVIEW: DATE l Distribution
- i. - Original: Document Control File A21 6226 i, i i i Figure 3 Rev. 7
_-__ge_w_-m_-___.;_----v.--r,-
. . - - - - - - r--.n--, --
.~
FWs'-o- Em y'
- . I Cwp/y w:K UP-13 J sgydb de b ,,,s d, e f,,,
4.1 b f*
s< ce b x uf a /< - en h'*y 1.1.4 c, _,Q E77-IV lh 9..t.5- * ^ A
- C th3 A r y );7/ o /-es. k is t g/cg, yI ,yt cj *?9 Vf**'*
MPdem n dl.la1i e,) Jarv n3 e datees) j 4.14 D o es ~~+ M/ Jarvey CO 'k l
4.2.~1 fa& nod es t%l,//r4 cdol/ed .,aceess Ar'<+5 M "P/'
( ]
is 10 72c/mJ hpr+ Co.A T~f C. .
y33. gape + 4 n' d A e p l
8, s n eam m a<,4 n- nssi,- a s -,a :s e a ~+
l (wO4 ud ol&4.) skAP: '
) ;/di.vy . CJu.K cpeids 44.,
- LI.3.1 0+
Obk 1Re kr1T xi+ Jun }& cx t,aA,i%> peces d2 eg.,,p d,
- &erf *ey 3.:.p 9 4 3. 2 fietc up & +tes e el.ie~,,%<ersik7, focsikd i~ R Pr:ra pd preead f gz
)) ceeis A'd U/IP.) go;Idia, t/efiele or A maltale p/d <<kele-H.3 3 fer L n a.d;iee+ r & A gi,po,pcat,&, m g ,g ;,;,g,y,, ,,,,,,,
bhe k c, g fj ,;cs y
'^' M*4S d** y "+ kl 117 14 ew<yecy
/ s .2A, desiydea n;.4,.; ,,, y ,,,
' 1%,u. Rek +> @</ci .
/ on., TLD tocp,te<f ju 94 4 , g,g 4.3 4 8</ p eTt b s e 4,iu.4 A i e
.1./f W
. b* O(,J L imliv&w j
q,3. 4> ? i e is &h % Tsc. vj& ,d,'o, spct I,en%s p a.y,a As>.'y<uf fo mmlhn- n+ A Sode+s+ AI M ;
Tem y,q, & &% &a h>r<< P:
' p1e dic.s/ CnL s P
U M *h*
i 4.q.I p w kJo 19 loy An JM f'*wd er ~n1a av bl v &A '4 * I h * * ** *
- h
- Cas'-fJ7 leee :q 8
I 7~CA/ /04
-ey _
_w.__-
__.-m-.----
PROCEDURE REQUEST FORM FNP-0-AP-1
- 1. Procedu;a Number vin _o Revision Number 11 Procedure Title nanT ATTON EXPOStrRE ESTIMATION AND CLASSIFICATION OF EMERGENCIES
\ g Safety Related C Non-Safety Related C New Procedure Raquest C Procedure Revision, New Revision Number Change of Intent IX Temporary Procedure Change, Effective until next permanent
- change, TCN 11A C Temporary Procedure change, Req'd. by Plant Conditions, TCN _
l C Temporary Procedure Change, One Time Use DOCUMENT CONTROL
- 2. Change Summary CONTROLLED COPY
- DO NOT REPRODUCE t 2.1 Procedure Page Numbers Affected by Change COPY NO. Gy 3 PAGE 3 4.1.2 2.2 Description of Changes SEE ATTACHED PAGE Z .
2.3 Reason for Change CORRECT ERRONEOUS INFORMATION
- 3. Prepared By b' e , C/HP TECHNICIAN, 02-08-83 S)4 nature Title Date
[.
\
- 4. Reviewed By $ , C/hP DA -wd , 02-08-83 Sftnatutd Title Date i
- 5. Cross-Disciplinary /PORC Review Groun Signature Title Date .
, e * ,
- 6. Temporary Change Approval (Signature /Da Member Group Staff f br L/ 8 C A ift Foreman ._ _ / / '
V Senior Reactor Operator /A'/C5/ A - - /?-T-Y1 C Plant Manager -
/
- 7. Final Approval (Signature /Date, required within 60 days of tempora:;
I approval)
C Group Supervisor /
i O Plant Superintendent / ,
C MSAER / '
. O Vice President -
- Nuclear Generation / __ _ l C / l
/ Plant Manager A/.J ./4 I' s f't -s - f ? l l !
N. !
Figure 1 Rev. *0 . l r
i L -c & . .__ - -- ~ _m =. --s ..m v _+e vm e a ve+ i .3.-iem e m.....m- - - -
l FNP-0-AP-1 l FARLEY NUCLEAR PLANT NUCLEAR SAFETY EVALUATION CECK LIST l
(1) UNIT 1&2 !
~~
(2) CECK LIST APPLICABLE TO: EIP-9 Revision 11 TCN 11A i (3) SAFETY EVALUATION - PART A >
i The procedure, procedure change or modifcation to which this evaluation ,
is applicable represents:
(3.1) Yes No / A change to the plant as described in the FSAR? l (3.2) Yes No - A change to procedures as described in the FSAR?
(3.3) Yes , No V A test or experiment not described in the FSAR?
(3.4) Yes No / A change to the Technical Specifications? !
If the answer to any of the above questions is "Yes," complete Item (4) -
and attach a 10CFR50.59 evaluation. If the answer to all of the above is "No," omit Ites (4) and Ites (9). ,
(4) SAFETY EVALUATION - PART B i
(4.1) Yes No Will the probability of an accident previously [
evaluated in the FSAR be increased?
(4.2) Yes No Will the consequences of an accident previously i evaluated in the FSAR be increased? l j (4.3) Yes No May the possibility of an accident which is different than any already evaluated in the i FSAR be created?
(4.4) Yes No Will the probability of a malfunction of ,
m equipment important to safety previously l evaluated in the FSAR be increased? ;
(4.5) Yes No Will the consequences of a malfunction of l equipme.nt important to safety different than i any already evaluated in the FSAR be increased? [
(4.6) Yes No May the possiblity of a malfunction of equipment l important to safety different than any already !
evaluated in the FSAR be created? ;
(4.7) Yes No Will the margin of safety as defined in the !
basis to any Technical Specification be reduced? ;
If the answer to any of the above questions is "Yes," an unreviewed i safety question is involved. Explain the basis for each answer provided in Section 4. ,
(5) REMARKS: (Attach additional pages if necessary)
(6) PREPARED BY: b- DATE o 2.oe-V 3 (7) REVIEWED BY: St K f LN DATE t - r - Sg (8) PORC REVIEW: O dr DATE (9) NORB REVIEW: DATE Distribution l' Original: Document Control File A21 6226 Figure 3 Rev. 7 l
I i
f i - _ _ ,
. .- -_ - -- I - . - .- - - - . .- Y-
.. i VOL. 14 -
FNP-0-EIP-9 l
, - 4.1.2 The ApMS will generate whole body and thyroid doses.at the site boundary and plume centroid positions for the ground level plume and the elevated plume.
Note that these two plumes may not '
overlap. For the purpose of emergency classification the~ grouna level and elevated l
. plume at the site boundary should be considered. While other values may be useful for dose assessment in the surrounding countryside, the ground level plume at the site boundary serves as the reference ~
for classification.
4.1.3 Determine classification level and protective action recommendation from paragraph 4.3 4.2 Manual Dose Assessment 4.2.1 Obtain meteorological information on wind speed, wind direction, and atmospheric stability (AT) from plant meteorological instruments using Tab 1.
~ 4.2.2 If at least one value for wind speed,
(~; one value for wind direction, and one value for atmospheric stability are not available from 4.2.1 above, obtain this information from the following offsite sources in the order listed until all information needed is obtained:
4.2.2.1 Dothan Flight Service 1
4.2.2.2 National Weather Bureau-Montgomery '
4.2.2.3 National Weather Bureau -Birmingham 4.2.2.4 Great Southern Paper Company (windspeed and wind direction only).
NOTE: Refer to Tab 2 for specific instructions.
,; 4.2.3 Once the atmospheric stability class has been determined per 4.2.1 or 4.2.2, determine dose rates, projected doses, projected plume boundaries, and projected i
TEN 11A 3 -Rev. 10-j_ _ _ _ _ . _ _ __. .._ . _ _ _ _ _ . . _ ._ . _ _ _ . . _
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